New MHI safety analysis code package for DBA. (5) LOCA analysis code, MCOBRA/RELAP5-GOTHIC
- 1. Mitsubishi Heavy Industries, Ltd., Safeguards System Engineering Section Reactor Core and Safety Engineering Department, Yokohama, Kanagawa (Japan)
Description
With intent to adopt the COBRA-TF, RELAP5 and GOTHIC codes as a set of evaluation codes for licensing analysis of PWR Loss-of-Coolant Accident in compliance with US Regulatory Guide 1.203, 'Transient and Accident Analysis Methods.', MHI investigated the applicability of their models to the regulation, found necessary actions to suit them to the regulation with sufficient conservativeness, and finally developed a code named MCOBRA/RELAP5-GOTHIC by combining the three. Through the code development activities MCR5-G has been confirmed to be applicable to licensing safety analyses for Emergency Core Cooling System performance under any LOCA conditions and also to evaluations of Mass and Energy release and Containment Vessel response. In applying MCR5-G to licensing safety analyses, its best-estimate capability is utilized with a statistical safety analysis methodology for Large Break Loss-of-Coolant Accident, while several optional evaluation models are incorporated in the code such that the code allows conservative deterministic safety analysis for small-break LOCAs, mass and energy release and containment vessel response analyses. This paper describes the applicability of the MCR5-G code and statistical and deterministic methodologies to licensing safety analysis of PWR ECCS performance. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)
- Imprint Pagination
- 2573 p.
- Journal Page Range
- 6 p.
Conference
- Title
- 2017 international congress on advances in nuclear power plants
- Acronym
- ICAPP2017
- Dates
- 24-25 Apr 2017; 26-28 Apr 2017
- Place
- Fukui (Japan); Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49033564
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COUNTER CURRENT; CRITICAL HEAT FLUX; DESIGN-BASIS ACCIDENTS; ECCS; HEAT TRANSFER; LOSS OF COOLANT; M CODES; NEUTRON REFLECTORS; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; SAFETY ANALYSIS; STEAM GENERATORS; VOIDS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT FLUX; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format. Folder Name: pdf; Paper ID: 17596.pdf; 9 refs., 1 fig., 1 tab.