Analysis of RCS injection strategy with RNS on severe accident mitigation
Creators
- 1. School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai (China)
Description
According to the severe accident management guidelines (SAMG), the active non-safety systems can be considered for severe accidents mitigation for 1000MWe advanced passive pressurized water reactor (PWR). The normal residual heat removal system (RNS) which is a non-safety system can be adopted to implement the reactor coolant system (RCS) injection strategy during severe accidents. Hence its effectiveness needs to be evaluated. Two typical severe accident sequences: the typical low-pressure core melt accident induced by Large-break Loss of Coolant Accident with double-ended guillotine break in the cold leg (LLOCA) and typical high-pressure core melt accident induced by Loss of Feed Water (LOFW) are selected and analyzed with an integral severe accident analysis code. The mitigation effect and negative impact of the RNS injection strategy are both evaluated. The result shows that RNS injection can effectively terminate core melt progression and keep long-term core cooling in these two typical severe accident sequences. However, more hydrogen will be generated during the reflooding which may lead to hydrogen hazard in the containment. The RCS needs to be depressurized for RNS injection. Therefore, for LOFW two RCS depressurizing strategies are discussed: opening the automatic depressurization system (ADS) stage 1-3 and opening the ADS stage 4. The result indicates that opening ADS stage 1-3 valves can cause rapidly increase of the hydrogen concentration in the in-containment refueling water storage tank (IRWST) compartment and lead to hydrogen denotation if hydrogen igniters unavailable. However, hydrogen can be well dispersed in the loop compartment with intentional open of ADS stage 4 valves. Therefore, suggestions are made: opening ADS stage 4 should be preferred for RCS depressurization before implementing RNS injection strategy. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)
- Imprint Pagination
- 2846 p.
- Journal Page Range
- 10 p.
Conference
- Title
- 10. international topical meeting on nuclear thermal hydraulics, operation and safety
- Acronym
- NUTHOS-10
- Dates
- 14-18 Dec 2014
- Place
- Ginowan, Okinawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47077894
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLANT LOOPS; DEPRESSURIZATION SYSTEMS; FEEDWATER; HYDROGEN; INJECTION; IN-VESSEL HEAT EXCHANGERS; LOSS OF COOLANT; LOSS OF FLOW; MELTDOWN; MITIGATION; PRESSURE DROP; PWR TYPE REACTORS; REACTOR CORES; REACTOR VESSELS; RHR SYSTEMS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT EXCHANGERS; HYDROGEN COMPOUNDS; INTAKE; NONMETALS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format. Paper ID: NUTHOS10-1135.pdf; 11 refs., 15 figs., 3 tabs.