The objectives of this production test are: (1) to authorize the irradiation of enriched uranium hot-die-size diffusion-bonded fuel elements; (2) to provide information for further evaluation of the hot-die-size process; (3) to evaluate the relative corrosion behavior of the enriched hot-die-sized fuel as compared to the corresponding Al-Si fuel model; and (4) to determine the gross dimensional stability of the fuel under irradiation. This test authorizes irradiation of 19 monitor columns of enriched self-support fuel elements in the C Reactor. The columns will contain 28 fuel elements each; each of the columns will contain 14 fuel elements fabricated by the hot-die-size diffusion-bonded process and 14 elements of the standard Al-Si type. Ten of the columns will contain, in alternate positions in the downstream half of the charge, ``paired`` Al-Si and hot-die-size elements -- elements containing cores from adjacent ingot rod positions. The remaining nine columns will contain hot-die-sized and Al-Si elements, paired by ingot only, in alternate positions in the downstream half of each column. The upstream portion of all charges will contain hot-die-sized and Al-Si elements in alternate column positions. All of the columns of this test will be irradiated to an average column exposure of 1000 Mwd/t. The …

Attached is the interpolated uranium burnout values Financial Consolidations will apply to the current AEC ten year cost study. We have made additional copies which may be of use to you in future studies since the source data was based on the most recent burnout schedule obtained from Washington AEC. We currently have a program to interpolate future burnout schedules. If you have a need for such a program, please contact the author.

Because of rod-sticking problems at DR Reactor, a knuckle rod of B Reactor design was installed in vertical safety channel number 28. The substitute VSR, which has a smaller diameter than the original DR rod, has been tested for its operational feasibility including both drop time and reactivity effect. The reactivity effect of the rod was estimated by comparison of the reactivity transient caused by insertion of the specific B-type rod after scramming into the pile, with similar transients caused by normal vertical safety rod in an adjacent channel. This document lists the indicated relative control strength of the rod as an empirical basis for future safety calculations. Results indicate that the B-type knuckel rod in DR reactor is about 80% as strong as a normal DR vertical safety rod if used in equivalent flux distribution and location; this makes it reasonable to assume that the local control strength of the B-type knuckel rod is 98 {mu}b.

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A discrepancy of about 1000 gpm has existed between the full-flow recorded 190, 105 and ROL flows. While past operating practices have not used the 190 or ROL flow rates for official purposes, the disquieting, though not theoretically unexplicable, differences require some quantitative resolution. On November 24, 1962, a drawdown test of the 190-H storage tanks was performed to establish the accuracy of the various flowmeters. The drawdown test of the 190 storage tanks was run at the beginning of a scheduled reactor shutdown. With the full reactor flow supplied by the electric process pumps feeding from the storage tanks, the 183-H supply to the storage tanks was valved off. Additionally, non-process water usually taken from the storage tanks was valved off. The storage tank water levels were taken, then recorded as a function of time.

This document is divided into the following sections: Fuel element swelling model, tubular fuel element irradiations, Zircaloy-2 cladding strain study, comparison of swelling of U-2 wt % Zr and unalloyed uranium, and Th-U alloy fuel.

An analytical chemistry program was conducted to determine total U-233 and U-232/U-233 ratio in the irradiated thorium oxide. This report summaries the results for samples exposed for one month and briefly describes the analytical procedures.

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This report addresses comments on "Request for Proposal" and digital data system functional specifications and attachments "A".

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Research on numerical analysis, biological and medical statistics, and programming is reported. Programming and analysis work involved chemistry, health physics, analytical chemistry and chemical technology, neutron physics, physics, reactors, reactor chemistry, metallurgy, and computer operation and programming. Agricultural research and the training courses offered are also reported. A list of lectures, papers, and publications for the report period is included. (D.C.W.)

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This report covers the development and qualifications of a brazing process capable of forming the bond between the instrument leads and the seal block. The process developed is unusal in that it permits the formation of a bond between austenitic stainless steel surfaces at the temperatures below 1350°F without a flux.

