Sensitivity Studies on uncertainty parameters and code modeling of calandria vessel integrity during late phase CANDU 6 severe accident
Creators
- 1. Power Plant Engineering Faculty, Politehnica University, Bucharest (Romania)
- 2. Institute for Nuclear Research, Mioveni, Pitesti (Romania)
- 3. Politehnica University, Bucharest (Romania)
Description
The present focus on the analysis of the coolability of a calandria vessel starting with a dry debris bed. The calculation are performed with SCDAP/RELAPSIM/MOD3.4 code version and using COUPLE routines modified to properly use the option for a horizontal cylinder. Parametric studies are performed in order to quantify the effect of several identified sources of uncertainty on calandria vessel (CV) failure: metallic fraction of zirconium inside the debris, containment pressure, timing of water depletion inside calandria vessel, Reactor Vault (RV) nodalization and, the gap heat transfer coefficient. The main outcome of the calculations is the identification of possible source of uncertainty and modality to improve the accuracy of results. Also the results obtained confirm the capability of the heat removal from the CV wall by the RV water, as long as the liquid phase is present in the tank
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of ICAPP 2011
- Imprint Pagination
- 2851 p.
- Journal Page Range
- p. 1322-1327
- 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
- 44092933
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; MELTDOWN; PARAMETRIC ANALYSIS; REACTOR ACCIDENT SIMULATION; REACTOR VESSELS; S CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS
Optional Information
- Notes
- 12 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/