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

Journal of Nuclear Materials

Volumn 371, Issue 1-3, 2007, Pages 314-328

  Ott, L J ^a   Morris, R N ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

GUNS (ARMAMENT); NUCLEAR FUELS; NUCLEAR REACTORS; PLUTONIUM;

FUEL PERFORMANCE; MIXED-OXIDE TEST CAPSULES; POST-IRRADIATION; WEAPONS-DERIVED PLUTONIUM;

NEUTRON IRRADIATION;

EID: 34547841396     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2007.05.030     Document Type: Article

References (18)

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, DC, 19 April, 2002.
2. S.A. Hodge, L.J. Ott, in: Presented at the 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, 19-22 September, 2004.
3. Kolman D.G., et al. J. Nucl. Mater. 283 (2000) 245
4. L.J. Ott, in: Presented at the 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, 19-22 September, 2004.
5. R.N. Morris et al., in: Presented at the 2004 International Meeting on LWR Fuel Performance, Orlando, Florida, 19-22 September, 2004.
6. Goll W., et al. Nucl. Technol. 102 April (1993) 29
7. G.A. Berna et al., FRAPCON-3: A computer code for the calculation of steady-state thermal-mechanical behavior of oxide fuel rods for high burnup, NUREG/CR-6534, December 1997.
8. M.A. McGrath, in: International Topical Meeting on LWR Fuel Performance, American Nuclear Society, Park City, Utah, 10-13 April, 2000.
9. A. Soniak et al., in: G.D. Moan, P. Rudling (Eds.), Zirconium in the Nuclear Industry: Thirteenth International Symposium, ASTM STP 1423, ASTM International, 2002, p. 837.
10. M. Limback, T. Andersson, in: E.R. Bradley, G.P. Sahol (Eds.), Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, American Society for Testing and Materials, 1996, p. 448.
11. In: Bailly H., Menessier D., and Prunier C. (Eds). The Nuclear Fuel of Pressurized Water Reactors and Fast Reactors - Design and Behaviour (1999), Lavoisier Publishing Inc., Secaucus, NJ
12. Bernaudat C. Nucl. Eng. Des. 156 (1995) 373
13. ABAQUS/Standard User's Manual Version 5.8, Hibbit, Karlsson and Sorensen, Inc., Pawtucket, Rhode Island, 1998.
14. Walker C.T., Goll W., and Matsumura T. J. Nucl. Mater. 245 (1997) 169
15. Lassmann K. J. Nucl. Mater. 188 (1992) 295
16. G.S. Chang, MCNP and ORIGEN2 - Calculated Axial, Radial, and Azimuthal Profiles Versus Burnup in the MOX Test Assembly, ORMOX-GSC-10-00, Idaho National Engineering and Environmental Laboratory (INEEL), March 2000.
17. J. Briesmeister (Ed.), MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709-M, Los Alamos National Laboratory, 2000.
18. C. Vitanza, E. Kolstad, U. Graziani, in: ANS Topical Meeting on Light-Water Reactor Fuel Performance, Portland, Oregon, 29 April-3 May 1979.