Degree Level

CP VIOLATION HIGHLIGHTS: CIRCA 2005 (open access)

CP VIOLATION HIGHLIGHTS: CIRCA 2005

Recent highlights in CP violation phenomena, are reviewed. B-factory results imply that, CP-violation phase in the CKM matrix is the dominant contributor to the observed CP violation in K and B-physics. Deviations from the predictions of the CKM-paradigm due to beyond the Standard Model CP-odd phase are likely to be a small perturbation. Therefore, large data sample of clean B's will be needed. Precise determination of the unitarity triangle, along with time dependent CP in penguin dominated hadronic and radiative modes are discussed. Null tests in B, K and top-physics and separate determination of the K-unitarity triangle are also emphasized.
Date: February 27, 2005
Creator: A., SONI
Object Type: Article
System: The UNT Digital Library
Management and Retrieval of Historical Nuclear Waste Previously Prepared and Concreted for Sea Disposal (open access)

Management and Retrieval of Historical Nuclear Waste Previously Prepared and Concreted for Sea Disposal

This paper describes the approach of dealing with an historic legacy of pharmaceutical manufacturing operations, which arose as a result of the temporary cessation of sea disposal in 1983. The result of that cessation was an accumulation of 1,000 reinforced concrete lined steel drums containing intermediate level nuclear waste of mixed chemical and physical form. Included are the steps taken which established a policy, the resulting strategy and the unique and innovative means by which the plan was implemented. The objective was to reduce the financial liability of the waste contained within the drums by removing those portions that had already decayed, segregating the waste in terms of non disposable and disposable isotopes, size reduction and long-term storage of the residues in a retrievable waste form. As part of this process the Company established a UK strategy which would ensure that the Company was self sufficient in radioactive waste handling storage facilities until the provision of a national facility, currently predicted to be approximately 2040.
Date: February 27, 2002
Creator: Abbott, H. & Davies, E.
Object Type: Article
System: The UNT Digital Library
Observation of the narrow state x (3872) --> j/psi pi+ pi- in pbar p collisions at s**(1/2) = 1.96 tev (open access)

Observation of the narrow state x (3872) --> j/psi pi+ pi- in pbar p collisions at s**(1/2) = 1.96 tev

The authors report the observation of a narrow state decaying into J/{psi}{pi}{sup +}{pi}{sup -} and produced in 220 pb{sup -1} of {bar p}p collisions at {radical}s = 1.96 TeV in the CDF II experiment. They observe 730 {+-} 90 decays. The mass is measured to be 3871.3 {+-} 0.7(stat) {+-} 0.4(syst) MeV/c{sup 2}, with an observed width consistent with the detector resolution. This is in agreement with the recent observation by the Belle Collaboration of the X(3872) meson.
Date: February 27, 2004
Creator: Acosta, D.
Object Type: Report
System: The UNT Digital Library
Building Material Characterization Using a Concrete Floor and Wall Contamination Profiling Technology (open access)

Building Material Characterization Using a Concrete Floor and Wall Contamination Profiling Technology

Certain radioisotopes can penetrate concrete and contaminate the concrete well below the surface. The challenge is to determine the extent and magnitude of the contamination problem in real-time. The concrete profiling technology, TRUPROSM in conjunction with portable radiometric instrumentation produces a profile of radiological or chemical contamination through the material being studied. The data quality, quantity, and representativeness may be used to produce an activity profile from the hot spot surface into the material being sampled. This activity profile may then be expanded to ultimately characterize the facility and expedite waste segregation and facility closure at a reduced cost and risk. Performing a volumetric concrete or metal characterization safer and faster (without lab intervention) is the objective of this characterization technology. This way of determining contamination can save considerable time and money. Currently, concrete core bores are shipped to certified laboratories where the concrete residue is run through a battery of tests to determine the contaminants. The existing core boring operation volatilizes or washes out some of the contaminants (like tritium) and oftentimes cross-contaminates the area around the core bore site. The volatilization of the contaminants can lead to airborne problems in the immediate vicinity of the core bore. Cross-contamination …
Date: February 27, 2003
Creator: Aggarwal, S.; Charters, G. & Thacker, D.
Object Type: Article
System: The UNT Digital Library
Commercial Application of Plasma Mass Separation in the Archimedes Filter Plant (open access)

