Published May 2009 | Version v1
Miscellaneous

A Benchmark CFD Calculation for a Cross Flow between Fuel Blocks of a Prismatic VHTR

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

Description

The computational fluid dynamics (CFD) technology has been successfully applied to many industrial engineering areas such as aircraft and vehicles. However, it is generally accepted that the CFD codes, even if they are commercial ones, require more sufficient validations to apply to the analysis and design of a very high temperature reactor (VHTR). One of the interesting phenomena of a prismatic VHTR is a cross flow between fuel blocks of a prismatic reactor. The CFD simulation of the phenomena is complex since laminar to turbulent transitions occur around the cross flow gap. It is considered that any turbulence model has not been generally accepted yet for laminar to turbulent transitions and their mixture flows. In this work, a CFD benchmark calculation has been made against the JAEA experiment to investigate the applicability of the existing CFD technology to a cross flow phenomena in fuel blocks of a VHTR

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2009 spring meeting of the KNS
Dates
18-23 May 2009
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40099356
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BENCHMARKS; C CODES; TURBULENCE; VALIDATION; VHTR REACTOR
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; TESTING; THERMAL REACTORS

Optional Information

Notes
3 refs, 4 figs, 1 tab