Published August 2012 | Version v1
Journal article

Preliminary safety analysis of ex-vessel LOCA for the European HCPB TBM system

  • 1. Karlsruhe Institute of Technology (KIT), P.O. Box 3640, D-76021 Karlsruhe (Germany)
  • 2. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 (United States)

Description

Highlights: ► Development of a methodology combining different codes for an accident analysis. ► Ex-vessel LOCA is considered as one of the most critical accident for the HCPB TBM. ► Investigation of the accident sequence and some interesting results are presented. ► In particular, beryllium–steam reaction has been modeled using MELCOR code. - Abstract: Ex-vessel loss of coolant accident caused by a double-ended pipe break of the helium coolant system inside port cell is considered as one of the most critical accident for the European Helium Cooled Pebble Beds Test Blanket Module (HCPB TBM) system. The resulting rapid helium blow-down causes an immediate block of the TBM cooling, which requires a prompt plasma shutdown. Even after the plasma shutdown the temperature can increase over the design limit and the accident sequence can lead up to a break of the TBM box protection after the failure of different protection systems. Thus air ingresses in the vacuum vessel from the damaged TBM system and steam from the surrounding ITER blanket and divertor structures. The evaluation of this sequence is very important for the definition of the correct protection strategy of the system. To consider all these different events a methodology has been developed in KIT combining different codes for a complete analysis of the accident. In particular, this paper shows an application of MELCOR code to model beryllium–steam reaction in a particular accidental sequence for the long term cooling.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2011.12.007

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2011.12.007;
PII
S0920-3796(11)00638-7;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
87
Journal Issue
5-6
Journal Page Range
p. 454-460
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
10. international symposium on fusion nuclear technology
Acronym
ISFNT-10
Dates
11-16 Sep 2011
Place
Portland, OR (United States)

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.