Coupled fluid/structure analyses of the MEGAPIE spallation source target during transients
Creators
- 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
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38090096
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BISMUTH; COMPUTERIZED SIMULATION; CONTROL SYSTEMS; COOLING; DESIGN; FAILURES; FLUID MECHANICS; HEAT TRANSFER; LEAD; OPERATION; PRIMARY COOLANT CIRCUITS; PROTON BEAMS; PUMPS; RISK ASSESSMENT; SPALLATION; STRESS ANALYSIS; SYSTEMS ANALYSIS; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- BEAMS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; EQUIPMENT; MECHANICS; METALS; NUCLEAR REACTIONS; NUCLEON BEAMS; PARTICLE BEAMS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; SIMULATION
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.