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Record of the first meeting of the Joint Coordinating Committee for Radiation Effects Research

Description: This conference was held July 27--28, 1994 in Moscow. The main purpose of the meeting was to implement an agreement between the Russian Federation and the US to facilitate cooperative research on health and environmental effects of radiation. It was hoped that the exchange of information would provide a good basis for employing new scientific knowledge to implement practical measures to facilitate the rehabilitation of radioactively contaminated areas and to treat radiation illnesses. The Russian Federation suggested five main scientific areas for cooperative research. They will prepare proposals on 4--5 projects within the scope of the scientific areas discussed and forward them to the US delegation for consideration of the possibility to facilitate joint research.
Date: December 31, 1994
Item Type: Article

Spatially fractionated microirradiation of normal CNS and gliosarcomas of the rat with synchrotron photons: Cell and tissue lesions; Raeumlich fraktionierte Mikrobestrahlung von normalem ZNS und Gliosarkomen der Ratte mit Synchrotron-Photonen: Zell- und Gewebelaesionen

Description: Rats were implanted intracerebrally with 9L gliosarcoma cells were used to experimentally determine the curative effectiveness of synchrotron radiation produced by the National Synchrotron Radiation Source. Radiation was delivered in beams with each ray 25 micrometers thick and arranged in an array of 4 mm corners. All experimental animals receiving the gliosarcoma cells and not treated died within four weeks. Treated animals surviving 113 days were sacrificed and their brains were examined histologically.
Date: December 31, 1995
Creator: Laissue, J.A.; Spanne, P.; Dilmanian, F.A.; Nawrocky, M.N.; Slatkin, D.N.; Joel, D.D. et al.
Item Type: Article

Proceedings -- US Russian workshop on fuel cell technologies

Description: On September 26--28, 1995, Sandia National Laboratories sponsored the first Joint US/Russian Workshop on Fuel Cell Technology at the Marriott Hotel in Albuquerque, New Mexico. This workshop brought together the US and Russian fuel cell communities as represented by users, producers, R and D establishments and government agencies. Customer needs and potential markets in both countries were discussed to establish a customer focus for the workshop. Parallel technical sessions defined research needs and opportunities for collaboration to advance fuel cell technology. A desired outcome of the workshop was the formation of a Russian/American Fuel Cell Consortium to advance fuel cell technology for application in emerging markets in both countries. This consortium is envisioned to involve industry and national labs in both countries. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.
Date: April 1, 1996
Creator: Baker, B. & Sylwester, A.
Item Type: Article

Zirconium and technetium recovery and partitioning in the presence of actinides in modified Purex process for ATW program. Final report

Description: The modified Purex process flowsheet is based on combination of all irradiated materials, their joint dissolution and reprocessing as a NPP spent fuel solution with abnormal Pu content after addition of recycled depleted U concentrate. Some groups of long-lived radionuclides could be completely recovered and localized at the stage of extraction reprocessing using 30% TBP. Studies were conducted for 10 y to develop the process for recovery, concentration, and localization of U, Pu, Np, Tc, and Zr within 1st extraction cycle. Actinides are recovered from high-level raffinate of this cycle after evaporation and feed adjustment. Results in this report show that combined deep recovery of several elements from highly irradiated materials by TBP extraction, for further transmutation, is possible. Selective stripping of Zr from solvent phase containing U, Pu, Np, and Tc is quite effective. Development of the modified Purex process is not complete; main problem to be solved should be oxide separation from the loop and permissible storage duration before reprocessing and reuse in the loop.
Date: December 31, 1994
Creator: Dzekun, E.G.; Fedorov, Y.S.; Galkin, B.Y.; Lyubtsev, R.I.; Mashkin, A.N.; Mishin, E.N. et al.
Item Type: Report

The United States of America and the People`s Republic of China experts report on integrated gasification combined-cycle technology (IGCC)

Description: A report written by the leading US and Chinese experts in Integrated Gasification Combined Cycle (IGCC) power plants, intended for high level decision makers, may greatly accelerate the development of an IGCC demonstration project in the People`s Republic of China (PRC). The potential market for IGCC systems in China and the competitiveness of IGCC technology with other clean coal options for China have been analyzed in the report. Such information will be useful not only to the Chinese government but also to US vendors and companies. The goal of this report is to analyze the energy supply structure of China, China`s energy and environmental protection demand, and the potential market in China in order to make a justified and reasonable assessment on feasibility of the transfer of US Clean Coal Technologies to China. The Expert Report was developed and written by the joint US/PRC IGCC experts and will be presented to the State Planning Commission (SPC) by the President of the CAS to ensure consideration of the importance of IGCC for future PRC power production.
Date: December 1, 1996
Item Type: Report

