PWR Response to an Inadvertent Boron-Dilution Event
Conference
·
OSTI ID:6025512
Response of a pressurized water reactor (PWR) to an inadvertent boron-dilution event during refueling was studied experimentally in the Loss-of-Fluid Test (LOFT) facility and in a plexiglass model of the LOFT reactor vessel. These experiments showed that good mixing of the diluent and fluid volumes occurred in the direct-flow-path volumes which are used in simulating residual heat removal (RHR) in a PWR. In addition, other fluid volumes, not in the RHR path, also mixed, delaying the time to criticality beyond that expected based on RHR volumes only.
- Research Organization:
- EG and G Inc., Idaho Falls, ID (United States); Illinois Institute of Technology, Chicago, IL (United States). Dept. of Chemical Engineering
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6025512
- Report Number(s):
- EGG-M-03783; CONF-830439-8; ON: DE83013666
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220600 -- Nuclear Reactor Technology-- Research
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ACCIDENTS
BORON
CHEMICAL COMPOSITION
CONTROL
COOLING SYSTEMS
CRITICALITY
ELEMENTS
ENERGY SYSTEMS
Experimentally
FLUID MECHANICS
FLUID POISON CONTROL
HYDRAULICS
Inadvertent Boron Dilution event
KINETICS
LOFT REACTOR
Loss-Of-Fluid Test (LOFT) Facility
MECHANICS
MIXING
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
Plexiglass Model of the LOFT Reactor Vessel
Pressurized Water Reactor (PWR)
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR FUELING
REACTOR KINETICS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RHR SYSTEMS
Refueling
Residual Heat Removal (RHR)
SAFETY
SEMIMETALS
SUBCRITICALITY
TANK TYPE REACTORS
TEST FACILITIES
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BORON
CHEMICAL COMPOSITION
CONTROL
COOLING SYSTEMS
CRITICALITY
ELEMENTS
ENERGY SYSTEMS
Experimentally
FLUID MECHANICS
FLUID POISON CONTROL
HYDRAULICS
Inadvertent Boron Dilution event
KINETICS
LOFT REACTOR
Loss-Of-Fluid Test (LOFT) Facility
MECHANICS
MIXING
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
Plexiglass Model of the LOFT Reactor Vessel
Pressurized Water Reactor (PWR)
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR FUELING
REACTOR KINETICS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RHR SYSTEMS
Refueling
Residual Heat Removal (RHR)
SAFETY
SEMIMETALS
SUBCRITICALITY
TANK TYPE REACTORS
TEST FACILITIES
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS