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DOE-NE Light Water Reactor Sustainability Program and EPRI Long Term Operations Program – Joint Research and Development PlanDOE-NE_LWRS_Program_and_EPRI_Long_Term_Operations_Program_Joint_Research_and_Development_Plan_Rev_6.pdf
  
DOE-NE Light Water Reactor Sustainability Program and EPRI Long Term Operations Program – Joint Research and Development Plan, Revision 6, INL/EXT-12-24562, April 2017.
Document
Light Water Reactor Sustainability Program Plan, Revision 5, INL-EXT-11-23452, February 2017.FY-17_LWRS_Integrated_Program_Plan.pdf
  
Light Water Reactor Sustainability Program Integrated Program Plan, Revision 5, INL-EXT-11-23452, February 2017.
Document
LWRS Program Accomplishments Report 2016LWRS_Program_Accomplishments_Report_2016.pdf
  
Light Water Reactor Sustainability Program Accomplishments Report, 2016.
Document
Light Water Reactor Sustainability Program Accomplishments Report, 2015Light_Water_Reactor_Sustainability_Program_Accomplishments_Report_2015.pdf
  
Light Water Reactor Sustainability Program Accomplishments Report, 2015.
Document
Light Water Reactor Sustainability Program Accomplishments Report, 2014.LWRS_Program_Accomplishments_Report_2014.pdf
  
Light Water Reactor Sustainability Program Accomplishments Report, 2014.
Document
Light Water Reactor Sustainability Program Accomplishments Report, 2013.LWRS_Program_Accomplishments_Report_2013.pdf
  
Light Water Reactor Sustainability Program Accomplishments Report, 2013.
Document
Light Water Reactor Sustainability Program Accomplishments Report, 2012.LWRS_Accomplishments_Report-2012.pdf
  
Light Water Reactor Sustainability Program Accomplishments Report, 2012.
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Materials Aging and Degradation​

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http://www.sciencedirect.com/science/article/pii/S0029549314005603
  
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PDF Downloads​
  
  
Description
Stress_Corrosion_Crack_Initiation_of_Alloy_600_in_Simulated_PWR_Primary_Water.pdf
  
Stress Corrosion Crack Initiation of Alloy 600 in Simulated PWR Primary Water, Z. Zhai, M. Toloczko, M. Olszta, D. Schreiber, S. Bruemmer, September 2017.
Stress_Corrosion_Crack_Initiation_and_Propagation_under_Different_Corrosion_Environmental_conditions,_and_the_Role_of_Post-.pdf
  
Stress Corrosion Crack Initiation and Propagation under Different Corrosion Environmental conditions, and the Role of Post-Irradiation Annealing on Irradiation Assisted Stress Corrosion Cracking, G. Was, W. Kuang, R. Bhambroo, September 2017.
Predictive_Model_For_Swelling_Accumulation_In_Austenitic_Steels_Under_Light_Water_Reactor_Relevant_Conditions.pdf
  
Predictive Model For Swelling Accumulation In Austenitic Steels Under Light Water Reactor Relevant Conditions, S. Golubov1, A. Barashev, ORNL/LTR-2017/407, September 2017.
Proton_Irradiation_Screening_Results_of_Select_Advanced_Replacement_Alloys_for_Core_Internals.pdf
  
Proton Irradiation Screening Results of Select Advanced Replacement Alloys for Core Internals, G. Was, M. Wang, M. Song, C. Lear, September 2017.
Complete_report_that_documents_the_completion_of_a_validated_model_for_transition_temperature_shifts_in_RPV_steels.pdf
  
Complete_report_that_documents_the_completion_of_a_validated_model_for_transition_temperature_shifts_in_RPV_steels, S. Shu, M. Mamivand, H. Ke, T. Mayeshiba, B. Afflerbach, J. Ke, D. Morgan, G. Odette, P. Wells, N. Almirall, September 2017.
Crystal_River_3_Cable_Materials_for_Thermal_and_Gamma_Radiation_Aging.pdf
  
Crystal River 3 Cable Materials for Thermal and Gamma Radiation Aging, L. Fifield, M. Correa, A. Zwoster, PNNL-26785, September 2017.
Localized_Deformation_Investigation_in_Irradiated_Materials_via_Electron_Microscopy_and_In_Situ_Testing.pdf
  
Localized Deformation Investigation in Irradiated Materials via Electron Microscopy and In Situ Testing. M. Gussev, P. Edmondson, G. Bellefon, B. Eckhart, J. Dixon, K. Leonard, ORNL/TM-2017/507, September 2017.
Microstructure_Characterization_of_Reactor_Pressure_Vessel_Alloys_ATR-2_Experiment_Update.pdf
  
Microstructure Characterization of Reactor Pressure Vessel Alloys: ATR-2 Experiment Update, G. Odette, T. Yamamoto, P. Wells, N. Almirall, D. Gragg, UCSB ATR-2 2017-2, September 2017.
Interdigital_Capacitance_Local_Non-Destructive_Examination_of_Nuclear_Power_Plant_Cable_for_Aging_Management_Programs_Inter.pdf
  
Interdigital Capacitance Local Non-Destructive Examination of Nuclear Power Plant Cable for Aging Management Programs – Interim Report, S. Glass, A. Jones, L. Fifield, M. Larche, N. Bowler, A. Sriraman, W. Palmer, PNNL-26807, September 2017
Microstructural_Characterization_of_Reactor_Pressure_Vessel_Alloys_ATR-2_Experiment_Update.pdf
  
Microstructural Characterization of Reactor Pressure Vessel Alloys: ATR-2 Experiment Update, G. Odette, T. Yamamoto, P. Wells, N. Almirall, D. Gragg, UCSB ATR-2 2017-2, September 2017.
Final_Report_on_CFD_and_Thermal-Mechanical_Stress_Analysis_of_PWR_Surge_Line_under_Transient_Condition_Thermal_Stratificati.pdf
  
Final Report on CFD and Thermal-Mechanical Stress Analysis of PWR Surge Line under Transient Condition Thermal Stratification and an Evolutionary Cyclic Plasticity Based Transformative Fatigue Evaluation Approach without Using S~N Curve, S. Mohanty, B. Barua, J. Listwan, S. Majumdar, Ken Natesan, ANL/LWRS-17/03, September 2017.
Specimen_Fabrication_From_Two_High_Fluence_Ginna_Baffle_Bolts.pdf
  
Specimen Fabrication From Two High Fluence Ginna Baffle Bolts, X. Chen, K. Leonard, M. Sokolov, M. Burke, M. Gussev, S. Clar, ORNL/TM-2017/455, August 25, 2017.
Development_of_Fast_Fourier_Transform_(FFT)_micro-mechanical_Simulations_of_Concrete_Specimens_Characterized_by_micro-X-ray.pdf
  
Development of Fast Fourier Transform (FFT) micro-mechanical Simulations of Concrete Specimens Characterized by micro-X-ray Fluorescence
Fracture_Toughness_Evaluation_of_Select_Advanced_Replacement_Alloys_for_LWR_Core_Internals.pdf
  
Fracture Toughness Evaluation of Select Advanced Replacement Alloys for LWR Core Internals, X. Chen, L. Tan, ORNL/TM-2017/377, August 2017.
IMAC_Database_v0_Concrete.pdf
  
IMAC Database v.0.3. – Concrete, Y. Pape, ORNL/SPR-2017/436, August 2017.
Development_of_Computational_Tools_for_Modeling_Thermal_and_Radiation_Effects_on_Grain_Boundary_Segregation.pdf
  
Development of Computational Tools for Modeling Thermal and Radiation Effects on Grain Boundary Segregation and Precipitation in Fe-Cr-Ni-based Alloys, Y. Yang, ORNL/TM-2017/438, August 2017.
Mechanical_and_Microstructural_Characteristics_of_Cast_Stainless_Steels_after_Thermal_Aging_for_10000_Hours.pdf
  
Mechanical and Microstructural Characteristics of Cast Stainless Steels after Thermal Aging for 10000 Hours, T. Byun, T. Lach, D. Collins, E. Barkley, F. Yu, PNNL-26656, August 2017.
Fracture_Toughness_Characterization_of_Reactor_Pressure_Alloys_from_the_ATR-2_Experiment.pdf
  
Fracture Toughness Characterization of Reactor Pressure Alloys from the ATR-2 Experiment, M. Sokolov, X. Chen, R. Nanstad, G. Odette, T.Yamamoto, P. Wells, ORNL/TM-2017/358, July 2017.
Effects_of_Swelling_on_Irradiation-Assisted_Stress_Corrosion_Cracking.pdf
  
Effects of Swelling on Irradiation-Assisted Stress Corrosion Cracking, S. Teysseyre, INL/EXT-17-42863, July 2017.
Report_Summarizing_the_Status_of_Second_Round_Irradiation_Experiments_and_Assessment_of_Materials_Available_for_Testing_Adv.pdf
  
Report Summarizing the Status of Second Round Irradiation Experiments and Assessment of Materials Available for Testing Advanced Welding Techniques, Zhili Feng, Roger Miller, Nesrin Cetiner1 and Xunxiang Hu, S. Clark, G. Frederick, B. Sutton, July 2017.
Accelerated_Thermal_aging_of_Harvested_Zion_Electrical_Cable_Jacket_and_Insulation_(Interim_Report).pdf
  
Accelerated Thermal aging of Harvested Zion Electrical Cable Jacket and Insulation (Interim Report), R. Duckworth, July 2017.
Analysis_of_simultaneous_thermal_gamma_radiation_aging_of_cross-linked_polyethylene_XLPE_insulation—interim_status_report.pdf
  
Analysis of simultaneous thermal/gamma radiation aging of cross-linked polyethylene (XLPE) insulation—interim status report, L. Fifield, M. Correa, PNNL-26554, June 2017.
Report_Summarizing_the_Effort_Required_to_Initiate_Welding_of_Irradiated_Materials_within_the_Welding_Cubicle.pdf
  
Report Summarizing the Effort Required to Initiate Welding of Irradiated Materials within the Welding Cubicle, Z. Feng, W. Tang, J. Chen, X. Hu, R. Miller, B. Gibson, A. Smith, M. Vance, S. Clark, G. Frederick, J. Tatman, B. Sutton, June 2017.
Analysis_of_simultaneous_thermal_gamma_radiation_aging_of_cross-linked_polyethylene_XLPE_insulation_interim_status_report.pdf
  
Analysis of simultaneous thermal/gamma radiation aging of cross-linked polyethylene (XLPE) insulation—interim status report, L. Fifield, M. Correa, PNNL-26554, June 2017.
High-Temperature_Steam_Oxidation_Testing_of_Select_Advanced_Replacement_Alloys_for_Potential_Core_Internals.pdf
  
High-Temperature Steam Oxidation Testing of Select Advanced Replacement Alloys for Potential Core Internals, L. Tan, B. Pint, ORNL/TM-2017/228, May 2017.
Development_of_Mini-Compact_Tension_Test_Method_for_Determining_Fracture_Toughness_Master_Curves_for_Reactor_Pressure.pdf
  
Development of Mini-Compact Tension Test Method for Determining Fracture Toughness Master Curves for Reactor Pressure Vessel Steels, M. Sokolov, ORNL/TM-2017/275, May 2017.
Physics-Based_Modeling_of_Cable_Insulation_Conditions_for_Frequency_Domain_Reflectometry_(FDR).pdf
  
Physics-Based Modeling of Cable Insulation Conditions for Frequency Domain Reflectometry (FDR), S. Glass, A. Jones, L. Fifield, T. Hartman, N. Bowler, PNNL-26493, May 2017.
PNNL_Presentations_on_SCC_Initiation_at_the_2017_International_Cooperative_Group_Meeting_on_Environment-Assisted_Cracking.pdf
  
PNNL Presentations on SCC Initiation at the 2017 International Cooperative Group Meeting on Environment-Assisted Cracking, S. Bruemmer, Z. Zhai, M. Toloczko, May 2017.
Effects_of_ATR-2_Irradiation_High_Fluence_Nine_RPV_Surveillance_Alloys.pdf
  
Effects of ATR-2 Irradiation to High Fluence on Nine RPV Surveillance Materials, R. Nanstad, G. Odette, N. Almirall, J. Robertson, L. Server, T. Yamamoto, P. Wells, ORNL/TM-2017/172, April 2017.
Linear_Array_Ultrasonic_Testing_of_a_Thick_Concrete_Specimen_for_Nondestructive_Evaluation.pdf
  
Linear Array Ultrasonic Testing of a Thick Concrete Specimen for Nondestructive Evaluation, D. Clayton, N. Ezell, L. Khazanovich, M. Zammerachi, ORNL/TM-2017/156, April 2017.
Complete_Report_on_the_Modeling_of_Precipitate_Processes_in_irradiated_Reactor_Pressure_Vessel_Steel.pdf
  
Complete Report on the Modeling of Precipitate Processes in irradiated Reactor Pressure Vessel Steel, M. Mamivand, H. Ke, S. SHu, T. Mayeshiba, D. Morgan, G. Odette, P. Wells, N. Almirall, March 2017.
Summary_of_Progress_on_the_ATR-2_Experiment_Post-Irradiation_Examination_of_Reactor_Pressure_Vessel_Alloys.pdf
  
Summary of Progress on the ATR-2 Experiment Post-Irradiation Examination of Reactor Pressure Vessel Alloys, G. Odette, T. Yamamoto, P. Wells, N. Almirall, K. Fields, D. Gragg, R. Nanstad, J. Robertson, K. Wilford, N. Riddle, T. Williams, UCSB ATR-2 2017-1,  March 2017.
3D-FE_Modeling_of_316_SS_under_Strain-Controlled_Fatigue_Loading_and_CFD_Simulation_of_PWR_Surge_Line.pdf
  
3D-FE Modeling of 316 SS under Strain-Controlled Fatigue Loading and CFD Simulation of PWR Surge Line, S. Mohanty, B. Barua, J. Listwan, S. Majumdar, K. Natesan, ANL/LWRS-17/01, March 2017.
Update_on_Combined_Thermal_Radiation_aging_at_five_dose_rates_in_Chlorosulfonated_Polyethylene_Hypalon_Ethylene_Propylene.pdf
  
Update on Combined Thermal/Radiation aging at five dose rates in Chlorosulfonated Polyethylene (Hypalon)/Ethylene-Propylene Rubber (EPR) Cable Jacket Insulation System, R. Duckworth, M3LW-17OR0404019, March 2017.
Development_and_initial_test _results_of_the_in-situ_Characterization_of_irradiated_materials_under_Deformation.pdf
  
Development and initial test results of the in-situ Characterization of irradiated materials under Deformation, M. Gussev, P. Edomondson, B. Eckhart, K. Leonard, ORNL/TM-2017/111, February 2017.
SSC_Initiation_in_Alloy_600_and_Alloy_690.pdf
  
SSC Initiation in Alloy 600 and Alloy 690, Milestone: M3LW-17OR0, S. Bruemmer, Z. Zhai, M. Toloczko, December 19, 2016.
IMAC_Database_v01_ Minerals.pdf
  
IMAC Database v.0.1. – Minerals, ORNL/TM-2016/ORNL/TM-2016/753, Y. Pape, December 2016.
Assessment_of_Radiation_Resistance_of_Selected_Alloys_in_The_ARRM_Program_Using_Ion_Irradiation.pdf
  
Assessment of Radiation Resistance of Selected Alloys in The ARRM Program Using Ion Irradiation, G. Was, M. Song, M. Wang, September 30, 2016.
Incorporation_of_copper-rich_precipitation_model_into_developed_Ni-Mn-Si_precipitate_development_models_September_30,_2016.pdf
  
Incorporation of copper-rich precipitation model into developed Ni-Mn-Si precipitate development models September 30, 2016 Milestone, M. Mamivand, H. Ke, S. Shu, D. Morgan, G. Odette, P. Wells, N. Almirall, September 30, 2016.
Toughness_and_High-Temperature_Steam_Oxidation_Evaluations_of_Advanced_Alloys_for_Core_Internals.pdf
  
Toughness and High-Temperature Steam Oxidation Evaluations of Advanced Alloys for Core Internals, ORNL/TM-2016/371, September 16, 2016.
Independent_Modeling_of_the_Alkali-Silica_Reaction_Mock_up_Test_Block.pdf
  
Independent Modeling of the Alkali-Silica Reaction: Mock-up Test Block, ORNL/TM-2016/537, M. Hariri-Ardebili, V. Saouma, Y. LePape, September 15, 2016.
L3_Milestone_M3LW-16OR0406015_Provide_documentation_on_the_information_and_states_of_both_the_first_and_second_series.pdf
  
 L3 Milestone M3LW-16OR0406015, Provide documentation on the information and states of both the first and second series of neutron irradiate series of B-doped steels for the weld validation testing to begin in FY17, Z. Feng, N. Cetiner, X. Hu, R. Miller, G. Frederick, B. Sutton, September 2016.
Bulk_and_Distributed_Electrical_Cable_Non-Destructive_Examination_Methods_for_Nuclear_Power_Plant_Cable_Aging_Management.pdf
  
Bulk and Distributed Electrical Cable Non-Destructive Examination Methods for Nuclear Power Plant Cable Aging Management Programs,  PNNL-25634, S. Glass, A. Jones, L. Fifield, T. Hartman, September 2016.
Development_of_Computational_Tools_for_Predicting_Thermal_and_Radiation-Induced_Solute_Segregation_at_Grain_Boundaries.pdf
  
Development of Computational Tools for Predicting Thermal- and Radiation-Induced Solute Segregation at Grain Boundaries in Fe-based Alloys, ORNL/TM-2016/460, Y. Yang, September 2016.
Evaluation_of_Advanced_Signal_Processing_Techniques_to_Improve_Detection_and_Identification_of_Embedded.pdf
  
Evaluation of Advanced Signal Processing Techniques to Improve Detection and Identification of Embedded Defects, ORNL-TM-2016-482, D. Clayton, H. Santos-Villalobos, J. Baba, September 2016.
Mechanical_Properties_of_304L_and_316L_Austenitic_Stainless_Steels_after_Thermal_Aging_for_1500_Hours.pdf
  
Mechanical Properties of 304L and 316L Austenitic Stainless Steels after Thermal Aging for 1500 Hours, PNNL-25854, T. Byun, T. Lach, September 2016.
Precursor_Damage_Evolution_and_Stress_Corrosion_Crack_Initiation_of_Cold-worked_Alloy_690_in_PWR_Primary_Water.pdf
  
Precursor Damage Evolution and Stress Corrosion Crack Initiation of Cold-worked Alloy 690 in PWR Primary Water, M2LW-16OR0402034, Z. Zhai, M. Toloczko, K. Kruska, N. Overman, M. Olszta, S. Bruemmer, September 2016.
Report Detailing Friction Stir Welding Process Development for the Hot Cell Welding System.pdf
  
Report Detailing Friction Stir Welding Process Development for the Hot Cell Welding System, M3LW-16OR0406014, W. Tang, B. Gibson, Z. Feng, S. Clark, A. Peterson, G. Frederick, September 2016.
Simulation_of_Concrete_Members_Affected_by_Alkali-Silica_Reaction_with_Grizzly.pdf
  
Simulation of Concrete Members Affected by Alkali-Silica Reaction with Grizzly, ORNL/TM-2016/523, A. Giorla, September 2016.
Status_Report_and_Research_Plan_for_Cables_Harvested_from_Crystal_River_Unit_3_Nuclear_Generating_Plant.pdf
  
Status Report and Research Plan for Cables Harvested from Crystal River Unit 3 Nuclear Generating Plant, PLNNL-25833, L. Fifield, September 2016.
Study of High Fluence Radiation-induced Swelling and Hardening under Light Water Reactor Conditions.pdf
  
Study of High Fluence Radiation-induced Swelling and Hardening under Light Water Reactor Conditions, ORNL/LTR-2016/549, S. Golubov, A. Barashev, R. Stoller, September 2016.
Study_the_Cyclic_Plasticity_Behavior_of_508_LAS_under_Constant_Variable_and_Grid-Load-Following_Loading_Cycles_for_Fatigue.pdf
  
Study the Cyclic Plasticity Behavior of 508 LAS under Constant, Variable and Grid-Load-Following Loading Cycles for Fatigue Evaluation of PWR Components, ALNl/LWRS-16/03, S. Mohanty, B. Barua, W. Soppet, S. Majumdar, K. Natesan, September 2016.
The_Assessment_and_Validation_of_Mini-Compact_Tension_Test_Specimen_Geometry_and_Progress_in_Establishing_Technique.pdf
  
The Assessment and Validation of Mini-Compact Tension Test Specimen Geometry and Progress in Establishing Technique for Fracture Toughness Master Curves for Reactor Pressure Vessel Steels, ORNL/TM-2016/602, M. Sokolov, R. Nanstad, September 2016.
Zion_Unit_1_Reactor_Pressure_Vessel_Sample_Acquisition_Phase_2_and_Phase_3_Status_Report.pdf
  
Zion Unit 1 Reactor Pressure Vessel Sample Acquisition: Phase 2 and Phase 3 Status Report, ORNL/TM-2016/561, T. Rosseel, M. Sokolov, X. Chen,  R. Nanstad, September 2016.
Identification of Mechanisms to Study Alkali-Silica Reaction Effects on Stressed-Confined Concrete Nuclear Thick Structures.pdf
  
Identification of Mechanisms to Study Alkali-Silica Reaction Effects on Stressed-Confined Concrete Nuclear Thick Structures, Z. Ma, S. Pape, N. Hayes, Q. Gui, A. Elhassan, Y. Jing, August 31, 2016.
LWRS contribution to the RILEM benchmark on materials modeling of ASR – Preliminary results.pdf
  
LWRS contribution to the RILEM benchmark on materials modeling of ASR – Preliminary results, ORNL/LTR-2016/395, Y.  Pape, A. Gloria, August 2016.
MAaD_Pathway_Technical_Program_Plan_2016.pdf
  
Materials Aging and Degradation Technical Program Plan, K. Leonard, T. Rosseel, and J. Busby, ORNL/LTR-2012/237 Rev 5, August 2016.
Progress in Characterizing Thermal Degradation of Ethylene-Propylene Rubber.pdf
  
Progress in Characterizing Thermal Degradation of Ethylene-Propylene Rubber, PNNL-25713, L. Fifield, Q. Huang, M. Childers, M. Correa, Y. Shin, A. Zwoster, August 2016
Report_on_the_Installation_of_the_Integrated_Welding_Hot_Cell_at_ORNL_Building_7930.pdf
  
Report on the Installation of the Integrated Welding Hot Cell at ORNL Building 7930, M2LW-16OR0406013, Z. Feng, W. Tang, R. Miller, B. GIbson, A. Peterson, J. Tatman, G. Frederick, June 30, 2016.
Update_on_the_High_Fluence_Advanced_Test_Reactor_2_Reactor_Pressure_Vessel_High_Fluence_Irradiation_Project.pdf
  
Update on the High Fluence Advanced Test Reactor – 2 Reactor Pressure Vessel High Fluence Irradiation Project, UCSB ATR-2 2016-1, G. Odette, T. Yamamoto, P Wells, N. Almirall, K. Fields, D. Gragg, R. Nanstad, M. Sokolov, J. Robertson,  June 30, 2016
Report_on_the_Harvesting_and_Acquisition_of_Zion_Unit_1_Reactor_Pressure_Vessel_Segments.pdf
  
Report on the Harvesting and Acquisition of Zion Unit 1 Reactor Pressure Vessel Segments, ORNL/TM-2016/240, T. Rosseel, M. Sokolov, R. Nanstad, June 2016.
Evaluation_of_Localized_Cable_Test_Methods_for_Nuclear_Power_Plant_Cable_Aging_Management_Programs.pdf
  
Evaluation of Localized Cable Test Methods for Nuclear Power Plant Cable Aging Management Programs, PNNL-25432, S. Glass, L. Fifield, T. Hartman, May 2016.
Progress_in_Characterizing_Naturally-Aged_Nuclear_Power_Plant_Cables.pdf
  
Progress in Characterizing Naturally-Aged Nuclear Power Plant Cables, PNNL-25439, L. Fifield, Q. Huang, M. Ian Childers,  A. Zwoster, May 2016.
Linear_Array_Ultrasonic_Test_Results_from_Alkali-Silica_Reaction_Specimens.pdf
  
