Problems Encountered During Four Years of ORR Operation (open access)

Problems Encountered During Four Years of ORR Operation

The over-all design and operation of ORR is reviewed in the light of four years of operating experience. Items discussed consist of the reactor components and instrumentation, reactor and pool cooling systems (including system cleanup), the emergency systems for electric power and reactor cooling, the waste-disposal systems (liquid, gaseous, and solid), and the building, itself. The ORR was the first of a class of reactors which combined the features of both the pool-reactor and tank-reactor types. Four years of operation indicated areas where problems of various degrees have developed. These problems are discussed. (auth)
Date: August 23, 1962
Creator: Tabor, W.H. & Costner, R.A. Jr.
Object Type: Report
System: The UNT Digital Library
Vacuum technology issues for the SSC (Superconducting Super Collider) (open access)

Vacuum technology issues for the SSC (Superconducting Super Collider)

The Superconducting Super Collider, to be built in Texas, will provide an energy of 40 TeV from colliding proton beams. This energy is twenty times higher than currently available from the only other cryogenic collider, the Fermilab Tevatron, and will allow experiments that can lead to a better understanding of the fundamental properties of matter. The energy scale and the size of the new machine pose intriguing challenges and opportunities for the its vacuum systems. The discussion will include the effects of synchrotron radiation on cryogenic beam tubes, cold adsorption pumps for hydrogen, methods of leak checking large cryogenic systems, the development of cold beam valves, and radiation damage to components, especially electronics. 9 figs., 1 tab.
Date: October 23, 1989
Creator: Joestlein, H.
Object Type: Article
System: The UNT Digital Library
Contained Events in Soudan 2 (open access)

Contained Events in Soudan 2

A search for contained events in the Soudan 2 nucleon decay detector has been made for the initial exposure of the first quarter of the 1.1 kiloton detector. This corresponds to an exposure of 0.083 kiloton years in the fiducial volume. We observe 5 {nu}{sub mu} candidate events and 5 {nu}{sub e} candidate events. Results of Monte Carlo simulations of neutrino events and proton decay events in Soudan 2 are compared. 6 refs., 3 figs.
Date: August 23, 1989
Creator: Allison, W. W. M.; Alner, G. J.; Ambats, I.; Balka, L.; Barr, G. D.; Benjamin, D. et al.
Object Type: Article
System: The UNT Digital Library
Enhanced durability and reactivity for zinc ferrite desulfurization sorbent (open access)

Enhanced durability and reactivity for zinc ferrite desulfurization sorbent

AMAX Research Development Center (AMAX R D) has been investigating methods for enhancing the reactivity and durability of the zinc ferrite desulfurization sorbent. Zinc ferrite sorbents are intended for use in desulfurization of hot coal gas in integrated gasification combined cycle (IGCC) or molten carbonate fuel cell (MCFC) applications. For the present program, the reactivity of the sorbent may be defined as its sulfur sorption capacity at the breakthrough point and at saturation in a bench-scale, fixed-bed reactor. Durability may be defined as the ability of the sorbent to maintain important physical characteristics such As size, strength, and specific surface area during 10 cycles of sulfidation and oxidation.
Date: February 23, 1987
Creator: Jha, M. C. & Baltich, L. K.
Object Type: Report
System: The UNT Digital Library
Torsional rigidity of central calorimeter module. [Using ANSYS computer code] (open access)

Torsional rigidity of central calorimeter module. [Using ANSYS computer code]

The torsional rigidity of the central calorimeter module is obtained using ANSYS.
Date: April 23, 1982
Creator: Leininger, M.
Object Type: Report
System: The UNT Digital Library
Computerized transportation model for the NRC Physical Protection Project. Versions I and II (open access)

Computerized transportation model for the NRC Physical Protection Project. Versions I and II

Details on two versions of a computerized model for the transportation system of the NRC Physical Protection Project are presented. The Version I model permits scheduling of all types of transport units associated with a truck fleet, including truck trailers, truck tractors, escort vehicles and crews. A fixed-fleet itinerary construction process is used in which iterations on fleet size are required until the service requirements are satisfied. The Version II model adds an aircraft mode capability and provides for a more efficient non-fixed-fleet itinerary generation process. Test results using both versions are included.
Date: February 23, 1978
Creator: Anderson, G.M.
Object Type: Report
System: The UNT Digital Library
OGRE-P1, A Monte Carlo Program for Computing Gamma-Ray Transmission Through Laminated Slabs (open access)

