QUARTERLY TECHNICAL REPORT SPERT PROJECTnOctober, November, December/ 1959

摘要

The kinetic test program using the Oak Ridge National labora¬tory BSR-II core at Spert I has been planned to yield information per¬taining to the safety of the core with and -without the ORNL safety system operative and, in addition, to supply detailed performance charac-teristics for the safety system during short-period power excursions. The data would also add to the store of information on the self-limiting behavior of cores with different physical and nuclear properties. The small, stainless steel, plate-type, BSR-II core has been installed in the Spert I reactor and neutron flux distributions, control rod worths, and void and temperature coefficients have been measured. The neutron flux peaking in a water-filled hole in this core has also been determined as an aid to the planning of future capsule-type experiments.nThe void coefficient of reactivity has been measured in the Spert III reactor as a function of system temperature.