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Title: Thermal-hydraulic interfacing code modules for CANDU reactors

Abstract

The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis.

Authors:
; ;  [1]
  1. Ontario Hydro Nuclear, Toronto (Canada); and others
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; Nuclear Energy Agency, 75 - Paris (France); SCIENTECH, Inc., Boise, ID (United States)
OSTI Identifier:
544402
Report Number(s):
NUREG/CP-0159; NEA/CSNI/R-(97)4; CONF-961192-
ON: TI97008508; TRN: 98:000240
Resource Type:
Conference
Resource Relation:
Conference: Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements, Annapolis, MD (United States), 5-8 Nov 1996; Other Information: PBD: Jul 1997; Related Information: Is Part Of Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements; Ebert, D.; PB: 824 p.
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; CANDU TYPE REACTORS; HYDRAULICS; SAFETY ANALYSIS; COMPUTER CODES; MODIFICATIONS; COMPUTERIZED SIMULATION

Citation Formats

Liu, W S, Gold, M, and Sills, H. Thermal-hydraulic interfacing code modules for CANDU reactors. United States: N. p., 1997. Web.
Liu, W S, Gold, M, & Sills, H. Thermal-hydraulic interfacing code modules for CANDU reactors. United States.
Liu, W S, Gold, M, and Sills, H. Tue . "Thermal-hydraulic interfacing code modules for CANDU reactors". United States. https://www.osti.gov/servlets/purl/544402.
@article{osti_544402,
title = {Thermal-hydraulic interfacing code modules for CANDU reactors},
author = {Liu, W S and Gold, M and Sills, H},
abstractNote = {The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis.},
doi = {},
url = {https://www.osti.gov/biblio/544402}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1997},
month = {7}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

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