<i>k</i><sub>eff</sub> Sensitivity Analysis to Nuclear Data with RMC Code

QIU Yi-shu; YU Jian-kai; LIANG Jin-gang; WANG Kan

doi:10.7538/yzk.2015.49.10.1821

Atomic Energy Science and Technology > 2015 > 49(10): 1821-1827. > DOI: 10.7538/yzk.2015.49.10.1821

QIU Yi-shu, YU Jian-kai, LIANG Jin-gang, WANG Kan. k_eff Sensitivity Analysis to Nuclear Data with RMC Code[J]. Atomic Energy Science and Technology, 2015, 49(10): 1821-1827. DOI: 10.7538/yzk.2015.49.10.1821

Citation:

PDF (674 KB)

k_eff Sensitivity Analysis to Nuclear Data with RMC Code

Department of Engineering Physics, Tsinghua University, Beijing 100084, China

More Information

Graphical Abstract

Abstract

Abstract

Methods suitable for sensitivity analysis in continuous-energy Monte Carlo codes become a research hotspot in the field of reactor physics. In this work, the formulas of sensitivity coefficients of five different reaction types were established. Then, the theoretical basis and the algorithm of the iterated fission probability method which was used widely currently were discussed. Furthermore, two Monte Carlo codes, RMC and MCNP6, were used to compute eigenvalue sensitivity coefficients to nuclear data. The agreement between RMC and MCNP6 is well. The results indicate that RMC is capable to perform sensitivity analysis preliminarily.
- sensitivity analysis,
- iterated fission probability method,
- continuous-energy,
- RMC code

FullText(HTML)

References (16)

References

[1]	ZWERMANN W, GALLNER L, KLEIN M, et al. XSUSA solution for the PWR Pincell burnup benchmark[C]∥Proceedings of the 6th Workshop on OECD Benchmark for Uncertainty Analysis in Best-Estimate Modeling for Design, Operation and Safety Analysis of LWRs (UAM-6). Karlsruhe, Germany: [s. n.], 2012.
[2]	SCALE: A comprehensive modeling and simulation suite for nuclear safety analysis and design, Version 6.1, ORNL/TM2005/39[R]. USA: Oak Ridge National Laboratory, 2011.
[3]	KIEDROWSKI B C, BROWN F B. Comparison of the Monte Carlo adjoint-weighted and differential operator perturbation methods[R]. USA: Los Alamos National Laboratory, 2010.
[4]	NAUCHI Y, KAMEYAMA T. Development of calculation technique for iterated fission probability and reactor kinetic parameters using continuous-energy Monte Carlo method[J]. J Nucl Sci Technol, 2010, 47(11): 977-990.
[5]	REARDEN B T, PERFETTI C M, WILLIAMS M L, et al. SCALE sensitivity calculations using contributon theory[C]∥ Proceedings of Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA+MC2010). Tokyo, Japan: [s. n.], 2010.
[6]	PERFETTI C M, REARDEN B T. Development of a SCALE tool for continuous-energy eigenvalue sensitivity coefficient calculations[C]∥Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA+MC 2013). Paris, France: [s. n.], 2013.
[7]	PERFETTI C M. Advanced Monte Carlo methods for continuous-energy eigenvalue sensitivity coefficient calculation[D]. USA: University of Michigan, 2012.
[8]	KIEDROWSKI B C, BROWN F B, WILSON P P H. Adjoint-weighted tallies for k-eigenvalue calculations with continuous-energy Monte Carlo[J]. Nuclear Science and Engineering, 2011, 168(3): 226-241.
[9]	KIEDROWSKI B C, BROWN F B. Adjoint-based k-eigenvalue sensitivity coefficients to nuclear data using continuous-energy Monte Carlo[J]. Nuclear Science and Engineering, 2012, 174: 227-244.
[10]	SHIM H J, KIM C H. Adjoint sensitivity and uncertainty analyses in Monte Carlo forward calculations[J]. Journal of Nuclear Science and Technology, 2011, 5: 1453-1461.
[11]	KIEDROWSKI B C. MCNP6.1 k-eigenvalue sensitivity capability: A users guide, LA-UR-13-22251[R]. USA: LANL, 2013.
[12]	SHIM H J, HAN B S, JUNG J S, et al. MCCARD: Monte Carlo code for advanced reactor design and analysis[J]. Nuclear Engineering and Technology, 2012, 44(2): 161-176.
[13]	REARDEN B T. Perturbation theory eigenvalue sensitivity analysis with Monte Carlo techniques[J]. Nucl Sci Eng, 2004, 146: 367-382.
[14]	HURWITZ H. Physical interpretation of the adjoint flux: iterated fission probability[M]∥Naval reactor physics handbook, Vol. Ⅰ. RADKOWSKY A. USA: Atomic Energy Commission, 1964: 864-869.
[15]	WANG Kan, LI Zeguang, SHE Ding, et al. RMC: A Monte Carlo code for reactor core analysis[C]∥Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA+MC 2013). Paris, France: [s. n.], 2013.
[16]	DALLE H M. Monte Carlo burnup simulation of the Takahama-3 benchmark experiment[C]∥2009 International Nuclear Atlantic Conference: INAC 2009. Brazil: [s. n.], 2009.

Cited By

Get Citation

PDF

XML

Article views (290) PDF downloads (1144)

Turn off MathJax

Article Contents

Abstract

References

keff Sensitivity Analysis to Nuclear Data with RMC Code

Abstract

References

Catalog

Export File

Citation

Format

Content

k_eff Sensitivity Analysis to Nuclear Data with RMC Code