Published 2021 | Version v1
Book

Robust relaxation-free multiphysics simulation via power-iteration-level-coupled CMFD acceleration in MPACT

  • 1. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Blvd, Ann Arbor, MI 48109 (United States)

Description

This paper describes a new multiphysics iteration scheme for coarse mesh finite difference (CMFD) accelerated transport problems where the multiphysics feedback is coupled with the low-order diffusion equation at the power iteration level. The power-iteration-level- coupled CMFD (X-CMFD) is demonstrated to improve the stability of the CMFD-accelerated transport schemes involving feedback. The X-CMFD method is described and optimized for implementation in the neutron transport code MPACT based on the existing CMFD solvers. The numerical results show that the performance of the X-CMFD method is consistent regardless of the presence or type of feedback. (authors)

Availability note (English)

Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)
Part of:
Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering - M and C 2021

Additional details

Publishing Information

Publisher
ANS - American Nuclear Society
Imprint Place
La Grange Park (United States)
Imprint Title
Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering - M and C 2021
Imprint Pagination
2418 p.
Journal Page Range
p. 2080-2089

Conference

Title
International conference on mathematics and computational methods applied to nuclear science and engineering
Acronym
M and C 2021
Dates
3-7 Oct 2021
Place
Raleigh, NC (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
54119349
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; DIFFUSION EQUATIONS; NEUTRON TRANSPORT; PERFORMANCE
Descriptors DEC
DIFFERENTIAL EQUATIONS; EQUATIONS; NEUTRAL-PARTICLE TRANSPORT; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION TRANSPORT; SIMULATION

Optional Information

Notes
20 refs.; Virtual meeting