Published 2011 | Version v1
Miscellaneous Metadata-only

Prevention and investigations of core degradation in case of beyond design accidents of the 2400 MWTH gas-cooled fast reactor

Creators

  • 1. CEA, DEN, DER, SESI, Cadarache, Saint Paul Lez Durance (France)
  • 2. CEA, DEN, DER, SSTH, Grenoble (France)
  • 3. CEA, DEN, DPC, SCP, Saclay, Gif Sur Yvette (France)

Description

The present paper deals with studies carried out to assess the ability of the core of the Gas Fast Reactor (GFR) to withstand beyond design accidents. The work presented here is aimed at simulating the behaviour of this core by using analytical models whose input parameters are calculated with the CATHARE2 code. Among possible severe accident initiators, the Unprotected Loss Of Coolant Accident (ULOCA of 3 Inches diameter) is investigated in detail in the paper with CATHARE2. Additionally, a simplified pessimistic assessment of the effect of a postulated power excursion that could result from the failure of prevention provisions is presented. (author)

Part of:
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-05-6
Imprint Title
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
Imprint Pagination
766 Megabytes
Journal Page Range
[16 p.]

Conference

Title
14. International Topical Meeting on Nuclear Reactor Thermalhydraulics
Acronym
NURETH-14
Dates
25-30 Sep 2011
Place
Toronto, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
47071173
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ANALYTICAL SOLUTION; GAS COOLED REACTORS; LOSS OF COOLANT; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS; REACTOR CORES
Descriptors DEC
ACCIDENTS; MATHEMATICAL SOLUTIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION

Optional Information

Notes
Paper NURETH14-037, 15 refs., 2 tabs., 12 figs.