Elk River Reactor Operations Analysis Program (Annual Progress Report July 1, 1965 - June 30, 1966)
- Allis-Chalmers Manufacturing Co., Bethesda, MD (United States)
During the period between July 1 ,1965 and June 30, 1966 the reactor heat generated was 14,117.1 Mwd; and the net electrical power generated was 129,408 Mw-hr. Overall plant behavior was excellent except for some minor difficulties caused by leaking tubes in the evaporators. Operations analysis efforts during this period have been directed mainly toward establishing a core loading pattern which best meets the objectives of the Elk River Reactor, making recommendations concerning proposed changes to the technical specifications, analyzing the operation of the plant energy systems and the thimble cooling system, and studying other problems of particular interest to the Chicago Operations Office of the U. S. Atomic Energy Commission.
- Research Organization:
- Allis-Chalmers Manufacturing Co., Bethesda, MD (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-21-001153
- OSTI ID:
- 4469779
- Report Number(s):
- ACNP-66557
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ANALYSIS-- BORON CARBIDES-- CONTROL ELEMENTS-- DISTRIBUTION-- FUEL ELEMENTS-- FUELS-- LOADING-- MEASUREMENT-- OPERATION-- POWER-- REACTIVITY-- REACTOR CORE-- REACTORS-- RODS
ANALYSIS-- COOLANT LOOPS-- CORROSION-- HEAT EXCHANGERS-- HIGH TEMPERATURE-- MATERIALS TESTING-- PERFORMANCE-- STRESSES-- WATER
CONTROL-- CONTROL ELEMENTS-- COOLING-- OPERATION-- PERFORMANCE-- RODS
Control Rods
Corrosion
ERR ANALYSIS-- BURNUP-- CRITICALITY-- FUEL ELEMENTS-- TRANSPORT-- VESSELS
Flux Distribution
Fuel Elements
Heat Exchanger
Materials
Nuclear Criticality Safety Program (NCSP)
Reactor Operation
ANALYSIS-- BORON CARBIDES-- CONTROL ELEMENTS-- DISTRIBUTION-- FUEL ELEMENTS-- FUELS-- LOADING-- MEASUREMENT-- OPERATION-- POWER-- REACTIVITY-- REACTOR CORE-- REACTORS-- RODS
ANALYSIS-- COOLANT LOOPS-- CORROSION-- HEAT EXCHANGERS-- HIGH TEMPERATURE-- MATERIALS TESTING-- PERFORMANCE-- STRESSES-- WATER
CONTROL-- CONTROL ELEMENTS-- COOLING-- OPERATION-- PERFORMANCE-- RODS
Control Rods
Corrosion
ERR ANALYSIS-- BURNUP-- CRITICALITY-- FUEL ELEMENTS-- TRANSPORT-- VESSELS
Flux Distribution
Fuel Elements
Heat Exchanger
Materials
Nuclear Criticality Safety Program (NCSP)
Reactor Operation