Published 2003 | Version v1
Miscellaneous Metadata-only

The simulation of flow-blockage experiment in LMR using MATRA-LMR

Creators

  • 1. Seoul National University, Seoul (Korea, Republic of)
  • 2. KAERI, Taejon (Korea, Republic of)

Description

LMR(Liquid Metal Reactor) core cinsists of highly dense assembly structures because of coolant characteristics. Therefore, in case of local flow blockage in the coolant channels, local flow velocity and rates are reduced remarkably, which may cause fuel cladding melting or fission product release. So, this kind of phenomena should be revealed in the real design procedure. The simulation results of flow blockage experiment using MATRA-LMR which was developed by KAERI were compared with the results of ASFRE-III. As a results, it is shown that the MATRA-LMR predicts the flow and temperature profile reasonably. However, the heat transfer model which can predict the temperature increase in the thick blockage plate are required

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2003 spring meeting of the KNS
Dates
29-30 May 2003
Place
Gyeongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
35063849
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLANTS; FISSION PRODUCT RELEASE; FLOW BLOCKAGE; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; M CODES; REACTOR CORES; VELOCITY
Descriptors DEC
COMPUTER CODES; ENERGY TRANSFER; REACTOR COMPONENTS; REACTORS

Optional Information

Notes
6 refs, 12 figs, 1 tab