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Fission product source terms for the LWR loss-of-coolant accident

Technical Report ·
DOI:https://doi.org/10.2172/5341503· OSTI ID:5341503
Models for cesium and iodine release from light-water reactor (LWR) fuel rods failed in steam were formulated based on experimental fission product release data from several types of failed LWR fuel rods. The models were applied to a pressurized water reactor (PWR) undergoing a hypothetical loss-of-coolant accident (LOCA) temperature transient. Calculated total iodine and cesium releases from the fuel rods were 0.053 and 0.025% of the total reactor inventories of these elements, respectively, with most of the release occurring at the time of rupture. These values are approximately two orders of magnitude less than releases used in WASH-1400, the Reactor Safety Study.
Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
5341503
Report Number(s):
NUREG/CR-1288; ORNL/NUREG/TM-321; ON: TI85015937
Country of Publication:
United States
Language:
English