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ADVANCED DESIGNS OF MAGNETIC JACK-TYPE CONTROL ROD DRIVE

Description: The magnetic jack is a device for positioning the control rods In a nuclear reactor, especially in a reactor containing water under pressure. Magnetic actuation precludes the need for shaft seals and eliminates the problems associated with mechanisms operating in water. It consists of a pressure shell, four sets of external stationary magnet coils (hold, grip, lift, pull down), and one Internal moving part (ammature) that impants linear motion to a cluster of rods. (W.L.H.)
Date: November 1, 1959
Creator: Young, J.N.
Partner: UNT Libraries Government Documents Department

DESIGN AND PERFORMANCE CHARACTERISTICS OF MAGNETIC JACK-TYPE CONTROL ROD DRIVE

Description: The magnetic jack is a hermetically sealed, step-motion linear motor which saiisfies the need for a reliable, lowcost, nuclear reactor conirol rod drive. It is especially applicable for operation under adverse conditions peculiar to pressurized water-cooled reactors. The jack consists of a pressure shell, four sets of external magnet coils, and one internal moving part ivhich imparts linear motion to rod extensions of the control rod. The desired motion is achieved by energizing and de-energizing the various coils in a given sequence. An electromagnetic position indicator registers the position of the drive rods, thereby loeating the position of the control rod in the reactor core. Two magmetic jacks were operated under simulated boiling water reactor operating conditions for 3150 hours (18,300 ft total rod travel, 2210 scrams) and 13 0 hours (7,700 ft total rod travel, 1000 scrams), respeetively. There were no mechanical malfunctions and no significant wear was observed on the components. The position of the rod was indicated to an accuracy of 0.05 in. Complementary information includes detailed formulas and work sheets for calculating magnetic circuits and component drawings for two alternate magnetic jack designs. (auth)
Date: December 1, 1957
Creator: Young, J.N.
Partner: UNT Libraries Government Documents Department

Bioaccumulation and food chain transfer of corrosion products from radioactive stainless steel

Description: Two sets of experiments were conducted to determine if corrosion products from radioactive Type 347 stainless steel could be biologically transferred from sediment through a marine food chain, and whether corrosion products dissolved in seawater could be bioaccumulated and then eliminated. Corrosion products containing /sup 60/Co and /sup 63/Ni from the radioactive stainless steel were introduced into marine sediments. Infaunal polychaete worms exposed to these sediments bioaccumulated the radionuclides. The feeding of these worms to shrimp and fish resulted in a trophic transfer of the radioactive products across a one-step food chain. The magnitude of the transfers are described in terms of transfer factors. Dissolved corrosion products as measured by the radionuclides were also bioaccumulated by shrimp and fish concentrating more than fish. Concentration factors were calculated.
Date: July 1, 1986
Creator: Young, J.S.
Partner: UNT Libraries Government Documents Department

Biological fate of cobalt-60 released during the corrosion of neutron-activated stanless steel in seawater

Description: Passing seawater over radioactive Type 347 stainless steel in a sediment/seawater laboratory system and exposing marine animals to this environment provided information on the bioaccumulation of /sup 60/Co from radioactive structural material. Exposure of marine organisms to radioactive corrosion products and directly to radioactive stainless steel in seawater simulated some of the possible conditions which could arise from the deposition of radioactive stainless steel on the ocean floor. Detectable levels of /sup 60/Co in marine animals were not observed on a short term basis (5 weeks). Longterm (13 months) exposure of marine animals in a sediment/seawater system resulted in /sup 60/Co bioaccumulation. The specific activity of /sup 60/Co in the organisms was as much as one million times less than that initially present in the radioactive stainless steel. This was due to the dilution of /sup 60/Co by stable cobalt in the seawater, sediments and organisms. As expected the /sup 60/Co specific activity of the organisms never increased above that of the radioactive source. This is because /sup 60/Co is chemicaly indistinguishable from stable Co. Increasing /sup 60/Co concentration factors with decreasing /sup 60/Co concentrations in the seawater and sediment media coupled with relatively constant /sup 60/Co specific activities suggest a possible homeostatic control of cobalt concentrations in certain marine organisms. The evidence indicates that the marine animals derived more of the accumulated /sup 60/Co from the sediments and interstitial water than from seawater. Cobalt-60 concentration factors were generally found to be lower than published cobalt concentration factors due to the predominantly insoluble nature of the corrosion products. Baseline information is provided on trace element concentrations in deep-sea organisms. Stable Co and twenty other elements were measured in abyssal invertebrates and a fish.
Date: March 1, 1982
Creator: Young, J.S.
Partner: UNT Libraries Government Documents Department

