The radiological aspects of a proposal to recover some of the heat now wasted in cooling water from the Hanford reactors by using the hot water as boiler feed for the steam plants in the 100 Areas are evaluated. The radioactive material in the hot effluent water will contaminate the boiler feed water system, cause additional radiation exposure of personnel, and increase the cost of maintenance and radiation protection, but very little radioactive material will be carried over into the steam system. At present steam loads, this proposal is economically attractive; other proposals being considered may nullify any savings from this one. 21 refs., 1 fig., 10 tabs.

Production Test 105--533-A and Supplements A and B which authorize an ``experimental area`` in C-pile in which the tube power limits are relaxed to allow tube power increases up to 16-2/3 per cent above the maximum allowed tube power outside of the experimental area. Supplement B (HW-28775) further limits the maximum tube power to 820 kw. The planned increase of tube powers at C-Pile (from 700 kw/tube to 800 kw/tube) for the tubes outside of the experimental area will cause the experimental area to operate at tube powers up to 935 kw.

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During the exploration of the possible use of an extraction process for the separation of gaseous cascade impurities from uranium hexafluoride, a number of short exploratory studies were carried out. These included (1) experimental determination of the vapor pressure and liquid density of perfluorodibutylcylicether, (2) calculation of the liquid vapor-equilibria of the systes perfluoro-n-pentane-uranium hexafluoride and 1,2-dichlorohexafluoropropane-uranium hexafluoride, and (3) derivation of equations for the estimation of activity coefficients in ternary systems from the properties of the pure components. The results of these studies are summarized in this report.

A large number of experiments relating to nuclear structure and materialization of energy will fall within the energy range of primary and secondary particles available from the Bevatron. Some experiments of interest are outlined below with pertinent comments. Proton-proton scattering can be extended to the high energy range using liquid hydrogen targets and hydrogenous materials by bombarding the target with the internal beam or using externally scattered protons. Proton-deuteron scattering measurements using liquid deuterium targets or solid materials can also be extended. Proton scattering from heavier nuclei may be found less difficult to interpret at these level energies as the nucleons will interact more or less independently. The wavelength of the bombarding particles will now be much smaller than nucleon diameters. Nuclear collisions represent by far the most important interaction between high energy nucleons and matter. Proton-neutron charge exchange interaction within the internal target will provide an external flux of neutrons which can be used directly for total nuclear cross section measurements and neutron-proton scattering. Low energy measurements, say below 200 Mev; show that nuclear interaction cross sections do not go down as 1/{lambda} as reactions become predominantly nuclear rather than electromagnetic. Measurements can now be extended into the Bev …

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Processes for preparing a suitable ThCl/sub 4/ electrolyte free of H/sub 2/O and C/sub 2/ were investigated including chlorination with C -Cl/sub 2/, sulfur chlorides, NaCl, and preparation from anhydrous solvents. The method selected consisted of reacting ThOCO/sub 3/ with HCl, adding NH/sub 4/Cl, and heating in inert atmosphere to drive off NH/sub 4/Cl. (T.R.H.)

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A theoretical study of the kinetics of a model of the Los Alamos Power Reactor Experiment (LAPRE) was made through integration of the dynamic equations with the IBM 701 computer. The stability is investtgated under various conditions of power demand, rod-induced reactivity changes, and other conditions especially applicable to LAPRE. The results are given in graphical form, along with conclusions as to appropriate conditions of operation. (auth)

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