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Reactor Development Program Progress Report, August 1961

Description: Progress is reviewed on the following reactors: EBWR; Borax-V; ZPR-III- ZPR-VI; ZPR-IX; EBR-I; and EBR-II. An outline of fast and slow reactor safety studies in TREAT is presented. Progress is also reported in applied nuclear and reactor physics; development of reactor fuels, materials, and components; heat engineering technology; separation processes; and advanced reactor concepts. (T.F.H.)
Date: September 15, 1961
Partner: UNT Libraries Government Documents Department
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CONCEPTUAL DESIGN AND ECONOMIC EVALUATION OF A STEAM-COOLED FAST BREEDER REACTOR

Description: A conceptual design and economic evaluation of 300 and 40 MW/.sub e/ steam-cooled fast breeder reactor power plants were performed. A reactor core composed of U-Pu oxide rod-type fuel elements clad with Inconel-X and surrounded by a blanket of depleted UO/sub 2/ fuel was studied in some detail. Reactor breeding ratios of from 1.27 to 1.5 and overall system doubling times of from 20 to 30 years are achievable. For the near term (1967) 300 MW/sub e/ plant, an energy cost of 7.6 mills/kwh is estim… more
Date: November 15, 1961
Creator: Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report (for) July 1961

Description: A summary is presented of activities in reactor and general engineering research programs. Discussions are included for developments in EBWR, BORAX-V, ZPR-III. ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Reactor safety studies were performed for fast and thermal reactors. Nuclear technology developments are discussed for applied nuclear and reactor physics, reactor fuels and materials development, heat engineering studies, separations processes, and advanced reactor concepts. (B.O.G.)
Date: August 15, 1961
Partner: UNT Libraries Government Documents Department
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AN ANALYSIS TO DETERMINE THE PERCENTAGE OF HELIUM BYPASSING THE CORE DUE TO THE REFLECTOR SEALING SYSTEM DURING NORMAL OPERATION OF THE HTGR

Description: The percentage of helium which will bypass the core if the reflector system shown is used is predicted. It is estimated that nominally about 0.1 to 0.2% of the total flow will bypass the core, which is not considered excessive. The most difficult parameter to determine was Z, the gap between the sealing surfaces. The method used to predict Z is presented. The effect of bowing due to a temperature gradient across the seals is discussed. (auth)
Date: November 15, 1961
Creator: Nimtz, F.B.
Partner: UNT Libraries Government Documents Department
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VOID COEFFICIENT OF REACTIVITY ASSOCIATED WITH THE ISLAND REGION OF THE HFIR

Description: Changes in neutron multiplication caused by voids in the island of the HFlR were calculated and measured experimentally. The results indicated that with only water initially in the island the maximum change in neutron multiplication ( DELTA k/sub max) associated with island voids is 0.032 with a corresponding void fraction of 70%. With a simulated 300 g Pu target in the island DELTA k/sub max/ was 0.0l6, and the corresponding void fraction was 42%. In view of these large changes in neutron mult… more
Date: November 15, 1961
Creator: Cheverton, R.D.
Partner: UNT Libraries Government Documents Department
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STEAM-COOLED POWER REACTOR EVALUATION, STEAM-COOLED FAST BREEDER REACTOR

Description: Conceptual design and economic studies of a steamcooled fast breeder reactor that can also be used as a source of power are presented. Two reactor plant sizes were considered: a 300-Mw(e) central power station plant and a 40 Mw(e) plant. It was concluded that attractive economics and good breeding characteristics breeding ratios from 1.27 to 1.42) can be achieved in steam- cooled PuO/sub 2/UO/sub 2/ fueled fast reactors. Low capital costs can be obtained by a compact reactor core and the absenc… more
Date: April 15, 1961
Creator: Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, September 1961

Description: BS>Data from examination of blade-type control rods which were used in BORAX are discussed. Operation and maintenance of EBWR is outlined. In work on Borax V, modifications for easier installation of reactor and components is outlined followed by discussion of superheat fuel element development, and fabrication of various reactor components. Borax reactor design is also reported along with information on development and testing. In research on sodiumcooled reactors, activities are summarized in… more
Date: October 15, 1961
Partner: UNT Libraries Government Documents Department
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DETERMINATIONS OF THE KINETICS AND MECHANISMS OF DEBORONIZATION AT 1135 C

Description: The mechanisms and kinetics of the loss of boron during heating at 1135 deg C under various dynamic environments were determined from powder compacts of 5 wt% elemental boron dispersed in matrices of Fe, Cr, Ni, Si, Fe/sub 2/O/sub 3/, Cr/sub 2/O/sub 3/, NiO, and SiO/sub 2/, compacts of austenitic stainless steel alloy powder containing 0.25 wt% boron, and wrought specimens of 0.13 wt% boron-- stainless steel alloy. The compacts containing 5 wt% boron were heat treated in vacuum, highpurity argo… more
Date: September 15, 1961
Creator: Cherubini, J.H.
Partner: UNT Libraries Government Documents Department
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Corrosion Associated With Hydrofluorination in the Oak Ridge National Laboratory Fluoride Volatility Process

