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<><DSN>16:009503<ABS>Included are summaries of studies of: DCX-1 operation and performance; DCX-2 design and engineering; plasma physics; vacuum arcs; ion production, acceleration, and injection; plasma theory and computations; magnetics; and vacuum system techniques. Separate abstracts were prepared for the eight sections. (B.O.G.) 9504(Faye unscannable abstract)

A dry criticality test was carried out to determine the minimum critical mass of the HNPF Core without sodium. A subcritical calibration of the central control rod was performed and the relative reactivity worths of the inner ring of six control rods were determined. The extrapolated critical loading for the various plots after each incremental fuel loading with all rods out is shown. A tabulation is presented of multiplication data taken throughout the dry critical test. In order to find the relative integral reactivity worth of the central control rod in the dry critical loading, subcrltical multiplication data were obtained. The test completion criteria as stated in the test procedure were met. (M.C.G.)

Progress in nuclear safety research and development is reported. Topics covered include: reactivity effects of fuel displacements in a pool-type reactor, release of fission products on out-of-pile melting of reactor fuels, release of fission products on in-pile melting of reactor fuels, fission product transport evaluations, characterization and control of accident-released fission products, nuclear safety pilot plant, preparation of reactor containment hardbook, and radiochemical plant safety studies. (M.C.G.)

The object of this test was to obtain data concerning the reactivity of the horizontal rods in the E-N fuel loading at H Reactor. An accurate calibration of the control rods could then be used to provide a more accurate measurement of the other reactivity variables associated with the E-N loading. A comprehensive rod calibration test was performed at H Pile in 1957. Results of the present test, needed because of the ``blacker`` E-N fuel in the pile, have been normalized to the 1957 test results and extrapolated to a full-system calibration. Two short tests were carried out for this purpose: (1) a scram transient test, and (2) a modified rising period calibration test.

This report explains a mathematical algorithm designed to complete contour descriptions of weapon components which have been only partially specified by free-form data.

Hanford production reactor operation requires the rejection of very large heat loads. At the present time the heat load is rejected to the Columbia River by the reactor effluent. At low river flows the hot effluent can have appreciable effects on river temperatures. The purpose of this study is to evaluate the feasibility and costs of Cooling Towers as a means of reducing the heat load rejected to the Columbia River. After evaluation of published information, available data, and Hanford plant conditions, it is concluded that: (1) That an induced draft cooling tower, because of its longer cooling range,, would be an effective cooling device for reduction of gross heat load rejected to the Columbia River. Additional study will be required to determine effective use on an area to area basis. (2) That a basically wood, counter-flow, induced draft cooling tower could be installed for approximately $1600 to $2000 per megawatt capacity. This cost is a probable minimum and might be increased by the cost of auxiliary features required for radiation control. (3) That additional study and developmental testing would be required to determine the extent of contamination problems which would result from the cooling tower installation. These problems would …

A continued decrease in flow measured during the periodic high velocity flushes indicated that corrosion buildup in the high tank discharge lines was deceasing backup flow to the reactor. An accurate determination of the high tank flow rate to the reactor was needed to evaluate present back-up adequacy. Riser pressure and flow rate were also measured with throttled high tank discharge lines to establish the low flow and critical portion of the reactor hydraulic characteristic curve. This report presents the numerical results of the test conducted on October 4, 1962.

The inherent stability of the EOCR at full power, exclusive of the heat exchanger, is investigated. Space and time dependent differential equations and transfer functions for the nuclear and thermal processes occurring in the reactor core and vessel are derived. Reactor stability is analyzed by application of the Nyquist stability criterion. The results show that the EOCR has an extremely large margin of inherent stability. (auth)

A total of seven papers is presented. Separate abstracts have been prepared for five papers; the other papers were abstracted previously in NSA. (R.J.S.)

>Brief summaries are presented on isotopic dilution studies on salts dissolved in JCH/sub 3/OH, studies on metal and metal salts in solvents of the amine type, and studies on phosphato complexes of the pentammine Co(III) series. A list of papers published on reactions of solvated ions is included. (N.W.R.)

Annealing beta-heat-treated production-size dingoturanium core blanks in the high alpha range (1150 to 1200 deg F) produced a fine, equiaxed grain size by a recrystallization process. The extent of recrystallization is dependent upon the rate of cooling through the beta-to-alpha transformation, the time and temperature of annealing, and whether or not impurities that retard grain growth are present. The cooling rate through the beta-to-alpha transformation was varied by using a range of beta temperatures and air cooling times prior to quenching into water. Longer air cooling times are permissible at the higher beta temperatures; however, the greatest amount of induced lattice strain was obtained after an air delay of only 2 seconds before quenching. Decreasing the annealing temperature results in a corresponding increase in the annealing time required for an equivalent amount of recrystallization. A second phase, present in the alloyed dingot metal, inhibited recrystallization and grain growth. Alloyed metal recrystallized progressively from the outer periphery to the center of the core, whereas unalloyed metal subjected to identical annealing conditions exhibited recrystallized grains throughout the cross section. A reduction in grain size from 0.38 mm to 0.25 mm occurred in a beta-treated, unalloyed core after annealing at 1200 deg F …

Boron carbide-graphite nuclear control-rod materials containing up to 45 wt% B were prepared by hot-pressing techniques. The densities of these compacts decreased with increasing B content. Compact strengths, however, were noticeably increased with B content of 20 wt%, suggesting that the B acts as a sintering aid. Thermal stability was evaluated by annealing compacts under a variety of temperature and atmospheric conditions. The upper limit of the ioss of 13 was 5% to 10%~ in 200 hr at 2000 deg C--considerably less than would be predicted from the Langmuir evaporation equation. Diffusion of B atoms through the pores of the graphite, rather than evaporation from the surface, was found to be the rate- controlling step in the loss of B. Compacts containing 20, 30, and 40 wt% B were irradiated at 350 and 700 deg C to 1.0 and 2 4 x 10/sup 21/ nvt(fast). Physical integrity of the compacts was good after irradiation. Slight increases in tensile strength were noted in several instances. (auth)

Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in determination of dissolution rates over a wide range of conditions. The addition of oxidants to 4.8M hydrofluoric acid used for the continuous dissolution of 3% uranium-Zircaloy- 2 fuel decreased the amount of uranium-containing residue in the dissolver at the expense of a decreased dissolution rate. Oxidized fuel was dissolved in 4.8M hydrofluoric acid by use of heat to initiate the reaction: the oxide film remained behind as a dissolver residue. Uranium in the dissolver product was oxidized to the extractable form by one minute treatment at 92 deg C with aluminum nitrate complexer solution: only 59% was extractable after 24-hour treatment at room temperature. Several hundred hours operation of a continuous bench scale unit indicated that uranium buildup should not be a problem in the dissolver since an apparent equilibrium was soon established. After 650 hours of operation, a Monel dissolver showed some signs of localized corrosion but exhibited generally good resistance. Preliminary results in a study of aluminum alloy dissolution rates, initiated because of unusually slow dissolution of certain aluminum-based fuel elements, …

This report addresses the analytical chemistry of Cobalt.

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This report addresses command links.

This memorandum describes studies undertaken to investigate the properties of Tory II-C with the aims of reducing weight and size and in increasing performance. Space and weight limitations aboard existing sea-going launch vehicles required this general parameter study which utilizes a bare, cylindrical reactor having the same materials as Tory II-C.