Published May 2001 | Version v1
Miscellaneous

Evaluation of dropped rod accident after elimination of NFRT and correction of hot channel factor reduction rate

  • 1. KEPCO Nuclear Fuel Co., Ltd., Taejon (Korea, Republic of)
  • 2. Korea Power Engineering Company Inc., Seoul (Korea, Republic of)

Description

In recent years, NFRT(Negative Flux Rate Trip) is eliminated in order to prevent the reactor trip during dropped rod accident in domestic Westinghouse type plants. The theoretical background of dropped rod accident is introduced and the correlations related FΔH are verified for KORI unit 1 which is 2-loop plant. The results show that the default line of Hot Channel Factor Reduction Rate(HCFRR) for low level leakage loading pattern isn't conservative. So, new correlation is generated and applied to the analysis of the dropped rod accident. The minimum pre-drop FΔH is decreased about 2.6% because of NFRT elimination and new HCFRR correlation. According to the sensitivity study on compensation for the reduction, the Rod Insertion Limit(RIL) is shifted 14 steps upward. So, the minimum pre-drop FΔH is increased about 2.5%. The effect of RIL change on plant operation is additionally evaluated

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[ONE CDROM]
Journal Page Range
[9 p.]

Conference

Title
2001 spring meeting of the Korean Nuclear Society
Dates
24-25 May 2001
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33040253
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
FUEL RODS; HOT CHANNEL FACTOR; KORI-1 REACTOR; LEAKS; RISK ASSESSMENT; ROD DROP ACCIDENTS; WESTINGHOUSE STANDARD REACTOR
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTIVITY INSERTIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs, 6 figs, 3 tabs