A design and operational description is presented of a BF/sub 3/ withdrawal mechanism planned for installation on one of the two startup channels at the SM-1. An analysis of possible malfunctions is included. (J.R.D.)

The sorption of the ions of uranium, copper, and nickel on hydrous zirconium oxide was investigated at temperatures from 25 to 250 deg C. The experiments were performed by equilibrating 5 ml of the test solution with 0.5 g of zirconium oxide in a titanium autoclave, which was heated by means of a rocking furnace. The sorption of uranium was affected by characteristics of the zirconium oxide, temperatare of equilibration, and concentrations of uranium and of free acid in the uranyl sulfate solutions. Conclusions are drawn concerning the relationship between each of these factors and uranium sorption. (auth)

A titanium pump loop, designed to circulate aqueous solutions at temperatures and pressures up to 370 deg C and 3000 psia, was constructed. It is to be used to study the chemical stability of uranyl sulfate fuel solutions of interest to the Fluid Fuels Reactor Program. The total loop voluime was minimized so that about 2 liters uf solution was sufficient for loop operation. The equipment includes a sampling system to remove solution samples from the loop while operating at elevated temperature and pressure; a hydroclone to separate and remove any solids and/or heavyphase material formed; and provisions for installation of corrosion test specimens in the main loop stream. All equipment performed satisfactorily at design conditions in tests with water. (auth)

Progress is reported on research and development work in pot calcination and radiant-heat spray calcination studies of synthetic Purex high-level wastes; and sorption studies using synthetic minerals and resins as well as natural minerals. The calcination studies are discussed in terms of batch calcination, melting of pot calcination products, spray calcination, and off-gas treatment; and sorption studies in terms of mineral reactions, fixation chemistry, and condensate wastes. (B.O.G.)

Two methods, the transpiration and direct P/sup 32/ counting methods, were tested for use in measuring the vapor pressure of TBP. With the transpiration technique, measured TBP vapor pressures were sufficiently reproducible, and probably of sufficient accuracy, to warrant improvement of the apparatus and its use in measuring the vapor pressure of TBP over various TBP- diluent-HNO/sub 3/-H//sub 2/O-UO/sub 2/ (NO/sub 3/)sub 2 solutions. With this method the vapor pressure of TBP containing 0.2 wt% H/sub 2/O was determined to be ~0.8 mu while that of TBP saturated with H/sub 2/O, ~6.5 wt% H/sub 2/O, was ~ 0.5l mu . The direct P/sup 32/counting technique was abandoned because of experimental difficulties. (auth)

A compilation is presented, in the twenty-five group Reactor Nuclear Data Tape format, of neutron cross sections for elements of major interest for GE- ANPD reactor analysis. The tabulated data are a reproduction of neutron cross section information contained on the Reactor Nuclear Data Tape, which was recently prepared. A brief outline of methods used in processing of the cross sections is also included. (auth)

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This study responds to the requests for data on the subject contained in the D.S. Burrows letter entitled ``Processing Plutonium Scrap`` (symbol FAc:EAS) dated June 30, 1961 and received for reading by Chemical Processing Department Management on July 5, 1961. Cognizance is also taken of the July 5 teletype from G.F. Quinn requesting an appendix updating the content of our document HW-63560 (Pu Reclamation -- January 18, 1960) with regard to safety aspects covered therein. Appendix A of this paper answers this request.

This report summarizes the evaluations of the maximum monetary liability associated with cesium-137 shipments in the STT Casks and strontium-90 shipments in the HAPO-IA Cask. These evaluations are of most immediate importance since these shipments are planned for the month of March 1961. These liability evaluations concern the direct consequences of a release of the fission product shipment in each case, but do not cover the probability of such events occurring. The liability evaluation of the STT shipment of cesium-137, 90,000 curies per car, was based upon the following premises. Cesium is a relatively volatile material, and the entire shipment quantity can be vaporized and released as a cloud during involvement of the car in a fire of sufficient magnitude and duration to rupture the cask. This mechanism would create, by far, the greatest potential exposure of personnel and property to the fission product.

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Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Validity of proposed contract between the Board for Texas State Hospitals and Special Schools and the county, whereby the county agrees to care for mentally ill committed to a Texas State Hospital under the control and management of the Board for Texas State Hospitals and Special Schools.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the State under the Foundation Program Act (Article 2922-11, et.seq.) by way of State allocations has a responsibility to educate, free of tuition, children within the district residenced, enrolled in and under the custody of a private school for exceptional children for all purposes, where the private school determines that enhancement of the children's progress (physical, mental and otherwise) will result from enrolling them in local public schools?

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Distribution for inheritance tax purposes of decedent's one-half community interest in savings accounts held by the decedent and his surviving spouse as joint tenants with right of survivorship.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Constitutionality of House Bill 248 of the 57th Legislature, which would create a civil service system of selection, tenure and status of all employees of counties having a population of not less than 314,000 and not more than 315,000 inhabitants according to the last preceding federal census.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether persons who were over 60 years of age on January 1, 1960, and reside in Bay City are required to possess an exemption certificate, by virtue of the fact that the 1960 Federal census shows that Bay City is now a city of 10,000 inhabitants or more.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether a truck, with a permanently fixed water tank, the only outlet for the water being a permanently fixed spray bar, used to water down road beds prior to paving and used for no other purposes, come within the classification of "construction machinery" as that is used in Art. 6675a, V.C.S.

The purpose of this report is to recommend variable goal plans for natural and enriched bumper fuel elements, specifically for 0-III-NB and 0-III-EB materials, to be irradiated at the B, D, DR, and F Reactors. The average goal exposure for all bumper fuel elements at D Reactor was specified to be 900 MWD/T, with provisions being made for revision by normal procedures. Exposures for enriched bumper material at the B, M. and F Reactors were not specified in the PITA supplement authorizing charging of this material.

It is the objective of this production test to authorize the use of PT IP-216-A (Quality Certification) fuel columns and supplementary numbered columns are required for obtaining routine axial flux measurements suitable for metal performance analysis.

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This document from the principal engineer of the manufacturing section at Hanford calls attention to irreconcilable costs for two fuel fabrication studies. Specifically, the major trouble areas appear to be in refinery, green salt and machining steps.

Technical report describing and evaluating the the three experimental methods for obtaining equation of state data at low temperatures; (1) approximate measurement of the PVT relationship by a piston-displacement technique, (2) the measurement of a heat capacity at constant volume as a function of molar volume and temperature, and (3) direct measurement of the pressure variation of the elastic constants using ultrasonic techniques. X-ray methods also might be applicable.

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A solvent extraction process was developed to produce high-purity Sr/sup 90/ from an irradiated U reprocessing waste solutlon. The extractant is D2EHPA diluted with TBP and Shell Spray Base. The process uses an acetic acid-acetate huffered aqueous phsse which is countercurrently contracted with the D2EHPA organic phase. Calcium and some Ce/sup 144/ extract with the Sr/sup 90/; extraction of other contaminants (Zr/sup 95/, Nb/sup 95/, Ru/sup 106/, and inert lead and iron) is prevented by adding either DTPA or EDTA to the feed solution. Decontamination from Ca and Ce/sup 144/ is provided by back extraction of the Sr/ sup 90/ into an aqueous 1M citric acid solution. The process was used to isolate and purify about one megacurie of Sr/sup 90/ for subsequent use in the fabrication of thermoelectric power generators as part of the Systems for Nuclear Auxiliary Power (SNAP) program. (auth)