A second order form of the cylindrical P-3 equations is obtained for the case of an isotropic source. The boundary conditions and numerical method are discussed. Input preparation and operating instructions are included. (auth)

Further studies of the Zr-water reaction by the condenser-discharge method are reported. The reaction was studied with initial metal temperatures from 1100 to 4000 deg C with 30- and 60-mil wires in water from room temperature to 315 deg C (1500-psi vapor pressure). Runs in heated water showed markedly greater reactions. This was explained in terms of a 2-step reaction scheme in which the reaction rate is initially controlled by the rate of gaseous diffusion of water vapor toward the hot metal particles and of hydrogen, generated by reaction, away from the particles. At a later time, the reaction becomes controlled by the parabolic rate law, resulting in rapid cooling of the particles. A mathematical model of the reaction of molten metal spheres with water was proposed. Explosive reactions were found to occur with particles smaller than about 1 mm in heated water and 0.5 mm in room-temperature water. The explosive reactions were caused by the ability of the evolving H/sub 2/ to propel the particles through water at high speed. The high-speed motion was detected on motion picture film and had the effect of removing the gaseous diffusion barrier (increasing the Nusselt number), resulting in very rapid reaction. Computed …

The losses of charged particles from a detector aperture, due to multiple scattering of the particles in thin layers of material preceding the detector, are calculated with the aid of a high-speed digitai computer. The rootmean-square multiple-scattering angle is computed after the method of Moliere, and graphs are presented for protons and alpha particles scattering in nitrogen, aluminum, argon, copper, silver, and gold, and for deuterons and tritons scattering in aluminum and copper. The range of particle energy covered is from 5 to 100 Mev. A second program is used to construct a map from which losses, as a function of the root-mean-square multiple-scattering angle and the scattering configuration, may be directly read. The FORTRAN listings for both programs are given. (auth)

Based on the classical theory of diffusion and reaction kinetics, the kinetics of radiation of chemical reactions in fluid systems is represented by a system of parabolic partial differential equations. A code for the solution of a mathematical model which allows up to two radicals and two solutes to be present simultaneously is devised; it gives the concentrations as functions of time and space, and the recombination integrals as functions of time. When the model is applied to water, the radicals may be thought of as H and OH, and the solutes as forming together a redox couple. the reactions are thought to be initiated either by a narrow beam of gamma rays or alpha particles. (auth)

During April 1962, equipment in both the main Redox Building (202-S) and the Plutonium Concentration Building (233-S) vas rearranged to allow the accumulation and recovery of neptunium without interference with the production of uranium and plutonium. In order to do this, the former rework column (1S) was put into continuous service as a neptunium recovery column, the Third Plutonium Cycle was converted to a neptunium decontamination cycle, and ion-exchange equipment was installed in the 233-S Building to replace the Third Plutonium Cycle. The neptunium, once decontaminated, will be concentrated and loaded out via its own system in the 233-S Building. To check the critical mass safety of the new arrangement, a formal hazards review was made, the results of which are reported in this document.

References (165) on diffusion in ceramic systems such as oxides, silicates and glasses, borides, and carbides and graphite, are given to books, reports, and U.S. and foreign journals published from 1904 to 1961. Data on the frequency factor, Da, and activation energy, Q, are given for various elements and systems. A separate author index is also included. (P.C.H.)

A safety evaluation of the SNAP 7E thermoelectric generator system is described. Analyses were performed to assess the radiobiological effects in event of a fuel release and the shielding was evaluated to determine the safe working limits for personnel. The entire evaluation is based on a fuel loading of 31,000 curies of radiostrontium. It is concluded that the safety criteria are met and there is reasonable assurance that this generator is safe for its intended mission. (J.R.D.)

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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.

For approximately the past two years, alloyed dingot uranium has been irradiated on a production scale for evaluation of rupture performance relative to ingot uranium. Supplementary data on dimensional behavior and certain pre-irradiation measurements have been accumulated under the Quality Certification Program. This report presents a comparison of ingot and dingot performance based on data obtained to date from this testing program. The discussion consists of three sections: (I) dimensional stability, (II) external bond quality, and (III) reactor rupture performance.

