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Nuclear safety experience -- Hanford production reactors

Description: Reactor operations at Hanford are to be conducted in the future under a new contract clause on nuclear health and safety, which sets up a form of AEC control somewhat akin to the licensing and regulatory function of the Commission with respect to commercial nuclear plants. As this transition in functional responsibilities approaches, it seems appropriate to review the record of more than 100 reactor-years of General Electric operation at Hanford, and to give an accounting of stewardship in rega… more
Date: August 27, 1963
Creator: Greager, O. H.
Partner: UNT Libraries Government Documents Department
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Comparative reactor flux spectra

Description: This document is explanatory in nature and is intended to clarify certain questions about reactor neutron flux spectra in various AEC production facilities. Simplified models are used to illustrate neutron ``temperature,`` spectral ``hardening,`` and the so-called ``Westcott R.``
Date: November 27, 1963
Creator: Gumprecht, R. O.
Partner: UNT Libraries Government Documents Department
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Reactivation of shutdown reactor plants

Description: This report presents preliminary planning information which supplements two prior special reactor study reports. It is the purpose of this study to consider expedited reactivation of reactors and to evaluate the factors which are likely to be controlling to, or have a major influence on the time required to reactivate one or more of Hanford`s six small reactors after an assumed period in the lay-away status. It is assumed that the methods to be applied in preserving and protecting inactive equi… more
Date: August 27, 1963
Creator: Smith, E. A.
Partner: UNT Libraries Government Documents Department
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Preliminary engineering study linear power rate-of-rise instrumentation -- B, C, D, DR, F, H and KE

Description: When the ``stop-gap`` rate-of-rise meter was installed on all 8 reactors by Amendment 1 to CGI-806 it was intended to replace it with a more satisfactory design when possible. Successful completion of the development program now permits installation of equipment of sufficient reliability to be utilized in the safety circuit. This document defines the program necessary to provide power rate-of-rise protection in the safety circuits of B, C, D, DR, F, H and KE Reactors, provides justification for… more
Date: September 27, 1963
Creator: Herrman, B. W.
Partner: UNT Libraries Government Documents Department
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Chemical decontamination of Hanford production reactors

Description: The conduct of outage work in the discharge areas of the Hanford production reactors has always been complicated by personnel exposure to radiation from the contaminants which accumulate in the effluent water piping in the course of normal operations. These containments represent trace impurities in the cooling water, together with corrosion products, which are irradiated in passing through the reactor and then deposit in the unshielded rear face piping. Radioactive residues also accumulate on … more
Date: June 27, 1963
Creator: Hauff, T. W.; Jensen, H. F. & Smith, R. H.
Partner: UNT Libraries Government Documents Department
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Materials tasks for LCRE, SNAP-50/SPUR, and advanced materials programs

Description: Declassified 30 Aug 1973. 125 figures are included which were presented at the Materials Review Meeting for the LCRE, SNAP-50/SPUR, and Advanced Materials programs, held at CANEL on Sept. 18 and 19, 1983. Fuels, structural materials. alkali metal coolants, and auxiliary materials are included. (DLC)
Date: September 27, 1963
Partner: UNT Libraries Government Documents Department
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Scattering of 14-Mev Neutrons From Nitrogen and Oxygen

Description: The differential cross sections for elastic scattering of 14-Mev neutrons from nitrogen and oxygen were measured in the angular range from 17 to 140 deg , using liquid targets and annular ring geometry. Inelastic scattering to the 2.31 and 3.95-Mev levels in N/sup 14/ and to the levels near 6 and 7 Mev in O/sup 16/ was investigated over a more restricted angular range. The 2.31-Mev level in N/sup 14/ was not excited appreciably, in disagreement with previously reported results. For both element… more
Date: February 27, 1963
Creator: Bauer, R. W.; Anderson, J. D. & Christensen, L. J.
Partner: UNT Libraries Government Documents Department
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PHASE ACCEPTANCE AND BUNCHING IN THE AGS LINAC. Internal Report

Description: Phase acceptance of the Alternating-Gradient Synchrotron Linear Accelerator is theoretically examined and found to agree well with an experimental determination of phase acceptance. Bunching in the AGS linac is also analyzed, the results indicating a satisfactory understanding of this process also. A double buncher that should be more efficient than the present single buncher is discussed, and space charge effects (as yet unobserved in bunching) are analyzed. (D.C.W.)
Date: March 27, 1963
Creator: Blewett, J.P.
Partner: UNT Libraries Government Documents Department
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Y-12 Plant Nuclear Safety Handbook

