VMR CRITICAL-ASSEMBLY STUDIES
Technical Report
·
OSTI ID:4094994
Critical-assembly research was conducted for Advanced Technology Laboratories of the American-Standard Corporation as a pad of a program to evaluate the technical and economic feasibility of the Variable Moderator Reactor (VMR) concept. The critical-assembly core consisted of 37 hexagonal stainless- steel fuel-element cans, each containing 61 fuel pins. The fuel pins were 0.485 in. OD aluminum tubing (0.028-in. wall) filled with UO/sub 2/ pellets, 0.415 in. in diameter and 1.80% enriched. Fuel pins and elements were arranged in triangular lattices. Core configurations that were combinations of 0.633- and 0.703-in. pin pitches and Light water served as the moderator; whereas water, furfural, furfuryl alcohol, and air were used within the fuel elements as coolant- simulating materials. In the parious core configurations measurements were made of nuclear parameters related to thermal-flux disadvantage factors, resonance- escape probability, fast effects in U/sup 238/ and U/sup 23 / 5>s, and effective neutron temperatures. Critical configurations, reactivity worth of liquid levels, core temperature coefficient of reactivity, and flux and power distributions were also obtained. (auth)
- Research Organization:
- Battelle Memorial Inst., Columbus, Ohio
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-15-010498
- OSTI ID:
- 4094994
- Report Number(s):
- BMI-1482
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
AIR
ALCOHOLS
ALUMINUM
CAPTURE
COOLANTS
COOLING
CRITICALITY
DISTRIBUTION
ENERGY
ENRICHMENT
FAST NEUTRONS
FISSION
FUEL CANS
FUEL ELEMENTS
FUELS
FURANS
LATTICES
LEVELS
LIQUIDS
MEASURED VALUES
NEUTRON FLUX
NEUTRONS
ORGANIC COMPOUNDS
PELLETS
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
RESONANCE NEUTRONS
RODS
SLOWDOWN
STAINLESS STEELS
TEMPERATURE
THERMAL NEUTRONS
TUBES
URANIUM 235
URANIUM 238
URANIUM DIOXIDE
WATER COOLANT
WATER MODERATOR
ALCOHOLS
ALUMINUM
CAPTURE
COOLANTS
COOLING
CRITICALITY
DISTRIBUTION
ENERGY
ENRICHMENT
FAST NEUTRONS
FISSION
FUEL CANS
FUEL ELEMENTS
FUELS
FURANS
LATTICES
LEVELS
LIQUIDS
MEASURED VALUES
NEUTRON FLUX
NEUTRONS
ORGANIC COMPOUNDS
PELLETS
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
RESONANCE NEUTRONS
RODS
SLOWDOWN
STAINLESS STEELS
TEMPERATURE
THERMAL NEUTRONS
TUBES
URANIUM 235
URANIUM 238
URANIUM DIOXIDE
WATER COOLANT
WATER MODERATOR