The current specifications for the cladding on {open_quotes}N{close_quotes} fuels were established early in the course of process development and were predicted on several basic considerations. Among these were: (a) a desire to provide an adequate safety factor in cladding thickness to insure against corrosion penetration and rupture from uranium swelling stresses; (b) an apprehension that the striations in the zircaloy cladding of the U/zircaloy interface and on the exterior surface might serve as stress-raisers, leading to untimely failures of the jacket; and (c) then existing process capability - the need to maintain a specified ratio between zircaloy and uranium in the billet assembly to effect satisfactory coextrusion. It now appears appropriate to review these specifications in an effort to determine whether some of them may be revised, with attendant gains in economy and/or operating smoothness.

In the past, in-reactor testing of materials was restricted to gross sorting. It has consequently been the practice to report the exposure of a sample by relating the exposure to the heat energy released by the nearby uranium fuel, usually reported in the familiar MWD/AT (megawatt day per adjacent ton) unit. The measurement is not complicated by the kind of material, geometry factors of the samples, or loading conditions of the reactor. However, these very facts limit the usefulness of the measurement. Current materials programs require refinement beyond the gross sorting phase, and many tests are now aimed at studying the effects of trace amounts of elements upon the structural properties of materials. This type of test requires a more quantitative determination of exposure than the MWD/AT estimate can provide. Therefore, a better definition of the neutron flux in the Hanford Irradiation Facilities is required in order to facilitate analyses of irradiation experiments and to accurately predict irradiation conditions for proposed experiments. The objective of this program is to define the neutron flux at various positions of a representative number of the irradiation facilities. To date, data has been collected, reduced, and partially analyzed for two side-to-side test facilities. This …

This monthly document details activities of the Hanford Operations Office during the month of April 1960. (FI)

Isotope production calculations have been prepared in the past to indicate present and potential reactor capability; however, the cases evaluated generally considered production of only one or possibly two isotopes. With the wide variety and potential demand for numerous isotopes, the question arises as to what the production capability would be if several isotopes were being produced at the same time. To study this problem in more detail and determine which of several alternates may be used in meeting production requirements, the Case Generator and Evaluator System has been developed. This document presents a production matrix and reviews the assumptions used to derive the matrix. This matrix should be useful in planning future CAGE isotope cases.

The polarization of the neutrons produced by photodisintegration of deuterium by 2.75-Mev gamma rays was measured and the results compared to theoretical predictions. The photoneutrons were tsken at five gamma-ray-neutron angles between 45 and 135 deg in the laboratory and scattered from magnesium which has a broad resonance at these neutron energies. Tne polarization was determined from the asymmetry in the left-right scattering from magnesium. The neutrons are found to be negatively polarized as predicted. The magnitude of the polarization and the dependence on the gamma-ray-neutron angle were found to be in agreement with the theory within experimental error. (auth)

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The Department of Computer Science of the University of Illinois has constructed and put into service ILLIAC II, a large-scale digital computer. ILLIAC II is used both in computer systems research and in general University service.

The results of test stand studies of a pneumatic atomizing nozzle to be used in the Demonstrational Waste Calcining Facility at the Idaho Chemical Processing Plant are presented. Atomization and performance characteristics are described. The liquid feed control system for the Demonstrational Waste Calciner is compared with results of bench scale tests, and recommendations are made for improving the system. (auth)

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The external holdup of expensive materials and associated capital costs for the heat removal systems of fluid fuel breeders were determined. The aqueous homogeneous and molten salt breeders were found to contain substantially less uranium holdup external to the core than the liquid metal fueled breeder. The cost of heat removal and turbogenerator plant equipment for the three systems was compared. (auth)

The hot-water corrosion resistance and mechanical properties of niobium and a number of its alloys were evaluated relative to their usefulness in pressurized-water thermal reactors. Unalloyed niobium was found to be rapidly attacked by 600 and 680 deg F water and 750 F steam. A number of alloying additions were found which markedly improve the corrosion resistance of niobium. Of these, binary and ternary combinations of chromium, molybdenum, titanium, vanadium, and zirconium were among the most effective. Many of these alloys exhibited as low or lower weight gains than those obtained for Zircaloy-2 under similar test conditions. Most of the niobium-base alloys tested for strength exhibited excellent resistance to creep at temperatures up to 1200 deg F under stresses through 20,000 psi. (auth)

This document is divided into: byproduct horizontal control rod system (5 reactors); high-speed scanning-effluent temperature monitoring system (KE reactor); improved reactor gas system (100-KE & KW); safety circuit system modifications (5 reactors); alternate process hot die sizing, 313 Building 300 Area; button line equipment (234-5 Building); in-tank waste solidification (3rd unit); and misc. minor equipment projects.

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