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Metal-clad thermocouples with a flat (spade) tip were used to measure the temperature of a 0.030-in.-thick metal plate acting as a forced convection heat transfer surface. The thermocouples were found to change the temperature of the plate at the point of attachment by 40 percent of the temperature difference between fluid and plate. This value was found to be independent of fluid velocity, heat flux, and fluid temperature. A heat transfer model of the thernrocouple was developed and analyzed to determine the effective fin height'' of the thermocouple at four test conditions. A correlation is presented between the average heat transfer coefficient of the system and the effective fin height'' of the thermocouple. The model and the correlation may be used to predict the calibration factor for other systems of similar thermocouples during either heating or cooling if the heat transfer coefficient is known. An evaluation of brazing and resistance spot welding for attaching the thermocouples to the plate was made. Resistance spot welding was found to give a weak attachment with poor thermal contact between plate and thermocouple. Brazing was found to give a strong attachment with excellent thermal contact between plate and thermocouple. (auth)

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Declassified 26 Nov 1973. Information on Tory-2C is presented concerning reactor performance, neutronics, design parameters, test program, and physical properties of reactor materials. (DCC)

The transfer of uranyl nitrate hexahydrate solution from the, Purex Plant in 200-East Area to the U0{sub 3} Plant in 200-West Area is presently being accomplished with the use of two specially built trailer trucks. This system has been used since the startup of the Purex Plant. Because the production rate of Purex has increased significantly since then, it seems appropriate to ask, ``Is trucking the optimum method under the present and predicted rates of production?`` At the request of Purex Operation, a study has been made of the UNH hauling system, and of some possible alternatives. The purpose of this study was to compare the various advantages and disadvantages of the present and alternate systems, to make recommendations, and to provide a basis for possible management action.

Activities in a program to test and develop prototype fission-heated thermionic cells for space uses are reported. During the period, in-reactor tests were conducted on two W-clad U-bearing fuel emitters and one unclad type. Fuel emitter proof tests were also conducted which demonstrated 1000-hr operational capability of W-clad systems. Output power density and the temperature of heat rejection were found to have major effects on the weight- performance characteristics of the system. Advances in techniques related to W vapor deposition are reported. Descriptions of the fuel-emitter development, cell design and development, and testing of out-of-pile and in-pile cells are included. Operation of the clad-type test cells at design power and temperature led to selection of these cells for planned long-duration in-pile tests. (J.R.D.)

The Analytical Mass Spectrometry Section at Oak Ridge National Laboratory has, for many years, been determining relative isotopic abundances from solid samples. Thus, useful analytical mass spectrometer experience with every pertinent element has been obtained. These include the 55 polyisotopic elements as well as products of irradiation and fission. The techniques used are summarized in this report. A separate page for each element lists preferred compound, loading of sample, manner of obtaining a stable ion beam, and solutions of special problems. (auth)

The properties of radioisotope fuel compounds and fuel capsule materials which are pertinent to the design and operation of radioisotope heat sources are outlined. These properties are grouped into the following categories: intrinsic, extrinsic, and compatibility. The properties of strontium titanate as the fuel and Hastelloy C as the capsule material are evaluated. (D.L.C.)

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A vacuum analytical method for the determination of oxygen in organic compounds was developed. Several milligrams (usually 3 to 5 mg) of the organic to be analyzed are sealed in an evacuated quartz bomb along with 2.5 to 3.5 mg of an organic reducing agent. Next the bomb is fired at 1050-- 1055 deg C for 30 minutes or longer. At the end of the heating period the bomb temperature is rapidly lowered from 1055 deg C to <650 deg C. As a last step the gaseous products are removed from the bomb and the volumes of CO and H/sub 2/ are determined. From these values the percentage of oxygen can be calculated providing an appropriate blank is obtained. Compounds containing carbon, hydrogen, nitrogen, sulfur, iodine, and chlorine have been successfully analyzed for oxygen. Organic compounds containing fluorine cannot be analyzed for oxygen by this method, because fluorine reacts with quartz to form oxygen and silicon tetrafluoride. (auth)