Published 2011 | Version v1
Miscellaneous

Sensitivity Studies on uncertainty parameters and code modeling of calandria vessel integrity during late phase CANDU 6 severe accident

  • 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

Part of:
Proceedings of ICAPP 2011

Additional details

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/