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Sample records for disposal part iii

  1. Workshop 96. Part III

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    Part III of the proceedings contain 155 contributions in various fields of science and technology including nuclear engineering, environmental science, and biomedical engineering. Out of these, 10 were selected to be inputted in INIS. (P.A.).

  2. Workshop 96. Part III

    International Nuclear Information System (INIS)

    1995-12-01

    Part III of the proceedings contain 155 contributions in various fields of science and technology including nuclear engineering, environmental science, and biomedical engineering. Out of these, 10 were selected to be inputted in INIS. (P.A.)

  3. Workshop 95. Part III

    International Nuclear Information System (INIS)

    1995-01-01

    Out of 140 short communications presented in the proceedings, 13 have been inputted into INIS. The topics covered include lifetime control in semiconductor devices by ion irradiation, single crystal scintillation detectors, environmental monitoring, diffusion and sorption of radionuclides in soils, accelerator driven reactors, radioactive waste disposal, digital reactor control systems and research reactors. (Z.S.)

  4. Workshop 95. Part III

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    Out of 140 short communications presented in the proceedings, 13 have been inputted into INIS. The topics covered include lifetime control in semiconductor devices by ion irradiation, single crystal scintillation detectors, environmental monitoring, diffusion and sorption of radionuclides in soils, accelerator driven reactors, radioactive waste disposal, digital reactor control systems and research reactors. (Z.S.).

  5. Standards in neurosonology. Part III

    Directory of Open Access Journals (Sweden)

    Joanna Wojczal

    2016-06-01

    Full Text Available The paper presents standards related to ultrasound imaging of the cerebral vasculature and structures. The aim of this paper is to standardize both the performance and description of ultrasound imaging of the extracranial and intracranial cerebral arteries as well as a study of a specific brain structure, i.e. substantia nigra hyperechogenicity. The following aspects are included in the description of standards for each ultrasonographic method: equipment requirements, patient preparation, study technique and documentation as well as the required elements of ultrasound description. Practical criteria for the diagnosis of certain pathologies in accordance with the latest literature were also presented. Furthermore, additional comments were included in some of the sections. Part I discusses standards for the performance, documentation and description of different ultrasound methods (Duplex, Doppler. Part II and III are devoted to standards for specific clinical situations (vasospasm, monitoring after the acute stage of stroke, detection of a right-to-left shunts, confirmation of the arrest of the cerebral circulation, an assessment of the functional efficiency of circle of Willis, an assessment of the cerebrovascular vasomotor reserve as well as the measurement of substantia nigra hyperechogenicity.

  6. Drilling miniature holes, Part III

    Energy Technology Data Exchange (ETDEWEB)

    Gillespie, L.K.

    1978-07-01

    Miniature components for precision electromechanical mechanisms such as switches, timers, and actuators typically require a number of small holes. Because of the precision required, the workpiece materials, and the geometry of the parts, most of these holes must be produced by conventional drilling techniques. The use of such techniques is tedious and often requires considerable trial and error to prevent drill breakage, minimize hole mislocation and variations in hole diameter. This study of eight commercial drill designs revealed that printed circuit board drills produced better locational and size repeatability than did other drills when centerdrilling was not used. Boring holes 1 mm in dia, or less, as a general rule did not improve hole location in brass or stainless steel. Hole locations of patterns of 0.66-mm holes can be maintained within 25.4-..mu..m diametral positional tolerance if setup misalignments can be eliminated. Size tolerances of +- 3.8 ..mu..m can be maintained under some conditions when drilling flat plates. While these levels of precision are possible with existing off-the-shelf drills, they may not be practical in many cases.

  7. Neuroscience in Nazi Europe Part III

    DEFF Research Database (Denmark)

    Zeidman, Lawrence A; Kondziella, Daniel

    2012-01-01

    In Part I, neuroscience collaborators with the Nazis were discussed, and in Part II, neuroscience resistors were discussed. In Part III, we discuss the tragedy regarding european neuroscientists who became victims of the Nazi onslaught on “non-Aryan” doctors. Some of these unfortunate...... of neuroscience, we pay homage and do not allow humanity to forget, lest this dark period in history ever repeat itself....

  8. Introduction to Part III: Application of LCA in Practice

    DEFF Research Database (Denmark)

    Rosenbaum, Ralph K.

    2018-01-01

    While Part II of this book presents the theoretical foundation and methodology of LCA, Part III is dedicated to a comprehensive discussion of how this methodology has been adapted and applied in practice. The chapters of Part III provide an easily readable and accessible introduction to different...

  9. Cubby : Multiscreen Desktop VR Part III

    NARCIS (Netherlands)

    Djajadiningrat, J.P.; Gribnau, M.W.

    2000-01-01

    In this month's final episode of our 'Cubby: Multiscreen Desktop VR' trilogy we explain how you read the InputSprocket driver from part II, how you use it as input for the cameras from part I and how you calibrate the input device so that it leads to the correct head position.

  10. 40 CFR Appendix Vii to Part 268 - LDR Effective Dates of Surface Disposed Prohibited Hazardous Wastes

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false LDR Effective Dates of Surface Disposed Prohibited Hazardous Wastes VII Appendix VII to Part 268 Protection of Environment ENVIRONMENTAL... VII to Part 268—LDR Effective Dates of Surface Disposed Prohibited Hazardous Wastes Table 1—Effective...

  11. Warship Radar Signatures (Ship Survivability Part III-A)

    NARCIS (Netherlands)

    Galle, L.F.; Heemskerk, H.J.M.; Ewijk, L.J. van

    2000-01-01

    Radar Cross Section (RCS) management is of paramount importance for a warships's survivability. In this first part of the paper (Part III-A), the operational benefits of low RCS will be explained. Basic RCS theory, measurement and simulation techniques will be addressed. The RCS of representative

  12. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 3. Safety assessment for geological disposal systems

    International Nuclear Information System (INIS)

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 3 of the progress report, concerns safety assessment for geological disposal systems definitely introduced in part 1 and 2 of this series and consists of 9 chapters. Chapter I concerns the methodology for safety assessment while Chapter II deals with diversity and uncertainty about the scenario, the adequate model and the required data of the systems above. Chapter III summarizes the components of the geological disposal system. Chapter IV refers to the relationship between radioactive wastes and human life through groundwater, i.e. nuclide migration. In Chapter V is made a reference case which characterizes the geological environmental data using artificial barrier specifications. (Ohno. S.)

  13. 9 CFR 354.132 - Disposal of condemned carcasses and parts.

    Science.gov (United States)

    2010-01-01

    ... Disposition of Diseased Rabbit Carcasses and Parts § 354.132 Disposal of condemned carcasses and parts. All... carbolic acid, (2) Kerosene, fuel oil, or used crank case oil, (3) Any phenolic disinfectant conforming to...

  14. Long-Term Management Strategy for Dredged Material Disposal for Naval Facilities at Pearl Harbor, Hawaii Phase III - Analysis of Alternatives and Development of an LTMS

    National Research Council Canada - National Science Library

    Palermo, Michael

    2000-01-01

    This report documents Phase III of a three-phase study to develop a Long-Term Management Study for disposal of dredged material unsuitable for ocean disposal from Pearl Harbor Naval Complex for the next 30 years...

  15. Application for Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site - U10c Disposal Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Programs

    2010-08-05

    The NTS is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. NNSA/NSO is the federal lands management authority for the NTS and NSTec is the Management & Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The U10C Disposal Site is located in the northwest corner of Area 9 at the NTS (Figure 1) and is located in a subsidence crater created by two underground nuclear events, one in October 1962 and another in April 1964. The disposal site opened in 1971 for the disposal of rubbish, refuse, pathological waste, asbestos-containing material, and industrial solid waste. A Notice of Intent form to operate the disposal site as a Class II site was submitted to the state of Nevada on January 26, 1994, and was acknowledged in a letter to the DOE on February 8, 1994. It operated as a state of Nevada Class II Solid Waste Disposal Site (SWDS) until it closed on October 5, 1995, for retrofit as a Class III SWDS. The retrofit consisted of the installation of a minimum four-foot compacted soil layer to segregate the different waste types and function as a liner to inhibit leachate and water flow into the lower waste zone. Five neutron monitoring tubes were installed in this layer to monitor possible leachate production and water activity. Upon acceptance of the installed barrier and approval of an Operating Plan by NDEP/BFF, the site reopened in January 1996 as a Class III SWDS for the disposal of industrial solid waste and other inert waste.

  16. Some Aspects of Facial Nerve Paralysis. Part III. Complications ...

    African Journals Online (AJOL)

    Some Aspects of Facial Nerve Paralysis. Part III. Complications, Prognosis and management. ... It should be possible to set a definite prognosis within 2 weeks after the onset of facial paralysis, and in many cases even sooner. In the prognosis of facial paralysis the aetiological and time factors involved, the completeness of ...

  17. 41 CFR 102-33.370 - What must we do to dispose of military FSCAP or life-limited parts?

    Science.gov (United States)

    2010-07-01

    ... before you exchange or sell the aircraft or engine (see rules for disposing of uninstalled life-limited... dispose of military FSCAP or life-limited parts? 102-33.370 Section 102-33.370 Public Contracts and... Aircraft Parts Special Requirements for Disposing of Flight Safety Critical Aircraft Parts (fscap) and Life...

  18. 7 CFR 1951.232 - Water and waste disposal systems which have become part of an urban area.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 14 2010-01-01 2009-01-01 true Water and waste disposal systems which have become... Water and waste disposal systems which have become part of an urban area. A water and/or waste disposal.... The following will be forwarded to the Administrator, Attention: Water and Waste Disposal Division...

  19. 10 CFR 51.62 - Environmental report-land disposal of radioactive waste licensed under 10 CFR part 61.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Environmental report-land disposal of radioactive waste....62 Environmental report—land disposal of radioactive waste licensed under 10 CFR part 61. (a) Each applicant for issuance of a license for land disposal of radioactive waste pursuant to part 61 of this...

  20. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    International Nuclear Information System (INIS)

    2010-01-01

    The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles (mi)) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan

  1. Solar neutrino oscillation parameters after SNO Phase-III and SAGE Part-III

    International Nuclear Information System (INIS)

    Yang Ping; Liu Qiuyu

    2009-01-01

    We analyse the recently published results from solar neutrino experiments SNO Phase-III and SAGE Part-III and show their constraints on solar neutrino oscillation parameters, especially for the mixing angle θ 12 . Through a global analysis using all existing data from SK, SNO, Ga and Cl radiochemical experiments and long base line reactor experiment KamLAND , we obtain the parameters Δm 12 2 =7.684 -0.208 +0.212 x 10 -5 eV 2 , tan 2 θ 12 =0.440 -0.057 +0.059 . We also find that the discrepancy between the KamLAND and solar neutrino results can be reduced by choosing a small non-zero value for the mixing angle θ 13 . (authors)

  2. 12 CFR Appendix III to Part 27 - Fair Housing Lending Inquiry/Application Log Sheet

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Fair Housing Lending Inquiry/Application Log Sheet III Appendix III to Part 27 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY FAIR HOUSING HOME LOAN DATA SYSTEM Pt. 27, App. III Appendix III to Part 27—Fair Housing Lending...

  3. 40 CFR 300.310 - Phase III-Containment, countermeasures, cleanup, and disposal.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) SUPERFUND, EMERGENCY PLANNING, AND COMMUNITY RIGHT-TO-KNOW PROGRAMS NATIONAL OIL AND HAZARDOUS..., landfilling, etc.); and sites for the disposal of collected oil, oiled debris, and animal carcasses; and...

  4. Thermodynamic sorption modelling in support of radioactive waste disposal safety cases - NEA sorption project phase III

    International Nuclear Information System (INIS)

    2012-01-01

    A central safety function of radioactive waste disposal repositories is the prevention or sufficient retardation of radionuclide migration to the biosphere. Performance assessment exercises in various countries, and for a range of disposal scenarios, have demonstrated that one of the most important processes providing this safety function is the sorption of radionuclides along potential migration paths beyond the engineered barriers. Thermodynamic sorption models (TSMs) are key for improving confidence in assumptions made about such radionuclide sorption when preparing a repository's safety case. This report presents guidelines for TSM development as well as their application in repository performance assessments. They will be of particular interest to the sorption modelling community and radionuclide migration modellers in developing safety cases for radioactive waste disposal Contents: 1 - Thermodynamic sorption models and radionuclide migration: Sorption and radionuclide migration; Applications of TSMs in radioactive waste disposal studies; Requirements for a scientifically defensible, calibrated TSM applicable to radioactive waste disposal; Current status of TSMs in radioactive waste management; 2 - Theoretical basis of TSMs and options in model development: Conceptual building blocks of TSMs and integration with aqueous chemistry; The TSM representation of sorption and relationship with Kd values; Theoretical basis of TSMs; Example of TSM for uranyl sorption; Options in TSM development; Illustration of TSM development and effects of modelling choices; Summary: TSMs for constraining Kd values - impact of modelling choices; 3 - Determination of parameters for TSMs: Overview of experimental determination of TSM parameters; Theoretical estimation methods of selected model parameters; Case study: sorption modelling of trivalent lanthanides/actinides on illite; Indicative values for certain TSM parameters; Parameter uncertainty; Illustration of parameter sensitivity

  5. Thallium (III) salts utilization in organic synthesis. Part II

    International Nuclear Information System (INIS)

    Ferraz, H.M.C.

    1989-01-01

    The utilizations of thallium (III) salts in organic synthesis with carbonylic and acitylenic substrates are presented. The reactions of carbonylic substra3ts with kitones and the oxidation reactions of acetylenic substrates are shown. Others reactions including thallium (III) salts and non aromatic unsatured substracts, as cleasage of ethers and epoxide using thallium trinitrate, hydrazones treatments with thallium triacetates, etc, are also mentioned. (C.G.C.) [pt

  6. Hominin skeletal part abundances and claims of deliberate disposal of corpses in the Middle Pleistocene.

    Science.gov (United States)

    Egeland, Charles P; Domínguez-Rodrigo, Manuel; Pickering, Travis Rayne; Menter, Colin G; Heaton, Jason L

    2018-05-01

    Humans are set apart from other organisms by the realization of their own mortality. Thus, determining the prehistoric emergence of this capacity is of significant interest to understanding the uniqueness of the human animal. Tracing that capacity chronologically is possible through archaeological investigations that focus on physical markers that reflect "mortality salience." Among these markers is the deliberate and culturally mediated disposal of corpses. Some Neandertal bone assemblages are among the earliest reasonable claims for the deliberate disposal of hominins, but even these are vigorously debated. More dramatic assertions center on the Middle Pleistocene sites of Sima de los Huesos (SH, Spain) and the Dinaledi Chamber (DC, South Africa), where the remains of multiple hominin individuals were found in deep caves, and under reported taphonomic circumstances that seem to discount the possibility that nonhominin actors and processes contributed to their formation. These claims, with significant implications for charting the evolution of the "human condition," deserve scrutiny. We test these assertions through machine-learning analyses of hominin skeletal part representation in the SH and DC assemblages. Our results indicate that nonanthropogenic agents and abiotic processes cannot yet be ruled out as significant contributors to the ultimate condition of both collections. This finding does not falsify hypotheses of deliberate disposal for the SH and DC corpses, but does indicate that the data also support partially or completely nonanthropogenic formational histories.

  7. Tanzania 1895-1920 : Part III: 1914-1920s

    NARCIS (Netherlands)

    Dietz, A.J.

    2016-01-01

    An earlier version of this African Postal Heritage Paper was published as African Studies Centre Leiden Working Paper 119 / 2015: "A postal history of the First World War in Africa and its aftermath - German colonies; III Deutsch Ostafrika / German East Africa", written by Ton Dietz.

  8. Study of extraterrestrial disposal of radioactive wastes. Part 1: Space transportation and destination considerations for extraterrestrial disposal of radioactive wastes. [feasibility of using space shuttle

    Science.gov (United States)

    Thompson, R. L.; Ramler, J. R.; Stevenson, S. M.

    1974-01-01

    A feasibility study of extraterrestrial disposal of radioactive waste is reported. This report covers the initial work done on only one part of the NASA study, that evaluates and compares possible space destinations and space transportation systems. The currently planned space shuttle was found to be more cost effective than current expendable launch vehicles by about a factor of 2. The space shuttle requires a third stage to perform the waste disposal missions. Depending on the particular mission, this third stage could be either a reusable space tug or an expendable stage such as a Centaur.

  9. Inteligencia Artificial y Neurología. (III Parte

    Directory of Open Access Journals (Sweden)

    Mario Camacho Pinto

    1987-04-01

    Full Text Available

    De acuerdo con mi anuncio esta III Parte estaría constituida por los mecanismos cerebrales susceptibles de extrapolación tal como fueron enumerados por mí: control de input-output para realizar conductas, y de inteligencia y aprendizaje, de los cuales por razón de espacio sólo se publica la mitad en esta edición de Medicina. Se trata de una presentación esquemática, auncuando ahora encuentro quizás más atractivo el enfoque de J’urgen Ruech expuesto en el Capítulo Comunicación y Psiquiatría de la obra extensa de Freedman (1 así: Input = percepción; análisis de datos = reconocimiento; procesamiento de datos = pensamiento; almacenamiento de datos = memoria; output = expresión y acción. A mi modo de ver se completaría este encuadre funcional con el tópico aprendizaje, proceso contiguo al de la memoria. Antes de entrar en materia hago unas consideraciones preliminares. En la primera me refiero a otro enfoque del concepto de LA. no incluido anteriormente. Se trata de Schank Roger y Hunter Larry (2 para quienes las indagaciones a que conduce el trasegar acerca de lA son las más atrevidas de nuestra existencia: ¿cuál es la naturaleza de la mente, qué pasa cuando estamos pensando, sintiendo, viendo o entendiendo? ¿Es posible comprender cómo trabaja nuestra mente realmente? Preguntas milenarias en cuyas respuestas no se ha registrado progreso. La lA ofrece una nueva herramienta para avanzar en este sentido: el computador.

