Published 2010 | Version v1
Miscellaneous Metadata-only

Modelling a RD-14M LOCA experiment with the TRACE thermal-hydraulics code

Creators

  • 1. McMaster Univ., Dept. of Engineering Physics, Hamilton, Ontario (Canada)

Description

RD-14M Test B9401, simulating a critical break loss-of-coolant accident in a CANDU primary heat transport system, is of note for serving as benchmark data for an IAEA code validation exercise. It has thus been modeled with the TRACE code to study the code's applicability towards modeling CANDU. TRACE reproduces the transient with fidelity comparable to other codes in the IAEA exercise, however predicts some phenomena with less accuracy than codes developed specifically for modeling CANDU-typical thermal-hydraulics. This was found to be due to limitations in TRACE's ability to account for some horizontal stratification effects common in CANDU accident analysis. (author)

Part of:
Atoms for Power, Health and the Environment. 31st annual conference of the Canadian Nuclear Society and 34th annual conference of the Canadian Nuclear Society and Canadian Nuclear Association

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-01-8
Imprint Title
Atoms for Power, Health and the Environment. 31st annual conference of the Canadian Nuclear Society and 34th annual conference of the Canadian Nuclear Society and Canadian Nuclear Association
Imprint Pagination
111 Megabytes
Journal Page Range
[12 p.]

Conference

Title
31. Annual Conference of the CNS; 34. Annual Student Conference of the CNS and CNA
Dates
24-27 May 2010
Place
Montreal, Quebec (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
44059003
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS

Optional Information

Notes
7 refs., 10 figs.