We have prepared what we call a bonded segmented fuel element. This fuel element has characteristics which make it an attractive prospect for high specific power operation at relatively low uranium temperatures. The fuel slug is made up of six longitudinal segments; each segment being bonded to the aluminum webbing and tubing that encases it. The pertinent information for this irradiation is summarized along with fabrication details and hazards, thermal aspects and calculations, and figures.

The purpose of this supplement is to authorize adjustment of the fuel loading to maintain a balanced longitudinal flux distribution in the region loaded for this Production Test.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the funds received by the State Industrial Commission in the form of donations and appropriated under Senate Bill 484 are available to the State Industrial Commission despite the fact that Senate Bill 484 was not submitted to the Comptroller for certification.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Are the monies appropriated under Senate Bill 471, Acts 55th Legislature, Regular Session, 1957, Chapter 502, page 1465, for the Texas Traffic Safety Council available for use of the Council, despite the fact that the bill was not submitted to the Comptroller for certification?

This report presents preliminary engineering analyses of costs and possible capabilities for recovering gross and mixed fission products at Hanford. Three alternates were considered for recovering gross or mixed FP from Purex 1WW in B Plant: gross FP recovery as an individual total program, gross FP recovery as an incremental part of a waste solidification program, and recovery of a mixture of zirconium-95 and niobium-95 as an individual total program.

It is recommended that the following described I & E fuel element pair be evaluated for rupture rate improvement, and if significantly improved, recommended for C Reactor usage. Operating conditions are estimated.

The Alco Products Criticality Facility, site location, and operating procedures are described in detail, including the handling of fissionable material and the operating procedures for the safe performance of critical experiments.

Equations are derived which relate the distribution of corrosion attack or cold-zone deposits with the ratecontrolling step of a system which exhibits a thermalgradient mass transfer. Characteristic distributions of attack and deposition are illustrated for thermalgradient mass-transfer processes which are: (1) hotzone controlled, (2) cold-zone controlled, and (3) both hot-zone and cold- zone controlled and the limitations of the method are discussed. It is concluded that both the hot-zone and cold-zone processes must be understood before the conditions leading to the least undesirable distribution of attack can be specified. (auth)

A densimeter system is described which was developed for use on HA column. Reproducibility of instrument readings is plus or minus 2 1/2% of recorder span for pulser frequencies of 44 to 104 cycles per minute. The effects of column pulsations and column static pressure at the feed point are small. Simulated column feed point static pressure of 10 psig caused improved precision due to added damping of float oscillations. (auth)

Radiation survey work at the Berkeley Bevatron has been a continuous project of the Health Physics Group since start-up of the accelerator in November 1954. A substantial body of survey data has accummulated, from which a general pattern for the stray radiation field can be constructed. This report includes a summary of the characteristics of the radiation field pattern as currently understood, a description of the various techniques used to make radiation measurements, and a discussion of some serious problems encountered in survey work at the accelerator. (auth)

The constitution of iron-chromium -aluminum alloys was investigated employing high-purity materials. Ternary sections illustrating the results are presented. The limits of the alpha-plus-sigma region are found to extend from 33 to 63 wt.% chromium at 600 C. At 750 C these limits decreasc to 38 and 57 wt.% chromium. Sigma is found in alloys coataining a maximum of about 9 wt.% aluminum at 600 C and 4 wt.% aluminum at 750 C. The limits of the alpha solid-solution region were investigated between 500 and 900 C. No observable change in limits occurred between 500 and 750 C. However, between 750 and 900 C the AlCr/sub 2/ phase decomposes resulting in a slightly expanded alpha region in the high-chromium alloys. Sigma is found to be unstable below 600 C in alloys of sigma-phase composition. Sigma formation and decomposition occur reversibly above and below this temperature. The nature of the products of the reaction below 600 C has not been determined. A detailed investigation of the physical metallurgy of iron alloys containing 25 to 35 wt.% chromium and 3 to 8 wt.% aluminum, has been made in an attempt to define the limits of usefulness of these materials as structural materials. It …

Report presenting an investigation at Mach numbers of 1.61 and 2.01 to determine the pressure distributions for a series of 20 controls on a 60 degree delta wing. Tests occurred at a range of angles of attack and control deflections. Results regarding basic pressure distributions, comparison of experimental and theoretical results, and experimental comparisons are provided.