    Las teorías sobre la mente han consistido en procesos descriptivos. Y los planteamientos iníciales hechos sobre lA por los investigadores han sido enfocados hacia lo que ellos mismos consideraron como manifestaciones de alta inteligencia: problemas matemáticos, ajedrez, rompecabezas complejos, etc.; gran cantidad de energía fue dedicada y se encontraron técnicas computacionales exitosas. Pero se comprendió que las técnicas desarrolladas no eran las mismas que emplea el cerebro, por lo cual se

  10. Irradiated uranium reprocessing, Final report - I-IV, Part III

    International Nuclear Information System (INIS)

    Gal, I.

    1961-12-01

    This third part of the final report include the following: Annex 5 - device for opening the cover; Annex 6 - inner part of the device for sampling of the radioactive solution; Annex 7 - outer part of the device for sampling of the radioactive solution; Annex 8 - pneumatic taps [sr

  11. Direct disposal of spent fuel. Simulation of shaft transport. Phase III. Final report

    International Nuclear Information System (INIS)

    Filbert, W.; Heda, M.; Khamis, M.; Neydek, J.; Niehues, N.; Rissel, J.; Schrimpf, C.; Weber, W.; Fuchs, D.; Gerlach, A.; Langebrake, F.; Sindern, W.; Gasch, A.; Leicht, R.; Schwab, B.; Hecke, R. van; Kipka, P.; Simmich, K.; Weber, H.

    1994-01-01

    The aim of these demonstration tests was to verify the technical feasibility of a shaft hoisting equipment with a payload of 85 t as well as the safe transport of POLLUX-casks. In phase III of the project the components and the test stand were built, their proper functioning and reliability were tested to demonstrate that they are state-of-the-art. The following additional investigations were carried out: - Tests to fix operational disturbances and simulation tests for the new components to demonstrate their licensibility -Selection and lifetime tests of ropes and investigation of the present state-of-the-art of rope slighting under the conditions of the conceptual design of the shaft hoisting facility - Execution of a probabilistic safety analysis e.g. the determination of the release of radioactive material (result: probability [de

  12. Seabed Disposal Program. Annual report, January--December 1976. Part II

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1977-08-01

    During the first two years of the program, studies were made of the water column extending from the seabed to the surface in mid-gyre regions. It was concluded that this water column is unsuitable for consideration as the disposal medium. Studies were shifted to characterization of the mid-plate, mid-gyre sediments, natural processes in the sediments, and how these natural processes are altered or impacted by the presence of high-level radioactive wastes. These activities continued in the third year of the Program and include (1) development of a number of analytical models as part of the overall systems analysis effort; (2) an extensive program to evaluate the sorption properties of the sediments with respect to single species ions and the competition provided by other waste constituents; (3) an assessment of thermal problems associated with the radiogenic heat produced by the waste and its impact upon the physical and chemical properties of the sediments; (4) continued studies to characterize the sediments; (5) development of capabilities to investigate waste canister emplacement techniques; (6) corrosion studies to evaluate potential canister materials; (7) biological investigations in support of assessment studies addressing accident scenarios and environmental impact; and (8) development of an international program of scientific investigations and information exchange. At the end of the third year, available data indicate that studies should be continued on the concept of disposal in the seabed

  13. 40 CFR Appendix III to Part 600 - Sample Fuel Economy Label Calculation

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 29 2010-07-01 2010-07-01 false Sample Fuel Economy Label Calculation...) ENERGY POLICY FUEL ECONOMY AND CARBON-RELATED EXHAUST EMISSIONS OF MOTOR VEHICLES Pt. 600, App. III Appendix III to Part 600—Sample Fuel Economy Label Calculation Suppose that a manufacturer called Mizer...

  14. 29 CFR Appendix III to Part 1918 - The Mechanics of Conventional Cargo Gear (Non-mandatory)

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 7 2010-07-01 2010-07-01 false The Mechanics of Conventional Cargo Gear (Non-mandatory.... 1918, App. III Appendix III to Part 1918—The Mechanics of Conventional Cargo Gear (Non-mandatory) Note: This appendix is non-mandatory and provides an explanation of the mechanics in the correct spotting of...

  15. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 2. Engineering technology for geological disposal

    International Nuclear Information System (INIS)

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the deep geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, part 2 of the progress report, concerns engineering aspect with reference to Japanese geological disposal plan, according to which the vitrified HLW will be disposed of into a deep, stable rock mass with thick containers and surrounding buffer materials at the depth of several hundred meters. It discusses on multi-barrier systems consisting of a series of engineered and natural barriers that will isolate radioactive nuclides effectively and retard their migrations to the biosphere environment. Performance of repository components, including specifications of containers for vitrified HLW and their overpacks under design as well as buffer material such as Japanese bentonite to be placed in between are described referring also to such possible problems as corrosion arising from the supposed system. It also presents plans and designs for underground disposal facilities, and the presumed management of the underground facilities. (Ohno, S.)

  16. Antipsychotics and Sexual Dysfunction: Sexual Dysfunction - Part III

    Directory of Open Access Journals (Sweden)

    Anil Kumar Mysore Nagaraj

    2009-11-01

    Full Text Available Satisfying sexual experience is an essential part of a healthy and enjoyable life for most people. Antipsychotic drugs are among the various factors that affect optimal sexual functioning. Both conventional and novel antipsychotics are associated with significant sexual side effects. This review has presented various studies comparing different antipsychotic drugs. Dopamine antagonism, increased serum prolactin, serotonergic, adrenergic and cholinergic mechanisms are all proposed to be the mechanisms for sexual dysfunction. Drug treatment for this has not given satisfactory long-term results. Knowledge of the receptor pharmacology of an individual antipsychotic will help to determine whether it is more or less likely to cause sexual side effects and its management.

  17. Radiobiology in clinical radiation therapy - Part III: Normal tissue damage

    International Nuclear Information System (INIS)

    Travis, Elizabeth L.

    1996-01-01

    Objective: This is the third part of a course designed for residents in radiation oncology preparing for their boards. This part of the course will focus on the mechanisms underlying damage in normal tissues. Although conventional wisdom long held that killing and depletion of a critical cell(s) in a tissue was responsible for the later expression of damage, histopathologic changes in normal tissue can now be explained and better understood in terms of the new molecular biology. The concept that depletion of a single cell type is responsible for the observed histopathologic changes in normal tissues has been replaced by the hypothesis that damage results from the interaction of many different cell systems, including epithelial, endothelial, macrophages and fibroblasts, via the production of specific autocrine, paracrine and endocrine growth factors. A portion of this course will discuss the clinical and experimental data on the production and interaction of those cytokines and cell systems considered to be critical to tissue damage. It had long been suggested that interindividual differences in radiation-induced normal tissue damage was genetically regulated, at least in part. Both clinical and experimental data supported this hypothesis but it is the recent advances in human and mouse molecular genetics which have provided the tools to dissect out the genetic component of normal tissue damage. These data will be presented and related to the potential to develop genetic markers to identify sensitive individuals. The impact on clinical outcome of the ability to identify prospectively sensitive patients will be discussed. Clinically it is well-accepted that the volume of tissue irradiated is a critical factor in determining tissue damage. A profusion of mathematical models for estimating dose-volume relationships in a number of organs have been published recently despite the fact that little data are available to support these models. This course will review the

  18. 18 CFR 410.1 - Basin regulations-Water Code and Administrative Manual-Part III Water Quality Regulations.

    Science.gov (United States)

    2010-04-01

    ... Code and Administrative Manual-Part III Water Quality Regulations. 410.1 Section 410.1 Conservation of... CODE AND ADMINISTRATIVE MANUAL-PART III WATER QUALITY REGULATIONS § 410.1 Basin regulations—Water Code and Administrative Manual—Part III Water Quality Regulations. (a) The Water Code of the Delaware River...

  19. Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 1 of 2

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-04-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-O; Part 2 contains Appendices P-FF. Separate abstracts have been prepared of each Appendix for inclusion in the Energy Data Base

  20. Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

    Energy Technology Data Exchange (ETDEWEB)

    Hinga, K.R. (ed.)

    1981-07-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-Q; Part 2 contains Appendices R-MM. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base.

  1. Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

    International Nuclear Information System (INIS)

    Hinga, K.R.

    1981-07-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume I, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-Q; Part 2 contains Appendices R-MM. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base

  2. Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 2 of 2

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-04-01

    Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume II, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-O; Part 2 contains Appendices P-FF. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base

  3. Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land.

    Science.gov (United States)

    Nancarrow, D J; White, M M

    2004-03-01

    A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950,000 m3). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

  4. Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land

    International Nuclear Information System (INIS)

    Nancarrow, D J; White, M M

    2004-01-01

    A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950 000 m 3 ). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

  5. Final Environmental Impact Statement on 10 CFR Part 61 licensing requirements for land disposal of radioactive waste

    International Nuclear Information System (INIS)

    1982-11-01

    The three-volume final environmental impact statement (FEIS) is prepared to guide and support publication of a final regulation, 10 CFR Part 61, for the land disposal of low-level radioactive waste. The FEIS is prepared in response to public comments received on the draft environmental impact statement (DEIS) on the proposed Part 61 regulation. The DEIS was published in September 1981 as NUREG-0782. Public comments received on the proposed Part 61 regulation separate from the DEIS are also considered in the FEIS. The FEIS is not a rewritten version of the DEIS, which contains an exhaustive and detailed analysis of alternatives, but rather references the DEIS and presents the final decision bases and conclusions (costs and impacts) which are reflected in the Part 61 requirements. Four cases are specifically considered in the FEIS representing the following: past disposal practice, existing disposal practice, Part 61 requirements, and an upper bound example. The Summary and Main Report are contained in Volume 1. Volume 2 consists of Appendices A - Staff Analysis of Public Comments on the DEIS for 10 CFR Part 61, and Appendices B - Staff Analysis of Public Comments on Proposed 10 CFR Part 61 Rulemaking. Volume 3 contains Appendices C-F, entitled as follows: Appendix C - Revisions to Impact Analysis Methodology, Appendix D - Computer Codes Used for FEIS Calculations, Appendix E - Errata for the DEIS for 10 CFR Part 61 and last, Appendix F - Final Rule and Supplementary Information

  6. International Working Group on Past Reactors Thirteenth Annual Meeting. Summary Report. Part III

    International Nuclear Information System (INIS)

    1981-04-01

    The Thirteenth Annual Meeting of the IAEA International Working Group on Fast Reactors was held at the IAEA Headquarters, Vienna, Austria from 9 to 11 April 1980. The Summary Report (Part I) contains the Minutes of the Meeting. The Summary Report (Part II) contains the papers which review the national programme in the field of LMFBRs and other presentations at the Meeting. The Summary Report (Part III) contains the discussions on the review of the national programmes

  7. Final disposal of spent fuels and high activity waste: status and trends in the world. Part 2

    International Nuclear Information System (INIS)

    Herscovich de Pahissa, Marta

    2008-01-01

    The proper management of spent fuel arising from nuclear power production is a key issue for the sustainable development of nuclear energy. Some countries have adopted reprocessing of spent fuel and part of them has continued to develop and improve closed fuel cycle technologies; some other countries have adopted a direct final disposal. The objective in this article is to provide an update on the latest development in the world related with the geological disposal of spent nuclear fuel and high level wastes. (author) [es

  8. Economic impacts of 10 CFR part 61 on the land disposal of low-level radioactive waste (LLRW)

    International Nuclear Information System (INIS)

    Gaynor, R.K.

    1984-01-01

    The new regulations for land disposal of radioactive waste, 10 CFR Part 61, as promulgated by the United States Nuclear Regulatory Commission (NRC) are effective as of December 27, 1983. These new rules have required modifications to the previous practices in commercial burial of LLRW which increased the costs associated with disposal. This paper addresses the requirements of the new regulations, and describes the efforts of one burial site operator to minimize the economic impact of the regulations. Each of the requirements addressed has economic impacts relative to increased paperwork and documentation, increased inspection time, increased labor and equipment costs, increased site construction requirements and decreased disposal efficiency. Discussed in the paper are the relative cost impacts, and the actions and the degree of success of US Ecology, Inc., to minimize cost increases through license negotiations, computerized record keeping and reporting, computerized class verification, and site management and operating procedures

  9. Superfund TIO videos: Set C. Land disposal restrictions. Part 3. Audio-Visual

    International Nuclear Information System (INIS)

    1990-01-01

    The videotape discusses the fundamental requirements of the Land Disposal Restrictions (LDRs) under RCRA, methods for determining whether LDRs are applicable or relevant and appropriate requirements for a CERCLA response, and LDR compliance options

  10. The WIPP RCRA Part B permit application for TRU mixed waste disposal

    International Nuclear Information System (INIS)

    Johnson, J.E.

    1995-01-01

    In August 1993, the New Mexico Environment Department (NMED) issued a draft permit for the Waste Isolation Pilot Plant (WIPP) to begin experiments with transuranic (TRU) mixed waste. Subsequently, the Department of Energy (DOE) decided to cancel the on-site test program, opting instead for laboratory testing. The Secretary of the NMED withdrew the draft permit in 1994, ordering the State's Hazardous and Radioactive Waste Bureau to work with the DOE on submittal of a revised permit application. Revision 5 of the WIPP's Resource Conservation and Recovery Act (RCRA) Part B Permit Application was submitted to the NMED in May 1995, focusing on disposal of 175,600 m 3 of TRU mixed waste over a 25 year span plus ten years for closure. A key portion of the application, the Waste Analysis Plan, shifted from requirements to characterize a relatively small volume of TRU mixed waste for on-site experiments, to describing a complete program that would apply to all DOE TRU waste generating facilities and meet the appropriate RCRA regulations. Waste characterization will be conducted on a waste stream basis, fitting into three broad categories: (1) homogeneous solids, (2) soil/gravel, and (3) debris wastes. Techniques used include radiography, visually examining waste from opened containers, radioassay, headspace gas sampling, physical sampling and analysis of homogeneous wastes, and review of documented acceptable knowledge. Acceptable knowledge of the original organics and metals used, and the operations that generated these waste streams is sufficient in most cases to determine if the waste has toxicity characteristics, hazardous constituents, polychlorinated biphenyls (PBCs), or RCRA regulated metals

  11. Experiments on container materials for Swiss high-level waste disposal projects. Part 2

    International Nuclear Information System (INIS)

    Simpson, J.P.

    1984-12-01

    The present concept for final disposal of high-level waste in Switzerland consists of a repository at a depth of 1000 to 1500 m in the crystalline bedrock of northern Switzerland. The waste will be placed in a container which is required to function as a high integrity barrier for at least 1000 years. This report is the second of a set of two dealing with the evaluation of potential materials for such containers. Four materials were identified for further evaluation in the first of these reports; they were cast steel, nodular cast iron, copper and Ti-Code 12. It was concluded that some testing was needed, in particular with respect to corrosion, in order to confirm these materials as candidate container materials. The experimental programme included: 1) corrosion tests on copper under gamma radiation; 2) immersion corrosion tests on the four candidate materials including welded specimens; 3) corrosion testing of the four materials in saturated bentonite; 4) constant strain rate testing of Ti-Code 12 and copper at 80 degrees C; 5) the behaviour of copper, Ti-Code 12 and Zircaloy-2 when immersed in liquid lead; 6) corrosion potential and galvanic current measurements on several material pairs. The standard test medium was natural mineral water from the Bad Saeckingen source. This water has a total dissolved solids content of approx. 3200 mg/l, about 1600 mg/l as chloride. The oxygen level was defined as 0.1 μg/g. In certain cases this medium was modified in order to test under more severe conditions. The results of the corrosion tests confirm in general the evaluation in the first part of the report. All of the materials are suitable for high-level waste containers: cast steel, nodular cast iron and copper as single layer containers, and Ti-Code 12 as an outer corrosion resistant layer. Copper could also be used under an outer steel layer, where it could arrest local penetration

  12. Laboratory determination of migration of Eu(III) in compacted bentonite–sand mixtures as buffer/backfill material for high-level waste disposal

    International Nuclear Information System (INIS)

    Zhou, Lang; Zhang, Huyuan; Yan, Ming; Chen, Hang; Zhang, Ming

    2013-01-01

    For the safety assessment of geological disposal of high-level radioactive waste (HLW), the migration of Eu(III) through compacted bentonite–sand mixtures was measured under expected repository conditions. Under the evaluated conditions, advection and dispersion is the dominant migration mechanism. The role of sorption on the retardation of migration was also evaluated. The hydraulic conductivities of compacted bentonite–sand mixtures were K=2.07×10 −10 –5.23×10 −10 cm/s, The sorption and diffusion of Eu(III) were examined using a flexible wall permeameter for a solute concentration of 2.0×10 −5 mol/l. The effective diffusion coefficients and apparent diffusion coefficients of Eu(III) in compacted bentonite–sand mixtures were in the range of 1.62×10 –12 –4.87×10 –12 m 2 /s, 1.44×10 –14 –9.41×10 –14 m 2 /s, respectively, which has a very important significance to forecast the relationship between migration length of Eu(III) in buffer/backfill material and time and provide a reference for the design of buffer/backfill material for HLW disposal in China. - Highlights: • The migration progress of Eu(III) in compacted bentonite–sand mixtures was researched. • The hydraulic conductivity of cominpacted bentonite–sand mixtures was measured. • The migration length of Eu(III) in buffer/backfill material after a certain period of time was forecasted

  13. ATWS: a reappraisal. Part III. Frequency of anticipated transients. Interim report

    International Nuclear Information System (INIS)

    Leverenz, F.L. Jr.; Koren, J.M.; Erdmann, R.C.; Lellouche, G.S.