Linear Array Ultrasonic Test Results from Alkali-Silica Reaction (ASR) Specimens, ORNL-TM-2016-159, D. Clayton, L. Khazanovich,
L. Salles, April 2016.
Mechanical_Properties_of_Model_Cast_Austenitic_Stainless_Steels_after_Thermal_Aging_for_1500_Hours.pdf
  
Mechanical Properties of Model Cast Austenitic Stainless Steels after Thermal Aging for 1500 Hours, PNNL-25377, T. Sang Byun, N. Overman, T. Lach, April 2016.
Effect_Of_Thermo-Mechanical_Processing_And_Aging_On_The_Stress_Corrosion_Cracking_Resistance_Of_Alloy_690.pdf
  
Effect Of Thermo-Mechanical Processing And Aging On The Stress Corrosion Cracking Resistance Of Alloy 690, 2011-01-K, March 2016.
Modeling_Late_Blooming_Phase_Evolution_during_Post-irradiation_Annealing_in_Select_Reactor_Pressure_Vessels.pdf
  
Modeling Late Blooming Phase Evolution during Post-irradiation Annealing in Select Reactor Pressure Vessels: Milestone 2 Report, S. Shu, H. Ke, D. Morgan, G. Odette, P. Wells, March 2016.
Finite_Element_Analysis_Based_Thermal-Mechanical_Stress_Analysis_of_PWR_Pressure_Vessel_with_without_Pre-existing_Crack.pdf
  
Finite Element Analysis Based Thermal-Mechanical Stress Analysis of PWR Pressure Vessel with/without Pre-existing Crack to Study the Effect of Cyclic Hardening Material Properties Under Grid Load Following Mode: An Interim Report, ANL/LWRS-16/01, S. Mohanty, W. Soppet, S. Majumdar, K. Natesan, March 2016.
Finite_Element_Analysis_Based_Thermal-Mechanical_Stress_Analysis_PWR_Pressure_Vessel.pdf
  
Finite Element Analysis Based Thermal-Mechanical Stress Analysis of PWR Pressure Vessel with/without Pre-existing Crack to Study the Effect of Cyclic Hardening Material Properties Under Grid Load Following Mode: An Interim Report, ANL/LWRS-16/01, S. Mohanty, W. Soppet, S. Majumdar, K. Natesan, March 2016
Thermodynamic_and_Kinetic_Model_Development_of_Thermal_Segregation_of_Phosphorus_in_Iron_Fe-Cr_and_Fe-Ni_Systems_Towards.pdf
  
Thermodynamic and Kinetic Model Development of Thermal Segregation of Phosphorus in Iron, Fe-Cr and Fe-Ni Systems – Towards the Development of a Comprehensive Solute Segregation Model, ORNL/TM-2016/93, Y. Yang, March 2016.
Alkali-Silica_Reaction_test_Assembly.pdf
  
Alkali-Silica Reaction test Assembly - Report describing the procurement of materials and equipment for the ASR test assembly Identification of Mechanisms to Study Alkali-Silica Reaction Effects on Stressed-confined Concrete Nuclear Thick Structures, Z Ma, University of Tennessee, January 2016.
Characterizing_Oxidation_with_DSC_PNNL-25172.pdf
  
Characterizing oxidation of cross-linked polyethylene and ethylene propylene rubber insulation materials by differential scanning calorimeter, L. Fifield, J. Liu, Q. Huang, A. Zwoster, PNNL-25172, January 2016
M3LW-16OR0403044-ORNL-LTR-2016-28_Gen_Mtg_ICIC.pdf
  
Summary Report on the First General Meeting of the International Committee on Irradiated Concrete, ORNL/LTR-2016/28,  T. Rosseel, January 2016
M3LW-16OR0403062-Alkali-Silica_reaction.pdf
  
Alkali-Silica Reaction Test Assembly - Report describing the final instrumentation plan of the ASR test assembly Identification of Mechanisms to Study Alkali-Silica Reaction effects on Stressed-Confined Concrete Nuclear Thickness Structures, Z. J. Ma, LWRS Deliverable M3LW-16OR0403062, November 2015.
M3LW-15OR0402053-UW-ORNL.pdf
  
Modeling Strategy to Assess Radiation Induced Segregation and Phase Stability in Austenitic Steels in Light Water Reactors During Extended Service: Milestone 7 Report, M. Mamivand, Y. Yang, D. Morgan, September 2015.
State-of-the-Art_Assessment_of_NDE.pdf
  
State-of-the-Art Assessment of NDE Techniques for Aging Cable Management in Nuclear Power Plants FY2015, S. Glass, L. Fifield, G. Dib, J. Tedeschi, A. Jones, T. Hartman, PNNL-24649, September 2015.
M3LW-15OR0402173-ORNL-TM-2015-479.pdf
  
Development of a robust modeling tool for radiation-induced segregation in austenitic stainless steels, Y. Yang, K. Field, T. Allen, J. T. Busby, ORNL/TM-2015/479, September 2015.
M3LW15OR0404013.CableAging.Fifield.PNNL-24634.pdf
  
Progress on Analysis of Inverse Temperature Effects, Submerged Cables, Diffusion Limited Oxidation and Dose Rate Effects. L.S. Fifield, M. P. Westman, M. K. Murphy, A. J. Zwoster, PNNL-24634, September 2015.
Summary of Stress Corrosion Crack Initiation Measurements.pdf
  
Summary of Stress Corrosion Crack Initiation Measurements and Analyses on Alloy 600 and Alloy 690, Z. Zhai, M. J. Olszta, M. B. Toloczko and S. M. Bruemmer, September 2015.
M2LW-15OR0402113-ANL-LWRS-15-02.pdf
  
Tensile and Fatigue Testing and Material Hardening Model Development for 508 LAS Base Metal and 316 SS Similar Metal Weld under In-air and PWR Primary Loop Water Conditions, S. Mohanty, W. Soppet, S. Majumdar, and K. Natesan, ANL/LWRS-15/02 September 2015.
M3LW-15OR0403012 RILEM TC ISR Summer 2015 Activity Report.pdf
  
RILEM TC ISR Summer 2015 Activity Report, Y. Le Pape, ORNL/LTR-2015/407 August 2015.
M3LW-15O0404022-PNNL-24309.pdf
  
Assessment of Additional Key Indicators of Aging Cables in Nuclear Power Plants – Interim Status for FY 2015, P. Ramuhalli, L. Fifield, M. Prowant, G. Dib, J. Tedeschi, J. Suter, A. Jones, M. Good, S. Glass, A. Pardini, PNNL-24309, Pacific Northwest National Laboratory, May 2015.
ANL-LWRS-15-01.pdf
  
System-Level Heat Transfer Analysis, Thermal-Mechanical Cyclic Stress Analysis, and Environmental Fatigue Modeling of a Two-Loop Pressurized Water Reactor: A Preliminary Study, S. Mohanty, W. Soppet, S. Majumdar, and K. Natesan, ANL/LWRS-15/01, Argonne National Laboratory, April 2015.
M2LW-15OR0404012.PNNL-24198.Fifield.pdf
  
Assessment of Cable Aging Equipment, Status of Acquired Materials, and Experimental Matrix at the Pacific Northwest National Laboratory, L. Fifield, M. Westman, A. Zwoster, and B. Schwenzer, PNNL-24198, Pacific Northwest National Laboratory, March 2015.
LWRS_MAaD_Assessment_Report2015.pdf
  
Assessment of the Quality Program for the Light Water Reactor Sustainability Program’s Materials Aging and Degradation Pathway at the Oak Ridge National Laboratory and the Pacific Northwest National Laboratory, March 2015.
LWRS.M3LW-15OR0404015.Duckworth.pdf
  
Scoping/Design Study on Optimum Configuration for Combined Thermal/Radiation Aging of Cable Insulation Samples at ORNL, R. Duckworth, Oak Ridge National Laboratory, March 2015.
LWRS_Semiannual report_2015_thermodynamics_final.pdf
  
Thermal aging modeling and validation on the Mo containing Fe-Cr-Ni alloys, Y. Yang, L. Tan, and J. Busby, ORNL/TM-2015/93, Oak Ridge National Laboratory, March 2015.
ORNL-TM-2015-72_Final.pdf
  
Thick Concrete Specimen Construction, Testing, and Preliminary Analysis, D. Clayton, K. Hoegh, and L. Khazanovich, ORNL/TM-2015/72, Oak Ridge National Laboratory, March 2015.
CASS_Aging_TestMatrix.pdf
  
Reestablishing Capability at PNNL and Aging and Testing Schedule, T. Byun, Pacific Northwest National Laboratory, January 2015.
M3LW-15OR0402012.RPV.RRTestMiniCT.pdf
  
Results of Fracture Toughness Tests for the Round Robin Test Program Using Mini-Compact Specimens, M.A. Sokolov, Oak Ridge National Laboratory, ORNL/LTR-2014/686, December 2014.
M2LW-14OR0402042_Swelling_Model.pdf
  
A Model of Radiation-Induced Microstructural Evolution, A. Barashev, S. Golubov, and R. Stoller, ORNL/LTR-2014/487, September 2014.
LW-140R0402152_CASS_Aging_Baseline_Data_2014.pdf
  
Baseline Characterization of Cast Stainless Steels, T.S. Byun and Y. Yang, Oak Ridge National Laboratory, ORNL/TM-2014/446, September 2014.
PNNL-23624_Aging_Cable_Study-Interim_Report-2014-091714.pdf
  
Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants—Interim Status for FY 2014, K. Simmons, L. Fifield, M Westman, J. Tedeschi, A. Jones, M. Prowant, A. Pardini, and P. Ramuhalli, Pacific Northwest National Laboratory, PNNL-23624, September 2014.
ANL-LWRS-14-01.pdf
  
Environmental Effect of Evolutionary Cyclic Plasticity Material Parameters of 316 Stainless Steel: An Experimental & Material Modeling Approach, S. Mohanty, W. K. Soppet, S. Majumdar, and K. Natesan, Argonne National Laboratory, ANL/LWRS-14/01, September 2014.
Concrete_TM-2014-362.pdf
  
Initial Investigation of Improved Volumetric Imaging of Concrete Using Advanced Processing Techniques, D. Clayton, A. Albright, and H. Santos-Villalobos, Oak Ridge National Laboratory, ORNL/TM-2014/362, September 2014.
65970.FY14.Q4 M3.pdf
  
New Technologies for Repairing Aging Cables in Nuclear Power Plants, K. Simmons, L. Fifield, M. Westman, and J. Roberts, Pacific Northwest National Laboratory, PNNL-XXXX, September 2014.
M2LW-14OR0404023_Cold-Worked_Alloy_600_690.pdf
  
Stress Corrosion Crack Initiation of Cold-Worked Alloy 600 and Alloy 690 in PWR Primary Water, S. Bruemmer, M. Olszta, D. Schreiber, and M. Toloczko, Pacific Northwest National Laboratory, September 2014.
M3LW-14OR0402053_Phase_Transformations_v2.pdf
  
Analysis of Phase Transformation Studies in Solute Addition Alloys, L. Tna, K. Field, and J. Busby, Oak Ridge National Laboratory, ORNL/TM-2014/303, August 2014.
A14129-R-001-Rev.0.pdf
  
Augmented Containment Inspection Results Supplement to LPI Reports A12191-R-001 and A12477-R-003, L. K. Wong, Report No. 14129-R-001, Rev. 0, August 2014.
A14129-LR-001_Rev0_Temperature_in_Containment.pdf
  
Joint Demonstration Project Completion Work at R.E. Ginna Nuclear Power Plant—Assessment of Temperature in Containment, R. Tilley and T. Rosseel, Ref. A141239-LR-001, Rev. 0, August 2014.
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Risk-Informed Safety Margin Characterization


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Description
Enhancements_to_Engineering-scale_Reactor_Pressure_Vessel_Fracture_Capabilities_in_Grizzly.pdf
  
Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, B. Spencer, W. Hoffman, W. Jiang, INL_EXT-17-43427, September 2017.
Status_of_Adaptive_Surrogates_within_the_RAVEN_framework.pdf
  
Status of Adaptive Surrogates within the RAVEN framework, A. Alfonsi, C. Wang, J. Cogliati, D. Mandelli, C. Rabiti, INL/EXT-17-43438, September 2017.
Nuclear_Power_Plant_Mechanical_Component_Flooding_Fragility_Experiments_FY-2017_Report.pdf
  
