Published 2006 | Version v1
Miscellaneous

Power-to-Energy Scaling Methodology in the SNUF for DVI line Break SBLOCA Using the MARS Code

  • 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

Part of:
Proceedings of the KNS autumn meeting

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