None

The purpose of this report is to present a semi-quantitative discussion of the effect of the heat capacity of the process tube assembly on the outlet water temperature following a mild inadequate cooling incident involving an entire reactor.

Knowledge has developed steadily over the past 18 months toward defining the characteristics of the gamma and neutron radiation associated with plutonium and its compounds. Laboratory measurement have been made on plutonium samples taken from the RMA Line, film badge studies have been made in plutonium processing areas, and calculations have been made predicting dose rates and shielding requirements at higher plutonium exposure levels. As these studies continue, and more precise data is accumulated, it will be possible to (1) more accurately evaluate the radiation received by operating personnel, and (2) more accurately (and economically) specify shielding for facilities designed for processing high exposure plutonium. This report gives the results of a gamma energy analysis of the RMA Line and Recuplex obtained with a laboratory model gamma spectrometer. Measurements have been made in the 234-5 Building which have defined the general gamma energy spectrum emitted by the plutonium processing hoods on the RMA Line and in Recuplex. The data obtained from this study has helped resolve the discrepancy between laboratory data and film badge data, and has provided additional information to help in prediction of the gamma radiation levels to be expected from plutonium irradiated to 2000 MWD/T (NPR) and …

Atomic Energy Commission has expressed interest in obtaining xenon with a composite neutron absorption cross section of less than one barn. This material may be obtainable from the off-gas of the Purex dissolver. A proposed gas purification facility would process the Purex off-gas through two distillation steps for isolation of a ``rough`` cut of xenon isotopes containing principally Xe{sup 131}, Xe{sup 132}, Xe{sup 134}, Xe{sup 136}, and a small quantity of krypton. This material would become the feed stream for a thermal diffusion plant for xenon isotope separation. Thermal diffusion has been shown to be the most economical way to concentrate the two heavier xenon isotopes of low cross section and to reject the krypton along with lighter xenon isotopes of high cross section. The objective of the work herein reported was to provide the basis for (l) a scope design of pilot thermal diffusion equipment and (2) design of experiments to be made with this equipment. In the absence of experimental data, the pilot design was developed from theoretical considerations of the parameters considered important in thermal diffusion column operations. It was assumed that the pilot unit would have to provide information on the correlation of theory with practice …

Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.

Abstract: In the present study, the variation of moderator composition was postulated to be effected by the inclusion of varying amounts of beryllium oxide in the graphite of an SGR.

Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).

Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).

This is the monthly report for the Hanford Laboratories Operation, August, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities, visits, biology operation, physics and instrumentation research, employee relations, and operations research and synthesis operation are discussed.

The Facilities Engineering Operation of the Chemical Processing Department prepared a process study scope design of a large thermal diffusion plant for xenon isotope separation. This scoping was done perforce on the basis of calculations made from exclusively theoretical considerations because actual design data are not available. The designers are of the opinion, however, that, such a basis is not adequate to justify the construction of the plant and have, therefore, requested that an appropriate supporting research and development program be carried out. This report presents an experimental plan for obtaining the data required. Anticipated results from the proposed experiments as outlined below, are expected to be useful for determining the correlation of thermal diffusion column theory with practice for this particular system of xenon isotopes. An interpretation of the data will permit the determination of the sensitivity of the column parameters to the change in operational and design variables over which the designer and operator have control. Basic observations made on the behavior of xenon may, in addition, be of general scientific and technological interest. Included in the report are estimates of the kind and quantity of data to be obtained, the analytical services required, and the total analytical …

This paper presents a scope design of two coaxial type thermal diffusion columns. These experimental columns are proposed to meet the requirements of the research and development program given in Part 2 of this report series. They would rearrange the isotopes of xenon from the Case II product of the Purex Gas Separations Facility to yield a product with a composite neutron absorption cross section of less than one barn. The theoretical basis for the design is given in Part 1. The auxiliary equipment necessary for the operation and control of the columns is described in Part 4. Major components of the columns and their functions are described in this part, The proposals for the materials of construction and the heating systems are not conclusive. Several possibilities for these requirements, however, are included. The design of two experimental thermal diffusion columns is given to meet the needs of a proposed research and development program for rearranging the isotopes of xenon. The proposed columns are six meters in length and have a maximum diameter of about five inches. They could be built at Hanford for an estimated cost of $10,000.

None

This document has been written in part to answer questions concerning the feasibility and advisability of ``quickie`` discharge of ruptures at C Reactor. Justification of full pile operational charge-discharge (OC-D) is based in part on outage savings resulting from improved, rupture removal. Since a portion of the rupture removals might be accomplished within the scram recovery time (quickie) it is necessary to consider recovery time as a function of anticipated future power levels. In addition to answering the questions mentioned above, it was felt worthwhile at this time to discuss equilibrium control problems associated with OC-D which have been apparent during operation of prototype equipment, and on the basis of this information to consider reactor control with full pile OC-D.

