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Design of Electrical Heater Pins to Simulate Transient Dryout and Post-Dryout of Water Reactor Fuel

机译:电热器设计模拟水反应堆燃料瞬态干涸和后干燥

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A theoretical assessment of indirect and direct filled heater simulations of nuclear reactor fuel pins is described. For reasons of fast temperature response, a direct unfilled heater, with thermocouples buried in the walls, is recommended for studies of Loss-of-Coolant Accidents leading to dryout, post-dryout and rewetting. A design of heater pins, for use in SGHWR or PWR experiments, and compatible with existing 9MW power supplies, is described. Experiments to confirm collapse pressure calculations at 1000 exp 0 C and thermocouple response times are also reported. (Atomindex citation 10:482755)

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