| 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. | 47939 | | | | 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. | | 9/30/2014 2:35:45 PM | Website http://www.osti.gov/scitech/ Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical | 236 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2014-09-01T06:00:00Z | |
| 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. | 47935 | | | | 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. | | 4/28/2014 8:47:05 AM | Reports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect Reports produced before January 1, 1996, may be purchased by | 257 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2014-04-01T06:00:00Z | |
| 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. | 47936 | | | | 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. | | 3/31/2014 3:17:12 PM | ASTM specifies that the precision, repeatability, and reproducibility of the test method be addressed in published test standards The preferred method of determining those | 656 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2014-03-01T07:00:00Z | |
| Materials Inventory Database for the Light Water Reactor Sustainability Program, K. Ahmed and S.M. Bragg-Sitton, INL/EXT-13-29960, August 2013. | 47937 | | | | Materials Inventory Database for the Light Water Reactor Sustainability Program, K. Ahmed and S.M. Bragg-Sitton, INL/EXT-13-29960, August 2013. | | 11/20/2013 10:55:24 PM | Advanced Light Water Reactor Nuclear Fuels | 156 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2013-09-01T06:00:00Z | |
| 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. | 47938 | | | | 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. | | 7/31/2013 5:52:18 PM | Web site http://www.osti.gov/bridge Reports produced before January 1, 1996, may be purchased by members of the public from the following source The views and opinions of authors | 267 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2013-07-01T06:00:00Z | |
| Evaluation of CVD and CVC SiC Reactivity towards UO2 , C. M. Silva, S. L. Voit, Y. Katoh, June 2013. | 47931 | | | | Evaluation of CVD and CVC SiC Reactivity towards UO2, C. M. Silva, S. L. Voit, Y. Katoh, June 2013. | | 7/1/2013 1:24:15 PM | Dr. Jeremy T. Busby Materials Science and Technology Division P.O. Box 2008 – MS-6138 Oak Ridge, TN 37831-6138 Telephone: (865) 241-4622 Fax: (865) 241-3650 E-mail | 150 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2013-06-01T06:00:00Z | |
| EBSD Characterization of Tubular Cladding Plasticity after Bend Testing: A Feasibility Study, I. J. van Rooyen, INL/EXT-13-28519, March 2013. | 47932 | | | | EBSD Characterization of Tubular Cladding Plasticity after Bend Testing: A Feasibility Study, I. J. van Rooyen, INL/EXT-13-28519, March 2013. | | 3/28/2013 10:13:11 PM | The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance This information was prepared as an account of work sponsored by an agency of the | 323 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2013-03-01T07:00:00Z | |
| 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. | 47934 | | | | 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. | | 3/29/2013 8:59:50 PM | ORNL is a U.S. Department of Energy National Laboratory operated by UT – Battelle INL/MIS-13-28798 ORNL/TM-2013/114 Updated Probabilistic Failure Analysis for Wound Composite | 211 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2013-03-01T07:00:00Z | |
| 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. | 47940 | | | | 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. | | 1/11/2013 11:26:24 AM | The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-12-27189 Revision 1 Pre-Irradiation Testing and Analysis to Support the | 144 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2013-01-01T07:00:00Z | |
| 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. | 48021 | | | | 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. | | 1/14/2013 10:24:41 PM | Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the | 1576 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2012-12-01T07:00:00Z | |
| U.S. Department of Energy Accident-Resistant SiC Clad Nuclear Fuel Development, G.W. Griffith, INL, INL/ CON-11-23186, October 2011. | 47933 | | | | U.S. Department of Energy Accident-Resistant SiC Clad Nuclear Fuel Development, G.W. Griffith, INL, INL/ CON-11-23186, October 2011. | | 12/8/2011 5:49:01 PM | This is a preprint of a paper intended for publication in a journal or proceedings Since changes may be made before publication, this preprint should not be cited or reproduced | 492 | https://lwrs.inl.gov/Advanced Light Water Reactor Nuclear Fuels/Forms/AllItems.aspx | pdf | False | pdf | | 2011-10-01T06:00:00Z | |