CONCEPTUAL DESIGN OF A GAS-COOLED LOOP FOR THE ATR
Results are presented of a conceptual design study for a gas-cooled loop to be inserted in one of the outer test facilities in the Advanced Test Reactor. The design objectives called for a circulating gas loop capable of operation in a maximum fast neutron flux of 1.3 x 10/sup 15/ n/cm/sup 2//sec with an associated gamma heat of 22 watts/gram. The maximum temperature of the gas would be 1400 deg F. The loop proposed was designed for air cooling; other gases such as N/sub 2/ or He may also be used but with some changes in the operating parameters. One pound per second of air at 250 psi and 200 deg F is circulated in a 4-in. OD (2.5-in. ID) top reentrant loop capable of removing 225 kw of fission plus gamma heat from a test specimen. The maximum outlet gas temperature with fission heat is 1400 deg F; without fission heat it is 900 deg F. Constructed primarily of 347 stainless steel with 304 stainless steel in some out-of-pile regions, the proposed loop is estimated to cost 0,000 including design and contingencies. Time required for engineering, procurement, fabrication, and installation is estimated to be twelve to fifteen months. (auth)
- Research Organization:
- Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(10-1)-205
- NSA Number:
- NSA-18-007966
- OSTI ID:
- 4105169
- Report Number(s):
- IDO-16707
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ABSORPTION
AIR
ATR
CONFIGURATION
ECONOMICS
EFFICIENCY
FABRICATION
FAST NEUTRONS
FISSION
GAMMA RADIATION
GAS COOLANT
GAS FLOW
GASES
HEAT TRANSFER
HEATING
HELIUM
HIGH TEMPERATURE
IN PILE LOOPS
IRRADIATION
MASS
MATERIALS TESTING
MECHANICAL STRUCTURES
NEUTRON FLUX
NITROGEN
OPERATION
PLANNING
PRESSURE
REACTOR CORE
REACTOR TECHNOLOGY
RESEARCH REACTORS
STAINLESS STEELS
AIR
ATR
CONFIGURATION
ECONOMICS
EFFICIENCY
FABRICATION
FAST NEUTRONS
FISSION
GAMMA RADIATION
GAS COOLANT
GAS FLOW
GASES
HEAT TRANSFER
HEATING
HELIUM
HIGH TEMPERATURE
IN PILE LOOPS
IRRADIATION
MASS
MATERIALS TESTING
MECHANICAL STRUCTURES
NEUTRON FLUX
NITROGEN
OPERATION
PLANNING
PRESSURE
REACTOR CORE
REACTOR TECHNOLOGY
RESEARCH REACTORS
STAINLESS STEELS