Distribution of fission products in an LMFBR: summary

Description: The overall distribution of fission products released from experimental subassemblies containing breached fuel elements has been determined in the fuel and throughout the EBR-II primary and secondary reactor systems. Identification of the fission products released to the primary sodium and location of areas of concentration was important in anticipating radioactive species and levels of deposited fission and activation products on components removed from the primary tank for maintenance and repair. The results of extensive radioanalytical measurements on the fuel, fuel cladding, primary sodium and cover gas system, secondary sodium and cover gas system and steam system are summarized.
Date: January 1, 1985
Creator: Villarreal, R. & Young, J.O.
Partner: UNT Libraries Government Documents Department

Determination of chlorinated solvents in high VOC wastewaters

Description: Gas chromatography - Mass Spectrometry using mass spectrometer source programming and a selected ion monitoring method has been applied to the analysis of trace levels of trichloroethene and tetrachloroethene in process waste waters that contain up to 20 wt percent volatile organic compounds. The method provides selectivity for the target compounds and freedom from interference from the other volatile compounds in the sample. Initial attempts at meeting customer required detection limits were unsuccessful using full-scan GC-MS, and electrolytic conductivity.
Date: July 1997
Creator: Young, J. E.
Partner: UNT Libraries Government Documents Department

Reconnaissance of intertidal and subtidal zones of Back Island, Behm Canal, Southeast Alaska

Description: A diver reconnaissance of the intertidal and subtidal zones of Back Island, Southeast Alaska, was performed May 20-22, 1986. The specific objectives were to catalog potentially vulnerable shellfish, other invertebrates, and plant resources, and to identify potential herring spawning sites. This effort was designed to supplement the existing ecological data base for Back Island that would be used during the National Environmental Policy Act (NEPA) documentation process. A NEPA document will be prepared that describes the site environment and assesses impacts from the proposed construction and operation of the Southeast Alaska Acoustic Measurement Facility (SEAFAC). Nine diver transects were established around Back Island. Particular attention was devoted to proposed locations for the pier and float facilities and range-operations and shore-power cable run-ups.
Date: September 1, 1986
Creator: Strand, J.A. & Young, J.S.
Partner: UNT Libraries Government Documents Department

In-line sensors for electrolytic magnesium cells

Description: This report includes: MgCl{sub 2} purification and molten salt preparation facilities have been completed at both the University of Tennessee, Knoxville, and Oak Ridge National Laboratory. The purification of MgCl{sub 2} is being studied. Initial Raman spectral results have been obtained at both facilities. Two analytical spectral techniques involving near-infrared (NIR) and IR reflectance spectral measurements show promise for identifying and quantifying OH species in solid salts of interest. A sealed IR reflectance cell has been developed for use in the project. An electrochemical cell for use in voltammetric studies concerned with the project has been designed and fabricated. 5 refs., 2 figs.
Date: November 12, 1990
Creator: Young, J.P. & Mamantov, G.
Partner: UNT Libraries Government Documents Department

Studies on production of metastable core-excited atoms by laser-produced x-rays. Final report, 1 October 1984-30 September 1985

