Flowrate reduction analysis of residual heat removal system during midloop operation for Kori Units 1 and 2
- 1. KOPEC, Taejon (Korea, Republic of)
Description
A flowrate reduction analysis of Residual Heat Removal System (RHRS) has been performed to increase operational margin during Mid-loop operation for KORI units 1 and 2. The reactor coolant level should be reduced below top of the hot leg for Steam Generator (S/G) nozzle dam installation/removal to reduce maintenance interval. The decay heat generated during this operation is removed by RHRS, and this special operating mode is called Mid-loop operation. Through the performance analysis to investigate a minimum RHRS flowrate for decay heat removal and reliable RHRS operation, the flowrate can decrease to 1410 gpm(Kori 1 and ) 1420 gpm(Kori 2), respectively. The analysis results can be used for the revisions of Technical Specification and operation procedure
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
- [14 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
- 33065437
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT; AFTER-HEAT REMOVAL; COOLANTS; FLOW RATE; KORI-1 REACTOR; KORI-2 REACTOR; NOZZLES; OPERATION; REDUCTION; STEAM GENERATORS
- Descriptors DEC
- BOILERS; CHEMICAL REACTIONS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; REMOVAL; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs, 13 figs