Published 2015 | Version v1
Miscellaneous Metadata-only

Development of a graphical animation interactive feature to assess MAAP-CANDU simulation results

Creators

  • 1. Canadian Nuclear Laboratories, Chalk River, ON (Canada)
  • 2. Fauske and Associates Inc. (FAI), Burr Ridge, IL (United States)
  • 3. Fauske and Associates Inc., Burr Ridge, IL (United States)
  • 4. Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

Description

MAAP-CANDU is an integrated severe accident analysis code for CANDU plant simulations that necessitates the assessment and post-processing of extensive amounts of information obtained from code run results. The MAAP-CANDU GRaphical Animation Package Extension (GRAPE) is a flexible, efficient, interactive and integrated visualization tool for analyzing plant behaviour during postulated accidents including accident management actions for single and multi-unit CANDU plants. GRAPE was developed by FAI in consultation with CNL (AECL) and CNSC from the FAI MAAP-GRAAPH code used in MAAP (LWR version). CNSC plans to use MAAP-CANDU and GRAPE as one of the tools in their Emergency Operations Centre.(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
[17 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
49003499
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Quality check status
Yes
Descriptors DEI
ACCIDENT MANAGEMENT; CANDU TYPE REACTORS; DATA VISUALIZATION; NUCLEAR POWER PLANTS; REACTOR ACCIDENT SIMULATION;
Descriptors DEC
DATA ANALYSIS; DATA PROCESSING; HEAVY WATER MODERATED REACTORS; MANAGEMENT; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; PROCESSING; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS;

Optional Information

Lead record
2bb5w-zd889
Notes
Paper 7ICMSNSE-091. 2 refs., 9 figs.