Published May 2018 | Version v1
Miscellaneous

Verification of GAMMA+ for Multi-Dimensional Heat Transfer in a Prismatic Core

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

The recent research for the GAMMA+ development is focusing on the verification and validation study. In 2016, an official report on the verification and validation of GAMMA+ for conceptual problems was issued. The conceptual problems consist of fluid flow problems, heat conduction problems, thermo-fluid conjugated problems, and thermo-fluid transient problems. The verification and validation of GAMMA+ for integrated problems are under progress. One of main concerns of the present work is to verify the application of hybrid grids (i.e, mixture of hexagonal, triangular and cylindrical grids) for a prismatic core. A commercial computational fluid dynamics code (CFD) has been used to verify the results of the GAMMA+ code. In this work, in order to verify the GAMMA+ capability for multi-dimensional heat transfer in a prismatic core, a simplified benchmark was proposed and the GAMMA+ and CFX calculations were conducted. The results of the calculation show that the data calculated by GAMMA+ agree well with the data obtained by CFX. It is concluded, therefore, that the GAMMA+ code can reliably simulate multi-dimensional heat transfer in a prismatic core.

Part of:
Proceedings of the KNS 2018 Spring Meeting

Additional details

Identifiers

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2018 Spring Meeting
Imprint Pagination
vp.
Journal Page Range
[3 p.]

Conference

Title
2018 Spring Meeting of the KNS
Dates
16-18 May 2018
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
50059163
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; DESIGN; FLUID MECHANICS; G CODES; HEAT TRANSFER; HTGR TYPE REACTORS; KAERI; TRANSIENTS; VALIDATION; VERIFICATION
Descriptors DEC
COMPUTER CODES; ENERGY TRANSFER; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; KOREAN ORGANIZATIONS; MECHANICS; NATIONAL ORGANIZATIONS; REACTORS; SIMULATION; TESTING

Optional Information

Notes
4 refs, 6 figs, 3 tabs