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Analysis of Stresses in Bellows

Description: Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date: October 15, 1964
Creator: Anderson, W. F.
Partner: UNT Libraries Government Documents Department
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Atomics International contribution to 19th High Temperature Fuels Committee. Preliminary information, Section II

Description: A description of the fuel elements for SNAP 1OA, SNAP 2, and SNAP 8 was presented at the 17th High Temperature Fuels Committee Meeting, and some of the experimental results obtained in the program were reviewed at the last meeting. This report present some of the more recent detailed findings of the research and development effort on SNAP fuel element materials.
Date: October 15, 1964
Partner: UNT Libraries Government Documents Department
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Battelle-Northwest Monthly Activities Report, February 1965

Description: Activities for each of the following departments are discussed in this report: Reactor and Materials Technology Dept.; Physics and Instruments Dept.; Chemistry Dept.; Biology Dept.; Applied Mathematics Dept.; Radiation Protection Dept.; and the Test Reactor and Engineering Services Dept.. Activities are in support of Hanford reactors (production reactors, N-reactor, PRTR reactor, etc) and reprocessing and radioactive waste management efforts at Hanford.
Date: March 15, 1964
Partner: UNT Libraries Government Documents Department
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Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses

Description: Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically.
Date: October 15, 1964
Creator: Lurie, H. & Noyes, R. C.
Partner: UNT Libraries Government Documents Department
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Carbon dioxide for pH adjustment 100-K Reactors

Description: This report presents the results of a recent analysis to determine if there is a practical method for using carbon dioxide for pH adjustment at the 100-K Reactors. Carbon dioxide could be recovered from the boiler stack gas and introduced into the K Reactor process water. The approximately $240,000 installation cost would be repaid in about one year by the reduction of sulfuric acid costs. The proposed system would consist of a blower, a purification system, and a distribution system for conduc… more
Date: December 15, 1964
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department
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Construction Completion Report: CAI-816, 100-N Reactor Plant

Description: Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
Partner: UNT Libraries Government Documents Department
transcript

Conversation with President Johnson

Description: Audio recording of an interview with Lyndon B. Johnson regarding his rise to presidency following the assassination of John F. Kennedy.
Date: March 15, 1964
Duration: 59 minutes 17 seconds
Creator: WFAA-TV (Television station : Dallas, Tex.)
Partner: UNT Libraries Special Collections
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Criticality-Accident Dosimetry Studies

Description: Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date: October 15, 1964
Creator: Bailey, J. C.
Partner: UNT Libraries Government Documents Department
open access

Developmental Test of Snap 10A Resistance Thermometers in a Copper Block Attachment Configuration

Description: The results of the RTD calibration at temperatures of 1000°F and the thermal cycling at this elevated temperature indicated the temperature transducers may be operated in this environment without a serious compromise in the accuracy of reliability for relatively short periods of time to meet the requirements of this test endeavor. The calibration change which was observed was with the 3°F inherent uncertainty in the measurement and could not be identified as degradation.
Date: June 15, 1964
Creator: Hamilton, A.P.
Partner: UNT Libraries Government Documents Department
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EG&G Rover progress report for 1-31 January 1964. Report No. L-64

Description: This report describes EG&G activities in support of the Rover Program for the month of January, 1964. Details are discussed in succeeding sections and in the appendices with respect to the various tasks included in our scope of work. At Test Cell A., the Facility Mapping Test, EP-IV, was success- fully completed. Preparation continued for the NRX-AL program scheduled for February, 1964. At Test Cell C., a high flow acoustics test, EP- 1, was conducted. This was the last experimental plan to be … more
Date: February 15, 1964
Partner: UNT Libraries Government Documents Department
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Estimates of river dilution factors from upstream reactors

Description: This documents contains a table has been prepared to assist in the evaluation of hazards to occupants of the Wahluke Slope associated with radioactive liquids discharged to the river in the event of reactor accidents. Concentration ratios have been estimated for both the maximum point in the river as well as along the shoreline opposite the reactors for several locations of potential interest and for reactors in B, K, and D Areas. The shoreline concentrations apply to water up to 25 yards from … more
Date: June 15, 1964
Creator: Corley, J.P.
Partner: UNT Libraries Government Documents Department
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Evaluation of Coolant Impurity Removal Equipment at the OMRE

Description: Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
Partner: UNT Libraries Government Documents Department
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