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Technical feasibility of using uranium oxide fuels at Hanford

Description: The use of uranium oxide fuel and the dispensing with metallic fuel elements in the Hanford production reactors have been contemplated in the past but have not been examined in any detail. This report reviews the technical feasibility of using oxide fuel and discusses the reactor limitations and changes in plutonium and isotope production. These results are based on preliminary calculations and a research and development program would be required to establish the validity of the calculated valu… more
Date: February 15, 1965
Partner: UNT Libraries Government Documents Department
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An Evaluation of Hanford Water Treatment Practices

Description: An evaluation of Hanford reactor process water treatment practices was made in an effort to ascertain the reasons for variations in the effluent activity between reactors. Recommendations are made for improvements in unit processes as well as for the over-all treatment process based on field inspection of the water treatment plants. In addition, a research program is proposed to supplement the recommendations. The proposed research is designed to uncover methods of more efficient filtration as … more
Date: September 1, 1965
Creator: Touhill, C. J.
Partner: UNT Libraries Government Documents Department
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Pacific Northwest Laboratory monthly activities report, April 1965

Description: This report discusses research at the Pacific Northwest Laboratory on topics relating to hanford production reactors. The topic deal with: reactor and material technology; reactor physics and instruments; chemistry; biology and medicine; applied mathematics; radiation protection; and test reactor and engineering services.
Date: May 14, 1965
Partner: UNT Libraries Government Documents Department
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An evaluation of Hanford water treatment practices addendum

Description: This is an addendum to the unclassified document entitled, ``An Evaluation of Hanford Water Treatment Practices.`` All classified data pertinent to the above document have been included here for reference. Data tables include chlorine demand (1964); chlorine contact times for reactor areas; calculation of flocculation; flow velocity in flocculation basins; overflow velocity; and particle removal efficiency; and filtration and backwash flow rates.
Date: May 1, 1965
Creator: Touhill, C. J.
Partner: UNT Libraries Government Documents Department
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Preliminary investigation of water coagulation characteristics as affects reactor effluent radionuclides

Description: Several theories have been advanced regarding the structure and characteristics of the aluminum hydroxide molecule when produced from alum in the water treatment process. The Water Treatment Task Force initiated this test to exploit a theory that increased adsorption of soil-leached elements, present in Columbia River water, by the floc particle would occur when the precipitate vas formed in its terminal pH state. This report discusses a half-plant test which was initiated at E Reactor Plant wh… more
Date: April 15, 1965
Creator: Frymier, J. W.
Partner: UNT Libraries Government Documents Department
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Interim report II: Production test IP-634, half-plant low pH test water treatment at D Reactor process tube examination results

Description: Two half-plant tests were conducted at D reactor to evaluate the effect of process water pH on corrosion of aluminum process tubes and fuel elements. The first test demonstrated that a reduction in coolant pH from 7.0 to 6.6 reduced aluminum corrosion by a factor of between 2 and 3. Fuel weight loss data from the second test indicated that reducing coolant pH from 6.6 to 6.2 would result in an additional factor of 2 to 3 reduction in aluminum corrosion. This report presents the results of ex-re… more
Date: January 1, 1965
Creator: Hough, C. G. & Paglieri, J. N.
Partner: UNT Libraries Government Documents Department
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M-1 N-Reactor fuel development. Excerpts from N-Reactor Department Research and Development Budget for FY-1967 and Revision of Budget for FY-1966

Description: The use of metallic uranium fuel elements on a large scale in a pressurized water cooled graphite moderated power reactor environment in N-Reactor not only represents an extrapolation from previous Hanford fuel technology but it represents the only production-scale application of this concept in this country or abroad. Provision of a supporting technology is and will continue to be a major activity at Hanford as only a limited amount of directly applicable R&D will be available from other sites… more
Date: April 19, 1965
Partner: UNT Libraries Government Documents Department
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PT-IP-759, channel caulking tests: C Reactor

