The gas thermometer in the F Pile has been overhauled and re-calibrated. The readings are still in agreement with the readings from the graphite thermocouples. A similar overhaul of the gas thermometer in the D Pile will be made during June. The progress of further outward bowing of Tube 2496-D can not be followed satisfactorily even though readings are obtained from both inlet and outlet ends of the tube. Preliminary results obtained from the one-tube mock-up suggest the possibility that the graphite adjacent to the gun barrels in the upper part of the D Pile may fracture after an additional expansion of about 50%, and that this fracturing may distort the tube locally so that 1.44-inch diameter pieces can not be passed through the tube. There is definite indication that continued expansion of the graphite in the D Pile is causing an increase in both the frequency and severity of gun-barrel binding. The committee endorses the proposal that tubes in the top corners of the F Pile which have yet to be discharged for the first time should be left empty rather than re-loaded. This move would be in the direction of reducing the size of the pile in anticipation …

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This report describes the physical description and functions of the capillary flowmeter.

Disposal of wastes from the processing of solid fuel elements and from solid blanket elements is discussed. The subjects considered include extraction of uranium by several methods, the removal of element jackets, the treatment of uraxium -zirconium fuel elements, disposal into deep wells, the hydraulics of wells, thermal considerations of disposal aquifers regional hydrology, potential deep-well disposal areas in the U. S., aud the cost of disposal. (J.R.D.)

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With higher power levels and probably higher river temperatures, the forthcoming warm water season is expected to impose bulk outlet temperature limits, with consequent production losses, on all Hanford reactors to an even greater extent than last year. The problem has received the attention of a number of management and engineering personnel, but the basis for this study was a letter originating in the Production Operation suggesting two alternate schemes for increasing the flow of process water to the rear face piping, thereby reducing bulk temperatures for a given power level. The purpose of the suggestions was to provide an interim solution to the problem pending I & E loadings. Loading with I & E slugs will increase reactor flows to some degree, depending on the actual slug dimensions used, and will probably result in encountering other limits than the B.O.T. limit. The applicable period for study was therefore taken to be this summer only, since I & E loadings are expected to begin in June or July at 105-D and during the fall at 105-F. The Managers, D and F Reactor Operations, requested Plant and Industrial Engineering Operation to investigate and compare the feasibility and applicability of the suggested …

In a recent report, means of circumventing the present bulk temperature limits are suggested. These have definite merit but do not present an over-all picture of the problem. Therefore, this bulk temperature limit is reviewed in order to place the problem in its full perspective. A program of action is suggested that should lead to: Revised operating conditions and process piping to obtain higher power levels at the same bulk outlet temperature; The completion of production tests to permit higher bulk outlet temperatures with no significant changes in reactor piping; or Redesign of the effluent system to eliminate bulk temperatures as a reactor operating limit.

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Two different measurements of the weight of D/sub 2/O required to fill the blanket to the level at which spillover into the core occurs and visual observation of this level, using a periscope, places the elevation of the hole (or crack) in the core vessel within about 1/2 in.~ of 812 ft 5 in., or approximately 1 to 1 1/2 in below the intersection of the 30 and 90 deg cones. The inherent errors involved in estimating a liquid level in the highpressure system by weighing the liquid drained to the low-pressure system and referring to a calibration of volume vs. elevation are greater for the core than for the blanket. An indication of the approximate size of the hole in the core was obtained by measuring the difference in liquid levels between the core and blanket using bubbler probes, as D/sub 2/O was caused to flow at measured rates from core to blanket, or vice versa. Heads of approximately 1/8 to approximately 3/4 in. were observed for flows in the range 19 to 65 lb/min., indicating a flow area of about 1.4 square inches, assuming a sharp-edged submerged orifice. (auth)

An apparatus designed to tsst aerosol filter efficiency at pressures equal to or less than atmospheric and at linear face velocities of 5 to 1000 ft/ min is described. Aerosol collection efficiency studies were completed for IPC paper at 20,000 and 40,000 ft. Data developed in these studies indicate that ia the impaction and diffusion regions collection efficiency increases with altitude for all linear face velocities less than 800 ft/min. A propeller-type flowmeter, calibrated to measure the volume of air moved by a blower in a balloon-borne system, was flown on five separate flights to obtain air flow data. These data sre presented. Flowmeter air flow measurement data were approximately 10% lower than telemetered data. (auth)

Answers by ICPP personnel to questions asked by Eurochemic are given on a variety of subjects, including off-gas sampling systems, off-gas filtration, iodine evolution during fuel dissolution, and process cell contamination. Data are presented on the% of I/sup 131/ retained in waste solutions in the absence and presence of mercury. (D.L.C.)

An experimental investigation into the gas dynamics of a jet-driven vortex tube for application of a cavity nuclear reactor to rocket propulsion has shown that viscous retardation of the vortex motion is severe, because of a high level of turbulence near the periphery. Based on the experience gained in this study, it is estimated that the achievement of vortex strengths sufficient for practical application will require the use of small diameter tubes with appreciable expenditure of power for recirculation of the gas. The effect of the high degree of turbulence on the separation process near the periphery remains to be determined. The independent variables which were found to influence the vortex strength significantly for a given gas and temperature condition are the tube diameter, the mass flow rate per unit tube length, the injection velocity, and the wall pressure. Estimates of the degree of turbulence in vortex flow have been made from data on the variation in tangential velocity with radius. Virtual (total) viscosities near the periphery ranged from 30 to 700 times the molecular viscosity for tangential Reynolds numbers of from 4 x 10/sup 4/ to 2 x l0/sup 6/. Measurements of the position of the mole- fraction peak …

This monthly document details activities of the Hanford Operations Office during the month of May 1960. (FI)

This memorandum discusses coupling of the reactor exhaust system to the filter building, under Project CG-791, which will require diversion of the 105 Building exhaust air to two temporary stacks. The temporary stacks will be installed over each of two exhaust fans. The use of these temporary (short) stacks during the tie-in period (estimated at 8 to 16 days) could greatly aggravate radiological problems because of reduced dilution and of the reactor building exhaust air. Special operating requirements are given.

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A compilation is presented, in the twenty-five group Reactor Nuclear Data Tape format, of neutron cross sections for elements of major interest for GE- ANPD reactor analysis. The tabulated data are a reproduction of neutron cross section information contained on the Reactor Nuclear Data Tape, which was recently prepared. A brief outline of methods used in processing of the cross sections is also included. (auth)

This document details activities of the Irradiation Processing Department during the month of May 1962.

This memorandum provides an discussion as to the possible application of nuclear ramjet propulsion in a submarine-based missile system. Questions are raised as to modifications required, compatibility with present submarine launch facilities, and missile and booster volume.