Published October 2001 | Version v1
Miscellaneous

Small break LOCA analysis for RCP trip strategy of Ulchin 1 and 2 emergency operating procedure

  • 1. KOPEC, Taejon (Korea, Republic of)
  • 2. KEPRI, Taejon (Korea, Republic of)

Description

A series of quantitative analyses were performed for Ulchin 1 and 2 small break loss-of-coolant accident to support technically the validity of Reactor Coolant Pump (RCP) trip criteria presented in the Emergency Operating Guideline (EOP). Based on the analyses results, the effect of RCP trip timing on the core uncovery and the margin for operator action time was evaluated. Limiting break location and size were found to be hot leg break and 3 inch in effective diameter. In addition, it was concluded that appropriate RCP trip timing is 20 minutes after the RCP trip condition is reached

Part of:
Proceedings of the Korean Nuclear Society autumn meeting

Additional details

Publishing Information

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

Conference

Title
2001 autumn meeting of the Korean Nuclear Society
Dates
24-26 Oct 2001
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33065492
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
LOSS OF COOLANT; PUMPS; REACTOR COOLING SYSTEMS; SIZE; ULCHIN-1 REACTOR; ULCHIN-2 REACTOR
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 15 figs, 1 tab