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Research in Nuclear Physics. Progress Report No. 7

Description: A twenty-inch analyzing magnet has been completed except for the final trimming of the pole pieces. In onder to further examine the systematics in the angular distribution of elastically scattered alpha particles, the scattering of alpha particles from spectroscopically pure O/sup 16/ and hydrogen sulfide gases was studied. The change of the static quadrupole interaction in indium metal wth temperature was investigated. Results give a value Q = 10/sup -24/ cm/sup 2/. An experimental study of the betagamma directional correlations in the decay of Au/sup 198/, he long-range as well as the short-range stabilily of the fast coinci-dence scintillation spectrometer has been improved by building new 404A limiter circuits. The directional correlation of the 172 to 247 kev gamma cascade of Cd/sup 111/ was measured for gaseous InCl/sub 3/ sources as a function of the delay introduced into the channel accepting the first gamma ray of the cascade, and also as a function of the source temperature and pressure. This was done in an attempt to determine the nature of the interaction to which the Cd/sup 111/ nucleus is subjected when the source is in the gaseous state. In the decay of Cl/sup 40/ there is evidence for gamma rays of 0.55, 0.66, 0.96, 1.1, 4.2, and 6.3 Mev. A half life of 1.42 plus or minus 0.02 min was determined. Isomerism of In/sup 110/ and In/sup 112/ is being investigated. (For preceding period see COO-173.) (W.D.M.)
Date: June 15, 1957
Partner: UNT Libraries Government Documents Department

Report on discussion of Pinex experiment with J-12 group at Los Alamos

Description: Plans for participation in Operation Hardtack include performance of a Pinex experiment on three barge-based events: Nutmeg, Hickory, and Juniper. The J-12 group at Los Alamos has been planning for a group of similar experiments. Inclusion of Pinex in the Hardtack diagnostic program occurred considerably later; also, J-12 has successfully carried out two Pinex experiments during Operation Plumbbob. This visit was made to take the fullest possible advantage of their experience to date. Discussion of the experiment at these meetings is summarized under five convenient headings: Detector; Pinhole and Collimator Assembly; Alignment; Data Analysis; and Recovery.
Date: December 30, 1957
Creator: Boyrie, E.; Chesterman, A. & Clark, A.
Partner: UNT Libraries Government Documents Department

Efficiency of Scavenging Devices in Determining Falloug. Progress Report No. 6 March 15 to July 31, 1957

Description: A fall-out sample collector was designed and tested for use in collecting samples at the soil surface. The sampler consists of artificial grass and a stainless steel pot. Results are included from preliminary studies on the scavenging properties of artificial grass. The effects of relative humidity, rain, and wind velocity on the efficiency of scavenging devices were investigated. A comparison was made of Sr/sup 90/ fall-out data from samples collected on gummed film and surface soil samples from various locations. Preliminary experiments were performed for the evaluation of devices used in determining air concentration of radioactive fall-out or other particulate matter. (For preceding period see AECU-3435.) (C.H.)
Date: September 23, 1957
Creator: Rosinski, J.
Partner: UNT Libraries Government Documents Department

Pressurized Water Reactor Program Technical Progress Report for the Period July 15, 1954 to August 26, 1954

Description: This progress report has 2 parts. Part 1 PWR Engineering covers the following topics: (1) power plant analysis and systems; (2) power plant components and component materials and tests; and (3) reactor and auxiliaries. Part 2 PWR Development covers: (1) fuel element development; (2) metallurgy of core materials; (3) materials application development; (4) chemistry development; (5) irradiation effects; and (6) reactor physics.
Date: October 31, 1957
Partner: UNT Libraries Government Documents Department

The Fast Oxide Breeder-the Fuel Cycle

Description: The development of a fast breeder fuel cycle based on a core fuel consisting of mixed dioxides of uranium and plutonium is described. Process flowsheets, material balances, operating schedules, cost schedules, and a plant layout are presented, and the laboratory- and plant-scale process and equipment demonstrations are described. A cost estimate based on a demonstration of the process including the unique plant equipment gives a total fuel cycle cost of 2.04 mils/kw-hr and a net fuel cycle cost of 1.53 mils/kw-hr (0.3 breeding gain assumed). (auth)
Date: July 1, 1957
Creator: Davidson, J. K.; Haas, W. O., Jr.; Mewherter, J. L.; Miller, R. S. & Smith, D. J.
Partner: UNT Libraries Government Documents Department

