Performance Evaluation for Overpressure Transient at Reactor Coolant System of SHINKORI 3/4 NPP by Loss of Turbine Load
Creators
- 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)
Description
Commercial NPP include depressurization-devices such as pressurizer safety valve and main steam safety valve with reactor protection system. In SINKORI 3/4 NPP (SK34), first commercial APR1400-type plant, the depressurization devices have distinguishing features. Fig. 1 shows schematic diagram for pilot operated safety relief valve (POSRV) as pressurizer safety valve of SK34. The valve includes two spring loaded safety valve (pilot valve) to set up the opening/closing pressure of main valve. And main valve operates with delay time after opening/closing of pilot valve. Main steam safety valve (MSSV) of SK34 is so-called IAD-type valve, for which opening set pressure was defined by manufacturer as initial audible discharge whereas previous definition was popping point. In this study, we evaluated the performance of SK34 for overpressure transient with conservative conditions. From calculation results, RCS and SG peak pressure is maintained lower than 110% of design pressure under conservative conditions. Therefore, performance for overpressure protection of RCS in SK34 will be satisfactory. And we also identify significant parameters or factors in overpressure transient analysis with sensitivity study. It was confirmed that loss of offsite power could be effective to overpressure significantly and MSSV and POSRV should also be modelled appropriately in overpressure transient analysis
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2014 Fall Meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2014 Fall Meeting of the KNS
- Dates
- 29-31 Oct 2014
- Place
- Pyongchang (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 46060567
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; DESIGN; PERFORMANCE; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; RELIEF VALVES; SENSITIVITY; TRANSIENTS
- Descriptors DEC
- CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; VALVES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 2 figs, 3 tabs