Pretest predictions for degraded shutdown heat-removal tests in THORS-SHRS Assembly 1. [LMFBR]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5487013

Rose, S D; Carbajo, J J

The recent modification of the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility at ORNL will allow testing of parallel simulated fuel assemblies under natural-convection and low-flow forced-convection conditions similar to those that might occur during a partial failure of the Shutdown Heat Removal System (SHRS) of an LMFBR. An extensive test program has been prepared and testing will be started in September 1983. THORS-SHRS Assembly 1 consists of two 19-pin bundles in parallel with a third leg serving as a bypass line and containing a sodium-to-sodium intermediate heat exchanger. Testing at low powers wil help indicate the maximum amount of heat that can be removed from the reactor core during conditions of degraded shutdown heat removal. The thermal-hydraulic behavior of the test bundles will be characterized for single-phase and two-phase conditions up to dryout. The influence of interassembly flow redistribution including transients from forced- to natural-convection conditions will be investigated during testing.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5487013
• Report Number(s): CONF-831047-91; ON: DE84001980
• Resource Relation: Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AFTER-HEAT REMOVAL
TEST FACILITIES
FUEL ASSEMBLIES
LMFBR TYPE REACTORS
RHR SYSTEMS
FAILURES
AFTER-HEAT
HEAT TRANSFER
HYDRAULICS
NATURAL CONVECTION
REACTOR CORES
REACTOR SAFETY
BREEDER REACTORS
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding