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Results from the Soviet-American gallium experiment
A radiochemical {sup 71}Ga-{sup 71}Ge experiment to determine the primary flux of neutrinos from the Sun has begun operation at the Baksan Neutrino Observatory. The number of {sup 71}Ge atoms extracted from thirty tons of gallium was measured in five runs during the period of January to July 1990. Assuming that the extraction efficiency for {sup 71}Ge atoms produced by solar neutrinos is the same as from natural Ge carrier, we observed the capture rate to be 20 + 15/{minus}20 (stat) {plus_minus} 32 (syst) SNU, resulting in a limit of less than 79 SNU (90% CL). This is to be compared with 132 SNU predicted by the Standard Solar Model.
Date:
December 31, 1991
Creator:
Abazov, A. I.; Anosov, O. L.; Faizov, E. L.; Gavrin, V. N.; Kalikhov, A. V.; Knodel, T. V. et al.
Object Type:
Report
System:
The UNT Digital Library
Development of novel copper-based sorbents for hot-gas cleanup. Technical report, September 1--November 30, 1991
The objective of this investigation is to evaluate several novel copper-based binary oxides for their suitability as regenerable sorbents for hot gas cleanup application in the temperature range of 650{degree} to 850{degree}C (1200{degree}--1550{degree}F). To achieve this objective, several novel copper-based binary oxide sorbents will be prepared. Experimental tests will be conducted at ambient pressure to determine the stability, sulfidation capacity, regenerability, and sulfidation kinetics of the novel sorbents. Tests will also be conducted at high pressure for the determination of the sulfidation reactivity, regenerability, and durability of the sorbents. The attrition characteristics of the sorbents will also be determined.
Date:
December 31, 1991
Creator:
Abbasian, J.
Object Type:
Report
System:
The UNT Digital Library
Stabilization and/or regeneration of spent sorbents from coal gasification. Technical report, September 1--November 30, 1991
The objective of this investigation is to determine the effects of SO{sub 2} partial pressure and reaction temperature on the conversion of sulfide containing solid wastes from coal gasifiers to stable and environmentally acceptable calcium-sulfate, while preventing the release of sulfur dioxide through undesirable side reactions during the stabilization step. An additional objective of this program is to investigate the use of the Spent Sorbent Regeneration Process (SSRP) to regenerate spent limestone, from a fluidized-bed gasifier with in-bed sulfur capture, for recycling to the gasifier. To achieve these objectives, selected samples of partially sulfided sorbents will be reacted with oxygen at a variety of operating conditions under sufficient SO{sub 2} partial pressure to prevent release of sulfur from the solids during stabilization that reduces the overall sorbent utilization. Partially sulfided limestone will also be regenerated with water to produce calcium hydroxide and release sulfur as H{sub 2}S. The regenerated sorbent will be dewatered, dried and pelletized. The reactivity of the regenerated sorbent toward H{sub 2}S will also be determined. During this quarter sulfidation tests were conducted in a quartz fluidized-bed reactor in which the selected calcium-based sorbents were first calcined and then were reacted with hydrogen sulfide at ambient pressure …
Date:
December 31, 1991
Creator:
Abbasian, J.
Object Type:
Report
System:
The UNT Digital Library
A novel approach to highly dispersing catalytic materials in coal for gasification. Eighth quarterly report, July 1, 1991--September 30, 1991
This project seeks to develop a technique, based on coal surface properties, for highly dispersing catalysts in coal for gasification and to investigate the potential of using potassium carbonate and calcium acetate mixtures as catalyst for coal gasification. The lower cost and high catalytic activity of the latter compound will produce economic benefits by reducing the amount of K{sub 2}CO{sub 3} required for high coal char activities. The effects of potassium impregnation conditions (pH and coal surface charge) on the reactivities, in carbon dioxide, of chars derived from demineralized lignite, subbituminous and bituminous coals have been determined. Impregnation of the acid-leached coal with potassium from strongly acidic solutions resulted in initial slow char reactivity which progressively increased with reaction time. Higher reactivities were obtained for catalyst (potassium) loaded at pH 6 or 10. The dependence of char gasification rates on catalyst addition pH increased in the order: pH 6 {approximately} pH 10 {much_gt} pH 1.