    1978-07-01

    The document is Part III of the Institute study of the ATWS question. The frequencies of the various events which have led to a reactor scram are documented from the nuclear power plant records. Some of these events, in the absence of scram, could lead to undesirable system response and are the ''transients of significance'' which comprise the anticipated transients of the ATWS question

  14. Market Analysis and Consumer Impacts Source Document. Part III. Consumer Behavior and Attitudes Toward Fuel Efficient Vehicles

    Science.gov (United States)

    1980-12-01

    This source document on motor vehicle market analysis and consumer impacts consists of three parts. Part III consists of studies and reviews on: consumer awareness of fuel efficiency issues; consumer acceptance of fuel efficient vehicles; car size ch...

  15. Japanese contributions to IAEA INTOR workshop, phase two A, part 2, chapter III: impurity control (engineering)

    International Nuclear Information System (INIS)

    Seki, Masahiro; Miki, Nobuharu; Shibutani, Yoji; Fujimura, Kaoru; Adachi, Jun-ichi; Sato, Kosuke; Fujii, Masaharu; Yamazaki, Seiichiro; Itoh, Shin-ichi.

    1985-07-01

    This report corresponds to the second half of Chapter III of Japanese contribution report to IAEA INTOR Workshop, Phase Two A, Part 2. Data base assessment are made on candidate materials for the divertor, limiter, and the first wall. Engineering trade-off studies are made for the high-recycling and low temperature conditions. The studies include material considerations, configuration, thermohydraulic and stress analysis, disruption, lifetime analysis, and tritium permeation. (author)

  16. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part III

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-09-01

    The Summary Report - Part III of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercialization LMFBRs according to national plans, mostly related to technology of fuel fabrication, PHENIX fuel pins testing, heterogeneous cores, in service inspection of fuel elements, regulations and licensing, and related OECD activities. Most of the discussions were related to the existing reactors: BR-10, BN-600, BN-350, BN-1600, RAPSODIE and PHENIX.

  17. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part III

    International Nuclear Information System (INIS)

    1978-09-01

    The Summary Report - Part III of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercialization LMFBRs according to national plans, mostly related to technology of fuel fabrication, PHENIX fuel pins testing, heterogeneous cores, in service inspection of fuel elements, regulations and licensing, and related OECD activities. Most of the discussions were related to the existing reactors: BR-10, BN-600, BN-350, BN-1600, RAPSODIE and PHENIX

  18. Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part III

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-11-01

    The Summary Report - Part III of the Tenth Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercial development of FBRs according to national plans, mostly related to technology problems of containment design, fuel fabrication, fuel failures, sodium pressure, fuel-sodium interaction, computer codes needed for licensing. Most of the discussions were related to the existing reactors: BN-600, BN-350, BN-1600, BOR-60, RAPSODIE, PHENIX.

  19. Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part III

    International Nuclear Information System (INIS)

    1977-11-01

    The Summary Report - Part III of the Tenth Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercial development of FBRs according to national plans, mostly related to technology problems of containment design, fuel fabrication, fuel failures, sodium pressure, fuel-sodium interaction, computer codes needed for licensing. Most of the discussions were related to the existing reactors: BN-600, BN-350, BN-1600, BOR-60, RAPSODIE, PHENIX

  20. 40 CFR Appendix III to Part 266 - Tier II Emission Rate Screening Limits for Free Chlorine and Hydrogen Chloride

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Tier II Emission Rate Screening Limits for Free Chlorine and Hydrogen Chloride III Appendix III to Part 266 Protection of Environment... to Part 266—Tier II Emission Rate Screening Limits for Free Chlorine and Hydrogen Chloride Terrain...

  1. Process for environmentally safe disposal of used fluorescent lamp potted ballast assemblies with component part reclamation and/or recycling

    Energy Technology Data Exchange (ETDEWEB)

    Nardella, A.; Norian, B.

    1993-07-27

    A process is described for the environmentally safe and economical disposal of used fluorescent lamp potted ballast housing assemblies comprising removing from the housing the potted assembly with its embedded electrical component assemblies including a component capacitor containing environmentally hazardous material PCB's; after or before such removing, immersing the potted assembly in a cryogenic bath and freezing the same to reader the potting sufficiently brittle to fragment into small pieces upon being impacted; impacting the potting thoroughly to crush and fragment the same into small pieces and to cleanly remove substantially all traces of the potting from all the electrical components and parts embedded therein and without imparting damage to the components and parts; disconnecting the component containing the environmentally hazardous material; and incinerating only the component containing the environmentally hazardous material, leaving all other components and parts including the housing and potting fragments for salvage, re-use and/or recycling.

  2. Building human resources capability in health care: a global analysis of best practice--Part III.

    Science.gov (United States)

    Zairi, M

    1998-01-01

    This is the last part of a series of three papers which discussed very comprehensively best practice applications in human resource management by drawing special inferences to the healthcare context. It emerged from parts I and II that high performing organisations plan and intend to build sustainable capability through a systematic consideration of the human element as the key asset and through a continuous process of training, developing, empowering and engaging people in all aspects of organisational excellence. Part III brings this debate to a close by demonstrating what brings about organisational excellence and proposes a road map for effective human resource development and management, based on world class standards. Healthcare human resource professionals can now rise to the challenge and plan ahead for building organisational capability and sustainable performance.

  3. Neuroscience in Nazi Europe Part III: victims of the Third Reich.

    Science.gov (United States)

    Zeidman, Lawrence A; Kondziella, Daniel

    2012-11-01

    In Part I, neuroscience collaborators with the Nazis were discussed, and in Part II, neuroscience resistors were discussed. In Part III, we discuss the tragedy regarding european neuroscientists who became victims of the Nazi onslaught on “non-Aryan” doctors. Some of these unfortunate neuroscientists survived Nazi concentration camps, but most were murdered. We discuss the circumstances and environment which stripped these neuroscientists of their profession, then of their personal rights and freedom, and then of their lives. We include a background analysis of anti-Semitism and Nazism in their various countries, then discuss in depth seven exemplary neuroscientist Holocaust victims; including Germans Ludwig Pick, Arthur Simons, and Raphael Weichbrodt, Austrians Alexander Spitzer and Viktor Frankl, and Poles Lucja Frey and Wladyslaw Sterling. by recognizing and remembering these victims of neuroscience, we pay homage and do not allow humanity to forget, lest this dark period in history ever repeat itself.

  4. Social class, political power, and the state: their implications in medicine--part III.

    Science.gov (United States)

    Navarro, V

    1977-01-01

    This is the third part of an article on the distribution of power and the nature of the state in Western industrialized societies and their implications in medicine. Parts I and II were published in the preceding issue of this Journal. Part I presented a critique of contemporary theories of the Western system of power; discussed the countervailing pluralist and power of elite theories, as well as those of bureaucratic and professional control; and concluded with an examination of the Marxist theories of economic determinism, structural determinism, and corporate statism. Part II presented a Marxist theory of the role, nature, and characteristics of state intervention. Part III focuses on the mode of that intervention and the reasons for its growth, with an added analysis of the attributes of state intervention in the health sector, and of the dialectical relationship between its growth and the current fiscal crisis of the state. In all three parts, the focus is on Western European countries and on North America, with many examples and categories from the area of medicine.

  5. 10 CFR Appendix III to Part 960 - Application of the System and Technical Guidelines During the Siting Process

    Science.gov (United States)

    2010-01-01

    ... 960—Application of the System and Technical Guidelines During the Siting Process 1. This appendix... 10 Energy 4 2010-01-01 2010-01-01 false Application of the System and Technical Guidelines During the Siting Process III Appendix III to Part 960 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE...

  6. R/V Endeavor cruise EN-024. Seabed Disposal Program: North Atlantic study area MPG-III 35030'N 61000'W, June 30--July 11, 1978. Final report

    International Nuclear Information System (INIS)

    Heath, G.R.; Laine, E.P.

    1978-09-01

    During 7 days in the vicinity of 35 0 30'N, 61 0 00'W (Seabed Disposal Program mid-late, mid-gyre study area MPG-III) we carried out 1830 km of subbottom acoustic profiling and 2 camera lowerings, and took 7 standard piston cores, 3 large diameter piston cores, 9 large diameter gravity cores and 2 dredge hauls of surface sediment. Pore fluids were extracted from 3 gravity cores and 1 piston core and on-board physical property measurements were made on 2 large diameter piston cores and 1 large diameter gravity core. These data and samples will be used to assess the lateral homogeneity and recent geologic history of the area, as well as to compare the sorption and physical barrier properties of the sediments with deposits from the MPG I and II areas in the Pacific

  7. Preparing sewage sludge for land application or surface disposal: A guide for preparers of sewage sludge on the monitoring, record keeping, and reporting requirements of the federal standards for the use of disposal of sewage sludge, 40 CFR part 503

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    The document focuses on the monitoring, recordkeeping, and reporting requirements that apply to persons who prepare sewage sludge or a material derived from sewage sludge. It defines persons who prepare sewage sludge and then summarizes their general responsibilities. USEPA promulgated at 40 CFR Part 503 Phase 1 of the risk-based regulations that govern the final use or disposal of sewage sludge. The intent of the Federal program is to ensure that the use or disposal of sewage sludge occurs in a way that protects both human health and the environment. The Part 503 regulation establishes general requirements, pollutant limits, operational standards, and management practices, as well as monitoring, recordkeeping, and reporting requirements. These requirements apply to sewage sludge that is land applied, placed on a surface disposal site, or incinerated in a sewage sludge-only incinerator.

  8. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Introductory part and summaries

    International Nuclear Information System (INIS)

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan and comprises seven chapters. Chapter I briefly describes the importance of HLW management in promoting nuclear energy utilization. According to the long-term program, the HLW separated from spent fuels at reprocessing plants is to be vitrified and stored for a period of 30 to 50 years to allow cooling, then be disposed of in a deep geological formation. Chapter II mainly explains the concepts of geological disposal in Japan. Chapters III to V are devoted to discussions on three important technical elements (the geological environment of Japan, engineering technology and safety assessment of the geological disposal system) which are necessary for reliable realization of the geological disposal concept. Chapter VI demonstrates the technical ground for site selection and for setup of safety standards of the disposal. Chapter VII summarizes together with plans for future research and development. (Ohno, S.)

  9. A Disposable Tear Glucose Biosensor—Part 2: System Integration and Model Validation

    Science.gov (United States)

    La Belle, Jeffrey T.; Bishop, Daniel K.; Vossler, Stephen R.; Patel, Dharmendra R.; Cook, Curtiss B.

    2010-01-01

    Background We presented a concept for a tear glucose sensor system in an article by Bishop and colleagues in this issue of Journal of Diabetes Science and Technology. A unique solution to collect tear fluid and measure glucose was developed. Individual components were selected, tested, and optimized, and system error modeling was performed. Further data on prototype testing are now provided. Methods An integrated fluidics portion of the prototype was designed, cast, and tested. A sensor was created using screen-printed sensors integrated with a silicone rubber fluidics system and absorbent polyurethane foam. A simulated eye surface was prepared using fluid-saturated poly(2-hydroxyethyl methacrylate) sheets, and the disposable prototype was tested for both reproducibility at 0, 200, and 400 μM glucose (n = 7) and dynamic range of glucose detection from 0 to 1000 μM glucose. Results From the replicated runs, an established relative standard deviation of 15.8% was calculated at 200 μM and a lower limit of detection was calculated at 43.4 μM. A linear dynamic range was demonstrated from 0 to 1000 μM with an R2 of 99.56%. The previously developed model predicted a 14.9% variation. This compares to the observed variance of 15.8% measured at 200 μM glucose. Conclusion With the newly designed fluidics component, an integrated tear glucose prototype was assembled and tested. Testing of this integrated prototype demonstrated a satisfactory lower limit of detection for measuring glucose concentration in tears and was reproducible across a physiological sampling range. The next step in the device design process will be initial animal studies to evaluate the current prototype for factors such as eye irritation, ease of use, and correlation with blood glucose. PMID:20307390

  10. A disposable tear glucose biosensor-part 2: system integration and model validation.

    Science.gov (United States)

    La Belle, Jeffrey T; Bishop, Daniel K; Vossler, Stephen R; Patel, Dharmendra R; Cook, Curtiss B

    2010-03-01

    We presented a concept for a tear glucose sensor system in an article by Bishop and colleagues in this issue of Journal of Diabetes Science and Technology. A unique solution to collect tear fluid and measure glucose was developed. Individual components were selected, tested, and optimized, and system error modeling was performed. Further data on prototype testing are now provided. An integrated fluidics portion of the prototype was designed, cast, and tested. A sensor was created using screen-printed sensors integrated with a silicone rubber fluidics system and absorbent polyurethane foam. A simulated eye surface was prepared using fluid-saturated poly(2-hydroxyethyl methacrylate) sheets, and the disposable prototype was tested for both reproducibility at 0, 200, and 400 microM glucose (n = 7) and dynamic range of glucose detection from 0 to 1000 microM glucose. From the replicated runs, an established relative standard deviation of 15.8% was calculated at 200 microM and a lower limit of detection was calculated at 43.4 microM. A linear dynamic range was demonstrated from 0 to 1000 microM with an R(2) of 99.56%. The previously developed model predicted a 14.9% variation. This compares to the observed variance of 15.8% measured at 200 microM glucose. With the newly designed fluidics component, an integrated tear glucose prototype was assembled and tested. Testing of this integrated prototype demonstrated a satisfactory lower limit of detection for measuring glucose concentration in tears and was reproducible across a physiological sampling range. The next step in the device design process will be initial animal studies to evaluate the current prototype for factors such as eye irritation, ease of use, and correlation with blood glucose. (c) 2010 Diabetes Technology Society.

  11. Experiments on container materials for Swiss high-level waste disposal projects. Part IV

    International Nuclear Information System (INIS)

    Simpson, J.P.

    1989-12-01

    One concept for final disposal of high-level waste in switzerland consists of a repository at a depth of 1000 to 1500 m in the crystalline bedrock of Northern Switzerland. The waste will be placed in a container which will be required to function as a high integrity barrier for at least 100 years. This report is the fourth and last in the current series dealing with the evaluation of potential materials for such containers. Four materials were identified for further evaluation in the first of these reports: cast steel, nodular cast iron, copper and Ti-Code 12. This report deals with the problem of demonstrating that cast steel containers will not fail by stress corrosion cracking and with the problem of hydrogen produced by the reduction of water. The experimental results on pre-cracked specimens revealed no susceptibility of cast steel to stress corrosion cracking under model repository conditions. No crack growth was detected on compact DCB specimens exposed in aerobic and anaerobic groundwaters at 80 and 140 o C for 16-24 months. Cast steel remains a candidate material for high-level waste containers. As expected from thermodynamic considerations no hydrogen could be detected from copper immersed in model groundwaters at 50 o C. Hydrogen is evolved from corroding steel under anaerobic conditions. Hydrogen evolution due to corrosion of iron or steel in waste repositories has to be considered in any safety analysis; the amounts produced can be significant. Evidence todate suggests that both cast steel and copper are suitable container materials. Because the corrosion behaviour of both materials is sensitive to service conditions, in particular length of the aerobic phase, groundwater chemistry and temperature, further testing should be undertaken when a specific site has been identified. (author) 9 tabs., 11 figs., 25 refs

  12. Anatomy of a decision III: Evaluation of national disposal at sea program action level efficacy considering 2 chemical action levels.

    Science.gov (United States)

    Apitz, Sabine E; Vivian, Chris; Agius, Suzanne

    2017-11-01

    The potential performance (i.e., ability to separate nontoxic from toxic sediments) of a range of international Disposal at Sea (DaS) chemical Action Levels (ALs) was compared using a sediment chemical and toxicological database. The use of chemistry alone (without the use of further lines of evidence) did not perform well at reducing costs and protecting the environment. Although some approaches for interpreting AL1 results are very effective at filtering out the majority of acutely toxic sediments, without subsequent toxicological assessment, a large proportion of nontoxic sediments would be unnecessarily subjected to treatment and containment, and a number of sublethally toxic sediments would be missed. Even the best tiered systems that collect and evaluate information sequentially resulted in the failure to catch at least some sublethally or acutely toxic sediments. None of the AL2s examined were particularly effective in distinguishing between non-, sublethally, or acutely toxic sediments. Thus, this review did not support the use of chemical AL2s to predict the degree to which sediments will be toxic. Integr Environ Assess Manag 2017;13:1086-1099.© 2017 The Authors. Integrated Environmental Assessment and Management Published by Wiley Periodicals, Inc. on behalf of Society of Environmental Toxicology & Chemistry (SETAC). © 2017 The Authors. Integrated Environmental Assessment and Management Published by Wiley Periodicals, Inc. on behalf of Society of Environmental Toxicology & Chemistry (SETAC).

  13. Thermal sensation and comfort models for non-uniform and transient environments: Part III: whole-body sensation and comfort

    OpenAIRE

    Zhang, Hui; Arens, Edward; Huizenga, Charlie; Han, Taeyoung

    2009-01-01

    A three-part series presents the development of models for predicting the local thermal sensation (Part I) and local thermal comfort (Part II) of different parts of the human body, and also the whole-body sensation and comfort (Part III) that result from combinations of local sensation and comfort. The models apply to sedentary activities in a range of environments: uniform and non-uniform, stable and transient. They are based on diverse findings from the literature and from body-part-specifi...

