You need JavaScript to view this

Preparation and documentation of a CATHENA input file for Darlington NGS

Technical Report:

Abstract

A CATHENA input model has been developed and documented for the heat transport system of the Darlington Nuclear Generating Station. CATHENA, an advanced two-fluid thermalhydraulic computer code, has been designed for analysis of postulated loss-of-coolant accidents (LOCA) and upset conditions in the CANDU system. This report describes the Darlington input model (or idealization), and gives representative results for a simulation of a small break at an inlet header.
Publication Date:
Mar 01, 1989
Product Type:
Technical Report
Report Number:
INFO-0320
Reference Number:
SCA: 210400; PA: AIX-24:007380; SN: 93000932200
Resource Relation:
Other Information: PBD: Mar 1989
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; DARLINGTON-1 REACTOR; PRIMARY COOLANT CIRCUITS; C CODES; HEAT TRANSFER; LOSS OF COOLANT; PIPELINES; RUPTURES; TWO-PHASE FLOW; 210400; POWER REACTORS, NONBREEDING, OTHERWISE MODERATED OR UNMODERATED
OSTI ID:
10119106
Research Organizations:
Atomic Energy Control Board, Ottawa, ON (Canada); Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Nuclear Research Establishment
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE93612450; TRN: CA9200958007380
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
[18] p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

None. Preparation and documentation of a CATHENA input file for Darlington NGS. Canada: N. p., 1989. Web.
None. Preparation and documentation of a CATHENA input file for Darlington NGS. Canada.
None. 1989. "Preparation and documentation of a CATHENA input file for Darlington NGS." Canada.
@misc{etde_10119106,
title = {Preparation and documentation of a CATHENA input file for Darlington NGS}
author = {None}
abstractNote = {A CATHENA input model has been developed and documented for the heat transport system of the Darlington Nuclear Generating Station. CATHENA, an advanced two-fluid thermalhydraulic computer code, has been designed for analysis of postulated loss-of-coolant accidents (LOCA) and upset conditions in the CANDU system. This report describes the Darlington input model (or idealization), and gives representative results for a simulation of a small break at an inlet header.}
place = {Canada}
year = {1989}
month = {Mar}
}