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Startup and Initial Testing of SM-1 Core II With Special Components

Description: The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 (Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium … more
Date: February 28, 1962
Creator: Moote, F. G. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
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Safety rod latch inspection

Description: During an attempt to raise control rods from the 100 K reactor in December, one rod could not be withdrawn. Subsequent investigation revealed that a small button'' in the latch mechanism had broken off of the lock plunger'' and was wedged in a position that prevented rod withdrawal. Concern that this failure may have resulted from corrosion or some other metallurgical problem resulted in a request that SRL examine six typical latch mechanisms from the 100 L reactor by use of radiography and met… more
Date: February 1, 1992
Creator: Leader, D.R.
Partner: UNT Libraries Government Documents Department
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ORR Operations for Period April 1961 to April 1962

Description: A summary of the activities in the 4th operational year is presented for the ORR. On-stream time at 30 Mw was relatively steady with 75.4 and 83.7% representing the lowest and highest quarters. Modification of the ball-latch mechanism of the shim-rod-drives is in progress. The primary cooling system bypass control valve was modified and a d-c pony motor was added at the No. 3 primary pump. This addition was made to increase the reliability of adequate water flow for afterheat cooling. A study o… more
Date: October 16, 1962
Creator: Binford, F.T.; Casto, W.R. & Colomb, A.L.
Partner: UNT Libraries Government Documents Department
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Design configuration of GCFR core assemblies

Description: The current design configurations of the core assemblies for the gas-cooled fast reactor (GCFR) demonstration plant reactor core conceptual design are described. Primary emphasis is placed upon the design innovations that have been incorporated in the design of the core assemblies since the establishment of the initial design of an upflow GCFR core. A major feature of the design configurations is that they are prototypical of core assemblies for use in commercial plants; a larger number of the … more
Date: May 1, 1980
Creator: LaBar, M.P.; Lee, G.E. & Meyer, R.J.
Partner: UNT Libraries Government Documents Department
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Rapid quenching of molten lithium-aluminum jets in water under loss-of-control-rod-cooling conditions

Description: A series of fifteen tests were performed to investigate the thermal interactions between molten LiAl control rod material and water under conditions prototypic of the loss-of-control-rod-cooling (LCRC) accident scenario. The experimental parameters such as melt mass, stream diameter, melt temperature and flowrate, water depth and water temperature were controlled or varied to agree with analytically determined conditions, thus insuring prototypicality of the experiments and applicability of the… more
Date: January 1, 1992
Creator: Greene, G. A.; Finfrock, C. C.; Schwarz, C. E.; Allison, D. K. & Hyder, M. L.
Partner: UNT Libraries Government Documents Department
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CRITICAL EXPERIMENTS FOR THE PRELIMINARY DESIGN OF THE ARGONNE HIGH FLUX REACTOR

Description: Critical experiments were performed with two assemblies simulating a cold clean, and an end-of-cycle,- Argonne High Flux Reactor, core. Data were obtained for flux distributions; cadmium ratios; temperature and void coefficients; and control rod, beam hole, and reflector worths. The data obtained furnished confirmation of theoretical predictions. The peak 2200-m/sec flux per unit power was measured as 3 x 10/sup 7/ n/(cm/sup 2/)(sec)(watt) for both cores. The two cores had internal H/sub 2/O th… more
Date: June 1, 1961
Creator: de Villiers, J.W.L. ed.
Partner: UNT Libraries Government Documents Department
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Measurements and Changes on SM-1 Core II During Period October 1, 1961 to May 30, 1962

Description: Tests at the SM-1 reactor are reported for the period October 1, 1961, to May 31, 1962. Loading changes were made in SM-1 Core II during the scheduled semiannual shutdowns in October to November 1961 and April to May 1962. Core physics tests include control rod bank calibrations, bank position at several temperature and xenon poison conditions vs core changes and energy release, shutdown neutron source decay and startup channel testing, and critical rod positions for stuck rod configurations. S… more
Date: July 1, 1962
Creator: Motte, F. G.; Best, W. C. & Kortheuer, J. D.
Partner: UNT Libraries Government Documents Department
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CORE A CRITICAL STUDIES FOR THE ENRICO FERMI ATOMIC POWER PLANT ON ZPR-III