Commercial Application of Plasma Mass Separation in the Archimedes Filter Plant

This paper describes the commercial application of an innovative plasma mass separator called the Archimedes Filter to a pre-treatment plant that can be integrated into the U.S. Department of Energy (DOE) Hanford and Savannah River Sites to significantly enhance the treatment of radioactive high-level waste. The output of the Archimedes Filter is completely compatible with existing waste immobilization processes such as vitrification and requires no new waste form to be developed. A full-geometric-scale Demonstration Filter Unit (DEMO) has been constructed and is undergoing initial testing at the Archimedes Technology Group Development Facilities in San Diego. Some of the technology and engineering development is being performed by other organizations in collaboration with Archimedes. The Commissariat a l'Energie Atomique (CEA) is developing the plasma calcination technology and all of the associated systems for AFP feed preparation. Two Russian institutes are involved in the development of the ICP torch and injector system. The Remote System Group (UT-Battelle) at ORNL is developing the remote maintenance system for the filter units. Conceptual design of the Archimedes Filter Plant (AFP) is being developed concurrently with the DEMO testing program. The AFP mission is to significantly reduce the cost and accelerate the rate of vitrification of high-level …
Date: February 27, 2003
Creator: Ahlfeld, C.E.; Gilleland, J.G. & Wagoner, J.D.
Object Type: Article
System: The UNT Digital Library
ASHTABULA SUCCESSES--MACRO NOW OR FOREVER HOLD YOUR PIECES! (open access)

ASHTABULA SUCCESSES--MACRO NOW OR FOREVER HOLD YOUR PIECES!

As facility demolition and remediation continued at the DOE Ashtabula Environmental Management Project (AEMP), a DOE closure site located in Ashtabula, OH, the quantity of mixed waste increased by approximately twenty-fold from the original Site Treatment Plan estimates to over 567 m3 (20,000 cubic feet). Also, a greater variety of low-level mixed waste (MW) was identified that was suitable for alternate debris treatment like macroencapsulation (MACRO) instead of traditional shredding, stabilization, and solidification to improve the overall safety and cost-effectiveness. Macroencapsulation is required for lead and authorized for hazardous debris under the alternate debris treatment standards per 40 CFR 268.45. Several polymer encapsulation processes were being explored, developed, and deployed in the mid-1990's by various groups including the DOE Mixed Waste Focus Area, DOE EM-50 Office of Science and Technology, Brookhaven National Laboratory, DOE Macro Working Group, DOE-Albuquerque Mixed Waste/Mobile Treatment Unit, and Envirocare of Utah, Inc. As a result, technically-proven macroencapsulation and microencapsulation processes using extruded polyethylene beads were verified as being technically acceptable for waste treatment to RCRA standards. The AEMP had a variety of waste forms where technically-proven systems were needed to perform on-site treatment of challenging mixed wastes (MW) from production operations (i.e. HEPA filters, barium …
Date: February 27, 2003
Creator: Altmayer, S. A.; Forschner, J. A.; Kulpa, J. P. & Spoerner, M. T.
Object Type: Article
System: The UNT Digital Library
Altus Times (Altus, Okla.), Vol. 105, No. 297, Ed. 1 Friday, February 27, 2004 (open access)

Altus Times (Altus, Okla.), Vol. 105, No. 297, Ed. 1 Friday, February 27, 2004

Daily newspaper from Altus, Oklahoma that includes local, state, and national news along with advertising.
Date: February 27, 2004
Creator: Andrews, Mike
Object Type: Newspaper
System: The Gateway to Oklahoma History
Altus Times (Altus, Okla.), Vol. 106, No. 277, Ed. 1 Sunday, February 27, 2005 (open access)

