An analysis of self-terminating power transients in the reactor HIFAR

Abstract

Consequences of step reactivity additions above critical have been calculated for HIFAR under conditions of no coolant flow and the operating coolant flow rate of 400 kgs. In particular, the maximum core excess reactivity that will allow loss of a central coarse control arm blade from the core has been determined. In order to perform these calculations a cylindrical geometry version of the neutron kinetics, heat transfer code ZAPP has been written and tested against the experimental data from the SPERT III-E oxide core. The results of this comparison are given as an appendix to this report.