SASSYS pretest analysis of the THORS-SHRS experiments. [LMFBR]
The THORS Facility at ORNL was recently modified to allow the testing of two parallel 19-pin simulated fueled subassemblies under natural circulation conditions similar to those that might occur during a partial failure of the shutdown heat removal system (SHRS) of a liquid-metal fast breeder reactor. The planned experimental program included a series of tests at various inlet plenum temperatures to determine boiling threshold power levels and the power range for stable boiling during natural circulation operation. Pretest calculations were performed at ANL, which supplement those carried out at ORNL for the purposes of validating the SASSYS model in the natural circulation regime and of providing data which would be useful in planning the experiments.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 6123086
- Report Number(s):
- CONF-850410-17; ON: DE85005046
- Resource Relation:
- Conference: ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985
- Country of Publication:
- United States
- Language:
- English
Similar Records
THORAX pretest prediction of a sodium-boiling transient in a 19-pin simulated LMFBR driver bundle
Forced-to-natural convection transition tests in parallel simulated liquid metal reactor fuel assemblies
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
LOSS OF FLOW
RHR SYSTEMS
HEAT TRANSFER
HYDRAULICS
FAILURES
AFTER-HEAT
BOILING
COMPUTER CALCULATIONS
FUEL ASSEMBLIES
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding