APPR-1 RESEARCH AND DEVELOPMENT PROGRAM SHIELDING EXPERIMENTS AND ANALYSES. Task No. IV
The APPR-l shielding was conservatively designed and therc are many places where it can be reduced with a saving in both cost and weight. The neutron distribution through the APPR-1 shield is described with sufficicnt accuracy by modified two group theory to warrant its use in future shield designs. The IBM 650 code which was written to calculate the gamma flux distribution through the primary shield gave results sufficiently close to the measured values so that it can be used with confidence in futurc design work. Calculation of the N/sup 16/ activity in the primary coolant with the use of the activating flux above l0 Mev and a l6.3 mb cross section gives results which are within the experimental error of the measured value. Calculation of the dose rate due to the N/sup 16/ activity was done by an available IBM 650 code. It gave results that were considerably below the measured values within the vapor container but that agreed sufficiently well with the measured values outside the vapor container. This eode can be used for secondary shield design with confidence. All the mechanisms involved in the accumulation of corrosion product activity in the primary coolant cannot be adequately described analytically. The prediction of the demineralizer activity is only within a factor of three. (auth)
- Research Organization:
- Alco Products, Inc., Schenectady, NY (United States)
- DOE Contract Number:
- AT(30-3)-326
- NSA Number:
- NSA-13-013693
- OSTI ID:
- 4258694
- Report Number(s):
- APAE-35andSuppl.1
- Resource Relation:
- Other Information: Includes Supplement, by S.S. Rosen. Decl. Feb. 19, 1959. 7p. Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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