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Increased process water pressure to 105 buildings

Description: 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.
Date: February 22, 1951
Creator: Measly, H. F.
Partner: UNT Libraries Government Documents Department

Pile Technology Test Report: Flapper Nozzle Assembly

Description: The functional operation of the flapper nozzle was tested by charging slugs through it while water flow rates up to 48.4 gpm and inlet header pressures up to 400 psig. were maintained. Comparative damage to the slugs by the flapper nozzle and an H-type inlet nozzle was determined by charging slugs through the nozzles with a 105-D type air cylinder charging machine under conditions of no water flow or lubrication. The effect of the nozzle design on the inlet pressure fluctuations was determined while using 0.140, 0.200, and 0.285 inlet orifices as well as no orifice. The flapper nozzles operated satisfactorily for all conditions tested, without leakage from the flapper valve or the needle valve. However, the flapper valve became loosened on the shaft after several operations, and it is felt that the design should be changed to insure that it is rigidly fastened to the shaft at all times. Damage to the slugs by either the flapper nozzle or the H-type inlet nozzle was negligible. The ribs of the process tube caused the normal parallel, longitudinal scratches the length of the slugs. Maximum fluctuations of {+-} 5 psig were noted on the inlet pressure gauge reading, at compared with a maximum of about {+-} 7 psig for standard nozzle Panellit pressure.
Date: December 29, 1951
Creator: Schilson, R. E.
Partner: UNT Libraries Government Documents Department

Technical activities report heat, water, and mechanical studies

Description: 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.
Date: December 1, 1951
Creator: Alexander, W. K.
Partner: UNT Libraries Government Documents Department

Removal of ruptured slug from tube No. 2169-B

Description: 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.
Date: July 25, 1951
Creator: Baker, J. T.
Partner: UNT Libraries Government Documents Department

Technical activities report: Heat, water, and mechanical studies

Description: 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 Ball 3-X and VSR systems.
Date: October 4, 1951
Creator: Alexander, W. K.
Partner: UNT Libraries Government Documents Department

Memo on process water refrigeration: A current evaluation, 100 F, D, and DR Areas

Description: 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.
Date: July 3, 1951
Creator: Nelson, S. L.
Partner: UNT Libraries Government Documents Department

Pile modification resulting in increased power levels

Description: The power output of the piles is being restricted primarily by three important limitations; those due to graphite temperatures, slug and tube corrosion and maximum power per tube or ``boiling disease.`` The purpose of this document is to present means for increasing very appreciably the ``boiling disease`` limits. In addition, means for alleviating the corrosion limitations will be discussed.
Date: July 10, 1951
Creator: Carbon, M. W. & Fryar, R. M.
Partner: UNT Libraries Government Documents Department

Pile level objectives

Description: 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.
Date: April 16, 1951
Creator: Windsheimer, W.
Partner: UNT Libraries Government Documents Department

Calculated and observed P-10 production in H-10

Description: 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.
Date: January 12, 1951
Creator: Ozeroff, W. J.
Partner: UNT Libraries Government Documents Department

A review of water treatment technology as applied in the 100 Areas, Hanford Works

Description: 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.
Date: January 23, 1951
Creator: Conley, W. R.
Partner: UNT Libraries Government Documents Department

100 Areas engineers technical activities report, December 1950

Description: 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.
Date: January 2, 1951
Partner: UNT Libraries Government Documents Department

New reactor area

Description: This memorandum discusses discusses the design of a new reactor area in relation to the H pile.
Date: January 29, 1951
Creator: Gross, C. N.
Partner: UNT Libraries Government Documents Department

100 Areas technical activities report Engineers, January 1951

Description: Monthly reports are given for the B, D, DR, F and H piles. And the Engineering Development Group reports on the: Ball 3-X program, thermocouple slug irradiation and related studies, process water study, metallurgical and corrosion studies, analytical research, heat transfer and temperature effect experiment, assistance to pile physics group, miscellaneous development projects, and a job status report from Engineering Development.
Date: February 2, 1951
Partner: UNT Libraries Government Documents Department

100 Areas technical activities report -- Physics, November 1951

Description: 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.
Date: December 6, 1951
Partner: UNT Libraries Government Documents Department

Technical Progress Letter

Description: It was agreed at the February, 1951 meeting of the Atomic Energy Commission Technical Information Panel that, wherever practical, progress reports should periodically include a list of previous reports issued in the same series. Such a list would greatly facilitate servicing by installation document rooms since requests are frequently received for reports in a specific series. This report lists the Technical Progress Letters from 1944 to date, and is distributed to recipients of the Letters in accordance with the recommendations of the Panel. Because of its length it was not deemed practical to include it as a part of the report itself. lt is anticipated that it will serve as a reference list and permit reduction of personal files.
Date: October 9, 1951
Creator: Linkous, I. G.
Partner: UNT Libraries Government Documents Department