This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of materials undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, {open_quotes}Status Report Equations.{close_quotes} The integrated exposure reported is the average exposure received by the surrounding uranium columns. Conversion to exposure received by the sample is left to the customer.

Cadastral map of Blanco County showing rivers and property lines, with notations referencing land grant citations. Scale ca. 1:66,667.

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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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.

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In accordance with agreements reached at the Systems Analysis Meeting held between WANL, AGC and SNPO personnel at WANL on 6 April 1965, an equation set has been developed which describes the NERVA systems. The equations are documented herein.

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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A limited program of evaluation of the ML-1 technology as related to the design of the calandria/pressure vessel assembly was completed. This work included: a photoelastic experimental program which resulted in the conclusion that values recommended by Langer and O'Donnell for the effective elastic constants employed in the analysis of ligament stresses in the ML-1 type tube sheets in the past results in a good approximation of the bending constants but in a value of the tensile elastic modulus which is about 40% too high; several modifications to the TSA computer code for stress calculations which improved the precision and flexibility of the code; and a very preliminary evaluation of the properties of candidate materials for use in a high-performance, advanced ML-1 type pressure vessel.

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This report details activities at Battelle Pacific Northwest Laboratory for the month of June 1965.

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Report that "compares gas turbines with steam turbines as means of producing electric power from gas-cooled reactors with all-ceramic fuel elements." (p. 1)

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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).

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

The LACBWR is a nuclear power plant of nominal 50 Mw electrical output, which utilizes a forced-circulation, direct-cycle boiling-water reactor as its heat source. The plant is on the east bank of the Mississippi River in Vernon County, Wisconsin, approximately 1 mile south of the village of Genoa, Wisconsin, and approximately 19 miles south of the city of La Crosse, Wisconsin.

This report addresses the La Crosse boiling-water reactor safeguards report for operating Authorization.

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