Published 2005 | Version v1
Miscellaneous

LBLOCA Analyses for 4.5% Power Uprating using KREM

  • 1. Korea Nuclear Fuel Co., Ltd., Taejon (Korea, Republic of)

Description

KREM is a best-estimate LBLOCA (Large Break Loss-Of-Coolant Accident) evaluation model, which was developed to comply with Regulatory Guide 1.157, 10 CFR 50.46 and their equivalents in Korea. A licensing LBLOCA analysis using KREM was performed for the first time to assess the ECCS (Emergency Core Cooling System) performance of Kori-3/4 and Yonggwang-1/2 under the condition of power uprating by 4.5%. A break spectrum analysis for 100%, 80%, and 60% DECLG (Double Ended Cold Leg Guillotine) breaks was performed and eighty SRS (Simple Random Sampling) calculations were conducted on the limiting break size. Another analysis with the same procedure was done for the current operating conditions to evaluate the effect of 4.5% power uprating including 1.5% TDF (Thermal Design Flow) reduction on LBLOCA consequences

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
37072190
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING SYSTEMS; DESIGN; LOSS OF COOLANT; PERFORMANCE; PWR TYPE REACTORS
Descriptors DEC
ACCIDENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 ref, 2 figs, 1 tab