PLUTONIUM RECYCLE TEST REACTOR FINAL SAFEGUARDS ANALYSIS. SUPPLEMENT 4. GAS-COOLED LOOP ANALYSIS

Technical Report · Thu Mar 01 04:00:00 EST 1962

OSTI ID:4793742

Wittenbrock, N G

A gas-cooled loop is being installed in the PRTR in process channel 1542. This loop will be used initially to study the radiation damage and radiation- induced chemical reactions of graphite in high temperature gases. In addition, it will be possible to study the irradiation behavior of gascooled fuel elements at powers up to 500 kw. Carbon dioxide or other gases will be used as the primary loop coolant and will be pressurized to a maximum of 500 psig. The maximum test section effluent temperature will be 1500 deg F. To achieve the high coolant temperature planned for the test program, regenerative heat exchange and supplemental electrical heating of the influent coolant is used. High speed, canned-motor blowers equipped with self-acting, gas-lubricated bearings are used for circulating the primary CO/sub 2/ coolant. A shroud tube cooling loop, using helium as the coolant, is provided to prevent overheating of the PRTR calandria aluminum shroud tube. This loop is designed to keep the maximum shroud tube temperature below 530 deg F. A loop safety system is provided for protection of the reactor and the loop against off-standard conditions. Protection is provided against primary coolant high outhet temperature, primary coolant low flow, primary loop low pressure, and shroud coolant loop low flow. Tripping the loop safety circuit will scram the reactor and cool the gas loop. Insertion of the gas loop test section in the PRTR core will have a small negative reactivity effect. It was experimentally determined that the reactivity loss from insertion of the test section, without a fuel element, was 6 mk. This loss of reactivity will be approximately compensated by the charging of additional enrichment. The presence of the gas loop test section in the reactor will have only a small effect on the magnitude of a reactor excursion, amounting to about 2% increase in the energy release from an excursion if the excursion is terminated by the negative fuel temperature coefficient alone. Analysis of the gas loop final detailed design revealed no serious adverse effect on the nuclear safety of the PRTR. The radiological consequences of a reactor accident would not be changed by the presence of the gas loop. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-16-015022
• OSTI ID: 4793742
• Report Number(s): HW-61236(Suppl.4)
• Country of Publication: United States
• Language: English

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ACCIDENTS
ALUMINUM
BEARINGS
CANNING
CARBON DIOXIDE
CHEMICAL REACTIONS
COATING
EFFICIENCY
ELECTRICITY
ENRICHMENT
EXCURSIONS
FUEL ELEMENTS
FUELS
GAS COOLANT
GAS FLOW
GASES
GRAPHITE
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LABORATORY EQUIPMENT
LUBRICATION
MOTORS
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RADIATION INJURIES
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REPROCESSING
RESEARCH REACTORS
SAFETY
STANDARDS
TEMPERATURE
TUBES
VELOCITY