Irradiation tests of mixed-oxide fuel prepared with weapons-derived plutonium

Proceedings of the 2004 International Meeting on LWR Fuel Performance

Volumn , Issue , 2004, Pages 285-293

  Hodge, S A ^a   Ott, L J ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ADVANCED TEST REACTOR; FISSION GAS RELEASE; MASTER MIX PROCESSES; MOX FUELS;

CLADDING (COATING); INTERFACES (COMPUTER); IRRADIATION; NUCLEAR REACTORS; OXIDATION;

FUELS;

EID: 32044472519     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (9)

1. Department of Energy, National Nuclear Security Administration, Amended Record of Decision for the Surplus Plutonium Disposition Program, 67 FR 76, Office of the Federal Register, Washington, D.C., April 19, 2002.
2. D. G. KOLMAN et al., "Thermally Induced Gallium Removal from Plutonium Dioxide for MOX Fuel Production," Journal of Nuclear Materials, 283, pp. 245-254, Elsevier, 2000.
3. L. J. OTT, "Thermal/Hydraulic Behavior Calculations for Weapons-Derived MOX Fuel with Comparison to PIE Observations," to be presented at the 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, September 19-22, 2004.
4. R. MANZEL and C. J. Walker, "EPMA and SEM of Fuel Samples from PWR Rods with an Average Burnup of Around 100 MWd/kgHM," Journal of Nuclear Materials, 301, p. 170-182, 2002.
5. R. N. MORRIS et al., "Post-Irradiation Examinations of FMDP Weapons-Derived MOX Fuel," to be presented at the 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, September 19-22, 2004.
6. 2 Fuel in Light Water Reactors," Nuclear Technology, 102, p. 29, 1993.
7. W. MCAFEE et al., "Postirradiation Ductility Demonstration Tests of Weapons-Derived MOX Fuel Cladding," to be presented at the ASME/JSME Pressure Vessel and Piping (PVP) Conference at San Diego, California (July 25-29).
8. L. DESGRANES, "Internal Corrosion Layer in PWR Fuel," OECD Proceedings, Seminar on Thermal Performance of High Burn-up LWR Fuel, p. 187-195, CEA, Caderache, France (1998).
9. A. M. GARDE, G. P. Smith, and R. C. Pirek, "Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy-4," Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, American Society for Testing and Materials, p. 407-430, 1996.