Thermal-hydraulic and structural safety analysis of SLSF P3 experiment
Creators
- 1. Argonne National Lab., IL (USA). Reactor Analysis and Safety Div.
- 2. Notre Dame Univ., IN (USA). Dept. of Aerospace and Mechanical Engineering
Description
The Sodium Loop Safety Facility (SLSF) P3 experiment was the fourth in a series of in-reactor tests in the Engineering Test Reactor and simulated an unprotected flow coastdown in a 37 pin bundle. A comprehensive thermal-hydraulic analysis of the SLSF loop was coupled with a structural analysis of the test section hexcan outer duct in order to provide assurance, before the transient, that the loop would safely contain the P3 experiment. This analysis was performed for both the expected transient and for an off-normal condition of failure of redundant logic circuits to provide the proper pump power demand signal. Results of the analysis showed the hexcan outer duct to safely contain the P3 experiment for both conditions. The analysis for the expected transient has been verified by the successful completion of the P3 experiment. (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. E3/5 (1-6).
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
- 12589128
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HYDRAULICS; LMFBR TYPE REACTORS; REACTOR SAFETY; SODIUM; THERMAL ANALYSIS
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; METALS; REACTORS; SAFETY
Optional Information
- Secondary number(s)
- INKA-Conf--79-321-161.