Analysis of the Initial Nuclear Superheat Critical Experiments: Supplementary Study Related to Bonus and Nuclear Superheat Programs
A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boiler superheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods used in the study predict the measured reactivity and power distribution to within the limits of experimental accuracy.
- Research Organization:
- General Nuclear Engineering Corp., Dunedin, FL (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- NSA Number:
- NSA-15-028808
- OSTI ID:
- 4843230
- Report Number(s):
- GNEC--153
- Country of Publication:
- United States
- Language:
- English
Similar Records
An Engineering Physics Method of Calculation Applied to Light-Water Critical Experiments Investigating Nuclear Superheat
BONUS ZERO POWER CRITICAL EXPERIMENTS AND APPLICATION TO THE REACTOR DESIGN. Terminal Report
FABRICATION OF SUPERHEATER FUEL ROD ASSEMBLIES FOR BONUS CRITICAL EXPERIMENTS
Journal Article
·
Fri Jun 01 00:00:00 EDT 1962
· Nuclear Science and Engineering
·
OSTI ID:4808337
BONUS ZERO POWER CRITICAL EXPERIMENTS AND APPLICATION TO THE REACTOR DESIGN. Terminal Report
Technical Report
·
Fri Feb 09 23:00:00 EST 1962
·
OSTI ID:4828649
FABRICATION OF SUPERHEATER FUEL ROD ASSEMBLIES FOR BONUS CRITICAL EXPERIMENTS
Technical Report
·
Sat Dec 31 23:00:00 EST 1960
·
OSTI ID:4805317
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
ABSORPTION
BONUS
BUCKLING
CADMIUM
CONFIGURATION
CONTROL ELEMENTS
CRITICAL ASSEMBLIES
CRITICALITY
Control rods
DISTRIBUTION
EPITHERMAL NEUTRONS
EQUATIONS
FLUID FLOW
Fast-fission factor
MEASURED VALUES
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
POWER PLANTS
REACTIVITY
REACTOR CORE
REACTORS
STAINLESS STEELS
SUPERHEATING
WATER COOLANT
WATER MODERATOR
ZONES
ABSORPTION
BONUS
BUCKLING
CADMIUM
CONFIGURATION
CONTROL ELEMENTS
CRITICAL ASSEMBLIES
CRITICALITY
Control rods
DISTRIBUTION
EPITHERMAL NEUTRONS
EQUATIONS
FLUID FLOW
Fast-fission factor
MEASURED VALUES
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
POWER PLANTS
REACTIVITY
REACTOR CORE
REACTORS
STAINLESS STEELS
SUPERHEATING
WATER COOLANT
WATER MODERATOR
ZONES