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Fission gas inventories and estimated releases from PRTR HPD fuel

Description: The PRTR is entering a phase of operation in which there is an increased danger of high level fission product release from failed fuel. The higher fuel operating temperatures result in a much larger percentage fission gas release from the fuel crystal; also it is believed that the central voids and inter-crystal cracks greatly improve the transport of fission gases from the far end of a fuel rod to a defect location. 6 tabs.
Date: September 21, 1965
Creator: Stoddard, J. A.
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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Report to the Working Committee from Hanford

Description: This Hanford Report to the Working Committee details activities and research programs in current reactor production fuels, N-Reactor fuels, N-Reactor fuel development, and current reactor fuel development.
Date: September 21, 1965
Creator: Lewis, M.; Minor, J. E. & Stringer, J. T.
Partner: UNT Libraries Government Documents Department
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Research and Engineering Operation N-Reactor Department, Monthly record report

Description: Plant status, reactor physics, technical activities to include fuel element comparisons, ceramic targets, fuel element testing, alignment studies, tube removal, and nuclear safety specifications are all considered in this progress report.
Date: September 30, 1965
Creator: Leverett, M. C.
Partner: UNT Libraries Government Documents Department
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Uranium swelling in N-Reactor (PT-NR-4, Sup. A, Report No. 1)

Description: Five monitor columns, containing some pre-irradiation weighed inner and outer fuel elements, were discharged under authorization of PT-NR-4, Sup A at tube average exposures in the range from 1554 to 1631 MWD/T. Uranium swelling values have been calculated from post-irradiation weight measurements and these swelling values have been compared with those swelling values obtained in the KER loop tests. There is acceptable agreement between KER and NPR results for swelling of inner uranium; there is… more
Date: September 16, 1965
Creator: Guay, A. E.
Partner: UNT Libraries Government Documents Department
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Status of plant assistance irradiations as of September 10, 1965

Description: This report covers the activities with regard to on-site customer irradiations as of September 10, 1965. The report covers the status of material undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes.
Date: September 28, 1965
Creator: Ferguson, J. H.
Partner: UNT Libraries Government Documents Department
open access

Energy budget

Description: This document consists of tabulated calculations of the energy budget for the Hanford production reactors. Examples of the heat transport calculations are illustrated along with the complete final data. Travel times are estimated.
Date: September 10, 1965
Creator: Corley, J. P.
Partner: UNT Libraries Government Documents Department
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Production Test IP-728 half-plant sodium silicate test: Interim report 1

Description: The radionuclides in reactor effluent are produced almost exclusively from the irradiation of patent elements which are adsorbed on the film which forms on the in-reactor surfaces. The nuclides are subsequently desorbed into the effluent water, one of the areas of activity in the research and development program directed toward reducing reactor effluent radioactivity has been to find some means of minimizing the adsorption of parent materials and/or desorption of radioisotopes. In the course of… more
Date: September 16, 1965
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Research and Engineering Operation, Irradiation Processing Department: Monthly record report, August 1965

Description: Brief summaries are given for the status of activities in the following areas: Reactor fuels; Reactor engineering; Reactor physics; Radiological engineering; Process standards; Process change authorization; Fuel failure experience; Pile physics assistance; Process physics studies; Testing of fuel elements; and Testing and irradiation services.
Date: September 3, 1965
Creator: Ambrose, T. W.
Partner: UNT Libraries Government Documents Department
open access

Carbide Fuels in Fast Reactors

Description: Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
Partner: UNT Libraries Government Documents Department
open access

WANL wide band data converter

Description: No Description Available.
Date: September 1, 1965
Creator: Blau, P. & Moran, M. J.
Partner: UNT Libraries Government Documents Department
open access

Hardening of transistor circuits to ionizing radiation

Description: It is shown experimentally that transistor circuits may have their fundamental sensitivities to ionizing radiation reduced by factors of ten by addition of a simple reverse biased diode. Bipolar transistors, field effect transistors and microcircuits have been hardened. (auth)
Date: September 10, 1965
Creator: Crowe, J. W.
Partner: UNT Libraries Government Documents Department
open access

Compressive Mechanical Properties of Fuel Elements at Elevated Temperatures

Description: An investigation of the ultimate compressive strength of fuel elements as a function of temperature was conducted. A series of tests were performed on a group of two inch long fuel elements with maximum fuel loading. The tests were performed over the temperature range of 3600°R to 2500°R. The maximum increase in ultimate compressive stress was approximately 33 percent of the ambient temperature (530°R) ultimate stress of 12,000 psi and occurred in the temperature range from 3800°R to 4000°R. At… more
Date: September 1, 1965
Creator: Gesinski, L.T.
Partner: UNT Libraries Government Documents Department
open access

Safety analysis report: evaluation of passive re-entry approach

Description: An analysis is made to predict the behavior of a nuclear rocket engine in the event of an in-flight failure subsequent to stantup of the nuclear stage. The accident model assumes loss-of-coolant to the reactor at time of system failure. It is also assumed that the only direct action taken subsequent to failure is separation of a re-entry, vehicle from the remainder of the stage. This vehicle consists of the reactor, pressure vessel, and nozzle. The behavior of the vehicle during its residence t… more
Date: September 1, 1965
Creator: Bridges, J. M.; Brown, W. S.; Call, D. W.; Cleary, J. D.; Hargrove, H. G. & Trammell, M. R.
Partner: UNT Libraries Government Documents Department
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