Effect of CASMO-5 Cross-Section Data and Doppler ... - Studsvik

Gerardo Grandi et.al.Further investigation of the CASMO-5 cross-section effects shall be performed using realistic UO 2 /MOXcore designs in which the core state depends on the cross-section data set. Also, the CASMO-5 crosssectioneffects will be conducted for two other S3K mainstream applications, namely: BWR stability andfast operational transients.REFERENCES1. J. Borkowski, J. Rhodes, P. Esser, K. Smith, “Three Dimensional Transient Capability inSIMULATE-3,” Trans. Am. Nucl. Soc., 71, 456, (1994).2. G. Grandi and K. Smith, “SIMULATE-3K Explicit Fuel Pin Modelling in RIAs,” Trans. Am. Nucl.Soc., 96, 627, (2007).3. J. L. Eller, “Application of SIMULATE-3K To PWR Reactivity Insertion Accident,” Advances inNuclear Fuel Management (ANFM 2009), Hilton Head Island, South Carolina, April 12-15, on CD-ROM, (2009).4. H. Ferroukhi, M.A. Zimmermann, “Study of the PWR REA Pulse Width for Realistic UO2 and MOXCore Designs using 3-D Kinetics,” Annals of Nuclear Energy, 36, pp.274-280 (2009).5. K. Smith and J. Rhodes, “CASMO-4 Characteristic Methods for Two Dimensional PWR and BWRCore Calculations,” Trans. Am. Nucl. Soc., 83, 322, (2000).6. J. Rhodes, K. Smith and D. Lee, “CASMO-5 Development and Applications,” Advances in NuclearAnalysis and Simulation (PHYSOR 2006), Vancouver, BC, Canada, September 10-14, (2006).7. D. Lee, K. Smith and J. Rhodes, “The Impact of 238 U Resonance Elastic Scattering Approximationson Thermal Reactor Doppler Reactivity,” Annals of Nuclear Energy, 36, pp.274-280 (2009).8. D. Lee, J. Rhodes, K.Smith, “Quadratic Depletion Model for Gadolinium Isotopes in CASMO-5,”Advances in Nuclear Fuel Management IV (ANFM 2009), South Carolina, April 12-15, on CD-ROM,(2009).9. A. Yamamoto, M. Tabuchi, N. Sugimura, T. Ushio And M. Mori, “Derivation of Optimum PolarAngle Quadrature Set for the Method of Characteristics Based on Approximation Error for theBickley Function,” J. Nucl. Sci. Technol., 44, pp. 129-136 (2007).10. B. Becker, R. Dagan, and G. Lohnert, “Proof and Implementation of the Stochastic Formula for IdealGas, Energy Dependent Scattering Kernel,” Annals of Nuclear Energy, 36, pp.1170-1183 (2009).11. Y. Danon, E. Liu, D. Barry, and T. Ro, “Benchmark Experiment of Neutron Resonance ScatteringModels In Monte Carlo Codes,” International Conference on Mathematics, Computational Methodsand Reactor Physics (M&C 2009), Saratoga Springs, New York, May 3-7, on CD-ROM, (2009).12. T. Kozlowski, T. J. Downar, “The PWR MOX/UO2 Core Transient Benchmark, Final Report”,NEA/NSC/DOC(2006)20.13. A. O. Goltsev et al, “The Influence of a Non-Uniform Radial Temperature Distribution in the Fuel onthe Results of Calculations of Transients,” Annals of Nuclear Energy, 30, pp.1135-1153 (2003).14. D.D. Lanning, et al., “FRAPCON-3 Updates,” NUREG/CR-6534, Vol. 4, PNL-11513, (2005).15. G. Grandi and D. Hagrman, “Improvements to the INTERPIN Code for High Burnup and MOXFuel,” Trans. Am. Nucl. Soc., 96, 614-615, (2007).16. G. Grandi, “Effect of the Discretization and Neutronic Thermal Hydraulic Coupling on LWRTransients,” Proceedings of the 13 th International Topical Meeting on Nuclear Reactor ThermalHydraulics (NURETH-13), Kanazawa, Ishikawa-Ken, Japan, September 27-October 2, on CD-ROM,(2009).PHYSOR 2010 – Advances in Reactor Physics to Power the Nuclear RenaissancePittsburgh, Pennsylvania, USA, May 9-14, 201012/13