Description: The overall objective of the work on this program was to study methods for production of core-excited metastable atoms by laser-generated x-rays. We are interested in the spectroscopy of these levels, their autoionizing and radiative rates, and their metastability in the presence of hot electrons and ions. The concept of using x-rays emitted from a laser-produced plasma to excite large densities of energetic excited levels in atoms and ions has been thoroughly experimentally investigated using modest, 100 mJ, plasma-producing lasers. One of the objectives of this work was to verify that these techniques could be scaled up to higher energies, such as 20 J. Thus a major effort this year has been devoted to the design and construction of the high energy (20 J) 1064 nm plasma-forming laser system and the tunable probe/transfer laser.
Date: April 1, 1986
Creator: Harris, S.E. & Young, J.F.
Partner: UNT Libraries Government Documents Department

Developments in computation, modeling and experimentation: Impacts on R D

Description: The original objective was to document the feasibility of the coordinated research program sponsored by ECUT called Materials-by-Design (MBD).'' The MBD program funds research to develop hierarchical models to predict materials' performance based on microstructural information. This paper was specifically prepared for this meeting to help technical staff and their managers justify and plan for an advanced computer infrastructure within their companies. In order to do this, several additional objectives for this paper are (1) to foster an appreciation of the dramatic increase in computational power that have occurred over the last forty years, (2) to encourage better utilization of supercomputing in current scientific research by identifying current issues and opportunities, and (3) to promote anticipation and enthusiasm for the dramatic changes supercomputers currently being developed will offer scientists in the near future.
Date: October 1, 1989
Creator: Young, J.K.
Partner: UNT Libraries Government Documents Department

ECUT energy data reference series: ammonia synthesis energy-use and capital stock information

Description: Energy requirements for ammonia synthesis totaled 0.55 quadrillion Btu of natural gas in 1980 and 28,500 MMBtu (8.3 x 10/sup 6/ kWh) of electricity. Efficiencies ranged from 0.72 to 0.8 for natural gas and 0.65 for electricity. Ammonia production in 1980 is estimated at 21 million tones. In the year 2000, U.S. ammonia production is estimated to be between 27 to 34 million tones with 19 to 31 million tons being produced using natural gas. A most likely value of 25 million tons of ammonia from natural gas feedstock is projected. As much as 20% of the energy from natural gas fuel could be saved if a more active catalyst could be developed that would reduce the operating pressure of ammonia synthesis to 1 atm.
Date: July 1, 1984
Creator: Young, J.K. & Johnson, D.R.
Partner: UNT Libraries Government Documents Department

The effect of operational charge-discharge on the slug rupture limit

Description: This report discusses the installation of operational charge-discharge equipment on the Hanford reactors has been proposed as a means of eliminating the reactor downtime required for charging and discharging the metal in the reactors. Additional benefits such as the minimization of the effects of slug ruptures, improved reactivity control, and improved metal utilization have become apparent during the investigation of the use of the equipment. Since the minimization of the effects of ruptures has been considered only qualitatively in previous justification documents for operational charge-discharge, the purpose of this document is to evaluate quantitatively the effect of such equipment on operation with a slug rupture limit.
Date: June 6, 1956
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department

Tube Wall Thickness Isotope Production Tubes

Description: Irradiation of process tubes containing appropriate parent materials has been proposed by Manufacturing as a method for obtaining new products from the Hanford Reactors. The process tubes would be removed at appropriate intervals and shipped to separations plants for recovery of the products. The tube residence in the reactor could be determined by the optimum irradiation period for isotope production rather than by the period required to corrode tubes of current design to the minimum permissible wall thickness at replacement. This paper, presents an analysis to determine the benefits from red reducing the initial wall thickness of the process tubes below the current 65 mils when the desired residence for isotope production is shorter than the residence based on maximum permissible internal corrosion for tubes of current design.
Date: July 10, 1963
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department

