EVESR-Nuclear Superheat Fuel Development Project (Eleventh Quarterly Report, December 1964 - February 1965)
- General Electric Co., San Jose, CA (United States)
This is the eleventh in the series of quarterly progress reports being issued to cover the work performed on the EVESR-AEC Nuclear Superheat Fuel Development Project under Contract AT(04-3)-189, P. A. 29. The EVESR plant design and the design of the first core load of fuel are described in detail in GEAP-4105, "The First Quarterly Report," and in APED-3958, "Final Hazards Summary Report for the ESADA-VESR." The eleventh quarterly report is intended to cover the technical progress on the AEC-sponsored EVESR Nuclear Superheat Fuel Development Project for the period between December 1, 1964 and February 28, 1965.
- Research Organization:
- General Electric Co., San Jose, CA (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- NSA Number:
- NSA-19-035757
- OSTI ID:
- 4583354
- Report Number(s):
- GEAP--4810
- 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
22 GENERAL STUDIES OF NUCLEAR REACTORS
BOILING
BONUS
COMPUTERS
CONTROL SYSTEMS
COOLANT LOOPS
CORROSION
CRITICALITY
D-CODES
ENRICHMENT
ESADA-VESR
FAILURES
FUEL CANS
FUELS
GAS FLOW
GASES
GENERATORS
HYDROGEN
Heat transfer
IMPURITIES
INJECTION
Mark II
Nuclear Criticality Safety Program (NCSP)
OPERATION
OXYGEN
PLANNING
POWER PLANTS
PROGRAMMING
Power and Power-Breeder Reactors
REACTOR CORE
REACTOR FUELING
REACTORS
SHUTDOWN
STEAM
SUPERHEATING
TEMPERATURE
TESTING
THERMOCOUPLES
TUBES
TURBINES
Turbine
URANIUM 235
WATER COOLANT
WATER MODERATOR
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BOILING
BONUS
COMPUTERS
CONTROL SYSTEMS
COOLANT LOOPS
CORROSION
CRITICALITY
D-CODES
ENRICHMENT
ESADA-VESR
FAILURES
FUEL CANS
FUELS
GAS FLOW
GASES
GENERATORS
HYDROGEN
Heat transfer
IMPURITIES
INJECTION
Mark II
Nuclear Criticality Safety Program (NCSP)
OPERATION
OXYGEN
PLANNING
POWER PLANTS
PROGRAMMING
Power and Power-Breeder Reactors
REACTOR CORE
REACTOR FUELING
REACTORS
SHUTDOWN
STEAM
SUPERHEATING
TEMPERATURE
TESTING
THERMOCOUPLES
TUBES
TURBINES
Turbine
URANIUM 235
WATER COOLANT
WATER MODERATOR