The heat studies include: automatic time-delay relay for Panellit System; heating of fuel rods; installation of a thermocouple slug; effect of tube length and annulus on tube power; pressure drop film studies; full scale mock-up; flow tests; front to rear enrichment of B, D, and F piles; electrical analog studies; studies on thermal and biological shields; and recirculating system heat exchangers. Some of the topics discussed in the water studies section are: the 100-D flow laboratory; film formation test apparatus; can difference test; Calgon chemical purge for film removal; flow laboratory recirculating studies; slug jacket abrasion at high flow rates; sodium dichromate elimination tests; process water studies; and corrosion studies. The mechanical development studies sections includes the following subjects: Sphincter seal test; ball corrosion test; horizontal control rod conversion study; P-13 removal; chemical slug stripper; temperature monitoring of tube outlets; slug air weigher; slug damage; process tube replacement; crossheader improvement; water cooled test hole facility; 189-D test laboratory; creep in process tubes; charging and discharging machines; flapper nozzle assembly test; horizontal rod gland seal test; and horizontal rod mock-up test.

Plant Assistance Group summaries are given for the B, D, F, H, and DR piles. The Engineering Development Group reports on: ball 3-X program, special field instruments, pile flux density measurements, magnesium inlet dummies, assistance to pile physics group, water survey program, boiling studies, slug temperature measurements, and the job status report for engineering development.

This document discusses increases in water pressure from the 190 Building process pumps which has been contemplated for a range of pressures up to 550 PSIG. The existing process pumps are dual units, consisting of a steam turbine driven primary pump operated: in series with an electric driven secondary pump. The secondary pumps installed in 100-B, D, F, and H Areas were designed for 400 PSIG working pressure, and were given factory hydrostatic tests of 600 PSIG. The 100-DR pumps were given factory hydrostatic tests of 650 PSIG. The Ingersoll-Rand Company advises that a working pressure of 425 PSIG is as high as they would-recommend for pump casing pressure on the secondary pumps. In consideration of problems incident to increased operating pressures, the immediate limiting factor is the total head pressure permissible on secondary pump casings. Other limiting factors are filter plant capacities, and 183 process water capacities.

This report is a monthly progress report for the 100 Area of the Hanford Reservation, covering work by the plant assistance group and engineering development group. It summarizes activities of these groups in support of the production reactors in this area.

This memorandum discusses the expected life of the piles with regard to additional production capacity.

This memorandum discusses the removal of ruptured slugs utilizing new methodology.

The 105-B Pile which was shut down on July 18, 1951 to permit removal of a ruptured uranium slug from tube No. 2169-B. The rupture was detected from effluent water monitor evidence and a survey of rear face pigtails. Removal was accomplished with the pneumatic charging machine using only normal pushing force.

Recently three H-10 tubes (2,772, 2,176, 3,673) have been removed and the tritium and other gases have been extracted from the Z slugs. It is of interest to compare the calculated volumes of gases with the amounts obtained in these extractions. The comparison is given in this paper. The reasons for the large disagreement are not known at present. As pointed out below, the weakest part of the calculation is the knowledge of the exposure which these Z slugs have received. It is possible that some losses, particularly of tritium, occur during exposure and extraction. In view of these uncertainties, it does not appear likely that more 25 has been burnt up per unit of tritium than has been previously estimated.

Activities discussed in this report are as follows: shielding studies; xenon generator; assay of xenon sample counting techniques; crystal diffraction neutron spectrometer; C{sup 12} cross sections measurements; magnetic spectrometer; scintillation spectroscopy; improved pile structure; criticality for the untamped 16 inch spherical reactor; exponential experiments; large scale pile structure; and operational pile physics.

This memorandum discusses a meeting held to fix water requirements necessary for additional production capacity.

At the 100{endash}300 Areas Steering Committee meeting of March 7, following a general discussion of pile level increases, the chairman pointed out the necessity for programming tentative level objectives as far in advance as possible so that the P and Service Divisions may proceed with the planning details incidental to making the necessary equipment changes. A committee consisting of Mr. Warren and Mr. McCullough was appointed to prepare an outline of pile level objectives and to determine the major equipment changes involved in attaining such levels.

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The policy of operating the Hanford Piles at the highest level attainable under existing standards has resulted in pile levels` being occasionally limited by maximum permissible exit water temperatures. The practicability of using refrigeration to reduce the inlet water temperature during peak periods and so increase pile levels has been reviewed and is discussed in this document.

Higher operating levels in the 100 Area piles have caused alarming increases in pile effluent activity and pressure drop through the process tubes. Projected additional increases in power level may not be possible unless the problems of film formation and pile effluent activity are overcome. Although a solution to these problems is not the responsibility of the Power Division, we do not have an interest in seeing that any proposed solution meets the test of operational practicability. Consequently, this was written in order that pertinent water treatment information may be readily available.