Description: Information needed to solve nuclear safety problems is condensed into a reference book for use by persons familiar with the field. Included are a glossary of terms; useful tables; nuclear constants; criticality calculations; basic nuclear safety limits; solution geometries and critical values; metal critical values; criticality values for intermediate, heterogeneous, and interacting systems; miscellaneous and related information; and report number, author, and subject indexes. (C.H.)
Date: March 27, 1963
Creator: Wachter, J. W.; Bailey, M. L.; Cagle, T. J.; Mee, W. T.; Pletz, R. H.; Welfare, F. G. et al.
Partner: UNT Libraries Government Documents Department
open access

Design and Analysis of the Experimental Gas-Cooled Reactor Fuel Assemblies

Description: The design of the Experimental Gas-Cooled Reactor fuel assemblies is described and a brief outline of the experimental heat transfer and fluid dynamic studies and mechanical testing is given, and he results of their application to the fuel element analysis are shown. The failure criteria are presented, the hot-channel factors are described, and the expected fission-gas pressure buildup within the elements is discussed.
Date: September 27, 1963
Creator: Samuels, G.
Partner: UNT Libraries Government Documents Department
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Evaluation of tensile specimen types used for uranium

Description: An evaluation was undertaken to compare the results of various thicknesses of flat tensile specimens with results of round specimens from the same uranium plate, and to analyze the effect of some of the fabrication and testing variables on the test results. Flat specimens gave good reproducibility, particularly at thicknesses of 0.150 and 0.200 inch, but showed biases when compared to round specimens which varied as a function of thickness. Fabrication variables such as omitting hand polishing … more
Date: June 27, 1963
Creator: Burditt, R. B.
Partner: UNT Libraries Government Documents Department
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Hanford Reactor and Separations Facility Advantages

Description: This document describes the advantages and limitations of Hanford production facilities. In addition to summarizing the technical parameters of the reactors and separations plants and their mechanical features, the unique aspects of these facilities to the production of special materials in which the Commission may be interested have been discussed. As the primary difference between the B-C-D-DR-F-H reactors and the K reactors and the K reactors is in the number and length of process channels. … more
Date: June 27, 1963
Partner: UNT Libraries Government Documents Department
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Theory of Proton Compton Scattering

Description: The preliminary results of a quantitative calculation of the differential cross section for proton Compton scattering using a previously reported fixed angle dispersion relation formalism are discussed. A relatively large two-spin exchange contribution is indicated. (auth)
Date: June 27, 1963
Creator: Hearn, A. C. & Leader, E.
Partner: UNT Libraries Government Documents Department
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High Energy Elastic Scattering of $Pi$$Sup 1$, P,/Anti P/ and K$Sup 1$ by Protons (and Regge Pole Predictions)

Description: The counter hodoscope experiments at incident particle momenta of 7-20 Bev/c are summarized. The data are presented, together with the associated Regge pole analyses. The effective radii, opacities, and total cross sections obtained for the interactions are included. A magnetic spectrometer setup used for low four-momentum transfer data is also described, and optical theorem predictions for pi /sup -/-p and p-p are given. (D.C.W.)
Date: June 27, 1963
Creator: Lindenbaum, S. J.
Partner: UNT Libraries Government Documents Department
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Non-Destructive and Destructive Transient Tests of the Spert I-D, Fully Enriched, Aluminum-Plate-Type Core: Data Summary Report

Description: This report is a documentation of the experimental data from each test of the series performed in the Spert I reactor with the type D, fully enriched, aluminum plate-type core. The series of tests consisted of step-wise insertions of excess reactivity under conditions of ambient temperature and atmospheric pressure. The data obtained from each test are presented in tabular form and as plots of the time behavior of reactor power, fuel plate surface temperature, and pressure. Composite figures, d… more
Date: November 27, 1963
Creator: Zeissler, M. R.
Partner: UNT Libraries Government Documents Department
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Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process

Description: Report documenting the process of decontaminating low-activity fuel waste water via the Scavenging-Precipitation Ion-Exchange process. This includes analyses of the costs of the process as well as a description of the operation of the pilot plant.
Date: May 27, 1963
Creator: Brooksbank, R. E.; Browder, F. N.; Holcomb, R. R. & Whitson, W. R.
Partner: UNT Libraries Government Documents Department
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