Published September 2007 | Version v1
Journal article

Coupled fluid/structure analyses of the MEGAPIE spallation source target during transients

  • 1. Thermal-Hydraulics Laboratory, Nuclear Energy and Safety Department, Paul Scherrer Institut, CH-5232 Villigen PSI (Switzerland)
  • 2. Spallation Neutron Source Division, Paul Scherrer Institute, CH-5232 Villigen PSI (Switzerland)
  • 3. UTS Tecnologie Fisiche Avanzate, Sezione Metodologie e Diagnostiche, ENEA, Bologna (Italy)

Description

The paper describes some R and D activities undertaken in support of the design and safe operation of MEGAPIE (MEGAwatt PIlot Experiment) spallation source target, which is scheduled to be irradiated by a proton beam in the SINQ facility at the Paul Scherrer Institute in 2006. The target material is lead bismuth eutectic (LBE), which also acts as the primary coolant. As a consequence of the spallation reactions, about 600 kW of heat would be deposited in the target during operation, and considerable R and D effort is being expended to demonstrate continuing coolability and structural integrity under a variety of operational and abnormal conditions. The paper gives three examples of transient analyses carried out as part of the safety assessment of the target: (1) a beamline trip and recovery; (2) failure of the primary electro-magnetic pump (EMP); (3) failure of the secondary EMP (used to cool the base of the target). The study involves the simultaneous application of a system-analysis code, in our case a version of RELAP5, a computational fluid dynamics (CFD) tool (CFX-4), and a structural analysis code (ABAQUS). The RELAP5 code is used to provide transient boundary conditions for a localized conjugate heat transfer analysis of the lower target region, undertaken using CFD, and includes the feed-back effects arising from the secondary cooling and control systems. A conjugate heat transfer problem is then solved using CFD, which provides time-dependent thermal and flow data within the LBE, together with the thermal and mechanical loads to the target structures. Finally, an in-house interface program is employed to transfer mesh geometry, model topology and (time-dependent) thermal/mechanical data to enable stress analysis of the principal lower-target structural components to be performed. It is demonstrated that none of the transients considered result in critical stress conditions occurring in the target components, but that further operation is not recommended unless both pumps are fully operational

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2007.02.020;
PII
S0029-5493(07)00224-5;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
237
Journal Issue
15-17
Journal Page Range
p. 1656-1667
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
11. international topical meeting on nuclear reactor thermal hydraulics
Acronym
NURETH-11
Dates
2-6 Oct 2005
Place
Avignon (France)

INIS

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.