A logical sequence for evaluating the mechanical properties of N-Reactor pressure tubing in the as-received condition is similar to evaluation after reactor service. The usual difficulties associated with testing a heavy tube to failure with 300 C water are compounded after reactor service by the high gamma radioactivity of the discharged tubes. Success in testing of discharged reactor pressure tubing in a pilot underwater facility led to the construction of an Irradiated Tube Testing ·Facility (ITTF) adjacent to the Radiometallurgy Building. The ITTF consists of a 10 .ft 6 in. deep, water-filled basin 15 ft long by 10 ft wide, …
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Publisher Info:
Brookhaven National Laboratory (BNL), Upton, NY (United States)
Place of Publication:
Upton, New York
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A logical sequence for evaluating the mechanical properties of N-Reactor pressure tubing in the as-received condition is similar to evaluation after reactor service. The usual difficulties associated with testing a heavy tube to failure with 300 C water are compounded after reactor service by the high gamma radioactivity of the discharged tubes. Success in testing of discharged reactor pressure tubing in a pilot underwater facility led to the construction of an Irradiated Tube Testing ·Facility (ITTF) adjacent to the Radiometallurgy Building. The ITTF consists of a 10 .ft 6 in. deep, water-filled basin 15 ft long by 10 ft wide, with six test chambers placed within the basin. These chambers are stainless steel bell jars that enclose the specimen, blast shielding, and electric furnace. The vessels exclude water from the hot specimen and furnace during testing and contain the pressure surge that occurs when the hot pressurized water flashes to steam upon failure of the test specimen. The ITTF basin is connected to the Radiometallurgy Building Basin by an underwater tube containing a conveyor system. The conveyor makes it possible to transfer highly radioactive materiais with ease and safety. Remote handling tools were developed to measure the tubes, attach end closures, attach thermocouples, and load lhe specimen within the furnace containment vessels.
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