Single-Fluid Two-Region Aqueous Homogeneous Reactor Power Plant Conceptual Design and Feasibility Study. Final Report

Description: The feasibility of a 150 Mwe aqueous homogeneous nuclear power plant was investigated by a joint study team of the Nuclear Power Group and The Babcock & Wilcox Company. In this concept, the reactor is a single-fluid two-region design in which the fuel solution circulates through the thoria pellet blanket as the coolant. Componeats and plant arrangement were designed to provide maximum overhead accessibility for maintenance. All components in contact with reactor fuel at high pressure are themselves enclosed in close-fitting high-pressure containment envelopes. (auth)
Date: July 1, 1957
Partner: UNT Libraries Government Documents Department

PROCEEDINGS OF THE SECOND ANNUAL MEETING ON BIO-ASSAY AND ANALYTICAL CHEMISTRY, OCTOBER 11 AND 12, 1956

Description: Topics discussed include procedures for the determination of Po in urine, feces, and blood; the determination of Be in biological materials; application of statistical methods to bio-assay; techniques for low-level alpha counting and pulse-height analysis; the toxicology of plutonium; the metabolism and toxic effects of fission products; methods for the radiometric determination of I/sup 131/ and Sr/sup 90/ in urine; procedures for the radiochemical analysis of Sr and Ba in human urine; and the design and performance of a wholebody gamma counter. (See also NLCO-595.) (C.H.)
Date: September 27, 1957
Creator: none,
Partner: UNT Libraries Government Documents Department

Transient Heat Transfer in Reactor Coolant Channels

Description: An analysis is presented of the transient behavior of a generalized cooiant channel neglecting temperature dependent reactivity changes. The analysis is applicable to forced convection cooling of heterogeneous reactor fuel elements or electrically heated simulation thereof. Derivations are given for cases of variation of coolant inlet temperature and of heat generation. An approximation is also developed applicable to thin fuel elements. From this, solutions are obtained for cases-of impulsive, step, linear, and step-exponential variations of inlet temperature, and, of impulsive and uniform variations of heat generation. The solutions presented will be of use during preliminary stages of design of new heterogeneous reactor concepts (when the use of computing machines may not be warranted), and, in the design and interpretation of transient experiments simulating reactor fuel channels. (auth)
Date: October 31, 1957
Creator: Stein, R. P.
Partner: UNT Libraries Government Documents Department

Definitive scope of a facility for E-Metal product segregation at the UO{sub 3} Plant Project CG-767

Description: E-Metal production is scheduled to start through the UO{sub 3} Plant in July of 1958. E-Metal is defined in HW-46138 as uranium metal enriched with U-235 to a level selected to be always-safe for non-metallic uranium forms, i.e. for compounds encountered during solvent extraction or calcination. Currently E-metal as selected contains 0.94% U-235 prior to irradiation. Planning of a segregation facility requires that the mixing of E-Metal with normal uranium be minimized, thereby preventing costly downgrading. Segregation of E-Metal through existing facilities would require extensive cleanout and flushing. Production scheduling with present demonstrated capacity would make this method impossible. The Redox Plant will produce E-Metal on an intermittent basis. It is expected that normal operating production of E-Metal through the Redox Plant will be quantities of 100 to 200 tons. Production through the UO{sub 3} Plant will follow on this same intermittent basis. During the first two quarters of FY `59 the UO{sub 3} Plant production of E-Metal is forecast at not greater than 100 tons per quarter. Following this initial period the E-Metal production is forecast to run 135 to 200 tons per quarter for the next three to four years. It is the purpose of this document to establish a scope and design criteria for a facility providing segregation of E-metal in the UO{sub 3} Plant until the continuous calciners have demonstrated sufficient capacity to process all production. The two new tanks required for this project may be obtained from excess vessels available on-site. In order to complete this facility by July, 1958, it will be required that existing on-site equipment and materials be adapted for all possible applications.
Date: November 4, 1957
Creator: Gustafson, L. D.
Partner: UNT Libraries Government Documents Department