Description: The graphite movement which has occurred at the various reactors has been characterized by two problems: (1) Crooked channels and (2) cracks and miscellaneous voids where pieces of blocks are missing. Of these problems, the cracks and voids have been the most serious in the case of ball drops. Alleviation of the crooked channels can sometimes be accomplished by graphite removal methods such as broaching, but unless some method is found to prevent the balls from entering cracks, the total effect… more
Date: March 19, 1965
Creator: Cooke, J. P. & Russell, A.
Partner: UNT Libraries Government Documents Department
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C-1 coproduct development for N Reactor: Excerpts from N-Reactor Department research and development budget for FY-1967 and revision of budget for FY-1966

Description: This report discusses the production of weapon grade plutonium and tritium as an economically attractive mode of operation for N-Reactor. With the successful completion of the proposed research and development program coproduct production in N-Reactor could begin in January 1967. Approximately 5 kg of tritium could be produced at a reduction in unit total cost of up to $7 per gram equivalent when compared to other modes of operation of N-Reactor that yield only-weapon grade plutonium. Achieving… more
Date: April 19, 1965
Partner: UNT Libraries Government Documents Department
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Letter to N.T. Saunders NASA-Lewis Research Center

Description: Studies during the last two years have shown that the pneumatic impaction process is a flexible process for the production of cermet fuel elements. However, there is still much basic information to be acquired about the process before the limits of process capability can be established. Development work proposed herein is intended to continue optimization of the process, to establish the process parameters necessary to a pilot plant or production line operation, and to better define the process… more
Date: June 28, 1965
Creator: Fawcett, B. L.
Partner: UNT Libraries Government Documents Department
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Report to the Working Committee from Hanford

Description: This report to the working committee details technical activities and research programs for current reactor fuels, N-Reactor fuels, and reactor fuel development.
Date: April 12, 1965
Creator: Lewis, M.; Minor, J. E. & Stringer, J. T.
Partner: UNT Libraries Government Documents Department
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Historical events of the Chemical Processing Department

Description: The purpose of this report is to summarize and document the significant historical events pertinent to the operation of the Chemical Processing facilities at Hanford. The report covers, in chronological order, the major construction activities and historical events from 1944 to September, 1965. Also included are the production records achieved and a history of the department`s unit cost performance.
Date: November 12, 1965
Creator: Lane, W. A.
Partner: UNT Libraries Government Documents Department
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Reactor Branch monthly report, January--December 1965

Description: This document provides a discussion of Reactor Branch activities during the months of January 1965 through December 1965. (FI)
Date: February 9, 1965
Creator: Plum, R. L.
Partner: UNT Libraries Government Documents Department
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Pressure drop characteristics of solid aluminum dummy patterns in K Zircaloy-2 process tube

Description: Pressure drop tests were performed in the 189-D-Hydraulics Laboratory to determine the number of K-Reactor solid aluminum pieces (SAs) required to throttle the tube flow of a 46-piece KVE and a 38-piece KVN arch-rail I&E fuel charge to that of a corresponding bridge-rail charge. In addition, the effects on Panellit pressure and tube flow were determined for several cases.
Date: February 16, 1965
Creator: Angle, C. W.
Partner: UNT Libraries Government Documents Department
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Status of special reactor process tube loadings, June 1, 1965

Description: This report shows the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials.
Date: June 8, 1965
Creator: Bown, R. W.
Partner: UNT Libraries Government Documents Department
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Technical Services: Testing of NASA fuel elements for Battelle Columbus

Description: We are pleased to enclose copies of our Work Statement and Cost Estimate as a subproject to your program to nondestructively inspect the fuels on your NASA-Lewis contract. This confirms our telephone call and teletype of November 19, 1965 from Mr. Chockie to you. As we understand, the duration of this agreement should extend over the next six or nine months and will probably include the inspection of one or two fuel elements singly; later on, three batches of five elements. Accordingly, we reco… more
Date: December 3, 1965
Creator: Worlton, D. C.
Partner: UNT Libraries Government Documents Department
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