A STUDY OF THE SHIELD OF THE VIRGINIA POLYTECHNIC INSTITUTE UTR-10 REACTOR

A study of the radiation leakage from the shield of the Virginia Polytechnic Institute UTR-10 reactor was completed. Fast-neutron, thermal- neutron, and gamma dosimeters of high sensitivity were employed to obtain a detailed network of data over all surfaces of the shield. Supplementary experiments evaluated gamma dose rat es in a corridor and in a classroom adjoining the reactor room andd also determined a rough value for argon dispersal through the reactor room ventilating system. The results of the detailed survey showed generally satisfactory performance of the shield for fast- and thermal- neutron radiations, but a number of regions were identified in which the gamma dose rat e was higher than that predicted by the shield design. (auth