Date:
December 31, 1991
Creator:
Abotsi, G. M. K. & Bota, K. B.
Object Type:
Report
System:
The UNT Digital Library
Development of a stable cobalt-ruthenium Fischer-Tropsch catalyst. Technical progress reports No. 7 and 8, April 1, 1991--September 30, 1991
The objective of this contract is to examine the relationship between catalytic properties and the function of cobalt Fischer-Tropsch catalysts and to apply this fundamental knowledge to the development of a stable cobalt-based catalyst with a low methane-plus-ethane selectivity for use in slurry reactors. An experimental cobalt catalyst 585R2723 was tested three times in the fixed-bed reactor. The objective of the tests was to identify suitable testing conditions for screening catalyst. The {alpha}-alumina was determined to be a suitable diluent medium for controlling the catalyst bed temperature close to the inlet temperature. With 13 g of catalyst and 155 g of diluent, the catalyst maximum temperature were within 2{degree}C from the inlet temperatures. As a result of this work, 210{degree}C and 21 atm were shown to result in low methane selectivity and were used as initial conditions in the catalyst screening test. Ethane, which along with methane is undesirable, is typically produced with low selectivity and follows the same trend as methane. Other work reported here indicated that methane selectivity increases with increasing temperature but is not excessively high at 230{degree}C. Consequently, the catalyst screening test should include an evaluation of the catalyst performance at 230{degree}C. During Run 67, the …
Date:
December 31, 1991
Creator:
Abrevaya, H.
Object Type:
Report
System:
The UNT Digital Library
Chronic lung injury risk estimates for urban areas having ozone patterns similar to those in the Northeast
This paper describes the approach and result of an assessment of health risks associated with long-term exposure to ozone. The health endpoint of interest is the probability of formation of mild lesions in the centriacinar region of the lung among children living in New York City. The risk model incorporates an exposure model and a health model. The exposure model is preliminary results of the probabilistic NAAQS Exposure Model (P-NEM) for ozone, and the health model is the judgments of active researchers about the likelihood of formation of ozone-induced lesions in the human lung. Children and New York City were chosen as the population and city of interest because it is believed that children are more sensitive to ozone than any other group of people, and New York City is more representative of other urban areas than Los Angeles, the other city of which P-NEM exposure results are available. Risk results are presented for ten exposure distributions generated by P-NEM, two air quality scenarios (``as-is`` and ``attainment``), and two exposure periods (1 and 10 ozone seasons). The results vary across experts, are not very sensitive to variations in P-NEM exposure distributions, are lower for attainment conditions than as-is conditions, and …
Date:
December 31, 1991
Creator:
Absil, M.; Narducci, P.; Whitfield, R. & Richmond, H. M.
Object Type:
Article
System:
The UNT Digital Library
Plutonium recovery from spent reactor fuel by uranium displacement
This report discusses a process for separating uranium values and transuranic values from fission products containing rare earth values when the values which are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride. Then the solid cathode with the uranium metal deposited thereon is removed and molten cadmium having uranium dissolved therein is brought into contact with the electrolyte resulting in chemical transfer of plutonium values from the electrolyte to the molten cadmium and transfer of uranium values from the molten cadmium to the electrolyte until the first ratio of plutonium chloride to uranium chloride is re-established.
Date:
December 31, 1991
Creator:
Ackerman, J. P.
