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ACTIVATION ANALYSIS NUCLEAR CHEMICAL RESEARCH RADIOCHEMICAL SEPARATIONS. Progress Report No. 8 for November 1958-October 1959

Description: Activities at the Michigan Reactor and pneumatic tube system are outlined. Various modifications including installation and operation of a "bunny" rabbit pneumatic tube system for transferring samples from laboratory to counter are described. Prelimirary investigation for design of a neutron generator for activation work is described. Modifications to the 100-channel pulse-height analyzer including addition of auxillary circuits and additioral detectors are sumnnarized. In nuclear chemistry a cyclotron bombardment to produce long-lived vanadium tracer for yield determinations in activation analysis is described. Summaries of project work which have been published on absolute (d, alpha) reaction cross sections and excitation functions, use of computers in nuclear data analysis, and research on Ir/sup 196/ are presented. Study of the gamma spectra of 33-second Kr/sup 90/, 41-second Xe/sup 139/, and some longer-lived fission product rare gases is reported and a summary of preliminary results is given. Detection of a long-lived isomer of Ag/sup 108/ in old Ag/sup 110m/ samples is reported and new values for the branching ratios of 2.4minute Ag/sup 108/ are given. Activities of the Subcommittee on Radiochemistry are summarized. Development of a radiochemical procedure by the use of amalgam exchange is reported and exchange of the elements Cd, Tl, Zn, Pb, Bi, Sr, In, and Sn was demonstrated. Methods of expressing the efficiency of radiochemical separations are defined and presented tabularly. Application of activation analysis for many types of systems is reported. Data from activation analysis for trace constituents in meteorites, vanadium in petroleum process streams and in petroleum catalysts are presented. Activation analysis of niobium, rhenium, gold, and thalllum are also described. Information on personnel, published reports, and committee meetings is included. (For preceding period see AECU-3887.) (J.R.D.)
Date: November 1, 1959
Creator: Maddock, R.S. & Meinke, W.W. eds.

ADVANCED DESIGNS OF MAGNETIC JACK-TYPE CONTROL ROD DRIVE

Description: The magnetic jack is a device for positioning the control rods In a nuclear reactor, especially in a reactor containing water under pressure. Magnetic actuation precludes the need for shaft seals and eliminates the problems associated with mechanisms operating in water. It consists of a pressure shell, four sets of external stationary magnet coils (hold, grip, lift, pull down), and one Internal moving part (ammature) that impants linear motion to a cluster of rods. (W.L.H.)
Date: November 1, 1959
Creator: Young, J.N.

AIR CORE CRYOGENIC MAGNET COILS FOR FUSION RESEARCH AND HIGH ENERGY NUCLEAR PHYSICIS APPLICATIONS

Description: It is shown that cryogenic techniques offer the possibility of substantially improving the efficiency and practicality of generating high magnetic fields in air-core coils of large size. Over-all reductions in power requirements of as high as 25, by comparison with conventional coils, are predicted, provided high purity conductors and efficient refrigeration cycles are used. (W.D.M.)
Date: October 30, 1959
Creator: Post, R. F. & Taylor, C. E.

LOS ALAMOS MOLTEN PLUTONIUM REACTOR EXPERIMENT (LAMPRE) HAZARD REPORT

Description: This report supersedes K-1-3425 and LA-2327(Prelim). The first experiment (LAMPRE I) in a program to develop molten plutonium fuels for fast reactors is described and the hazards associated with reactor operation are discussed and evaluated. The reactor desc=iption includes fuel element design, core configuration, sodium coolant system control, safety systems, fuel capsule charger, cover gas system, and shielding. Information of the site comprises population in surrounding areas, meteorological data, geology, and details of the reactor building. The hazmalfunction of the several elements comprising the reactor system. A calculation on the effect of fuel element bowiing appears in an appendix. (auth)
Date: June 1, 1959
Creator: Swickard, E. O.