OGRE-P1, A Monte Carlo Program for Computing Gamma-Ray Transmission Through Laminated Slabs

A Monte Carlo IBM-7090 program (OGRE-P1) was written for calculation of the dose rate on one side of a slab owing to an isotropic, cosine, or collimated monoenergetic gamma radiation source on the other side of the slab. A maximum of 50 homogeneous regions are permitted. (auth)
Date: May 23, 1962
Creator: Trubey, K. K.; Penny, S. K. & Emmett, M. B.
Object Type: Report
System: The UNT Digital Library
Fiber-tile optical studies at Argonne (open access)

Fiber-tile optical studies at Argonne

In support of a fiber-tile calorimeter for SDC, we have done studies on a number of topics. The most basic problems were light output and uniformity of response. Using a small electron beam, we have studied fiber placement, tile preparation, wrapping and masking, fiber splicing, fiber routing, phototube response, and some degradation factors. We found two configurations which produced more light output than the others and reasonably uniform response. We have chosen one of these to go into production for the EM test module on the basis of fiber routing for ease of assembly of the calorimeter. We have also applied some of the tools we developed to CDF end plug tile uniformity, shower max testing and development for a couple of detectors, and development of better techniques for radiation damage studies. 18 figs.
Date: July 23, 1991
Creator: Underwood, D.G.; Morgan, D.J. & Proudfoot, J.
Object Type: Report
System: The UNT Digital Library
Characterizing W-2 SLSF experiment temperature oscillations using computer graphics. [Sodium Loop Safety Facility] (open access)

Characterizing W-2 SLSF experiment temperature oscillations using computer graphics. [Sodium Loop Safety Facility]

The W-2 SLSF (Sodium Loop Safety Facility) experiment was an instrumented in-reactor test performed to characterize the failure response of full-length, preconditioned LMFBR prototypic fuel pins to slow transient overpower (TOP) conditions. Although the test results were expected to confirm analytical predictions of upper level failure and fuel expulsion, an axial midplane failure was experienced. Extensive post-test analyses were conducted to understand all of the unexpected behavior in the experiment. (1) The initial post-test effort focused on the temperature oscillations recorded by the 54 thermocouples used in the experiment. In order to synthesize the extensive data records and identify patterns of behavior in the data records, a computer-generated film was used to present the temperature data recorded during the experiment.
Date: June 23, 1983
Creator: Smith, D. E.
Object Type: Article
System: The UNT Digital Library
Partitioning between sediment and porewater of radiocesium from Chernobyl fallout (open access)

Partitioning between sediment and porewater of radiocesium from Chernobyl fallout

As part of a joint USA/USSR Environmental Agreement to determine the distribution and concentration of Chernobyl radioactivity in the northwest Black Sea area, the sediment from eight stations was collected and analyzed to assess the ability of sediment from the northwest Black Sea to adsorb radiocesium. Two methods were used to determine partitioning between liquid and solid phases; batch tests and porewater separation. In the batch test, Cs-137 tracer was added to mixtures of sediment and bottom water, with contact solutions ranging from 85 Bq/ml to 1760 Bq/ml. The distribution ratios (R{sub D}) for individual batch tests ranged from 390 to 1770 ml/g. Isotherms were linear for all cores and R{sub D} values calculated from the slopes of the isotherms ranged from 660 to 1660 ml/g. A second approach was used to determine the partitioning of Cs-137 between the porewater and the sediment under more natural conditions. The top 2 cm of two cores were sectioned and the sediment and the porewater were separated. In both samples the sediment contained significant amounts of Cs-137 and Cs-134 indicating the presence of fallout from the Chernobyl reactor accident. There was no cesium activity observed in the porewater at a minimum detectable level …
Date: April 23, 1991
Creator: Fuhrmann, M.; Pietrzak, R. (Brookhaven National Lab., Upton, NY (USA)); Neiheisel, J. & Dyer, R. (Environmental Protection Agency, Washington, DC (USA))
Object Type: Article
System: The UNT Digital Library
Characterization techniques for high quality ICF targets (open access)

