A detailed study of four reactor and shield configurations was made. Two basic reactor types, the boiling water and pressurized water reactors were considered. Shield materials of lead-water and iron-water were used with varying thicknesses for determining the optimum shield configuration for the PL-3 reactor. Also presented is a survey of available shielding codes. (auth)

As for any nuclear reactor, the operation of the Hanford reactors is governed by many technical and administrative considerations. With the completion of current project action, later this year, certain of the technical limitations on reactor power level will be relieved, notably at the K Reactors, At that time, the technical and engineering limitations will be more liberal at some reactors than required for operation at the administrative power level limits, imposed by the Atomic Energy Commission, that are currently in force. The following report discusses the various technical factors governing reactor power levels and compares these with the currently imposed administrative power level limits.

Enclosed is the data that was collected during the recent thermal cycle of KER-1. This data includes the RTD readings and information taken from the thermocouple fuel element. In conjunction with obtaining data on film build-up, the test provided an excellent opportunity to study the effect of temperature on measured tube power. It has been noticed that the KER reactor tubes appear to produce more power (greater {Delta}T) at lower operating temperatures, but the reason for this power increase is not known. With the additional thermocouples to measure water temperatures at the center of the tube, it should be possible to determine if this increase is from the graphite or from the fuel elements.

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, Crawford Martin, regarding a legal question submitted for clarification: Validity of Section 49 of Article V of the Appropriations Bill No. 15 of the 60th Legislature, Regular Session, and related question.

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, Crawford Martin, regarding a legal question submitted for clarification: Whether under Articles 1269m and 6252-4a, V. C. S., a city fireman, on returning from military leave prior to the effective date of Article 6252-4a, is entitled to credit for pay purposes for the time spent in military service.

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, Crawford Martin, regarding a legal question submitted for clarification: Whether a Justice of the Peace, acting as local registrar, is authorized to issue certified copies of birth and death certificates, and related questions.

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, Crawford Martin, regarding a legal question submitted for clarification: Whether the making of investments in the name of a nominee and the payment of custodial fees are deemed to be within the provisions of Article 6243e, V. C. S.

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, Waggoner Carr, regarding a legal question submitted for clarification: Whether Section 7(a) of S.B. 15, Acts 58th Leg., R.S., 1963, ch. 205, p. 550, codified as Art. 6165b., V.C.S., is ambiguous, and, if so, are applicants for one or more licenses required to pay an investigation fee or $200.00 for each license applied for in addition to the annual license fee.

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, Waggoner Carr, regarding a legal question submitted for clarification: Whether the operator of a commercial feed lot, who conducts his business as outlined, is subject to the requirements of Article 3881e, V.C.S.

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 Texas Youth Council has the authority, under existing law, to furnish a prescribed uniform for staff members under their control to wear while carrying our their duties, and related questions.

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: Legal Status of Texas Public Junior Colleges as regards their eligibility for financial assistance under Title III of the National Defense Education Act of 1958.

Studies during the last two years have shown that the pneumatic impaction process is a flexible process for the production of cermet fuel elements. However, there is still much basic information to be acquired about the process before the limits of process capability can be established. Development work proposed herein is intended to continue optimization of the process, to establish the process parameters necessary to a pilot plant or production line operation, and to better define the process limitations.

This report details model studies performed as required by the design, development, and research contract between the General Electric Company and Washington State University. These studies provide analytical considerations for K-Downcomer and Bellows.

The following document describes the usage and results of sending pulsed beams of electrically charged particles with electrically wide range of pulse lengths and pulse repetition rates.

This is one of twenty-one volumes sumarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume discusses the background to the General Electric program, and summarizes the various direct-air-cycle nuclear test assemblies and power plants that were developed. Because of the requirements of high performance, low weight, and small size, vast improvements in existing technology were required to meet the flight objectives. The technological progress achieved during the program is also summarized. The last appendix contains a compilation of the abstracts, tables of contents, and reference lists of the other twenty volumes.

Early work on the interaction of high energy deuterons with large /sup 238/U targets is reexamined and current theoretical study is discussed. Results of fission and neutron yield calculations are compared with experiment. (SDF)

The feasibility of contoured I&E cans for production use has been demonstrated using our present flat base I&E sleeve (HW-37187). Studies by Process Engineering and Quality Control have shown that only a material savings would result from the use of only the contoured I&E can. Consideration was then given to the use of contoured sleeves (H-3-16879) to improve the contact areas and the resulting heat transfer during fuel assembly.

The purpose of this program is to conduct studies in the freshwater environment to acquire data needed to evaluate and predict the potential radiation hazards to human populations in the defined regions of proposed nuclear excavations in the Republics of Panama and Colombia. The results of the field surveys conducted in Phase II are presented in this report. Specifically, the data describes the elemental composition of the major components of the ecosystem, and reports the calculated stable element concentration factors for the major food organisms. This data provides baseline values from which predictions can be made of the potential maximum radionuclide intake by populations using this resource.

3 8 ; 9 4 5 7 5 C 9 E ; < : 7over a 1456-day period. The half life was calculated to be 12.355 plus or minus 0.0l0 years, based on measurements in three calorimeters. The yields of /sup 208/Po and /sup 209/Po from the irradiation of multicurie quantities of /sup 210/Po were calculated. Production of small quantities of /sup 208/Po and /sup 209/Po is possible by the (n,xn) reaction; however, large quantities of /sup 210/Po would be present in the /sup 208/Po--/sup 209/Po sample. On the basis of these calculations the maximum /sup 208/Po content would occur after 466 days' irradiation in the materials testing reactor. An experimental decay scheme was drawn for /sup 208/Po on the basis of experimental data. Experiments are in progress to determine whether levels at about 1.4 Mev in /sup 208/Bi are populated in the electron capture decay of /sup 208/Po The known half-life method for determining the resolution time of a counting instrument was found to yield only an average value for the counting range in the computation. To correct the counting error a series of computations should be made with data covering only a short segment of the decay curve …

Declassified 24 Sep 1973. The purpose of this work was to develop a process for recovering the uranium from spent Rover fuels. Only one reactor is used, and the process involves a 4-hr combustion of the fuel in oxygen at about 800 deg C, a 4-hr chlorination of the U/sub 3/O/sub 8/-Nb/ sub 2/O/sub 5/ ash in refluxing hexachloropropene at 180 deg C, dissolution-extraction of the UCl/sub 4/ and NbCl/sub 5/ products at room temperature by dilute nitric acid, and extraction of the uranium from the resulting acid solution with 30% TBP in Amsco diluent. The results indicate that an extract containing 50 g of uranium per liter can be produced in seven or eight extraction stages, with total uranium losses of less than 0.02%. Corrosion rates of several possible construction materials during chlorination are less than 0.1 mil/month. Problems in the process involve handling about 10% of the niobium as a solid during the liquid- liquid separations, and handling solutions containing chloride. The results of this laboratory-scale work indicate that the liquid-phase chlorination and subsequent extraction operations are reducible to large-scale practice, since these operations resemble the liquid-phase operations typically performed in radiochemical separation plants. (auth)

The Experimental Beryllium Oxide Reactor is described. The configurations and properties of BeO blocks are discussed. Various BeO shapes were fabricated and tested. BeO specimens of selected compositions and densities were irradiated. Dimensional changes due to radiation were in the range below 1.4% as determined from micrometer measurements. Some of the specimens in the highest exposure region of the capsule exhibited radial fractures. (M.C.G.)

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