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The original objective of the work on coated fuel particles at the Nuclear Materials and Propulsion Operation of the General Company was to prepare coated fuel particles less than twenty microns in diameter and to incorporate them n BeO to yield a fuel element in which fuel-matrix reactions, grain growth, and fission product release would be inhibited up to 1650 degrees Celsius.

The primary effort to date in connection with this study has been directed toward obtaining source data which indicates (1) the functions performed during reactor outages and the distribution of time required to accomplish these corrective functions, (2) the groups of crafts associated with each of the recovery functions performed, and (3) the radiation exposures experienced during these activities. The first phase of preliminary analysis has been based on the ``time accountability`` report data originated by the various reactor analysts. The attached computer tabulation is one of the analyses performed considering the time and date a reactor was shut down, the ``cause`` for which it went down and the time and date the reactor was considered back on-line. The report summarizes these accountability data into the following summaries in the order presented below: (1) Total hours down per reactor per cause. (April, 1961 to April, 1962) (2) Number of records indicating experience of outages per reactor per cause. (3) The average and standard deviation; same relationship. (4) Outage summary; total hours down, percentage contribution to the department total outage, and time operating efficiency. (5) Department summary (self explanatory). (6) through (21). Interval between like outages by cause. These reports illustrate …

This report presents the technical observations and conclusions to date of the full-reactor demonstration E-N loading for the combined production of plutonium and tritium. A major incentive for such a loading is the increase in conversion ratio resulting from three factors: (1) A ``blacker`` lattice,, in which a combination of ``E`` metal fuel elements (uranium enriched to 0.95% U{sup 235}) and ``N`` metal target elements (enriched lithium-aluminum alloy) approximately matches the reactivity properties of a natural uranium lattice, results in a smaller proportion of parasitic capture of neutrons in the moderator and other reactor components. (2) The capture of neutrons in fringe target material results in the formation of useful product by a significant fraction of the neutrons otherwise lost by leakage. (3) The burnout of product atoms (plutonium and tritium) is reduced in the blacker E-N lattice, thereby increasing the net yield of product atoms per MWD of heat generation compared to the natural loading. Potential advantages for plant-wide E-N production include the routine processing of a single metal stream for Hanford, increased product quality at reduced throughput, and increased production and recovery of higher isotopes in recycled streams.

Given multigroup fluxes and adjoint fluxes of any cylindrical R-Z configuration, 2D PERT may compute: the prompt-neutron lifetime; the relative worth of various delayed neutrons; the integrals of capture, fission, etc., of given materials over any given region; local perturbations, i.e., danger coefflcients; and integrated perturbations, i.e., reactivity effect of uniform variation in the cross sections affecting a whole region. 2D PERT is programmed for a 32K IBM-704 using 3 tape units. The code is written in FORTRAN with the exception of two SAP subroutines. Input fluxes and adjoint fluxes are on tapes which may be obtained either directly from CUREM output or manufactured by a special tape-writing routine. Homogeneous cross sections and variations of these cross sections are either read in as input information or are computed by the code from a microscopic-cross-section library and atomic densities given as input. A combination of these methods may be used. (auth)

The objectives of this test are to determine the gross dimensional stability of hot pressed fuel and to evaluate bond quality differences between Al-Si bonds and solid state diffusion bonds. Irradiation testing will be conducted at C Reactor and will be carried out in two parts: Part 1, Sylcor and Hanford hot press diffusion bonding processes will be compared to the Hanford Al-Si bonding process. Eighteen (18) measured monitor columns of CVNS fuel elements will be irradiated to an 800 MWD/T goal exposure. Part 2, Hanford gas pressure and Hanford hot die sizing solid state diffusion bonding processes will be compared to the Hanford Al-Si bonding process. Again, eighteen (18) measured monitor columns of CVNS fuel elements will be irradiated to an 800 MWD/T goal exposure.

