Published December 2021 | Version v1
Journal article

Thorough analyses and resolution of various errors in pin-homogenized multigroup core calculation

  • 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.2021.108502

Additional 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.