This report addresses the contributions by the Atomics International to the 24th High Temperature Fuels Committee Preliminary Information.

Work that has been carried out in several areas of High Energy Physics is described. Visual techniques are used. For the study of the three-pion decay of the K/sup +/ meson, bubble chamber and emulsion methods are used to complement each other, particularly for the tau' mode. Several separate bubble chamber experiments in ..pi../sup +/p, anti pp and K/sup -/p interactions are also described, and the large effort devoted to computer reprogramming for the data analysis indicated. Two emulsion research projects are also described which have for their purpose the study of electromagnetic processes induced by 16 BeV electrons and the study of hypernuclei by K/sup -/ mesons. For the latter work high speed computer methods have been successfully applied to the analysis of the product hypernuclei. These programs of work have not been under way long enough for the main results yet to be available, but some preliminary data have been published and several reports on data analysis and related subjects have been prepared.

This program on electron radiation damage in metals have included studies of the recovery spectrum of stage I for aluminium. Radiation doping was studied. (DLC)

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This report itemizes the irradiations performed by Testing for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

Work is reported in these areas: general radiation effects; toxicity of radioelements; studies at the molecular and cellular levels; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.

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The production reactors operated by Douglas United Nuclear, Inc., use treated Columbia River water as the coolant on a once through basis. Thus, radionuclides formed largely by the neutron activation of river salts are discharged to the river. One method of reducing the quality of radionuclides in the effluent is to increase the efficiency of parent isotope removal during the water treatment process. Prior to 1961 the water treatment process for preparing reactor coolant had been improved to the point that reactor quality coolant could be produced using an average alum flocculent feed rate of 6 ppM. Laboratory experiments carried out in 1959 and 1960 demonstrated that a markedly increased removal of parent isotopes resulted when alum feed rates in the neighborhood of 20 ppM were used. The results were confirmed by two half-plant tests of short duration in July, 1961, all water treatment plants began to use alum at a somewhat arbitrarily selected rate of 18 ppm. The practice Continues to date at all plants except at the K Reactors. The K Reactor alum feed has been limited to a nominal 15 ppM because of the high filtered water requirements. The use of the high alum feed rate did …

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A half reactor test was initiated at B Reactor on February 1, 1967, to determine whether the concentration of P{sup 32} and As{sup 76} in the reactor effluent water would be reduced by the addition of activated alumina in the water treatment process. This test was prompted by the reported effectiveness of activated alumina in sorption of phosphates when water flow is through a packed bed of this material. Although direct feed of material would not be expected to be as effective, testing of this possible approach appeared warranted. This report summarizes the results of this test. Samples taken from each effluent riser during reactor operation indicated no improvement in either As{sup 76} or P{sup 32} performance. This comparison is shown below with a complete tabulation of daily values included as Attachment 1.

Declassified 5 Sep 1973. A reactor configuration and operating conditions are selected for a 200 kW(e) Brayton cycle space power system as a reference point for the 710 Reactor fuel systems development program and for studies of the effects of the reactor and space power system designs on the 710 Reactor fuel system. (auth)

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Declassified 21 Sep 1973. A wide range of metallic hydrides (to NH 9.0), each containing additives to tailor the nuclear characteristics, have been fabricated successfully. Specific additives have included B compounds and high Z- material compounds, e.g., W, Hf, Th. Hydrided Ti which contains B compounds has proven relatively easy to fabricate and has shown excellent radiation stability. Post-irradiation appearance (through 6 x 10/sup 20/ nvt thermal) shows no visible changes. Strengths to 150,000 psi at 380 deg C (with ductile failure) have been observed for TiH. Sound, massive N/sub H/ 6.9 hydrided Zr rods have been fabricated in hydride-furnace batches as large as 50 kg, with 100% yield. A 50 Th-50 Zr hydride of N/sub H/ 6.7 and higher has been fabricated. The basic structure, apparently ThZr/sub 2/H/sub 8/, is a cubic spinel-type structure and is the first reported hydride having this structure. This material, when containing a B compound additive, will probably provide more gamma shielding than is generally needed, but the material has interesting possibilities as a combination breeder-blanket-shield. It now appears that almost any combination of looked-for nuclear properties can be incorporated into a metallic hydride composite having useful engineering characteristics. (16 tables, 23 figs) (DLC)

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This report gives the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. These data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.

This report lists the bound periodicals in the Technical Library at the Pacific Northwest Laboratory, operated by Battelle Memorial Institute. It was prepared from a computer program and is arranged in two parts. Part one is an alphabetical list of journals by title; part two is an arrangement of the journals by subject. The list headings are self-explanatory, with the exception of the title code, which is necessary in the machine processing. The listing is complete through June, 1966 and updates an earlier publication issued in March, 1965.

This report presents details of the activities of Douglas United Nuclear at the Hanford site during the month of April 1967.

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