A simple novel analysis procedure for IVR calculation in core-molten severe accident
Creators
- 1. Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an City 710049 (China)
Description
In-Vessel Retention (IVR) of core melt is a key severe accident management strategy adopted by operating nuclear power plants and advanced light water reactors (ALWRs), AP600, AP1000, etc. External Reactor Vessel Cooling (ERVC), which involves flooding the reactor cavity to submerge the reactor vessel in an attempt to cool core debris relocated to the vessel low head, is a novel severe accident management for IVR analysis. In present study, IVR analysis code in severe accident (IVRASA) has been proposed to evaluate the safety margin of IVR in AP600 with anticipative depressurization and reactor cavity flooding in severe accident. For, IVRASA, a simple novel analysis procedure has been developed for modeling the steady-state endpoint of core melt configurations. Furthermore, IVRASA was developed in a more general fashion so that it is applicable to compute various molten configurations such as UCSB Final Bounding State (FIBS). The results by IVRASA were consistent with those of the UCSB and INEEL. Benchmark calculations of UCSB-assumed FIBS indicate the applicability and accuracy of IVRASA and it could be applied to predict the thermal response of various molten configurations.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.03.055Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.03.055;
- PII
- S0029-5493(11)00324-4;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 241
- Journal Issue
- 12
- Journal Page Range
- p. 4634-4642
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 18. international conference on nuclear engineering
- Acronym
- ICONE-18
- Dates
- 17-21 May 2010
- Place
- Xi'an (China)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43074027
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; ACCURACY; BENCHMARKS; CAVITIES; COMPUTERIZED SIMULATION; COOLING; DEPRESSURIZATION; MELTDOWN; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR VESSELS; RETENTION; SAFETY MARGINS; STEADY-STATE CONDITIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; MANAGEMENT; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.