
doi: 10.2172/5147225
Meaningful qualification testing of nuclear reactor components requires a knowledge of the radiation fields expected in a loss-of-coolant accident (LOCA). The overall objective of this program is to define the LOCA source terms and compare these with the output of various simulators employed for radiation qualification testing. The basis for comparison will be the energy deposition in a model reactor component. The results of the calculations are presented and some interpretation of the results given. The energy release rates and spectra were validated by comparison with other calculations using different codes since experimental data appropriate to these calculations do not exist.
Reactor Safety, 22 General Studies Of Nuclear Reactors, After-Heat, Loss Of Coolant, 210100 -- Power Reactors, Boiling Water Cooled, Nonbreeding, Nonboiling Water Cooled, 21 Specific Nuclear Reactors And Associated Plants, Bwr Type Reactors, Reactors, Reactor Accidents, Accidents, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Fission Product Release, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Light-Water Moderated
Reactor Safety, 22 General Studies Of Nuclear Reactors, After-Heat, Loss Of Coolant, 210100 -- Power Reactors, Boiling Water Cooled, Nonbreeding, Nonboiling Water Cooled, 21 Specific Nuclear Reactors And Associated Plants, Bwr Type Reactors, Reactors, Reactor Accidents, Accidents, Water Cooled Reactors, 210200 -- Power Reactors, Safety, Fission Product Release, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Light-Water Moderated
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