Published 2015 | Version v1
Miscellaneous

Sensitivity study of break opening characteristics for large LOCA using CATHENA

  • 1. Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

Description

A study was performed using a CATHENA based generic model of a CANDU6 reactor to demonstrate the sensitivity of system response to single and two-stage break opening characteristics following a Reactor Inlet Header Large Break LOCA. Figures of merit for the analysis were the power pulse amplitude and the 5 second integrated normalized power. The analysis demonstrates in a qualitative manner a threshold time for 'instantaneous' break opening, and a threshold initial break size above which shutdown system trip times remain unchanged. The analysis also attempts to establish the relative impacts of initial and second stage opening times on figures of merit. (author)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-20-9
Imprint Title
Seventh International conference on modelling and simulation in nuclear science and engineering
Imprint Pagination
48.3 Megabytes
Journal Page Range
[13 p.]

Conference

Title
7. International Conference on Modelling and Simulation in Nuclear Science and Engineering
Dates
18-21 Oct 2015
Place
Ottawa, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
49003497
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Quality check status
Yes
Descriptors DEI
ATWS; CANDU TYPE REACTORS; LOSS OF COOLANT; REACTOR ACCIDENT SIMULATION; SCRAM;
Descriptors DEC
ACCIDENTS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; SIMULATION; THERMAL REACTORS;

Optional Information

Lead record
2bb5w-zd889
Notes
Paper 7ICMSNSE-69. 2 refs., 6 tabs., 14 figs.