Nuclear Power Plant Mechanical Component Flooding Fragility Experiments FY-2017 Report, C. Pope, B. Savage, B. Johnson, C. Muchmore, L. Nichols, G. Roberts, E. Ryan, S. Suresh, A. Tahhan, R. Tuladhar, A. Wells, C. Smith, INL/EXT-17-43439, September 2017.
RELAP-7_Software_Verification_and_Validation_Plan_Requirements_Traceability_Matrix_(RTM)_Update_and_Code_Verification_Strat.pdf
  
RELAP-7 Software Verification and Validation Plan Requirements Traceability Matrix (RTM) Update and Code Verification Strategy, J. Yoo, Y. Choi, INL/EXT-17-43199, September 2017.
Preliminary_Study_on_the_Suitability_of_a_Second-Order_Reconstructed_Discontinuous_Galerkin_Method_for_RELAP-7_Thermal.pdf
  
Preliminary Study on the Suitability of a Second-Order Reconstructed Discontinuous Galerkin Method for RELAP-7 Thermal-Hydraulic Modeling, Y. Xia, J. Hansel, R. Berry, D. Andrs, R. Martineau, INL/EXT-17-4310, September 2017.
RELAP-7_Closure_Verification_Part_1_Vertical_Pre-CHF_Closures.pdf
  
RELAP-7 Closure Verification Part 1: Vertical Pre-CHF Closures, R. Johns, G. Swindlehurst, D. Andrs, R. Berry, J. Hansel, R. Martineau, L. Zou, INL/EXT-17-43592, September 2017.
Risk-Informed_Analysis_of Commercial_Nuclear_Reactors_the_RISMC_Approach_and_10CFR5069.pdf
  
Risk-Informed Analysis of Commercial Nuclear Reactors: the RISMC Approach and 10CFR50.69, D. Mandelli, C. Parisi, Z. Ma, D. Maljovec, A. Alfonsi, C. Smith, INL/LTD-17-43208, September 2017.
Risk-Informed_Safety_Margins_Characterization_RISMC_Pathway_Technical_Program_Plan.pdf
  
Risk-Informed Safety Margins Characterization (RISMC) Pathway Technical Program Plan, C. Smith,. C. Rabiti, R. Szilard, INL/EXT-17-43243, September 2017.
Modeling_of_Cu_Precipitate_Contributions_to_Reactor_Pressure_Vessel_Steel_Microstructure_Evolution_and_Embrittlement.pdf
  
Modeling of Cu Precipitate Contributions to Reactor Pressure Vessel Steel Microstructure Evolution and Embrittlement, S. Pitts, X. Bai, Y. Zhang, INL/EXT-17-43110, August 2017.
Advanced_Seismic_Probabilistic_Risk_Assessment_Methodology_Development_of_Beta_1-0_MASTODON_Toolset.pdf
  
Advanced Seismic Probabilistic Risk Assessment Methodology Development of Beta 1-0 MASTODON Toolset, C. Bolisetti, S. Veeraraghaven, A. Slaughter, J. Coleman, A. Kammerer, INL/EXT-17-43148, August 2017.
Nuclear_Power_Plant_Mechanical_Component_Flooding_Fragility_Experiments_Status.pdf
  
Nuclear Power Plant Mechanical Component Flooding Fragility Experiments Status, C. Pope, B. Savage, B. Johnson, C. Muchmore, L. Nichols, G. Roberts, E. Ryan, S. Suresh, A. Tahhan, R. Tuladhar, A. Wells, C. Smith, INL/EXT-17-42728, July 2017.
Risk-Informed_External_Hazards_Analysis_for_Seismic_and_Flooding_Phenomena_for_a_Generic_PWR.pdf
  
Risk-Informed External Hazards Analysis for Seismic and Flooding Phenomena for a Generic PWR, C. Parisi, S. Prescott, Z. Ma, B. Spears, R. Szilard, J. Coleman, B. Kosbab, INL/EXT-17-42666, July 2017.
Industry_Application_ECCS_LOCA_Integrated_Cladding_Emergency_Core_Cooling_System_Performance_Demonstration_of_LOTUS-Base.pdf
  
Industry Application ECCS / LOCA Integrated Cladding/Emergency Core Cooling System Performance: Demonstration of LOTUS-Baseline Coupled Analysis of the South Texas Plant Model, H. Zhang, R. Szilard, A. Epiney, C. Parisi, R. Vaghetto, A. Vanni, K. Neptune, INL/EXT-17-42461, June 2017.
RELAP-7_Closure_Correlations.pdf
  
RELAP-7 Closure Correlations, L. Zou, R.A. Berry, R.C. Martineau, D. Andrs, H. Zhang, J.E. Hansel, J.P. Sharpe, R.C. Johns, INL/EXT-17-4165, April 2017.
Software_Requirements_Specification_for_RELAP-7.pdf
  
Software Requirements Specification for RELAP-7, H. Zhang, D. Andrs, R. Martineau, N. Kyle, H. Henry, S. McKirdy, INL/EXT-17-41891, April 2017.
RELAP-7_Closure_Model_Verification_and_Benchmarking_Plan.pdf
  
RELAP-7 Closure Model Verification and Benchmarking Plan, R. Johns, R. Berry, L. Zou, R. Martineau, D. Andrs, and J. Hans, March 2017.
Smoothed-particle_Hydrodynamics_based_Wind_Representation.pdf
  
Smoothed-particle Hydrodynamics based Wind Representation, INL/EXT-16-40614, S. Hess, L. Lin, R. Sampath, S. Prescott, C. Smith, December 2016.
Additional_Model_Datasets_Results_to_Accelerate_the_Verification_and_Validation_of_RELAP-7.pdf
  
Additional Model Datasets and Results to Accelerate the Verification and Validation of RELAP-7, INL/EXT-16-40577, J. Yoo, Y. Choi, November 2016.
Data_Analysis_Approaches_for_the_Risk-Informed_Safety_Margins_Characterization_Toolkit.pdf
  
Data Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit, INL/EXT-16-39851, D. Mandelli, D. Maljovec, A. Alfonsi, C. Parisi, P. Talbot, C. Picoco, J. Cogliati, C. Wang, C. Smith, C. Rabiti,  September 2016.
Enhancements_of_the_RAVEN_code_in_FY16.pdf
  
Enhancements of the RAVEN code in FY16, INL/EXT-16-40094, A. Alfonsi, C. Rabiti, D. Maljevoic, D. Mandelli, J. Cogliati, September 2016.
Flooding_Fragility_Experiments_and_Prediction.pdf
  
Flooding Fragility Experiments and Prediction, INL/EXT-16-39963, C. Smith, B. Bhandari, C. Muchmore, A. Tahhan, A. Wells, L. Nichols, C. Pope, September 2016.
Loss_of_Coolant_Accident_Emergency_Core_Collant_System_Evaluation_of_Risk-informed_Margins.pdf
  
Loss of Coolant Accident Emergency Core Coolant System Evaluation of Risk-informed Margins Management Strategies for a Representative Pressurized Water Reactor, INL/EXTG-16-39805, R. Szilard, H. Zhang, A. Epiney, C. Parisi, P. Talbot, September 2016.
Lower_Length_Scale_Model_Development_for_Embrittlement_of_Reactor_Pressure_Vessel_Steel.pdf
  
Lower Length Scale Model Development for Embrittlement of Reactor Pressure Vessel Steel, INL/EXT-16-40011, Y. Zhang, P. Charkraborty, X. Bai, D. Schwen, September 2016.
Multi-Hazard_Advanced_Seismic_Probabilisitc_Risk_assessment_Tools_and_Applications.pdf
  
Multi-Hazard Advanced Seismic Probabilisitc Risk Assessment Tools and Applications, INL/EXT-16-4005, J. Coleman, C. Bolisetti, S. Veeraraghavan, C. Parisi, S. Prescott, A. Gupta, A. Kammerer, September 2016.
Probabilistic_Fracture_Mechanics_of_Reactor_Pressure_Vessels_with_Populations_of_Flaws.pdf
  
Probabilistic Fracture Mechanics of Reactor Pressure Vessels with Populations of Flaws, INL/EXT-16-40050, B. Spencer, M. Backman, P. Williams, W. Hoffman, A. Alfonsi, T. Dickson, B. Bass, H. Klasky, September 2016.
RELAP-7_Software_Verification_and_Validation_Plan.pdf
  
RELAP-7 Software Verification and Validation Plan, INL/EXT-16-40015, J. Yoo, Y. Choi, C. Smith, September 2016.
Risk-informed_Safety_Margins_Charterization_(RISMC)_Pathway_Technical_Program_Plan.pdf
  
Risk-informed Safety Margins Charterization (RISMC) Pathway Technical Program Plan, INL/EXT-11-22977, C. SMith, C. Rabiti, R. Martineau, R. Szilard, September 2016.
INL-EXT-16-39195_V_V_Plan_for_RIMM_Methods_and_Tools.pdf
  
Plan to Verify and Validate Multi-Hazard Risk-Informed Margin Management Methods and Tools, INL/EXT-16-39195, J. Coleman, C. Smith, A. Kammerer, July 2016
Demonstration_of_External_Hazards_Analysis.pdf
  
Demonstration of External Hazards Analysis, INL/EXT-16-39353, C. Parisi, S. Prescott, R. Szilard, J. Coleman, R. Spears, A. Gupta, July 2016.
Large_Scale_Laminar_Box_Test_Plan.pdf
  
Large Scale Laminar Box Test Plan, INL/EXT-16-39479, J. Coleman, J. Colletti, A. Tessari, July 2016.
Plan_to_Verify_and_Validate_Multi-Hazard_Risk-Informed_Margin_Management.pdf
  
Plan to Verify and Validate Multi-Hazard Risk-Informed Margin Management Methods and Tools, INL/EXT-16-39195, J. Coleman, C. Smith, A. Kammerer, July 2016.
Integration_of_Human_Reliability_Analysis_Models_into_the_Simulation-Based_Framework.pdf
  

Integration of Human Reliability Analysis Models into the Simulation-Based Framework, INL/EXT-16-39015, R. Boring, D. Madelli, M. Rasmussen, S. Herberger, T. Ulrich, K. Groth, C. Smith, June 2016.
RELAP-7_Theory_Manual.pdf
  
RELAP-7 Theory Manual, INL/EXT-14-31366, R. Berry, L., Zou, H. Zhao, H. Zhang, J. Peterson, R. Martineau, S. Kadioglu, D. Andrs, June 2016.
Status_of_the_Flooding_Fragility_Testing_Development.pdf
  
Status of the Flooding Fragility Testing Development, INL/EXT-16-39115, C. Pope, B. Savage, A. Sorensen, B. Bhandari, D. Kamerman, A. Tahhan, C. Muchmore, G. Roberts, E. Ryan, S. Suresh, A. Wells, C. Smith, June 2016.
INL-EXT-16-38931_Development_of_Three-Field_Poromechanics_Capability_in_MOOSE.pdf
  
Development of Three-Field Poromechanics Capability in MOOSE, M. Sivaselvan, N. Oliveto, A. Whittaker, INL/EXT-16-38931, April 2016.
INL-EXT-16-3823_R_D_Plan_for_RISMC_Industry_Application_ECCS_LOCA_Cladding_Acceptance_Criteria.pdf
  
R&D Plan for RISMC Industry Application #1: ECCS/LOCA Cladding Acceptance Criteria, INL/EXT-16-38231, R. Szilard, H. Zhang, A. Epiney, L. Tu, April 2016.
INL-EXT-16-38328_Development_Plan_for_the_External_Hazards_Experimental_Group.pdf
  
Development Plan for the External Hazards Experimental Group, INL/EXT-16-38328, J. Coleman, C. Smith, D. Burns, A. Kammerer, March 2016.
INL-EXT-16-38310_Grizzly_Usage_and_Theory_Manual.pdf
  
Grizzly Usage and Theory Manual, INL/EXT-16-38310, B. Spencer, M. Backman, P. Chakraborty, D. Schwen, Y. Zhang, H. Huang, X. Bai, W. Jiang, March 2016.
INL-EXT-16-38185_RELAP_Pressurizer_Component_Development_Updates.pdf
  
RELAP-7 Pressurizer Component Development Updates, INL/EXT-16-38185, H. Zhao, H. Zhang, L. Zou, R. Martineau, M. Holten, Q. Wu, March 2016.
INL-EXT-16-38089_RISMC_Toolkit_and_Methodology_R_and_D_Plan_for_Ext_Hazards_Analysis.pdf
  
