Published 2016 | Version v1
Miscellaneous

A cross-platform multi-physics reactor transient simulation framework through a SALOME-Backbone joint platform

  • 1. Canadian Nuclear Labs., Chalk River, ON (Canada)
  • 2. Univ. of Toronto, Toronto, ON (Canada)

Description

Predicting nuclear reactor behaviour during transient conditions can be enhanced through numerical multi-physics simulation framework involving neutron transport, thermal hydraulics, and fuel behaviour codes to improve nuclear reactor safety analysis. Two tools are used in this work to accomplish the coupling of these codes. One is SALOME, an open source software that provides a generic platform for Pre- and Post-Processing of numerical simulations. Another one is Backbone, developed at the Canadian Nuclear Laboratories, which has the capability of coupling multi-physics codes under different operating systems. Also, Backbone is capable of synchronizing various scientific codes through a Time Step Controller (TSC), which permits appropriate and efficient data exchange at the time-step level. This paper studies a SALOME-Backbone joint platform for code coupling with comparisons made to a Large Break Loss of Coolant Accident (LB-LOCA) experiment performed in a five channel per pass configuration at the CNL Whiteshell RD-14M facility. (author)

Part of:
CANDU fuel : evolution towards optimal performance. 13th international conference on CANDU fuel

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-24-7
Imprint Title
CANDU fuel : evolution towards optimal performance. 13th international conference on CANDU fuel
Imprint Pagination
66.6 Megabytes
Journal Page Range
[14 p.]

Conference

Title
13. International conference on CANDU fuel
Dates
15-18 Aug 2016
Place
Kingston, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
50005396
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CODES; LBLOCA; NEUTRON TRANSPORT; REACTOR ACCIDENT SIMULATION; SAFETY ANALYSIS; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; FLUID MECHANICS; HYDRAULICS; LOSS OF COOLANT; MECHANICS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTOR ACCIDENTS; SIMULATION

Optional Information

Notes
16 refs., 1 tab., 6 figs.