Published May 2011 | Version v1
Miscellaneous

Design and Construction of 3-Ch Cross Flow Test Facility

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

Description

To evaluate the reactor thermal margin of APR+, reactor core flow distribution including both axial and lateral directional hydraulic resistances of fuel assemblies should be known. Test facility on reactor core flow distribution (ACOP) is being designed and constructed. ACOP will use 257 core simulators and each core simulator should have the same core flow characteristics of the PLUS-7 fuel assembly. However, data on the lateral directional hydraulic resistance of full-size fuel assemblies is rare while data on the axial resistance is currently available. To design a core simulator which will be used at the ACOP test facility, a 3-Ch cross flow test facility is being designed and constructed with three full-size fuel assemblies. The axial and lateral directional hydraulic resistances of fuel assemblies will be measured. The test results will be applied to the design of the core simulator of the ACOP. The experimental data can also be utilized for the sub-channel analysis by upgrading the CFD model

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
2011 spring meeting of the KNS
Dates
26-27 May 2011
Place
Taebaek (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
42099154
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
DESIGN; EXPERIMENTAL DATA; FUEL ASSEMBLIES; PWR TYPE REACTORS; REACTOR CORES; TEST FACILITIES
Descriptors DEC
DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs, 3 figs