RISMC Toolkit and Methodology Research and Development Plan for External Hazards Analysis, INL/EXT-16-38089, R. Szilard, J. Coleman, S. Prescott, C. Parisi, C. Smith, March 2016.
INL-EXT-16-37953_ RAVEN_BETA_1.0_Release.pdf
  
RAVEN Beta 1.0 Release, INL/EXT-16-37953, C. Rabiti, A. Alfonsi, J. Cogliati, D. Mandelli, R. Kinoshita, C. Wang, D. Maljovec, P. Talbot, February 2016.
INL-EXT-15-34123_RAVEN_User_Manual.pdf
  
RAVEN User Manual, INL/EXT-15-34123, Revision 4, C. Rabiti, A. ALfonsi, J. Cogliati, D. Mandelli, R. Kinoshita, S. Sen, C. Wang, February 2016.
System_Reliability_Analysis_Capability_and_Surrogate_Model_Application_in_RAVEN.pdf
  
System Reliability Analysis Capability and Surrogate Model Application in RAVEN, C. Rabiti, A. Alfonsi, D. Huang, F. Gleicher, B. Wang, H. Abdel-Khalik, V. Pascucci, C. Smith, INL/EXT-16-37243, November 2015
INL-EXT-16-37243 System Reliability Analysis Capability Surrogate Model Application in RAVEN.pdf
  
System Reliability Analysis Capability and Surrogate Model Application in RAVEN. C. Rabiti, A. Alfonsi, D. Huang, F. Gleicher, B.Wang, H.S. Abdel-Khalik, V. Pascucci, and C.L. Smith. Idaho National Laboratory INL/EXT-16-37243, November 2015.
Initial_Probabilistic_Evaluation_of_Reactor_Pressure_Vessel_Fracture_With_Grizzly_and_RAVEN.pdf
  
Fracture with Grizzly and RAVEN, B. Spencer, W. Hoffman, S. Sen, C. Rabiti, T. Dickson, R. Bass, INL/EXT-15-37121, October 2015
Flooding_Capability_for_River-based_Scenarios.pdf
  
Flooding Capability for River-based Scenarios, C. Smith, S. Prescott, E. Ryan, D. Calhoun, R. Sampath, D. Anderson, C. Cateneda, INL/EXT-15-37901
INL-EXT-15-36773 3D Simulation of External Flooding Events.pdf
  
3D Simulation of External Flooding Events for the RISMC Pathway. S. Prescott, D. Mandelli, R. Sampath, C. Smith, L. Lin. INL-EXT-15-36773 Idaho National Laboratory, September 2015.
INL-EXT-15-36735 Advanced Seismic Fragility Modeling.pdf
  
Advanced Seismic Fragility Modeling using Nonlinear Soil-Structure Interaction Analysis. C. Bolisetti, J. Coleman, M. Talaat, P. Hashimoto. INL-EXT-15-36735 Idaho National Laboratory, September 2015.
INL-EXT-15-36801 Demonstration Multievent Scenario.pdf
  
Demonstration of Coupled Multievent Scenario at a Nuclear Power Plant. J. Coleman, S. Prescott, C. Smith, R. Sampath. INL-EXT-15-36801 Idaho National Laboratory, September 2015.
INL-EXT-15-36758 Dynamic Event Tree Adv. and Control Logic Improvements.pdf
  
Dynamic Event Tree Advancements and Control Logic Improvements. A. Alfonsi, C. Rabiti, J. Cogliati, D. Mandelli, S. Sen, R. Kinoshita, C. Wang, P. Talbot, D. Maljovec, A. Slaughter, C. Smith. INL-EXT-15-36758, Idaho National Laboratory, September 2015.
INL-EXT-15-36752 Fracture Capabilities in Grizzly (X-FEM).pdf
  
Fracture Capabilities in Grizzly with the eXtended Finite Element Method (X-FEM). J. Dolbow, Z. Zhang, B. Spencer, W. Jiang. INL-EXT-36752, Idaho National Laboratory, September 2015.
INL-EXT-15-36425 Grizzly Model of Multi-Species Reactive Diffusion.pdf
  
Grizzly Model of Multi-Species Reactive Diffusion, Moisture/Heat Transfer, and Alkali-Silica Reaction in Concrete. H. Huang, B. Spencer, and G. Cai. INL-EXT-15-36425, Idaho National Laboratory, September 2015.
INL-EXT-15-36541 Industry Application ECCS Cladding Acceptance Criteria.pdf
  
Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration. R. H. Szilard, C. Frepoli, J. P. Yurko, R. Youngblood, A. Alfonsi, A. Zoino, C. Rabiti, H. Zhang, Paul D Bayless, H. Zhao, G. Swindlehurst, C. L. Smith. INL-EXT-15-36541, Idaho National Laboratory, September 2015.
INL-EXT-15-36754 Mesoscale Modeling of Solute Precipitation and Radiation Damage.pdf
  
Mesoscale modeling of solute precipitation and radiation damage. Y. Zhang, D. Schwen, H. Ke, X. Bai, J. Hales. INL-EXT-15-36754, Idaho National Laboratory, September 2015.
INL-EXT-15-36749 Progress on Industry Application Ext. Hazard Analyses.pdf
  
Progress on the Industry Application External Hazard Analyses Early Demonstration. C. L Smith, S. Prescott, J. Coleman, E. Ryan, B. Bhandari, D. Sludern, C. Pope, R. Sampath, INL-EXT-15-36749, Idaho National Laboratory, September 2015.
INL-EXT-15-36741 Modeling Operator Performance During Flooding Scenarios.pdf
  
Proof-of-Concept Demonstrations for Computation-Based Human Reliability Analysis: Modeling Operator Performance During Flooding Scenarios. J. C. Joe, R. L. Boring, S. Herberger, T. Miyake, D. Mandelli, and C. L. Smith. INL-EXT-15-36741 Idaho National Laboratory, September 2015.
INL-EXT-15-36656 RAVEN Quality Assurance Activities.pdf
  
RAVEN Quality Assurance Activities. J. J. Cogliati. INL-EXT-15-36656, Idaho National Laboratory, September 2015.
INL-EXT-15-36649 Reduced Order Model Implementation in the RISMC Toolkit.pdf
  
Reduced Order Model Implementation in the Risk-Informed Safety Margin Characterization Toolkit. D. Mandelli, C. Smith, A. Alfonsi, C. Rabiti, J. Cogliati, H. Zhao, I. Rinaldi, D. Maljovec, P. Talbot, B. Wang, V. Pascucci. INL-EXT-15-36649 Idaho National Laboratory September 2015.
INL-EXT-15-36763 RELAP-7 Development Updates.pdf
  
RELAP-7 Development Updates. H. Zhang, H. Zhao, F. Gleicher, M. DeHart, L. Zou, D. Andrs, R. Martineau. INL-EXT-36763, Idaho National Laboratory, September 2015.
INL-EXT-15-36771 RELAP-7 Progress Report.pdf
  
RELAP-7 Progress Report: FY-2015 Optimization Activities Summary. R. A. Berry, L. Zou, D. Andrs, R. C. Martineau. INL-EXT-15-36771, Idaho National Laboratory September 2015.
INL-EXT-11-22977 Revision 3 Risk-Informed Safety Margins Characterization (RISMC) Pathway Technical Program Plan Sept. 2015.pdf
  
Risk-Informed Safety Margins Characterization (RISMC) Pathway Technical Program Plan. C. Smith, C. Rabitii, R. Martineau, R. Szilard. INL-EXT-11-22977, Revision 3, Idaho National Laboratory September 2015.
INL-EXT-15-35933 RISMC Improved Sampling Algorithms.pdf
  
Improved Sampling Algorithms in the Risk-Informed Safety Margin Characterization Toolkit, D. Mandelli, C. Smith, A. Alfonsi, C. Rabiti, J. Cogliati. INL-EXT-15-35933, Idaho National Laboratory, August 2015.
INL-EXT-15-36051 A Research Roadmap for Computation-Based Human Reliability Analysis July 2015.pdf
  
A Research Roadmap for Computation-Based Human Reliability Analysis. R. Boring, D. Mandelli, J. Joe, C. Smith - Idaho National Laboratory INL-EXT-15-36051, K. Groth - Sandia National Laboratories July 2015.
INL-EXT-15-34786 Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement.pdf
  
Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly. P. Chakraborty, S. Bulent Biner, Y. Zhang, B. Spencer. INL/EXT-15-34786, Idaho National Laboratory July 2015.
INL-EXT-15-36100 Improving Limit Surface Search Algorithms in RAVEN.pdf
  
Improving Limit Surface Search Algorithms in RAVEN Using Acceleration Schemes. A. Alfonsi, C. Rabiti, D. Mandelli, J. Cogliati, S. Sen, C. Smith, INL-EXT-15-36100, Idaho National Laboratory July 2015.
INL-EXT-15-36101 Industry Application External Hazard Analyses Problem Statement. July 2015.pdf
  
Industry Application External Hazard Analyses Problem Statement. R. H Szilard, J. Coleman, C..L Smith, S. Prescott, A. Kammerer, R. Youngblood, C. Pope. INL-EXT-15-36101, Idaho National Laboratory July 2015.
INL-EXT-15-35687 Advanced Seismic Soil Structure Modeling.pdf
  
Advanced Seismic Soil Structure Modeling. C. Bolisetti, J. Coleman. INL/EXT-15-35687, Idaho National Laboratory, September 2015.
INL-EXT-35687 Advanced Seismic Soil Structure Modeling.pdf
  
Advanced Seismic Soil Structure Modeling. C. Bolisetti, J. Coleman. INL-EXT-15-35687, Idaho National Laboratory, June 2015.
INL-EXT-15-35073 Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Problem Statement.pdf
  
Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Problem Statement, R. Szilard, R. Youngblood, C. Frepoli, J. Yurko, G. Swindlehurst, H. Zhang, H. Zhao, P. Bayless, C. Rabiti, A. Alfonsi, and C. Smith, INL/EXT-15-35073, Idaho National Laboratory, April 2015.
INLEXT-15-34123_raven_user_manual_Rev_1.pdf
  
RAVEN User Manual, C. Rabiti, A. Alfonsi, J. Cogliati, D. Mandelli, R. Kinoshita, and S. Sen, INL/EXT-15-34123, Rev. 1, March 2015.
grizzly_fracture_milestone.pdf
  
Reactor Pressure Vessel Fracture Analysis Capabilities in Grizzly, B. Spencer, M. Backman, P Chakraborty, and W. Hoffman, INL-EXT-15-34736, March 2015.
Seismic Data Gathering and Validation.pdf
  
Light Water Reactor Sustainability Program Seismic Data Gathering and Validation, J. Coleman, Idaho National Laboratory, February 2015.
RELAP-7_Theory_Manual_INL-EXT-14-31366.pdf
  
RELAP-7 Theory Manual, R. Berry, J. Peterson, H. Zhang, R. Martineau, H. Zhao, L. Zou, and D. Andrs, Idaho National Laboratory, INL/EXT-14-31366, December 2014.
RELAP-7_Users_Guide_INL-EXT-14-33977.pdf
  
RELAP-7 User's Guide, H. Zhang, H. Zhao, L. Zou, D. Andrs, R. Berry, and R. Martineau, Idaho National Laboratory, INL/EXT-14-33977, December 2014.
INL-EXT-14-33903-Simulation_and_Non-Simulation_Based_Human_Reliability_Analysis_Approaches.pdf
  
Simulation and Non-Simulation Based Human Reliability Analysis Approaches, R. Boring, R. Shirley, J. Joe, D. Mandelli, and C. Smith, INL-EXT-14-33903, December 2014.
INL-EXT-14-33257- 3D_J-Integral_Capability_in_Grizzly.pdf
  
3D J-Integral Capability in Grizzly, B. Spencer, M. Backman, P. Chakraborty, and W. Hoffman, INL/EXT-14-33257, September 2014.
INLEXT-14-33200.pdf
  
Accident Tolerant Fuel Analysis, C. Smith, H. Chichester, J. Johns, M. Teague, M. Tonks, and R. Youngblood, Idaho National Laboratory, INL/EXT-14-33200, September 2014.
INL-EXT-14-33302-Advanced_Seismic_Probabilistic_Risk_Assessment_Demonstration_Project_Plan.pdf
  
