SADD - Severe accident database directory

DataBase In-Vessel - Focus area 4: Fission products release (2)

Facility Name	Test Identification	Measured Parameters	Country
ACRR-ST	ST1	4 UO2 rods, burn-up=47 GWd/tU, H2/Ar, max T=2500	Albuquerque, NM, USA
References: Allen M D, Stockwell H W, Reil K O and Fisk J W, "Fission Product Release and Fuel Behaviour of Irradiated Light Water Reactor Fuel Under Severe Accident Conditions - The ACRR ST-1 Experiment", NUREG/CR-5345, SAND89-0308, Sandia National Laboratories, Albuquerque, NM, October 1992. IP/Copyright Situation: To be checked
ACRR-ST	ST2	4 UO2 rods, burn-up=47 GWd/tU, H2/Ar, max T=2500	Albuquerque, NM, USA
References: Allen M D, Stockwell H W, Reil K O and Fisk J W, "Fission Product Release and Fuel Behaviour of Irradiated Light Water Reactor Fuel Under Severe Accident Conditions - The ACRR ST-1 Experiment", NUREG/CR-5345, SAND89-0308, Sandia National Laboratories, Albuquerque, NM, October 1992. IP/Copyright Situation: To be checked

fission product release from irradiated LWR fuel in a fission heated environment.