Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly

Annals of Nuclear Energy

Volumn 35, Issue 3, 2008, Pages 478-484

  Perret, G ^a   Plaschy, M ^a   Murphy, M F ^a   Jatuff, F ^a   Chawla, R ^a,b  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

^b EPFL   (Switzerland)

Author keywords

[No Author keywords available]

Indexed keywords

FISSION PRODUCTS; FISSION REACTIONS; MATHEMATICAL MODELS; NUCLEAR FUELS; REACTION RATES; URANIUM;

CAPTURE RATES; FISSION RATES; RADIAL DISTRIBUTIONS;

BOILING WATER REACTORS;

EID: 38849151533     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2007.06.025     Document Type: Article

References (13)

1. 238U-capture-to-total-fissions in reactor fuel. Nucl. Instrum. Methods Phys. Res., Sect. A 556 (2006) 331-338
2. Gilmore G., and Hemingway J.D. Practical Gamma-Ray Spectrometry (1995), John Wiley & Sons
3. Helmersson S., Nerman H., and Paulsson L. SVEA-96: BWR Fuel for the 1990s. Nucl. Europe 1-2 (1989) 37
4. Jatuff F., Grimm P., Joneja O., Murphy M.F., Lüthi A., Seiler R., Brogli R., Jacot-Guillarmod R., Williams T., Helmersson S., and Chawla R. LWR-PROTEUS verification of reaction rate distributions in Modern 10x10 BWR Fuel. Nucl. Sci. Eng. 139 (2001) 262-272
5. Joneja O.P., Plaschy M., Jatuff F., et al. Validation of an MCNP4B whole-reactor model for LWR-PROTEUS using ENDF/B-V, ENDF/B-VI and JEF-2.2 cross-section libraries. Ann. Nucl. Energy 28 (2001) 701-713
6. Koning, A., Forrest, R., Kellett, M., Mills, R., Henriksson, H., Rugama, Y., 2006. The JEFF-3.1 Nuclear Data Library. JEFF Report 21, NEA No. 6190. ISBN 92-64-02314-3.
7. Leinweber G., Barry D.P., Trbovich M.J., Burke J.A., Drindak N.J., Knox H.D., and Ballad R.V. Neutron capture and total cross-section measurements and resonance parameters of gadolinium. Nucl. Sci. Eng. 154 (2006) 261-279
8. Murphy, M.F., 1999. The LWR-PROTEUS fuel pin γ-scanning machine. In: Proceedings of the Annual Meeting on Nuclear Technology 99, pp. 425-428, ISSN 0720-9207.
9. Murphy M.F., Lüthi A., Seiler R., Grimm P., Joneja O., Meister A., van Geemert R., Jatuff F., Brogli R., Jacot-Guillarmod R., Williams T., Helmersson S., and Chawla R. Neutronics investigations for the lower part of a Westinghouse SVEA-96+ Assembly. Nucl. Sci. Eng. 141 (2002) 32-45
10. Pelowitz, D.B., 2005. MCNPX User's Manual Version 2.5.0, Los Alamos National Laboratory Report LA-CP-05-0369.
11. Plaschy M., Jatuff F., Grimm P., Tani F., Jacot-Guillarmod R., Giust F., Krouthen J., and Chawla R. Comparison of deterministic neutronic calculations with Monte Carlo results for and advanced BWR fuel assembly with hafnium control blades. J. Nucl. Sci. Technol. 143 (2006) 1298-1310
12. Rose, P.F., 1991. ENDF/B-VI summary documentation, Report BNL-NCS-17541 (ENDF-201).
13. Williams, T., Chawla, R., Grimm, P., Joneja, O.P., Seiler, R., Ziver, A.K., 1998. New experiments at a zero-power facility using power reactor fuel. In: Proceedings of the International Conference on the Physics of Nuclear Science and Technology, Long Island, USA, 1, pp. 720-727.