Characterization techniques for high quality ICF targets

To avoid the effects of fluid instabilities, stringent requirements must be imposed on the surface quality and wall thickness uniformity of fuel pellets used in Inertial Confinement Fusion compression experiments. A systematic method was developed for specifying the type of defects which must be avoided and for evaluating measurement techniques for their suitability for detecting these defects. A review is given of the techniques currently available and those under development to show the relationship between these capabilities and the current and future requirements for pellet uniformity. The speed of these techniques and the implications for automated production of fuel pellets for a reactor are discussed.
Date: March 23, 1979
Creator: Weinstein, B.W. & Hendricks, C.D.
Object Type: Article
System: The UNT Digital Library
Decontamination methods (open access)

Decontamination methods

This paper discusses decontamination methods for LWRs. Emphasis is on the chemical cleaning of primary systems and contaminated equipment and components. The equipment is composed primarily of stainless steel, Inconel, Zircaloy, and a few other materials. Variables affecting efficiency are discussed. 10 figures. (DLC)
Date: May 23, 1979
Creator: Perrigo, L. D. & Divine, J. R.
Object Type: Article
System: The UNT Digital Library
Comparative evaluation of effects of ozonated and chlorinated thermal discharges on estuarine and freshwater organisms (open access)

Comparative evaluation of effects of ozonated and chlorinated thermal discharges on estuarine and freshwater organisms

Although limited, the results of tests evaluating the comparative effects of chlorinated and ozonated thermal discharges on mummichog and white perch indicate that the biological effects of ozonation are much less severe than those of chlorination. The data also show white perch to be more sensitive than mummichog to the tested biocides. The relative effects of ozonation and chlorination in the behavioral studies were similar to those observed in the toxicity studies. Cough rates were higher in chlorinated than in ozonated thermal discharges at similar test concentrations. Avoidance concentrations of white perch were less than those for mummichog and all determined avoidance concentrations were less than lethal levels. The biological effects of any oxidizing biocide on a given species, however, are usually site specific. The chlorine avoidance concentrations of white perch tested at Bergen averaged 0.04 mg/1 total chlorine but averaged 0.06 mg/1 total chlorine when tested in Delaware estuarine waters. Although the amount of data obtained at Bergen is not large, it is indicative of the comparative biological effects in despoiled waters. Assuming such waters will be improved, however, concern then arises over the comparative effects of chlorination and ozonation in waters which support large populations of aquatic organisms. …
Date: July 23, 1979
Creator: Meldrim, J. W.; Holmstrom, E. R. & Balog, G. E.
Object Type: Report
System: The UNT Digital Library
Normal incident solar radiation measurements at Upton, New York (open access)

Normal incident solar radiation measurements at Upton, New York

Normal incident solar energy measurements made at Upton, L.I., New York, are reported and analyzed relative to the total energy received on a horizontal surface. A new method for estimating normal incident solar radiation is developed and used to determine average values for other east coast locations.
Date: August 23, 1979
Creator: Cottingham, J.G.
Object Type: Report
System: The UNT Digital Library
Environmental radiological studies downstream from the Rancho Seco Nuclear Power Generating Station - 1985. Appendices. Part II (open access)

Environmental radiological studies downstream from the Rancho Seco Nuclear Power Generating Station - 1985. Appendices. Part II

Eight appendices address the following concentrations of radionuclides: in fish; in frog legs; in crayfish; in sediments; in soil samples; in surface and ground water samples; in water hyacinths; and in beef samples.
Date: January 23, 1986
Creator: Noshkin, V. E.; Wong, K. M.; Eagle, R. J.; Brunk, J. L. & Jokela, T. A.
Object Type: Report
System: The UNT Digital Library
Value-impact analysis of regulations for the nuclear industry (open access)

Value-impact analysis of regulations for the nuclear industry

This paper summarizes a quantitative tool developed at Lawrence Livermore National Laboratory to aid the NRC in establishing Material Control and Accounting (MC and A) regulations for safeguarding Special Nuclear Material (SNM). Illustrative Value-Impact results of demonstrating the methodology at a facility handling SNM to evaluate alternative safeguards rules is given. The methodology developed also offers a useful framework for facility designers to choose safeguards measures that meet the NRC's criteria in a cost-effective manner. Furthermore, the methodology requires very modest computing capability and is straightforward to apply.
Date: June 23, 1980
Creator: Al-Ayat, R.; Judd, B. & Huntsman, J.
Object Type: Article
System: The UNT Digital Library
Collider detector beam line test table: a structural analysis (open access)