  14. Waste disposal

    International Nuclear Information System (INIS)

    2005-01-01

    Radioactive waste, as a unavoidable remnant from the use of radioactive substances and nuclear technology. It is potentially hazardous to health and must therefore be managed to protect humans and the environment. The main bulk of radioactive waste must be permanently disposed in engineered repositories. Appropriate safety standards for repository design and construction are required along with the development and implementation of appropriate technologies for the design, construction, operation and closure of the waste disposal systems. As backend of the fuel cycle, resolving the issue of waste disposal is often considered as a prerequisite to the (further) development of nuclear energy programmes. Waste disposal is therefore an essential part of the waste management strategy that contributes largely to build confidence and helps decision-making when appropriately managed. The International Atomic Energy Agency provides assistance to Member States to enable safe and secure disposal of RW related to the development of national RWM strategies, including planning and long-term project management, the organisation of international peer-reviews for research and demonstration programmes, the improvement of the long-term safety of existing Near Surface Disposal facilities including capacity extension, the selection of potential candidate sites for different waste types and disposal options, the characterisation of potential host formations for waste facilities and the conduct of preliminary safety assessment, the establishment and transfer of suitable technologies for the management of RW, the development of technological solutions for some specific waste, the building of confidence through training courses, scientific visits and fellowships, the provision of training, expertise, software or hardware, and laboratory equipment, and the assessment of waste management costs and the provision of advice on cost minimisation aspects

  15. Final Environmental Impact Statement on 10 CFR Part 61 licensing requirements for land disposal of radioactive waste. Summary and main report

    International Nuclear Information System (INIS)

    1982-11-01

    The three-volume final environmental impact statement (FEIS) is prepared to guide and support publication of a final regulation, 10 CFR Part 61, for the land disposal of low-level radioactive waste. The FEIS is prepared in response to public comments received on the draft environmental impact statement (DEIS) on the proposed Part 61 regulation. The DEIS was published in September 1981 as NUREG-0782. Public comments received on the proposed Part 61 regulation separate from the DEIS are also considered in the FEIS. The FEIS is not a rewritten version of the DEIS, which contains an exhaustive and detailed analysis of alternatives, but rather references the DEIS and presents the final decision bases and conclusions (costs and impacts) which are reflected in the Part 61 requirements. Four cases are specifically considered in the FEIS representing the following: past disposal practice, existing disposal practice, Part 61 requirements, and an upper bound example. The Summary and Main Report are contained in Volume 1. Volume 2 consists of Appendices A - Staff Analysis of Public Comments on the DEIS for 10 CFR Part 61, and Appendices B - Staff Analysis of Public Comments on Proposed 10 CFR Part 61 Rulemaking. Volume 3 contains Appendices C-F, entitled as follows: Appendix C - Revisions to Impact Analysis Methodology, Appendix D - Computer Codes Used for FEIS Calculations, Appendix E - Errata for the DEIS for 10 CFR Part 61 and last, Appendix F - Final Rule and Supplementary Information

  16. 10 CFR Appendix G to Part 20 - Requirements for Transfers of Low-Level Radioactive Waste Intended for Disposal at Licensed Land...

    Science.gov (United States)

    2010-01-01

    ... Disposal Facilities and Manifests I. Manifest A waste generator, collector, or processor who transports, or... who is the “waste generator” or “generator,” as defined in this part; or (c) Radioactively... Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-7232, or by...

  17. Physiotherapy and low back pain - part iii: outcomes research utilising the biosychosocial model: psychosocial outcomes

    Directory of Open Access Journals (Sweden)

    L. D. Bardin

    2003-02-01

    has evolved that necessitates the use of a biopsychosocial model, focusing on illness rather than disease and incorporating the biological, psychological and social aspects that are important to understand and to study LBP in its chronic form. Traditional outcome measures that measure elements within the biological component are limited to assess the spectrum of impacts caused by chronic low back pain (CLBP and the validity, reliability and sensitivity of some of these measures has been questioned.Few physiologic tests of spine function are clinically meaningful to patients, objective physical findings can be absent, and in CLBP disability and activity intolerance are often disproportional to the original injury. Biological outcomes should be complemented by outcomes of the psychosocial aspects of back pain that measure the considerable functional and emotional impact on the quality of life of patients experiencing low back dysfunction. Outcomes research is an analysis of clinical practice as it actually occurs and can  make a valuable contribution to understanding the multidimensional impact of LBP. Psychosocial aspects of the biopsychosocial model for outcomes research are discussed in part III: functional status/disability, psychological impairment, patient satisfaction, health related quality of life

  18. A Structural Molar Volume Model for Oxide Melts Part III: Fe Oxide-Containing Melts

    Science.gov (United States)

    Thibodeau, Eric; Gheribi, Aimen E.; Jung, In-Ho

    2016-04-01

    As part III of this series, the model is extended to iron oxide-containing melts. All available experimental data in the FeO-Fe2O3-Na2O-K2O-MgO-CaO-MnO-Al2O3-SiO2 system were critically evaluated based on the experimental condition. The variations of FeO and Fe2O3 in the melts were taken into account by using FactSage to calculate the Fe2+/Fe3+ distribution. The molar volume model with unary and binary model parameters can be used to predict the molar volume of the molten oxide of the Li2O-Na2O-K2O-MgO-CaO-MnO-PbO-FeO-Fe2O3-Al2O3-SiO2 system in the entire range of compositions, temperatures, and oxygen partial pressures from Fe saturation to 1 atm pressure.

  19. GEOSAF Part II. Demonstration of the operational and long-term safety of geological disposal facilities for radioactive waste. IAEA international intercomparison and harmonization project

    Energy Technology Data Exchange (ETDEWEB)

    Kumano, Yumiko; Bruno, Gerard [International Atomic Energy Agency, Vienna (Austria). Vienna International Centre; Tichauer, Michael [IRSN, Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Hedberg, Bengt [Swedish Radiation Safety Authority, Stockholm (Sweden)

    2015-07-01

    International intercomparison and harmonization projects are one of the mechanisms developed by the IAEA for examining the application and use of safety standards, with a view to ensuring their effectiveness and working towards harmonization of approaches to the safety of radioactive waste management. The IAEA has organized a number of international projects on the safety of radioactive waste management; in particular on the issues related to safety demonstration for radioactive waste management facilities. In 2008, GEOSAF, Demonstration of The Operational and Long-Term Safety of Geological Disposal Facilities for Radioactive Waste, project was initiated. This project was completed in 2011 by delivering a project report focusing on the safety case for geological disposal facilities, a concept that has gained in recent years considerable prominence in the waste management area and is addressed in several international safety standards. During the course of the project, it was recognized that little work was undertaken internationally to develop a common view on the safety approach related to the operational phase of a geological disposal although long-term safety of disposal facility has been discussed for several decades. Upon completion of the first part of the GEOSAF project, it was decided to commence a follow-up project aiming at harmonizing approaches on the safety of geological disposal facilities for radioactive waste through the development of an integrated safety case covering both operational and long-term safety. The new project was named as GEOSAF Part II, which was initiated in 2012 initially as 2-year project, involving regulators and operators. GEOSAF Part II provides a forum to exchange ideas and experience on the development and review of an integrated operational and post-closure safety case for geological disposal facilities. It also aims at providing a platform for knowledge transfer. The project is of particular interest to regulatory

  20. Acuity and case management: a healthy dose of outcomes, part III.

    Science.gov (United States)

    Huber, Diane L; Craig, Kathy

    2007-01-01

    This is the third of a 3-part series presenting 2 effective applications--acuity and dosage--that describe how the business case for case management (CM) can be made. In Part I, dosage and acuity concepts were explained as client need-severity, CM intervention-intensity, and CM activity-dose prescribed by amount, frequency, duration, and breadth of activities. Concepts were presented that related the practice of CM to the use of evidence-based practice (EBP), knowledge, and methods and the development of instruments that measure and score pivotal CM actions. Part I also featured a specific exemplar, the CM Acuity Tool, and described how to use acuity to identify and score the complexity of a CM case. Part II further explained dosage and 2 acuity instruments, the Acuity Tool and AccuDiff. Part III presents linkage to EBP and practical applications. The information contained in the 3-part series applies to all CM practice settings and contains ideas and recommendations useful to CM generalists, specialists, supervisors, and business and outcomes managers. The Acuity Tools Project was developed from frontline CM practice in one large, national telephonic CM company. Dosage: A literature search failed to find research into dosage of a behavioral intervention. The Huber-Hall model was developed and tested in a longitudinal study of CM models in substance abuse treatment and reported in the literature. Acuity: A structured literature search and needs assessment launched the development of the suite of acuity tools. A gap analysis identified that an instrument to assign and measure case acuity specific to CM activities was needed. Clinical experts, quality specialists, and business analysts (n = 7) monitored the development and testing of the tools, acuity concepts, scores, differentials, and their operating principles and evaluated the validity of the acuity tools' content related to CM activities. During the pilot phase of development, interrater reliability testing of

  1. Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel and Transuranic Radioactive Wastes (40 CFR Part 191)

    Science.gov (United States)

    This regulation sets environmental standards for public protection from the management and disposal of spent nuclear fuel, high-level wastes and wastes that contain elements with atomic numbers higher than uranium (transuranic wastes).

  2. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 1. Geological environment of Japan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 1 of the progress report, describes first in detail the role of geological environment in high-level radioactive wastes disposal, the features of Japanese geological environment, and programs to proceed the investigation in geological environment. The following chapter summarizes scientific basis for possible existence of stable geological environment, stable for a long period needed for the HLW disposal in Japan including such natural phenomena as volcano and faults. The results of the investigation of the characteristics of bed-rocks and groundwater are presented. These are important for multiple barrier system construction of deep geological disposal. The report furthermore describes the present status of technical and methodological progress in investigating geological environment and finally on the results of natural analog study in Tono uranium deposits area. (Ohno, S.)

  3. Providing for energy efficiency in homes and small buildings. Part III. Determining which practices are most effective and installing materials

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

    The training program is designed to educate students and individuals in the importance of conserving energy and to provide for developing skills needed in the application of energy-saving techniques that result in energy-efficient buildings. A teacher guide and student workbook are available to supplement the basic manual. Subjects covered in Part III are: determining which practices are most efficient and economical; installing energy-saving materials; and improving efficiency of equipment.

  4. Technical Reports (Part I). End of Project Report, 1968-1971, Volume III.

    Science.gov (United States)

    Western Nevada Regional Education Center, Lovelock.

    The pamphlets included in this volume are technical reports prepared as outgrowths of the Student Information Systems of the Western Nevada Regional Education Center (WN-REC) funded by a Title III (Elementary and Secondary Education Act) grant. These reports describe methods of interpreting the printouts from the Student Information System;…

  5. Geologic and hydrologic characterization and evaluation of the Basin and Range Province relative to the disposal of high-level radioactive waste: Part I, Introduction and guidelines

    Science.gov (United States)

    Bedinger, M.S.; Sargent, Kenneth A.; Reed, J.E.

    1984-01-01

    The U.S. Geological Survey's program for geologic and hydrologic evaluation of physiographic provinces to identify areas potentially suitable for locating repository sites for disposal of high-level nuclear wastes was announced to the Governors of the eight States in the Basin and Range Province on May 5, 1981. Representatives of Arizona, California, Idaho, New Mexico, Nevada, Oregon, Texas, and Utah, were invited to cooperate with the Federal Government in the evaluation process. Each Governor was requested to nominate an Earth scientist to represent the State in a province working group composed of State and U.S. Geological Survey representatives. This report, Part I of a three-part report, provides the background, introduction and scope of the study. This part also includes a discussion of geologic and hydrologic guidelines that will be used in the evaluation process and illustrates geohydrologic environments and the effect of individual factors in providing multiple natural barriers to radionuclide migration.Part II is a reconnaissance characterization of the geologic and hydrologic factors to be used in the initial screening of the Basin and Range Province. Part III will be the initial evaluation of the Province and will identify regions that appear suitable for further study.The plan for study of the Province includes a stepwise screening process by which successively smaller land units are considered in increasing detail. Each step involves characterization of the geology and hydrology and selection of subunits for more intensive characterization. Selection of subunits for further study is by evaluation of geologic and hydrologic conditions following a set of guidelines. By representation on the Province Working Group, the States participate in a consultation and review role in: (1) Establishing geologic and hydrologic guidelines, and (2) characterizing and evaluating the Province. The States also participate in compilation of geologic and hydrologic data

  6. Quantitative assessment of consequences of natural events for the performance of waste disposal isolation system: Part (II)

    International Nuclear Information System (INIS)

    Ohkubo, Hiroo

    1999-12-01

    This year, first, regarding to the volcanism, seismicity and faulting, and uplift and erosion scenarios, in addition to the evaluation of those scenarios are variant cases carried out last year, variant cases where directly impacted repository could be also treated have been studied and evaluated. Secondly, based on a series of discussions in these years, a comprehensive study was made to evaluate the complex effect caused by combining natural events such as volcanism, seismicity and faulting, uplift and erosion, and climate change as well as human activity, where discussions have been made on which combined scenario was more important and how to set the analysis framework. Finally, in order to discuss alternatives such as non-groundwater scenario and/or non-geological disposal strategy, long-term storage scenario was considered to be compared with geological disposal scenario. (author)

  7. Large-scale demonstration of disposal of decontaminated salt as saltstone. Part I. Construction, loading, and capping of lysimeters

    International Nuclear Information System (INIS)

    Wolf, H.C.

    1984-06-01

    The installation phase of a large-scale demonstration of the disposal concept for decontaminated, low-level radioactive salt waste at the Savannah River Plant was completed in December 1983 and January 1984. The installation entailed immobilizing 7500 gallons of decontaminated salt solution with a blended cement formulation and pouring the resulting grout, saltstone, into three specially designed lysimeters for extended in-field leaching tests under natural conditions. 4 references, 35 figures, 4 tables

  8. Final disposal of spent fuels and high activity waste: the European model for a shared regional repository. Part 3

    International Nuclear Information System (INIS)

    Herscovich de Pahissa, Marta

    2009-01-01

    Geological disposal is a essential element and the only available approach to the management strategy for spent nuclear fuel and high level radioactive waste from reprocessing and also for other long-lived waste from nuclear technology applications. It is technically feasible and offers the required long term safety. The growth of existing nuclear programmes and the expansion of nuclear technology to new countries will have effects on the fuel cycle because of the increased concern on proliferation and waste management. The crucial task is to ensure that all countries that use nuclear energy now or will do it in the future, have defined and agreed safety and security standards for all facilities and a credible waste disposal strategy , accepted by the community, when this become necessary. Multinational cooperation on essential aspects of fuel cycle, particularly the geological disposal, is required for several countries with relatively small nuclear energy programmes or small quantities of radioactive waste. For these countries, that can be in different stages of development, the possibility to share a deep geological repository could be convenient. The European Union SAPIERR project is described in this paper as an example of a regional multinational cooperation. (author) [es

  9. Fracture toughness of A533B Part III - variability of A533B fracture toughness as determined from Charpy data

    International Nuclear Information System (INIS)

    Druce, S.G.; Eyre, B.L.

    1978-08-01

    This is the final part of a series of three reports examining the upper shelf fracture toughness of A533B Class 1 pressure vessel steel. Part I (AERE R 8968) critically reviews the current elasto plastic fracture mechanics methodologies employed to characterise toughness following extensive yielding and Part II (AERE R 8969) examines several sources of fracture mechanics data pertinent to A533B Class 1 in the longitudinal (RW) orientation. Part III is a review of the effects of (i) position and orientation within the plate (ii) welding processes and post weld heat treatment and (iii) neutron irradiation as measured by Charpy impact testing. It is concluded that the upper shelf factor energy is dependent on orientation and position and can be reduced by welding, extended post weld heat treatments and neutron irradiation. Neutron irradiation effects are known to be strongly dependent on composition and metallurgical conditions, but an explanation for the variability following extended post weld treatments has yet to be resolved. (author)

  10. Eighth annual meeting, Vienna, Austria, 15-18 April 1975. Summary report. Part III

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-01-01

    The Summary Report of the Eighth Annual Meeting of the International Working Group on Fast Reactors contains the minutes of the meeting (Part 1); papers which review the national programmes in the field of LMFBRs (Part 2) and the discussions on the review of national programmes (Part 3). The agenda of the meeting involved design, construction, operating experiences of demonstration fast power reactors, reprocessing of spent fuel from LMFBRs, reliability of decay heat removal systems, fuel failure mechanisms, safety of LMFBRs.

