Irradiation performance of uranium-plutonium mixed nitride fuel pins in JOYO

Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy

Volumn , Issue , 2003, Pages 1694-1703

  Inoue, Masaki ^a   Iwai, Takashi ^a   Arai, Yasuo ^a   Asaga, Takeo ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

ACTINIDES; CLADDING (COATING); FAST REACTORS; FISSION REACTIONS; FUEL CONSUMPTION; IRRADIATION; MIXTURES; NITRIDES; PLUTONIUM; SWELLING; THERMAL EFFECTS; URANIUM;

FUEL IRRADIATION; FUEL PINS; JOYO; NITRIDE FUELS;

NUCLEAR FUELS;

EID: 2642523753     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (20)

1. H. NODA, and Y. KANI, "Summary of Phase 1 Feasibility Study on Commercialized Fast Reactor Systems", J.A.E.S.J., 43, 858 (2001) (in Japanese).
2. Y. KURATA et al., "The Accelerator Driven System Strategy in Japan", J. Nucl. Mater., 301, 1 (2002).
3. Y. ARAI et al., "Post Irradiation Examinations of Uranium-Plutonium Mixed Nitride Fuel Irradiated in JMTR (88F-5A Capsule)", Japan Atomic Energy Research Institute Report JAERI-Research 95-008 (1995) (in Japanese).
4. T. IWAI et al., "Behavior of Actinides and Fission Products in Mixed Nitride Fuels Irradiated in JMTR (88F-5A Capsule)", Japan Atomic Energy Research Institute Report JAERI-Research 2000-009 (2000) (in Japanese).
5. T. IWAI et al., "Post-Irradiation Examinations of Uranium-Plutonium Mixed Nitride Fuel Irradiated in JMTR (89F-3A Capsule)", Japan Atomic Energy Research Institute Report JAERI-Research 2000-010 (2000) (in Japanese).
6. Y. ARAI et al., "Fabrication of (U,Pu)N Fuel Pellets", J. Nucl. Mater., 168, 280 (1989).
7. Y. ARAI et al., "Fabrication of Uranium-Plutonium Mixed Carbide and Nitride Fuel Pins for the Irradiation Test in JOYO", Japan Atomic Energy Research Institute Report JAERI-Research 96-009 (1996) (in Japanese).
8. K. KATSUYAMA et al., "Post Irradiation Examination of (U,Pu)C and (U,Pu)N Fuel for Fast Reactor; Non-destructive Examination Results of the Fuel Pin", Japan Nuclear Cycle Development Institute Report JNC TN9410 2000-009 (2000) (in Japanese).
9. K. TANAKA et al., "Post Irradiation Examination of Uranium-Plutonium Mixed Nitride Fuels for Fast Reactor; Destructive Examinations of Nitride Fuel", Japan Nuclear Cycle Development Institute Report JNC TN9400 2002-001 (2002) (in Japanese).
10. T. IWAI et al., "Post Irradiation Examination of (U,Pu)C and (U,Pu)N Fuels for fast Reactors; Destructive Examination Results of the Fuel Pins", Japan Atomic Energy Research Institute Report JAERI-Research 2002-038 (2003) (in Japanese).
11. A.A. BAUER et al., "Mixed-Nitride Fuel Performance in EBR-II", Proceedings of Topical Meeting on Advanced LMFBR Fuels, p.299, Tucson, Arizona, USA, October 10-13, 1977.
12. A.A. BAUER et al., "Helium- and Sodium- Bonded Mixed-Nitride Fuel Performance", Proceedings of International Conference on Fast Breeder Reactor Fuel Performance, p.827, Monterey, California, USA, March 5-8, 1979.
13. H. BLANK, "Basic Aspects of Swelling in Dense Liquid Metal Fast Breeder Reactor Fuels", J. Less-Common Metals, 121, 583 (1986).
14. A.M. ROSS and R.L. STOUTE, "Heat Transfer Coefficient between UO2 and Zircaloy-2", Atomic Energy of Canada Limited Report AECL-1552, (1962).
15. M.C. BILLONE et al., "Progress in Modelling Carbide and Nitride Fuel Performance in Advanced LMFBRs", Proceedings of Topical Meeting on Advanced LMFBR Fuels, p.516, Tucson Arizona USA, October 10-13, 1977.
16. Y. ARAI et al. "Dependence of the Thermal Conductivity of (U,Pu)N on Porosity and Plutonium Content", J. Nucl. Mater., 195, 37 (1992).
17. P.G. LUCUTA et al., "A Pragmatic Approach to Modelling Thermal Conductivity of Irradiated UO2 Fuel: Review and Recommendation", J. Nucl. Mater., 232, 166 (1996).
18. S.B. ROSS et al., "Uranium Nitride Fuel Swelling Correlation", J. Nucl. Mater., 170, 169 (1990).
19. W.F. LYON et.al., "Advanced Liquid Metal Reactor Technology with Nitride Fuels", Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR'91), Vol. II, p.14.8, Kyoto, Kyoto, Japan, October 28 - November 1, 1991.
20. I.L.F.RAY and H.J.MATZKE, "Observation of a High Burnup Rim-Type Structure in an Advanced Plutonium-Uranium Carbide Fuel", J. Nucl. Mater., 250, 242 (1997).