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ADDITIONAL ANALYSIS OF THE SL-1 EXCURSION. Final Report of Progress, July- October 1962

Description: Work was carried out to obtain significant data on reactor excursions, in particular the SL-1 excursion, to extend the analysis of reactor transient behavior so as to obtain an improved understanding of the thermal and mechanical processes that take place during and following a reactor excursion, and to obtain chemical, metallurgical, and nuclear data relative to the pre-accident performance of the SL-1. Laboratory investigations were made of samples of the SL-1 power plant. Results are given a… more
Date: November 21, 1962
Partner: UNT Libraries Government Documents Department
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LAMPRE I FINAL DESIGN STATUS REPORT

Description: This report is intended to supplement LA-2327. A description is given of LAMPRE I as it was built including preliminary operating experience of the components. (auth)
Date: January 1, 1962
Partner: UNT Libraries Government Documents Department
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IDO REPORT ON THE NUCLEAR INCIDENT AT THE SL-1 REACTOR, JANUARY 3, 1961 AT THE NATIONAL REACTOR TESTING STATION

Description: A summary of activities which took place following an incident at the SL- 1 is presented. No attempt to determine the incident cause is included. A brief description of the SL-1 and the operating program in progress prior to the incident is given along with detailed information on various aspects of the past incident developments. (J.R.D.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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Temperature Coefficients of the Reactivity Measurement Facility

Description: The temperature coefficient of the Reactivity Measurement Facility was found to be 49 plus or minus 1 mu k/ deg C (1 mu k = 10/sup -6/ DELTA k/k) in the range 15.4 to l7.8 deg C. The change in the net reactivity of a standard sample was --0.48 plus or minus 0.02, --0.66 plus or minus 0.03, and --0.78 plus or minus 0.02 mu k/ deg C in three measuring positions. These low values generally make temperature corrections insignificant. The above results are compared with previous determined values. T… more
Date: July 27, 1962
Creator: Fast, E.
Partner: UNT Libraries Government Documents Department
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Selection of Core Design No. 1 for Type 5 Replacement Cores in SM-1 and SM-1A

Description: Nuclear and thermal analyses were performed to determine the characteristics of the Type 5 core in the SM-1 and SM-1A reactor plants as a function of geometry and composition. The following nuclear properties were investigated: core energy release, maximum midlife reactivity, average fuel burnup fraction, B-10 reactivity coefficient, and power distribution. Thermal parameter surveys determined the effects of channel thickness and power distribution upon the DNBR, nominal and hot channel thermal… more
Date: July 1, 1962
Creator: Davidson, S. L. & Paluszkiewicz, S.
Partner: UNT Libraries Government Documents Department
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A Retrospective Analysis of Aspects of the Alpr (Sl-1) Design

Description: Design, testing, and early operation of the Argonne Low Power Reactor (SL- 1) that was subsequently destroyed in a nuclear incident are reviewed. Motives determining the design of the control system are explained; and information from tests, operation, and the incident itself is analyzed for the purpose of improving reactor design and operation. (D.C.W.)
Date: November 1, 1962
Creator: Kann, W. J. & Shaftman, D. H.
Partner: UNT Libraries Government Documents Department
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Stress Analysis of the SM-1A Reactor Vessel

Description: The stress analysis performed on the SM-lA reactor vessel and cover is presented. The msximum combined stress (51,360 psi in compression) occurs in the vessel cover during a 50 deg F/hr transient. A fatigue analysis of these stresses indicated that they could be applied safely at least 2500 times, and since the vessel is expected to receive less than 900 cycles, it should not suffer any fatigue damage. (auth)
Date: March 30, 1962
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A. & Aitken, C. C.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, April 1962

Description: Research and development of water-cooled reactors are reported including work on EBWR and BORAX-V. Work on liquid metal cooled reactors is also reported in sections on general research and development, EBR-I and II, aud FARET. Other work is reported on genenal nuclear technology and advanced systems development. (J.R.D.)
Date: May 15, 1962
Partner: UNT Libraries Government Documents Department
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Preliminary Stress and Fatigue Analysis of the SM-1 Primary System

