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Open AccessReport10.2172/4594525

Fast Reactor Fuel Meltdown Test Facility Requirements

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TL;DRAbstract

To provide a basis for the evaluation of existing or proposed reactor facilities for fast reactor meltdown testing, a study was conducted to establish the nuclear characteristics and supporting auxiliaries required of a test reactor facility to enable it to make a significant contribution to existing data on meltdown phenomena for fast reactor safety studies. The range of meltdown accident types of interest to fast reactor safety analysts is discussed in detail. It is concluded that, in addition to burst-type operation, a test facility must be capable of brief periods of high-power operation. It is necessary to approximate steady-state temperature conditions in a fuel test sample prior to initiation of meltdown such as by reduction of coolant flow or an increase in power. A minimum-sized oxide fuel test bundle containing 19 pins 0.25 inch in outside diameter is specified, to be tested in a sodium or NaK loop capable of removing up to 112 Mw of heat from the test bundle. The data requir

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To provide a basis for the evaluation of existing or proposed reactor facilities for fast reactor meltdown testing, a study was conducted to establish the nuclear characteristics and supporting auxiliaries required of a test reactor facility to enable it to make a significant contribution to existing data on meltdown phenomena for fast reactor safety studies. The range of meltdown accident types of interest to fast reactor safety analysts is discussed in detail. It is concluded that, in addition to burst-type operation, a test facility must be capable of brief periods of high-power operation. It is necessary to approximate steady-state temperature conditions in a fuel test sample prior to initiation of meltdown such as by reduction of coolant flow or an increase in power. A minimum-sized oxide fuel test bundle containing 19 pins 0.25 inch in outside diameter is specified, to be tested in a sodium or NaK loop capable of removing up to 112 Mw of heat from the test bundle. The data requir

Keywords

Nuclear engineeringNuclear reactor coreNeutron fluxHeat fluxCore (optical fiber)Nuclear reactorProcess engineeringEnvironmental science

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