Published 2005 | Version v1
Miscellaneous Metadata-only

Modeling and preliminary thermal analysis of the capsule for a creep test in HANARO

Creators

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

Description

A creep capsule is a device to investigate the creep characteristics of nuclear materials during inpile irradiation tests. To obtain the design data of the capsule through a preliminary thermal analysis, a 2-dimensional model for the cross section of the capsule including the specimens and components is generated, and an analysis using the ANSYS program is performed. The gamma-heating rates of the materials for the HANARO power of 30MW are considered, and the effect of the gap size and the control rod position on the temperature of the specimen is discussed. From the analysis it is found that the gap between the thermal media and the external tube has a significant effect on the temperature of the specimen. The temperature by increasing the position of the control rod is decreased

Part of:
Proceedings of international symposium on research reactor and neutron science

Additional details

Publishing Information

Publisher
KAERI
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of international symposium on research reactor and neutron science
Imprint Pagination
922 p.
Journal Page Range
p. 275-278

Conference

Title
International symposium on research reactor and neutron science
Dates
11-13 Apr 2005
Place
Taejon (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
37008083
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CAPSULES; CONTROL ELEMENTS; CREEP; CROSS SECTIONS; DESIGN; HANARO REACTOR; IN PILE LOOPS; REACTOR CONTROL SYSTEMS; TEMPERATURE DISTRIBUTION; THERMAL ANALYSIS; TUBES
Descriptors DEC
CONTAINERS; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST FACILITIES; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 4 figs, 1 tab