Conceptual studies for pressurized water reactor cores employing plutonium-erbium-zirconium oxide inert matrix fuel assemblies

Journal of Nuclear Materials

Volumn 274, Issue 1, 1999, Pages 146-152

  Stanculescu, A ^a   Kasemeyer, U ^b   Paratte, J M ^a   Chawla, R ^a,c  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

^b OECD HALDEN REACTOR PROJECT   (Norway)

^c EPFL   (Switzerland)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; ERBIUM COMPOUNDS; PLUTONIUM COMPOUNDS; PRESSURIZED WATER REACTORS; REACTOR CORES; URANIUM DIOXIDE; ZIRCONIA;

INERT MATRIX FUELS (IMF);

MIXED OXIDE FUELS;

EID: 0032678925     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(99)00082-3     Document Type: Article

References (11)

1. C. Degueldre, U. Kasemeyer, F. Botta, G. Ledergerber, Mater. Res. Soc. Symp. Proc. 412 (1995) 15.
2. J.-M. Paratte, R. Chawla, Ann. Nucl. Energy 22 (1995) 471.
3. U. Kasemeyer, J.-M. Paratte, R. Chawla, Reactor physics characteristics of possible fuel materials for plutonium-incinerating LWRs, in: Proc. IAEA Technical Committee Meeting on Unconventional Options for Plutonium Disposition, Obninsk, Russia, Nov. 7-11, 1994.
4. U. Kasemeyer, P. Grimm, J.-M. Paratte, R. Chawla, Nucl. Technol. 121 (1998) 52-63.
5. U. Kasemeyer, PhD thesis No. 1757, Swiss Federal Institute of Technology, Lausanne, 1998.
6. G. Ledergerber, C. Degueldre, U. Kasemeyer, A. Stanculescu, J.-M. Paratte, R. Chawla, Using civilian plutonium in LWRs with an inert matrix fuel, in: Proceedings of the International Conference on Future Nuclear Systems (GLOBAL '97), vol. 2, 1997, p. 1068.
7. J.-M. Paratte, K. Foskolos, P. Grimm, C. Maeder, Das PSI-Codesystem ELCOS zur stationären Berechnung von Leichtwasserreaktoren, in: Proceedings of Jahrestagung Kerntechnik, Travemünde, Germany, 17-19 May, 1988.
8. J. Rowlands, N. Tubbs, The joint evaluated file, a new data resource for reactor calculations, in: Proceedings of the International Conference on Nuclear Data for Basic and Applied Science, Santa Fe, New Mexico, 13-17 May, 1985.
9. A.I. Blokhin et al., Current status of Russian evaluated neutron data libraries (Files BROND-2, FOND and ABBN-90), in: Proceedings of the International Conference on Nuclear Data for Science and Technology, Gatlinburg, Tennessee, 9-13 May, 1994, American Nuclear Society, vol. 2, 1994, p. 695.
10. Y. Kikuchi, Present status and benchmark tests of JENDL-2, in: Proceedings of the International Conference Nuclear Data for Science and Technology, Antwerp, Belgium, 6-10 Sept. 1982.
11. J. Bouchard, Influence des stratégies du cycle du combustible sur le choix des réacteurs de nouvelle génération, in: Proceedings of the International ENS Topical Meeting on Next Generation LWRs (TOPNUX '93), The Hague, The Netherlands, 1993.