Fuel performance code COSMOS for analysis of LWR UO2 and MOX fuel

Nuclear Engineering and Technology

Volumn 43, Issue 6, 2011, Pages 499-508

  Lee, Byung Ho ^a   Koo, Yang Hyun ^a   Oh, Jae Yong ^a   Cheon, Jin Sik ^a   Tahk, Young Wook ^a   Sohn, Dong Seong ^b  

^a Korea Atomic Energy Research Institute   (South Korea)

^b Ulsan National Institute of Science and Technology   (South Korea)

Author keywords

COSMOS; Fission Gas Release; Fuel; High Burnup; Performance Code; Thermal Conductivity

Indexed keywords

EID: 84555170141     PISSN: 17385733     EISSN: None     Source Type: Journal    
DOI: 10.5516/NET.2011.43.6.499     Document Type: Article

References (18)

1. 2 and MOX Fuel up to High Burnup", Annals of Nuclear Energy, 26, 47 (1999).
2. H. Zimmermann, "Investigations on Swelling and Fission Gas Behavior in Uranium Oxide", J. Nucl. Mater. 75 (1978) 154.
3. T. Kogai, K. Ito and Y. Iwano, "The Effect of Cladding Restraint on Fission Gas Release Behaviors", J. Nucl. Mater. 158, 64 (1988).
4. 2 Fuel under the Effect of External Restraint", J. Nucl. Mater. 280 86 (2000).
5. K. Une and S. Kashibe, J. Nucl Sci. Tech. 27, 1002 (1990).
6. Y.H. Koo, B.H. Lee, J.S. Cheon, D.S. Sohn, "Modeling and parametric studies of the effect of inhomogeneity on fission gas release in LWR MOX fuel", Annals of Nuclear Energy, 29, 271 (2002).
7. W. Wiesenack, T. Tverberg, "Thermal Performance of High Burnup Fuel In-pile Temperature Data and Analysis", 2000 International Topical Meeting on LWR Fuel Performance, Park City, Utah, April, 2000.
8. H. Kampf and G. Karsten, "Effect of Different Types of Void Volumes on the Radial Temperature Distribution of Fuel Pins", Nucl. Appl. Tech., 9, 288 (1970).
9. 2-x Mixed Oxide Fuel", J. Nucl. Maters., 188, 194 (1992).
10. G. Gates, et al., "Thermal Performance Modeling with the ENIGMA Code", Proc. of Seminar on Thermal Performance of High Burnup LWR Fuel, France, p.301 (1998).
11. L. Heins, H. Landskron, "Fuel Rod Design by Statistical Methods for MOX Fuel", Int. Symposium on MOX Fuel Cycle Technologies for Medium and Long-term Deployment, IAEA-SM-358/21, Austria (1999).
12. 2 Fuels", Proc. of the Seminar on Thermal Performance of High Burnup LWR Fuel, France, p.243 (1998).
13. B.H. Lee, Y.H. Koo, J.Y. Oh, D.S. Sohn, "Zircaloy-4 cladding corrosion model covering a wide range of PWR experiences", 378, 127 (2008).
14. B.H. Lee, Y.H. Koo, Cheon, D.S. Sohn, "Modeling of creep behavior of Zircaloy-4 by considering metallurgical effect", Annals of Nuclear Energy 29, 1 (2002).
15. Y. Kosaka, "Thermal Conductivity Degradation Analysis of the Ultra High Burnup Experiment (IFA-562)", HWR-341, Halden Reactor Project.
16. L.J. Ott, T. Tverberg, E. Sartori, Annals of Nuclear Energy, 36, 375 (2009).
17. L.J. Ott, NEA/NSC/DOC (2009)
18. M. Lipppens, FIGARO International Programme, 2000