Published 2006 | Version v1
Miscellaneous Metadata-only

GOTHIC-IST model of ISP-47 phase B MISTRA experiment

Creators

  • 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

Description

International Standard Problem 47 examined the ability of computer codes to predict local gas distributions during experiments simulating Loss of Coolant Accidents with Loss of Emergency Core Coolant (LOCA/LOECC) or Pressurized Water Reactor severe accident scenarios that involve hydrogen release to containment. It involved three experimental test facilities (TOSQAN, MISTRA and ThAI) located in France and Germany. This report documents AECL's GOTHIC-IST 6.1bp2 model of Phase B of the MISTRA experiment with steam condensation in an air-helium atmosphere. The GOTHIC-IST model used to model the TOSQAN test (open simulation) was scaled up to model the MISTRA test (blind simulation). The GOTHIC-IST results are in good agreement with the MISTRA results, except for some anomalies in the experimental results. (author)

Part of:
Nuclear energy: a world of service to humanity. 27th annual conference of the Canadian Nuclear Society and 30th Canadian Nuclear Society/Canadian Nuclear Association student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-86-0
Imprint Title
Nuclear energy: a world of service to humanity. 27th annual conference of the Canadian Nuclear Society and 30th Canadian Nuclear Society/Canadian Nuclear Association student conference
Imprint Pagination
233 Megabytes
Journal Page Range
[14 p.]

Conference

Title
27. Annual conference of the Canadian Nuclear Society and 30. Canadian Nuclear Society/Canadian Nuclear Association student conference
Dates
11-14 Jun 2006
Place
Toronto, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
38050895
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ATOMIC ENERGY OF CANADA LTD; HYDROGEN; LICENSING; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR ACCIDENTS; SAFETY ANALYSIS; SIMULATION
Descriptors DEC
ACCIDENTS; CANADIAN ORGANIZATIONS; ELEMENTS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs., 2 tabs., 10 figs.