Published 2014 | Version v1
Miscellaneous

Validation of MCCI models implemented in ASTEC MEDICIS on OECD CCI-2 and CCI-3 experiments and further consideration on reactor cases

  • 1. Ruhr-Universitat Bochum, Energy Systems and Energy Economics, Reactor Simulation and Safety Group, Bochum (Germany)

Description

Within a severe accident in a light water reactor a loss of coolant can result in core melting and vessel failure. Afterwards, molten core material may discharge into the containment cavity and interact with the concrete basemat. Due to concrete erosion gases are released, which lead to exothermic oxidation reactions with the metals in the corium and to formation of combustible mixtures. In this work the MEDICIS module of the Accident Source Term Evaluation Code (ASTEC) is validated on experiments of the OECD CCI programme. The primary focus is set on the CCI-2 experiment with limestone common sand (LCS) concrete, in which nearly homogenous erosion appeared, and the CCI-3 experiment with siliceous concrete, in which increased lateral erosion occurred. These experiments enable the analysis of heat transfer depending on the axial and radial orientation from the interior of the melt to the surrounding surfaces and the impact of top flooding. For the simulation of both tests, two existing models in MEDICIS are used and analysed. Results of simulations show a good agreement of ablation behaviour, layer temperature and energy balance with experimental results. Furthermore the issue of a quasi-steady state in the energy balance for the long term appeared. Finally the basic data are scaled up to a generic reactor scenario, which shows that this quasi-steady state similarly occurred. (author)

Part of:
PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-16-2
Imprint Title
PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
Imprint Pagination
270 Megabytes
Journal Page Range
[13 p.]

Conference

Title
19. Pacific Basin Nuclear Conference; 38. Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
Dates
24-28 Aug 2014
Place
Vancouver, British Columbia (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
49016224
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature, Numerical Data
Descriptors DEI
COMPUTER CODES; CONCRETES; EXPERIMENTAL DATA; LOSS OF COOLANT; MELTDOWN; REACTOR ACCIDENTS; REACTOR CORES
Descriptors DEC
ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BUILDING MATERIALS; DATA; INFORMATION; MATERIALS; NUMERICAL DATA; REACTOR ACCIDENTS; REACTOR COMPONENTS; SEVERE ACCIDENTS

Optional Information

Notes
Paper PBNC2014-051. 10 refs., 4 tabs., 18 figs.