TRANSIENT TESTS OF THE FULLY ENRICHED URANIUM-OXIDE STAINLESS STEEL PLATE-TYPE C-CORE IN THE SPERT III REACTOR:DATA SUMMARY REPORT

摘要

This report presents the data obtained from the transient test series of the Spert III C-core. The purposes of these tests were to obtain information on the effects of various parametric changes on transient behavior and to provide an opportunity for checking models and theories of reactor behavior over a wide range of parameters. These tests were initiated by a stepwise insertion of reactivity and resulted in initial asymptotic periods ranging from approximately 10 sec to approximately 10 msec. The reactor was operated under the following range of initial system conditions:reactor power -- 10 watts, temperature — ambient to ≈ 320°C, pressure -- atmospheric to 2500 psi, forced coolant flow rate -- 0 to 20,000 gpm. The experimental data obtained from these tests are presented in tabular form and as plots of the time behavior of reactor power, fuel plate surface temperature rise, system reactivity, and energy.