journal article·2010-06

Helium release from the uranium–plutonium mixed oxide (MOX) fuel irradiated to high burn-up in a fast breeder reactor (FBR)

Kozo Katsuyama, Akihiro Ishimi, Koji Maeda, Tsuyoshi Nagamine, Takeo Asaga

Journal of Nuclear Materials· Volume 401· Issue 1-3
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Abstract

Abstract The helium releases were investigated in FBR fuel pins irradiated to high burn-up. The released amounts increased with the increase of burn-up, but no burn-up dependence of their release fraction to total amounts generated was seen. The contents of 241Am in fuel pellets affected the released amounts. The effect of released helium on the internal pressure in fuel pins was smaller in FBR fuel pins than in LWR fuel pins, but released helium in fuel pins containing increased amounts of 241Am, which are anticipated in future FBRs, is expected to affect the internal pressure.
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

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References (12)

Show source-provided references
1. H. Bairiot, M. Lippens, Commercial MOX fuel: the experimental and demonstration background, in: Technical Committee Meeting Recycling of Pu and U in Water Reactor Fuel, Cadarache, France, 13–16 November 1989.
2. Grimes · J. Nucl. Mater. · 1990 · 172 · 12310.1016/0022-3115(90)90016-G ↗
3. M. Billaux, M. Lippenns, D. Boulanger, Proceedings of a Conference on Water Reactor Fuel Element Computer Modelling in Steady State, Transient and Accident Conditions, Preston, UK, 18–22 September 1988, pp. 182–186.
4. T. Mitsugi, N. Kushida, K. Kikuchi, 1997 International Topical Meeting on Light Water Reactor Fuel Performance, Portland, Oregon, 2–6 March 1997, pp. 54–61.
5. Roudil · J. Nucl. Mater. · 2008 · 378 · 7010.1016/j.jnucmat.2008.05.001 ↗
6. Ronchi · J. Nucl. Mater. · 2004 · 325 · 110.1016/j.jnucmat.2003.10.006 ↗
7. R.L. Yang, R.L. Crowther, International Working Group on Water Reactor Fuel Performance and Technology, Tokyo, 26–30 November 1984, pp. 220–229.
8. Maeda · J. Nucl. Mater. · 2005 · 346 · 24410.1016/j.jnucmat.2005.06.014 ↗
9. B.F. Rider, Compilation of Fission Product Yields, NEDO-12154-3(C), General Electric Co., Nuclear Fuel and Services Engineering Department, General Electric Co., 1981.
10. S. Maeda, T. Sekine, T. Aoyama, Trans. Int. Meeting of RRFM 2001, European Nuclear Society, Aachen, Germany, 2001, pp. 56–60.
11. D.R. Olander et al., Fundamental Aspects of Nuclear Reactor Fuel Elements, Energy Research and Development Administration, Washington DC, 1976 (Chapter 15).10.2172/7343826 ↗
12. V. Tikare, E.A. Holm, P.G. Medvedev, Proceedings of Top Fuel 2009, Paris, France, 6–10 September 2009, pp. 782–788.