The SNAP II boilers which were designed are summarized. As shown by test results from the three boilers which were tested, a continuous progress in design was achieved. These designs were based on test data from both the SNAP I and SNAP II programs. As the quantity of data increased, physical models describing the heat transfer process were developed. These physical models provide the necessary correlation parameters which permit the extension of existing data to advanced design. Preliminary test sections were designed on the assumption that an allvapor nmodel which ignores the presence of the liquid phase during forced convection boiling could be used to describe the process quantitatively. The conventional Dittus-Boelter equation was applied with the increase in the vapor flow along the tube being ascribed to liquid evaporation. The assumption led to a design that fell short by about an order of magnitude since the exit qualities were only in the range of 10%, far less than required for complete vaporization. As a result, a revision in the concept of the mechanics of boiling was found necessary and a theoretical analysis was formulated, based on a dry wall'' or dropwise'' type boiling phenomenon. The test results of the …

Solutions of the Boltzmann equation for monoenergetic neutron transport in spherical geometry are derived which are respectively singular and regular at the center of the sphere. A few specific partial singular solutions are presented. The regular solutions in spherical geometry are constructed by superposition of solutions in plane geometry which belong to the same k. Finally, the solutions are compared with their representations by a series of spherical harmonics. (D. L.C.)

Additional data were obtained on the separation of linear polymers from cyclic polymers by precipitation with barium chloride. An unexpected peak was observed in the anion-exchange chromatography of a sodium poly-phosphate of n-bar average degree of polymerization) = 6, and the compound represented by this peak was isolated. An end-group titration of this compound by microtechnique proved unequivocally that it is a cyclic phosphate. Although the identification (number of phosphorus atoms per molecule) is not completed, evidence from its position in the elution graph by ion-exchange chromatography' and from paper chromatography indicate that it is probable pentametaphosphate, Na/sub 5/P/sub 5/O/sub 15/, or the boat form of tetrametaphosphate, Na/sub 4/P/sub 4/O/sub 12/. (P.C.H.)

Both the effect of resonant coupling of ion cyclotron motion to electron plasma oscillations, as previously discussed by Harris, and the effect of a negative radial gradient in a magnetic mirror field, the so-called "negative mass'' effect, were combined in an approximate calculation for the threshold for electrostatic instability in DCX. The two mechanisms for instability were found to act more or less independently. (auth)

The 15,000 MW nuclear economy assumed for the long range study of pot calcination costs reported earlier was used as a basis for calculating optimum fill volumes. An algebraic expression was developed for cost as a functmon of the normalized radius of the central void space in a partially filled vessel. Minima of this expression were found for acmdmc and neutralized wastes in 6, 12, and 24in.-diameter vessels. Optimum fill volumes decreased as vessel diameter increased, varying for acidic wastes from 99.8% for 6-in.-diameter vessels to 92.5% for 24-in.diameter vessels. Decreases in costs by using optimum fill volumes instead of the 90% fill volume assumed for all cases in the long range study were small, the largest being an 8% decrease for neutralized wastes in 6- in.-diameter vessels. (auth)

>Fundamental Alloying. Studies of crystal structures, reactions at metal surfaces, spectroscopy of molten salts, mechanical deformation, and alloy theory are reported. Long-Range Applied Metallurgy. A thermal comparator is described and the characteristic temperature of U0/sub 2/ determined. Sintering studies were carried out on ThO/sub 2/. The diffusion of fission products in fuel and of Al/sup 26/ and Mn/sup 54/ in Al and the reaction of Be with UC were studied. Transformation and oxidation data were obtained for a number of Zr alloys. Reactor Metallurgy. A large number of ceramic technology projects are described. Some corrosion data are given for metals exposed to impure He and molten fluorides. Studies were made of the fission-gas-retention Properties of ceramic fuel bodies. A large number of materials compatibility studies are described. The mechanical properties of some reactor materials were studied. Fabrication work was conducted to develop materials for application in low-, medium-, and high-temperature reactors or systems. A large number of new metallographic and nondestructive testing techniques are reported. Studies were carried out on the oxidation, carburization, and stability of alloys. Equipment for postirradiation examination is described. Preparation of some alloys and dispersion fuels by powder metallurgy methods was studied. The development of welding …

Fifty-seven papers and l7 abstracts of papers are presented in the report. Fifty two of the papers are abstracted separately; in addition, a single abstract is written to cover the section on Plasma Physics Theory, which contains 3 papers and 8 abstracts of papers. The two brief papers not abstracted separately are concerned with fast neutron detection, and homogeneous critical assemblies of 3%enriched UF/sub 4/-paraffin systems. (T.F.H.)

This report examines the many interrelated nuclear, physical, and mechanical phenomena and actions which take place following a loss-of-coolant accident in a Hanford reactor operating at equilibrium power.

The knowledge of the fraction of decay-heat which is absorbed in fuel elements after a reactor is shutdown is important for many reasons. For example, allowable, reduced flow-rates after shutdown are very sensitive to the manner in which the decay-heat is distributed. Also, the temperature-rise in a discharged, uncooled fuel element is dependent on the total heat generated in the slug. Apart from any heat consideration, the escape of rays from a discharged fuel element is also of importance in certain applications. A significant refinement in the knowledge pertaining to decay-heat in irradiated uranium in recent years warrants a complete review of the fractional heat generation in the Hanford reactors. Earlier work was based on very qualitative aspects of fission product decay rates and energy spectra following reactor shutdown. The results of these early calculations on the original, solid, Hanford slug indicated that about 20 per cent of the energy generated in a fuel element from both fission product decay and delayed fission escaped from slug. The results reported here show a much smaller escape-fraction. Also, the time-dependence of the escape-fraction is considered for times greater than 100 seconds after reactor shutdown. Fractional heat-generation rates are calculated for various Hanford …

This report contains daily data of the D reactor`s: outlet temperature; panelist dial; panelist base; front header pressure; and downstream probe thermocouple readings.