Advanced Seismic Probabilistic Risk Assessment Demonstration Project Plan, J. Coleman, Idaho National Laboratory, INL/EXT-14-33302, September 2014.
Case_Study_Enhanced_Accident_Tolerance_Design_Changes-INL-EXT-14-32355-Rev1.pdf
  
Case Study for Enhanced Accident Tolerance Design Changes, S. Prescott, C. Smith, T. Koonce, and T. Yang, Idaho National Laboratory, INL/EXT-14-32355, Rev. 1, September 2014.
INL-EXT-14-33222-Demonstration_of_Nonlinear_Sesimic_and_New_Fragility_Curves.pdf
  
Demonstration of NonLinear Seismic Soil Structure Interaction and Applicability to New System Fragility Seismic Curves, J. Coleman, Idaho National Laboratory, INL/EXT-14-33222, September 2014.
INL-EXT-14-33102_9-25-14.pdf
  
Developing Fully Coupled Subchannel Model in RELAP-7, H. Zhang, L. Zou, H. Zhao, and R. Martineau, Idaho National Laboratory, INL/EXT-14-33102, September 2014.
RISMC-ESTAP-INL-EXT-14-33228.pdf
  
Enhanced Severe Transient Analysis for Prevention Technical Program Plan, H. Gougar, Idaho National Laboratory, INL/EXT-33228, September 2014.
INL-EXT-14-33251-Grizzly_Status_Report.pdf
  
Grizzly Status Report, B. Spencer, Y. Zhang, P. Chakraborty, M. Backman, W. Hoffman, D. Schwen, S. Bulent Biner, and X. Bai, Idaho National Laboratory, INL/EXT-14-33251, September 2014.
M3LW-14IN0702039_(HYSPLIT)_Software.pdf
  
Prototype Consequence Modeling Tool Based Upon the Hybrid Single Particle Lagrangian Integrated Trajectory (HYSPLIT) Software, C. Pope, B. Byambadorj, C. Hill, E. Lum, B. Nield, and J. Swanson, Idaho State University, September 2014.
INL-EXT-14-33162-Refined_BWR_SBO_Simulation_with_RELAP-7.pdf
  
Refined Boiling Water Reactor Station Blackout Simulation with RELAP-7, H. Zhao, H. Zhang, L. Zou, D. Andrs, R. Berry, and R. Martineau, Idaho National Laboratory, INL/EXT-14-33162, September 2014.
INL-EXT-14-33201-RELAP-7_Software_Verification_and_Validation_Plan-2014.pdf
  
RELAP-7 Software Verification and Validation Plan, C. Smith, Y. Choi, and L. Zou, Idaho National Laboratory, INL/EXT-14-33201, September 2014.
INL-EXT-14-33191-RISMC_Methods_Development_Work.pdf
  
Risk-Informed Safety Margin Characterization Methods Development Work, D. Mandelli, C. Smith, Z. Ma, T. Riley, J. Nielsen, A. Alfonsi, C. Rabiti, J. Cogliati, Idaho National Laboratory, INL/EXT-14-33191, September 2014.
INL-EXT-14-33186-RISMC_Advanced_Safety_Analysis_Project_Plan-Final.pdf
  
RISMC Advanced Safety Analysis Project Plan FY 2015 – FY 2019. R. H. Szilard, C. L. Smith, R. Youngblood. INL-EXT-14-33186, Idaho National Laboratory, September 2014.
External_Flooding_Pressurized_Water_Reactor_Station_Blackout_EXT-14-32906.pdf
  
Analysis of Pressurized Water Reactor Station Blackout Caused by External Flooding Using the RISMC Toolkit, C. Smith, D. Mandelli, S. Prescott, A. Alfonsi, C. Rabiti, J. Cogliati, and R. Kinoshita, Idaho National Laboratory, INL/EXT-14-32906, August 2014.
Survey_of_Models_for_Concrete Degradation_INL-EXT-14-32925.pdf
  
Survey of Models for Concrete Degradation, B. Spencer and H. Huang, INL/EXT-14-32925 Rev. 0, August 2014.
Case_Study_for_Enhanced_Accident_Tolerance_Design_Changes-INL-EXT-14-32355_R0.pdf
  
Light Water Reactor Sustainability Program Case Study for Enhanced Accident Tolerance Design Changes, S. Prescott, C. Smith, and T. Koonce, INL/EXT-14-32355, June 2014.
INL-EXT-14-32352_R0.pdf
  
RELAP-7 Numerical Stabilization: Entropy Viscosity Method, R. Berry, M. Delchini, and J. Ragusa, INL/EXT-14-32352, June 2014.
Grizzly_Year_End_M2LW-13IN07040110.pdf
  
Grizzly Year-End Progress Report, B. Spencer, Y. Zhang, P. Chakraborty, S.B. Biner, M. Backman, B. Wirth, S. Novascone, J. Hales, INL/EXT-13-30316, Revision 0, September 2013.
Modeling_Aging_RPV_Steels_M3LW-13IN0704019.pdf
  
Modeling of Late Blooming Phases and Precipitation Kinetics in Aging Reactor Pressure Vessel (RPV) Steels, Y. Zhang, P. Chakraborty, and S.B. Biner, INL/EXT-13-30267, September 2013.
INL-EXT-13-30203 Black Out Case Study RELAP and RAVEN.pdf
  
Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN. D. Mandelli, C. Smith, T. Riley, J. Schroeder, C. Rabiti, A. Alfonsi, J. Nielsen. (Idaho National Laboratory). D. Maljovec, B. Wang, V. Pascucci (University of Utah). INL/EXT-13-30203 Idaho National Laboratory, September 2013.
Technical_Approach_and_Results_from_the_Fuels_Pathway_on_an_Alternative_Selection_Case_Study-INL-EXT-13-30195.pdf
  
Technical Approach and Results from the Fuels Pathway on an Alternative Selection Case Study, R. Youngblood and C. Smith, INL/EXT-13-30195 Rev. 0, September 2013.
RELAP-7_SBO_Scenario_M2LW-13IN0704014.pdf
  
RELAP-7 Simulation Resolving an SBO Scenario on a Simplified Geometry of a BWR, H. Zhang, H. Zhao, L. Zou, D. Andrs, J. Peterson, R. Berry, and R. Martineau INL/EXT-13-29887, August 2013.
Technical_Basis_Guide_M2LW-13IN0702013.pdf
  
Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management, J. Knudsen and C. Smith, INL/EXT-13-30019, August 2013.
INL-EXT-13-29514_RELAP-7_M3LW-13IN0704018.pdf
  
RELAP-7: Demonstrating the Integration of Two-phase Flow Components for an Ideal BWR Loop, H. Zhang, H. Zhao, L. Zou, D. Andrs, J. Peterson, R. Berry, R. Martineau, INL/EXT-13-29514, June 2013.
EONY_Model_M3LW-13OR0704032.pdf
  
Implementation of Changes to the EONY Model to Account for Extended Service Conditions and Late Blooming Phases for Reactor Pressure Vessel Steels, J.T. Busby and B.D. Wirth, ORNL, May 2013.
RELAP-7_Seven-Equation_Two-Phase_M2LW-13IN0704013.pdf
  
RELAP-7: Demonstrating Seven-Equation, Two-Phase Flow Simulation in a Single-Pipe, Two-Phase Reactor Core and Steam Separator/Dryer, R. Berry, L. Zou, H. Zhao, D. Andrs, J. Peterson, H. Zhang, and R. Martineau, INL/EXT-13-28750, April 2013.
Grizzly-POC_b1_d.pdf
  
A Proof of Concept: Grizzly, the LWRS Program Materials Aging and Degradation Pathway Main Simulation Tool, B. Spencer (INL), J. Busby (ORNL), R. Martineau (INL), B. Wirth (UTK), September 2012.
RISMC_ATR_Case_Study_-_Final.pdf
  
Risk Informed Safety Margin Characterization (RISMC), Advanced Test Reactor Demonstration Case Study, INL/EXT-12-27015, Rev. 0, August 2012.
Report_on_Prevention_Analysis_Trial_Method_and_Case_Study_Improvements-April_2012.pdf
  
Report on Prevention Analysis Trial Method and Case Study Improvements, D. Blanchard and R. Youngblood, M3LW-12IN0702012, April 2012.
PNNL-Cumulative Damage Framework-20110804.pdf
  
Physics-Based Stress Corrosion Cracking Component Reliability Model Cast in an R7-Compatible Cumulative Damage Framework, S. D. Unwin, K. I. Johnson, R. F. Layton, P. P. Lowry, S. E. Sanborn, and M. B. Toloczko, PNNL- 20596, July 2011.
​​


​Advanced Instrumentation, Information, and Control System Technologies

  
  
Description
Evaluation_of_Control_Room_Interface_Designs_to_Support_Modernization_in_Nuclear_Power_Plants.pdf
  
Evaluation of Control Room Interface Designs to Support Modernization in Nuclear Power Plants, K. Le Blanc, C. Kovesdi, R. Hill, Z. Spielman, T. Hansen, J. Oxstrand, INL/EXT-17-43250
September 2017.
Technologies_for_Detecting_Interactions_between_Current_Plant_Configuration_States_and_Component_Manipulations_Directed.pdf
  
Technologies for Detecting Interactions between Current Plant Configuration States and Component Manipulations Directed by In-Use Procedures, S. St. Germain, J. Hugo, M. Manic, K. Amarasinghe, INL/EXT-17-43234, September 2017.
FY_2017_Summary_Report_on_Industrial_and_Regulatory_Engagement_Activities.pdf
  
FY 2017 Summary Report on Industrial and Regulatory Engagement Activities, K. Thomas, INL/EXT-17-43352, September 2017.
Prototype_Design,_Analysis,_and_Results_for_a_Liquid_Radiological_Waste_Control_Room.pdf
  
Prototype Design, Analysis, and Results for a Liquid Radiological Waste Control Room, C. Kovesdi, R. Hill, J. Oxstrand, Z. Spielman, K. Le Blanc, T. Hansen, INL/EXT-17-43226 September 2017.
Advanced_Instrumentation,_Information,_and_Control_Systems_Technologies_Technical_Program_Plan_for_FY_2018.pdf
  
Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan for FY 2018, B. Hallbert, K. Thomas, INL/EXT-13-28055, September 2017.
Automated_Work_Packages_Radio_Frequency_Identification,_Bluetooth_Beacons,_and_Video_Applications_in_the_Nuclear_Power_Ind.pdf
  
Automated Work Packages: Radio Frequency Identification, Bluetooth Beacons, and Video Applications in the Nuclear Power Industry, A. Rashdan, S. St Germain, R. Boring, T. Ulrich, B. Rice, INL/EXT-17-43264, September 2017.
Potential_to_Extend_the_Range_of_Established_Online_Monitoring_Technologies_Such_as_Guided_Waves_in_Nuclear_Power_Plant_Sys.pdf
  
Potential to Extend the Range of Established Online Monitoring Technologies, Such as Guided Waves, in Nuclear Power Plant Systems, Andrei Gribok, INL/ EXT-17-43242, September 2017.
Seamless_Digital_Environment_Data_Analytics_Use_Case_Study.pdf
  
Seamless Digital Environment – Data Analytics Use Case Study, J. Oxstrand, A. Bly, INL/EXT-17-42918, August 2017.
Development_of_an_Initial_Business_Case_Framework_for_Fleet-Based_Control_Room_Modernization.pdf
  
Development of an Initial Business Case Framework for Fleet-Based Control Room Modernization, C. Adolfson, K. Thomas, J. Joe, INL/EXT-17-42604, July 2017.
Human_Factors_Engineering_Aspects_of_Modifications_in_Control_Room_Modernization.pdf
  
Human Factors Engineering Aspects of Modifications in Control Room Modernization, J. Hugo, G. Clefton, J. Joe, INL/EXT-17-42190, June 2017.
Interrogation_of_Alkali-Silica_Reaction_Degraded_Concrete_Samples_using_Acoustic_and_Thermal_Techniques_to_Support.pdf
  
Interrogation of Alkali-Silica Reaction Degraded Concrete Samples using Acoustic and Thermal Techniques to Support Development of a Structural Health Monitoring Framework, S. Mahadevan, S. Miele, K. Neal, Y. Bao, V. Agarwal, B. Pham, D. Adams, INL/EXT-17-41852, Rev 1, April 2017.
Advanced_Instrumentation_Information_and_Control_Systems_Technologies_Technical_Program_Plan_for_FY17.pdf
  
