Published 2021 | Version v1
Miscellaneous

Unsteady RANS analysis of CNL corium convection experiment

  • 1. McMaster University, Hamilton, Ontario (Canada)

Description

In the event of a severe accident, it is essential to maintain radiological material within the calandria vessel. Thermal stresses at the vessel wall have been identified as a dominant failure mechanism. There is therefore a need to analyze the heat transfer processes in the molten corium to determine if the heat removal at the exterior of the vessel wall is sufficient to maintain vessel integrity. The current research uses computational fluid dynamics (CFD) to simulate the natural convection flows and crust formation within the molten corium, including the conjugate heat transfer at the vessel wall. Unsteady Reynolds Averaged Navier-Stokes (RANS) is used to model the effects of turbulence in the fluid. This paper presents the results of a validation study on a 1/5 scale CANDU calandria vessel using molten salts as the corium simulant. Numerical predictions are compared to the experimental results provided by Canadian Nuclear Laboratories (CNL). (author)

Availability note (English)

Available from the Canadian Nuclear Society, Toronto, Ontario (Canada).
Part of:
Enabling net zero carbon emissions through clean nuclear power. 40th annual conference of the Canadian Nuclear Society (virtual) and 45th annual CNS/CNA student conference (virtual)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
Imprint Title
Enabling net zero carbon emissions through clean nuclear power. 40th Annual CNS conference and 45th CNS/CNA student conference (virtual)
Imprint Pagination
vp.
Journal Page Range
[5 p.]
Report number
INIS-CA--0016

Conference

Title
40. Annual Canadian Nuclear Society Conference (Virtual); 45. Annual CNS/CNA Student Conference (Virtual)
Dates
6-9 Jun 2021
Place
Toronto (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
53064605
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; CORIUM; FLUID MECHANICS; NATURAL CONVECTION; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS
Descriptors DEC
ACCIDENTS; CONVECTION; ENERGY TRANSFER; HEAT TRANSFER; HEAVY WATER MODERATED REACTORS; MASS TRANSFER; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS

Optional Information

Notes
14 refs., 4 figs.