A METHOD FOR THE COMPARATIVE EVALUATION OF REACTOR CONTROL MATERIALS

摘要

This report describes a method of comparing the approximate nuclear worth and reactivity life of various neutron absorber materials. It is intended that someone relatively unfamiliar with reactor physics can use this method for an approximate comparison of nuclear reactor control materials.nThe method is applicable to thermal reactors with slab type control elements. It is not suitable for comparing control materials when used in rectangular or cylindrical rod geometries.nThe use of this calculation method is demonstrated in a typical reactor appli¬cation. This illustrative example used the control system of the Argonne Experimental Boiling Water Reactor as a model.