Published 2005 | Version v1
Miscellaneous Metadata-only

Review of Thermal-Chemical Experiments for a CANDU Fuel Channel

Creators

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

Description

During a postulated Loss-of-Coolant Accident (LOCA) without Emergency Core Cooling System (ECCS), it is important to through understand high temperature fuel channel behavior and to know the effectiveness of the moderator as a heat sink to demonstrate the safety of CANDU reactors. For this purpose, the CHAN thermal Chemical Experimental Program has been performed at Whiteshell Laboratories in Canada since 1981. It consists of several series of experiments: a single fuel element simulator (FES), 7-element, and 28-element tests. This paper reviews the experimental results from two single-element tests, six 7-element tests, and three 28-element tests. The information on these experiments is reviewed and summarized. The test data has been collected from the published references and will be used to validate 3-dimensional Computational Fluid Dynamic (CFD) code model of a 37-element CANDU6 fuel channel

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

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

Conference

Title
2005 autumn meeting of the KNS
Dates
27-28 Oct 2005
Place
Busan (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
37072145
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
C CODES; CANDU TYPE REACTORS; ECCS; FUEL CHANNELS; FUEL ELEMENTS; LOSS OF COOLANT
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENGINEERED SAFETY SYSTEMS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS

Optional Information

Notes
4 refs, 5 figs, 2 tabs