Hanford/Tomsk reciprocal site visit: Plutonium agreement compliance talks

Description: The objective of the visit to Hanford Site was to: demonstrate equipment, technology, and methods for calculating Pu production, measuring integrated reactor power, and storing and safeguarding PuO{sub 2}; demonstrate the shutdown of Hanford production reactors; and foster openness and transparency of Hanford operations. The first day`s visit was an introduction to Hanford and a review of the history of the reactors. The second day consisted of discussions on the production reactors, reprocessing operations, and PuO{sub 2} storage. The group divided on the third day to tour facilities. Group A toured the N reactor, K-West reactor, K-West Basins, B reactor, and participated in a demonstration and discussion of reactor modeling computer codes. Group B toured the Hanford Pu Storage Facility, 200-East Area, N-cell (oxide loadout station), the Automated Storage Facility, and the Nondestructive Assay Measurement System. Group discussions were held during the last day of the visit, which included scheduling of a US visit to Russia.
Date: November 1, 1994
Creator: Libby, R.A.; Sorenson, R.; Six, D. & Schiegel, S.C.
Item Type: Article

Selected translated abstracts of Russian-language climate-change publications. 4: General circulation models

Description: This report presents English-translated abstracts of important Russian-language literature concerning general circulation models as they relate to climate change. Into addition to the bibliographic citations and abstracts translated into English, this report presents the original citations and abstracts in Russian. Author and title indexes are included to assist the reader in locating abstracts of particular interest.
Date: October 1, 1996
Creator: Burtis, M. D.; Razuvaev, V. N. & Sivachok, S. G.
Item Type: Report

Energia Renovable para Centros de Salud Rurales (Renewable Energy for Rural Health Clinics)

Description: Esta es la primera de una serie de guias de aplicaciones que el Programa de Energia de Villas de NREL esta comisionando para acoplar sistemas comerciales renovables con aplicaciones rurales, incluyendo agua, escuelas rurales y micro empresas. La guia esta complementada por las actividades de desarrollo del Programa de Energia de Villas de NREL, proyectos pilotos internacionales y programas de visitas profesionales.
Date: July 28, 1999
Creator: Jimenez, T. & Olson, K.
Item Type: Book

Proceedings of the Chornobyl phytoremediation and biomass energy conversion workshop

Description: Many concepts, systems, technical approaches, technologies, ideas, agreements, and disagreements were vigorously discussed during the course of the 2-day workshop. The workshop was successful in generating intensive discussions on the merits of the proposed concept that includes removal of radionuclides by plants and trees (phytoremediation) to clean up soil in the Chornobyl Exclusion Zone (CEZ), use of the resultant biomass (plants and trees) to generate electrical power, and incorporation of ash in concrete casks to be used as storage containers in a licensed repository for low-level waste. Twelve years after the Chornobyl Nuclear Power Plant (ChNPP) Unit 4 accident, which occurred on April 26, 1986, the primary 4radioactive contamination of concern is from radioactive cesium ({sup 137}Cs) and strontium ({sup 90}Sr). The {sup 137}Cs and {sup 90}Sr were widely distributed throughout the CEZ. The attendees from Ukraine, Russia, Belarus, Denmark and the US provided information, discussed and debated the following issues considerably: distribution and characteristics of radionuclides in CEZ; efficacy of using trees and plants to extract radioactive cesium (Cs) and strontium (Sr) from contaminated soil; selection of energy conversion systems and technologies; necessary infrastructure for biomass harvesting, handling, transportation, and energy conversion; radioactive ash and emission management; occupational health and safety concerns for the personnel involved in this work; and economics. The attendees concluded that the overall concept has technical and possibly economic merits. However, many issues (technical, economic, risk) remain to be resolved before a viable commercial-scale implementation could take place.
Date: June 1, 1998
Creator: Hartley, J. & Tokarevsky, V.
Item Type: Article


Description: Unsaturated drip tests have been used to investigate the alteration of unirradiated UO{sub 2} and spent UO{sub 2} fuel in an unsaturated environment, such as may be expected in the proposed repository at Yucca Mountain. In these tests, simulated groundwater is periodically injected onto a sample at 90 C in a steel vessel. The solids react with the dripping groundwater and water condensed on surfaces to form a suite of U(VI) alteration phases. Solution chemistry is determined from leachate at the bottom of each vessel after the leachate stops interacting with the solids. A more detailed knowledge of the compositional evolution of the leachate is desirable. By providing just enough water to maintain a thin film of water on a small quantity of fuel in batch experiments, we can more closely monitor the compositional changes to the water as it reacts to form alteration phases.
Date: May 11, 1998
Creator: Finch, Robert J.; Wolf, Stephen F.; Hanchar, John M. & Bates, John K.
Item Type: Report