Altus Times (Altus, Okla.), Vol. 106, No. 277, Ed. 1 Sunday, February 27, 2005

Daily newspaper from Altus, Oklahoma that includes local, state, and national news along with advertising.
Date: February 27, 2005
Creator: Andrews, Mike
Object Type: Newspaper
System: The Gateway to Oklahoma History
Experience with Dismantling of the Analytic Cell in the JRTF Decommissioning Program (open access)

Experience with Dismantling of the Analytic Cell in the JRTF Decommissioning Program

The analytic cell was mainly used for process control analysis of the reprocessing process and for the measurement of fuel burn up ratio in JAERI's Reprocessing Test Facility (JRTF). The analytic cell was a heavy shielded one and equipped with a conveyor. The cell was alpha and beta(gamma)contaminated. For dismantling of analytic cells, it is very important to establish a method to remove the heavy shield safely and reduce the exposure. At first, a green house was set up to prevent the spread out of contamination, and next, the analytic cell was dismantled. Depending on the contamination condition, the workers wore protective suits such as air ventilated-suits for prevention of internal exposure and vinyl chloride aprons, lead aprons in order to reduce external exposure. From the work carried out, various data such as needed manpower for the activities, the collective dose of workers by external exposure, the amount of radioactive wastes and the relation between the weight of the shield and its dismantling efficiency were obtained and input for the database. The method of dismantling and the experience with the dismantling of the analytic cell in the JRTF, carried out during 2001 and 2002, are described in this paper.
Date: February 27, 2003
Creator: Annoh, Akio; Nemoto, Koichi; Tajiri, Hideo; Saito, Keiichiro; Miyajima, Kazutoshi & Myodo, Masato
Object Type: Article
System: The UNT Digital Library
Evaluation of Management Routes for the Paldiski Sarcophagi (open access)

Evaluation of Management Routes for the Paldiski Sarcophagi

The necessity to develop the submarine fleet in Russia required constructing a special training base for the training of submarine crews. To this purpose two prototypes of nuclear power units, close analogous to those fitting out nuclear submarines were constructed and commissioned in the sixties on the Navy training centre's base located in Paldiski (Pakri peninsula, Estonia). In 1994, nuclear fuel was discharged from the reactors and transported to Russia while the reactors themselves were prepared for prolonged storage, prior to transfer of the Paldiski facilities to the ownership of the Estonian Republic. The Paldiski facilities are currently being dismantled with the exception of two sarcophagi made of concrete that are housing the two reactor compartments. The question of the future management of both sarcophagi is a key-issue in the cleaning up of the whole Paldiski site. Actually, three basic questions should answered: when should dismantling operations occur, how this should be done, and what could be the corresponding cost. Within the context of enlargement of the European Union, the Commission services (first Directorate-General for Environment and then Directorate-General for Enlargement) decided to support Estonia to respond to these three questions through a study contract that was awarded in 1999 …
Date: February 27, 2002
Creator: Antonel, L.; Robin, B.; Miller, J. W.; Putnik, H. & Simanovski, Y.
Object Type: Article
System: The UNT Digital Library
REMEDIATION FACILITY WORKER DOSE ASSESSMENT (open access)

REMEDIATION FACILITY WORKER DOSE ASSESSMENT

The purpose of this design calculation is to estimate radiation doses received by personnel in the Remediation Facility performing operations to receive, prepare, open, repair, recover, disposition, and correct off-normal and non-standard conditions with casks, canisters, spent nuclear fuel (SNF) assemblies, and waste packages (WP). The specific scope of work contained in this calculation covers both collective doses and individual worker group doses on an annual basis, and includes the contributions due to external and internal radiation. The results of this calculation will be used to support the design of the Remediation Facility and provide occupational dose estimates for the License Application.
Date: February 27, 2004
Creator: Arakali, V. & Faillace, E.
Object Type: Report
System: The UNT Digital Library
SUBSURFACE FACILITY WORKER DOES ASSESSMENT (open access)

