Natural circulation in simulated LMFBR fuel assemblies
Description
Natural circulation experiments have been performed using simulated liquid metal fast breeder reactor fuel assemblies in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility, an engineering-scale sodium loop. Objective of these tests has been to provide experimental data under conditions that might be encountered during a partial or total loss of the shutdown heat removal system (SHRS) in a reactor. The experiments have included single- and two-phase tests under quasi-steady and transient conditions, at both nominal and non-nominal system conditions. Results from these test indicate that the potential for reactor damage during degraded SHRS operation is extremely slight, and that natural circulation can be a major contributor to safe operation of the system in both single- and two-phase flow during such operation
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE85011424.Files
16086083.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- CONF-850420--4
Conference
- Title
- 2. specialists' meeting on decay heat removal and natural convection in LMFBRs.
- Dates
- 17-19 Apr 1985.
- Place
- Long Island, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16086083
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; COOLANT LOOPS; FUEL ASSEMBLIES; LMFBR TYPE REACTORS; NATURAL CONVECTION; REACTOR SAFETY EXPERIMENTS
- Descriptors DEC
- BREEDER REACTORS; CONVECTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; REACTORS