Separate abstracts have been prepared for 19 sections of this report. (For preceding period see ANL-6104.) (C.H.)

Twenty-four experimental alloys were developed and evaluated as container materials or welding alloys for use with Sulfex and Niflex decladding solutions. Niflex solutions which were more corrosive than Sulfex solutions to most of the experimental alloys, produced severe localized attack on weldments made on vacuum-melted Hastelloy F with the experimental alloys. However, several of the alloys, when self-welded, were not selectively attacked. Some of these showed a substantial improvement in resistance to the decladding solutions. The most promising alloys were based on either 45 wt.% nickel--22 wt.% chromium or 50 wt.% nickel--25 wt.% chromium, with at least 6 wt.% molybdenum, and 1 wt.% titanium, 0.6 wt.% manganese, 0.4 wt. % silicon, 0.02 wt.% carbon, and the balance, iron. The alloy most resistant to both solutions contained 6 wt.% molybdenum and 1 wt.% copper in the 50 wt.% nickel--25 wt.% chromium base. Its corrosion rate of 22 mils per month in Niflex, with no selective attack, was significantly lower than the 105 mils per month recorded for Hastelloy F. Even lower rates would be expected under the less stringent conditions of actual process operation. Indications are that more resistance might be obtained by increasing the chromium and nickel contents. (auth)

There is a need for a special type of nuclear reactor that can test fuel elements nondestructively to determine the total amounts and the distributions of both fissionable and parasitically absorbing materials in completed, unirradiated fuel elements. Such a reactor, called the Fuel Assay Reactor, is proposed. Theoretical considerations are presented to show the reactivity changes that result from the insertion of both fissionable and absorbing material into a central test hole. The choice of moderator depends upon the size of material to be tested. For testing small pellets of fissionable material, a light-water- moderated assembly is advantageous because of its small critical mass; for large, completed fuel elements a graphite or heavy-watermoderated system is more suitable. An internal reflector gives increased sensitivity in the center and allows enough space surrounding the test element so that spectral changes in a nonfuel region may be produced in order to discriminate between fissionable and absorbing materials. The factors determining maximum sensitivity are discussed, as are several reactivity measurement methods suitable for testing fuel elements. The limits of accuracy are governed by the statistical variation of the neutron population within the reactor core. The theoretical limits of accuracy of all methods have the …

The selective removal of halide fission products from an aqueous solution by exchange with the halide in a solid silver halide was studied as the basis for a fuel-element leak detector. The retention of fission-product halides on a silver halide column was investigated as a function of coolant flow rate, halide anion, and column size. Fission prcduct decontamination factors and predicted operating lifetimes were obtained for a number of reactor operating conditions. It is concluded that a sensitive, rapid leak detector for a water- cooled reactor could be constructed from a silver bromide or iodide column monitored by a neutron detector to detect delayed neutrons from the halide fission products. The feasibility of gross gamma monitoring was found to be dependent upon the intensity of the gamma background arising from absorbed fission products on the silver halide column. (auth)

The fluorination of uranium from dried solids representative of those obtained from the fluid-bed drying of dissolver solutions of high zirconium alloy fuels. e.g.. Dresden and Army Package Power Reactor fuels, was studied under a variety of conditions. Variables investigated were particle size, additives, temperature, time. hydrofluorination, and pyrolysis. Temperatures in excess of 650 deg C were needed to ensure complete removal of uranium from the solid. Pyrolysis with HF of previously fluorinated materials aided in uranium removal from the zirconium solid. (C.J.O.)

Supercritical water-reactor design studies are reviewed. The status of supercritical water technology relative to heat transfer and fluid flow, water chemistry, internal deposition on heated surfaces, plant power cycles, and reactor construction materials is reviewed. The direct cycle was found to offer the highest probability for achieving economic power. (C.J.G.)

The irradiation of highly enriched Ca/sup 48/ CO/sub 3/ with a bremsstrahlung beam of maximum energy 46 Mev produced Ca/sup 47/ with a yield of 1.1 to 3.0 mu c/mg Ca/sup 48/ at half saturation. The half life of a sample measured through aluminum absorber to eliminate the contribution by the Sc/sup 47/ daughter was 4.51 plus or minus 6.02 days. By comparison with the Cu/sup 63/ ( gamma ,n)Cu/sup 62/ reaction the integrated cross section from 0 to 46 Mev for the sum of the reactions Ca/sup 48/( gamma ,n)Ca/sup 47/ and Ca/sup 48/( gamma ,p)K/sup 47/ was calculated to be 29 Mev-mbarn. The Ca/sup 45/ content of the sample calculated to the end of the bombardment was approximately 0.04%, probably the result of the Ca/sup 48/( gamma ,3n) and ( gamma ,p2n) reactions. (auth)

Results of a conceptual design study for a curium powered thermoelectric generator of minimum size and weight which is capable of sustaining hard impact is presented. The generator produces a minimum of 13 watts of d-c power at 3 volts, and weighs 6.2 pounds excluding shielding. (J.R.D.)

SNAP III, a 3- to 5-watt electrical generator, was designed as a proof- of-principle device in the development of radioisotope-powered thermoelectric power-conversion systems. A program involving five development areas was employed in achieving this aim. These areas were: (1) generator development, fuel encapsulation, and handling techniques; (2) system safety studies; (3) system dynamic tests; (4) system parametric performance tests; and (5) system life tests. Particular attention was given to fuel encapsulation and handling techniques, system safety studies, system parametric performance tests, and system life tests. (auth)

None

"Investigations into the behavior of the gas flow behind spherical or cylindrical blasts have shown that secondary shocks arise within the original detonation gases. The secondary shock, at first weak, is carried outward with the expanding gases. Subsequently it strengthens and bends back toward the origin, arriving there with high intensity. By using some recently developed techniques in shock dynamics a theory is developed by which the motion of the main shock wave, as well as the formation and subsequent motion of the secondary shock, are given by explicit formulae."

From Forward: "Although the first paper in this volume describes the general aspects of the technical management of the program, it is important to emphasize that much of success and productivity of this program stemmed from the sympathetic understanding of its basic viewpoint by both the Department of Defense and the National Bureau of Standards."

The principal types of particle accelerators are described briefly according to operation and history. Known operating particle accelerators are listed with their pertinent dimensions.

Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.

A prccedure is described for designing and making logarithmic spiral light pipes which are to be used in coupling scintillators to photomultipliers in cases where the scintillator must be placed in a strong magnetic field. (C.J.G.)

"Recent theoretical advances in describing the nucleon-nucleon interaction (particularly in the T=1 state) have emphasized the importance of obtaining an unambiguous experimental determination of the scattering matrix so that the nuclear phase shifts and details of the nuclear potential may be revealed. It is possible to select five experiments, the results of which, in principle at least, determine the scattering matrix and phase shifts uniquely at one energy. Two of these experiments, the cross section and polarization over the angular range of 0 to 90 degrees in the center of mass system, have been made at the University of Rochester at a laboratory energy of about 210 Nev."