Analysis of mechanical load on cladding induced by fuel swelling during power ramp in high burn-up rod by fuel performance code FEMAXI-6

Nuclear Engineering and Design

Volumn 229, Issue 1, 2004, Pages 1-14

  Suzuki, Motoe ^a   Uetsuka, Hiroshi ^a   Saitou, Hiroaki ^a,b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b CRS Solutions Ltd   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

BUBBLE GROWTH; DIFFUSION EQUATIONS; MECHANICAL LOADING;

ABSORPTION; BUBBLE FORMATION; COMPUTER SIMULATION; CRACK PROPAGATION; CREEP; DUCTILITY; EQUATIONS OF STATE; FINITE ELEMENT METHOD; GRAIN BOUNDARIES; HARDENING; IRRADIATION; MATHEMATICAL MODELS; NUCLEAR ENGINEERING; SWELLING;

NUCLEAR FUEL CLADDING;

EID: 1242276092     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.11.017     Document Type: Article

References (15)

1. Hagrman, D.L., Reyman, G.A., 1979. MATPRO-Verson11, A Handbook of Materials for Use in the Analysis of Light Water Reactor Fuel Rod Behavior. NUREG/CR-0497, TREE-1280, Rev. 3.
2. MacDonald, P.E., Thompson, L.B., 1976. MATPRO-9 - A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior. USNRC TREE NUREG-1005.
3. Nakajima, T., Ichikawa, M., et al., 1985. FEMAXI-III: A Computer Code for the Analysis of Thermal and Mechanical Behavior of Fuel Rods. JAERI-1298.
4. NUPEC (Nuclear Power Engineering Corporation), 2002. The Annual Report on Irradiation Tests of High Burnup Fuels in FY 2001. Integrated Evaluation on Irradiation Behavior of BWR High Burnup Fuel [in Japanese].
5. Olander, D.R., 1976. Fundamental Aspects of Nuclear Reactor Fuel Elements. TID-26711-P1.
6. 2 and Zircaloy-2. CRFD-1075.
7. Sakurai, H., Ito, K., Tukada, Y., et al., 2000. Irradiation Characteristics of High Burnup BWR Fuels. ANS Topical Meeting, Park City, USA.
8. 2 Fuel. HPR-349/22, Enlarged HPG Meeting, Lillehammer, Norway.
9. Speight M.V. A calculation on the migration of fission gas in material exhibiting precipitation and re-solution of gas atoms under irradiation. Nucl. Sci. Eng. 37:1969;180.
10. Suzuki, M., 2000. Light Water Reactor Fuel Analysis Code FEMAXI-V (Ver. 1). JAERI-Data/Code 2000-030.
11. Uchida, M., Saito, H., 1993. RODBURN: A Code for Calculating Power Distribution in Fuel Rods. JAERI-M 93-108 [in Japanese].
12. Une, K., Nogita, et al., 1997. Effect of irradiation-induced microstructural evolution on high burnup fuel behavior. In: Proceedings of the International Topical Meeting on LWR Fuel Performance, Portland, pp. 478-489.
13. White, R.J., 2000. The Development of Grain Face Porosity in Irradiated Oxide Fuel. NEA/NSC/DOC (2000) 20. Seminar on Fission Gas Behavior in Water Reactor Fuels. Cadarache, France.
14. White R.J., Tucker M.O. A new fission gas release model. J. Nucl. Mater. 118:1983;1.
15. 2 Conductivity Degradation Based on In-Pile Temperature Data. HWR-469.