Advanced Instrumentation Information and Control Systems Technologies Technical Program Plan for FY17, Revision 6, INL/EXT-13-28055, B. Hallbert, K. Thomas, September 2016.
Computer-Based_Procedures_FY16_Research_Activities.pdf
  
Computer-Based Procedures for Field Workers – FY16 Research Activities, INL/EXT-39984, J. Oxstrand, A. Bly, September 2016.
Data_Analysis_of_Different_Nondestructive_Testing_Techniques_to_Monitor_Concrete_Structure_Degradation_due_to_Alkali-Silica.pdf
  
Data Analysis of Different Nondestructive Testing Techniques to Monitor Concrete Structure Degradation due to Alkali-Silica Reaction, INL/EXT-16-39915, V. Agarwal, K. Neal, S. Mahadevan, B. Pham, D. Adams, September 2016.
Design_Guidance_CBP_for_Field_Workers.pdf
  
Design Guidance for Computer-Based Procedures for Field Workers, INL-EXT-16-39808, J. Oxstrand, K. Le Blanc, A. Bly, September 2016.
Development_Overview_Display_to_Allow_Advanced_Outage_Control_Center_Management_to_Quickly_Evaluate_Outage_Status.pdf
  
Development of an Overview Display to Allow Advanced Outage Control Center Management to Quickly Evaluate Outage Status, INL/EXT-16-39622, S. St. Germain, J. Hugo, September 2016.
Framework_Structural_Online_Health_Monitoring_of_Aging_Degradation.pdf
  
Framework for Structural Online Health Monitoring of Aging and Degradation of Secondary Systems due to some Aspects of Erosion, INL/EXT-16-39903, A. Gribok, S. Patnaik, C. Williams, M. Pattanaik, R. Kanakala, September 2016.
IFE_Control_Room_Recommendations.pdf
  
Report for Task 8.4: Development of Control Room Layout Recommendations, INL/EXT-16-39800, R. McDonald, September 2016.
Baseline_Study_Methodology_for_Future_Phases_of_Research_on_Nuclear_Power_Plant_Control_Room_Technologies.pdf
  
Baseline Study Methodology for Future Phases of Research on Nuclear Power Plant Control Room Technologies, INL/EXT-16-39497, K. Le Blanc, G. Bower, R. Hill, Z. Spielman, B. Rice, July 2016.
Business_Case_Cntrl_Rm_Modern.pdf
  
A Business Case for Nuclear Plant Control Room Modernization, INL/EXT-16-39098, K. Thomas, S. Lawrie, J. Niedermuller, June 2016.
Plan_to_Verify_and_Validate_Multi-Hazard.pdf
  
Plan to Verify and Validate Multi-Hazard Risk-Informed Margin Management Methods and Tools, INL/EXT-16-39195, J. Coleman, C. Smith, June 2016.
Automated_Work_Package_Conceptual_Design_and_Data_Architecture.pdf
  
Automated Work Package: Conceptual Design and Data Architecture, INL-EXT-16-38809, A. Al Rashdan, J. Oxstrand, V. Agarwal, May 2016.
Migration_of_Older_to_New_Digital_Control_Systems_in_Nuclear_Power_Plant_Main_Control_Rooms.pdf
  
Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms, INL/EXT-16-38576, C. Kovesdi,
J. Joe, R. Boring, April 2016.
A_Demonstration_of_Concrete_Structural Health Monitoring Framework for Degradation_due_to_Alkali-Silica_Reaction.pdf
  
A Demonstration of Concrete Structural Health Monitoring Framework for Degradation due to Alkali-Silica Reaction, INL_EXT-16-38602, S. Mahadevan, V. Agarwal, K. Neal, P. Nath, Y. Bao, G. Cai, P. Orme, D. Adams, D. Kosson, April 2016.
Modeling_Late_Blooming_Phase_Evolution_during_Post-irradiation_Annealing_in_Select_Reactor_Pressure_Vessels_Milestone.pdf
  
Modeling Late Blooming Phase Evolution during Post-irradiation Annealing in Select Reactor Pressure Vessels: Milestone 2 Report, S. Shu, H. Ke, D. Morgan, G. Odette, P. Wells, March 2016.
A_Business_Case_for_Advanced_Outage_Management.pdf
  
A Business Case for Advanced Outage Management, INL/EXT-16-38265, K. Thomas, S. Lawrie, J. Niedermuller, March 2016.
Digital_Architecture_Planning_Model.pdf
  
Digital Architecture Planning Model, INL/EXT-16-38220, J. Oxstrand, A. Al Rashdan, A. Bly, B. Rice, K. Fitzgerald, K. Wilson, March 2016.
Online_Monitoring_of_Induction_Motors.pdf
  
Online Monitoring of Induction Motors, T. McJunkin, V. Agarwal, N. Lybeck, INL/EXT-15-36681, January 2016.
INL-EXT-13-28055_Advanced_II_C_Technical_Program_Plan_Rev5.pdf.pdf
  
Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan for FY 2016, B. Hallbert, K. Thomas, INL/EXT-13-28055, Revision 5, November 2015.
2015 Summary Report on Industrial and Regulatory Engagement Activities.pdf
  
2015 Summary Report on Industrial and Regulatory Engagement Activities, K. Thomas, INL/EXT-15-36705, September 2015.
Digital Architecture.pdf
  
Digital Architecture – Results from a Gap Analysis, J. Oxstrand, K. Thomas, K. Fitzgerald, INL/EXT-15-36662 September 2015.
Computer-Based Procedures for Field Workers—Result and Insights from Three Usability and Interface Design Evaluations.pdf
  
Computer-Based Procedures for Field Workers—Result and Insights from Three Usability and Interface Design Evaluations, J. Oxstrand, K. Le Blanc, A. Bly, H. Medema, W. Hill, INL/EXT-15-36658, September 2015.
INL-EXT-15-36704 Verification and Validation of Digitally Upgraded Control Rooms.pdf
  
Verification and Validation of Digitally Upgraded Control Rooms, R. Boring, N. Lau, INL/EXT-15-36704, Idaho National Laboratory, September 2015.
LWRS_Benefits_Final_May2015.pdf
  
Benefits of Advanced Control Room Technologies: Phase One Upgrades to the HSSL and Performance Measures, K. Le Blanc, J. Joe, B. Rice, T. Ulrich, R. Boring, INL/EXT-15-3538, May 2015.
LWRS_Requirements_for_Control_Room.pdf
  
Requirements for Control Room Computer-Based Procedures for use in Hybrid Control Rooms, K. Le Blanc, J. Oxstrand, and J. Joe, INL/EXT-15-35284 Revision 0, Idaho National Laboratory, May 2015.
Simple_Demonstration_of_Concrete.pdf
  
A Simple Demonstration of Concrete Structural Health Monitoring Framework, S. Mahadevan, V. Agarwal, G.i Cai, P. Nath, Y. Bao, J. Maria Bru Brea, N. Myrent, D. Koester, D. Adams, and D. Kosson, INL/EXT-15-34729 Revision 0, March 2015.
LWRS_2015_M3_Report_Human_Performance_Measures.pdf
  
Operator Performance Metrics for Control Room Modernization: A Practical Guide for Early Design Evaluation, R. Boring, J. Joe, T. Ulrich, and R. Lew, INL/EXT-14-31511 Revision 0, Idaho National Laboratory, March 2015.
Cyber_Security_Evaluation_of_IIandC_Technologies_Final.pdf
  
Cyber Security Evaluation of II&C Technologies, K. Thomas, Idaho National Laboratory; M. Thow, T. Kenny, L Watkins, AREVA Inc., INL/EXT-14-33609, Revision 0, November 2014.
LWRS_2014_M3_Halden_Displays.pdf
  
Implementation of Software Tools for Hybrid Control Rooms in the Human Systems Simulation Laboratory, H. Jokstad, O. Berntsson, R, McDonald, Halden Reactor Project; R. Boring, B., K. Fitzgerald, Idaho National Laboratory, INL/EXT-14-33710, November 2014.
LWRS_IIandC_Technologies_Technical_Program_Plan_2014.pdf
  
Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan for 2014, B. Hallbert and K. Thomas, Idaho National Laboratory, INL/EXT-13-28055 Rev. 3, September 2014.
Automated_Work_Packages_Architecture.pdf
  
Automated Work Packages Architecture: An Initial Set of Human Factors and Instrumentation and Controls Requirements, V. Agarwal, J. Oxstrand, and K. Le Blanc, Idaho National Laboratory, INL/EXT-14-33172 Rev. 0, September 2014.
LWRS_Sept_2014_M3_Report_Baseline_HFE.pdf
  
Baseline Human Factors and Ergonomics in Support of Control Room Modernization at Nuclear Power Plants, R. Boring and J. Joe, Idaho National Laboratory, INL/EXT-14-33223, September 2014.
CBP_Report.pdf
  
Computer-Based Procedures for Field Activities: Results from Three Evaluations at Nuclear Power Plants, J. Oxstrand, K. Le Blanc, and A. Bly, Idaho National Laboratory, INL/EXT-14-33212 Rev. 0, September 2014.
Diagnostic_and_Prognostic_Models_for_Generator_Step-Up_Transformers.pdf
  
Diagnostic and Prognostic Models for Generator Step-Up Transformers, V. Agarwal, N. Lybeck, and B. Pham, Idaho National Laboratory, INL/EXT-14-33124 Rev.0, September 2014.
LWRS_AOCC_2014_Milestone_Report.pdf
  
Guidelines for Implementation of an Advanced Outage Control Center to Improve Outage Coordination, Problem Resolution, and Outage Risk Management, S. St. Germain, R. Farris. A. Whaley, H. Medema, and D. Gertman, Idaho National Laboratory, INL/EXT-14-33182 Rev. 0, September 2014.
LWRS_2014_M2_Report_Design_Phase_Control_Room_Modernization_Final_Release.pdf
  
Human Factors Engineering Design Phase Report for Control Room Modernization, T. Ulrich, R. Boring, and R. Lew, Idaho National Laboratory, INL/EXT-14-33221, September 2014.
M3_OLM_Passive.pdf
  
Interim Report on Concrete Degradation Mechanisms and Online Monitoring Techniques, S. Mahadevan, V. Agarwal, K. Neal, D. Kosson, and D. Adams, Idaho National Laboratory, INL/EXT-14-33134 Rev. 0, September 2014.
Status Report_Development_of_Micro-Scheduling_Software_Advanced_Outage_Control_Center Project.pdf
  
Status Report on the Development of Micro-Scheduling Software for the Advanced Outage Control Center Project, S. St. Germain, K. Thomas, J. Joe, and R. Farris, Idaho National Laboratory, INL/EXT-14-33036 Rev. 0, September 2014.
LWRS_2014_M3_Report_Human_Performance_Measures.pdf
  
Light Water Reactor Sustainability Program Operator Performance Metrics For Control Room Modernization: A Practical Guide For Early Design Evaluation , R. Boring, R. Lew, T Ulrich, and J. Joe, INL/EXT-14-31511, March 2014.
Long-Term_IIandC_Modernization_Future_Vision_Strategy_Nov 2013.pdf
  
Long-Term Instrumentation, Information, and Control Systems (II&C) Modernization Future Vision and Strategy, K. Thomas, B. Hallbert, Revision 3, INL/EXT-11-24154, November 2013.
Control_Room_Modernization_M2LW-13IN0603073.pdf
  
A Reference Plan for Control Room Modernization: Planning and Analysis Phase, J. Hugo, R. Boring, L. Hanes, and K. Thomas INL/EXT-13-30109, September 2013.
Computer_Based_Procedures_M2LW-13IN0603098.pdf
  
Computer-Based Procedures for Field Workers: Results from Three Evaluation Studies, J. Oxstrand, K. Le Blanc, and A. Bly, INL/EXT-13-30183, September 2013.
Advanced_Outage_Control_Centers_M3LW-13IN0603103.pdf
  
Development of Methodologies for Technology Deployment for Advanced Outage Control Centers That Improve Outage Coordination, Problem Resolution and Outage Risk Management, S. St. Germain, R. Farris, and H. Medema, INL/EXT-13-29934, Revision 0, September 2013.
Industrial_Regulatory_Engagement_M3LW-13IN0603055.pdf
  
