Thermal and stress analyses of meltdown cups for LMFBR safety experiments using SLSF in-reactor loops
- 1. Argonne National Lab., IL (USA)
- 2. Notre Dame Univ., IN (USA)
Description
The test trains for the Sodium Loop Safety Facility (SLSF) in-reactor experiments, which simulate hypothetical LMFBR accidents, have a meltdown cup to protect the primary containment from the effects of molten materials. Thermal and stress analyses were performed on the cup which is designed to contain 3.6 kg of molten fuel and 2.4 kg of molten steel. Thermal analyses were performed with the Argonne-modified version fo the general heat transfer code THTB, based on the instantaneous addition of 3200 0K molten fuel with a decay heat of 9 W/gm and 1920 0K molten steel. These analyses have shown that the cup will adequately cool the molten materials. The stress analysis showed that the Inconel vessel would not fail from the pressure loading, it was also shown that brittle fracture of the tungsten liner from thermal gradients is unlikely. Therefore, the melt-down cup meets the structural design requirements. (Auth.)
Additional details
Publishing Information
- Publisher
- North-Holland.
- Imprint Place
- Amsterdam, Netherlands
- ISBN
- 0 444 85062 7
- Imprint Title
- Structural mechanics in reactor technology
- Journal Page Range
- v. E p. E4/4 1-11.
Conference
- Title
- 4. international conference on structural mechanics in reactor technology.
- Dates
- 15 - 19 Aug 1977.
- Place
- San Francisco, USA.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 10430785
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT; HEAT TRANSFER; IN PILE LOOPS; INCONEL 625; LMFBR TYPE REACTORS; MELTDOWN; STRESS ANALYSIS; T CODES; THERMAL ANALYSIS; TUNGSTEN; VERY HIGH TEMPERATURE
- Descriptors DEC
- ACCIDENTS; ALLOYS; BREEDER REACTORS; CHROMIUM ALLOYS; COMPUTER CODES; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; INCONEL ALLOYS; IRON ALLOYS; LIQUID METAL COOLED REACTORS; METALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ALLOYS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTORS; TANTALUM ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS