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
Technical Report
·
OSTI ID:4249106
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.)
- Research Organization:
- Washington. Univ., Seattle. Engineering Experiment Station
- NSA Number:
- NSA-13-015710
- OSTI ID:
- 4249106
- Report Number(s):
- NP-7597
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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OSTI ID:4249106