  11. Eighth annual meeting, Vienna, Austria, 15-18 April 1975. Summary report. Part III

    International Nuclear Information System (INIS)

    1976-01-01

    The Summary Report of the Eighth Annual Meeting of the International Working Group on Fast Reactors contains the minutes of the meeting (Part 1); papers which review the national programmes in the field of LMFBRs (Part 2) and the discussions on the review of national programmes (Part 3). The agenda of the meeting involved design, construction, operating experiences of demonstration fast power reactors, reprocessing of spent fuel from LMFBRs, reliability of decay heat removal systems, fuel failure mechanisms, safety of LMFBRs

  12. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    International Nuclear Information System (INIS)

    2010-01-01

    The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

  13. Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Programs

    2010-10-04

    The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

  14. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2010-07-19

    The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

  15. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

    International Nuclear Information System (INIS)

    2010-01-01

    The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

  16. Thermal sensation and comfort models for non-uniform and transient environments, part III: Whole-body sensation and comfort

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Hui; Arens, Edward; Huizenga, Charlie [Center for the Built Environment, UC Berkeley (United States); Han, Taeyoung [General Motors Company (United States)

    2010-02-15

    A three-part series presents the development of models for predicting the local thermal sensation (Part I) and local thermal comfort (Part II) of different parts of the human body, and also the whole-body sensation and comfort (Part III) that result from combinations of local sensation and comfort. The models apply to sedentary activities in a range of environments: uniform and non-uniform, stable and transient. They are based on diverse findings from the literature and from body-part-specific human subject tests in a climate chamber. They were validated against a test of automobile passengers. The series is intended to present the models' rationale, structure, and coefficients, so that others can test them and develop them further as additional empirical data becomes available. A) The whole-body (overall) sensation model has two forms, depending on whether all of the body's segments have sensations effectively in the same direction (e.g warm or cool), or whether some segments have sensations opposite to those of the rest of the body. For each, individual body parts have different weights for warm versus cool sensations, and strong local sensations dominate the overall sensation. If all sensations are near neutral, the overall sensation is close to the average of all body sensations. B) The overall comfort model also has two forms. Under stable conditions, people evaluate their overall comfort by a complaint-driven process, meaning that when two body parts are strongly uncomfortable, no matter how comfortable the other body parts might be, the overall comfort will be near the discomfort level of the two most uncomfortable parts. When the environmental conditions are transient, or people have control over their environments, overall comfort is better than that of the two most uncomfortable body parts. This can be accounted for by adding the most comfortable vote to the two most uncomfortable ones. (author)

  17. PIO I-II tendencies. Part 2. Improving the pilot modeling

    Directory of Open Access Journals (Sweden)

    Ioan URSU

    2011-03-01

    Full Text Available The study is conceived in two parts and aims to get some contributions to the problem ofPIO aircraft susceptibility analysis. Part I, previously published in this journal, highlighted the mainsteps of deriving a complex model of human pilot. The current Part II of the paper considers a properprocedure of the human pilot mathematical model synthesis in order to analyze PIO II typesusceptibility of a VTOL-type aircraft, related to the presence of position and rate-limited actuator.The mathematical tools are those of semi global stability theory developed in recent works.

  18. Active Control of Low-Speed Fan Tonal Noise Using Actuators Mounted in Stator Vanes: Part III Results

    Science.gov (United States)

    Sutliff, Daniel L.; Remington, Paul J.; Walker, Bruce E.

    2003-01-01

    A test program to demonstrate simplification of Active Noise Control (ANC) systems relative to standard techniques was performed on the NASA Glenn Active Noise Control Fan from May through September 2001. The target mode was the m = 2 circumferential mode generated by the rotor-stator interaction at 2BPF. Seven radials (combined inlet and exhaust) were present at this condition. Several different error-sensing strategies were implemented. Integration of the error-sensors with passive treatment was investigated. These were: (i) an in-duct linear axial array, (ii) an induct steering array, (iii) a pylon-mounted array, and (iv) a near-field boom array. The effect of incorporating passive treatment was investigated as well as reducing the actuator count. These simplified systems were compared to a fully ANC specified system. Modal data acquired using the Rotating Rake are presented for a range of corrected fan rpm. Simplified control has been demonstrated to be possible but requires a well-known and dominant mode signature. The documented results here in are part III of a three-part series of reports with the same base title. Part I and II document the control system and error-sensing design and implementation.

  19. EFSUMB Guidelines on Interventional Ultrasound (INVUS), Part III - Abdominal Treatment Procedures (Long Version)

    DEFF Research Database (Denmark)

    Dietrich, Christoph F; Lorentzen, T.; Appelbaum, L.

    2016-01-01

    The third part of the European Federation of Societies for Ultrasound in Medicine and Biology (EFSUMB) Guidelines on Interventional Ultrasound (INVUS) assesses the evidence for ultrasound-guided and assisted interventions in abdominal treatment procedures. Recommendations for clinical practice ar...

  20. EFSUMB Guidelines on Interventional Ultrasound (INVUS), Part III - Abdominal Treatment Procedures (Short Version)

    DEFF Research Database (Denmark)

    Dietrich, Christoph F; Lorentzen, T.; Appelbaum, L.

    2016-01-01

    The third part of the European Federation of Societies for Ultrasound in Medicine and Biology (EFSUMB) Guidelines on Interventional Ultrasound assesses the evidence for ultrasound-guided and assisted interventions in abdominal treatment procedures. Recommendations for clinical practice are presen...

  1. Geologic and hydrologic characterization and evaluation of the Basin and Range Province relative to the disposal of high-level radioactive waste. Part I. Introduction and guidelines

    International Nuclear Information System (INIS)

    Bedinger, M.S.; Sargent, K.A.; Reed, J.E.

    1984-01-01

    The US Geological Survey's program for geologic and hydrologic evaluation of physiographic provinces to identify areas potentially suitable for locating repository sites for disposal of high-level nuclear wastes was announced to the Governors of the eight states in the Basin and Range Province on May 5, 1981. Representatives of Arizona, California, Idaho, New Mexico, Nevada, Oregon, Texas, and Utah, were invited to cooperate with the federal government in the evaluation process. Each governor was requested to nominate an earth scientist to represent the state in a province working group composed of state and US Geological Survey representatives. This report, Part I of a three-part report, provides the background, introduction and scope of the study. This part also includes a discussion of geologic and hydrologic guidelines that will be used in the evaluation process and illustrates geohydrologic environments and the effect of individual factors in providing multiple natural barriers to radionuclide migration. 27 refs., 6 figs., 1 tab

  2. Antibacterianos de acción sistémica: Parte III. Sulfonamidas y tetraciclinas

    Directory of Open Access Journals (Sweden)

    Manuel Cué Brugueras

    1999-04-01

    Full Text Available Resumen: Se presenta la tercera parte de una revisión bibliográfica sobre los antibacterianos de elección, en la cual se abordan los grupos sulfonamidas y tetraciclinas; además, se incluye un cuadro resumen con los antibióticos tratados en las tres partes, así como sus vías de administración y nombres comerciales que se utilizan en Cuba. Se hacen algunas consideraciones sobre la manera de enfrentar la gran variedad de antibióticos y el costo de la antibióticoterapia por parte de los países en vías de desarrollo, tomando como referencia algunas recomendaciones hechas por la OPS/OMSSummary: The third part of a bibliographic review on the elective antibacterials in which the groups of sulfonamides and tetracyclines are approached is presented. It is also included a summary picture with the antibiotics dealt with in the three parts, the routes of administration, and the trade names used in Cuba. Some considerations are made on the way to face the wide range of antibiotics and the cost of antibiotic therapy in the developing countries, taking into account some recommendations made by the PAHO/WHO

  3. Transport properties of gaseous ions over a wide energy range. Part III

    International Nuclear Information System (INIS)

    Ellis, H.W.; Thackston, M.G.; McDaniel, E.W.; Mason, E.A.

    1984-01-01

    This paper updates and extends in scope our two previous papers entitled ''Transport Properties of Gaseous Ions over a Wide Energy Range.'' The references to the earlier publications (referred to as ''Part I'' and ''Part II'') are I, H. W. Ellis, R. Y. Pai, E. W. McDonald, E. A. Mason, and L. A. Viehland, ATOMIC DATA AND NUCLEAR DATA TABLES 17, 177--210 (19876); and II, H. W. Ellis, E. W. McDaniel, D. L. Albritton, L. A. Veihland, S. L. Lin, and E. A. Mason, ATOMIC DATA AND NUCLEAR DATA TABLES 22, 179--217 (1978). Parts I and II contained compilations of experimental data on ionic mobilities and diffusion coefficients (both longitudinal and transverse) for ions in neutral gase (almost exclusively at room temperature) in an externally applied electric field

  4. Theoretical analysis of nuclear reactors (Phase III), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (III faza) I-IV, III Deo, Zatrovanje reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    Report on calculation of poisoning in experimental and power reactor includes four parts. Part one describes the influence of poisoning on the physical parameters of a reactor. part two includes transformation of differential equations for iodine and xenon. It was needed for easier solution of of differential equation using the analog computer. This calculation was done for RA reactor operating at 5 MW power. The RA reactor was used an example of calculation by the proposed method. Part four shows the application of the method for calculating the Calder Hall power reactor.

  5. The energy balance experiment EBEX-2000. Part III: Behaviour and quality of the radiation measurements

    NARCIS (Netherlands)

    Kohsiek, W.; Liebethal, C.; Foken, T.; Vogt, R.; Oncley, S.P.; Bernhofer, C.; Debruin, H.A.R.

    2007-01-01

    An important part of the Energy Balance Experiment (EBEX-2000) was the measurement of the net radiation and its components. Since the terrain, an irrigated cotton field, could not be considered homogeneous, radiation measurements were made at nine sites using a variety of radiation instruments,

  6. Broadcasting Stations of the World; Part III. Frequency Modulation Broadcasting Stations.

    Science.gov (United States)

    Foreign Broadcast Information Service, Washington, DC.

    This third part of "Broadcasting Stations of the World", which lists all reported radio broadcasting and television stations, with the exception of those in the United States which broadcast on domestic channels, covers frequency modulation broadcasting stations. It contains two sections: one indexed alphabetically by country and city, and the…

  7. CBIOS Science Sessions - 2016 - Part I and III National Symposium on Nanoscience and Biomedical Nanotechnology - Proceedings

    Directory of Open Access Journals (Sweden)

    L. Monteiro Rodrigues, et al.

    2016-05-01

    Full Text Available CBiOS Science Sessions - 2016 – Part 1 New methods to explore efficacy and safety of natural origin products; Stefânia Duz Delsin Effectiveness of Hypopressive Exercises in women with pelvic floor dysfunctions; Beatriz Navarro Brazález Indoor air quality in baby rooms: a study about VOC levels; Raquel Rodrigues dos Santos, Ana Sofia Fernandes e Liliana Mendes A medicinal chemistry approach for the development of novel anti-tumor agentes; Maria M. M. Santos Isolation, modelling and phytosome forms of antibacterial and anti-proliferative compounds from Plectranthus spp; Diogo Matias Intellectual Property – Patenting Propriedade Intelectual – Patenteamento Rui Gomes Biomarkers in wastewater; Álvaro Lopes A Contribution for a Better Comprehension of Donkey Dentistry: the Importance of Dental Care; João Brandão Rodrigues Characterization of Lusitano’s Pure Blood Pressure Centers using two pressure plates; Pequito M.; Gomes-Costa M.; Prazeres J.; Bragança M.; Roupa I.; Fonseca R.G.; Abrantes J. Application of photoplethysmography to monitor heart rate in dogs; Rui Assunção, Henrique Silva, João Requicha, Luis Lobo, Luis Monteiro Rodrigues Looking into the oscillatory properties of the laser Doppler flowmetry signal in human microcirculation; Henrique Silva, Hugo Ferreira, Marie-Ange Renault, Alain-Pierre Gadeau, Julia Buján, LM Rodrigues III Symposium of Nanoscience and Biomedical Nanotechnology – Proceedings April 15/04/2016 Lisboa - Universidade Lusófona Honor Commitee /Comissão de Honra Magnífico Reitor da Universidade Lusófona, Mário Moutinho Presidente do Conselho de Administração da Universidade Lusófona, Manuel de Almeida Damásio Sr. Bastonário da Ordem dos Engenheiros, Carlos Matias Ramos Sr. Bastonário da Ordem dos Médicos, José Silva Vice-presidente do Conselho de Enfermagem, Maria José Costa Dias Presidente da Associação Nacional de Farmácias, Paulo Cleto Duarte Presidente da Sociedade Portuguesa de Ci

  8. LHC Beam Dump Design Study - Part III : Off-normal operating conditions

    CERN Document Server

    Bruno, L; Ross, M; Sala, P

    2000-01-01

    The LHC beam dump design study has been preliminarily substantiated by energy deposition simulations (Part I) and heat transfer analyses (Part II). The present report is devoted to the abnormal operating conditions induced by a malfunction of the beam diluters. A general approach to the analysis of off-normal operation is presented, which is derived from standard design norms adopted in the nuclear industry. Attention is focused mainly on the carbon core, which is longitudinally split into segments of different density in order to better distribute the deposited energy. The maximum energy density it absorbs decreases by at least 33%, compared to a uniform standard density carbon core. This structure may sustain any partial sweep failure without major damage, up to the ultimate beam intensity and energy. To minimise the risks inherent in a fully unswept beam, a sacrificial graphite mandrel will be placed on the core axis, surrounded by a thick high strength carbon-carbon composite tube. With this arrangement, ...

  9. Normal and sonographic anatomy of selected peripheral nerves. Part III: Peripheral nerves of the lower limb.

    Science.gov (United States)

    Kowalska, Berta; Sudoł-Szopińska, Iwona

    2012-06-01

    The ultrasonographic examination is currently increasingly used in imaging peripheral nerves, serving to supplement the physical examination, electromyography and magnetic resonance imaging. As in the case of other USG imaging studies, the examination of peripheral nerves is non-invasive and well-tolerated by patients. The typical ultrasonographic picture of peripheral nerves as well as the examination technique have been discussed in part I of this article series, following the example of the median nerve. Part II of the series presented the normal anatomy and the technique for examining the peripheral nerves of the upper limb. This part of the article series focuses on the anatomy and technique for examining twelve normal peripheral nerves of the lower extremity: the iliohypogastric and ilioinguinal nerves, the lateral cutaneous nerve of the thigh, the pudendal, sciatic, tibial, sural, medial plantar, lateral plantar, common peroneal, deep peroneal and superficial peroneal nerves. It includes diagrams showing the proper positioning of the sonographic probe, plus USG images of the successively discussed nerves and their surrounding structures. The ultrasonographic appearance of the peripheral nerves in the lower limb is identical to the nerves in the upper limb. However, when imaging the lower extremity, convex probes are more often utilized, to capture deeply-seated nerves. The examination technique, similarly to that used in visualizing the nerves of upper extremity, consists of locating the nerve at a characteristic anatomic reference point and tracking it using the "elevator technique". All 3 parts of the article series should serve as an introduction to a discussion of peripheral nerve pathologies, which will be presented in subsequent issues of the "Journal of Ultrasonography".

  10. Burnout in boiling heat transfer. Part III. High-quality forced-convection systems

    International Nuclear Information System (INIS)

    Bergles, A.E.

    1979-01-01

    This is the final part of a review of burnout during boiling heat transfer. The status of burnout in high-quality forced-convection systems is reviewed, and recent developments are summarized in detail. A general guide to the considerable literature is given. Parametric effects and correlations for water in circular and noncircular ducts are presented. Other topics discussed include transients, steam-generator applications, correlations for other fluids, fouling, and augmentation

  11. PIO I-II tendencies case study. Part 1. Mathematical modeling

    Directory of Open Access Journals (Sweden)

    Adrian TOADER

    2010-03-01

    Full Text Available In the paper, a study is performed from the perspective of giving a method to reduce the conservatism of the well known PIO (Pilot-Induced Oscillation criteria in predicting the susceptibility of an aircraft to this very harmful phenomenon. There are three interacting components of a PIO – the pilot, the vehicle, and the trigger (in fact, the hazard. The study, conceived in two parts, aims to underline the importance of human pilot model involved in analysis. In this first part, it is shown, following classical sources, how the LQG theory of control and estimation is used to obtain a complex model of human pilot. The approach is based on the argument, experimentally proved, that the human behaves “optimally” in some sense, subject to his inherent psychophysical limitations. The validation of such model is accomplished based on the experimental model of a VTOL-type aircraft. Then, the procedure of inserting typical saturation nonlinearities in the open loop transfer function is presented. A second part of the paper will illustrate PIO tendencies evaluation by means of a grapho-analytic method.

  12. Low-level radioactive waste from commercial nuclear reactors. Volume 3. Bibliographic abstracts of significant source references. Part 2. Bibliography for treatment, storage, disposal and transportation regulatory constraints

    Energy Technology Data Exchange (ETDEWEB)

    Jolley, R.L.; Rodgers, B.R.

    1986-05-01

    The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 3 of this series is a collection of abstracts of most of the reference documents used for this study. Because of the large volume of literature, the abstracts have been printed in two separate parts. Federal, state, and local regulations affect the decision process for selecting technology applications. Regulations may favor a particular technology and may prevent application of others. Volume 3, part 2 presents abstracts of the regulatory constraint documents that relate to all phases of LLRW management (e.g., treatment, packaging, storage, transportation, and disposal).

  13. The Characteristics on the Terrace and Uplift around the South-eastern part of Korean Peninsula for a Suitability of High level Radioactive Waste Disposal in Korea

    International Nuclear Information System (INIS)

    Koh, Yong Kwon; Bae, Dae Seok; Kim, Kyung Su; Kim, Geon Young; Park, Kyung Woo; Ji, Sung Hoon; Ryu, Ji Hoon

    2009-08-01

    The result of existing studies on the uplift in Korean peninsula would be regarded as high variety and rough uplifting range because of different approach method and various geologic formation with some location. As the results of this studies, the uplift around the southern part of Korean peninsula was estimated as the range from 0.0096mm to 1.4mm/year according to a geologic formation and location. It could be For the applying to HLW disposal project, the study on the uplift characteristics should be conducted according to the following guidelines: - should be a master program for the characterization of uplift in Korean peninsula considering long-term and systematic - should be applied scientific and quantitative approach methods and made subjective results - should be required an effective approach focused on limited area such as eastern, southern and western part of peninsula

  14. Building Worlds and Learning Astronomy on Facebook Part III: Testing, Launch, and Evaluation

    Science.gov (United States)

    Harold, J.; Hines, D.; Vidugiris, E.; Goldman, K. H.

    2015-11-01

    James Harold (SSI), Dean Hines (STScI/SSI) and a team at the National Center for Interactive Learning at the Space Science Institute are developing Starchitect, an end-to-end stellar and planetary evolution game for the Facebook platform. Supported by NSF and NASA, and based in part on a prototype presented at ASP several years ago, Starchitect uses the “sporadic play” model of games such as Farmville, where players might only take actions a few times a day, but may continue playing for months. This paper is an update to a presentation at last year's ASP conference.