Object Type:
Patent
System:
The UNT Digital Library
Magnesium transport extraction of transuranium elements from LWR fuel
This report discusses a process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl{sub 2} and a U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800{degrees}C to about 850{degrees}C to produce additional uranium metal which dissolves in the U-Fe alloy raising the uranium concentration and having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein. The CaCl{sub 2} having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO{sub 2}. The Ca metal and CaCl{sub 2} is recycled to reduce additional oxide fuel. The U-Fe alloy having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with Mg metal which takes up the actinide and rare earth fission product metals. The U-Fe …
Date:
December 31, 1991
Creator:
Ackerman, J. P.; Battles, J. E.; Johnson, T. R.; Miller, W. E. & Pierce, R. D.
Object Type:
Patent
System:
The UNT Digital Library
INEL BNCT Program: Volume 5, No. 9. Bulletin, September 1991
This Bulletin presents a summary of accomplishments and highlights of the Idaho National Engineering Laboratory`s (INEL) Boron Neutron Capture Therapy (BNCT) Program for September 1991. This bulletin includes information on the brain tumor and melanoma research programs, Power Burst Facility (PBF) technical support and modifications, PBF operations, and updates to the animal data charts.
Date:
December 31, 1991
Creator:
Ackermann, A. L.
Object Type:
Report
System:
The UNT Digital Library
An analytical assessment of the chemical form of fission products during postulated severe accidents in the SRS production reactors
An analysis has been performed to determine the principal chemical forms for the structural and fission product elements during a postulated severe core damage accident in tritium powered core in the Savannah River Site (SRS) reactors. These reactors are powered with UAl{sub x} fuel and are used for the production of weapons materials. Six core elements, cesium, iodine, tellurium, strontium, barium, and lithium, were emphasized in this analysis. Other elements also included were aluminum, hydrogen, oxygen, uranium, molybdenum, silicon, zirconium, magnesium, iron, chromium, nickel, cadmium, zinc, cooper, manganese, nitrogen, and argon. The masses of each of the constituents used in the analyses were based on end-or-core life masses for the structural and fission product elements and on core gas volume for steam, N, and Ar. A chemical equilibrium analysis was performed using the Facility for Analysis of Chemical Thermodynamics (FACT) computer code at three temperatures (800, 1100, 1400 K) and two pressures (1 and 10 atmospheres). These temperatures and pressures are typical for postulated severe core accidents in the ATR.
Date:
December 31, 1991
Creator:
Adams, J. P.
Object Type:
Article
System:
The UNT Digital Library
Fission product transport and behavior during two postulated loss of flow transients in the air
This document discusses fission product behavior during two postulated loss-of-flow accidents (leading to high- and low-pressure core degradation, respectively) in the Advanced Test Reactor (ATR). These transients are designated ATR Transient LCPI5 (high-pressure) and LPP9 (low-pressure). Normally, transients of this nature would be easily mitigated using existing safety systems and procedures. In these analyses, failure of these safety systems was assumed so that core degradation and fission product release could be analyzed. A probabilistic risk assessment indicated that the probability of occurrence for these two transients is of the order of 10{sup {minus}5 }and 10{sup {minus}7} per reactor year for LCP15 and LPP9, respectively.
Date:
December 31, 1991
Creator:
Adams, J. P. & Carboneau, M. L.
Object Type:
Article
System:
The UNT Digital Library
Steam generator secondary pH during a steam generator tube rupture
The Nuclear Regulatory Commission requires utilizes to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant. The SGTR analysis includes assumptions regarding the partitioning of iodine between liquid and vapor in steam generator secondary. Experimental studies have determined that the partitioning of iodine in water is very sensitive to the pH. Based on this experimental evidence, the NRC requested the INEL to perform an analytical assessment of secondary coolant system (SCS) pH during an SGTR. Design basis thermal and hydraulic calculations were used together with industry standard chemistry guidelines to determine the SCS chemical concentrations during an SGTR. These were used as input to the Facility for Analysis of Chemical Thermodynamics computer system to calculate the equilibrium pH in the SCS at various discrete time during an SGTR. The results of this analysis indicate that the SCS pH decreases from the initial value of 8.8 to approximately 6.5 by the end of the transient, independent of PWR design.
