Comparisons of Deterministic Neutronic Calculations with Monte Carlo Results for an Advanced BWR Fuel Assembly with Hafnium Control Blades

Journal of Nuclear Science and Technology

Volumn 43, Issue 11, 2006, Pages 1298-1310

  Plaschy, Michael ^a   Jatuff, Fabian ^a   Grimm, Peter ^a   Tani, Filippo ^a,b   Jacot Guillarmod, Roland ^c   Giust, Flavio ^c   Krouthen, Jan ^c   Chawla, Rakesh ^a,b  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

^b EPFL   (Switzerland)

^c Nordostschweizerische Kraftwerke AG   (Switzerland)

Author keywords

BOXER; BWR fuel assembly; CASMO4; Data libraries; Deterministic codes; Hafnium control blades; HELIOS1.6; MCNPX2.5; Monte Carlo methods

Indexed keywords

ACCIDENT PREVENTION; CONTROL RODS; DATA STORAGE EQUIPMENT; DIGITAL LIBRARIES; FLUXES; GADOLINIUM; HAFNIUM; MODERATORS; MONTE CARLO METHODS; NEUTRONS; NUMERICAL METHODS; OPTIMIZATION; RATE CONSTANTS;

BWR FUEL ASSEMBLY; CONTROL BLADES; DETERMINSTIC CODE; REACTION RATE DISTRIBUTIONS;

BOILING WATER REACTORS;

EID: 33846491232     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2006.9711224     Document Type: Article

References (13)

1. J. Rowlands, et al., Light Water Reactor (LWR) Pin Cell Benchmark Intercomparisons, JEFF Report 15, OECD/NEA, (1999).
2. S. Cathalau, et al., Benchmark Calculations of Power Distribution within Fuel Assemblies, NEA/NSC/DOC(2000)3, OECD/NEA, (2000).
3. T. Williams, R. Chawla, P. Grimm, et al., “New experiments at a zero-power facility using power reactor fuel,” Proc. Int. Conf. Physics of Nuclear Science and Technology, Long Island, New York, Oct. 5-8, 1998, p. 720 (1999).
4. F. Jatuff, P. Grimm, M. Murphy, R. Seiler, R. Jacot-Guillarmod, J. Krouthen, T. Williams, S. Helmersson, R. Chawla, “Experimental validation of pin power distributions for a BWR assembly with hafnium control blades,” Proc. Int. Conf. on the New Frontier of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, PHYS-OR, Chicago, USA, April 25-29, 2004, (2004).
5. S. Helmersson, H. Nerman, L. Paulsson, “SVEA-96: BWR fuel for the 1990s,” Nucl. Eur., 1-2, 37 (1989).
6. J. S. Hendricks, G. W. McKinney, L. S. Waters, T. L. Roberts, H. W. Egdorf, J. P. Finch, H. R. Trellue, E. J. Pitcher, D. R. Mayo, M. T. Swinhoe, S. J. Tobin, J. W. Durkee, F. X. Gallmeier, J. C. David, W. B. Hamilton, J. Lebenhaft, MCNPX Extensions Version 2.5.0, LA-UR-04-0570, Los Alamos National Laboratory, (2004).
7. D. Knott, B. Forssen, M. Edenius, CASMO-4, A Fuel Assembly Burnup Program: Methodology, SOA-95/2, Studsvik of America, (1995).
8. J. M. Paratte, K. Foskolos, P. Grimm, J. M. Hollard, ELCOS, The PSI Code System for LWR Core Analysis. Part II: User’s Manual for the Fuel Assembly Code BOXER, PSI Bericht Nr. 96-08, Paul Scherrer Institute, (1996).
9. Studsvik-Scanpower S, Program Manual Rev. 3, Program HELIOS-1.6, Studsvik-Scanpower, (2002).
10. O. P. Joneja, M. Plaschy, F. Jatuff, 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, 701 (2001).
11. F. Tani, F. Jatuff, R. Chawla, “Study of spectral heterogeneities for the interpretation of calculational trends in predicting pin power distribution in a SVEA-96+ BWR assembly,” Ann. Nucl. Energy, 33, 490 (2006).
12. 238U-capture-to-total-fissions in a Westing-house SVEA-96+ assembly,” Submitted to Nucl. Sci. Eng.
13. J. J. Casal, J. Krouthen, M. Albendea, “Reliable tools to model advanced SVEA fuel assemblies,'' Advances in Nuclear Fuel Management III (ANFM 2003), Hilton Head Island, USA, Oct. 5-8, 2003, (2003).