  15. National Energy Board 1992-93 estimates part III expenditure plan

    International Nuclear Information System (INIS)

    1992-01-01

    This Expenditure Plan is designed to be used as a reference document. As such, it contains several levels of detail to respond to the various needs of its audience. This Plan is divided into two sections. Section 1 presents an overview of the Program including a description, information on its background, objectives and planning perspective as well as performance information that forms the basis for the resources requested. Section 2 provides further information on costs and resources as well as special analyses that the reader may require to understand the Program more fully. Section 1 is preceded by details of Spending Authorities from Part 2 of the Estimates and Volume 2 of the Public Accounts. This is to provide continuity with other Estimates documents and to help in assessing the Program's financial performance over the past year. The format and organization of the document should be regarded as transitional. For the most part the document is organized to be consistent with the program structure approved for the National Energy Board. 16 figs

  16. National Energy Board 1992-93 estimates part III expenditure plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-31

    This Expenditure Plan is designed to be used as a reference document. As such, it contains several levels of detail to respond to the various needs of its audience. This Plan is divided into two sections. Section 1 presents an overview of the Program including a description, information on its background, objectives and planning perspective as well as performance information that forms the basis for the resources requested. Section 2 provides further information on costs and resources as well as special analyses that the reader may require to understand the Program more fully. Section 1 is preceded by details of Spending Authorities from Part 2 of the Estimates and Volume 2 of the Public Accounts. This is to provide continuity with other Estimates documents and to help in assessing the Program`s financial performance over the past year. The format and organization of the document should be regarded as transitional. For the most part the document is organized to be consistent with the program structure approved for the National Energy Board. 16 figs.

  17. Two-loop renormalization in the standard model, part III. Renormalization equations and their solutions

    International Nuclear Information System (INIS)

    Actis, S.; Passarino, G.

    2006-12-01

    In part I and II of this series of papers all elements have been introduced to extend, to two loops, the set of renormalization procedures which are needed in describing the properties of a spontaneously broken gauge theory. In this paper, the final step is undertaken and finite renormalization is discussed. Two-loop renormalization equations are introduced and their solutions discussed within the context of the minimal standard model of fundamental interactions. These equations relate renormalized Lagrangian parameters (couplings and masses) to some input parameter set containing physical (pseudo-)observables. Complex poles for unstable gauge and Higgs bosons are used and a consistent setup is constructed for extending the predictivity of the theory from the Lep1 Z-boson scale (or the Lep2 WW scale) to regions of interest for LHC and ILC physics. (orig.)

  18. Two-loop renormalization in the standard model, part III. Renormalization equations and their solutions

    Energy Technology Data Exchange (ETDEWEB)

    Actis, S. [Deutsches Elektronen-Synchrotron (DESY), Zeuthen (Germany); Passarino, G. [Torino Univ. (Italy). Dipt. di Fisica Teorica; INFN, Sezione di Torino (Italy)

    2006-12-15

    In part I and II of this series of papers all elements have been introduced to extend, to two loops, the set of renormalization procedures which are needed in describing the properties of a spontaneously broken gauge theory. In this paper, the final step is undertaken and finite renormalization is discussed. Two-loop renormalization equations are introduced and their solutions discussed within the context of the minimal standard model of fundamental interactions. These equations relate renormalized Lagrangian parameters (couplings and masses) to some input parameter set containing physical (pseudo-)observables. Complex poles for unstable gauge and Higgs bosons are used and a consistent setup is constructed for extending the predictivity of the theory from the Lep1 Z-boson scale (or the Lep2 WW scale) to regions of interest for LHC and ILC physics. (orig.)

  19. Study of irradiated bone: Part III. /sup 99m/Tc pyrophosphate autoradiographic changes

    International Nuclear Information System (INIS)

    King, M.A.; Corriveau, O.; Casarett, G.W.; Weber, D.A.

    1978-01-01

    The macroautoradiographic and microautoradiographic localization of /sup 99m/Tc-pyrophosphate (/sup 99m/TcPPi) was studied in x-irradiated bone of rabbits up to one year post-irradiation. In cortical bone, /sup 99m/TcPPi was concentrated on bone surfaces near vasculature. Both forming and resorbing bone surfaces were comparably labeled at 2 hrs post-injection. Uptake on the surface of sites of haversian bone remodeling was observed to be at least part of the increased /sup 99m/TcPPi observed in irradiated bone in camera images. In irradiated trabecular bone 12 months following irradiation, a patchy decrease in /sup 99m/TcPPi uptake was correlated with localized decreases in vasculature

  20. Atomic Energy Control Board 1991-92 estimates part III expenditure plan

    International Nuclear Information System (INIS)

    1991-01-01

    This Expenditure Plan is designed to be used as a reference document. As such, it contains several levels of detail to respond to the various needs of its audience. This Plan is divided into two sections. Section 1 presents an overview of the Program including a description, information on its background, objectives and planning perspective as well as performance information that forms the basis for the resources requested. Section 2 provides further information on costs and resources as well as special analyses that the reader may require to understand the Program more fully. Section 1 is preceded by details of Spending Authorities from Part 2 of the Estimates and Volume 2 of the Public Accounts. This is to provide continuity with other Estimates documents and to help in assessing the Program's financial performance over the past year. 22 figs

  1. Atomic Energy Control Board 1991-92 estimates part III expenditure plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-31

    This Expenditure Plan is designed to be used as a reference document. As such, it contains several levels of detail to respond to the various needs of its audience. This Plan is divided into two sections. Section 1 presents an overview of the Program including a description, information on its background, objectives and planning perspective as well as performance information that forms the basis for the resources requested. Section 2 provides further information on costs and resources as well as special analyses that the reader may require to understand the Program more fully. Section 1 is preceded by details of Spending Authorities from Part 2 of the Estimates and Volume 2 of the Public Accounts. This is to provide continuity with other Estimates documents and to help in assessing the Program`s financial performance over the past year. 22 figs.

  2. Atomic Energy Control Board 1992-93 estimates part III expenditure plan

    International Nuclear Information System (INIS)

    1992-01-01

    This Expenditure Plan is designed to be used as a reference document. As such, it contains several levels of detail to respond to the various needs of its audience. This Plan is divided into two sections. Section 1 presents an overview of the Program including a description, information on its background, objectives and planning perspective as well as performance information that forms the basis for the resources requested. Section 2 provides further information on costs and resources as well as special analyses that the reader may require to understand the Program more fully. Section 1 is preceded by details of Spending Authorities from Part 2 of the Estimates and Volume 2 of the Public Accounts. This is to provide continuity with other Estimates documents and to help in assessing the Program's financial performance over the past year. 7 refs., 21 figs

  3. Atomic Energy Control Board 1992-93 estimates part III expenditure plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-31

    This Expenditure Plan is designed to be used as a reference document. As such, it contains several levels of detail to respond to the various needs of its audience. This Plan is divided into two sections. Section 1 presents an overview of the Program including a description, information on its background, objectives and planning perspective as well as performance information that forms the basis for the resources requested. Section 2 provides further information on costs and resources as well as special analyses that the reader may require to understand the Program more fully. Section 1 is preceded by details of Spending Authorities from Part 2 of the Estimates and Volume 2 of the Public Accounts. This is to provide continuity with other Estimates documents and to help in assessing the Program`s financial performance over the past year. 7 refs., 21 figs.

  4. Notes on the Birds of Central Oaxaca, Part III: Hirundinidae to Fringillidae

    Directory of Open Access Journals (Sweden)

    John M. Forcey

    2015-06-01

    Full Text Available Notas sobre las aves de Oaxaca central, parte II: Hirundinidae a Fringillidae Se reportan nuevos datos que amplían y clarifican nuestro conocimiento del estatus y distribución de 112 especies de aves en la región central del Estado de Oaxaca. Las observaciones se realizaron abarcando partes de los distritos de Centro, Etla, Ixtlan, Tlacolula, y Zaachila dentro de 35 km alrededor de la Ciudad de Oaxaca. El reporte se basa en observaciones tomadas durante 752 días, comprendidos entre diciembre 1996 y mayo 2002. Los principales hábitats del área son de pino-encino (incluyendo zonas pequeñas de pino-encino-oyamel y pino-encino mezclado con pastizales, matorral de encino, matorral subtropical, vegetación riparia, y vegetación secundaria, campos agrícolas y otros (incluyendo áreas urbanas, jardines, y parques. Las siguientes especies se reportan por primera vez en la zona: Progne sinaloae (registro nuevo en el estado de Oaxaca, Thryothorus felix, Hylocichla mustelina, Vermivora pinus, Vermivora chrysoptera, Dendroica pensylvanica, Dendroica magnolia, Dendroica fusca, Dendroica graciae, Oporornis philadelphia, Wilsonia canadensis, y Spiza americana.Además, las siguientes nueve especies se han reportado solamente en los Conteos Navideños o por registros únicos: Tachycineta bicolor, Dumetella carolinensis, Vermivora peregrina, Dendroica dominica, Dendroica discolor, y Piranga erythrocephala (en temporada de reproducción. Se reportan datos de la reproducción de 43 especies, 18 de los cuales no se habían registrado en estado reproductivo antes en esta zona. De estos 43, 39 se pueden agrupar como reproduciéndose en los meses de abril a julio.

  5. Siting a municipal solid waste disposal facility, part II: the effects of external criteria on the final decision.

    Science.gov (United States)

    Korucu, M Kemal; Karademir, Aykan

    2014-02-01

    The procedure of a multi-criteria decision analysis supported by the geographic information systems was applied to the site selection process of a planning municipal solid waste management practice based on twelve different scenarios. The scenarios included two different decision tree modes and two different weighting models for three different area requirements. The suitability rankings of the suitable sites obtained from the application of the decision procedure for the scenarios were assessed by a factorial experimental design concerning the effect of some external criteria on the final decision of the site selection process. The external criteria used in the factorial experimental design were defined as "Risk perception and approval of stakeholders" and "Visibility". The effects of the presence of these criteria in the decision trees were evaluated in detail. For a quantitative expression of the differentiations observed in the suitability rankings, the ranking data were subjected to ANOVA test after a normalization process. Then the results of these tests were evaluated by Tukey test to measure the effects of external criteria on the final decision. The results of Tukey tests indicated that the involvement of the external criteria into the decision trees produced statistically meaningful differentiations in the suitability rankings. Since the external criteria could cause considerable external costs during the operation of the disposal facilities, the presence of these criteria in the decision tree in addition to the other criteria related to environmental and legislative requisites could prevent subsequent external costs in the first place.

  6. Circuit modeling of the electrical impedance: part III. Disuse following bone fracture

    International Nuclear Information System (INIS)

    Shiffman, C A

    2013-01-01

    Multifrequency measurements of the electrical impedance of muscle have been extended to the study of disuse following bone fracture, and analyzed using the five-element circuit model used earlier in the study of the effects of disease. Eighteen subjects recovering from simple fractures on upper or lower limbs were examined (ten males, eight females, aged 18–66). Muscles on uninjured contralateral limbs were used as comparison standards, and results are presented in terms of the ratios p(injured)/p(uninjured), where p stands for the circuit parameter r 1 , r 2 , r 3 , 1/c 1 or 1/c 2 . These are strikingly similar to the diseased-to-healthy ratios for patients with neuromuscular disease, reported in part I of this series. In particular, r 1 is virtually unaffected and the ratios for r 2 , r 3 , 1/c 1 and 1/c 2 can be as large as in serious disease. Furthermore, the same pattern of relationships between the parameters is found, suggesting that there is a common underlying mechanism for the impedance changes. Atrophy and fibrosis are examined as candidates for that mechanism, but it is argued that their effects are too small to explain the observed changes. Fundamental considerations aside, the sensitivity, reproducibility and technical simplicity of the technique recommend its use for in-flight assessments of muscles during orbital or interplanetary missions. (paper)

  7. The Systemic Theory of Living Systems and Relevance to CAM: the Theory (Part III

    Directory of Open Access Journals (Sweden)

    José A. Olalde Rangel

    2005-01-01

    Full Text Available Western medical science lacks a solid philosophical and theoretical approach to disease cognition and therapeutics. My first two articles provided a framework for a humane medicine based on Modern Biophysics. Its precepts encompass modern therapeutics and CAM. Modern Biophysics and its concepts are presently missing in medicine, whether orthodox or CAM, albeit they probably provide the long sought explanation that bridges the abyss between East and West. Key points that differentiate Systemic from other systems' approaches are ‘Intelligence’, ‘Energy’ and the objective ‘to survive’. The General System Theory (GST took a forward step by proposing a departure from the mechanistic biological concept—of analyzing parts and processes in isolation—and brought us towards an organismic model. GST examines the system's components and results of their interaction. However, GST still does not go far enough. GST assumes ‘Self-Organization’ as a spontaneous phenomenon, ignoring a causative entity or central controller to all systems: Intelligence. It also neglects ‘Survive’ as the directional motivation common to any living system, and scarcely assigns ‘Energy’ its true inherent value. These three parameters, Intelligence, Energy and Survive, are vital variables to be considered, in our human quest, if we are to achieve a unified theory of life.

  8. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume III of V

    International Nuclear Information System (INIS)

    1997-01-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type

  9. Dispersion of a Passive Scalar Fluctuating Plume in a Turbulent Boundary Layer. Part III: Stochastic Modelling

    Science.gov (United States)

    Marro, Massimo; Salizzoni, Pietro; Soulhac, Lionel; Cassiani, Massimo

    2018-01-01

    We analyze the reliability of the Lagrangian stochastic micromixing method in predicting higher-order statistics of the passive scalar concentration induced by an elevated source (of varying diameter) placed in a turbulent boundary layer. To that purpose we analyze two different modelling approaches by testing their results against the wind-tunnel measurements discussed in Part I (Nironi et al., Boundary-Layer Meteorology, 2015, Vol. 156, 415-446). The first is a probability density function (PDF) micromixing model that simulates the effects of the molecular diffusivity on the concentration fluctuations by taking into account the background particles. The second is a new model, named VPΓ, conceived in order to minimize the computational costs. This is based on the volumetric particle approach providing estimates of the first two concentration moments with no need for the simulation of the background particles. In this second approach, higher-order moments are computed based on the estimates of these two moments and under the assumption that the concentration PDF is a Gamma distribution. The comparisons concern the spatial distribution of the first four moments of the concentration and the evolution of the PDF along the plume centreline. The novelty of this work is twofold: (i) we perform a systematic comparison of the results of micro-mixing Lagrangian models against experiments providing profiles of the first four moments of the concentration within an inhomogeneous and anisotropic turbulent flow, and (ii) we show the reliability of the VPΓ model as an operational tool for the prediction of the PDF of the concentration.

  10. Dispersion of a Passive Scalar Fluctuating Plume in a Turbulent Boundary Layer. Part III: Stochastic Modelling

    Science.gov (United States)

    Marro, Massimo; Salizzoni, Pietro; Soulhac, Lionel; Cassiani, Massimo

    2018-06-01

    We analyze the reliability of the Lagrangian stochastic micromixing method in predicting higher-order statistics of the passive scalar concentration induced by an elevated source (of varying diameter) placed in a turbulent boundary layer. To that purpose we analyze two different modelling approaches by testing their results against the wind-tunnel measurements discussed in Part I (Nironi et al., Boundary-Layer Meteorology, 2015, Vol. 156, 415-446). The first is a probability density function (PDF) micromixing model that simulates the effects of the molecular diffusivity on the concentration fluctuations by taking into account the background particles. The second is a new model, named VPΓ, conceived in order to minimize the computational costs. This is based on the volumetric particle approach providing estimates of the first two concentration moments with no need for the simulation of the background particles. In this second approach, higher-order moments are computed based on the estimates of these two moments and under the assumption that the concentration PDF is a Gamma distribution. The comparisons concern the spatial distribution of the first four moments of the concentration and the evolution of the PDF along the plume centreline. The novelty of this work is twofold: (i) we perform a systematic comparison of the results of micro-mixing Lagrangian models against experiments providing profiles of the first four moments of the concentration within an inhomogeneous and anisotropic turbulent flow, and (ii) we show the reliability of the VPΓ model as an operational tool for the prediction of the PDF of the concentration.

  11. A Study of Future Communications Concepts and Technologies for the National Airspace System-Part III

    Science.gov (United States)

    Ponchak, Denise S.; Apaza, Rafael D.; Wichgersm Joel M.; Haynes, Brian; Roy, Aloke

    2014-01-01

    The National Aeronautics and Space Administration (NASA) Glenn Research Center (GRC) is investigating current and anticipated wireless communications concepts and technologies that the National Airspace System (NAS) may need in the next 50 years. NASA has awarded three NASA Research Announcements (NAR) studies with the objective to determine the most promising candidate technologies for air-to-air and air-to-ground data exchange and analyze their suitability in a post-NextGen NAS environment. This paper will present progress made in the studies and describe the communications challenges and opportunities that have been identified as part of the study. NASA's NextGen Concepts and Technology Development (CTD) Project integrates solutions for a safe, efficient and high-capacity airspace system through joint research efforts and partnerships with other government agencies. The CTD Project is one of two within NASA's Airspace Systems Program and is managed by the NASA Ames Research Center. Research within the CTD Project is in support the 2011 NASA Strategic Plan Sub-Goal 4.1: Develop innovative solutions and advanced technologies, through a balanced research portfolio, to improve current and future air transportation. The focus of CTD is on developing capabilities in traffic flow management, dynamic airspace configuration, separation assurance, super density operations and airport surface operations. Important to its research is the development of human/automation information requirements and decisionmaking guidelines for human-human and human-machine airportal decision-making. Airborne separation, oceanic intrail climb/descent and interval management applications depend on location and intent information of surrounding aircraft. ADS-B has been proposed to provide the information exchange, but other candidates such as satellite-based receivers, broadband or airborne internet, and cellular communications are possible candidate's.

