## A NATURAL URANIUM-GRAPHITE SUBCRITICAL REACTOR SYSTEM FOR EDUCATION AND RESEARCH. Report No. 7. PART I. DESCRIPTION AND EXPERIMENTAL MEASUREMENTS. PART II. IBM 650 COMPUTER PROGRAMS FOR EFFECTIVE SIZE, DIFFUSION LENGTH, AND MATERIAL BUCKLING CALCULATIONS

Critical measurements were performed on an exponential pile. Routines for the IBM-650 computer were developed for the calculation of the effective size from horizontal neutron flux traverses, and the diffusion length and the material buckling from the best fit to axial traverses for a parallelopiped subcritical reactor. The programs were checked with data obtained from the natural uranium - graphite subcritical reactor. (W.L.H.)