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This monthly report details reactor and materials technology activities during the month of June 1965.

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This reports documents progress in process and reactor development, reactor engineering, reactor physics, radiological engineering, process technology, auditing, fuel failure experience, operational physics, process physics, and testing.

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From ninth meeting of the USAEC reactor decontamination information exchange group; Washington, District of Columbia, USA (1 Sep 1965). The decontamination activity described includes: laboratory studies to evaluate reagents, and actual decontamination of 2 steam generators at New Production Reactor. ln laboratory tests, a proprietery oxalic acid solution appeared to be more effective th:dn sny other tried. No excessive corrosion was noted. Special reegents to dissolve high fired ceramic core materials (UO/sub 2/ and PuO/sub 2/) are being developed and evaluated. Phosphorous acid, sulfuric acid and a mixture of sulfuric and nitric acids were effective. Corrosion of 304 stainless steel was low. Two N Reactor steam generators were decontaminated to facilitate inspection and repair. The APSUL procedure was tried, but control of concentrations was inadequate and decontamination factors were low, ranging from 1.6 to 9.0. No excessive corrosion was noted. (auth)

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From Introduction: "The investigation of solar distillation described in this Summary Report is part of the wide-ranging program of the Office of Saline Water to develop economical processes for the conversion of saline water to fresh water." From Summary: " Since the submission of the Summary Report which covered the first two years' progress, several new stills have been constructed, including four basin-type stills for the evaluation of basin liners and other materials."

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This report provides the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials.

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Thermocouples are used for the control and diagnostic measurement of the thermal behavior of cores in the Kiwi and Nerva reactors of Project Rover. The predominant hostile environmental conditions are those of hot hydrogen, hot graphite, and intense nuclear radiation. W/W Re thermocouples, insulated by BeO and encased in Mo or Ta sheaths, seem to show the most promise. Some aspects of thermocouple development, principally shunt effects and sheath integrity, are discussed.

What is attempted here is to compute the energy absorbed in several elements from interactions with neutrons in the energy range of 0 to 14 Mev. In these calculations the results have been normalized to one neutron per square centimeter incident per gram of target material, thus making it a simpler matter to calculate energy absorbed in compounds containing these elements. In these calculations the single-collision approximation is assumed in that each neutron is considered to undergo only one collision in the sample, that scattered neutron escaping from the sample. The results are presented graphically for the elements hydrogen, carbon, nitrogen; oxygen: ·aluminum, ·silicon, germanium, tantalum, and bismuth. Plotted in these figures is the energy transferred per gram of target material per single neutron per square centimeter incident as a function of the-incident neutron energy.

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This report is a guide for producing permuted indexes for personal files, annotated bibliographies and or the Ames Laboratory's annual progress reports.

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This manual provides a list of the quantities of plutonium and plutonium isotope formation. Other isotopes whose concentrations are important and included in this report are U-236 buildup, U-235 burnout, U burnout, Np-237 build-up, GVR (the Gas Volume Ratio) in coproduct target elements and equivalent gram of plutonium. These conversion tables have been calculated on the IBM 7090 digital computer using a program entitled ``FLEX-3.`` The results of the computer solutions have not been normalized to conversion observed by Chemical Processing Department measurement since none are yet available. Conversion ratios for four types of N-Reactor fuel have been evaluated, they are: (1).947 percent U-235 normal fuel loading; (2)1.25 percent U-235 ``spike`` enrichment; (3)1.25 percent U-235 outer, Li-Al inner -- coproduct fuel; (4)1.96 percent U-235 outer, Li-Al inner -- coproduct fuel.

This report describes the Coupled NOFLOW-FIPDIF computer program which has been written to perform the following two related functions: (1) Determination of the temperature attained by reactor materials following a loss of coolant accident. (2) Evaluation of the fission product inventory which would exist at any time (following loss of coolant).

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