Published 2011 | Version v1
Miscellaneous

A computational study on instrumentation guide tube failure during a severe accident in boiling water reactors

  • 1. Royal Inst. of Techn. (KTH), Div. of Nuclear Power Safety, Stockholm (Sweden)
  • 2. Inst. of Energy, Dong Da, Hanoi (Viet Nam)

Description

This paper focuses on the nature and timing of Instrumentation Guide Tube (IGT) failure in case of severe core melt accident in a Nordic type Boiling Water Reactor (BWR). First, a 2D structural analysis of a RPV lower head is performed to determine global vessel deformation, timing and mode of failure. Next, a structural analysis is also performed on a 3D IGT section taking into account the influence of global vessel deformation and thermo-mechanical load from the melt pool. We have found that the IG tube was not clamped in the housing at the time when welding ring of the IGT nozzle has been melted and global failure of the vessel wall has not started yet. This suggests that IGT failure is the dominant failure mode in the considered case of a large (~200 tons) melt pool. (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
[14 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
47071101
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; FAILURE MODE ANALYSIS; GUIDE TUBES; MELTDOWN; REACTOR ACCIDENT SIMULATION; REACTOR COMPONENTS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Paper NURETH14-627, 20 refs., 1 tab., 15 figs.