Collider detector beam line test table: a structural analysis

The apparatus which sweeps calorimeter and endwall modules through the beam during testing is called a beam line test table. Because of rather stringent requirements for the physical positioning of the modules an analysis is done here to determine the modifications to the current test table design which will minimize deflections of the table under load.
Date: December 23, 1983
Creator: Leininger, M.B.
Object Type: Report
System: The UNT Digital Library
Data report for the Southwest Residential Experiment Station, January 1982 (open access)

Data report for the Southwest Residential Experiment Station, January 1982

Physical performance data obtained from the photovoltaic energy systems under test at the Southwest Residential Experiment Station in Las Cruces, New Mexico are tabulated and graphed for the month of January, 1982. Data drawn from the Residential Data System (RDS) appears in several formats. A one-page summary is provided as well as a more detailed hour-by-hour tabulation for an average day of the month. Energy histograms are provided, based on RDS data and recording kilowatt hour meters. The histograms also present horizontal and plane-of-array insolation data as well as comments that explain data and/or energy production anomalies. (LEW)
Date: February 23, 1982
Creator: Lieberman, M.; Hai, O. Y.; Hocking, G. & Whitaker, C.
Object Type: Report
System: The UNT Digital Library
Delayed-fission properties of neutron-deficient americium nuclei (open access)

Delayed-fission properties of neutron-deficient americium nuclei

Characteristics of the delayed-fission decay mode in light americium nuclei have been investigated. Measurements on the unknown isotopes {sup 230}Am and {sup 236}Am were attempted, and upper limits on the delayed-fission branches of these nuclei were determined. Evidence of the existence of {sup 236}Am was observed in radiochemical separations. Total kinetic energy and mass-yield distributions of the electron-capture delayed-fission mode were measured for {sup 232}Am (t{sub 1/2} = 1.31 {plus minus} 0.04 min) and for {sup 234}Am (t{sub 1/2} = 2.32 {plus minus} 0.08 min), and delayed-fission probabilities of 6.9 {times} 10{sup {minus}4} and 6.6 {times} 10{sup {minus}5}, respectively, were determined. The total kinetic energy and the asymmetric mass-yield distributions are typical of fission of mid-range actinides. No discernible influence of the anomalous triple-peaked mass division characteristic of the thorium-radium region was detected. Measurements of the time correlation between the electron-capture x-rays and the subsequent fission conform that the observed fissions arise from the electron-capture delayed-fission mechanism. Delayed fission has provided a unique opportunity to extend the range of low-energy fission studies to previously inaccessible regions. 71 refs., 44 figs., 13 tabs.
Date: October 23, 1989
Creator: Hall, H.L. (California Univ., Berkeley, CA (USA). Dept. of Chemistry)
Object Type: Report
System: The UNT Digital Library
Development of advanced NO sub x control concepts for coal-fired utility boilers (open access)

Development of advanced NO sub x control concepts for coal-fired utility boilers

Hybrid technologies for reduction of NO{sub x} emissions from coal fired utility boilers may offer greater levels of NO{sub x} control than the sum of the individual technologies, leading to more cost effective emissions control strategies. Energy and Environmental Research Corporation had developed a hybrid NO{sub x} control strategy involving two proprietary concepts which has the potential to meet the US Department of Energy's goal at a significant reduction in cost compared to existing technology. The process has been named CombiNO{sub x}. CombiNO{sub x} is the integration of three separate NO control technologies: (1) Gas Reburning, (2) CO-Promoted Selective Non-Catalytic Reduction, and (3) Methanol Injection/NO{sub 2} Scrubbing.
Date: December 23, 1991
Creator: Newhall, J.; England, G. & Seeker, W. R.
Object Type: Report
System: The UNT Digital Library
Simple spherical ablative-implosion model (open access)

Simple spherical ablative-implosion model

A simple model of the ablative implosion of a high-aspect-ratio (shell radius to shell thickness ratio) spherical shell is described. The model is similar in spirit to Rosenbluth's snowplow model. The scaling of the implosion time was determined in terms of the ablation pressure and the shell parameters such as diameter, wall thickness, and shell density, and compared these to complete hydrodynamic code calculations. The energy transfer efficiency from ablation pressure to shell implosion kinetic energy was examined and found to be very efficient. It may be possible to attach a simple heat-transport calculation to our implosion model to describe the laser-driven ablation-implosion process. The model may be useful for determining other energy driven (e.g., ion beam) implosion scaling.
Date: June 23, 1980
Creator: Mayer, F. J.; Steele, J. T. & Larsen, J. T.
Object Type: Report
System: The UNT Digital Library
Mechanical properties of high-current multifilamentary Nb/sub 3/Sn conductors (open access)

