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Hanford Operations Office monthly status and progress report. Part 1

Description: This is the monthly report for the Hanford Laboratories Operation, July, 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: July 1, 1960
Creator: Travis, J. E.
Partner: UNT Libraries Government Documents Department
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Section on Salt and Adrenals

Description: There is no evidence to suggest that the adrenal medulla plays a significant role in the production or maintenance of renal hypertension. The decisive experiment was made by Goldblatt and collaborators/who successfully produced experimental hypertension in dogs by renal artery constriction despite the surgical removal of·one entire adrenal and the medulla of the other.
Date: July 25, 1966
Creator: Dahl, Lewis K
Partner: UNT Libraries Government Documents Department
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Dependence of the Vertical Excitation Energy of Benzene on the Size and Force Constant of the Excited State

Description: Griffing1 computed the vertical excitation energy for the first electronic transition of benzene as a function of the carbon-carbon distance (rn) within the Sklar valence bond (SVB) and Goeppert-Mayer and Sklar molecular orbital (G1SMO) methods to evaluate the change on excitation of the carbon-carbon equilibrium internuclear separation (rn0) and of the corresponding stretching force constant, f. While ring expansion was correctly predicted, both methods appeared to predict that f increases on … more
Date: July 22, 1966
Creator: Ehrenson, S & Wolfsberg, Max
Partner: UNT Libraries Government Documents Department
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Duplex bath variables experiments

Description: No Description Available.
Date: July 20, 1960
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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Neutron lifetimes in the Hanford lattices

Description: An important parameter which is required in the study of short-term reactor transients is the prompt neutron lifetime. This document presents calculated values for the prompt neutron lifetime in the Hanford IPD lattices under a variety of conditions. The calculated values for the prompt neutron lifetimes in the various Hanford IPD lattices are shown. None of the values shown include any contribution from the neutron slowing down time. Two different values (1{sub o1} and 1{sub o2}) are presented… more
Date: July 23, 1963
Creator: Tiller, R. E.
Partner: UNT Libraries Government Documents Department
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Proposal for charging test fuel element with corrugated outer jacket, GEH-10-62

Description: Localized tensile necking and splitting of the Zircaloy-2 clad on coextruded uranium cored fuel elements may represent an ultimate exposure limit. One way to increase the total energy capability of the fuel element is to corrugate the outside cladding so its perimeter is greater than that of a circle circumscribing the equivalent cross-sectional area. Thus swelling of the core will be accommodated by bending of the cladding rather than by large cladding tensile strains. The principal purpose of… more
Date: July 6, 1962
Creator: Wheeler, R. G. & Heck, E. N.
Partner: UNT Libraries Government Documents Department
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KER-4 operating report, Test K-4-14, PT IP-477-A, PT IP-482-A

Description: Test K-4-14 described in this report, was the second ``full charge`` test to be irradiated in KER-4 following loop modification under Project CGI-839. It provided an opportunity to accumulate additional data on the behavior of N Reactor fuel elements at conditions equivalent to or more severe than those anticipated in N Reactor during Phase I, equilibrium operation. Objectives and test results are provided.
Date: July 3, 1963
Creator: Oberg, K. C.
Partner: UNT Libraries Government Documents Department
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Conversion ratio tables

Description: This manual provides a list of the quantities of plutonium and plutonium isotope formation. Other isotopes whose concentrations are important and included in this report are U-236 buildup, U-235 burnout, U burnout, Np-237 build-up, GVR (the Gas Volume Ratio) in coproduct target elements and equivalent gram of plutonium. These conversion tables have been calculated on the IBM 7090 digital computer using a program entitled ``FLEX-3.`` The results of the computer solutions have not been normalized… more
Date: July 2, 1965
Creator: Chitwood, R. A.
Partner: UNT Libraries Government Documents Department
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Production test IP-695-AC thorium oxide irradiation -- K Reactors

Description: Irradiation of thorium for the production of ``clean`` U-233 at HAPO began in CY 1963. Several small-scale tests, involving from gram-size quantities up to a few elements, were successfully conducted; the results from these tests, coupled with theoretical predictions, indicated the desirability of further investigation. The objectives of this test are to (1) authorize the irradiation of about two tons of thorium oxide target elements in central zone process tubes of KE Reactor, (2) determine th… more
Date: July 7, 1964
Creator: Gross, P. D. & Hladek, K. L.
Partner: UNT Libraries Government Documents Department
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Variable goal exposure plans for production type fuel elements