Description: Studies carried out on corrosion associated with the hydrofluorination- dissolution phase in the fused-salt Fluoride Volatility Process are summarized. Corrosion for hydrofluorination-dissolver vessels used in bench-scale and semiworks-scale process development at ORNL is discussed. The results of a study on construction materials for the dissolution phase are presented. Corrosion studies at ANL are described for comparison purposes. A full-size hydrofluorinator dissolver is described. (M.C.G.)
Date: November 15, 1961
Creator: Goldman, A. E. & Litman, A. P.
Partner: UNT Libraries Government Documents Department
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SL-1 ANNUAL OPERATING REPORT, FEBRUARY 1960-JANUARY 3, 1961

Description: >The plant was operated from Feb. l959 until Jan. 3, 1961 when a nuclear excursion rendered the plant inoperable, A summary of operations is presented for the period Feb. 1960 until the incident. Plant operational tinwe during the period was 78% of that available. Satisfactory operation of conventional plant equipment was observed during 196 startups and scrams. An inspection of fuel assemblies after 700 Mwd showed no damage except to the B-Al strips attached to these assemblies. A greater than… more
Date: June 15, 1961
Partner: UNT Libraries Government Documents Department
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Mortality in Small Animals Exposed in a Shock Tube To "Sharp"-Rising Overpressures of 3-4 Msec Duration. Technical Progress Report

Description: A total of 661 animals was exposed to sharp''-rising overpressures of 3 to 4 msec duration using a shock tube of novel design which produced a pressure pulse similar to that obtained with high explosives. The reflected shock overpressures associated with 50% lethality were 29.0, rabbit, respectively. Other observations included the time of death in mortally wounded animals and gross pathological lesions likely to contribute to mortality. Selected data from the literature bearing upon the influe… more
Date: June 15, 1961
Creator: Richmond, D. R.; Goldizen, V. C.; Clare, V. R.; Pratt, D. R.; Sherping, F.; Sanchez, R. T. et al.
Partner: UNT Libraries Government Documents Department
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Study of the Feasibility of Shipping the First Spent Core From Elk River, Minn. To Policoro, Italy. Final Report, August 1 to September 15, 1961

Description: A study was conducted to assess the feasibility of transporting the first spent core of the Elk River Power Reactor to Policoro, ltaly. Commercial transport arrangements were also examined and it was found that changes in indemnity and/or insurance are required. Other aspects appear favorable. (J.R.D.)
Date: September 15, 1961
Creator: Fraenkel, S.J.
Partner: UNT Libraries Government Documents Department
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SHUTDOWN COOLING TEST. Pathfinder Atomic Power Plant Summary Report

Description: Tests are performed on Pathfinder superheat fuel element mockups, under reactor conditions of 600 psig, in order to determine the parameters influencing heat transfer from the fuel elements to the moderating water under shutdown conditions. The peak temperatures reached by the superheat elements are also found as functions of the heat generation rate. A mathematical model of the heat transfer system is developed. (T.F.H.)
Date: December 15, 1961
Creator: Littleton, W.E. & Ross, W.
Partner: UNT Libraries Government Documents Department
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SL-1 Annual Operating Report: February, 1960-January 3, [1961]

Description: The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date: June 15, 1961
Partner: UNT Libraries Government Documents Department
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Electron Paramagnetic Resonance in Biology

Description: A review of the theories of electron paramagnetic resonance in biology is presented, including a discussion of the nature of the physical observation, followed by examples of materials of biological interest. Iq discussing these examples, information is presented in terms of the nature of the starting material under observation rather than the nature of the magnetic entities observed. The examples proceed from the simpler molecules of biological interest (metabolites, vitamins, cofactors) into … more
Date: August 15, 1961
Creator: Androes, G. M. & Calvin, Melvin
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: January 1961

Description: This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: February 15, 1961
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: February 1961

Description: This is the monthly report for the Hanford Laboratories Operation, February 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: March 15, 1961
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Design of production test IP-310-A-FP, determination of the dimensional stability of uranium fuel cores classified by the fuel core tester (UT-2)

Description: The objectives of this test are: 1. To establish grain size limits for acceptable uranium fuel element cores. 2. To establish, if possible, criteria for predicting core dimensional stability during irradiation by comparing the relative dimensional stabilities associated with grain size and with variations in grain size in individual cores. 3. To obtain process tube and fuel corrosion data associated with bumper fuel elements in new tubes with no mixer, one mixer in the 10th position and two mix… more
Date: February 15, 1961
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Current status of H Reactor total control

Description: This document presents the total control aspects of the current blanket and central zone E-N loading at H Reactor based on the calculational parameters in Physics of E-N Load compared to Natural Uranium Load at H Reactor, D.I. Monnie, May 11, 1961. The original charge for the E-N core load at H Reactor, (19.37 in. E to 1 in. N) was found to be more reactive than desirable for maximum production efficiency. Therefore a less reactive E to N ratio (18.14 in. E to 1 in. N) has now replaced the orig… more
Date: October 15, 1961
Creator: Vaughn, A. D.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation monthly activities report, August 1961

Description: This is the monthly report for the Hanford Laboratories Operation August 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.
Date: September 15, 1961
Partner: UNT Libraries Government Documents Department
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