Neutron transport problems with nonlinear temperature feedback
Creators
- 1. The Ohio State University, 201 West 19. Avenue, Columbus, OH 43210 (United States)
Description
We investigate k-eigenvalue neutron transport problems with the effect of nonlinear temperature feedback based on a homogenous model problem. Cross sections are assumed to be linearly dependent on temperature, which is calculated by a heat transfer equation considering both convection and conduction. The effect of thermal expansion on cross sections is considered. The coupled system is solved using the standard method of power (or source) iteration. The spectral radius of the linearized system is obtained using Fourier analysis, and stability conditions in terms of physical parameters are given. Numerical results based on typical physical parameters for PWRs and fast reactors are presented to verify the theoretical result. The main novelty of the work is that the theoretical result is an explicit function of physical parameters such as the temperature coefficients of cross sections, the effects of heat convection and conduction, and thermal expansion. Although the result is obtained based on the oversimplified problems, it can offer insights into how the physical parameters would affect the convergence and stability of the coupled multiphysics system, and it can also be useful for code validation
Availability note (English)
Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)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. 1342-1351
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
- 54094374
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONVECTION; CROSS SECTIONS; EIGENVALUES; FAST REACTORS; FOURIER ANALYSIS; HEAT; NEUTRON TRANSPORT; PWR TYPE REACTORS; TEMPERATURE COEFFICIENT; THERMAL EXPANSION
- Descriptors DEC
- ENERGY; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPANSION; HEAT TRANSFER; MASS TRANSFER; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; RADIATION TRANSPORT; REACTIVITY COEFFICIENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 15 refs.; Virtual meeting