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.

This report addresses the buckling tests of scaled graphite barrel inner reflectors.

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This report, for June 1965 from the chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

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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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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).

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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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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