journal article·2003-06

Comparison of various partial light water reactor core loadings with inert matrix and mixed-oxide fuel

U Kasemeyer, Ch Hellwig, J Lebenhaft, R Chawla

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Abstract

Abstract Two types of plutonium-containing cores have been compared, each comprising of four different stages of plutonium deployment in an actual 1000 MW (electric) pressurized water reactor. In a first step, core-follow calculations for four real-life cores with increasingly larger mixed-oxide (MOX) loadings were validated against measured plant data. In a second step, core loadings with inert matrix fuel (IMF) have been designed and considered which contain, on the average, the same amounts of plutonium as the four partial MOX loadings. From the latter loadings, the IMF rods with the highest power ratings were identified. The data depend on a pin power reconstruction of three-dimensional nodal calculations, and a partial verification of the pin power values was carried out using the transport codes CASMO and HELIOS as well as the Monte Carlo code MCNP. Fuel behaviour calculations were then performed for the highest power-rating rods employing models partly validated via recent data from the comparatory IMF/MOX irradiation test currently under way at Halden. Based on the various results obtained, conclusions have been drawn regarding IMF rod designs most likely to yield (in partial IMF core loadings) fuel behaviour similar to that of UO 2 fuel.
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Research context

OpenAlex topics: Nuclear reactor physics and engineering · Nuclear Materials and Properties · Nuclear and radioactivity studies

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References (21)

Show source-provided references
1. J.-S. Choi, IAEA, in: N. Numark, A. Michel (Eds.), Proceedings of the Conference Report of the International Conference on the Future of Plutonium, October 2000, Brussels, Belgium
2. P. Ledermann, D. Grenèche, in: Proceedings of the International Conference on Future Nuclear Systems GLOBAL’99, August–September 1999, Jackson Hole, Wyoming, USA
3. Kasemeyer · Prog. Nucl. Energy · 2001 · 383&384 · 30910.1016/S0149-1970(00)00123-2 ↗
4. Schram · Prog. Nucl. Energy · 2001 · 383&384 · 25910.1016/S0149-1970(00)00112-8 ↗
5. R. Chawla, C. Hellwig, F. Jatuff, U. Kasemeyer, G. Ledergerber, B.H. Lee, G. Rossiter, in: Proceedings of the ENS TOPFUEL 2001, Stockholm, Sweden, 27–30 May 2001
6. M. Edenius, K. Ekberg, B.H. Forssen, D. Knott, CASMO-4, a Fuel Assembly Burnup Program, User’s Manual, StudsvikSOA-951, Studsvik of America, Newton MA, September 1995
7. J.J. Casal, R.J.J. Stamm’ler, E.A. Villarino, A.A. Ferri, in: Proceedings of the International Topical Meeting on Advances in Mathematics, Computations and Reactor Physics, vol. 2, Pittsburgh, USA, 1991, p. 10.2.1
8. E.A. Villarino, R.J.J. Stamm’ler, in: Proceedings of the International Conference on Physics of Reactors PHYSOR 96, Mito, Japan, September 1996, vol. 1, p. A230
9. J.F. Briesmeister (Ed.), MCNP-A General Monte Carlo N-Particle Transport Code, Version 4C, Los Alamos National Laboratory, LA-13709-M, April 2000
10. L.S. Waters, MCNPX User’s Manual, Version 2.3.0, Los Alamos National Laboratory, LA-UR-02-2607, April 2002
11. T. Bahadir, CMS-Link User’s Manual, StudsvikSOA-9704, Studsvik of America, Newton MA, 1997
12. A.S. DiGiovine, J.D. Rhodes, SIMULATE-3 User’s Manual, StudsvikSOA-9515, Studsvik of America, Newton MA, 1995
13. M. Edenius et al., Core Analysis: New Features and Applications, Nuclear Europe Worldscan, No. 3/4, March–April, 1995, p. 35
14. M. Edenius, D. Knott, K. Smith, in: Proceedings of the International Conference on Physics of Nuclear Science and Technology, vol. 1, Long Island, NY, October 1998, p. 135
15. D. Knott et al., in: Proceedings of the International Conference on Physics of Nuclear Science and Technology, vol. 1, Long Island, NY, October 1998, p. 51
16. M. Edenius, D. Knott, K. Smith, Technical Meeting of Fuel Assembly and Reactor Physics and Calculation Methods Groups of the German Nuclear Society (KTG), Karlsruhe, Germany, February 1998, p. 27
17. Mori · Nucl. Sci. Eng. · 1995 · 121 · 4110.13182/NSE95-A24127 ↗
18. Chawla · Prog. Nucl. Energy · 2001 · 38 · 35910.1016/S0149-1970(00)00135-9 ↗
19. Lassmann · J. Nucl. Mater. · 1992 · 188 · 29510.1016/0022-3115(92)90487-6 ↗
20. K. Lassmann, A. Schubert, J. van de Laar, C.W.H.M. Vennix, Recent developments of the TRANSURANUS code with emphasis on high burnup phenomena, IAEA Technical Committee Meeting on Nuclear Fuel Behaviour Modelling at High Burnup, Lake Windermere, UK, June 2000
21. Ch. Hellwig, U. Kasemeyer, in: Proceedings of the Enlarged Halden Group Meeting, March 2001, Lillehammer, Norway