APPR-1: Design, Construction and Operation
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- Alco Products, Inc., Schenectady, NY (United States)
- Stone and Webster Engineering Corp., Boston, MA (United States)
- Univ. of Virginia, Charlottesville, VA (United States)
Papers presented at the Second Winter Meeting of the American Nuclear Society on October 28, 1957 in New York City are presented. Included are papers on Army Package Power Reactor design and construction, core loading calculations and experiments, zero power experiments, heat removal calculations and experiments, mechanical design features, shield design and measurements, startup and operation, and water treatment and waste disposal.
- Research Organization:
- Alco Products, Inc., Schenectady, NY (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(11-1)-318
- NSA Number:
- NSA-12-011819
- OSTI ID:
- 4337595
- Report Number(s):
- APAE-23
- Resource Relation:
- Conference: Second Winter Meeting of the American Nuclear Society, New York City, NY (United States), 28 Oct 1957; Other Information: Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
APPR-1
BIBLIOGRAPHY
CONFIGURATION
COOLANT LOOPS
CRITICALITY
EQUATIONS
HEAT TRANSFER
ION EXCHANGE
MASS
MEASURED VALUES
MECHANICAL STRUCTURES
OPERATION
PLANNING
POWER PLANTS
REACTOR CORE
REACTOR FUELING
SHIELDING
STARTUP
WASTE DISPOSAL
WATER COOLANT
Nuclear Criticality Safety Program (NCSP)
Core Loading
Plant Design
Zero Power Experiments
Heat Removal
Shield Design
Water Treatment
Waste Disposal
Radio Chemical Data
42 ENGINEERING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
APPR-1
BIBLIOGRAPHY
CONFIGURATION
COOLANT LOOPS
CRITICALITY
EQUATIONS
HEAT TRANSFER
ION EXCHANGE
MASS
MEASURED VALUES
MECHANICAL STRUCTURES
OPERATION
PLANNING
POWER PLANTS
REACTOR CORE
REACTOR FUELING
SHIELDING
STARTUP
WASTE DISPOSAL
WATER COOLANT
Nuclear Criticality Safety Program (NCSP)
Core Loading
Plant Design
Zero Power Experiments
Heat Removal
Shield Design
Water Treatment
Waste Disposal
Radio Chemical Data