SUBSURFACE FACILITY WORKER DOES ASSESSMENT

The purpose of this design calculation is to estimate radiation doses received by personnel working in the subsurface facility of the repository performing emplacement, maintenance, and retrieval operations under normal conditions. The results of this calculation will be used to support the design of the subsurface facilities and provide occupational dose estimates for the License Application.
Date: February 27, 2004
Creator: Arakali, V.; Faillace, E. & Linden, A.
Object Type: Report
System: The UNT Digital Library
Conditioning Technology for Radioactive Waste Resulted From the Treatment of Liquid Waste From the Romanian Nuclear Power Plant (open access)

Conditioning Technology for Radioactive Waste Resulted From the Treatment of Liquid Waste From the Romanian Nuclear Power Plant

For the conditioning of spent resins contaminated with radionuclides, such as: 137Cs, 134Cs, 60Co, 58Co, 57Co, 54Mn, etc., techniques of direct immobilization in cement, bitumen and organic polymers have been tested. The selected process was the bituminization using industrial bitumen, I 60-70, made in Romania, which had very good characteristics. The paper presents stages of the research project, technical conditions for the process and advantages of the bituminization of spent resins.
Date: February 27, 2003
Creator: Arsene, Carmen; Andrei, Veronica & Negoiu, Dumitru
Object Type: Article
System: The UNT Digital Library
Alpha Waste Minimization in Terms of Volume and Radioactivity at Cogema's Melox and la Hague Plants (open access)

Alpha Waste Minimization in Terms of Volume and Radioactivity at Cogema's Melox and la Hague Plants

This paper describes the management of alpha waste that cannot be stored in surface repositories under current French regulations. The aim of the paper is to provide an overview of COGEMA's Integrated Waste Management Strategy. The topics discussed include primary waste minimization, from facility design to operating feedback; primary waste management by the plant operator, including waste characterization; waste treatment options that led to building waste treatment industrial facilities for plutonium decontamination, compaction and cement solidification; and optimization of industrial tools, which is strongly influenced by safety and financial considerations.
Date: February 27, 2003
Creator: Arslan, M.; Dumont, J. C.; Londres, V. & Poncelet, F. J.
Object Type: Article
System: The UNT Digital Library
DEGRADED TBP SOLVENT REGENERATION TECHNOLOGY USING BUTYLAMINE AS A SOLVENT WASHING TO REDUCE SOLID SALT WASTE (open access)

DEGRADED TBP SOLVENT REGENERATION TECHNOLOGY USING BUTYLAMINE AS A SOLVENT WASHING TO REDUCE SOLID SALT WASTE

Normal butylamine compounds are studied as salt-free wash reagents for degraded solvent used in PUREX process in spent fuel reprocessing. The solvent wash tests were carried out with two types of butylamine compounds, n-butylamine oxalate and n-butylamine bicarbonate, by counter-current mode using a small size mixer-settler composed of two 4-stage wash steps. Di-n-butyl phosphoric acid (HDBP), the main degradation product from TBP, was removed from real degraded solvent with decontamination factor of 2.5 {approx} 7.9. The study on electrolytic decomposition of butylamine compounds was also conducted for waste treatment.
Date: February 27, 2003
Creator: Asakura, T.; Itoh, Y.; Hotoku, S.; Morita, Y. & Uchiyama, G.
Object Type: Article
System: The UNT Digital Library
Mercury removal at Idaho National Engineering and Environmental Laboratory's New Waste Calcining Facility (open access)

Mercury removal at Idaho National Engineering and Environmental Laboratory's New Waste Calcining Facility