Consequences of a generalization of the theory of superconductivity that yields a finite Knight shift are presented. In this theory, by introducing an electron-electron interaction that is not spatially invariant, the pairing of electrons with varying total momentum is made possible. An expression for Xs (the spin susceptibility in the superconducting state) is derived. In general Xs is smaller than Xn, but is not necessarily zero. The precise magnitude of Xs will vary from sample to sample and will depend on the nonuniformity of the samples. There should be no marked size dependence and no marked dependence on the strength of the magnetic field; this is in accord with observation. The basic superconducting properties are retained, but there are modifications in the various electromagnetic and thermal properties since the electrons paired are not time sequences of this generalized theory on flux quantization arguments are presented. (auth)

>The Yiftah, Okrert, and Moldauer cross-section set (ANL Set 135) was modified to include new measurements of nu and alpha for U/sup 235/, and to include, in an approximate manner, Hummel, Rago, and Meneghetti's corrections for flux depression at resonance energies in Al and stainless steel. This modified set, ANL Set 635, was used to compute values of k for 22 ZPR-III assemblies of widely varying composition. The DSN neutron transport code was used in spherical geometry and the S4 approximation; shape factors were used to convert from cylindrical to spherical geometry. Seventeen of the calculated values of k lie within plus or minus 1% of a mean value of 1.003, and the remaining 5 lie within plus or minus 2%. In terms of prediction of critical mass, it appears that the procedure used here can achieve an accuracy of 5% to 10% for a wide range of U/ sup 235/-fueled assemblies. (auth)

We are enclosing three copies of a proposal concerned with the preparation for preliminary evaluation of up to 128 Hanford CV size I and II fuel elements to determine an optimum gas-pressure-bonding cycle for the fabrication of this type of fuel element. This proposal is based on your request as outlined in your letter dated May 7, 1962, and document No. HW-72417. Included is a cost estimate of the funding required to conduct this experimental study. All of the aluminum-clad uranium fuel assemblies are to be prepared and furnished by HAPO for gas-pressure bonding at Battelle in existing equipment. To implement the proposed program we have also enclosed six copies of the BMI-AEC research agreement (Serial No. 88). The agreement provides for a six-month research period with an estimated total cost of $24,780. This sum includes $1,180 find fee as established in Contract No. W-7405-ENG-92. Receipt of two fully amounted copies of the agreement, classification guidance, and the specimens will allow us to proceed.

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An analysis is presented concerning the reactor kinetics of TREAT used as a pulsed, engineering test reactor for fast reactor fuel element studies. A description of the reactor performance is given for a wide range of conditions associated with its use as a test reactor. Supplemental information on meltdown experimentation is included. (J.R.D.)

The development of the system and techniques to permit determination of strains at right angle to the axis of loading in the specimen was continued. An additional optical system was developed to accept the lateral image of the gage points and project a vertical image of the same proportion to the apertures of the strain analyzer. Using a dummy specimen of steel in the load train, the automatic pressure control system for the gas-bearing universals was operated. A fluctuation of gas pressure occurred within the bearings. Multiple progressive fracture planes were observed throughout the gage length of fractured graphite and tungsten. (M.C.G.)

A manual is presented for those who use or service the transistorized instruments for nuclear spectroscopy: the transistor amplifier; the snip-snap single-channel analyzer; the fast coincidence unit; and the biased amplifier and linear gate. A general description is given for each instrument along with the specifications, a description of the circuit, and a procedure for initial testing. (auth)

The feasibility of employing the Mossbauer resonant absorption phenomenon for new and useful applications of radioisotopes was studied and evaluated. For these experimental studies radioactive Co/sup 57/ sources were used which allow observations of the Mossbauer resonance in Fe/sup 57/ at room temperatures. However, the results of the investigations can be extrapolated to other Mossbauer isotopes which, unfortunately, usually require low-temperature apparatus to obtain an appreciable fraction of recoilless emissions and absoiptions. The investigations centered aiound the utilization of the Mossbauer effect for practical problems in measui ement and control technology. The use of nuclear resonant techniques in the general areas involving small velocity, acceleration, and displacement measurements appears very promising. For example, velocities in the range from 0.005 to 0.0l5 cm/sec are easily measured using Fe/ sup 57/ nuclear resonance, and this range can be extended several orders of magnitude in both directions if other sources and techniques are endployed. Measurements of gravitational fields in interplanetary space or on the surfaces of celestial bodies, together with altitude measurements of space vehicles, using Mossbauer techniques do not appear practical because the measurement times required to obtain reasonably accurate results is of the order of hours or days under the most …