Description: A deterministic method for solving the time-dependent, three-dimensional Boltzmam transport equation with explicit representation of delayed neutrons has been developed and evaluated. The methodology used in this study for the time variable of the neutron flux is known as the improved quasi-static (IQS) method. The position, energy, and angle-dependent neutron flux is computed deterministically by using the three-dimensional discrete ordinates code TORT. This paper briefly describes the methodology and selected results. The code developed at the University of Tennessee based on this methodology is called TDTORT. TDTORT can be used to model transients involving voided and/or strongly absorbing regions that require transport theory for accuracy. This code can also be used to model either small high-leakage systems, such as space reactors, or asymmetric control rod movements. TDTORT can model step, ramp, step followed by another step, and step followed by ramp type perturbations. It can also model columnwise rod movement can also be modeled. A special case of columnwise rod movement in a three-dimensional model of a boiling water reactor (BWR) with simple adiabatic feedback is also included. TDTORT is verified through several transient one-dimensional, two-dimensional, and three-dimensional benchmark problems. The results show that the transport methodology and corresponding code developed in this work have sufficient accuracy and speed for computing the dynamic behavior of complex multidimensional neutronic systems.
Date: January 14, 1998
Creator: Goluoglu, S.; Bentley, C.; DeMeglio, R.; Dunn, M.; Norton, K.; Pevey, R. et al.
Item Type: Report

Energy Savers: Tips for Saving Energy and Money at Home; El Ahorro de Energa: Sugerencias para ahorrar energa y dinero en el hogar

Description: The Department of Energy of the United States of America works to guarantee provisions of safe energy, reliable and economically accessible to support to one developing economy and to protect the atmosphere. These suggestions and ideas to increase the energy efficiency in their house represent simple ways in which our citizens can contribute to preserve the atmosphere at world-wide level, to reduce the level of contamination of the air and to reserve our natural resources for future generations. [Spanish] El Departamento de Energa de los Estados Unidos de America trabaja para garantizar suministros de energa seguros, confiables y econmicamente accesibles para apoyar a una economa en desarrollo y proteger el medio ambiente. Estas sugerencias e ideas para aumentar la eficiencia energetica en su casa representan maneras sencillas en que nuestros ciudadanos pueden contribuir a preservar el medio ambiente a nivel mundial, a reducir el nivel de contaminacin del aire y a reservar nuestros recursos naturales para las generaciones futuras.
Date: June 1, 2000
Creator: Jones, J.
Item Type: Book

Electroproduction of Photons and of Pawns on the Proton in Quadrimoment of Transfer Q2=1.0GeV2. Measure Cross Sections and Extraction of Polarizabilities Generalities; Electroproduction de Photons et de Pions sur le Proton au Quadrimoment de Transfert Q2=1.0GeV2. Mesure des Sections Efficaces et Extraction des Polarisabilites Generalisees

Description: In hadronic physics, the nucleon structure and the quarks confinement are still topical issues. The neutral pion electroproduction and virtual Compton scattering (VCS) reactions allow us to access new observables that describe this structure. This work is focused on the VCS experiment performed at Jefferson Lab in 1998.
Date: November 6, 2001
Creator: Laveissiere, Geraud

Evaluation of DUF{sub 6}-G-Q-STU-001 (ALARA analysis supporting approval of authorized limits).

