Modeling of the rim effect on thermal behavior of high-burnup UO2 fuel

Nuclear Technology

Volumn 127, Issue 2, 1999, Pages 151-159

  Lee, Byung Ho ^a   Koo, Yang Hyun ^a   Sohn, Dong Seong ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

CORRELATION METHODS; HIGH PRESSURE EFFECTS IN SOLIDS; MATHEMATICAL MODELS; POROSITY; PRESSURIZATION; PYROLYSIS; THERMAL CONDUCTIVITY OF SOLIDS; URANIUM DIOXIDE;

BURNUP; RIM EFFECT; RIM POROSITY MODEL;

NUCLEAR FUEL PELLETS;

EID: 0032689209     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT99-A2991     Document Type: Article

References (30)

1. 2 Fuel Retaining Rim Region," J. Korean Nucl. Soc., 29, 201 (1997).
2. 2 Fuel: Review and Recommendations," J. Nucl. Mater., 232, 166 (1994).
3. 2 Fuels," J. Nucl. Mater., 208, 223 (1994).
4. 2 Pellets on Irradiation to High Burnup," J. Nucl. Mater., 188, 73 (1992).
5. 2 Nuclear Fuel: Implication for Thermal Conductivity, Grain Growth and Gas Release," J. Nucl. Mater., 211, 11 (1994).
6. 2 LWR Fuels," J. Nucl. Mater., 189,141 (1992).
7. 2 Fuels with Burnup of 6-83GWd/t," J. Nucl. Mater., 206, 22 (1993).
8. 2 Fuel," J. Nucl. Mater., 226, 302 (1995).
9. 2," J. Nucl. Mater., 240, 205 (1997).
10. 2 and MOX Fuel Up to High Burnup," Ann. Nucl. Energy, 26, 47 (1998).
11. P. CHANTOIN, J. A. TURNBULL, and W. WIESENACK, C97F34, Organization for Economic Cooperation and Development, Nuclear Energy Agency Database (1997).
12. 2 Fuel Pellets," J. Nucl. Mater., 188, 19 (1992).
13. S. R. PATI, A. M. GARED, and L. J. CLINK, "Contribution of Pellet Rim Porosity to Low-Temperature Fission Gas Release at Extended Burnups," Proc. Int. Topl. Mtg. LWR Fuel Performance, Williamsburg, Virginia, April 17-20, 1988, p. 204, American Nuclear Society (1998).
14. N. KJAER-PEDERSON, "Rim Effect Observations from the Third RISO Fission Gas Project," Proc. Technical Committee Mtg., Ontario, Canada, April 28, 1992, p. 111 (1992).
15. L. E. THOMAS, C. E. BEYER, and L. A. CHARLOT, "Microstructural Analysis of LWR Spent Fuels at High Burnup," J. Nucl. Mater., 188, 80 (1992).
16. J. O. BARNER, M. E. CUNNINGHAM, M. D. FRESHLEY, and D. D. LANNING, "Evaluation of Fission Gas Release in High-Burnup Light Water Reactor Fuel Rods," Nucl. Technol., 102, 210 (1993).
17. R. MANZEL and R. EBERLE, "Fission Gas Release at High Burnup and the Influence of the Pellet Rim," Proc. Int. Topl. Mtg. LWR Fuel Performance, Avignon, France, April 21-24, 1991, p. 528, American Nuclear Society (1991).
18. M. R. BILLAUX, S. H. SHANN, L. F. VAN SWAM, and F. SONTHEIMER, "SIERRA: A Fuel Performance Code to Predict the Mechanical Behavior of Fuel Rods up to High Burnup," Proc. Int. Topl. Mtg. LWR Fuel Performance, Portland, Oregon, March 2-6, 1997, p. 576, American Nuclear Society (1997).
19. K. UNE, K. NOGITA, S. KASHIBE, T. TOYONAGE, and M. AMAYA, "Effect of Irradiated Microstructural Evolution on High Burnup Fuel Behavior," Proc. Int. Topl. Mtg. LWR Fuel Performance, Portland, Oregon, March 2-6, 1997, p. 478, American Nuclear Society (1997).
20. 2 Structure in LWR Fuel," J. Nucl. Mater., 226, 1 (1995).
21. J. SPINO, K. VENNIX, and M. COQUERELLE, "Detailed Characterization of the Rim Microstructure in PWR Fuels in the Burnup Range 40-67 GWd/tM," J. Nucl. Mater., 231, 179 (1996).
22. D. R. OLANDER, "Fundamental Aspects of Nuclear Reactor Fuel Elements," TID 26711-P1, Technical Information Center, Springfield, Virginia (1974).
23. J. STACKMANN and R. EBERLE, "Material Properties of Core Components Part 1: Fuel Rod and Gases," Kraftwerk Union (1983).
24. "MATPRO-VERSION 11 (Rev. 2) : A Handbook of Materials Properties for Use in the Analysis for Light Water Reactor Fuel Rod Behavior," NUREG/CR-0497, EG&G Idaho (Aug. 1981).
25. J. SPINO and M. COQUERELLE, "Microstructure and Fracture Toughness Characterization of Irradiated PWR Fuels in the Burnup Range 40-67 GWd/tM," presented at International Atomic Energy Agency Technical Committee Mtg. Advanced In-Pellet Technology for Improved Performance at High Burnup, Tokyo, Japan, 1996.
26. 2-Based SIMFUEL Thermal Conductivity: The Effect of the Burnup," J. Nucl. Mater., 217, 279 (1994).
27. 2 Conductivity Degradation Based on In-Pile Temperature Data," Proc. Int. Topl. Mtg. LWR Fuel Performance, Portland, Oregon, March 2-6, 1997, p. 507, American Nuclear Society (1997).
28. H. KAMPF and G. KARSTEN, "Effect of Different Types of Void Volumes on the Radial Temperature Distribution of Fuel Pins," Nucl. Appl. Technol., 9, 288 (1970).
29. 2 and Mixed (U,Pu) Oxide Fuels," J. Nucl. Mater., 110, 73 (1982).
30. E. KOLSTAD and C. VITANZA, "Fuel Rod and Core Materials Investigations Related to LWR Extended Burnup Operation," J. Nucl. Mater., 188, 104 (1992).