Date:
December 1, 1991
Creator:
Adams, J. P. & Peterson, E. S.
Object Type:
Report
System:
The UNT Digital Library
Steam generator secondary pH during a steam generator tube rupture
The Nuclear Regulatory Commission requires utilizes to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant. The SGTR analysis includes assumptions regarding the partitioning of iodine between liquid and vapor in steam generator secondary. Experimental studies have determined that the partitioning of iodine in water is very sensitive to the pH. Based on this experimental evidence, the NRC requested the INEL to perform an analytical assessment of secondary coolant system (SCS) pH during an SGTR. Design basis thermal and hydraulic calculations were used together with industry standard chemistry guidelines to determine the SCS chemical concentrations during an SGTR. These were used as input to the Facility for Analysis of Chemical Thermodynamics computer system to calculate the equilibrium pH in the SCS at various discrete time during an SGTR. The results of this analysis indicate that the SCS pH decreases from the initial value of 8.8 to approximately 6.5 by the end of the transient, independent of PWR design.
Date:
December 1, 1991
Creator:
Adams, J. P. & Peterson, E. S.
Object Type:
Report
System:
The UNT Digital Library
Advanced Processing Technology semiannual report, March--December 1991. Volume 1, Number 1
This first issue of the APT Semiannual Report focuses on APT`s defense-related technologies. These technologies are a continuation of the research, development, and engineering work performed by LLNLs Special Isotope Separation (SIS) Program. SIS was the first large-scale DOE venture that had environmentally conscious manufacturing processes and facilities as its deliverables. The objectives were to create a facility where the only outputs were either usable products or disposable wastes, and to comply with existing and anticipated federal, state, and local regulations related to safeguards, security, health and safety. To meet these objectives, revolutionary changes were needed in plutonium processing operations, chemistry, and equipment. New processes had to be developed that enhanced worker safety, minimized operator radiation dose, minimized waste at the point of generation, and provided for built-in recycling of residues. The SIS Program developed and demonstrated the technology (both chemistry and physics) necessary to provide plutonium with individual isotopic tailoring. This process made it possible to transform fuel-grade plutonium into weapon-grade material. However, due to the changing world political climate, the country`s need for plutonium to make new weapons has decreased dramatically. As a result, the planned SIS plutonium-separation plant will not be built. After the SIS Program was …
Date:
December 31, 1991
Creator:
Adamson, M. & Kline-Simon, K.
Object Type:
Report
System:
The UNT Digital Library
Harvard-MIT research program in short-lived radiopharmaceuticals. Technical progress report, 1991
This report presents research on radiopharmaceuticals. The following topics are discussed: antibody labeling with positron-emitting radionuclides; antibody modification for radioimmune imaging; labeling antibodies; evaluation of technetium acetlyacetonates as potential cerebral blood flow agents; and studies in technetium chemistry. (CBS)
Date:
December 31, 1991
Creator:
Adelstein, S. J.
Object Type:
Report
System:
The UNT Digital Library
A computational model for coal transport and combustion. Quarterly technical progress report, September 1--November 30, 1991
During the last three months, considerable progress has been made in formulation of the thermodynamically consistent rate dependent model for turbulent two-phase flows. The basic governing equations were derived and the case of a simple shear flow was also analyzed. Preliminary comparisons with the available experimental data were also performed. The thermodynamical approach was successfully formulated for developing a stress transport model for granular flows. The appropriate constitutive equations were derived and it was shown that the model contains the existing kinetic theory results as special limiting cases. The formulation also allows for the possible rotation of the frame of reference. Using a kinetic-based model which includes frictional losses, several rapid granular shear flows including Couette and gravity flows were analyzed. Preliminary comparisons with experimental data were also performed. The experimental setup for the simple shear flow device is being designed. The procedure for constructing the device is being studied.
Date:
December 31, 1991
Creator:
Ahmadi, G.
