The problem of heat transfer and fluid flow in a heatgenerating porous media was studied analytically. The study was limited to the range of parameters of interest to the packed-bed fuel element concept. The available heat transfer and pressure drop correlations are reviewed. A system of partial differential equations which govern the velocity and temperature fields in an isotropic porous media was derived. Steady-state temperature distribution in a one-dimensional packed bed was studied, and a numerical method is presented for calculating transient temperature distributions. Pressure drop in a heat-generating packed bed was considered, and flow and temperature stabilities were examined. (auth)

BAND-1 is an IBM-704 program to reduce the experimental data obtained from measurements of the neutron activation distribution within a critical facility. The data reduction consists of correcting the measured data, sorting and ordering it, and calculating the critical buckling parameters by means of a least squares analysis. (auth)

The flowsheet visualized from development work thus far for final plutonium recovery and purification will accept as feed a Purex partition stream without feed adjustment beyond the usual reoxidation. Extraction with trilaurylamine at approximately 0.3M appears suitable for 20 to 60 g Pu/liter product from 0.5 to 2 g Pu/liter feed. Scrubbing with either ((2 M or))2 M HNO/ sub 3/ is possible. Acetic acid is at present the first choice for stripping agent, with oil-soluble and aqueous-soluble organic reductants as alternates. (auth)

Experimental results are summarized for investigations on the condenser fluid mechanics of mercury under zerogravity, two-phase conditions. Conditions required for interfacial stability in tubes were determined as a function of tube diameters. Correlated two-phase pressure drop data are presented as functions of tube inlet Reynolds number and vapor specific volume. Flow regime stability was studied under zero-gravity and 2.55-gravity conditions and at various Reynolds numbers. the effect of noncondensable gas on flow performance in mercury forced convection condensers was evaluated. (D.L.C.)

Control of the exit temperature of the coolant from each fuel channel of the Hallam Nuclear Power Facility reactor is obtained by adjusting the coolant flow rate by a remotely operated variable orifice. Two variable orifices were designed and the hydraulic characteristics determined. Both orifice designs utilized a tapered plug moving in and out of a restricted flow passage at the upper end of the fuel channel. Data were obtained on pressure drop as a function of flow rate at different orifice plug positions; all measurements were made using water, and data were converted to equivalent values for sodium. Either type of orifice was capable of adjusting flow rate to match the power output of a fuel element at any location in the reactor core. The temperature sensitivity (change in exit temperature per unit change in orifice plug position) of the first type of orifice was low (lO deg F/in.) when used in combination with a central fuel element, and high (7OO deg F/in.) when used with a peripheral element. The temperature sensitivity of the second type was more uniform (varying from 90 to 250 deg F/ in.). Consequently, the second type of orifice was selected for the HNPF. (auth)

A graphical compilation is presented of atomic and molecular cross sections of interest to controlled thermonuclear research. The cross sections are shown, as a function of energy, for collision processes involving molecular ion dissociation, charge exchange, excitation, ionization, photoionization, scattering, energy loss, and recombination. Pertinent nuclear cross sections are also included. A bibliography is given covering the literature since 1950. (auth)

A full scale 15 deg sector of the P122 reactor configuration was constructed. The model was complete with respect to all internal cooling air passages, and reflectors, thermal shielding, and island reflector. The contract was terminated before any test data could be obtained. Investigation of the effect of atmospheric dust on performance of reactor systems using wire screen matrix fuel elements is reported. The interim conclusion is that dust would not limit aircraft performance or life. Work proposed but not completed is outlined. Appendices contain previously unpublished reports. (auth)

The Bevatron operated an average of 80% of the scheduled operating time with the exception of one 5-day shutdown period for emergency maintenance of the motor generator sets. The machine was shut off l9% of the scheduled operating time because of component failure and 1% at the request of the user. During and following the Christmas shutdown period an ultrasonic inspection was made of the flywheel keyway on each of the motor generator sets. No faults were apparent. Charpy samples were taken from the inspection bore in the flywheels. Subsequent"vee notch" Charpy impact tests indicated that the flywheels are operated in a brittle region rather than in the ductile range expected. The research program again was devoted mainly to study of pi - and K-meson interactions. (auth)

