Summary Report On Design And Development Of High Temperature Gas-Cooled Power Pile

Technical Report · Mon Sep 15 00:00:00 EDT 1947

DOI:https://doi.org/10.2172/4359623· OSTI ID:4359623

McCullough, C. R. ^[1]

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1. Clinton Labs., Oak Ridge, TN (United States)

This report presents a description of a design for an experimental nuclear power plant utilizing a high temperature gas-cooled power pile as the energy source. The plant consists of the pile, a heat exchanger or boiler, a conventional steam turbine generator and their associated auxiliaries. Helium gas under pressure transfers heat from the pile to the boiler which generates steam for driving the generator. The plant is rated at a normal output of 12,000 kilowatts of heat and an electrical output of 2400 kilowatts. Provision is made for operation up to 20,000 kilowatts of heat (4000 kilowatts of electrical output) in the event operation of the plants proves this possible.

• Research Organization: Clinton Labs., Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-35-058-ENG-71
• NSA Number: NSA-11-013961
• OSTI ID: 4359623
• Report Number(s): MonN-383
• Resource Relation: Other Information: Decl. Feb. 27, 1957. Orig. Receipt Date: 31-DEC-57
• Country of Publication: United States
• Language: English

Related Subjects

71 CLASSICAL AND QUANTUM MECHANICS
GENERAL PHYSICS
BERYLLIUM MODERATOR
BERYLLIUM OXIDES
CONFIGURATION
COOLANT LOOPS
CYLINDERS
ELECTRICITY
FABRICATION
FUEL ELEMENTS
GAS COOLANT
GAS FLOW
GENERATORS
GRAPHITE MODERATOR
HEAT EXCHANGERS
HEAT TRANSFER
HELIUM
HIGH TEMPERATURE
MECHANICAL STRUCTURES
MODERATORS
PLANNING
POWER PLANTS
PRESSURE
REACTOR CORE
REACTOR SAFETY
STEAM
TEMPERATURE
THERMAL NEUTRONS
TURBINES
URANIUM
URANIUM 235
Beryllium Moderator
Beryllium Oxides
Configuration
Coolant Loops
Cylinders
Electricity
Fabrication
Fuel Elements
Gas Coolant
Gas Flow
Generators
Graphite Moderator
Heat Exchangers
Heat Transfer
Helium
High Temperature
Mechanical Structures
Moderators
Planning
Power Plants
Pressure
Reactor Core
Reactor Safety
Steam
Temperature
Thermal Neutrons
Turbines
Uranium
Uranium 235