Published 1996 | Version v1
Miscellaneous Metadata-only

The thermal-hydraulic effects of thimble plug removal for Westinghouse type PWR plants

Creators

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

Description

The thermal-hydraulic effects of removing the RCC guide thimble plugs are evaluated for Westinghouse type PWR plants as a part of feasibility study: core outlet loss coefficient, thimble bypass flow, and best estimate flow. It is resulted that the best estimate thimble bypass flow increases about by 2% and the best estimate flow increases approximately by 1.2%. The resulting DNBR penalties can be covered within the current DNBR margin. Accident analyses are also investigated and the dropped rod transient is shown to be limiting and relatively sensitive to bypass flow variation

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
3566 p.
Journal Page Range
p. 1166-1172

Conference

Title
1996 spring meeting of the KNS
Dates
31 May - 1 Jun 1996
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
37120256
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BYPASSES; FEASIBILITY STUDIES; REMOVAL; SENSITIVITY; THERMAL HYDRAULICS; TRANSIENTS; WESTINGHOUSE STANDARD REACTOR
Descriptors DEC
ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
9 refs, 2 figs, 5 tabs