As a part of the RAIL feasibility study, Operation Dorothe (March 1961) was conducted to determine if a liquid explosive could survive the acceleration of launch from a 155 mm howitzer. This operation was successful, although some structural difficulty was experienced with the test round (C-90). Upon completion of that exercise, it was decided to design a test round that could be used with the more viscous slurry-type explosives, and to fire several of these new rounds with inert filler prior to their use with slurry High Explosives (H.E.), precluding the difficulty previously experienced. The C-91 projectile, is a modified M107 H.E. round. It has been reduced in weight, equipped with an obturator, and provided with a large fill orifice. The rotating band has been altered to eliminate rotation. Internally, a plastic plug is used to control column height. A piston-type `O` ring seal prevents gun gas from reaching the interior to the projectile. Four of these projectiles were fired from a 155 mm howitzer at 15,500 g`s, plus. They survived not only the launch, but also impact and repeated ricochet in sand, gravel, and small rock. No leakage of the inert filler (glycerin) occurred. All rounds were destroyed with …

Accelerated alpha particles from the Berkeley heavy-ion linear accelerator were used in a series of experiments designed to elucidate the conditions by which radiation can stimulate or modify nerve action in mammals. Single millisecond pulses in excess of 40,000 radsor pulse trains of less than 1 sec duration elicited the corneal blinking reflex when delivered to the cornea of unanesthetized rabbits. The lowest threshold dose was observed when the Bragg ionization peak was placed at 140 {mu} depth.

The Reactor Nuclear Data Tape Programs were designed to compile and/or modify a nuclear data library tape from basic nuclear cross-section input. It is intended that this cross-section library tape will be utilized to provide up-to- date nuclear data for various reactor codes. Program RNDP was designed to compile an initial tape from certain minimal input data, or to add or delete complete blocks of data from an existing tape. Program RNDM was designed to compile and add to an existing tape macroscopic cross section data consisting of mixtures of microscopic cross sections available on the tape. Program RNOC was designed to modify and copy an existing tape, or to compile a new tape from sets of binary cards punched by Program RNDP. These programs were written using the FORTrAN-II system of automatic coding for the IBM7090. (auth)

The distortion behavior of graphite as a function of irradiation temperature is reviewed. The behavior of needlecoke and CSF graphite was examined over moderate exposures in the GETR. Results showed needle-coke to be less contracting than CSF. Details of contraction show a minimum contraction rate per 10/sup 21/ nvt at 600 to 800 deg C for both types. Limitations to be placed on the data presented are listed. (P. C.H.)

Laboratory and pilot plant work directed toward development of decontamination methods for high-temperature pressurized water systems are deseribed. It is noted that failure and corrosion of metallic U fuel elements in such systems produces uranium oxides wofth a large percentage of fission products remaining assoeiated with the oxide particles. Decontamination requires dissolution and/or flushing of these oxides from the system. A summary of spceific tests involving promising solutions is presented. (J.R.D.)

The condenser-discharge method of conducting molten metal- water reactions at high temperatures was refined. Two methods to measure energy input to specimen wires and, therefore, to compute initial metal temperatures were developed. Calculated metal temperatures were estimated to be accurate to within 100 deg C. Two reaction cells were designed, one for operation at atmospheric pressure with water at room temperature, and the other for operation at high pressure and with water at elevated temperature. Means were developed to determine the surface area of metal exposed to reaction and to determine the total extent of reaction. Pressure transducers were used to record the rate of reactions. The zirconium- water reaction was studied with initial metal temperatures from 1100 to 4000 deg C with 30 and 60-mil wires in room-temperature water. Initial pressures in these runs were the vapor pressures of water at room temperature (20-30 mm). Runs were made with 60-mil wires in water heated to 200 deg C (225 psi). Results in room-temperature water indicated that the reaction became explosive at an initial metal temperature of 2600 deg C. Below this temperature, 20% or less reaction occurred. At higher water temperatures, reaction ranged from 40 to 70%. Runs in …