Calculations on fission gas behaviour in the high burnup structure
Source abstract
Abstract
The behaviour of fission gas in high burnup fuel during steady-state and transient conditions is of special interest for safety reasons. Despite this, mechanistic models that reflect the fission gas transport processes and reliably predict the evolution of the remaining fission gas in the high burnup structure (HBS) are largely missing today. We start to address this problem by developing a one-dimensional, mass balance model and apply it to LWR UO2 fuel at the moderate temperatures found in the rim region. We examine the quantity of gas remaining in the HBS fuel matrix at steady state and compare it with experimental values. We find that the current model reproduces the 0.2wt% observed xenon concentration under certain conditions, viz. fast grain boundary diffusion and an effective volume diffusion coefficient. A sensitivity analysis is also conducted for the model parameters, the relative importance for which is not well established a priori. [All rights reserved Elsevier]
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 (26)
Show source-provided references
1. Secker · Nucl. Technol. · 2005 · 151 · 10910.13182/NT05-A3636 ↗
2. Schmitz · J. Nucl. Mater. · 1999 · 270 · 5510.1016/S0022-3115(98)00895-2 ↗
3. Fuketa · J. Nucl. Mater. · 1997 · 248 · 24910.1016/S0022-3115(97)00173-6 ↗
4. High Burnup Effects Programme Final Report, DOE/NE/34046-1.
5. Lassmann · J. Nucl. Mater. · 1995 · 226 · 110.1016/0022-3115(95)00116-6 ↗
6. IAEA, Fuel modeling at extended burnup, IAEA-TECDOC-998, Vienna, Austria, January 1998.
7. Spino · J. Nucl. Mater. · 2004 · 328 · 6710.1016/j.jnucmat.2004.03.009 ↗
8. Manzel · J. Nucl. Mater. · 2002 · 301 · 17010.1016/S0022-3115(01)00753-X ↗
9. Spino · J. Nucl. Mater. · 2000 · 281 · 14610.1016/S0022-3115(00)00236-1 ↗
10. Lozano · J. Nucl. Mater. · 1998 · 257 · 7810.1016/S0022-3115(98)00056-7 ↗
11. Spino · J. Nucl. Mater. · 1996 · 231 · 17910.1016/0022-3115(96)00374-1 ↗
12. Sonoda · Nucl. Instrum. and Meth. B. · 2002 · 191 · 62210.1016/S0168-583X(02)00622-5 ↗
13. J. Noirot, L. Desgranges, P. Marimbeau, in: Proceedings of the International Seminar on Fission Gas Behaviour in Water Reactor Fuels, Cadarache France, Les Journees de Caderache, 26–29 September 2000.
14. Brémier · Radiat. Eff. Def. S. · 2002 · 157 · 31110.1080/10420150213000 ↗
15. Losonen · J. Nucl. Mater. · 2002 · 304 · 2910.1016/S0022-3115(02)00856-5 ↗
16. H. Wallin, L.Å. Nordström, Ch. Hellwig, in: Proceedings of the International Seminar on Fission Gas Behaviour in Water Reactor Fuels, Cadarache France, Les Journees de Caderache, 26–29 September 2000.
17. Kogai · J. Nucl. Mater. · 1997 · 244 · 13110.1016/S0022-3115(96)00731-3 ↗
18. Veshchunov · J. Nucl. Mater. · 2000 · 277 · 6710.1016/S0022-3115(99)00136-1 ↗
19. Speight · Nucl. Sci. Eng. · 1969 · 37 · 18010.13182/NSE69-A20676 ↗
20. Olander · J. Nucl. Mater. · 2001 · 288 · 13710.1016/S0022-3115(00)00725-X ↗
21. Rest · J. Nucl. Mater. · 2003 · 321 · 30510.1016/S0022-3115(03)00303-9 ↗
22. P. Van Uffelen, Contribution to the Modelling of Fission Gas Release in Light Water Reactor Fuel, Ph.D. Thesis, l’Université de Liége, SCK-CEN, January 2002.
23. Kim · J. Nucl. Mater. · 2004 · 326 · 9710.1016/j.jnucmat.2003.12.014 ↗
24. J.A. Turnbull, R.J. White, C. Wise, in: IAEA Technical Committee meeting on Water Reactor Fuel Element Computer Modelling in Steady-state, Transient and Accident Conditions, T1-TC-659, Preston, England, 1998, p. 168.
25. Matzke · Radiat. Eff. Def. S. · 1980 · 53 · 21910.1080/00337578008207118 ↗
26. Hiernaut · J. Nucl. Mater. · 2001 · 294 · 3910.1016/S0022-3115(01)00469-X ↗