Metallurgical examinations and evaluations were performed on a group of four target tubes from Atomic Power Development Associates (APDA) Rig 10. This group included two 2/sup 1///sub 4/ Cr--1 Mo ferritic steel tubes, one Type 304 SS, and one Incoloy 800 tube. These tubes had been exposed to small leaks of water in 600/sup 0/F sodium. Metallographic data indicate that the material loss (wastage) was primarily due to impact (or erosion) of liquid particles. No evidence of corrosion was found in the wasted areas of any target tubes. Minor corrosion was observed on the outside diameter of the austenitic stainless-steel tubes only in areas away from impact; no corrosion was detected on the outside diameter of the ferritic steel tubes. Hardness measurements and microstructural analyses revealed that the maximum temperature may have reached 1600/sup 0/F in the wasted areas. This localized temperature increase appeared to enhance the wastage process for all target tubes regardless of composition. Surface grain elongation and plastic deformation lines were observed in wasted areas, as well as in other areas. However, their cause(s) cannot be ascertained with respect to deformation due to water-jet impact, or deformation due to fabrication and handling, or both. Based on the …

Information on the JOSHUA system for lattice physics measurements is presented concerning leakage modules, edit modules, control modules, lattice depletion modules, lattice Monte Carlo modules.

Lattice physics subsystems of the JOSHUA system are described. Information is included on data management, geometry modules, nuclear data modules, and integral transport modules. The JOSHUA system is a set of computer codes for the design of heterogeneous reactors.

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The purpose of this study is to experimentally determine the thermal hydraulic characteristics of the One-Inch Overbore fuel geometry under both single and two-phase flow conditions. Results of these experiments demonstrate the relation between pressure drop and flow at various tube power levels and will be utilized to establish process tube operating limits and trip margins.

This report presents calculations to reduce the quantity of tritium released to the environment from the Purex Plant.

The complete annual R & D report consists of this summary and two companion reports, one from DUN which covers reactors and another from ARHCO which covers separations. These companion reports are listed in the set of references in the back of this summary.

Thoria is irradiated in the Hanford reactors for the production of U-233. The product quality is acutely sensitive to the control of the unseparable contaminant isotopes U-232 and U-238. Recent discussions between personnel of ARCHO and DUN indicate that product quality of a forthcoming separations campaign can be significantly enhanced by analysis of data for which we solicit your support. This letter describes the necessary background and the required analysis. Virgin thoria lots are processed to required transient impurity levels by the National Lead Company of Ohio. They are subsequently shipped to DUN identified by this virgin lot number and are accompanied by the transient impurity levels and U-238 contaminant levels based on statistical samples and analytic chemistry results. Virgin NOL thoria lots consist of various tonnages or fractions thereof, and two or three such lots are typically combined into a single DUN thoria element lot. By weighted averages, the U-238 contaminant level of DUN thoria lots is thus accurately known. The range of U-238 contaminant in any given DUN lot was further controlled by establishing three categories, A, B, and C, with U-238 ranges of 0-1.99, 2.0-3.3, and 3.4-5.0, respectively, on a thoria basis. Thus when a DUN lot …

An earlier attempt to demonstrate our capability to produce medical-grade Pu-238 was discontinued because of unanticipated growth of the neptunium oxide-graphite matrix targets. It has since been established through a subsequent test discharged in February that the graphite matrix targets failed because of inadequate provisions for target expansion and not because of inadequacies in the graphite matrix targets could be used successfully to produce low impurity plutonium. A report on the graphite matrix growth analysis test will be completed by mid-June 1970.

In FY-1970, the former ten missions which had existed under the Richland Five-Year 02 Research and Development Program were consolidated into four program areas as follows: Basic Production; Product Flexibility; Environmental and Regulatory Technology; and Waste Management. Each program area has included one or more separate distinct programs, some of which were basic to sustaining and improving production operations while others were directed to broadening plant versatility for producing potentially marketable products. Midway through FY-1970, the shutdown of KW Reactor with subsequent curtailment of funding resulted in a substantial reduction in the level of effort in both of these directions. Consequently, during the balance of FY-1970 improvement effort has primarily been concentrated on N Reactor operation, and plant versatility effort was virtually stopped. The research and development reported herein represents progress made during the period January 1, 1970, through May 30, 1970, and, contrary to recent annual and semiannual reports, includes only that work primarily funded with 02 R&D funds. No process technology funded activities are included, these being reported regularly in Douglas United Nuclear Monthly Reports.

An analytical parametric study was made of an infinitely long, cylindrical fuel capsule containing thulia (Tm/sub 2//sup 170/O/sub 3/) encapsulated in two different physical forms and in two different liner configurations. Diameters of wafers maintained at 0.060 inch thickness were varied between 0.6 and 3.0 inches. Radial temperature profiles were determined for thulia power densities ranging from 8 to 24 W/cc and fuel capsule surface temperatures ranging from 1000 to 2732/sup 0/F. Hastelloy-X, Haynes-25, T-222, tungsten, platinum and molybdenum are the liner materials investigated. Methods of calculation, (including computer codes), assumptions used, error analyses and results are presented and discussed.

Procedures are presented for the following: Tm/sub 2/O/sub 3/-Yb/sub 2/O/sub 3/ pseudo - binary phase diagram tests; compatibility tests; thulium-170 oxide dose rate measurements; preparation of Tm/sub 2/O/sub 3/ wafers; SRL thulium and/or ytterbium oxide powder reprocessing for sintering; cold pressing and sintering thulium oxide wafers; preparation of thulium and/or ytterbium oxide powder via precipitation with oxalic acid, ammonium oxalate, urea and methyl oxalate; determination of the total surface area of rare earth oxide powders; determining oxygen in thulia - thulia/ytterbia for the purpose of determining metal-to-oxygen ratios; and determination of the impact resistance to fines generation of sintered rare earth oxide.

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An evaluation is presented of the media/method (Phase I) and the system concept (Phase II) to be used for the efficient storage, retrieval and transmittal of data. These data include drawings, parts lists, specifications, data items, test information sheets , variation requests, DRMs, PMDs, non-conforming matieral discrepancy reports, ERCOs, ECPs, etc.

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The authors have measured the asymmetry in the cross section for the reaction {gamma}p {yields} {pi}{sup +}n between the two stages of polarization of the initial proton normal to the plane of scattering. The initial laboratory photon energies, k, were 5 GeV and 16 GeV, and the regions of momentum transfer, t, covered were 0.14 {le} {radical}-t {le} 1.01 GeV/c and 0.14 {le} {radical}-t {le} 0.78 GeV/c respectively. A butanol polarized target was used with the SLAC 20 GeV/c magnetic spectrometer. The data show a sizeable asymmetry at both 5 GeV and 16 GeV. The 16 GeV data peak at {radical}-t {approx} 0.30 GeV/c with an asymmetry of about -0.70, and the 5 GeV data pak at {radical}-t {approx} 0.80 GeV/c with an asymmetry of about -0.70. The direction of our normal to the scattering plane is along (photon in) x (pion out).