TY - BOOK
T1 - Preliminary Results from ORNL Fission Product Release Test VI-7
AU - Osborne, M. F.
AU - Lorenz, R. A.
AU - Travis, J. R.
PY - 1994
Y1 - 1994
N2 - Test VI-7, the seventh and final in a series of high-temperature tests of irradiated fuel in a vertical furnace facility, was conducted September 16, 1993. This series of tests, and the previous series of six HI tests, was sponsored by the U.S. Nuclear Regulatory Commission (NRC). The objectives of these experiments have been to provide the reliable data on fission product release and behavior under light-water reactor (LWR) accident conditions that are needed for sequence-dependent analyses and to evaluate and compare these data with results from other laboratories. Release values for the major fission product and fuel elements have been measured, and chemical forms of the released species have been determined where possible. The results, which are used for the development of the release models required for LWR accident analysis, have been reported in data summary reports and in the open literature.
AB - Test VI-7, the seventh and final in a series of high-temperature tests of irradiated fuel in a vertical furnace facility, was conducted September 16, 1993. This series of tests, and the previous series of six HI tests, was sponsored by the U.S. Nuclear Regulatory Commission (NRC). The objectives of these experiments have been to provide the reliable data on fission product release and behavior under light-water reactor (LWR) accident conditions that are needed for sequence-dependent analyses and to evaluate and compare these data with results from other laboratories. Release values for the major fission product and fuel elements have been measured, and chemical forms of the released species have been determined where possible. The results, which are used for the development of the release models required for LWR accident analysis, have been reported in data summary reports and in the open literature.
KW - 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
U2 - 10.2172/2404617
DO - 10.2172/2404617
M3 - Commissioned report
BT - Preliminary Results from ORNL Fission Product Release Test VI-7
CY - United States
ER -