Technologies were investigated to determine viable processes for removing mercury from the calciner (NWCF) offgas system at the Idaho National Engineering and Environmental Laboratory. Technologies for gas phase and aqueous phase treatment were evaluated. The technologies determined are intended to meet EPA Maximum Achievable Control Technology (MACT) requirements under the Clean Air Act and Resource Conservation and Recovery Act (RCRA). Currently, mercury accumulation in the calciner off-gas scrubbing system is transferred to the tank farm. These transfers lead to accumulation in the liquid heels of the tanks. The principal objective for aqueous phase mercury removal is heel mercury reduction. The system presents a challenge to traditional methods because of the presence of nitrogen oxides in the gas phase and high nitric acid in the aqueous scrubbing solution. Many old and new technologies were evaluated including sorbents and absorption in the gas phase and ion exchange, membranes/sorption, galvanic methods, and UV reduction in the aqueous phase. Process modifications and feed pre-treatment were also evaluated. Various properties of mercury and its compounds were summarized and speciation was predicted based on thermodynamics. Three systems (process modification, NOxidizer combustor, and electrochemical aqueous phase treatment) and additional technology testing were recommended.
Date: February 27, 2000
Creator: Ashworth, S. C.
Object Type: Article
System: The UNT Digital Library

Doctoral Recital: 2006-02-27 – Christopher Astilla, piano

Recital presented at the UNT College of Music Recital Hall in partial fulfillment of the Doctor of Musical Arts (DMA) degree
Date: February 27, 2006
Creator: Astilla, Christopher
Object Type: Sound
System: The UNT Digital Library
CAMX - A High Performance Cutting Technique for Underwater Use (open access)

CAMX - A High Performance Cutting Technique for Underwater Use

During the past years a new cutting technology, the CAMX-process-family (Contact-Arc-Metal-X [X is for Cutting, Grinding and Drilling]) was developed at the Institute of Materials Science in Hanover. These are electro-thermal underwater separation processes for metallic structures. The CAMX technology covers the Contact-Arc-Metal- Cutting (CAMC) with a sword-like cutting electrode, the Contact-Arc-Metal-Grinding (CAMG) with a rotating electrode and the Contact-Arc-Metal-Drilling (CAMD) with a wrap mechanism to fix and carry the workpiece. There are no limitations of CAMC concerning the capability of cutting complicated structures of workpieces. Undercuts and cavities in the workpiece do not affect the CAMC. The CAMG is a separation process for straight cuts with a very high cutting speed. The CAMD is a technology to drill holes or pocket holes of any geometry. With the integrated wrap mechanism it is possible to fix and carry workpieces, which are not to handle with conventional mechanisms.
Date: February 27, 2003
Creator: Bach, Fr.-W.; Versemann, R.; Bienia, H. & Kremer, G.
Object Type: Article
System: The UNT Digital Library
Hourly Simulation of Grid-Connected PV Systems Using Realistic Building Loads (Preprint) (open access)

Hourly Simulation of Grid-Connected PV Systems Using Realistic Building Loads (Preprint)

This is one of two companion papers that describe the ENERGY-10 PV design tool computer simulation program. The other paper is titled ''ENERGY-10 Photovoltaics: A New Capability.'' Whereas this paper focuses on the PV aspects of the program, the companion paper focuses on the implementation method. The case study in this paper is a commercial building application, whereas the case study in the companion paper is a residential application with an entirely different building load characteristic. Together they provide a balanced view.
Date: February 27, 2001
Creator: Balcomb, J. D.; Hayter, S. J. & Weaver, N. L.
Object Type: Article
System: The UNT Digital Library
The Silicon Tracker Readout Electronics of the Gamma-ray Large Area Space Telescope (open access)

The Silicon Tracker Readout Electronics of the Gamma-ray Large Area Space Telescope