Object Type:
Report
System:
The UNT Digital Library
Novel reactor configuration for synthesis gas conversion to alcohols. Quarterly report, July 1, 1991--September 30, 1991
Our objectives during this quarter were to complete construction and shake down runs on our new reactor assemblies, obtain activity data on the catalyst employing the slurry reactor, incorporate pressure drop and change in number of moles options into our reactor simulation code and start experiments in the trickle bed reactor.
Date:
December 31, 1991
Creator:
Akgerman, A. & Anthony, R. G.
Object Type:
Report
System:
The UNT Digital Library
IMC Post: A Comparison of QC Tensile Tests, and Finite Element Analysis Results
None
Date:
December 25, 1991
Creator:
Alforque, R. & Sondericker, J. H.
Object Type:
Report
System:
The UNT Digital Library
Vibration monitoring of EDF rotating machinery using artificial neural networks
Vibration monitoring of components in nuclear power plants has been used for a number of years. This technique involves the analysis of vibration data coming from vital components of the plant to detect features which reflect the operational state of machinery. The analysis leads to the identification of potential failures and their causes, and makes it possible to perform efficient preventive maintenance. Earlydetection is important because it can decrease the probability of catastrophic failures, reduce forced outgage, maximize utilization of available assets, increase the life of the plant, and reduce maintenance costs. This paper documents our work on the design of a vibration monitoring methodology based on neural network technology. This technology provides an attractive complement to traditional vibration analysis because of the potential of neural networks to operate in real-time mode and to handle data which may be distorted or noisy. Our efforts have been concentrated on the analysis and classification of vibration signatures collected by Electricite de France (EDF). Two neural networks algorithms were used in our project: the Recirculation algorithm and the Backpropagation algorithm. Although this project is in the early stages of development it indicates that neural networks may provide a viable methodology for monitoring and …
Date:
December 31, 1991
Creator:
Alguindigue, I. E.; Loskiewicz-Buczak, A.; Uhrig, R. E.; Hamon, L. & Lefevre, F.
Object Type:
Article
System:
The UNT Digital Library
Collection and analysis of existing data for waste tank mechanistic analysis
Pacific Northwest Laboratory (PNL) is conducting this study for Westinghouse Hanford Company (Westinghouse Hanford), a contractor for the US Department of Energy (DOE). The purpose of the work is to study possible mechanisms and fluid dynamics contributing to the periodic release of gases from the double-shell waste storage tanks at the Hanford Site in Richland, Washington. The waste inside the tank is generating and periodically releasing potentially flammable gases into the tank's vent system according to observations. Questions scientists are trying to answer are: (1) How are these gases generated (2) How did these gases become trapped (3) What causes the periodic gas releases (4) And, what is the mechanism of the gas releases To develop a safe mitigation strategy, possible physical mechanisms for the periodic release of flammable gases need to be understood. During initial work, PNL has obtained, correlated, analyzed, and compared data with expected physical properties, defined mechanisms; and prepared initial models of gas formation and retention. This is the second interim report summarizing the status of the work done to data.
Date:
December 1, 1991
Creator:
Allemann, R. T.; Antoniak, Z. I.; Friley, J. R.; Haines, C. E.; Liljegren, L. M. & Somasundaram, S.
Object Type:
Report
System:
The UNT Digital Library
Collection and analysis of existing data for waste tank mechanistic analysis. Progress report, December 1990
Pacific Northwest Laboratory (PNL) is conducting this study for Westinghouse Hanford Company (Westinghouse Hanford), a contractor for the US Department of Energy (DOE). The purpose of the work is to study possible mechanisms and fluid dynamics contributing to the periodic release of gases from the double-shell waste storage tanks at the Hanford Site in Richland, Washington. The waste inside the tank is generating and periodically releasing potentially flammable gases into the tank`s vent system according to observations. Questions scientists are trying to answer are: (1) How are these gases generated? (2) How did these gases become trapped? (3) What causes the periodic gas releases? (4) And, what is the mechanism of the gas releases? To develop a safe mitigation strategy, possible physical mechanisms for the periodic release of flammable gases need to be understood. During initial work, PNL has obtained, correlated, analyzed, and compared data with expected physical properties, defined mechanisms; and prepared initial models of gas formation and retention. This is the second interim report summarizing the status of the work done to data.