The purpose of this report is to describe a means of relaxing the process tube flow trip requirements as now specified for the Hanford reactors. The results of such a relaxation would be a liberalization of flow trip settings on the Panellit pressure gages and higher outlet water temperature limits for sane process tubes.

Two chemically nickel-plated, internally and externally cooled, Hanford production fuel elements, which were irradiated to approximately 800 MWD/T as part of PT-IP-263-A, were transferred to the Radiometallurgy Laboratory in December 1960. The elements were selected for detailed examination because one had incurred a hot spot during irradiation and the other contained some unusual cracks in the nickel plate. Prior to irradiation, both fuel elements had been baked at 300 C to heat-treat the nickel plate. Also, the nickel plate of several unirradiated elements was damaged by scraping, marring, scratching and punching. The elements were exposed for six weeks to 105 C basin water, which was approximately the length of time the irradiated elements were in 105 C basin prior to transfer. Two unirradiated elements were submitted for comparison with irradiated pieces. The examination was requested by Process Engineering, Fuels Preparation Department; and Process and Reactor Development, Irradiation Processing Department, to determine the effects of irradiation on elements with improved nickel plating and to aid in evaluating the nickel-plated fuel element program.

ABS>A test was made on the Radioactive Waste Disposal (RWD) system to determine the acceptability of procedures used in containing, processing, and disposing the wastes received from the plant during a steady-state operation. The RWD system was found to be adequate and to have 60,000 gallons available at all times in the Surge and Decay tanks for safety injection. (D.L.C.)

This volume presents the charts and some backup material presented to members of the Division of Reactor Development on April 17, 1961.

Structural and thermodynamic properties of beryllium, beryllium-oxygen systems, beryllium-nitrogen systems, and beryllium-hydrogen systems as determined by various researchers are surveyed. Diffusion properties, reaction kinetics, and vapor pressures are given where they were available. 44 references. (D.C.W.)

This document details activities of the irradiation processing department during the month of October, 1961. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

A periodic survey was conducted to determine changes in radiation level in the hairpin loops resulting from continued operation of the reactor at power. Results indinate that Co/sup 66/ was the major contributor to the gamma activity present on the 1 BD Hairpin Loop. Loose scale in this area amounted to 0.104 mg/ cm/sup 2/. (J.R.D.)

A transistcrized, portable alpha-survey instrument was developed. Features included are: time-proved air proportional probe (18 in./sup 2/ area); D- cell powered, built-in speaker and audio amplifier; circuit board modules; and sufficient sensitivity and high-voltage power to operate almost any similar type of detector without modification. (auth)

In some recent theories of the equation of state of classical ionized systems, the free energy depends on integrals of the form {integral}{sub 0}{sup {infinity}}[e{sup -{beta}V{sub s}}-1+{beta}V{sub s}-{beta}{sup 2}V{sub s}{sup 2}/2]r{sup 2}dr, where V{sub s} is a "screened" potential obtained from the real potential by summing certain infinite series of diagrams. This integral has been tabulated for V{sub s} appropriate to a potential {+-}(e{sup 2}/ r)(1 - e{sup -{gamma}r}). The equation of state is also given for a one-component electron gas in a uniform background of positive charge (limit{gamma}{approaches}{infinity}).

Plant scale tests were conducted to determine the feasibility of decomposing the nitrous oxide in dissolver off gases with a heated rhodium catalyst. The test results from two fixed bed reactors operating on off gases containing between 14.2 and 19.8 vol.% nitrous oxide show that the nitrous oxide content can be reduced to less than 0.05% with catalyst bed outlet at 1300 to 1500 deg F and space velocities at 472 to 700 hr/sup -//sup 1/. Rate constants appear to be comparable to those reported in the literature. Suggestions are made for the design of a permanent installation. (auth)

Information on the development of pulse columns for the Purex Process is presented in order to indicate qualitutively the performance attainable with improved cartridge designs, and to show some of the factors involved in scaling up pilot plant results to full plant scale. The pulse columns were designed to produce separated uranium and plutonium products decontaminated by at least a factor of 10>s7/sup /om fission products, with average uranium and plutonium losses of less than 0.2% per column and an overall yield of at least 99% of each product. The five types of behavior observed in pulse columns as a function of throughout rate and pulsing conditions are described. The effects of increasing frequency and throughput rate on pulse column efficiency are shown. The different types of perforated plates and packings investigated for Purex service are discussed. Short cuts, indicated by Purex development studies, that may be taken to provide a suituble column design with a minimum of pilot plant development are described. (M.C.G.)

This report is about the Absorption Spectra of spinach chloroplast fragments and the stability of the pigments.

Molecular sieves are used as the basic adsorber in a close-capture air recirculation system designed primarily for remote operation with master-siave equipment. A compact evaporator-dissolver unit provides a vessel for dissolution of an Al slug containing the radioactive material and provides an evaporator head under which volume reduction may be carried out within a specially prepared centrifuge cone. One movable condenser serves both operations. Resistance films of Pt provide heat for the centrifuge cone and for a jet of air impinging on the surface of the iiquid being evaporated. Moisture and acid vapors from the chemical operations are pumped from the main box and adsorbed on the molecular sieves in a separate enclosure. The dry air is then returned to the main box. Thus, by capturing vapors within a closed system and by continuously recirculating the box air through the absorbers, a reasonably dry atmosphere is maintained at all times within the chemistry enclosure, and corrosive action is effectively reduced. (auth)

This report includes a summary of materials research and engineering of the aircraft nuclear propulsion project.