SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations

被引:54
|
作者
Perfetti, Christopher M. [1 ]
Rearden, Bradley T. [1 ]
Martin, William R. [2 ]
机构
[1] Oak Ridge Natl Lab, POB 2008,MS 6170, Oak Ridge, TN 37831 USA
[2] Univ Michigan, Dept Nucl Engn & Radiol Sci, 2355 Bonisteel Blvd, Ann Arbor, MI 48109 USA
关键词
SCALE; TSUNAMI; eigenvalue sensitivity coefficients; MONTE-CARLO METHOD;
D O I
10.13182/NSE15-12
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The need to model geometrically complex systems with improved ease of use and fidelity and the desire to extend the Tools for Sensitivity and UNcertainty Analysis Methodology Implementation (TSUNAMI) analysis to advanced applications have motivated the development of a methodology for calculating sensitivity coefficients in continuous-energy (CE) Monte Carlo applications. The Contributon-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance CHaracterization (CLUTCH) and Iterated Fission Probability (IFP) eigenvalue sensitivity methods were recently implemented in the CE KENO framework of the SCALE code system to enable TSUNAMI-3D to perform eigenvalue sensitivity calculations using CE Monte Carlo methods. This paper provides a detailed description of the theory behind the CLUTCH method and describes in detail its implementation. This work also explores the improvements in eigenvalue sensitivity coefficient accuracy that can be gained through use of CE sensitivity methods and compares several sensitivity methods in terms of computational efficiency and memory requirements. The IFP and CLUTCH methods produced sensitivity coefficient estimates that matched, and in some cases exceeded, the accuracy of those produced using the multigroup TSUNAMI-3D approach. The CLUTCH method was found to calculate sensitivity coefficients with the highest degree of efficiency and the lowest computational memory footprint for the problems examined.
引用
收藏
页码:332 / 353
页数:22
相关论文
共 50 条
  • [31] Optimizations of the energy grid search algorithm in continuous-energy Monte Carlo particle transport codes
    Walsh, Jonathan A.
    Romano, Paul K.
    Forget, Benoit
    Smith, Kord S.
    COMPUTER PHYSICS COMMUNICATIONS, 2015, 196 : 134 - 142
  • [32] Continuous-energy Monte Carlo neutron transport on GPUs in the Shift code
    Hamilton, Steven P.
    Evans, Thomas M.
    ANNALS OF NUCLEAR ENERGY, 2019, 128 : 236 - 247
  • [33] A truncated RQ iteration for large scale eigenvalue calculations
    Sorensen, DC
    Yang, C
    SIAM JOURNAL ON MATRIX ANALYSIS AND APPLICATIONS, 1998, 19 (04) : 1045 - 1073
  • [34] WEAK SOLUTIONS OF TIME-DEPENDENT CONTINUOUS-ENERGY EQUATION OF NEUTRON DIFFUSION
    CANNON, JR
    NELSON, P
    SIAM JOURNAL ON MATHEMATICAL ANALYSIS, 1977, 8 (01) : 155 - 165
  • [35] Explicit Treatment of Thermal Motion in Continuous-Energy Monte Carlo Tracking Routines
    Viitanen, Tuomas
    Leppanen, Jaakko
    NUCLEAR SCIENCE AND ENGINEERING, 2012, 171 (02) : 165 - 173
  • [36] Application of wavelets scaling function expansion to continuous-energy neutron transport calculation
    Yang, Wei-Yan
    Wu, Hong-Chun
    Cao, Liang-Zhi
    Zheng, You-Qi
    Hedongli Gongcheng/Nuclear Power Engineering, 2009, 30 (SUPPL. 1): : 18 - 22
  • [37] TIME-DEPENDENT CONTINUOUS-ENERGY NEUTRON-TRANSPORT IN SPHERICAL GEOMETRY
    ROYBAL, JA
    GANAPOL, BD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 34 (JUN): : 283 - 284
  • [38] RECONSTRUCTION OF THE TIME-DEPENDENT CONTINUOUS-ENERGY NEUTRON-FLUX IN AN INFINITE MEDIUM
    GANAPOL, BD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 49 (JUN): : 221 - 223
  • [39] PREPARATION OF DATA LIBRARIES FOR EFFICIENT RETRIEVAL BY CONTINUOUS-ENERGY MONTE-CARLO CODES
    WEISBIN, CR
    HARRIS, DR
    BATTAT, ME
    LABAUVE, RJ
    TAYLOR, WM
    TURNER, GD
    SEAMON, RE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1972, 15 (01): : 572 - &
  • [40] Measurement of continuous-energy neutron-incident neutron-production cross section
    Shigyo, N
    Kunieda, S
    Watanabe, T
    Noda, S
    Ishibashi, K
    Iwamoto, Y
    Satoh, D
    Nakamura, T
    Haight, RC
    INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, PTS 1 AND 2, 2005, 769 : 924 - 927