The challenges associated with high burnup, high temperature and accelerated irradiation for TRISO-coated particle fuel
Source abstract
Abstract
Abstract Fuel service conditions proposed for the very high temperature reactor will be challenging. All major fuel-related design parameters (burnup, temperature, fast neutron fluence, power density, particle packing fraction) exceed the values that were qualified in the successful German UO2 coated particle fuel development program in the 1980s. Of particular concern are the high burnup and high temperatures expected in the very high temperature reactor. In this paper, the challenges associated with high burnup and high temperature are evaluated quantitatively by examining the performance of the fuel in terms of different known failure mechanisms. Potential design solutions to ameliorate the negative effects of high burnup and high temperature are discussed. Also of concern are the effects of accelerated irradiation on coated fuel that often occur during irradiation testing. These effects are evaluated in this paper and recommendations concerning allowable levels of accelerations are presented.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (18)
Show source-provided references
1. US DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, A technology roadmap for generation IV nuclear energy systems, GIF-002-00, December 2002.
2. G.K. Miller et al., in: Proceedings of the High Temperature Reactor Conference HTR-2004, Beijing, China, September 2004.
3. F. Ho, Material models of pyrocarbon and pyrolytic silicon carbide, CEGA-002820, July 1993.
4. D.A. Petti (Ed.), Development of improved models and designs for coated-particle gas reactor fuels, INEEL/EXT-05-02615, December 2004.
5. R. Gontard, H. Nabielek, Performance evaluation of modern HTR TRISO fuels, HTA-IB-05/90, July 1990.
6. Coen · J. Nucl. Mater. · 1972 · 45 · 9610.1016/0022-3115(72)90177-8 ↗
7. Coen · 1973
8. Minato · J. Nucl. Mater. · 1994 · 208 · 26610.1016/0022-3115(94)90336-0 ↗
9. C.A. Young, Pre- and postirradiation evaluation of fuel capsule HRB-14, GA-A15969, UC-77, 1980.10.2172/6772940 ↗
10. J. W. Ketterer et al., Capsule HRB-15A Postirradiation Examiantion Report, GA-A16758, UC-777, 1984.
11. J. W. Ketterer, B.F. Myers, Capsule HRB-16 Postirradiation Examination Report, HTGR-85-053, 1985.
12. G. Borschat, B. Hurttlen, G. Pott, Experiment FRJ2-P24 bestrahlungsbericht, KFA-ZBB-IB-19/82, August 1982.
13. Ch. Bauer, H. Klocher, Elektrolytische desintegration an 3 compacts aus dem experiment, FRJ-P24IRW-IN-8/83, 1983.
14. C.B. Scott, Summary Report on Selection of Reference LEU/Th Fuel System, GA Document 906330, Issue A, 12 April 1982.
15. J. Kendall, R. Bullock, in: Proceedings of the Second International Topical Meeting on High Temperature Reactor Technology, HTR-2004, Bejing, China, September 2004.
16. Bullock · J. Nucl. Mater. · 1983 · 115 · 6910.1016/0022-3115(83)90344-6 ↗
17. Bullock · J. Nucl. Mater. · 1984 · 125 · 30410.1016/0022-3115(84)90558-0 ↗
18. International Atomic Energy Agency, Fuel performance and fission product behaviour in gas cooled reactors, IAEA-TECDOC-978, November 1997.