Approach to Phebus containment nodalization for lumped-parameter codes
Creators
- 1. Lithuanian Energy Institute, Breslaujos g.3, LT-44403 (Lithuania)
Description
Containment of the Nuclear Power Plant is the last barrier preventing the release of radioactive fission products to the environment in case of an accident. Therefore investigation of the fission product transport and deposition processes is a very important task. Phebus test facility and the performed fission product program provides the most extensive experimental results on severe accident phenomena in a Light Water Reactor, starting from the nuclear fuel bundle degradation, continuing to radioactive material transport through the reactor cooling circuit and release to containment and ending with fission product deposition in containment. In order to understand and explain the obtained experimental results different computer codes are used. Though the Computational Fluid Dynamics (CFD) codes are already well advanced the lumped-parameter codes remain the main tool for safety assessment of NPPs and validation of these codes is an important task. The lumped-parameter codes have certain limitations that require a special attention while performing safety analyses of the nuclear power plants. A special attention has to be paid to development of the containment nodalization to be used for analysis. This nodalization has to provide possibilities to take into account the phenomena that are expected in the course of the accident progression. This paper presents analysis of aerosol deposition and distribution processes in PHEBUS containment using lumped-parameter code COCOSYS. For the analysis two models of 19 and 16 nodes were developed. The calculated thermal-hydraulic parameters are in good agreement with the measured results. The correct simulation of thermal-hydraulic phenomena is a precondition for simulation of transport and deposition of the materials released from the degrading core. Analysis of aerosol deposition showed, that the calculated deposition velocity is in good agreement with measured. Different ways of nodalization give different flow paths inside the containment and lead to different aerosol deposition distribution. In both cases deposition on the containment walls is significantly smaller than measured. Further investigation of diffusive deposition model is needed. (authors)
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of ICAPP 2011
- Imprint Pagination
- 2851 p.
- Journal Page Range
- p. 1200-1208
- Report number
- INIS-FR--13-0283
Conference
- Title
- The Power of Innovation
- Acronym
- ICAPP 2011 - Performance and Flexibility
- Dates
- 2-5 May 2011
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 44092920
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; CONTAINMENT; FISSION PRODUCT RELEASE; IN PILE LOOPS; MESH GENERATION; OPTIMIZATION; REACTOR SAFETY EXPERIMENTS; SPATIAL DISTRIBUTION; TEMPERATURE DISTRIBUTION; TRANSIENTS; VALIDATION
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; SIMULATION; TESTING
Optional Information
- Notes
- 8 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/