Comparison of SMART-SDA and SMART-PSS Behaviors Using an SBLOCA Scenario
Creators
- 1. System Engineering and Technology Co., Ltd., Daejeon (Korea, Republic of)
- 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
In this study, an analysis of an SBLOCA scenario of safety injection line break accident was performed using the MARS-KS code to understand the general behavior between the SMART-SDA and the SMART-PSS design. An SBLOCA for the safety injection line break has been analyzed using the MARS-KS code to compare the thermal-hydraulic behaviors between the SMARTSDA and SMART-PSS. The present comparison analysis provides good insight into the passive safety system design features of the SMART-PSS and the thermal-hydraulics characteristic of the SMART design. It was found that the SMART-PSS has sufficient emergency core cooling capability during the transient period. Further study will be focused on the transient time. It should be able to compute the problem during 72 hours without AC power or operator action after an accident. SMART has been developed by KAERI, and SMART-Standard Design Approval (SDA) was recently granted in 2012. A SMART-Passive Safety System (PSS) is being developed by KAERI to improve the safety system. Active safety systems such as safety injection pumps will be replaced by a passive safety system, which is actuated only by the gravity force caused by the height difference. All tanks for the passive safety systems are higher than the injection nozzle, which is located around the reactor coolant pumps (RCPs)
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS Fall meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2013 Fall meeting of the KNS
- Dates
- 23-25 Oct 2013
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 45082332
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DESIGN; ENGINEERED SAFETY SYSTEMS; LOSS OF COOLANT; PUMPS; PWR TYPE REACTORS; TANKS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs, 4 figs, 1 tab