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Attached to this report is a letter from Raymond R. Schiff, containing pertinent information, dated Jan. 28, 1957. 2p. (WAPD-S5W-NA-1451. The input for the program includes radial and axiai power distributions and rules for combining them into three-dimensional power distributions, radially and axially variable local peaking factors, engineering hot channel factors, and geometrical data. The output consists of the average inlet and outlet temperatures for each pass, the maximum relative heat flux, outlet temperature, surface temperature, and normal channel temperature rise in each pass together with the location of each of these maxima and the heat flux distribution in each channel where one of the maxima occurs. The program allows very rapid evaluation of these quantities and permits calculation without the simplifying approximations usually involved in hand methods. The program was successfully applied to S5W problems and requires from 3 to 5 minutes of machine time for solution of a full-scale case. (M.H.R.)

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The electrolytic polishing of uranium-rich U-Nb and U-Zr alloys was investigated. The Disa-Electropol'' electrolytic polisher was used in the tests with the electrolyte being a mixture based on perchloric acid and alcohol. The effects of the polishing time and the potential used and the relationships between voltage and time and between current and voltnge were determined for U-Zr alloys. The results showed that the electrolyte used gave relatively goed results for U-Zr alloys. The same technique was applied to Nb-U alloys, but poor results were obtained. (J.S.R.)

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This report discusses production testing of dingot material. Advantages and disadvantages of uranium produced by the dingot process are noted.

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This paper presents, in two parts, a general discussion of fused-salt heat transfer. The first part is a report on current experimental results with three new salts - an alkali metal-base fluoride, a zirconium-base fluoride, and an alkali metal nitrate-nitrite mixture known as 'HTS'. In the second part fused salts are compared with liquid metals on the basis of their heat transfer effectiveness as reactor coolants. An analysis is presented for a general solid fuel-element reactor which transfers its heat to a fluid boiling on the outside of the heat exchanger tubes. The results show that fused salts can be as good heat transfer media as liquid metals. (auth)

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The spectrum and yield of internal bremsstrahlung accompanying electron capture form S- and P-states in sb119 were measured and compared with the theory of Glauber and Martin. sb119 was obtained as the daughter from el l9 produced by the ~b(dx,n )~ell9 and Sn(a, xn)~ell9 reactions. The decay is by orbital electron capture to the 23.83-key state in Sb¹¹⁹. The following results were obtained: Sb¹¹⁹ half life, 38.0 hr ; Sb¹¹⁹ -Snl l9 decay energy. 579 f 20 kev; half life of the 23 83-kev state and its total conversion coefficient, 1.85 t 0.1 x 10"; sec and 6.3 * 0.4. respectively. The intensity of internal bremsstrahlung for capture from S-states was 1.06 + 0.15 x loo4 quanta/ K-capture. This agrees with the theoretical prediction of 0.97 x loo4* The large contribution at low energies from P-etate capture was measured down to 70 kev and agrees with the theory in its present state of completion.

The results of two test runs conducted with surfaceconditioned fuel fillers are reported to evaluate the effect upon diffusion zone thickness, bond strength, and corrosion properties of Zircaloy-2 clad U--1O wt.% Nb. Results indicate that there is no significant effect of fuel surface condition upon diffusion zone thickness. The bonding interface of the rolled fuel element has greater strength than either the clad or the rod. The corrosion data were inconclusive because of the small number of tests, the uncontrolled variables, and the erratic corrosion properties of the particular U-- Nb alloy used. (L.T.W.)

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Tests of materials for use in liquid-metal and fused-salt systems were continued. Corrosion tests, penetrability tests, thermal tests, and solubility tests were conducted on structural alloys, brazing alloys, special alloys, cermets, carbides, nitrides, and rare-earth oxides. Progress in loop design and testing is reported. Hastelloy W creep and stress testing and general welding and brazing tests and investigations are reported. Development work is reported in nickel-molybdenum base alloys and iron-zirconium alloys and the fabrication of control rods. Research in the physical chemistry of corrosion, fundamental and applied metallurgy, and ceramics is reported. Development of alloys, fuel assemblies and fuel alloys, and brazing and welding techniques for the Homogeneous Reactor Project (HRP) and the Army Package Power Reactor (APPR) and testing of these materials in the Materials Testing Reactor (MTR) are described. (W. L.H.)

The feasibility of discharging radioactive wastes into underground formations is dependent on the predictability of the movement of certain hazardous radioisotopic components. This progress report examines several theories concerned with the equilibria and kinetics of ion-exchange as they apply to estimating the rate of underground movement of radiostrontium. Laboratory studies were conducted with the objective of testing the applicability of these theories to estimating the displacement and dispersion of radiostrontium fronts in natural media. The porous media studied with both hntch and column systems included several connate-water bearing sands, an agricultural soil, and a standard halloysite clay. The parameters investigated were the exchange capacity, various expressions of equilibria, the influence of calcium, sodium, and hydrogen ions on the rate of strontium movement, the hydraulic rate of liquid application, and the rate coefficients controlling the ion-exchange reactions. The results indicate that a proper application of existing ion-exchange theory will greatly reduce the uncertainties in estimating the rate of radiocontaminant travel through natural media and may ultimately provide criteria for the design of subsurface disposal systems. (auth)

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The program presented is for use with the IBM-650 computer. (D. E.B.)

Research is reported in the development of materials for Hanford reactors, development, of Al-clad fuel elements. plant assistance to MCW, reactions between HiO and Zr alloys, general fuel element development, Zr --U alloy studies, corrosion of Zr, reactor materials development, physical metallurgy, development of PWR, and Na-- Ta compatibility at high temperatures. (T.R.H.)

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Natural U plates that were irradiated to 600 and 1500 Mwd/t were cut under water by a guillotine-iype shear. Irradiation reduced the force required for shearing to 50% of that required for unirradiated U. Measurements were made of radioactivity released to treated and untreated water in which the cut sections were stored. (auth)