Published November 2019 | Version v1
Journal article

Development of the neutronics transport code based on the MOC method and adjoint-forward Coarse Mesh Finite Difference technique: PerMOC code for lattice and whole core calculations

  • 1. Department of Nuclear Engineering, School of Mechanical Eng., Shiraz University, 71936-16548 Shiraz (Iran, Islamic Republic of)
  • 2. Ionizing and Non-Ionizing Research Center, Shiraz University of Medical Science, Shiraz (Iran, Islamic Republic of)
  • 3. Radiation Research Center, Shiraz University, Shiraz (Iran, Islamic Republic of)

Description

Highlights: • The Method of Characteristics is applied as a new transport code called PerMOC. • Both forward and adjoint CMFD acceleration techniques are applied to the MOC kernel. • A newly proposed adjoint solver reduces about 30% the number of transport sweeps. • More speed-ups are achieved using a parallel transport sweeping in the MOC kernel. • The calculated reactivity of 2D C5G7 benchmark has only 51pcm error with the reference. - Abstract: In this research, the Coarse Mesh Finite Difference (CMFD) acceleration technique in both adjoint and forward mode is applied to the MOC kernel, to develop a new code called PerMOC. A new approach in the adjoint MOC kernel which is called thermal-up-scattering-like iteration scheme reduces the total number of adjoint iteration sweeps. In additions, more speed-up is achieved using a parallel transport sweeping in MOC kernel. Validation test for PerMOC C-Sharp code is carried out for four distinct criticality benchmarks in which C5G7 is one of those. In the case of C5G7 benchmark, the best-calculated multiplication factor has 51 pcm differences with the reference case. Furthermore, the newly proposed adjoint solver reduces about 30% the number of adjoint transport sweeps in comparison with the normal adjoint solver. The present article describes the PerMOC methodologies and illustrates its ability to model large problems with acceptable accuracy.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2019.04.050

Additional details

Identifiers

DOI
10.1016/j.anucene.2019.04.050;
PII
S0306454919302336;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
133
Journal Page Range
p. 84-95
ISSN
0306-4549
CODEN
ANENDJ

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51007842
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BENCHMARKS; CRITICALITY; FINITE DIFFERENCE METHOD; MATHEMATICAL MODELS; MULTIPLICATION FACTORS; REACTIVITY; TRANSPORT THEORY; VALIDATION
Descriptors DEC
CALCULATION METHODS; DIMENSIONLESS NUMBERS; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; TESTING

Optional Information

Notes
© 2019 Elsevier Ltd. All rights reserved.