ANALYSIS OF FUEL ELEMENT CORE BLANKS FOR ARGONNE LOW POWER REACTOR BY GAMMA COUNTING

Description: A technique based on a determinaiion of the differential counting rate exhibited by the 184-kev gamma radiation associated with the decay of U/sup 235/ was developed for the determination of the U/sup 235/ content in Argonne Low Power Reactor fuel element core blanks. The Argonne Low Power Reactor core blanks were an aluminum-highly enriched uranium alloy containing 17.5 weight per cent uranium (approximately 4 g U/sup 235/) having the following dimensions: length, 6.875 inches, width, 3.31 inches, and thickness, 0.200 inch. The gamma- ray spectrum emitied by uranium is rather complex. Using a scintillation spectrometer and scanning the spectrum, the energy is found to be concentrated primarily in two regions, at 184 and 90 kev. The 184-kev gamma rays result primarily from the decay of U/sup 235/ The gammas in the 90-kev region result from the U/sup 235/ decay and daughter products of U/sup 238/ and U/sup 235/. Using a pulse-height analyzer, it is possibie to select the desired radiation emitted from the source and determine the counting rate for a given source. In this work the 184-kev gamma radiation was counted to determine the amount of U/ sup 235/ present in the individual core blanks. (auth)
Date: December 1, 1959
Creator: McGonnagle, W.J. & Perry, R.B.

ANNUAL REPORT

Description: The national laboratory concept, laboratory objectives, the staff, research facilities. research activities, and administration are discussed in general terms and a financial statement is given. Fairly detailed accounts are given for the research programs in the fields of physics, accelerator development, instrumentation, applied mathematics, chemistry, nuclear engineering, biology, and medicine. (W.D.M.)
Date: July 1, 1959

ANPP Code Development Program Pressurized Water Task Quarterly Progress Report: Number One, November 1959

Description: From introduction: The objective of this program is the development of a nuclear physical model and its calculation code for pressurized-water cooled and moderated reactors to predict accurately reactivity, rod positions and power distributions at operating temperatures, and reactor life from a nuclear standpoint.
Date: November 1959
Creator: Olsen, T. M.; Welshans, L. & Eicheldinger, C.

Appendix to Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission Idaho Operations Office Contract No. AT(10-1)-925

Description: Report containing outlines of operating procedures, costs, construction, safety analysis, studies, and design specifications of a 30,000 kilowatt prototype partially enriched uranium nuclear power plant.
Date: March 1959
Creator: Kaiser Engineers

APPLICATION OF ELECTROLESS-NICKEL BRAZING TO TUBULAR FUEL ELEMENTS FOR THE N.S. SAVANNAH. Status Report

Description: The feasibility of using electroless nickel, a chemical deposit containing about 10 wt.% phosphorous in nickel, as the brazing alloy for assembling tubular stainless steel fuel elements of the type specified in Core I of the N. S. Savannah was investigated. This material was selected primarily because of the ease of braze-metal preplacement by chemical deposition of the alloy on type 304 stainiess steel ferrule spacers, prior to fuelbundle assembly. Brazed joints produced by this method were generally characterized by a relatively ductile solid-solution region at the thinnest portions of the fillet. This ductile zone should minimize the possibility of complete propagation of hairline cracks, which form in the brittle, eutectic regions of fillet. The microstructural appearance of the electroless-nickel joints was not appreciably affected by variations in the brazing temperature from 1750 to 1900 deg F or the brazing time from 15 to 60 min. Several plating solutions were evaluated and all were found to be capable of producing deposits suitable for brazing applications. Corrosion tests conducted in static 525 deg F water indicated that no significant attack of joints brazed with electroless nickel had occurred after 300-hr exposure. A small fuel bundle was successfully assembled by brazing with electroless nickel. (auth)
Date: June 1, 1959
Creator: Lamartine, J T & Thurber, W C

Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Description: Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Date: June 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.

Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date: May 25, 1959
Creator: Aerojet-General Corporation