METHOD AND APPARATUS FOR REACTOR SAFETY CONTROL
Patent
·
OSTI ID:4804382
A nuclear reactor control device is disclosed which releases a neutron absorbing gas in the event the reactor flux exceeds a predetermined value. The device consists of a stainless steel or aluminum can containing a cadmiumplated high-pressure chamber, a low-pressure chamber, and a normally sealed passage connecting the two chambers. A heating element responslve to neutron flux is so arranged that when the flux becomes excessive, the temperature of the heating element becomes sufficient to unseal the passage and release a neutron absorbing gas such as boron trifluoride (BF/sub 3/) enriched in B/sub 10/
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-16-006137
- OSTI ID:
- 4804382
- Report Number(s):
- AU 222673
- Country of Publication:
- Australia
- Language:
- English
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Related Subjects
ABSORPTION
ALUMINUM
AMMONIUM COMPOUNDS
BORON 10
BORON FLUORIDES
CADMIUM
CELLULOSE
CHROMATOGRAPHY
COATING
COMBUSTION
CONTROL SYSTEMS
ETHERS
EXCURSIONS
FUSED SALTS
GASES
HEATING
HIGH TEMPERATURE
HYDROGEN PEROXIDES
INJECTION
LEACHING
MELTING
NEUTRON FLUX
NITRIC ACID
PATENT
PLANNING
POTASSIUM SULFATES
PRECIPITATION
PRESSURE
QUALITATIVE ANALYSIS
QUANTITATIVE ANALYSIS
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
RESIDUES
SEALS
SEPARATION PROCESSES
SERVOMECHANISMS
SHUTDOWN
SODIUM CARBONATES
SODIUM PHOSPHATES
SOLVENT EXTRACTION
SPECTROSCOPY
STAINLESS STEELS
THERMAL NEUTRONS
TUBES
U3O8
URANATES
URANIUM
ALUMINUM
AMMONIUM COMPOUNDS
BORON 10
BORON FLUORIDES
CADMIUM
CELLULOSE
CHROMATOGRAPHY
COATING
COMBUSTION
CONTROL SYSTEMS
ETHERS
EXCURSIONS
FUSED SALTS
GASES
HEATING
HIGH TEMPERATURE
HYDROGEN PEROXIDES
INJECTION
LEACHING
MELTING
NEUTRON FLUX
NITRIC ACID
PATENT
PLANNING
POTASSIUM SULFATES
PRECIPITATION
PRESSURE
QUALITATIVE ANALYSIS
QUANTITATIVE ANALYSIS
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
RESIDUES
SEALS
SEPARATION PROCESSES
SERVOMECHANISMS
SHUTDOWN
SODIUM CARBONATES
SODIUM PHOSPHATES
SOLVENT EXTRACTION
SPECTROSCOPY
STAINLESS STEELS
THERMAL NEUTRONS
TUBES
U3O8
URANATES
URANIUM