Introduction: The description of the Organic Moderated Reactor Experiment, (OMRE), its location, its safety system, and operative procedures have been previously detailed. The present report, although dealing with the subject of OMRE safety, has the more detailed intent of (1) determining the behavior of the OMRE under extremely unlikely sets of conditions; and (2) providing additional design information in the areas of reactivity coefficients, burnout heat flux, and reactor control.

This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.

Chemical control of the SM-2 was evaluated both as a partial substitute for burnable poison in the fuel element meat and as a means of improving plant performance. Based on a review of existing information, boric acid was chosen as the reference soluble poison. It was shown that 60% of the burnable B/sup 10/ in the fuel element matrix could be replaced by soluble B/sup 10/ in the coolant without impairing plant stability during load transients. The feasibility of improving power distribution and reducing the number of control rods by supplementing the burnable poison with chemical control was also demonstrated. A preliminary design of an injection and removal system was prepared for the SM-2. (auth)

>The materials problems associated with the present sodium graphite reactor system have generally been approached by using existing knowledge and data to meet the proposed operating conditions. This discussion reviews the general reactor concept and the specific materials used for the major reactor components: (1) shielding materials; (2) core materials; and (3) sodium cooling system materials. In each case, the materials problems and the materials used to minimize or eliminate these problems are described. Economical nuclear power is currently dependent on the flow of improved materials for high temperature use in high radiation fields. Rapid progress is being made in this respect. (auth)

A parameter study was made of some of the nuclear characteristics the HRT would have if the core and blanket were operated at different temperatures. The power density in the fuel solution at the inner surface of the core tank was found to be affected very little by the temperature distribution. However, the thermal flux at the core-tank wall increased when the blanket temperature was reduced (a consequence of the reduced critical concentration). (auth)

The properties of zirconium alloyed with aluminum tin, and molybdenum were investigated. Using reactorgrade zirconium sponge, 11 zirconium-base alloys were double arc-melted and cast into 6-in.-diam. ingots weighing 35 lb each. By such standard hot working procedures as extruding and rolling, the ingots were converted to 1/8-in.-thick strips. The extruded and rolled products were used for a variety of evaluation studies which included corrosion thermal conductivity, tensile, and creep tests. The alloys demonstrated short-time elevated temperature strength properties equal to or greater than type-304 stainless steel. Their corrosion resistance in sodium, at 1000 deg F, compares favorable with that of unalloyed zirconium. The creep resistance and the thermal conductivity were found to be less than those for type-304 stainless steel, but adequate for nuclear reactor application. (auth)

The ''absolute'' containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confine;, ment in space and momentum are plotted for 300-kev deuterons. (auth)

Two designs of sodium cold traps for the HNPF have been subjected to full scale tests, Performance features that were investigated include oxide removal efficiency, oxide capacity, pressure drop characteristics, economizer effectiveness, and temperature profiles, Results indicate that both designs should perform satisfactorily in the Hallam plant, (auth)

The casting of shapes of uranium--molybdenum metal of varying sizes and thicknesses from a molten charge has been successfally accomplished with specificially designed graphite distributors and molds. Solid cylinders, hollow cylinders, and flat plate shapes were cast in gang molds. As many as 35 solid cylinders have been cast simultaneously. All castings had smooth surfaces, and solid shapes were cast to 0.006-in. tolerance on all dimensions except length. (auth)

Solid phases in the zirconium-nitric acid-hydrofluoric acid system were identified by chemical and x-ray diffraction methods. Five different compounds were crystallized at various temperatures and fluoride concentrations from fluoride or fluoborate solutions. These include the mono- and trihydrates of zirconium tetrafluoride, plus three hydrolysis products which possess a fluoride- to-zirconium ratio of approximately three, yet produce different x-ray patterns. The trifluorides crystallize from solutions of low fluoride-to-zirconium ratio at temperatures of below 90, 65 to 100, and above above 95 deg C, respectively. Solubilities of these basic trifluorides were measured at 25 deg C in 1, 6, and 16M nitric acid. (auth)

Tests have been made to determine the sensitivity of various radiation detection instruments for known amounts of ThO/sub 2/ contained in simulated cuts and abrasions. A shielded Geiger-Mueller counter tube can be expected to detect at least 0.1 mg ThO/sub 2/ when counting for a reasonable length of time provided the ThO/sub 2/ deposit is on the surface of the subject being counted. A shielded gamma-spectrometer-crystal, set at a 50-kev cutoff, can be expected to detect at least 0.5 mg ThO/sub 2/ even when an absorber equivalent to 1/2 in. of paraffin is placed between the crystal and the ThO/sub 2/ sample. Duration of exposure of standard film badge photographic emulsions is inversely proportional to the amount of material present and an exposure of about 300 hr is required to detect 10 mg of surface ThO/sub 2/. Although no information is available on the amount of thorium required to induce fibrosarcomas, an extrapolation of data for plutonium indicates that of the order of 1/2 gram of thorium must be present before occurrence of fibrosarcomas would be observed. This value does not represcnt a lower limit but is more likely to be a value for which occurrence of fibrosarcomas are a …