Mechanical properties of high-current multifilamentary Nb/sub 3/Sn conductors

Nb/sub 3/Sn is a strain-sensitive superconductor which exhibits large changes in properties for strains of less than 1 percent. The critical current density at 12 T undergoes a reversible degradation of a factor of two for compressive strains of about 1 percent and undergoes an irreversible degradation for tensile strains on the Nb/sub 3/Sn greater than 0.2 percent. Consequently, the successful application of Nb/sub 3/Sn in large high-field magnets requires a complete understanding of the mechanical properties of the conductor. One conductor which is being used for many applications consists of filaments of Nb/sub 3/Sn in a bronze matrix, and much progress has been made in understanding the mechanical behavior of this composite. The Nb/sub 3/Sn filaments are placed in compression due to the differential thermal contraction between Nb/sub 3/Sn and bronze which occurs when the composite is cooled from the Nb/sub 3/Sn formation temperature (typically 700/sup 0/C) to the 4.2/sup 0/K operating temperature. The general behavior of the critical current when this conductor is subjected to a tensile stress is an increase to a maximum when the compressive strain on the Nb/sub 3/Sn is relieved, followed by a decrease as the Nb/sub 3/Sn filemants are placed in tension. The …
Date: May 23, 1980
Creator: Scanlan, R. M.; Hoard, R. W.; Cornish, D. N. & Zbasnik, J. P.
Object Type: Article
System: The UNT Digital Library
Mechanical and thermal behavior of a prototype support structure for a large silicon vertex detector (BCD) (open access)

Mechanical and thermal behavior of a prototype support structure for a large silicon vertex detector (BCD)

The Bottom Collider Detector (BCD) has been proposed as a device to study large numbers of events containing B mesons. To identify secondary vertices in hadronic events it will employ the most ambitious silicon strip tracking detector proposed to-date. This report will discuss results from measurements on a first mechanical/thermal model of the vertex detector support structure. The model that was built and used for the studies described here is made of brass. Brass was used because it is readily available and easily assembled by soft soldering, and, for appropriate thicknesses, it will behave similarly to the beryllium that will be used in the actual detector. The trough was built to full scale with the reinforcement webbing and the cooling channels in place. There were no detector modules in place. We plan, however, to install modules in the trough in the future. The purpose of the model was to address two concerns that have arisen about the proposed structure of the detector. The first is whether or not the trough will be stable enough. The trough must be very light in weight yet have a high degree of rigidity. Because of the 3m length of the detector there is question …
Date: August 23, 1989
Creator: Mulderink, H.; Michels, N.; Joestlein, H. (La Grange High School, IL (USA); Apple Valley High School, Rosemont, MN (USA) & Fermi National Accelerator Lab., Batavia, IL (USA))
Object Type: Report
System: The UNT Digital Library
Using computer graphics to analyze the placement of neutral-beam injectors for the Mirror Fusion Test Facility (open access)

Using computer graphics to analyze the placement of neutral-beam injectors for the Mirror Fusion Test Facility

To optimize the neutral-beam current incident on the fusion plasma and limit the heat load on exposed surfaces of the Mirror Fusion Test Facility magnet coils, impingement of the neutral beams on the magnet structure must be minimized. Also, placement of the neutral-beam injectors must comply with specifications for neutral-current heating of the plasma and should allow maximum flexibility to accommodate alternative beam aiming patterns without significant hardware replacement or experiment down-time. Injector placements and aimings are analyzed by means of the Structural Analysis Movie Post Processor (SAMPP), a general-purpose graphics code for the display of three-dimensional finite-element models. SAMPP is used to visually assemble, disassemble, or cut away sections of the complex three-dimensional apparatus, which is represented by an assemblage of 8-node solid finite elements. The resulting picture is used to detect and quantify interactions between the structure and the neutral-particle beams.
Date: September 23, 1977
Creator: Horvath, J. A.
Object Type: Article
System: The UNT Digital Library