Published May 2001
| Version v1
Miscellaneous
Safety evaluation on RCS flow asymmetry for WH type NPPs
Description
A safety evaluation was performed for RCS flow asymmetry for Kori units 1/2/3/4 and Yonggwang units 1/2. The amount of RCS flow asymmetry is based on the design uncertainties and the margin of steam generator tube plugging limit. RCP locked rotor event, steam line break event and feedline break event were reanalyzed and the other design basis events in the current FSAR were evaluated. As a result, RCS flow asymmetry affects RCP locked rotor event considerably. The increase of peak RCS pressure during the RCP locked rotor event is about 30 psi and 20 psi for 2-LOOP plants and 3-LOOP plants, respectively. However, all the safety analysis criteria can be met for RCS flow asymmetry phenomena
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
- [13 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
- 33040455
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ASYMMETRY; EVALUATION; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; SAFETY ANALYSIS; STEAM GENERATORS; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- BOILERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs, 7 figs