Published April 2018
| Version v1
Journal article
Study on Coupling of Integral Severe Accident Analysis Code with System Code
- 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
Description
The integral severe accident analysis code and RELAP5 were directly coupled for improving the overall safety analysis of the containment and primary system. Two kinds of coupling were implemented, i.e. breaks on the pressure boundary between the primary system and containment, interfaces between the safety injection systems and primary system. The feasibility of this coupling methodology and the applicability of the coupling code were verified through the calculation of a numerical case Marviken CFT 24 in which a pressurized vessel inflow to the containment reactor cavity. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 39
- Journal Issue
- 2
- Journal Page Range
- p. 157-161
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 54087351
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- CONTAINERS; CONTAINMENT; COUPLING; INTEGRALS; INTERFACES; M CODES; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; R CODES; SAFETY ANALYSIS; SAFETY INJECTION; SEVERE ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 figs., 9 refs.; http://dx.doi.org/10.13832/j.jnpe.2018.02.0157