Published May 1998 | Version v1
Miscellaneous Metadata-only

Fuel channel analysis for 35% RIH break in CANDU reactor loaded with CANFLEX-RU fuel bundles

Creators

  • 1. KAERI, Taejon (Korea, Republic of)

Description

A preliminary fuel channel analysis for 35% reactor inlet header (RIH) break in CANDU reactor loaded with the CANFLEX-RU fuel bundles has been performed. The predicted results are compared with those for the reactor compared with those for the reactor loaded with standard 37-element bundles. The maximum fuel centerline and sheath temperatures for the CANFLEX-RU bundle channel were lower by 338 and 122 degree C, respectively, than those for the standard bundle because of the lower maximum linear power of the CANFLEX-RU bundle in spite of the 0.4 FPS higher power pulse of the CANFLEX-RU case. Fuel integrity margin to fuel breakup for the CANFLEX-RU bundle is about 50 J/g higher than that for the standard bundle. The PT/CT contact for the CANFLEX-RU bundle occurred 2 s later than that for the standard bundle. The PT/CT contact temperature for the CANFLEX-RU bundle was 2 degree C lower than that for the standard bundle. These provide the CANFLEX-RU bundle with the negligibly enhanced safety margin for the fuel channel integrity in CANDU 6 reactor, compared with the standard bundle

Part of:
Proceedings of the Korean Nuclear Society spring meeting Vol. 1

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting Vol. 1
Imprint Pagination
905 p.
Journal Page Range
p. 719-724

Conference

Title
1998 spring meeting of the Korean Nuclear Society
Dates
29-30 May 1998
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33056779
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BURNUP; CANDU TYPE REACTORS; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; FUEL ELEMENTS; FUEL INTEGRITY; POWER DISTRIBUTION; TRANSIENTS
Descriptors DEC
FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS

Optional Information

Notes
3 refs, 2 figs, 4 tabs