Description: The purpose of this memorandum is to transmit revisions to the goal exposure plans of reference (1). The plans, herein, supersede the previous recommendations. Similar to the plans of reference (1), the exposures calculated from these plans are designed to maximize plant return on the basis that the only restraint on metal usage is that imposed by the economics of the plutonium production process and associated uranium cycle, as described and defined in references (2) and (3). When metal throug… more
Date: July 6, 1960
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Preliminary hazards evaluation for enriched uranium-thoria (E-Q) loading: Hanford IPD reactors

Description: The General Electric Company, as contractor to the AEC at Hanford, is proposing to modify the fuel loading of one or more of the IPD production reactors for the purpose of producing ``clean`` U-232 as a coproduct with plutonium. The isotope, U-233, with low (3-5 ppM) U-232 content, is expected to become a material with important nuclear applications. The IPD reactors are well suited to produce clean U-233. A proposal to produce 200 kg of U-233 for critical experiments for the AEC`s seed-and-bla… more
Date: July 23, 1964
Creator: Nilson, R.; Carlson, P. A. & Owsley, G. F.
Partner: UNT Libraries Government Documents Department
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Irradiation summary report - PT-IP-288-A, evaluation of seven rod cluster elements with modified end closures

Description: The objective of this report is to summarize all in-reactor operating data associated with PT-288-A. This document will serve as a ready reference to the irradiation history of the fuel elements, and will record any anomalies encountered in the performance of this test.
Date: July 13, 1960
Creator: Kratzer, W. K. & Peacock, D. W.
Partner: UNT Libraries Government Documents Department
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Preliminary hazards review overboring Hanford reactors

Description: The General Electric Company, as prime contractor to the AEC at Hanford, is proposing to modify the lattice characteristics of the 8 3/8-inch lattice reactors for the purposes of improving the conversion ratio of these reactors. The proposed overbore modification of the reactors would remove the existing aluminum process tubes, enlarge the diameters of the graphite channels by about one-half inch, insert smooth-bore Zircaloy-2 process tubes and refuel the reactor with larger size, self-supporte… more
Date: July 25, 1962
Creator: Nilson, R. & Carlson, P. A.
Partner: UNT Libraries Government Documents Department
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Design of supplement B to PT-IP-262-A-11-FP, evaluation of projection fuel elements for use in ribbed process tubes

Description: One of the three major categories of HAPO fuel element failures is the side corrosion type rupture. The majority of side-corrosion failures has been characterized by oval or tear-drop shaped flow patterns containing evidence of accelerated corrosion. Thorough examination of many of these so-called `hot spot` failures has indicated the failure was caused by poor heat transfer associated with misalignment, dimensional distortion or poor jacket-to-core bonding. It has been postulated that misalign… more
Date: July 18, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-409-A-FP, pilot test of self-supported fuel elements in K size smoothbore zirconium process tubes

Description: In the Plant Improvement Program, it is proposed to retube the K-Reactors with standard size Zircaloy-2 smooth-bore process tubes and to charge self supported fuel elements starting March 15, 1964. The first step in support of this transition program is to confirm compatibility of the fuel-tube geometry and secondly to obtain fuel-tube performance information prior to full scale commitment of the K-Reactors to this design. In view of the testing of self-supported fuel which has been accomplishe… more
Date: July 26, 1961
Creator: Clinton, M. A. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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Irradiation performance of enriched seven-rod cluster fuel elements with 20- and 30-mil-thick cladding, Supplement B to production test IP-226-A, (RM-562): Final report

Description: The proposed operating conditions for Hanford`s N-Reactor fuel elements require the fuel to be an extended surface geometry and to maintain adequate mechanical strength and corrosion resistance in high-temperature water. The fuel element geometry which has been selected for N-Reactor use is a Zircaloy-2-clad, coextruded, tube-in-tube fuel element. A seven-rod cluster fuel element had been considered early in the N-Reactor design program. This report describes the testing of seven-rod cluster fu… more
Date: July 1, 1962
Creator: Call, R. L.
Partner: UNT Libraries Government Documents Department
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Personnel exposure reduction

Description: Process Physics Unit has investigated in our sphere of responsibility the changes in reactor operating methods which would result in lower personnel radiation exposure. Reduced spline usage is the only innovation I can suggest for reducing personnel radiation accumulation.
Date: July 23, 1968
Creator: Hamric, J. P.
Partner: UNT Libraries Government Documents Department
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