Published October 2020 | Version v1
Journal article

Development and validation of non LOCA thermal hydraulics and three dimensional neutronics coupling code GINKGO/COCO

  • 1. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an (China)
  • 2. China Nuclear Power Technology Research Institute, Shenzhen (China)

Description

For the needs of more detailed and accurate core modeling and thermal hydraulic analysis, based on the Non LOCA thermal hydraulic analysis code GINKGO developed on self-reliance and three-dimensional core physical code COCO, GINKGO/COCO coupling code has been developed by using Dynamic Link Library (DLL) method. This paper introduces the development principle and implementation of the coupling code, and the international benchmark for main steam line break accident (MSLB) completed by Organization for Economic Co-operation and Development (OECD) is chosen to validate the coupling code. The results show that the calculation results of GINKGO/COCO are in good agreement with the benchmark values. It is indicated that the GINKGO/COCO coupling code is with good computing performance and reliability. (authors)

Additional details

Identifiers

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
41
Journal Issue
5
Journal Page Range
p. 15-19
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
55086478
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
Descriptors DEI
BENCHMARKS; COUPLING; REACTOR PHYSICS; RELIABILITY; THERMAL HYDRAULICS; VERIFICATION
Descriptors DEC
FLUID MECHANICS; HYDRAULICS; MECHANICS; PHYSICS

Optional Information

Notes
7 figs., 1 tab., 9 refs.; http://dx.doi.org/10.13832/j.jnpe.2020.05.0015