  12. Ultrasound assessment of selected peripheral nerve pathologies. Part III: Injuries and postoperative evaluation

    Directory of Open Access Journals (Sweden)

    Berta Kowalska

    2013-03-01

    Full Text Available The previous articles of the series devoted to ultrasound diagnostics of peripheral nerves concerned the most common nerve pathologies, i.e. entrapment neuropathies. The aim of the last part of the series is to present ultrasound possibilities in the postoperative control of the peripheral nerves as well as in the diagnostics of the second most common neuropathies of peripheral nerves, i.e. posttraumatic lesions. Early diagnostics of posttraumatic changes is of fundamental importance for the course of treatment and its long-term effects. It aids surgeons in making treatment decisions (whether surgical or conservative. When surgical treatment is necessary, the surgeon, based on US findings, is able to plan a given type of operative method. In certain cases, may even abandon the corrective or reconstructive surgery of the nerve trunk (when there are extensive defects of the nerve trunks and instead, proceed with muscle transfers. Medical literature proposes a range of divisions of the kinds of peripheral nerve injuries depending on, among others, the mechanism or degree of damage. However, the most important issue in the surgeon-diagnostician communication is a detailed description of stumps of the nerve trunks, their distance and location. In the postoperative period, ultrasound is used for monitoring the operative or conservative treatment effects including the determination of the causes of a persistent or recurrent neuropathy. It facilitates decision-making concerning a repeated surgical procedure or assuming a wait-and-see attitude. It is a difficult task for a diagnostician and it requires experience, close cooperation with a clinician and knowledge concerning surgical techniques. Apart from a static assessment, a dynamic assessment of possible adhesions constitutes a crucial element of postoperative examination. This feature distinguishes ultrasound scanning from other methods used in the diagnostics of peripheral neuropathies.

  13. Cosmic disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Inoue, Y; Morisawa, S [Kyoto Univ. (Japan). Faculty of Engineering

    1975-03-01

    The technical and economical possibility and safety of the disposal of highly radioactive waste into cosmos are reviewed. The disposal of highly radioactive waste is serious problem to be solved in the near future, because it is produced in large amounts by the reprocessing of spent fuel. The promising methods proposed are (i) underground disposal, (ii) ocean disposal, (iii) cosmic disposal and (iv) extinguishing disposal. The final disposal method is not yet decided internationally. The radioactive waste contains very long life nuclides, for example transuranic elements and actinide elements. The author thinks the most perfect and safe disposal method for these very long life nuclides is the disposal into cosmos. The space vehicle carrying radioactive waste will be launched safely into outer space with recent space technology. The selection of orbit for vehicles (earth satellite or orbit around planets) or escape from solar system, selection of launching rocket type pretreatment of waste, launching weight, and the cost of cosmic disposal were investigated roughly and quantitatively. Safety problem of cosmic disposal should be examined from the reliable safety study data in the future.

  14. PACE. A Program for Acquiring Competence in Entrepreneurship. Part III: Being an Entrepreneur. Unit F: Managing Human Resources. Research and Development Series No. 194 C-6.

    Science.gov (United States)

    Ohio State Univ., Columbus. National Center for Research in Vocational Education.

    This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-level colleges and adult education, but it can be adapted for special groups or vocational teacher education. The emphasis of the eight instructional units in Part III is operating a business. Unit F focuses on proper management of human…

  15. PACE. A Program for Acquiring Competence in Entrepreneurship. Part III: Being an Entrepreneur. Unit A: Managing the Business. Research and Development Series No. 194 C-1.

    Science.gov (United States)

    Ohio State Univ., Columbus. National Center for Research in Vocational Education.

    This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-year colleges and adult education, but it can be adapted for special groups or vocational teacher education. The emphasis of the eight instructional units in Part III is operating a business. Unit A focuses on the management process. It…

  16. PACE. A Program for Acquiring Competence in Entrepreneurship. Part III: Being an Entrepreneur. Unit B: Financial Management. Research and Development Series No. 194 C-2.

    Science.gov (United States)

    Ohio State Univ., Columbus. National Center for Research in Vocational Education.

    This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-year colleges and adult education, but it can be adapted for special groups or vocational teacher education. The emphasis of the eight instructional units in Part III is operating a business. Unit B focuses on good financial management…

  17. PACE. A Program for Acquiring Competence in Entrepreneurship. Part III: Being an Entrepreneur. Unit H: Business Protection. Research and Development Series No. 194 C-8.

    Science.gov (United States)

    Ohio State Univ., Columbus. National Center for Research in Vocational Education.

    This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-year colleges and adult education, but it can be adapted for special groups or vocational teacher education. The emphasis of the eight instructional units in part III is operating a business. Unit H focuses on business protection. It…

  18. PACE. A Program for Acquiring Competence in Entrepreneurship. Part III: Being an Entrepreneur. Unit G: Community Relations. Research and Development Series No. 194 C-7.

    Science.gov (United States)

    Ohio State Univ., Columbus. National Center for Research in Vocational Education.

    This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-year colleges and adult education, but it can be adapted for special groups of vocational teacher education. The emphasis of the eight instructional units in Part III is operating a business. Unit G focuses on community relations. It…

  19. PACE. A Program for Acquiring Competence in Entrepreneurship. Part III: Being an Entrepreneur. Unit E: Successful Selling. Research and Development Series No. 194 C-5.

    Science.gov (United States)

    Ohio State Univ., Columbus. National Center for Research in Vocational Education.

    This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-year colleges and adult education, but it can be adapted for special groups or vocational teacher education. The emphasis of the eight instructional units in Part III is operating a business. Unit E focuses on personal (face-to-face)…

  20. PACE. A Program for Acquiring Competence in Entrepreneurship. Part III: Being an Entrepreneur. Unit D: Marketing Management. Research and Development Series No. 194 C-4.

    Science.gov (United States)

    Ohio State Univ., Columbus. National Center for Research in Vocational Education.

    This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-year colleges and adult education, but it can be adapted for special groups or vocational teacher education. The emphasis of the eight instructional units in Part III is operating a business. Unit D focuses on market management. It…

  1. Electronics and telecommunications in Poland, issues and perspectives: Part III. Innovativeness, applications, economy, development scenarios, politics

    Science.gov (United States)

    Modelski, Józef; Romaniuk, Ryszard

    2010-09-01

    important role of ET is combined with the existence in the society of an adequate infrastructure which recreates the full development cycle of high technology embracing: people, institutions, finances and logistics, in this also science, higher education, education, continuous training, dissemination and outreach, professional social environment, legal basis, political support and lobbying, innovation structures, applications, industry and economy. The digest of chosen development tendencies in ET was made here from the academic perspective, in a wider scale and on this background the national one, trying to situate this branch in the society, determine its changing role to build a new technical infrastructure of a society based on knowledge, a role of builder of many practical gadgets facilitating life, a role of a big future integrator of today's single bricks into certain more useful unity. This digest does not have a character of a systematic analysis of ET. It is a kind of an arbitrary utterance of the authors inside their field of competence. The aim of this paper is to take an active part in the discussion of the academic community in this country on the development strategy of ET, choice of priorities for cyclically rebuilding economy, in competitive environments. The review paper was initiated by the Committee of Electronics and Telecommunications of Polish Academy of Sciences and was published in Polish as introductory chapter of a dedicated expertise, printed in a book format. This version makes the included opinions available for a wider community.

  2. Confirmation tests of construction method and initial performance quality for low permeable engineered barrier in side part of radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Yamada, Atsuo; Chijimatsu, Masakazu; Akiyama, Yoshihiro; Komine, Hideo; Iizuka, Atsushi

    2016-01-01

    As for the low permeable layer, important functions are expected as an engineered barrier of radioactive waste disposal for low-level waste with comparatively high radiation levels. On examining the construction methods of this low permeable layer, it is important to confirm the possibility of the construction in the conditions similar to the actual constructed conditions with a true scale size. Therefore, the construction examination for the side part of the low permeable layer by bentonite and the performance check test of the low permeable layer were carried out. The result of the construction examination showed that the possibility of the construction were confirmed, and the result of performance check test showed that it was possible to ensure the required performance of the low permeable layer, such as hydraulic conductivity. (author)

  3. Staff analysis of public comments on proposed rule 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories

    International Nuclear Information System (INIS)

    1983-12-01

    On February 25, 1981, the Nuclear Regulatory Commission published rules which establish procedures for the licensing of geologic disposal, by the US Department of Energy, of high-level radioactive wastes. On July 8, 1981, proposed technical criteria which would be used in the evaluation of license applications under those procedural rules were published in the Federal Register. The Commission received 93 comment letters on the proposed technical criteria, 89 of which were received in time for the Commission to consider in preparing the final technical criteria which were published on June 21, 1983. This document presents a detailed analysis of the comments received on the proposed rule by the Commission's staff and also contains the Rationale for the Performance Objectives of 10 CFR Part 60

  4. Disposal safety

    International Nuclear Information System (INIS)

    Bartlett, J.W.

    International consensus does not seem to be necessary or appropriate for many of the issues concerned with the safety of nuclear waste disposal. International interaction on the technical aspects of disposal has been extensive, and this interaction has contributed greatly to development of a consensus technical infrastructure for disposal. This infrastructure provides a common and firm base for regulatory, political, and social actions in each nation

  5. Waste disposal

    International Nuclear Information System (INIS)

    Neerdael, B.; Marivoet, J.; Put, M.; Verstricht, J.; Van Iseghem, P.; Buyens, M.

    1998-01-01

    The primary mission of the Waste Disposal programme at the Belgian Nuclear Research Centre SCK/CEN is to propose, develop, and assess solutions for the safe disposal of radioactive waste. In Belgium, deep geological burial in clay is the primary option for the disposal of High-Level Waste and spent nuclear fuel. The main achievements during 1997 in the following domains are described: performance assessment, characterization of the geosphere, characterization of the waste, migration processes, underground infrastructure

  6. Review of models for use in probabilistic assessments of the disposal of high level radioactive wastes on or beneath the seabed: appendix III

    International Nuclear Information System (INIS)

    Hooper, A.G.; Gibson, A.E.

    1985-08-01

    MARINRAD (MARINe RADionuclide Transport and Dose) is a system of computer programs designed to evaluate the consequences from release of radioactive waste into the ocean. It is presently being used in safety assessment studies for the Subseabed Disposal Program by Sandia National Laboratories. MARINRAD calculates doses to humans and biota and health effects to humans. The MARINRAD software system is composed of three computer programs: ORIGEN, MARRAD and MAROUT. The use of the ORIGEN program to generate a nuclide inventory file is optional. The MARRAD program incorporates an ocean transport box model that calculates radionuclide concentrations as a function of time, and a steady-state food-chain model that calculates the biota concentration factors. Program MAROUT evaluates a pathways-to-man model which is used to calculate dose and health effects to man for up to seven different exposure pathways. (author)

  7. Series of selenoid valve pneumatic AC 220 volts with disposable contra angle as a replacement for micromotor in preclinic laboratory (experimental study on the health ministry of health polytechnic course D-III department of dental nursing Tasikmalaya

    Directory of Open Access Journals (Sweden)

    Hadiyat Miko

    2016-06-01

    Full Text Available To report on the essential performance characteristics of disposable air turbine handpiece and on aspect of their convenience and safety for preclinical use. The disposable handpiece is not recommended drilling in oral cavity. We use for student practical  in Operative Dentistry at preclinic laboratory. The other side micromotor low speed handpiece used as bur device on the phantom, the problem usually found in preclinik laboratory on practical conservation with the use of micromotor frequent damage to the handpiece (contra angel. Micromotor tend to heat up faster and have a low-speed, so it took a long time to complete the drilling, using the micromotor tend to be less safe because of the power generated from the flow of electricity at any time could damage. The price of  micromotor also is quite expensive. The limitations of the budget funds for maintenance, repair and procurement of mikromotor also became a problem. Based on these problems, the research team made a solution in the form of a replacement tool (substitute micromotor with the aim to resolve the existing problems as well as creating practices preclinic more effectively and efficiently. The use of a simple drill tool in the form of a series of Pneumatic Valve 220 volt (include electric compressor and Selenoid Disposible Handpiece Contra-angles as a new innovation in the laboratory of Dental Nursing. Majors preclinik Health Polytechnic Tasikmalaya  have been applied for last 3 years and have been able to more efficient cost of procurement tool of 70%. This disposible tool is apparently able to drill up to 20 times preparasicavity. This research uses descriptive method. Data collection techniques are used through the question form or questionnaire. Population and sample the study is a students collage 2nd years D-III of department of dental nursing Health Polytechnic Tasikmalaya. From the results of research that the majority of students expressed pleased and satisfied. This

  8. Performance assessment studies for the long-term safety evaluation of radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Bujoreanu, D.; Olteanu, M.; Bujoreanu, L.

    2008-01-01

    Especially during the last ten years, a part of Romanian research program 'Management of Radioactive Waste and Spent Fuel' was focused mainly on applicative research for the design of near-surface disposal facility, which intends to accommodate the low and intermediate radioactive waste generated from Cernavoda NPP. In this frame, our contribution was at the acquisition of technical data for the characterization of the future disposal facility. In the present, the project of the disposal facility, located on the Saligny site, near Cernavoda NPP, must be licensed. As regards to the safe disposal, the location of final disposal, the Saligny site, has been characterized through the five geological formations which contain potential routes for transport of radionuclide released from disposal facility, in the receiving zones(potential receiving zones), into liquid and gaseous phases. The technical characteristics of the disposal facility were adapted at the Romanian disposal concept using the reference data from IAEA technical report (IAEA,1999). Input parameters which characterized from physical and chemical point of view the disposal system, were partially taken from literature. The performance assessment studies, which follows the preliminary design development phases and the selection, describes how the source term is affected by the infiltration of water through the disposal facility, degradation process of engineering barriers (reflected in the distribution coefficient values) and solubility limit. The studies regard the evaluation of the source term, sensitivity and uncertainty analysis provide the information on 'how' and 'why' were evaluated, following: (i) radiological safety assessment of near-surface disposal facility on Saligny site; (ii) complexity standard assessment of the Engineering Barriers Systems (EBS); (iii) identification of the elements which must be elaborated for the increase of the disposal safety and the necessity for new technical data for

  9. Elasto-dynamic analysis of a gear pump-Part III: Experimental validation procedure and model extension to helical gears

    Science.gov (United States)

    Mucchi, E.; Dalpiaz, G.

    2015-01-01

    This work concerns external gear pumps for automotive applications, which operate at high speed and low pressure. In previous works of the authors (Part I and II, [1,2]), a non-linear lumped-parameter kineto-elastodynamic model for the prediction of the dynamic behaviour of external gear pumps was presented. It takes into account the most important phenomena involved in the operation of this kind of machine. The two main sources of noise and vibration are considered: pressure pulsation and gear meshing. The model has been used in order to foresee the influence of working conditions and design modifications on vibration generation. The model's experimental validation is a difficult task. Thus, Part III proposes a novel methodology for the validation carried out by the comparison of simulations and experimental results concerning forces and moments: it deals with the external and inertial components acting on the gears, estimated by the model, and the reactions and inertial components on the pump casing and the test plate, obtained by measurements. The validation is carried out comparing the level of the time synchronous average in the time domain and the waterfall maps in the frequency domain, with particular attention to identify system resonances. The validation results are satisfactory globally, but discrepancies are still present. Moreover, the assessed model has been properly modified for the application to a new virtual pump prototype with helical gears in order to foresee gear accelerations and dynamic forces. Part IV is focused on improvements in the modelling and analysis of the phenomena bound to the pressure evolution around the gears in order to achieve results closer to the measured values. As a matter of fact, the simulation results have shown that a variable meshing stiffness has a notable contribution on the dynamic behaviour of the pump but this is not as important as the pressure phenomena. As a consequence, the original model was modified with the

  10. The Feasibility of Administering a Practical Clinical Examination in Podiatry at a College of Podiatric Medicine: Results of a Field Trial Under Simulated Part III Test Conditions.

    Science.gov (United States)

    And Others; Valletta, Michael

    1978-01-01

    The results of a practical clinical examination in podiatric medicine administered to fourth-year students are presented. The examination could become the prototype of a Part III practical clinical examination under the auspices of the National Board of Podiatry Examiners. Its feasibility is established and problems and issues are discussed.…

  11. Proceedings of the Annual Meeting of the Association for Education in Journalism and Mass Communication (83rd, Phoenix, Arizona, August 9-12, 2000). Miscellaneous, Part III.

    Science.gov (United States)

    Association for Education in Journalism and Mass Communication.

    The Miscellaneous, part III section of the proceedings contains the following 11 papers: "The Relationship between Health and Fitness Magazine Reading and Eating-Disordered Weight-Loss Methods among High School Girls" (Steven R. Thomsen, Michelle M. Weber, and Lora Beth Brown); "A Practical Exercise for Teaching Ethical Decision…

  12. Air quality and climate change, Topic 3 of the Model Inter-Comparison Study for Asia Phase III (MICS-Asia III) - Part 1: Overview and model evaluation

    Science.gov (United States)

    Gao, Meng; Han, Zhiwei; Liu, Zirui; Li, Meng; Xin, Jinyuan; Tao, Zhining; Li, Jiawei; Kang, Jeong-Eon; Huang, Kan; Dong, Xinyi; Zhuang, Bingliang; Li, Shu; Ge, Baozhu; Wu, Qizhong; Cheng, Yafang; Wang, Yuesi; Lee, Hyo-Jung; Kim, Cheol-Hee; Fu, Joshua S.; Wang, Tijian; Chin, Mian; Woo, Jung-Hun; Zhang, Qiang; Wang, Zifa; Carmichael, Gregory R.