This memorandum discusses factors involved in the additional production capacity of Hanford Works.

Topics in the heat studies section include: front and rear face reflector shields at the C-pile; process tube channel thermocouples; water temperature limits for horizontal rods; slug temperature and thermal conductivity calculations; maximum slug-end cap temperature; boiling consideration studies; scram time limit for Panellit alarm; heat transfer test; slug stresses; thermal insulation of bottom tube row at C-pile; flow tests; present pile enrichment; electric analog; and measurement of thermal contact resistance. Topics in the water studies section include: 100-D flow laboratory; process water studies; fundamental studies on film formation; coatings on tip-offs; can difference tests; slug jacket abrasion at high flow rates; corrosion studies; front tube dummy slugs; metallographic examination of tubes from H-pile; fifty-tube mock-up; induction heating facility; operational procedures and standards; vertical safety rod dropping time tests; recirculation; and power recovery. Mechanical development studies include: effect of Sphincter seal and lubricant VSR drop time; slug damage; slug bubble tester; P-13 removal; chemical slug stripper; effect of process tube rib spacing and width; ink facility installation; charging and discharging machines; process tube creep; flapper nozzle assembly test; test of single gun barrel assembly; pigtail fixture test; horizontal rod gland seal test; function test of C-pile; and intermediate test of …

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The stability and corrosion resistance of thorium exposed to eutectic NaK were investigated. Satisfactory results on thorium tube or rod fabrication by means of extrusion were obtained. Rolling and swaging thorium presented no difficulty but drawing proved unsuccessful. Strainhardening values of iodide thorium were about half of those of Ames thorium. The fubrication of unanium tubing by extrusion was successful in the alpha but not in the gamma nange. By increasing the extrusion ratio, an increaae in the strength of the STA410! fiber texiure with respect to that of the STA010! component and an increase in sharpness of both resulted. Static corrosion tests using a two-component system was initiated. The characteristics of a plate which is to be fabricated into a fuel element tube were determined and methods for fabrication of such a plate are discussed. (See also ORNL-910(Del).) (C.J.G.) Preliminary investigations on SAP (sintered aluminum powder) alloys are reported. The mechanical properties of SAP at elevated temperatures are oniy slightly altered by prolonged heating. Its structaral stability is not effected by temperatures at 450 deg C and lower temperatures, blistering starts at 520 deg C and fissures appear in thin walled SAP 930 tubes at temperatures higher than 500 …

Investigations on problems related to the use of MgX and other feed materials in the Plant 6 U refinery at St. Louis, Mo., have continued, with emphasis on the extraction of process feeds by neutral ether. Results of Scheibel column extraction tests wtth neutral ether on a variety of pitchblende, MgX, and V-20 soda salt feed materials indicate that the addition of Fe to complex interfering elements can reduce U losses in raffinates to lower levels than are attainable with acid ether in the absence of Fe. The beneficial effect of neutral ether on transfer of contaminants, especially Mo, to the ether extract was substantiated. It is indicated that the inclusion of V-20 soda salt in a feed tends to increase U losses in extraction; the addition of Fe was shown to be advantageous here also. Sources and costs of added Fe are considered. (G.Y.)

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Design and construction of remote control equipment for plutonium metal production are described. Criteria for the design of the equipment included the following: rubber gloves were to be completely eliminated; all mechanisms were to be built as integral units to facilitate replacement through use of the plastic- bag technique; no accessory equipment such as switches, valves, piping, or cylinders were to be inside the contaminated enclosure unless required to handle the plutonium; and all units were to be tested in mockups before final design. The chemical process, general layout, and operating function are outlined. Descriptions are given of all mechanical units, electrical systems, hydroxide slurry systems, ventilation systems, and chemical tanks and manifolds. (W.L.H.)

Studies were continued on processes for the separation and purification of Ac/sup 227/ from neutron-irradiated Ra and for the deposition of Ac on various metal surfaces. (For preceding period see MLM-519.) (C.W.H.)

A study was made of the stability of tributyl phosphate (TBP) to acids, bases, and UO/sub 2/(NO/sub 3/su)/sub 2/ solutions, and of the chemistry of its decomposition products. The effect of such decomposition products on the extraction behavior of ion of MBP and lines the RAW analyzer and a subsequent reduction of feed flow rate in each case resulted in immediate reduction in losses, as evidenced by the polarographic results. In many such instances, several hours of operation at high waste losses were avoided. A dropping mercury electrode was used for stream analysis, and the RAW solution was analyzed directiy without either dilution or addition of supporting eleclrolyte. Removal of dissolved oxygen and control of temperature were urnecessary. The precision of the method was better than plus or minus 5%, and the accuracy, which is dependent on calibration with a standard solution, was well within the precision value. The calibration curve is linear, for practical purposes, up to approximately 8 g/l UNH or 0.032 lb/gal uranium. (auth)