Coupled hydrodynamic-structural analysis of an integral flowing sodium test loop in the treat reactor
Creators
- 1. Argonne National Lab., IL (USA). Reactor Analysis and Safety Div.
Description
A hydrodynamic-structural response analysis of the Mark-IICB loop was performed for the TREAT (Transient Reactor Test Facility) test AX-1. Test AX-1 is intended to provide information concerning the potential for a vapor explosion in an advanced-fueled LMFBR. The test will be conducted in TREAT with unirradiated uranium-carbide fuel pins in the Mark-IICB integral flowing sodium loop. Our analysis addressed the ability of the experimental hardware to maintain its containment integrity during the reference accident postulated for the test. Based on a thermal-hydraulics analysis and assumptions for fuel-coolant interaction in the test section, a pressure pulse of 144 MPa maximum pressure and pulse width of 1.32 ms has been calculated as the reference accident. The response of the test loop to the pressure transient was obtained with the ICEPEL and STRAW codes. Modelling of the test section was completed with STRAW and the remainder of the loop was modelled by ICEPEL. The ICEPEL representation of the Mark-IICB integral loop included two-dimensional, axi-symmetric, hydrodynamic models for individual pipes and components coupled together to treat the structural response of the loop to the pressure transient originating in the test section. All pipes and components (excluding elbows) were modelled with deformable walls. A burst disc was included in the model at the lower bend of the loop with a rupture pressure threshold of 34.5 MPa. Analyses were performed to investigate the system behavior with and without the pressure of this component. (orig.)
Additional details
Publishing Information
- Publisher
- North-Holland Publishing Co.
- Imprint Place
- Amsterdam, Netherlands
- ISBN
- 0444 85361 8
- Imprint Title
- Structural mechanics in reactor technology. Transactions. Vol. E
- Journal Page Range
- p. E3/4 (1-8).
Conference
- Title
- 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2).
- Dates
- 9 - 21 Aug 1979.
- Place
- Berlin, Germany, F.R.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 12589189
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HYDRODYNAMICS; LIQUID FLOW; MECHANICAL STRUCTURES; SODIUM; TRANSIENTS; TREAT REACTOR
- Descriptors DEC
- AIR COOLED REACTORS; ALKALI METALS; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUID FLOW; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; MECHANICS; METALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; THERMAL REACTORS
Optional Information
- Secondary number(s)
- INKA-Conf--79-321-160.