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AN 80 MEGAWATT AQUEOUS HOMOGENEOUS BURNER REACTOR. Reactor Design and Feasibility Problem

Description: An 80 Mw aqueous homogeneous burner reactor suitable for producing 20 Mw of electricity at a remote location is described. The reactor fuel consists of a light water uranyl sulfate solution which acts as its own moderator and coolant. The uranium is highly enriched (93% U/sup 235/). The primary considerstions for the design were simplicity and reliability of the components, automatic demand control and safe for any load change, full xenon override not required, possibility of construction withi… more
Date: August 1, 1957
Creator: Chapman, R.H.; Collins, H.L.; Dollard, W.J.; Fieno, D.; Hernandez- Fragoso, J.; Miller, J.W. et al.
Item Type: Refine your search to only Report
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100 Area process improvement program for the period November 1954--April 1955

Description: This is the second of a series of documents issued quarterly. The documents present, for critical examination by management and for the information of related groups, that portion of the future 100 Area technical program which relates directly and more or less immediately to the Technical-Manufacturing efforts to increase both power levels and production. An attempt is made to describe and justify the key production tests planned for the following six month period. Only those tests necessary fo… more
Date: November 19, 1954
Creator: Reinker, P. H. & Bupp, L. P.
Item Type: Refine your search to only Report
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100 Area Process Water Pressure Decay Test Program: Part 1

Description: The increase in process tube outlet water temperature to 90{degree}C resulted in increased emergency water flow requirements as indicated by recently approved curves which establish minimum crossheader pressure requirements for the first three minutes following an electrical power failure. To determine whether 190 Building secondary process water pump capacities are adequate for current minimum reactor water pressure requirements, process water pump trip-cut tests are being conducted at all rea… more
Date: January 2, 1953
Creator: Thompson, P.
Item Type: Refine your search to only Report
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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
Item Type: Refine your search to only Report
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100 Areas technical activities report, Engineering December 1949

Description: Pile Engineering reports on: metal deformation studies, status of group I metal, flow laboratory activities, boroscope inspection details, pile control details, elimination of silica feed, controlled exposure temperature for graphite samples, naval fuel test channel, strength of masonite at elevated temperatures, carbon dioxide pile temperature, H pile graphite temperature, sampling of pile graphite, special pile motion measurements, pile expansion, far side restraining clamps, vortical thimble… more
Date: January 18, 1950
Item Type: Refine your search to only Report
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100 Areas technical activities report -- Engineering, February, 1950

Description: This report covers work done by the Physical Chemistry Group and the Pile Engineering Groups. Subjects covered are as follows: metal exposure details; slug corrosion details; pile control -- thimble removal study; Van Stone flange corrosion details; process tube corrosion details; carbon dioxide experiment; graphite sampling; special pile measurements; routine pile measurements; 105 technical laboratories; P-10; boiling studies; pile annealing studies; gas tube experiment; thermal conductivity … more
Date: March 29, 1950
Item Type: Refine your search to only Report
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100 Areas technical activities report -- Engineering, May, 1950

Description: This report discusses progress made by the Physical Chemistry Group and Pile Engineering Groups. Topics covered are as follows: x-ray studies--tube bore mining; physical expansion of capsule exposures; special capsule exposures; pile annealing; thermal conductivity and pile annealing; total stored energy; Sykes stored energy method; slug corrosion rate; effect of pressure drop on slug corrosion; exposure of P-10 fuel slugs; slug corrosion weight loss variables; vertical safety rod thimble corro… more
Date: June 28, 1950
Item Type: Refine your search to only Report
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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
Item Type: Refine your search to only Report
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100 Areas technical activities report - physics, July 1951

Description: This is the monthly 100 areas technical activities report for the physics group for the month of July 1951. This group was concerned with pile related studies. Work discussed includes neutron attenuation measurements in pile shielding test facilities, studies of physical properties of shielding materials (concrete), work on a xenon generator and separation facility, further development and shielding work for a neutron spectrometer, continued work on a magnetic spectrometer, and counting equipme… more
Date: August 3, 1951
Item Type: Refine your search to only Report
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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
Item Type: Refine your search to only Report
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100 Areas water treatment specifications

Description: This memorandum discussed review of the data from tests using alum in the treatment of pile process water, and using activated silica as a coagulant aid during period of low water temperature, which shows that this method should be substituted for the present method of treating pile process water in all 100 Areas. It was recommended that the water treatment procedures and specifications attached to this memorandum be initiated as standard practice in all 100 Areas as soon as it is possible to m… more
Date: July 11, 1952
Creator: Greninger, A. B.
Item Type: Refine your search to only Report
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100-B Area flow analysis

Description: Results of experimental programs indicate that it might be desirable in the future to modify the existing reactors by replacing the aluminum process tubes with tubes made of a zirconium alloy. The zirconium tubes would be more corrosion resistant than the aluminum ones and would also be stronger at higher temperatures. These new tubes would have the same outer diameter as the present tubes (for ease of handling and in order to provide adequate graphite cooling) but would have a thinner wall (si… more
Date: June 1, 1957
Creator: Bainard, W. D.
Item Type: Refine your search to only Report
open access

100-K water plant facilities data for G.E. scoping

Description: This report discusses seven items related to the design of the 100-K water plant facilities. These items include: the number of process water connections to the reactor building, valving at the control building, and number of main pumping units; effect on heating system of the Hanford power outage during the winter period; reactor supply conditions; power requirements and steam flow at the local power plant; the service water system; general arrangement of the heat exchanger building; and pumpi… more
Date: August 8, 1952
Creator: Patterson, R. K.
Item Type: Refine your search to only Report
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100-Mw Nuclear Power Plant Utilizing a Sodium Cooled, Graphite Moderated Reactor

Description: The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-cooled graphite-moderated reactor with stainless- steel clad. slightiy enriched UO/sub 2/ fuel. The reactor is provided with three main coolant circuits, and the steam cycle has three stages of regenerative heating. The plant control system allows automatic operation over the range of 20 to 100% load, or manual operation at all loads. The site, reactor, sodium systems, reactor auxiliaries, fuel ha… more
Date: February 28, 1958
Item Type: Refine your search to only Report
open access

100-N temporary construction line considerations

Description: Present thinking and planning appears to be developing from the following factors as concern the 13.8 KV temporary construction power limit. 1. It is understood that the present intent is to supply 100-N operating requirements from a single stub source in the 230 KV loop. 2. The original thoughts were to obtain construction power over a 13.8 KV line from 151-D substation. 3. Construction load requirements are now less than originally planned since steam has been substituted for electrical drive… more
Date: December 30, 1958
Creator: Mollerus, F. J.
Item Type: Refine your search to only Report
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