Thorough analyses and resolution of various errors in pin-homogenized multigroup core calculation
Creators
- 1. Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul, 08826 (Korea, Republic of)
Description
Highlights: • The pinwise diffusion solver involves significant error cancellation. • The SP5 is not better than SP3 in the two-step calculation with the SPH factors. • The use of SN for the two-step calculation with the SPH factors is not practical. • The SP3 source expansion nodal method is determined as the optimal solver. • The spectral leakage correction technique is required for further improvement. The errors in pin-homogenized multigroup calculation (PHMGC) from various sources are thoroughly analyzed to find the optimal neutronics solution method. The dependence of the errors due to the use of pin-homogenized multigroup cross sections on the energy groups are investigated first to clarify the need for proper equivalence factor and more groups in pinwise calculation. Various transport approximations including the simplified PN (SPN) and the discrete ordinate method (SN) are then examined with different degrees of spatial discretization. It is demonstrated that the diffusion calculations involve significant error cancellation which would result in seemingly good results. It turns out that SP5 is not any better than SP3 and SN yields intolerable errors due to the inconsistency of single assembly based SPH factors especially noted in the fast energy range. Through the analyses, the source expansion nodal method solver of the SP3 equations is determined as the optimal solver for PHMGCs.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2021.108502Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2021.108502;
- PII
- S0306454921003789;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 163
- Journal Page Range
- vp.
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 53116229
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- CROSS SECTIONS; DIFFUSION; DISCRETE ORDINATE METHOD; ENERGY RANGE; ERRORS; NEUTRON TRANSPORT; RESOLUTION
- Descriptors DEC
- CALCULATION METHODS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT
Optional Information
- Copyright
- Copyright (c) 2021 Elsevier Ltd. All rights reserved.