Published September 1978
| Version v1
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Simulation experiments for a large leak sodium-water reaction analysis. Volume 4. IHTS/relief system simulation tests
Description
Tests were performed in which a simplified 1/8-scale model of the intermediate heat transfer system and relief system of a LMFBR was subjected to a simulated sodium-water reaction in a steam generator. Pressures in the intermediate heat exchanger (IHX) and in the pipe were measured. The flow of water through the relief system was photographed and its velocity was measured. The forces on the relief system elbows resulting from the fluid flow were also measured. The tests were performed primarily to validate pulse propagation codes used for design and for direct use as design data
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 125 p.
- Report number
- SRI-PYD--6272-Vol.4
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13664790
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FLUID FLOW; HEAT EXCHANGERS; LEAKS; LMFBR TYPE REACTORS; MOCKUP; MOLTEN METAL-WATER REACTIONS; REACTOR COOLING SYSTEMS; REACTOR SAFETY EXPERIMENTS; SIMULATION; SODIUM; STEAM GENERATORS; VALVES; VELOCITY; WATER
- Descriptors DEC
- ALKALI METALS; BOILERS; BREEDER REACTORS; CONTROL EQUIPMENT; COOLING SYSTEMS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLOW REGULATORS; HYDROGEN COMPOUNDS; LIQUID METAL COOLED REACTORS; METALS; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTORS; STRUCTURAL MODELS; VAPOR GENERATORS