A description is given of the ferrite biasing system for the four tuned radio frequency cavities of the synchrotron. Each ferrite loaded double cavity has a single turn bias winding which is driven to a peak current of 13,500 amperes by a push-pull transformer arrangement. There is automatic tap changing of the transformer to accommodate the variable impedance load (for power considerations). The programming and frequency response of the system have to be such that each cavity can operate as the reso nant circuit of a self tracking radio frequency amplifier over the frequency range 6.5 to 30 Mc at the 20 cps repetition rate of the synchrotron. Between acceleration cycles it is necessary to program the ferrite to a given magnetic state, near that of maximum radio frequency permeability. (auth)

A detailed 4urvey of the radiation from the N.S. Savannah shield was made. The study was accomplished with the reactor at its full power of 69 Mw during a cruise of 2821 miles. The results of the detailed shield survey show that the design dose rate of 0.5 rem/yr for passenger spaces is not exceeded in any region to which passengers have access. ln the area restricted to crew access the design dose rate of 5.0 rem/yr is nowhere exceeded except in a small region on D'' deck in a room to which entry can readily be controlled. Specifications for cargohold dose rates, 0.5 rem/yr at 1/5 full power, are satisfactorily met. Additional data obtained include measurements of special points for comparison with dose rates predicted in design calculations, and an experiment examining the result of loss of water from the Savannah's subreactor shield tanks. Predicted dose rates were conservatively higher than the dose rates measured, and the result of the water-loss experiment showed that even with a total emptying of the tanks a safe condition exists only a few feet from the shield. (auth)

Calcium-magnesium precipitation apparatus was used to reduce the concentrations of these elements in ORNL tap water, used as a substitute for waste water of low level of radioactivity, prior to strontium removal by foam separation. With and without alkali and flocculator chambers and with a stirred sludge of ratio height to diameter equal to 1/1 to ~4/1, use of 5 x 10/sup -3/ M each of NaOH and Na/sub 2/CO/sub 3/ and 2 ppm Fe/sup 3+/ reduced the dissolved Ca + Mg concentrations to 1 to 2 ppm as calcium. Simultaneously, a strontium DF of 20 to 200 was achieved, and, by adding Grundite clay in the proportion ~0.5 1b/ 1000 gal, a cesium DF of 10 to 40 was achieved. (auth)

Techniques for conditioning of Ta filaments for improved bonding and emission with a Ta metal powder-Ta/sub 2/O/sub 5/ mixture are described. A porous Ta metal layer is deposited which restricts sample to the filament. Metal- oxide ion emission is enhanced with additional Ta/sub 2/O/sub 5/ to the porous layer. Reduction of fractionation through action of liquid Ta/sub 2/O/sub 5/ is discussed in particular for Sr+ emission. Use of conditioned filaments for rapid U concentration analysis with a single-filament mass spectrometer is emphasized. (auth)

Compatibility studies of type 304 stainless steel in helium containing low concentrations of CO and CO/sub 2/ were conducted. The oxidation rates were insensitive to impurity concentrations between 0.0006--0.3 vol% in the temperature range 400--1000 deg C when P/sub co2/P/sub co/ was less than 0.66. Ratios above this value resulted initially in a slow oxidation rate, but was followed by an accelerated attack. The incubation period for the break-away varied with the P/sub co2//P/sub co/ ratio and the pressure of the two gases. The oxidation reactions proceeded through a selective depletion of chromium from the alloy which increased the carbon solubility and depletion of nickel which led to the transformation of austenite to ferrite. Parabolic reaction rates were observed for the formation of the protective oxides. Arrhenius plots of rate constants versus 1/T indicated the presence of several oxides which was confirmed by other methods. Carburization or decarburization reactions occurred coincidentally with oxidation and depended upon temperature and (P/sub CO/)/sup 2/ /P/sub CO2/ and the P/sub co2//P /sub CO/. Neither was detected below 600 deg C. Between 600--900 deg C, only carburization occurred and appeared to be mainly dependent on the temperature. Above 900 deg C, both carburization and decarburization …

A thermal and hydraulic design investigation of the Pathfinder Reactor, including analytical and experimental determinations, as well as a complete set of performance calculations, was carried out. A detailed analysis of the reactor energy balance was conducted. Results of the analyses indicated that the reactor will perform within the limits of the material design criteria and operational requirements. Fuel element temperatures are not excessive under the worst combination of circumstances. Thermal stresses in the superheater were minimized by designing the annular element so that temperatures are kept as uniform as possible at every axial location. In all cases, sufficient heat dissipation capacity was found to exist to ensure an ample margin of safety. (M.C.G.)

Molybdenum and tungsten hexafluorides form the solids nitrosylium pentafluoroxymolybdate(VI) and -tungstate(VI), respectively. Uranium hexafluoride gives nitrosylium hexafluorouranate(V) STANOUF/sub 6/!, the same salt that it forms with nitric oxide. (auth)

The processing of Al fuel, principally of the MTR-ETR type, is reported. Processing rate averaged 90% of flow sheet values for the entire operating period, and a U recovery of 99.85% was achieved. Aqueous Zr fuel processing studles continued with the objective of adapting the HF process to continuous dissolution-complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Good results were indicated in a 190-hr run dissolving 2% U-Zr fuel in a Monel dissolver using 4.8M HF-0.03M HNO/sub 3/ dissolvent at 200 deg F; insoluble material did not accumulate in the dissolver, although a U-containing film was formed, apparently in small, equilibrium quantity. Shorter term continuous laboratory dissolutions indicated that 4.8M acid was preferable to 10M acid for the acid feed rate/fuel surface ratios proposed, resulting in dissolver products of greater stability and higher uranium content. Additional laboratory data are presented on UF/sub 4/ hydrate form and solubility, together with maximum dissolvable U compositions with Zircaloy under various flowsheet condltions. Processing of Al alloys containing high Si was found to present no unusual problems in laboratory studies. Siliceous residues resulting from dissolution of Al-U alloys containing 2% …

The possible effects of a hydrogen atmosphere in reducing film deposition were studied in the large circulating loop and in rocking cell and pyrolytic capsule tests. At H/sub 2/ pressures of 200 to 400 psig no reduction in film weight deposited was observed in the loop tests, and in the pyrolytic tests film deposits were doubled. Heat conductivity of the films was much higher however. ln these high ash films the inorganic constituent was found to be alpha -Fe rather than the usual magnetite, which seems to account for the heat conductivity. Separation of benzene-insoluble material from high boiler and coolant was accomplished by centrifugation and by deposition on glass. The material was closely related to film formation. The nature of the inorganic and organic constituents of this material was examined in several analytical studies. Advances in the techniques of nuclear magnetic resonance, O/sub 2/ analysis, measurement of chromatograms, application of computers, and other methods were made. It was demonstrated by use of Fe5/sup 59/ that irradiated terphenyl under air attacks Fe rapidly and possibly the Fe is in solution as a chelate or other complex. It also was indicated by some tests that such a soluble form of Fe …

A series of computer programs are described which Were successfully applied to the reduction of pulse-height data using digital computers. Calculations carried out by these programs include: determination of pulse height vs energy response of an NaI detector; calculation of coincidence sum spectra; and the analysis of complex pulse-height spectra to obtain energies and relative intensities of individual gamma rays or relative abundances from a mixture of radionuclides. Measurement problems and instrumental requirements are discussed in detail. (auth)

The introduction of poison splines as operating aid at the Hanford reactors has resulted in an impressive production increase. This increase is mainly due to the effect on startup control and to better equilibrium flux shaping. In providing sufficient reactivity effect for startup control, however, present splines sometimes increase rather than decrease flattening and distribution control problems when utilized during equilibrium operation. In additional being of constant poison strength along their length, they have limited effectiveness for axial flux control and shaping. It has therefore been proposed that in addition to the present spline, the use of two other types of splines with finer reactivity effects might be advantageous. These splines are as follows: (1) To reduce large rod movements and increase flattening efficiency - a spline with uniform poison distribution along its length but only about 50 per cent of the present spline reactivity strength. (2) To increase axial flux control and shaping -- a spline with poison only on the downstream end, no poison on the upstream end.

The following information was prepared to assist the physicist who encounters a large reactivity lass as in a water soaked lattice or a more permanent loss as in the case of balls remaining in the pile after a ball drop. The discussion is based on experience gained during F Reactor`s severe water leak of July 27, 1961.

The objective of this test is to prove a new method of intentional rupturing of fuel elements under conditions of high specific powers and central core temperatures. The fuel will be the inner component of an NPR fuel element assembly. Permission to change one tubular fuel element (GEH-10-57) into the GEH-P7 loop is requested. A hydraulic cylinder will be attached to the fuel basket assembly. The hydraulic cylinder will be used to move a cutter along the outer surface of the fuel element. The cutter is designed to machine through the Zircaloy cladding and expose the uranium core to the loop coolant.

Two computer codes (1- and 6-node models) were used in the calculations. For the 1-node model, standard reactor kinetics,heat transfer, and instrument delay equations were programmed for analog and digital computers; effects of full-pile reactivity insertions were calculated. The 6-node model contains the time-dependent diffusion equations and heat transfer and instrument delay equations; it was programmed for the analog computer only, and was used to calculate effects of local reactivity insertions. Three types of protection had to be provided: period, rate, and level. The reactors covered include B, D, DR, F, C, H, and K. Results indicate that if the rod system withdrawal speed was reduced, the Zone Temperature Monitor would meet the established criteria over an adequate high level range, whereas the ability of a percentage trip instrument to meet the criteria would be unduly dependent on procedure. The conclusions relative to the older reactors should apply qualitatively to K reactor high-level protection.

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The purpose of Test K-4-13 detailed in this report was to evaluate the behavior of N Reactor fuel elements at conditions equivalent to or more severe than those expected in N Reactor during Phase I) equilibrium operation. Specific objectives of Test K-4-13 were: Measurement of fuel distortion and swelling; Evaluation of irradiation damage to the jacket uranium bond and to the uranium core; and Evaluation of the performance of the fuel element support system.

The objective of this test is to determine the concentrations of radioisotopes in the effluent from a Zircaloy tube and an aluminum tube when both are charged with Zircaloy clad fuel elements and cooled with deionized water. Deionized water is currently being used as the coolant for a Zircaloy and an aluminum tube at KE Reactor. To date the fuel for these tubes has been aluminum clad. Progress is being made in assessing the relative importance of fuel element film and tube film on the radioisotope content of the effluent as well as the contribution of aluminum corrosion to effluent activity. However, there is no information available at present on a channel in which corrosion is reduced to a minimum. It is anticipated that the data supplied by this test will permit a complete evaluation of the variables delineated above.

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Preparation of enriched fuel elements and target (N) elements for a full H-Reactor E-N demonstration loading was authorized in April, 1960. The objective of this loading was to demonstrate the feasibility of operating a Hanford reactor economically as a plutonium-tritium producer to increase over-all conversion ratio and diversify product output. Irradiation of the E-N load began in May, 1961 and was completed in January, 1962.

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Appendices C and D may further be identified as SL1925 and CF-61-12- 20(Rev.), respectively. A comparative report is presented in which the economics and feasibility of plant protection from nuclear attack by plant hardening, remote siting, and utilization of optional fueling concepts for the coal-fired plant are evaluated. (J.R.D.)

Research and development progress is reported on plastics, analytical methods, radioelements, isotope separation and purification, reactor fuels and materials developmert, Ranger x-ray sensor program, and SNAP a. (M.C.G.)

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