Power-to-Energy Scaling Methodology in the SNUF for DVI line Break SBLOCA Using the MARS Code
Creators
- 1. Seoul National University, Seoul (Korea, Republic of)
Description
APR1400 (Advanced Power Reactor 1400MWe) adopted the DVI (Direct Vessel Injection) system as the advanced feature of ECCS (Emergency Core Cooling System). It requires the safety analysis for the DVI line break SBLOCA and the conventional analysis model should be estimated or revised for application of the accident. The integral test loop, SNUF (Seoul National University Facility) is utilized for this study. It has been constructed to be scaled down to 1/6.4 in length and 1/178 in area from APR1400. And it is RHRP (Reduced-Height and Reduced-Pressure) system. Therefore, an appropriate scaling methodology in the RHRP facility is indispensable to observe the key thermal-hydraulic transient phenomena. Thus the major task of this paper is to propose a suitable scaling method in the SNUF for DVI link break SBLOCA using the best-estimate safety analysis code, MARS
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2006 autumn meeting of the KNS
- Dates
- 2-3 Nov 2006
- Place
- Kyongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 38049342
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ECCS; LOSS OF COOLANT; M CODES; PWR TYPE REACTORS; SAFETY ANALYSIS; SAFETY INJECTION; SCALING; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs, 4 figs