Stabilization of multi-group neutron transport with transport-corrected cross-sections

被引:7
|
作者
Gunow, Geoffrey [1 ]
Forget, Benoit [2 ]
Smith, Kord [2 ]
机构
[1] Bloomberg LP, 731 Lexington Ave, New York, NY 10022 USA
[2] MIT, Dept Nucl Sci & Engn, 77 Massachusetts Ave,Bldg 24, Cambridge, MA 02139 USA
关键词
Transport correction; Convergence; Neutron transport; Method of characteristics; ANISOTROPIC SCATTERING;
D O I
10.1016/j.anucene.2018.10.036
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
Many deterministic neutron transport solvers rely on the source iteration method to solve the multi-group neutron transport equation. Often, these solvers rely on transport corrected cross-sections for accurate prediction of the neutron flux distribution. Transport corrected within-group scattering cross sections can become negative, and if these negative cross-sections are large in magnitude, source iteration can become unstable and fail to converge for certain cases. In this study, we present evidence of this convergence issue for the method of characteristics (MOC) on full-core PWR problems with common transport correction schemes. A theoretical discussion is presented to illustrate the reason for the convergence issues. Previously established stabilization methods are compared with a newly proposed stabilization method. Results show that the new stabilization method allows for faster convergence than previous techniques. In addition, the effect of Coarse Mesh Finite Difference (CMFD) acceleration on stability is analyzed, showing that CMFD acceleration with full-group structure can overcome the convergence issues, but a stabilization technique is necessary for convergence when a condensed group structure is used. (C) 2018 Published by Elsevier Ltd.
引用
收藏
页码:211 / 219
页数:9
相关论文
共 50 条
  • [21] Transport-corrected diffusion theory for image reconstruction in optical tomography
    Panasyuk, GY
    Markel, VA
    Schotland, JC
    OPTICAL TOMOGRAPHY AND SPECTROSCOPY OF TISSUE VI, 2005, 5693 : 1 - 3
  • [22] MULTI-GROUP TRANSPORT-THEORY WITH ANISOTROPIC SCATTERING
    GARCIA, RDM
    SIEWERT, CE
    JOURNAL OF COMPUTATIONAL PHYSICS, 1982, 46 (02) : 237 - 270
  • [23] NEW SCATTERING CROSS-SECTIONS FOR ELECTRON-TRANSPORT
    HAGGMARK, LG
    MACCALLUM, CJ
    RILEY, ME
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1974, 19 (OCT27): : 471 - 471
  • [24] COLLISION CROSS-SECTIONS AND TRANSPORT PARAMETERS IN NEON AND XENON
    PUECH, V
    MIZZI, S
    JOURNAL OF PHYSICS D-APPLIED PHYSICS, 1991, 24 (11) : 1974 - 1985
  • [25] Development and verification of neutron and photon multi-group cross sections processing code TXMAT2.0
    Zhang, Bin
    Ma, Xubo
    Hu, Kui
    Zhou, Feng
    Chang, Changcheng
    Chen, Yixue
    PROGRESS IN NUCLEAR ENERGY, 2021, 138
  • [26] CROSS-SECTIONS AND TRANSPORT NUMBERS OF LI+-CO
    GRICE, ST
    HARLAND, PW
    MACLAGAN, RGAR
    JOURNAL OF CHEMICAL PHYSICS, 1993, 99 (10): : 7631 - 7637
  • [27] A METHOD OF CALCULATING CRITICAL SIZE IN MULTI-GROUP NEUTRON TRANSPORT THEORY FOR SOME SIMPLE SYSTEMS
    WOODCOCK, ER
    PROCEEDINGS OF THE PHYSICAL SOCIETY OF LONDON SECTION A, 1953, 66 (404): : 705 - 709
  • [28] A parallel unified gas kinetic scheme for three-dimensional multi-group neutron transport
    Tan Shuang
    Sun Wenjun
    Wei Junxia
    Ni Guoxi
    JOURNAL OF COMPUTATIONAL PHYSICS, 2019, 391 : 37 - 58
  • [29] Monte Carlo Source Convergence Acceleration by Hybrid Multi-group and Continuous Energy Neutron Transport
    Raffuzzi, Valeria
    Shwageraus, Eugene
    Morgan, Lee
    Cosgrove, Paul
    NUCLEAR SCIENCE AND ENGINEERING, 2023, 197 (03) : 364 - 380
  • [30] On multi-group neutron transport in planar one dimensional geometry: A solution for a localized pulsed source
    Fernandes, J. C. L.
    Bodmann, B. E. J.
    Vilhena, M. T.
    ANNALS OF NUCLEAR ENERGY, 2017, 101 : 552 - 558