Results of studies with ZPR-IH Assembly 29, a mockup of a typical, dilute UO/sub 2-/-fueled fast reactor, are reported. The assembly consisted of a 454-liter cylindrical core, blanketed with depleted uranium, with a critical mass of 42l kg U/sup 235/. Experimnents included measurements of fission rates, material reactivity worths, and Rossi alpha. The results of multigroup calculations using the present Argonne cross-section sets are presented, and discrepancies between experimental results and calculations are discussed. (auth)

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Separate abstracts were prepared for 10 papers presented at this meeting. (C.H.)

A study was made of approximately 132 reports on gascooled reactors and related subjects. Charts and tables containing the following information are included: all available reactor information, reactor flow diagrams of suggested concepts, possible core arrangement at core cross section, typical fuel and moderator cell. possible fuel types for unit fuel cell, the properties of materials for moderators and reflectors. the compatibility of gases and base fuel materials at maximum surface temperatures, maximun interfacs temperatures of fuel elements and core-jacket combinations, allowable operating temperatures and compatibility of gases and various metals. prefenences for gas coolants, cost and availability of gases plant thermal cycle efficiencies, thermal properties of gases, pumping power and reactor coolant inlet temperatures, obtainable heat fluxes, composition and physical properties of potential cladding materials. atomic and themal properties of cladding materials. fabrication characteristics and costs of cladding materials. possible process applications of gases at high temperature, and potential high-temperature materials. The various categories of gas-cooled reactors and examples of each type are discussed. A gas reactor program for high-temperature experimentation is proposed. (M.C.G.)

A fuel element, consisting of a cluster of stainlesssteel-clad sodium- bonded, U - 10 wt.% Mo fuel rods, has been proposed for the first core loading in the Hallam Nuclear Power Facility. Analytical data on density, soundness, chemical composition, dimensions, and surface finish were obtained from more than 100 heats of fuel slugs which were vacuum cast in graphite molds. The quality levels obtained were satisfactory, and casting was proven to be a feasible fabrication method for U - 10 wt.% Mo fuel slugs. Extrusion and liquid pouring were both investigated as methods of handling sodium to bond fuel rods. The extrusion technique was shown to be impractical because of difficulty in supplying a sufficient volume of sodium to fill the rod. Satisfactory bonding was obtained using the liquid technique. Two full-scale fuelelement mock-ups were fabricated. Each element contained 19 fuel rods located by spacers made from spot welded strips and enclosed in a process tube. Assembly problems encountered in the first mock-up were corrected by modifying the fuel-rod spacers. Methods were developed for safe handling of the fuel rods and other long (15 ft) components. The second mock-up demonstrated that the fuel element was suitable for fabrication and assembly. …

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The results of a study are presented which provided additional experimental-loop irradiation space for the AECDRD testing program. It was a premise that the experiments allocated to this reactor were those which could not be accommodated in the MTR, ETR, or in existing commercial test reactors. To accomplish the design objectives called for a reactor producing perturbed neutron fluxes exceeding 1O/sup 15/ thermal n/cm/sup 2/-sec and 1.5 x 1O/sup 15/ epithermal n/cm/sup 2/-sec. To accommodate the experimental samples, the reactor fuel core is four feet long in the direction of experimental loops. This is twice the length of the MTR core and a third longer than the ETR core. The vertical arrangement of reactor and experiments permits the use of loops penetrating the top cap of the reactor vessel running straight and vertically through the reactor core. The design offers a high degree of accessibility of the exterior portions of the experiments and offers very convenient handling and discharge of experiments. Since the loops are to be integrated into the reactor design and the in-pile portions installed before reactor start-up, it is felt that many of the problems encountered in MTR and ETR experience will cease to exist. Installation of …

The final design of the operating control rods for the Enrico Fermi Atomic Power Plant was completed. Two such rods are located near the center of the reactor, which is sodium cooled. Boron carbide is used as poison material. A flow distribution test and analysis, thermal analysis, and stress analysis of the rod were performed for both the normal operating and scram conditions. The test and analysis show that the design meets APDA specifications. (auth)

The distribution of the kinetic energy of fragments emitted as a result of the neutron-induced fission of Th/sup 232/ has been determined. Incident neutron energies of 1475 plus or minus 35 kev and l600 plus or minus 35 kev were used. The distributions determined at the two incident neutron energies are identical. The measured total average fragment kinetic energy was l55 plus or minus 4.5 Mev. The most probable fragment mass ratio is 1.47 plus or minus 0.05, and the average kinetic energies of the light and heavy fragments are 95 plus or minus 2 and 60 plus or minus 3 Mev, respectively. The experimental results were related to the known systematics of neutron-induced and spontaneous fission. The effect of collective nuclear rotations at the saddle point is discussed, with particular emphasis on fission from specific rotational bands. (auth)

The objective of the program is to determine the effect of variations of aluminum content, heat treatment, surface preparation, and other metallurgical factors upon the room-temperature ductility of Fe-- Al alloys. As a continuation of the metallographic deformation studies, two coarse-grained tensile specimens of 13.9-Alfenol were heat treated, electropolished, and pulled to fracture. (W.L.H.)

Uranium dioxide clad with Type 304 stainless steel was fabricated into rod, tubular, and flat-plate shapes by the gas pressure-bending process. Modifications of these basic designs included compartmented rods, corrugrted rods, and compartmented plates. The cold-compacting behavior in methods other than direct cold pressing and the pressurebonding behavior of seven commercial oxides and various mixtures were defined. Through the selection of initial oxides and compacting procedures, final oxide densities of 86 to 99.5% of theoretical were achieved. It was noted that the oxides tend to approach stoichiometry during the pressure-bonding process. Permeability measurements of high-density pressure-bonded uranium dioxide resulted in values that were within the blank rate of measuring apparatus, indicating equivalence to high-density sintering oxides. Thermal-conductivity measurements on similar materials also are consistent with high-density oxide as prepared by pressing and sintering. Of the oxides investigated, mixtures of ceramic and fused oxides appear to offer the most promise of achieving low-cost fuel elements through the pressure-bonding process. Such mixtures containing from 30 to 60 wt.% ceramic oxide provide a high initial pressed density and also permit achieving a high final density. Both oxides are low-cost materials. The preparation and pressure bending of uranium dioxidestainless steel cermets were also briefly …

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