Summary Report on Industrial and Regulatory Engagement Activities, K. Thomas, INL/EXT-12-27161, Revision 1, September 2013.
INL-EXT-13-29039_Halden_M3LW-13IN0603023.pdf
  
Installation of Halden Reactor Project Digital Interface Prototypes in the Human Systems Simulation Laboratory, H. Jokstad, J. O. Hol, T. J. Bjorlo, A. O. Braseth, C. Nihlwing, H. Svengren, and L. Hurlen, with additional contributions by Idaho National Laboratory staff, including J. Joe, R. Boring, D. Gertman, J. Persensky, INL/EXT-13-29039, May 2013.
LWRS_2013_M1_Report_CR_Modernization-Final.pdf
  
Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability, R. Boring, V. Agarwal, K. Fitzgerald, J. Hugo, B. Hallbert, INL/EXT-13-28432, Revision 0, March 2013.
Long-Term_IIandC_Modernization_Future_Vision_Strategy_Final.pdf
  
Long-Term Instrumentation, Information, and Control Systems (II&C) Modernization Future Vision and Strategy, K. Thomas, B. Hallbert, INL/EXT-11-24154, Revision 2, February 2013.
M4-12-27754_OnlineMonitoringRpt_EDGs_FINAL.pdf
  
Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators—Interim Report for FY 2013, B. T. Pham, N. J. Lybeck, V. Agarwal, INL/EXT-12-27754, December 2012.
IIandCST_TechnicalProgramPlan_September2012.pdf
  
Advanced Instrumentation, Information, and Control Systems Technologies Technical Program Plan, INL/EXT-13-28055, Revision 0, September 2012.
M3LW-12IN0603092-Computer_Based_Procedures_Report.pdf
  
Evaluation of Computer-Based Procedure System Prototype, J. Oxstrand, K. Le Blanc, S. Hays,  INL/EXT-12-27155, September 2012.
M3 LW12IN0603082_Guidance_for_Deployment_of_Mobile_Technologies.pdf
  
Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers, R. K. Farris, H. Medema, INL/EXT-12-27094, September 2012.
M3LW-12IN0602062_Report_INL-EXT-12-27181.pdf
  
Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012, N. J. Lybeck, V. Agarwal, B. T. Pham, H. D. Medema, K. Fitzgerald, INL/EXT-12-27181, September 2012.
LWRS_M3LW-12IN0603054 V2.pdf
  
Summary Report on Industrial and Regulatory Engagement Activities, K. Thomas, INL/MIS-12-27161, September 2012.
LWRS_Simulator_Buildout_Milestone_Report_.pdf
  
Digital Full-Scope Mockup of a Conventional Nuclear Power Plant Control Room, Phase I: Installation of a Utility Simulator at the Idaho National Laboratory, R. Boring, V. Agarwal, J. Joe, and J. Persensky, June 2012.
Long-Term IIandC Modernization Future Vision Strategy Rev 1.pdf
  
Long-Term Instrumentation, Information, and Control Systems (II&C) Modernization Future Vision and Strategy. K.D. Thomas and B.P. Hallbert, INL/EXT-11-24154, Rev. 1, February 2012.
M3L11IN06030506-07-08.pdf
  
LWRS II&C Industry and Regulatory Engagement Activities for FY 2011. K. D. Thomas, INL/EXT-11-23451, September 2011.
M2 L11IN06040203 PNNL-20671.pdf
  
Advanced Instrumentation, Information and Control System Technologies: Nondestructive Examination Technologies FY11 Report, R. M. Meyer, P. Ramuhalli, J. B. Coble, L. J. Bond, Pacific Northwest National Laboratory, PNNL-20671, August 2011.
M2L11IN06020302-Final.pdf
  
Lifecycle Prognostics Architecture for Selected High-Cost Active Components, N. Lybeck, B. Pham, and M. Tawfik, INL, and J. B. Coble, R. M. Meyer, P. Ramuhalli, and L. J. Bond, Pacific Northwest National Laboratory, INL/ EXT-11-22915, August 2011.
09-16631 Final Report.pdf
  
Report from the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies, B.P. Hallbert, and J.J. Persensky, INL, C Smidts and T. Aldemir, OSU, and J. Naser, EPRI, INL/EXT-09-16631, August 2009.

 

Reactor Safety Technologies

  
  
Description
The_MELTSPREAD_Code_for_Modeling_of_Ex-Vessel_Core_Debris_Spreading_Behavior.pdf
  
The MELTSPREAD Code for Modeling of Ex-Vessel Core Debris Spreading Behavior, M. Farmer, ANL/NE-17/20, September 2017.
Status_Report_on_Ex-Vessel_Coolability_and_Water_Management.pdf
  
Status Report on Ex-Vessel Coolability and Water Management, ANL/NE-16/18, M. Farmer, K. Robb, September 15, 2016.
Development_and_Implementation_of_Mechanistic_Terry_Turbine_Models_in_RELAP-7_to_Simulate_RCIC_Normal_Operation_Conditions.pdf
  
Development and Implementation of Mechanistic Terry Turbine Models in RELAP-7 to Simulate RCIC Normal Operation Conditions, INL/EXT-16-39857, H. Zhao, L. Zou, H. Zhang, J. O'Brien, September 2016.
Development_and_Implementation_of_Mechanistic_Terry_Turbine_Models_in_RELAP.pdf
  
Development and Implementation of Mechanistic Terry Turbine Models in RELAP-7 to Simulate RCIC Normal Operation Conditions, INL/EXT-16-39857, H. Zhao, L. Zou, H. Zhang, J. O'Brien, September 2016.
US_Efforts_in_Support_of_Examinations_at_Fukushima_Daiichi _2016_Evaluations.pdf
  
US Efforts in Support of Examinations at Fukushima Daiichi – 2016 Evaluations, ANL/LWRS-16/02, P. Amway, N. Andrews, W. Bixby, R. Bunt, M. Corradini, P. Ellison, M. Farmer, T. Farthing, M. Francis, J. Gabor, R. Gauntt, C. Henry, P. Humrickhouse, S. Kraft, R. Linthicum, W. Luangdilok, R. Lutz, D. Luxat, J. Maddox, C. Negin, c. Paik, M. Plys, J. Rempe, K. Robb, R. Sanders, R. Warchowiak, B. Williamson, August 2016.
Reactor_Safety_Technologies_Pathway_Technical_Program_Plan.pdf
  
Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan, M. Corradini, D. Peko, M. Farmer, J. Rempe, P. Humrickhouse, J. O'Brien, K. Robb, R. Gauntt, and D. Osborn, INL/EXT-15-35976, Revision 1, Idaho National Laboratory, June 2016.
Fukushima_Daiichi_Unit_1_Accident_Progression_Uncertainty_Analysis_and_Implications_for_Decommissioning_of_Fukushima_Reacto.pdf
  
Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors – Volume I, Sandia National Laboratories, SAND2016-0232, January 2106.
Modeling_of_the_Reactor_Core_Isolation_Cooling_Response_to_Beyond_Design_Basis_Operations_Phase_1.pdf
  
Modeling of the Reactor Core Isolation Cooling Response to Beyond Design Basis Operations – Phase 1, K. Ross, J. Cardoni, C. Wilson, C. Morrow, D. Osborn, R. Gauntt, SAND2015-10662, December 2015.
Application_of_Nonlinear_Seismic_Soil-Structure_Interaction_Analysis_for_Identification_of_Seismic_Margins_at_Nuclear_Powe.pdf
  
Application of Nonlinear Seismic Soil-Structure Interaction Analysis for Identification of Seismic Margins at Nuclear Power Plants, A. Varma, J. Seo, J. Coleman, INL/EXT-15-37382, November 2015
ORNL-TM-2015-278 Post Severe Accident Environmental Conditions for Essential Instrumentation for Boiling Water Reactors.pdf
  
Post Severe Accident Environmental Conditions for Essential Instrumentation for Boiling Water Reactors, D. Clayton,
M. Poore, ONRL/TM-2015/278, September 2015.
1 - 10Next



​Systems Analysis and Emerging Issues

  
  
Description
Economic_Market_Challenges_Facing_the_US_Nuclear_Commercial_Fleet_Cost_Revenue_Study.pdf
  
Economic and Market Challenges Facing the U.S. Nuclear Commercial Fleet - Cost and Revenue Study, R. Szilard, P. Sharpe, E. Kee, E. Davis, E. Grecheck, INL-EXT-17-42944, September 2017.
Cooling Water Issues and Opportunities.pdf
  
Cooling Water Issues & Opportunities at U.S. Nuclear Power Plants, G. Vine, INL/EXT-10-20208, Revision 1, December 2010.
Status_and_Outlook_for_Nuclear_Energy_in_the_US.pdf
  
Status and Outlook for Nuclear Energy in the US, NEI , July 2010.
Running_Dry_at_the_Power_Plant - EPRI_Journal-Summer-2007.pdf
  
Running Dry at the Power Plant - EPRI Journal (Summer 2007).

 

Advanced Light Water Reactor Nuclear Fuels

  
  
Description
ORNL-TM-2014-513_SiC_Joint_Irradiation.pdf
  
Status of High Flux Isotope Reactor Irradiation of Silicon Carbide/Silicon Carbide Joints, Y. Katoh, T. Koyanagi, J. Kiggans, N. Cetiner, and J. McDuffee, Oak Ridge National Laboratory, ORNL/TM-2014/513, September 2014.
M3LW-14IN0502042_SiC-Report-2013.pdf
  
20 Gwd SiC Clad Fuel Pin Examination, R. Morris, C. Baldwin, R. Ellis, J. Giaquinto, L. Ott, J. Peterson, and J. Schmidlin, Oak Ridge National Laboratory, ORNL/TM-2014/102, April 2014.
M3LW-14IN0504025_ORNL_LWRS_SiC-TubeTensileRR_140326.pdf
  
Inter-Laboratory Test Planning Document for New ASTM C28.07 Standard for Axial Tensile Properties of Ceramic Composite Tubes, Y. Katoh and T. Gonczy, March 2014.
Materials_Inventory_Database_M3LW-13IN0502023.pdf
  
Materials Inventory Database for the Light Water Reactor Sustainability Program, K. Ahmed and S.M. Bragg-Sitton, INL/EXT-13-29960, August 2013.
ORNLTM-2013273_SiC_Joining_Report_M3LW-13OR0504073.pdf
  
Status of Silicon Carbide Joining and Irradiation Studies, Y. Katoh, J. O. Kiggans, C. Shih, T. Koyanagi, J. L. McDuffee, L.L. Snead, ORNL/TM-2013/273, July 2013.
CVC-CVD-SiC_Out-of-pile_Testing_M3LW-13IN0502045.pdf
  
Evaluation of CVD and CVC SiC Reactivity towards UO2, C. M. Silva, S. L. Voit, Y. Katoh, June 2013.
EBSD_INL_EXT-13-28519_MSlevel_3_Final.pdf
  
EBSD Characterization of Tubular Cladding Plasticity after Bend Testing: A Feasibility Study, I. J. van Rooyen, INL/EXT-13-28519, March 2013.
M3LW-13IN0504053-Silicon_Carbide_Ceramic_Matrix_Composite_Failure_Mode_Analysis.pdf
  
Updated Probabilistic Failure Analysis for Wound Composite Ceramic Cladding Assembly, J. G. Hemrick, E. Lara-Curzio, INL/MIS-13-28798, ORNL/TM-2013/114, March 2013.
PreIrradiationTestingAnalysisLWRSHybrid_Rooyen.pdf
  
Pre-Irradiation Testing and Analysis to Support the LWRS Hybrid SiC-CMC-Zircaloy-4 Unfueled Rodlet Irradiation, I. J. van Rooyen, INL/EXT-12-27189, January 2013.
AdvLWRNucFuelCladdingSys_TPP_December2012.pdf
  
Light Water Reactor Sustainability Program Advanced LWR Nuclear Fuel Cladding System Development: Technical Program Plan, S. M. Bragg-Sitton, INL/MIS-12-25696, Revision 1, December 2012.
inl-con-11-23186.pdf
  
U.S. Department of Energy Accident-Resistant SiC Clad Nuclear Fuel Development, G.W. Griffith, INL, INL/ CON-11-23186, October 2011.
​​

Page Contact Information:

Cathy Barnard
(208) 526-0382
Cathy.Barnard@inl.gov​​​