Hydride fuel behavior in LWRs

Journal of Nuclear Materials

Volumn 346, Issue 2-3, 2005, Pages 98-108

  Olander, Donald R ^a   Ng, Marowen ^a  

^a Etcheverry Hall MCI 730   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

FISSION PRODUCTS; FRACTURE; NEUTRONS; NUCLEAR FUELS; THERMAL STRESS;

FRACTURE STRESSES; IRRADIATION-INDUCED SWELLING; NEUTRONIC EFFECTS; RADIAL REDISTRIBUTION;

NUCLEAR REACTORS;

EID: 27344458248     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2005.05.017     Document Type: Article

References (22)

1. E. Greenspan, H. Garkisch, J. Malen, M. Moalem, D. Olander, B. Petrovic, Z. Shayer, and N. Todreas Trans. Am. Nucl. Soc. 89 2003 381
2. M.T. Simnad Nucl. Eng. Des. 64 1981 403
3. R. Chesworth, G. West, Final Results of Qualification Testing of TRIGA Fuel in the Oak Ridge Research Reactor (ORR), Paper Presented at the International Meeting on Reduced Enrichment for Research and Test Reactors, Petten, Netherlands, 1985.
4. C. Toma et al., Characterization of TRIGA LEU Fuel Behavior in 14 MW Core, un-numbered report, Institute for Nuclear Research, Pitesti, Romania.
5. D. Wongsawaeng, D. Olander, Liquid-Metal Bonding of the Fuel-Cladding Gap in Light-Water Reactors, International Meeting on Light-Water Reactor Fuel Performance, Orlando, FL, 2004.
6. A.F. Lillie et al., USAEC Report AI-AEC-13084, Atomics International, 1973.
7. G. West, M. Simnad, G. Copeland, Final Results from TRIGA LEU Fuel Postirradiation Examination and Evaluation Following Long-Term Irradiation Testing in the ORR, General Atomics report GA-A18641, 1986.
8. Yeon Soo Kim, G. Hofmann, Nucl. Technol., submitted for publication.
9. GA Technologies, Inc. Uranium-Zirconium Hydride TRIGA LEU Fuel, Appendix I-7, Research Reactor Core Conversion Guidebook, IAEA-TEDOC-643 (date unknown).
10. V.I. Shcherbak Atomnaya Énergiya 31 1991 178
11. S. Yamanaka J. Nucl. Mater. 294 2001 94
12. U. Merten J. Nucl. Mater. 10 1963 201
13. J. Huang J. Nucl. Sci. Technol. 37 2000 887
14. A. Sommer, W. Dennison, NAA Report NAA-SR-5066, 1960.
15. Wei-E. Wang, and D.R. Olander J. Am. Ceram. Soc. 78 1995 3323
16. L. Libowitz J. Nucl. Mater. 5 1962 228
17. G. Eggers, Method of Making ZrH Fuel Element, US Patent 4,071,587, column 2, 1978.
18. U. Merten et al., in: The Proceedings of the Second Conference On Peaceful Uses of Atomic Energy, P/789, Geneva, 1958.
19. J.D. Gylfe et al., Evaluation of Zirconium Hydride as Moderator in Integral Boiling-Water Superheat Reactors, NAA-SR-5943, 1960, p. 11.
20. C.F. Bonilla Nuclear Engineering 1957 McGraw-Hill 566 p
21. R. Montgomery, R. Yang, Topical Report on Reactivity-Initiated Accidents: Bases for RIA Fuel and Core Coolability Criteria, Figs. 3-12, EPRI 1002865, 2002.
22. H. Rust Nucl. Power Plant Eng. 1979 395