Report presenting an investigation to determine the effectiveness of experimental control signals applied to a theoretical inlet throat Mach number control system and normal-shock-position control system for varying the inlet geometry of a twin-duct prototype aircraft. Results regarding inlet instability, control requirements, individual throat Mach number control signals, average throat Mach number control signals, theoretical thraot Mach number control analysis, effect of angle of attack, and theoretical normal-shock-position control are provided.

Memorandum presenting an experimental turbine designed for a high weight flow per unit frontal area, a high specific work output, a relative critical velocity ratio of 0.82 at the rotor hub inlet, and zero rotor blade suction-surface diffusion. Results regarding a comparison of overall performance of subject turbine with that of configurations I and II and comparison of rotor blade momentum thickness of subject turbine with that of configurations I and II are provided.

Memorandum presenting the overall performance results obtained for a 7-inch transonic turbine and a comparison with the results of a 14-inch turbine of geometrically similar design that had been previously investigated. The peak efficiency obtained with the turbine was 0.85, which was 2 points lower than that obtained previously with the 14-inch turbine.

The pump-to-motor mixing rate of the ByronJackson 4000-gpm pump was determined as a function of motor purge flow. A purge rate of 63 liters/hr, which corresponds to a mixing rate of 0.55 liters/hr, is recommended for operation of this pump. Further increases in purge flow did not decrease the mixing rate significantly below this level. Two runs were made with cooling water bypassing the external motor cooler. These runs indicated that the external cooler was necessary to prevent overheating of the 4000 gpm pump motor. However, the observed heat balance checked the predicted heat balance, indicating that the method of prediction can be applied to the design of motor

Concretes containlng portland cement and vermiculite as the solid material and radioactive waste as the makeup liquor were prepared to study the effect of concrete composition on retention of radioactive wastes. The tests indicated that vermiculite-concrete could successfully contain radioactive waste agalnst water leaching if the concrete were flred to 1200 deg C. The tests also indicated that vermiculite-concrete contalning attapulgite gave a lower count lixivium. It was not clear whether this resulted from the presence of the attapulgite or from the use of a higher solids-to-waste ratio. Experiments were made to determine how effectively porous ceramic bodies can tie up radioactive wastes. Tvo procedures were utilizedi one in which the porous body was used as a wick (one end kept dry), and the other In which the entire piece was immersed in the waste solution, fired, and re-immersed for a total of four cycles. (W.L.H.)

Two methods were evaluated for removal of 1 to 5 kilowatts from a 1-in.- diam. by 10 in. long bomb to be (W-7405-eng-261. 8O(ph OTS); 70(mf OTS). maintained at 250 to 300 deg C. Conductance control, varying the composition of a helium--air mixture in a 8 mil annulus to give a controlled conduction heat transfer resistance, gave a simple, smooth, flexible control method. Use of water sprayed into air gave the required range of heat fluxes, but sometimes gave uncontrollable instabilities due to progressive vapor binding. (auth)

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A developmental program was conducted to provide a loop facility for use in evaluating fuel specimens for gas-cooled-reactor applications. The program included the design, construction, and operation of a recirculating in-pile loop featuring high-pressure gas as the primary coolant. The loop facility was designed for gas pressures of up to 200 psig and gas-flow rates up to 0.415 lb per sec with nitrogen as the coolant. Design features incorporated into the facility induced the mounting of the complete package'' on the movable bridge at the Battelle Research Reactor (BRR). This provided ease in moving the loop away from the reactor core for service and specimen transfers. The loop design featured an aluminum pressure wall and concentric counterflow gas passages with static-gas insulation adjacent to all pressure walls. The entire circulating system was located beneath the water level of the pool to signed for use at 750 F inlet-gas temperature, and it featured both oil and water cooling. The instmentation was designed to protect personnel and equipment, and to provide information on the specimen during irradiation. The specimen-transfer mechanism was designed to utilize pool-water shielding while moving a dry specimen from the loop cask located approximately 20 ft below the pool …

An analysis is presented of the dynamics of a turboblower acting together with its connecting circuit. This is to be distinguished from the aero- thermodynamics involved in the design of the blower itself. The effect on system stability of blower and circuit characteristics is discussed. (auth)

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The following document presents an analysis on a phase-shift of p-p scattering with various measurements in Mev.

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