Description: The U.S. Department of Energy (DOE) has selected Uranium Disposition Services, LLC (UDS) to proceed with disposition of the inventory of depleted uranium hexafluoride (DUF{sub 6}) for which DOE has management responsibility. To accomplish this task, UDS will construct and operate facilities at two DOE-owned sites, one near Paducah, Kentucky, and another near Portsmouth, Ohio, to convert DUF{sub 6} to uranium oxide (principally U{sub 3}O{sub 8}). The off-gas treatment system for the conversion process will produce aqueous hydrogen fluoride (AqHF), also known as hydrofluoric acid, and a relatively small amount of calcium fluoride (CaF{sub 2}), each containing some residual radioactive material. As part of its contractual charge, UDS must identify and implement a disposition for all three products generated by the DUF{sub 6} conversion facilities: uranium oxide, AqHF, and CaF{sub 2}. The UDS DUF{sub 6} Conversion Product Management Plan (DUF{sub 6}-UDS-PLN-004, September 2003) concludes that a viable commercial market exists for AqHF, which, if not sold, would have to be neutralized, producing a relatively large quantity of additional CaF{sub 2}. Although CaF{sub 2} has very limited market potential, there is some possibility that it also could be sold. If these potential markets could be developed, DOE would save the costs of neutralizing AqHF and/or disposing of the CaF{sub 2} neutralization product. Accordingly, UDS has decided to seek approval from DOE for unrestricted release of both AqHF and CaF{sub 2} that would be generated if AqHF could not be sold or if sales were interrupted. If AqHF were sold, the relatively small quantity of CaF{sub 2} still being generated by the DUF{sub 6} conversion process off-gas treatment system would most likely be disposed of as waste. The main product of conversion, depleted uranium oxide, will be reused to the extent possible or disposed of as waste, if no practical reuse option ...
Date: June 29, 2004
Creator: Ranek, N. L.; Croff, A. G.; Cheng, J.-J.; Gillette, J. L. & Avci, H. I.
Item Type: Report

Modeling report of the CEA cadarache MINERVE reactor for the OSMOSE project.

Description: The OSMOSE program (Oscillation in Minerve of isotopes in ''Eupraxic'' spectra) is a collaboration between the U.S. Department of Energy (DOE) and the Commissariat a l' Energie Atomique (CEA). It aims at measuring integral absorption rates of minor actinides by the oscillation technique in the MINERVE experimental facility located at the CEA Cadarache Research Center. The OSMOSE program also includes a complete analytical program to understand and resolve potential discrepancies between calculated and measured values. The OSMOSE program began in 2001 and will continue until 2013. The Argonne National Laboratory has developed Monte Carlo and deterministic calculation models of the MINERVE facility to determine core and safety parameters such as axial and radial fission rate distributions, control rod worth, spectral indices, and the reactivity worth of oscillated samples. Oscillation samples include calibration samples with different uranium enrichments and boron concentrations and the OSMOSE samples--separated actinides including {sup 232}Th, {sup 233}U, {sup 234}U, {sup 235}U, {sup 236}U, {sup 238}U, {sup 237}Np, {sup 238}Pu, {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 243}Am, {sup 244}Cm and {sup 245}Cm. Seven different neutron spectra will be created in the MINERVE facility: an overmoderated UO{sub 2} matrix (representative of a fuel processing plant or flooded storage cask), a UO{sub 2} matrix in water (representative of LWRs), a mixed oxide fuel matrix (representative of cores containing MOX fuels), two epithermal spectra (representative of under-moderated reactors), a moderated fast spectrum (representative of fast reactors which have some slowing down due to moderators such as lead-bismuth or sodium), and a very hard spectrum (representative of fast reactors with little moderation from reactor coolant). The different spectra are achieved by changing the experimental lattice within the MINERVE reactor. The currently investigated core configurations are R1UO2 and R1MOX, representative of a LWR loaded with UO{sub 2} and ...
Date: February 25, 2005
Creator: Klann, R.; Perret, G.; Hudelot, J. P. & Antony, M.
Item Type: Report

Thermophotovoltaic Spectral Control

Description: Spectral control is a key technology for thermophotovoltaic (TPV) direct energy conversion systems because only a fraction (typically less than 25%) of the incident thermal radiation has energy exceeding the diode bandgap energy, E{sub g}, and can thus be converted to electricity. The goal for TPV spectral control in most applications is twofold: (1) Maximize TPV efficiency by minimizing transfer of low energy, below bandgap photons from the radiator to the TPV diode. (2) Maximize TPV surface power density by maximizing transfer of high energy, above bandgap photons from the radiator to the TPV diode. TPV spectral control options include: front surface filters (e.g. interference filters, plasma filters, interference/plasma tandem filters, and frequency selective surfaces), back surface reflectors, and wavelength selective radiators. System analysis shows that spectral performance dominates diode performance in any practical TPV system, and that low bandgap diodes enable both higher efficiency and power density when spectral control limitations are considered. Lockheed Martin has focused its efforts on front surface tandem filters which have achieved spectral efficiencies of {approx}83% for E{sub g} = 0.52 eV and {approx}76% for E{sub g} = 0.60 eV for a 950 C radiator temperature.
Date: June 9, 2004
Creator: DePoy, DM; Fourspring, PM; Baldasaro, PF; Beausang, JF; Brown, EJ; Dashiel, MW et al.
Item Type: Article