The following document describes the usage of the LRL 9-ZOOM code, a neutron diffusion theory reactor code for the IBM 709. The code has been modified to solve configuration of a series of stacked cylindrical disks, designating a new geometry case.

A solid-state bonding technique involving the use of gas pressure at elevated temperatures was utilized for the self-bonding of molybdenum and niobium. Bonding conditions and surface preparation as a function of the integrity of the bond achieved were evaluated for each material. Optimum self-bonding of niobium was achieved by bonding parameters of 2100 to 2300 deg F at 10,000 psi for 3 hr with surfaces which had been prepared by etching in a nitrichydrofluoric acid solution prior to bonding. The process as developed was used to prepare niobium- clad flat-plate- and rod-type fuel elements and flat-plate subassemblies. Niobium tubing was also fabricated by this technique. (Molyb denum self-bonding was most readily achieved by gaspressure bonding at temperatures of 2300 to 2600 deg F at 10,000 psi for periods of 3 hr. With these bonding conditions a number of different surface preparations were satisfactory. Directional ductility of the molybdenum was encountered after bonding and methods to eliminate this were evaluated. Cross rolling with respect to the original rolling direction was shown to improve the ductility of molybdenum-clad specimens. (auth)

An economical process was successfully demonstrated in bench-scale continuous equipment for stripping U from amines with ammonium carbonate solution. A continuous countercurrent mixer-settler extraction system was set up for further testing of the process for recovery of Te, Np, and U by tertiary amine extraction from UF/sub 6/ transfer cylinder was solutions. The effect of Purex aqueous feed adjustment procedures on Pu extraction by 1 M di-secbutyl phenylphosphonate (DSBPP) was studied. Work was continued on plutonium(IV) nitrate extraction with TBP and phenylphosphonate esters. The response of Ru/sup 106/ extraction to variations in the treatment of TBP-Amsco 125-82 solvent was tested. Two solvents have shown ability to extract cesium. (For preceding period see CF-80-3-136.) (W.L.H.)

This specification covers the design, fabrication, testing and furnishing of two fire pumps complete with drivers and appurtenances.

Applications of sheathed (metal) thermocouples may require in many instances, the insertion of the thermocouple thermal junction into an area that must be hermetically sealed to the outside. This same area usually contains highly reactive heat transfer medium such as an eutectic alloy of sodium and potassium of sodium alone. When fissionable materials are being irradiated, fission products that are driven off would also be present and must be contained under varying temperatures and pressures.

The investigation of the stabilizing influence of oside additions to UO/ sub 2/ was continued. The effects of fast-neutron irradiation upon the mechanical properties of Type 347 stainless steel are being investigated. Tensile data are reported for alloys of Nb-Cr and Nb-Zr. The major effect of fast-neutron irradiation on the creep properties of Zircaloy-2 is being studied by comparing the in-reactor creep behavior of the alloy with out-of-reactor creep properties. New methods for the determination of low concentrations of oxygen in sodium are being investigated. The mechanisms of wear and friction of various metals in sliding contact in liquid sodium are being studied. Data are presented on corrosion properties, short-time tensile properties, stress-rupture properties, and electrical resistivity for Nb--U alloys. The development of Th and Th--U alloys with improved radiation resistance is being investigated. A program is reported for the determination of diffusion coefficients of Xe in single-crystal UO/sub 2/ specimens and the in-pile study of fission-product release from sintered UO/sub 2/. Thermal-conductivity, thermal-expansion, electrical-resistivity, and modulus-of-rupture measurements are being made on 80 vol.% UO/sub 2/ cermets. Techniques for the fabrication of compartmented Mo- and Nbclad UO/sub 2/ and cermet fuels are being investigated. Compaction studies of UO/sub 2/ were …

The Plutonium Recycle Test Reactor is heavy water moderated with a heavy or light water reflector contained by a complex aluminum vessel called a Calandria. ( See Figure 1). Construction of this vessel started in August, 1958, at a large West Coast vendor's plant and was completed at Hanford in December, 1959. The fabrication problems associated with a high integrity welded aluminum vessel were generally unrealized prior to this period. This report covers the fabrication of the Calandria and lists recommendations for improving the design and reducing the cost.

This semiannual progress report and future reports will be published as two documents to permit a wider distribution of the unclassified material. The report numbers are assigned in sequence so that the two reports will fall together when filed by report number.