A unique electronics system has been built and tested for reading signals from the silicon-strip detectors of the Gamma-ray Large Area Space Telescope mission. The system amplifies and processes signals from 884,736 36-cm strips using only 160 W of power, and it achieves close to 100% detection efficiency with noise occupancy sufficiently low to allow it to self trigger. The design of the readout system is described, and results are presented from ground-based testing of the completed detector system.
Date: February 27, 2006
Creator: Baldini, Luca; Brez, Alessandro; Himel, Thomas; Hirayama, Masaharu; Johnson, R. P.; Kroeger, Wilko et al.
Object Type: Article
System: The UNT Digital Library
Electric Power Interruption Cost Estimates for Individual Industries, Sectors, and U.S. Economy (open access)

Electric Power Interruption Cost Estimates for Individual Industries, Sectors, and U.S. Economy

During the last 20 years, utilities and researchers have begun to understand the value in the collection and analysis of interruption cost data. The continued investigation of the monetary impact of power outages will facilitate the advancement of the analytical methods used to measure the costs and benefits from the perspective of the energy consumer. More in-depth analysis may be warranted because of the privatization and deregulation of power utilities, price instability in certain regions of the U.S. and the continued evolution of alternative auxiliary power systems.
Date: February 27, 2002
Creator: Balducci, Patrick J.; Roop, Joseph M.; Schienbein, Lawrence A.; DeSteese, John G. & Weimar, Mark R.
Object Type: Report
System: The UNT Digital Library
Final Disposal of Radioactive Waste in Germany: Plan Approval Process of Konrad Mine and Acceptance Requirements (open access)

Final Disposal of Radioactive Waste in Germany: Plan Approval Process of Konrad Mine and Acceptance Requirements

Currently no final repository for any type of radioactive waste is operated in Germany. Preliminary Final Storage Acceptance Requirements for radioactive waste packages were published in 1995. Up to now these are the basis for treatment of radioactive waste in Germany. After licensing of the final repository these preliminary waste acceptance requirements are completed with licensing conditions. Some of these conditions affect the preliminary waste acceptance requirements, e. g. behavior of chemo-toxic substances in case of accidents in the final repository or the allowed maximum concentration of fissile material. The presented examples of radioactive waste conditioning campaigns demonstrate that no difficulties are expected in management, characterization and quality assurance of radioactive wastes due to the licensing conditions.
Date: February 27, 2003
Creator: Bandt, Gabriele; Posnatzki, Britta & Beckers, Klaus-Arno
Object Type: Article
System: The UNT Digital Library
The Extension of the URF HADES: Realization and Observations (open access)

The Extension of the URF HADES: Realization and Observations

An important step in the feasibility study of radioactive waste disposal in Boom Clay is the demonstration that we can construct galleries using industrial techniques, keeping the disturbance of the host-rock at an acceptable level for the long term safety of the disposal site. The successful construction of a connecting gallery of 85m in less than 6 weeks demonstrated the feasibility. To limit the disturbance, an expanding lining type was used: the wedge-block system; for the same reason, the lining was installed as soon as possible after excavation and a minimal excavation rate (2m/day) was imposed. The total radial convergence was limited to about 0.09m; the excavation radius was 2.445m. An extensive instrumentation and observation program accompanied the construction of the connecting gallery. Sensors measuring displacements, total pressure and pore water pressure were installed in the host rock to study the hydro-mechanical behavior of the clay when the gallery was excavated. Sensors in the tunneling shield gave information about the instantaneous convergence and excavation parameters. Strain gauges were placed in three sections of the lining to study the evolution of stresses in the lining with time. A systematic observation of the face and side-walls provided a useful database of the …
Date: February 27, 2003
Creator: Bastiaens, W & Demarche, M.
Object Type: Article
System: The UNT Digital Library
National Environmental Education Act of 1990: Overview, Implementation, and Reauthorization Issues (open access)

National Environmental Education Act of 1990: Overview, Implementation, and Reauthorization Issues

This report presents an overview of the National Environmental Education Act of 1990, discusses appropriations, examines Environmental Protection Agency (EPA's) implementation of the act, and analyzes potential issues for reauthorization that may be considered in the 109th Congress.
Date: February 27, 2006
Creator: Bearden, David M.
Object Type: Report
System: The UNT Digital Library