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Literature Survey on World Isotope and Radiation Technology : First Semi-Annual Report Covering the Period from June 15, 1961 to December 14, 1961

Description: The following report is the first semi-annual report of a literature survey designed to investigate the uses and technology of radioisotopes in the countries of the world from 1955 to the present. This survey includes two phases: 1) involves the direct comparison of radioisotopic work in all fields in various countries as demonstrated at international conferences. 2) involves a more detailed examination and evaluation of the individual fields of interest selected previously (Phase II is also ex… more
Date: January 10, 1962
Creator: Haffner, J. W. & Terrell, C. W.
Partner: UNT Libraries Government Documents Department
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Critical Path Scheduling of ETR and MTR Reactor Shutdowns

Description: Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
Date: January 10, 1962
Creator: Jacobs, R. T. & Myers, L. L.
Partner: UNT Libraries Government Documents Department
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Numerical Analysis of Neutron Resonances

Description: Neutron resonances are analyzed numerically by determining the resonant energies, the total widths, and the neutron widths of the resonances. It was assumed that the total cross section can be represented by the sum of single- level Breit-Wigner formulas, with interference between resonance and potential scattering but no interference between resonances; that the Doppler broadening is represented by a Gaussian function; and that the instrument resolution is represented by a Gaussian function. G… more
Date: January 10, 1962
Creator: Atta, S.E. & Harvey, J.A.
Partner: UNT Libraries Government Documents Department
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Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

Description: A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date: January 10, 1962
Creator: Brondel, J. O.
Partner: UNT Libraries Government Documents Department
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INDUSTRIAL CRITICALITY MEASUREMENTS ON ENRICHED URANIUM AND PLUTONIUM. PART II

Description: ABS>A series of neutron multiplication measurements made on sub-critical systems containing enriched uranium and plutonium is presented. These measurements involve both aqueous and metal systems. (auth)
Date: January 10, 1962
Creator: Schuske, C.L.; Bell, C.L.; Bidinger, G.H. & Smith, D.F.
Partner: UNT Libraries Government Documents Department
open access

A Bench-Scale Natural-Recirculation Dissolver

Description: A natural-recirculation dissolver closely approaching a stirred-tank reactor in behavior was developed, and its feasibility was demonstrated in the mercury-catalyzed dissolution of aluminum in nitric acid, It was designed to utilize the heat of reaction and evolution of gaseous reaction products for recirculation and mixing. The dissolvent was 5-molar nitric acid, containing mercury in concentrations from 10/sup -4/ to 10/sup -3/ molar as a catalyst. Dissolution rates for 1/7 scale, simulated M… more
Date: January 10, 1962
Creator: Erickson, E. E.
Partner: UNT Libraries Government Documents Department
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