Date:
December 1, 1991
Creator:
Allemann, R. T.; Antoniak, Z. I.; Friley, J. R.; Haines, C. E.; Liljegren, L. M. & Somasundaram, S.
Object Type:
Report
System:
The UNT Digital Library
Mechanistic analysis of double-shell tank gas release
Pacific Northwest Laboratory (PNL) is studying possible mechanisms and fluid dynamics contributing to the periodic release of gases from the double-shell waste storage tanks at Hanford. This study is being conducted for Westinghouse Hanford Company (WHC), a contractor for the US Department of Energy (DOE). This interim report discusses the work done through November 1990. Safe management of the wastes at Hanford depends on an understanding of the chemical and physical mechanisms that take place in the waste tanks. An example of the need to understand these mechanisms is tank 101-SY. The waste in this tank is generating and periodically releasing potentially flammable gases into the tank vent system according to observations of the tank. How these gases are generated and become trapped, the causes of periodic release, and the mechanism of the release are not known in detail. In order to develop a safe mitigation strategy, possible physical mechanisms for the periodic release of flammable gases need to be understood.
Date:
December 1, 1991
Creator:
Allemann, R. T.; Antoniak, Z. I.; Friley, J. R.; Haines, C. E.; Liljegren, L. M. & Somasundaram, S.
Object Type:
Report
System:
The UNT Digital Library
Mechanistic analysis of double-shell tank gas release. Progress report, November 1990
Pacific Northwest Laboratory (PNL) is studying possible mechanisms and fluid dynamics contributing to the periodic release of gases from the double-shell waste storage tanks at Hanford. This study is being conducted for Westinghouse Hanford Company (WHC), a contractor for the US Department of Energy (DOE). This interim report discusses the work done through November 1990. Safe management of the wastes at Hanford depends on an understanding of the chemical and physical mechanisms that take place in the waste tanks. An example of the need to understand these mechanisms is tank 101-SY. The waste in this tank is generating and periodically releasing potentially flammable gases into the tank vent system according to observations of the tank. How these gases are generated and become trapped, the causes of periodic release, and the mechanism of the release are not known in detail. In order to develop a safe mitigation strategy, possible physical mechanisms for the periodic release of flammable gases need to be understood.
Date:
December 1, 1991
Creator:
Allemann, R. T.; Antoniak, Z. I.; Friley, J. R.; Haines, C. E.; Liljegren, L. M. & Somasundaram, S.
Object Type:
Report
System:
The UNT Digital Library
In situ transmission electron microscope studies of irradiation-induced and irradiation-enhanced phase changes
Motivated at least initially by materials needs for nuclear reactor development, extensive irradiation effects studies employing TEMs have been performed for several decades, involving irradiation-induced and irradiation-enhanced, microstructural changes, including phase transformations such as precipitation, dissolution, crystallization, amorphization, and order-disorder phenomena. From the introduction of commercial high voltage electron microscopes (HVEM) in the mid-1960s, studies of electron irradiation effects have constituted a major aspect of HVEM application in materials science. For irradiation effects studies two additional developments have had particularly significant impact: (1) The availability of TEM specimen holders in which specimen temperature can be controlled in the range 10--2200 K; and (2) the interfacing of ion accelerators which allows in situ TEM studies of irradiation effects and the ion beam modification of materials within this broad temperature range. This paper treats several aspects of in situ studies of electron and ion beam-induced and enhanced phase changes, including the current state of in situ ion beam capability internationally, and presents two case studies involving in situ experiments performed in an HVEM to illustrate the dynamics of such an approach in materials research.
Date:
December 31, 1991
Creator:
Allen, C. W.
Object Type:
Article
System:
The UNT Digital Library