Forecast reactor water leaks

Description: Reactor water leaks cause outage time for locating and eliminating the leaks and for repairing damage paused by the vater that enters the reactor. The justification for equipment and process changes necessary for reducing the number of leaks and the resultant outage time is dependent on the number of leaks expected. This document presents an estimate of the future reactor water leak frequency and the average outage time charged to each leak. A water leak is defined as any entry of vater into the reactor moderator during operation. Future vater leaks are expected to result primarily from Van Stone flange failures and miscellaneous causes such as mechanical damage, fuel ruptures, and transverse cracks. It is assumed that continuous emphasis will be placed on corrosion monitoring to determine the tubes that must be replaced to prevent leaks because of internal and external corrosion. The number of water leaks is expected to average between 80 and 100 per year in the future. The normal-range of the number of leaks probably will be between 60 and 120 per year as a result of normal variation in the process tube physical condition. The number of outage hours charged per leak is expected to continue at the past average rate of approximately twelve hours per leak.
Date: June 3, 1963
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department

Current status -- Second generation process tube internal corrosion

Description: Seven water leaks during the past year because of internal corrosion of second generation process tubes have emphasized the need for additional corrosion information. Numerous out-of-pile and probolog examinations have been made to determine the nature of the corrosion, and mixer fuel elements currently are charged in central zone tubes in order to reduce the corrosion rates. This document presents the data obtained to date as a general description of the tube condition at the time when the mixer elements were adopted and outlines future action necessary to determine when the second generation tubes must be replaced because of internal corrosion.
Date: June 22, 1960
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department

Summary of the government/industry workshop on new materials and processing technologies for industrial applications

Description: This report presents a summary of the 1-day workshop conducted at Ann Arbor, Michigan, on April 16, 1992, between the National Center for Manufacturing Sciences (NCMS) and the US Department of Energy Advanced Industrial Materials Program (DOE AIM). The workshop objectives were to: (1) encourage collaboration between DOE, the DOE national laboratories, and NCMS material manufacturers and (2) assist the DOE AIM program in targeting research and development (R&D) more effectively. During the workshop, participants from industry and DOE laboratories were divided into three working groups. Representatives from the DOE national laboratories currently conducting major research programs for AIM were asked to be working group leaders. The groups developed recommendations for NCMS and AIM managers using a six-step process. As a result of the workshop, the groups identified problems of key concern to NCMS member companies and promising materials and processes to meet industry needs. Overall, the workshop found that the research agenda of DOE AIM should include working with suppliers to develop manufacturing technology. The agenda should not be solely driven by energy considerations, but rather it should be driven by industry needs. The role of DOE should be to ensure that energy-efficient technology is available to meet these needs.
Date: July 1, 1992
Creator: Young, J. K.
Partner: UNT Libraries Government Documents Department

Developments in computation, modeling and experimentation: Impacts on R&D

Description: The original objective was to document the feasibility of the coordinated research program sponsored by ECUT called ``Materials-by-Design (MBD).`` The MBD program funds research to develop hierarchical models to predict materials` performance based on microstructural information. This paper was specifically prepared for this meeting to help technical staff and their managers justify and plan for an advanced computer infrastructure within their companies. In order to do this, several additional objectives for this paper are (1) to foster an appreciation of the dramatic increase in computational power that have occurred over the last forty years, (2) to encourage better utilization of supercomputing in current scientific research by identifying current issues and opportunities, and (3) to promote anticipation and enthusiasm for the dramatic changes supercomputers currently being developed will offer scientists in the near future.
Date: October 1, 1989
Creator: Young, J. K.
Partner: UNT Libraries Government Documents Department

Effect of 6.6 pH process water on process tube and fuel element corrosion

Description: Reduction of the reactor process water pH from 6.9 to 6.6 at 100-B, D, DR, KF, and H currently is proposed in order to reduce the aluminum corrosion rate and the resultant outage time for water leaks, fuel ruptures, and process tube replacement. This document reviews the current knowledge of the effect of reducing the pH to 6.6 on aluminum corrosion. An estimate of the expected costs and benefits is included.
Date: May 20, 1963
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department