Description: A critical studies program for the Enrico Fermi Atomic Power Plant was run with the ZPR-III fast critical facility. The objectives of this program included determination of the U enrichment required for criticality, the effect of minor variations in core and blanket composition, reactivity coefficients, control and safety rod characteristics, power distribution, spectral indices, and the reactivity worth and wave shape of the oscillator rod. The experimental program was separated into two phase… more
Date: October 1, 1962
Creator: Branyan, C.E.
Partner: UNT Libraries Government Documents Department
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Summary of HTGR (high-temperature gas-cooled reactor) benchmark data from the high temperature lattice test reactor

Description: The High Temperature Lattice Test Reactor (HTLTR) was a unique critical facility specifically built and operated to measure variations in neutronic characteristics of high temperature gas cooled reactor (HTGR) lattices at temperatures up to 1000{degree}C. The Los Alamos National Laboratory commissioned Pacific Northwest Laboratory (PNL) to prepare this summary reference report on the HTLTR benchmark data and its associated documentation. In the initial stages of the program, the principle of th… more
Date: October 1, 1989
Creator: Newman, D.F.
Partner: UNT Libraries Government Documents Department
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SRE CONTROL ROD SHIELDING REQUIREMENTS

Description: Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended pow… more
Date: October 22, 1957
Creator: Whittum, H.O.
Partner: UNT Libraries Government Documents Department
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RADIOISOTOPE AND RADIATION APPLICATIONS QUARTERLY PROGRESS REPORT. SECTION I. USE OF INTRINSIC RADIOACTIVE TRACERS FOR PROCESS CONTROL. SECTION II. RADIATION-INDUCED GRAFT-POLYMERIZATION STUDIES

Description: Research was continued in the areas of intrinsic radioactive tracers for industrial process control and the influence of structural factors in radiation- induced graft polymerization. The use of in-process isotope neutron soarces to produce short-lived radiotraces is discussed. A 10c Po--Be neutron source was obtained for exploratory experiments. The design and construction of a neutronsource storage shield and an activatioa-cell holder are underway. The effect of structural factors oii the eIf… more
Date: October 23, 1961
Creator: McFarling, J.L.; Gluck, P.; Kircher, J.F.; Sunderman, D.N.; Sliemers, F.A.; Luttinger, M. et al.
Partner: UNT Libraries Government Documents Department
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Research and Development of Metal Hydrides. Summary Report for October 1, 1958-September 30, 1960

Description: A detailed study of the fundamental relations in the zirconium -- hydrogen system was made in order to clarify the many points of dispute and to evolve a complete picture describing all phases of this system. An engineering evaluation was made of means for utillzing the various high cross-section metal hydrides in shielding or control applications. These materials would combine the processes of thermalization and absorption. Consequently, they are of considerable interest for use in shielding o… more
Date: November 1, 1960
Creator: Beck, R. L.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962

Description: S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)
Date: June 30, 1962
Partner: UNT Libraries Government Documents Department
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Stress and Deflection of Boiler Fuel Element Boxes

Description: Equations were derived by strain-energy methods for analyzing the stress and deflection in the boiler fuel element boxes used in the Pathfinder nuclear reactor. These boxes are of two types, both constructed of Zircaloy lI. One box is approximately 5 in. sq. The second is approximately 10 1/2 in. sq divided internally into four compartments (5 in. sq) by a cruciform control-rod guide structure. Stress and deflection in the box walls are caused by pressure differences across the walls. The equat… more
Date: April 13, 1962
Creator: Vlies, L. E.
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on LAMPRE Program for Period Ending May 20, 1962

Description: During the report period 110 Mw-hr of operation were completed by LAMPRE I at various power levels, and observations were made of control element performance and reactivity losses. Metallographic examination of a Core I capsule having 120 Mw-hr of irradiation exposure disclosed no major attack. Core II utilizes Ta alloy melts and 13 fuel melts. Starting materials for Core II capsules are tabulated. In research and development a gamma-ray conversion television was used to observe the flow of mol… more
Date: June 1, 1962
Partner: UNT Libraries Government Documents Department
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