An advanced model for grain face diffusion transport in irradiated UO2 fuel. Part 1: Model formulation
Source abstract
Abstract
Abstract An advanced model for the grain face transport of gas atoms, self-consistently taking into consideration the effects of atom diffusion over the grain surface, their trapping by and irradiation induced resolution from intergranular bubbles is presented. The model allows prediction of a noticeable gas release from UO 2 fuel without visible interlinkage of grain face bubbles, i.e. at very low grain face coverage, below the critical value manifested by formation of bubble channels on grain faces interconnected with open porosity, in accordance with experimental observations of UO 2 and MOX fuel behaviour under various irradiation conditions.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (29)
Show source-provided references
1. White · J. Nucl. Mater. · 1983 · 118 · 110.1016/0022-3115(83)90176-9 ↗
2. Forsberg · J. Nucl. Mater. · 1985 · 135 · 14010.1016/0022-3115(85)90071-6 ↗
3. Dollins · J. Nucl. Mater. · 1976 · 91 · 143
4. Kogai · J. Nucl. Mater. · 1997 · 244 · 13110.1016/S0022-3115(96)00731-3 ↗
5. P. van Uffelen, Development of a new fission gas release and fuel swelling model, in: Enlarged Halden Programme Group Meeting, Lillehammer (Norway), 1998, HPR-349.
6. Ronchi · J. Nucl. Mater. · 1976 · 15 · 311
7. T.J. Heames, D.A. Williams, N.E. Bixler, A.J. Grimley, C.J. Wheatley, N.A. Johns, P. Domogala, L.W. Dickson, C.A. Alexander, I. Osborn-Lee, S. Zawadzki, J. Rest, A. Mason, R.Y. Lee, VICTORIA: A Mechanistic Model of Radionuclide Behaviour in the Reactor Coolant System Under Severe Accident Conditions, NUREG/CR-5545, 1992.10.2172/10121041 ↗
8. Une · J. Nucl. Sci. Technol. · 1990 · 27 · 100210.3327/jnst.27.1002 ↗
9. Kashibe · J. Nucl. Sci. Technol. · 1991 · 28 · 109010.3327/jnst.28.1090 ↗
10. Veshchunov · Nucl. Eng. Des. · 2006 · 236 · 17910.1016/j.nucengdes.2005.08.006 ↗
11. Veshchunov · J. Nucl. Mater. · 2007 · 362 · 32710.1016/j.jnucmat.2007.01.081 ↗
12. Zacharie · J. Nucl. Mater. · 1998 · 255 · 8510.1016/S0022-3115(98)00039-7 ↗
13. Veshchunov · J. Nucl. Mater. · 2008 · 374 · 4410.1016/j.jnucmat.2007.06.021 ↗
14. Walker · J. Nucl. Mater. · 1988 · 160 · 1010.1016/0022-3115(88)90003-7 ↗
15. Turnbull · J. Nucl. Mater. · 1974 · 50 · 6210.1016/0022-3115(74)90061-0 ↗
16. Turnbull · Philos. Mag. · 1974 · 30 · 4710.1080/14786439808206532 ↗
17. Wood · J. Nucl. Mater. · 1983 · 119 · 6710.1016/0022-3115(83)90053-3 ↗
18. Matthews · J. Nucl. Mater. · 1980 · 91 · 24110.1016/0022-3115(80)90224-X ↗
19. P. van Uffelen, Assessing the contribution of grain boundary diffusion to fission gas release in nuclear fuel. in: Enlarged Halden Programme Group Meeting, Loen (Norway), 1999.
20. Speight · Nucl. Sci. Eng. · 1969 · 37 · 18010.13182/NSE69-A20676 ↗
21. M.S. Veshchunov, A.V. Berdyshev, V.I. Tarasov, Development of Fission Gas Bubble Models for UO2 Fuel in Framework of MFPR Code, Preprint IBRAE-2000–08, Moscow, 2000.
22. A.V. Berdyshev, M.S. Veshchunov, Modelling of Grain Face Diffusion Transport and Swelling in UO2 Fuel, Preprint IBRAE-2002–14, Moscow, 2002.
23. Clemm · Acta Metall. · 1955 · 3 · 7010.1016/0001-6160(55)90014-6 ↗
24. G.B. Alcock, R.J. Hawkins, A.W.D. Hills, P. McNamara, Paper SM-66/36, IAEA, Symp. Thermodynamics, Vienna, 1965, p. 57.
25. Nichols · J. Nucl. Mater. · 1987 · 148 · 9210.1016/0022-3115(87)90523-X ↗
26. Y. Guerin, J. Noirot, D. Lispaux, C. Struzik, P. Garcia, P. Blainpain, G. Chigne, Microstructure evolution and in-reactor behaviour of MOX fuel, in: Proceedings of the International Topical Meeting on LWR Fuel Performance, 10–13 April 2000, Park City, Utah, USA, p. 706.
27. S. Mendez, Etude de l’interdiffusion U-Pu applique au combustible MOX, Thesis Universite Aix-Marseille, 1995.
28. Ukai · J. Nucl. Mater. · 1988 · 151 · 20910.1016/0022-3115(88)90073-6 ↗
29. C. Vitanza, E. Kolstad, U. Graziani, in: ANS Topical Meeting on Light Water Reactor Fuel Performance, Portland, Oregon, USA, 1979.