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This report summarizes the results of the seventh and last of a series of tests completed in the A-11 test program during the Contract Year 1964

This report summarizes the results of the fifth of a series of tests completed in the A-11 test program.

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This report discusses 105 intermediate range test hole which was bored in 105-F to demonstrate reactor hole boring techniques. This test hole was then utilized to determine the performance of neutron sensitive gamma compensated ion chambers (CIC), the effectiveness of epoxy reactor shield plug designs, the compatability of the prototype.components intermediate range instrumentation, and demonstrate the performance of an intermediate range monitor system on a typical Hanford reactor application. In the process of determining the above information physical, nuclear, gamma, and temperature data was recorded as related to the 105-F intermediate range monitor test hole and is provided in this report.

Salt wastes from the Redox solvent extraction process have been routed to the 241-SX tank farm for storage since May 21, 1954. Tanks in this farm contain wastes from three types of irradiated uranium processing: (1) low (approximately 250 MWD/T) and (2) high (approximately 600 MWD/T) natural uranium; and (3) E-metal. It is estimated that approximately 1.6 Kgs of Am-Cm, 17 Kgs of Np-237, 20 Kgs of Pu and 8 tons of uranium are present in the sludges from wastes generated through 4-30-64. A total of 12.1 Kgs of the 29.1 Kgs of Np-237 estimated has been recovered or is present in the Redox Np-237 accumulation cycle as of 4-30-64. Because of the potential for unmeasured losses (such as Pu or U precipitates) the total plutonium and uranium may exceed the quantities stated herein. A breakdown of the estimates by tanks is provided.

This document is a user manual for those who are familiar with problems 500 Node Transient Heat Transfer Code.

The thermal and hydraulic core parameters were determined using the SORTD I code for 90% ThO/sub 2/, 10% UO/sub 2/ fuel both for (1) a core containing 592 fuel elements corresponding to the UC reference core with a maximum UC temperature of 2000 deg F and (2) a core containing 784 fuel elements corresponding to a UC core with a maximum UC temperature of 1750 deg F. Eighteen rod elements with 2.5 in./sup 2/ and 3.5 in./sup 2/ fuel areas, and 30 rod elements with 4.5 in./sup 2/ and 5.5 in./sup 2/ fuel areas are analyzed for 8 cases. (auth)

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This progress report covers the period from November 15, 1963 to February 15, 1964. A study indicated that the most desirable type of blower drive turbine is one using main turbine throttie steam conditions and exhausting to the main turbine cross-over line. Preliminary planning for the initiation of a dynamic structural analyses of the overall steam generator was completed. External pressure loading and thermal stress calculations show that the calandria has a suitable design margin. A revised fuel latch operable from the rear face of the core was designed. A study was initiated to determine the feasibility of substituting Zircaloy for the stainless steel tubing within the active core. Preliminary sizing of control rod extensions and gang plates was completed. Initial loading of the second configuration of the 630A critical experiment reactor was completed. Detailed power distributions were measured in the 11 typical positions. Subcritical and critical rod worth curves were obtained in the critical experiment with up to 132 shim rods in the core. Moderator temperature coefficient measurements were made and agreed well with analytical data. Critical experiment correlation of fine radial power calculations in the revised mock-up showed good agreement. Performance specifications were prepared for a 1-Mw(e) power …

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In this letter the author describes a measurement of the absolute decay rate {Gamma}{sub 2}({+-}0) {approx_equal} {Gamma}(K{sub 2}{sup 0} {yields} {pi}{sup +}{pi}{sup -}{pi}{sup 0}). The result is based on 16 events of the type {pi}{sup -} p {yields} {Lambda}K{sup 0} followed by {Lambda} {yields} p{pi}{sup -} and K{sub 2}{sup 0} {yields} {pi}{sup +}{pi}{sup -}{pi}{sup 0}, and 2608 double-vec events {pi}{sup -} p {yields} {Lambda}K{sup 0} with {Lambda} {yields} p{pi}{sup -} and K{sub 1}{sup 0} {yields} {pi}{sup +}{pi}{sup -}.

Evidence is presented which points to (at least) two bound forms of bacteriochlorophyll present in chromatophores of Rhodospirillum rubrum, both of them readily converted to unbound bacteriochlorophyll (abs. max. 770 mu) when the chromatophores are extracted with acetone or ethanol. Controlled oxidation of the chromatophores with Ir(IV) or with Zn(II) and ferricyanide preferentially destroys the more strongly absorbing pigment (abs. max. 880 mu) but brings about only a slight decrease in the magnitude of the photoinduced absorption changes at 810 and 792 mu. Such oxidations yield a new pigment, absorbing at 715 mu in the aqueous preparation and, more strongly, at 680-684 mu when the pigment is extracted into organic solvents. This pigment is formed irreversibly and is therefore different from the material formed by photooxidation of chromatophores. Its visible spectrum and the spectrum of the material formed from it by acidification suggest that it is a chlorophyll-like substance, possibly derived from bacteriochlorophyll by (two-electron) oxidation of one of the dihydropyrrole rings to a pyrrole ring. Directions are given for separation of this pigment from other colored compounds present in the oxidation mixtures.

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This document outlines the Westinghouse Astronuclear Laboratory (WANL) specification and procedures for acceptance testing of accelerometers. All accelerometers that are to be used for reactor instrumentation shall meet the requirements of this specifications before being accepted.

This document outlines the Westinghouse Astronuclear Laboratory (WANL) specifications and procedures for acceptance testing of differential and absolute pressure transducers. All pressure transducers used for reactor instrumentation shall meet the requirements of this specification before being accepted .

This report is a descriptive journey of the Acceptance test specifications/procedure for thermocouples.

This report describes a series of acoustic noise sensitivity tests which have been run on accelerometer amplifiers. The test specimens consists of NRX-A1 type components and two additional piezoelectric accelerometers which are being considered for possible application in radiation environments.

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The potential of shipping a bucket of metal that has not had sufficient decay time is a common problem to all Reactor Processing Operations. The only method at present to assure shipping adequately decayed metal is by procedural control. This study was performed to determine the feasibility of establishing decay time for irradiated metal in buckets by radiation activity measurements.

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