Description: A preliminary analysis of the SM-1 primary system showed it-was safe from strain cycling damage with the possible exception of steam generator tube sheet and primary pump casing. These are recommended for further analysis. (auth)
Date: March 31, 1962
Creator: Chittum, R. A.; Knipe, R. K. & McLaughlin, D. W.
Partner: UNT Libraries Government Documents Department
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Detailed Stress Analysis of SM-1 Steam Generator Tube Sheet

Description: The detailed stress analysis of the SM-1 steam generator tube sheet showed it to be safe from strain cycling damage. However, the pressure stresses were greater than the yield strength during the hydrostatic test. The differential between pressure stresses and yield strength indicates that some initial deformation may have taken place in the tube sheet. (auth)
Date: July 11, 1962
Creator: Busuttil, J. J. & Chittum, R. A.
Partner: UNT Libraries Government Documents Department
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A DIAPHRAGM PUMP FOR LIQUID METAL SERVICE

Description: The use of centrifugal and electromagnetic pumps for liquid metals is briefly reviewed. Details are provided on the construction and operation of a two-stage diaphragm pump successfully used for the first time in liquid metal service. From the results of a 5,376 hr test of the pump it was concluded that it is well suited to the pumping of liquid metals at low flow rates where pulsating flow can be tolerated. Operating temperatures and pressures are limited only by the availability of suitable m… more
Date: October 1, 1962
Creator: Westerheide, D.E.; Clifford, J.C. & Burnet, G.
Partner: UNT Libraries Government Documents Department
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190-DR steam turbine backup adequacy report

Description: Because of the questionable performance of the 190-DR steam backup system during the power outage of April 6, 1962, it is felt that a general review of the DR secondary water system capabilities and the standby status of the pumping units is warranted. This report shall briefly describe the performance of the steam backup system during the April 6 power outage and the subsequent power outage of July 10, 1962. Since the former outage, tests have been conducted on the steam pump units to determin… more
Date: November 8, 1962
Creator: Radtke, W. H. & Keplinger, E. R.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, March 1962

Description: ABS>Developmental work is reported on the EBWR and Borax-V other general development work is reported in the area of liquid metal cooled reactors and particularly on the EBR-I and H, and the fast reactor test facility. General reactor technological development is described on applied reactor physics, reactor fuels development, reactor materials development, heat engineering and fluid flow, chemical separations, advanced systems, and nuclear safety. (J.R.D.)
Date: April 15, 1962
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, August 1962

Description: Technical progress is reported on specific reactor projects and on general engineering research and development programs. Developmental activities are reported on the EBWR, Borax-V, the liquid metal cooled zero power experiments, EBR-I EBR II, and FARET. In general reactor technology, research is reported on applied reactor physics, reactor fuels development, reactor materials, and chemical separations. In advanced systems research and development, work is reported on the Argonne Advanced Resea… more
Date: September 15, 1962
Partner: UNT Libraries Government Documents Department
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Operation support plan

Description: No Description Available.
Date: December 21, 1962
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on LAMPRE Porgram for Period Ending August 20, 1962

Description: Operation of the Lampre I during the report period is described and data on the operating history of this reactor are summarized. Other work is reported on core calculations, fuel and container development, and compatibility of Pu-Co- Ce alloys with Ta. Studies of the physical properties of Pu alloys with C, ln, Si, and rare earths are described. Data on the room temperature densities in the Pu-Ce-Co alloy system are presented. Solvent extraction studies concerning separation of Pu are included… more
Date: September 1, 1962
Partner: UNT Libraries Government Documents Department
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Core support blocks

Description: No Description Available.
Date: October 26, 1962
Creator: Parsons, L.E.
Partner: UNT Libraries Government Documents Department
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