Simulation Study of Total Loss of Feedwater in OPR1000 using SPACE
- 1. Korea Hydro and Nuclear Power Central Research Institute, Daejeon (Korea, Republic of)
- 2. System Engineering and Technology Co. Ltd., Daejeon (Korea, Republic of)
Description
Additional failure of the safety components are also considered in terms of sufficient safety margin with application of proper emergency operating procedures. In this paper, we studied about Total Loss of Feedwater (TLOFW) accident which is used to represent an accident involving the failure of cooling by the secondary cooling system. This work is focused on the thermal-hydraulic analysis for TLOFW accident in OPR1000 plant using Safety and Performance Analysis Code for Nuclear Power Plant (SPACE). Based on the thermal hydraulic features, simulation studies can provide physical insight to the system response and confirm the effectiveness of RCS cool down strategy according to the emergency operating guideline. In this study, the TLOFW accident in OPR1000 plant were assessed using SPACE 3.0. Two different cases were simulated to confirm safety criteria. In both cases, it is verified that the core cooling capability is sufficient. In case 2, it is expected that fuel rod is heated up in a short time.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Spring Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [3 p.]
Conference
- Title
- 2018 Spring Meeting of the KNS
- Dates
- 16-18 May 2018
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50059445
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; FAILURES; FEEDWATER; PERFORMANCE; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; S CODES; SAFETY; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs, 9 figs, 2 tabs