    2018-04-01

    Topic 3 of the Model Inter-Comparison Study for Asia (MICS-Asia) Phase III examines how online coupled air quality models perform in simulating high aerosol pollution in the North China Plain region during wintertime haze events and evaluates the importance of aerosol radiative and microphysical feedbacks. A comprehensive overview of the MICS-Asia III Topic 3 study design, including descriptions of participating models and model inputs, the experimental designs, and results of model evaluation, are presented. Six modeling groups from China, Korea and the United States submitted results from seven applications of online coupled chemistry-meteorology models. Results are compared to meteorology and air quality measurements, including data from the Campaign on Atmospheric Aerosol Research Network of China (CARE-China) and the Acid Deposition Monitoring Network in East Asia (EANET). The correlation coefficients between the multi-model ensemble mean and the CARE-China observed near-surface air pollutants range from 0.51 to 0.94 (0.51 for ozone and 0.94 for PM2.5) for January 2010. However, large discrepancies exist between simulated aerosol chemical compositions from different models. The coefficient of variation (SD divided by the mean) can reach above 1.3 for sulfate in Beijing and above 1.6 for nitrate and organic aerosols in coastal regions, indicating that these compositions are less consistent from different models. During clean periods, simulated aerosol optical depths (AODs) from different models are similar, but peak values differ during severe haze events, which can be explained by the differences in simulated inorganic aerosol concentrations and the hygroscopic growth efficiency (affected by varied relative humidity). These differences in composition and AOD suggest that future models can be improved by including new heterogeneous or aqueous pathways for sulfate and nitrate formation under hazy conditions, a secondary organic aerosol (SOA) formation chemical

  13. Geological disposal concept hearings

    International Nuclear Information System (INIS)

    1996-01-01

    The article outlines the progress to date on AECL spent-nuclear fuel geological disposal concept. Hearings for discussion, organised by the federal Environmental Assessment Review Panel, of issues related to this type of disposal method occur in three phases, phase I focuses on broad societal issues related to long term management of nuclear fuel waste; phase II will focus on the technical aspects of this method of disposal; and phase III will consist of community visits in New Brunswick, Quebec, Ontario, Manitoba and Saskatchewan. This article provides the events surrounding the first two weeks of phase I hearings (extracted from UNECAN NEWS). In the first week of hearings, where submissions on general societal issues was the focus, there were 50 presentations including those by Natural Resources Canada, Energy Probe, Ontario Hydro, AECL, Canadian Nuclear Society, Aboriginal groups, environmental activist organizations (Northwatch, Saskatchewan Environmental Society, the Inter-Church Uranium Committee, and the Canadian Coalition for Nuclear responsibility). In the second week of hearings there was 33 presentations in which issues related to siting and implementation of a disposal facility was the focus. Phase II hearings dates are June 10-14, 17-21 and 27-28 in Toronto

  14. Report on radioactive waste disposal

    International Nuclear Information System (INIS)

    1993-01-01

    The safe management of radioactive wastes constitutes an essential part of the IAEA programme. A large number of reports and conference proceedings covering various aspects of the subject have been issued. The Technical Review Committee on Underground Disposal (February 1988) recommended that the Secretariat issue a report on the state of the art of underground disposal of radioactive wastes. The Committee recommended the need for a report that provided an overview of the present knowledge in the field. This report covers the basic principles associated with the state of the art of near surface and deep geological radioactive waste disposal, including examples of prudent practice, and basic information on performance assessment methods. It does not include a comprehensive description of the waste management programmes in different countries nor provide a textbook on waste disposal. Such books are available elsewhere. Reviewing all the concepts and practices of safe radioactive waste disposal in a document of reasonable size is not possible; therefore, the scope of this report has been limited to cover essential parts of the subject. Exotic disposal techniques and techniques for disposing of uranium mill tailings are not covered, and only brief coverage is provided for disposal at sea and in the sea-bed. The present report provides a list of references to more specialized reports on disposal published by the IAEA as well as by other bodies, which may be consulted if additional information is sought. 108 refs, 22 figs, 2 tabs

  15. Superfund TIO videos. Set A. Regulatory overview - CERCLA's relationship to other programs: RCRA, Title III, UST, CWA, SDWA. Part 1. Audio-Visual

    International Nuclear Information System (INIS)

    1990-01-01

    The videotape is divided into five sections. Section 1 provides definitions and historical information on both the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The four types of RCRA regulatory programs - Subtitles C, D, I, and J - are described. Treatment, storage, and disposal (TSD) and recycling facilities are also discussed. Section 2 discusses the history behind the Emergency Planning and Community Right-to-Know Act (Title III). The four major provisions of Title III, which are emergency planning, emergency release notification, community right-to-know reporting, and the toxic chemical release inventory are covered. Section 3 outlines the UST program covering notification, record keeping, and the UST Trust Fund. Section 4 outlines the six major provisions of the Clean Water Act (CWA): water quality, pretreatment, prevention of oil and hazardous substance discharges, responses to oil and hazardous substance discharges, discharges of hazardous substances into the ocean, and dredge and fill. Section 5 explains the purpose, regulations, and standards of the Safe Drinking Water Act (SDWA). Specific issues such as underground injection, sole source aquifers, and lead contamination are discussed

  16. Land application of sewage sludge: A guide for land appliers on the requirements of the federal standards for the use or disposal of sewage sludge, 40 CFR part 503

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    The U.S. Environmental Protection Agency promulgated a regulation at 40 Code of Federal Regulations (CFR) Part 503 to ensure that sewage sludge is used or disposed of in a way that protects human health and the environment. Part 503 imposes requirements for the land application, surface disposal, and incineration of sewage sludge. The manual focuses on land application, providing guidance to land appliers of sewage sludge. The purpose of the document is to provide the land applier with sufficient guidance to comply fully with all applicable Part 503 requirements. The guidance is structured to first provide a general understanding of the Rule and its underlying principles, including definitions of sewage sludge, land application, and an explanation of who under the Rule is considered a land applier.

  17. Study of extraterrestrial disposal of radioactive wastes. Part 3: Preliminary feasibility screening study of space disposal of the actinide radioactive wastes with 1 percent and 0.1 percent fission product contamination

    Science.gov (United States)

    Hyland, R. E.; Wohl, M. L.; Finnegan, P. M.

    1973-01-01

    A preliminary study was conducted of the feasibility of space disposal of the actinide class of radioactive waste material. This waste was assumed to contain 1 and 0.1 percent residual fission products, since it may not be feasible to completely separate the actinides. The actinides are a small fraction of the total waste but they remain radioactive much longer than the other wastes and must be isolated from human encounter for tens of thousands of years. Results indicate that space disposal is promising but more study is required, particularly in the area of safety. The minimum cost of space transportation would increase the consumer electric utility bill by the order of 1 percent for earth escape and 3 percent for solar escape. The waste package in this phase of the study was designed for normal operating conditions only; the design of next phase of the study will include provisions for accident safety. The number of shuttle launches per year required to dispose of all U.S. generated actinide waste with 0.1 percent residual fission products varies between 3 and 15 in 1985 and between 25 and 110 by 2000. The lower values assume earth escape (solar orbit) and the higher values are for escape from the solar system.

  18. Environmental standards for management and disposal of spent nuclear fuel, high-level and transuranic radioactive wastes, 40 CFR part 191: draft environmental impact statement

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    The establishment of environmental standards for management and disposal of spent nuclear reactor fuel and high-level and transuranic radioactive wastes is proposed. The standards would require that maximum individual doses from all normal operations be limited to 25 millirem to the whole body, 75 millirem to the thyroid, and 25 millirem to any other organ. Regarding disposal of subject materials in geologic sites, the standards would include numerical containment requirements for the first 10,000 years following disposal, assurance requirements, and procedural requirements. The assurance requirements would provide seven principles necessary for developing confidence that long-term containment requirements would be upheld. The principles would call for well-designed, multiple-barrier disposal systems that would not rely on future generations for maintenance and would not be located near potential valuable resources. The principles would also require that future generations be provided with information about the location and dangers of the wastes and an option to recover the wastes if necessary. Procedural requirements would be developed to assure that the containment requirements were upheld. The implementation of the standards would protect public health and the environment against emissions of radioactivity. The maximum impact expected from a disposal system complying with the proposed standards would be less than 1000 premature cancer deaths over the first 10,000 years for disposal of high-level wastes produced by all currently operating reactors over their lifetime

  19. A Main Steam Safety Valve (MSSV) With Fixed Blowdown According to ASME Section III,Part NC-7512

    International Nuclear Information System (INIS)

    Follmer, Bernhard; Schnettler, Armin

    2002-01-01

    In 1986, the NRC issued the Information Notice (IN) 86-05 'Main Steam Safety Valve test failures and ring setting adjustments'. Shortly after this IN was issued, the Code was revised to require that a full flow test has to be performed on each CL.2 MSSV by the manufacturer to verify that the valve was adjusted so that it would reach full lift and thus full relieving capacity and would re-close at a pressure as specified in the valve Design Specification. In response to the concern discussed in the IN, the Westinghouse Owners Group (WOG) performed extensive full flow testing on PWR MSSVs and found that each valve required a unique setting of a combination of two rings in order to achieve full lift at accumulation of 3% and re-closing at a blowdown of 5%. The Bopp and Reuther MSSV type SiZ 2507 has a 'fixed blowdown' i.e. without any adjusting rings to adjust the 'blowdown' so that the blowdown is 'fixed'. More than 1000 pieces of this type are successfully in nuclear power plants in operation. Many of them since about 25 years. Therefore it can be considered as a proven design. It is new that an optimization of this MSSV type SiZ 2507 fulfill the requirements of part NC-7512 of the ASME Section III although there are still no adjusting rings in the flow part. In 2000, for the Qinshan Candu unit 1 and 2 full flow tests were performed with 32 MSSV type SiZ 2507 size 8'' x 12'' at 51 bar saturated steam in only 6 days. In all tests the functional performance was very stable. It was demonstrated by recording the signals lift and system pressure that all valves had acceptable results to achieve full lift at accumulation of 3% and to re-close at blowdown of 5%. This is an advantage which gives a reduction in cost for flow tests and which gives more reliability after maintenance work during outage compared to the common MSSV design with an individual required setting of the combination of the two rings. The design of the type SiZ 2507 without any adjusting rings in the

  20. Waste Disposal

    International Nuclear Information System (INIS)

    Neerdael, B.; Marivoet, J.; Put, M.; B-Verstricht, J.; Van Iseghem, P.; Buyens, M.

    1998-01-01

    This contribution describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 1997 in three topical areas are reported on: performance assessments, waste forms/packages and near-and far field studies

  1. Development of safety assessment method for human intrusion scenario in Japan. Part 1. Drilling scenario database for safety assessment of geological disposal (Contract research)

    International Nuclear Information System (INIS)

    Nagasawa, Hirokazu; Takeda, Seiji; Kimura, Hideo; Sasaki, Toshihisa

    2010-11-01

    In deep geological disposal or intermediate depth disposal, human intrusion, i.e. accidental excavation or drilling into the disposal site, may make a direct or an indirect effect on the disposal system. Safety assessment method for the human intrusion scenario, that is, the evaluation code of radiological effect from the human intrusion and the data to examine the reduction of the probability of the human intrusion occurring, is essential for the future safety regulation. Assuming that drilling action into the disposal site leads to the human proximity to the radioactive waste or the damage to the barrier system (drilling scenario), we have collected both the data on borehole drilling implemented in Japan and information on actual situation of drilling activities. Based on the data and information, we provide concrete exposure scenarios associated with borehole drilling in the vicinity of the repository and model for estimating the frequency on borehole reaching the depth of repository. The frequency is characterized with the relation to objective of excavation, geographical features, and region in Japan etc. We have developed an assembly of the information mentioned above as database, including the model parameters used in the code to assess radiation dose for drilling scenario. (author)

  2. [Operative treatment of traumatic fractures of the thoracic and lumbar spinal column: Part III: Follow up data].

    Science.gov (United States)

    Reinhold, M; Knop, C; Beisse, R; Audigé, L; Kandziora, F; Pizanis, A; Pranzl, R; Gercek, E; Schultheiss, M; Weckbach, A; Bühren, V; Blauth, M

    2009-03-01

    In this third and final part, the Spine Study Group (AG WS) of the German Trauma Association (DGU) presents the follow-up (NU) data of its second, prospective, internet-based multicenter study (MCS II) for the treatment of thoracic and lumbar spinal injuries including 865 patients from 8 trauma centers. Part I described in detail the epidemiologic data of the patient collective and the subgroups, whereas part II analyzed the different methods of treatment and radiologic findings. The study period covered the years 2002 to 2006 including a 30-month follow-up period from 01.01.2004 until 31.05.2006. Follow-up data of 638 (74%) patients were collected with a new internet-based database system and analyzed. Results in part III will be presented on the basis of the same characteristic treatment subgroups (OP, KONS, PLASTIE) and surgical treatment subgroups (Dorsal, Ventral, Kombi) in consideration of the level of injury (thoracic spine, thoracolumbar junction, lumbar spine). After the initial treatment and discharge from hospital, the average duration of subsequent inpatient rehabilitation was 4 weeks, which lasted significantly longer in patients with persistent neurologic deficits (mean 10.9 weeks) or polytraumatized patients (mean 8.6 weeks). Following rehabilitation on an inpatient basis, subsequent outpatient rehabilitation lasted on average 4 months. Physical therapy was administered significantly longer to patients with neurologic deficits (mean 8.7 months) or type C injuries (mean 8.6 months). The level of injury had no influence of the duration of the inpatient or outpatient rehabilitation. A total of 382 (72.2%) patients who were either operated from posterior approach only or in a combined postero-anterior approach had an implant removal after an average 12 months. During the follow-up period 56 (8.8%) patients with complications were registered and of these 18 (2.8%) had to have surgical revision. The most common complications reported were infection, loss

  3. Feasibility of deep ocean disposal of heat generating waste. V.1

    International Nuclear Information System (INIS)

    Hemming, C.R.

    1988-06-01

    This report summarises the research performed in the UK during the period 1977 to 1987 as part of the international programme investigating the feasibility of ocean disposal of heat generating radioactive waste. This study has involved: (i) the definition of the disposal operations needed to meet the minimum requirements for safely emplacing waste on or under the floor of the deep ocean; (ii) the identification and characterisation of areas of the deep ocean that might be suitable for containing heat generating waste; (iii) a study of the processes by which radionuclides might migrate through the multiple barriers that isolate the waste from man's environment; and (iv) a calculation of the radiological impact of the conceptual deep ocean repository. It is concluded that, from a technical and scientific viewpoint, disposal of heat generating waste in the deep ocean could provide a safe, economic and feasible alternative to deep disposal on land. (author)

  4. Study of extraterrestrial disposal of radioactive wastes. Part 2: Preliminary feasibility screening study of extraterrestrial disposal of radioactive wastes in concentrations, matrix materials, and containers designed for storage on earth

    Science.gov (United States)

    Hyland, R. E.; Wohl, M. L.; Thompson, R. L.; Finnegan, P. M.

    1972-01-01

    The results are reported of a preliminary feasibility screening study for providing long-term solutions to the problems of handling and managing radioactive wastes by extraterrestrial transportation of the wastes. Matrix materials and containers are discussed along with payloads, costs, and destinations for candidate space vehicles. The conclusions reached are: (1) Matrix material such as spray melt can be used without exceeding temperature limits of the matrix. (2) The cost in mills per kw hr electric, of space disposal of fission products is 4, 5, and 28 mills per kw hr for earth escape, solar orbit, and solar escape, respectively. (3) A major factor effecting cost is the earth storage time. Based on a normal operating condition design for solar escape, a storage time of more than sixty years is required to make the space disposal charge less than 10% of the bus-bar electric cost. (4) Based on a 10 year earth storage without further processing, the number of shuttle launches required would exceed one per day.

  5. Waste disposal

    CERN Multimedia

    2006-01-01

    We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container. type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3). nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.). building concerned. details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting o...

  6. Waste disposal

    CERN Multimedia

    2006-01-01

    We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container; type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3); nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.); building concerned; details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting...

  7. Field Surveys, IOC Valleys. Volume III, Part II. Cultural Resources Survey, Pine and Wah Wah Valleys, Utah.

    Science.gov (United States)

    1981-08-01

    including horse, camel, mammoth, Ertm E-TR-48-III-II 20 musk ox, and certain species of bison, goat, and bear, which had previously inhabited the marsh and...34 - - -9,$.. 𔄃 Im I I I Si to * Location lype/Contents Affiliation 42B@644 rid e over cr ek - P/J depression, cleared areas, Fr elon (f4-5-18-92) ground

  8. Chemical Stockpile Disposal Program

    Energy Technology Data Exchange (ETDEWEB)

    Krummel, J.R.; Policastro, A.J.; Olshansky, S.J.; McGinnis, L.D.

    1990-10-01

    As part of the Chemical Stockpile Disposal Program mandated by Public Law 99--145 (Department of Defense Authorization Act), an independent review is presented of the US Army Phase I environmental report for the disposal program at the Umatilla Depot Activity (UMDA) in Hermiston, Oregon. The Phase I report addressed new and additional concerns not incorporated in the final programmatic environmental impact statement (FPEIS). Those concerns were addressed by examining site-specific data for the Umatilla Depot Activity and by recommending the scope and content of a more detailed site-specific study. This independent review evaluates whether the new site-specific data presented in the Phase I report would alter the decision in favor of on-site disposal that was reached in the FPEIS, and whether the recommendations for the scope and content of the site-specific study are adequate. Based on the methods and assumptions presented in the FPEIS, the inclusion of more detailed site-specific data in the Phase I report does not change the decision reached in the FPEIS (which favored on-site disposal at UMDA). It is recommended that alternative assumptions about meteorological conditions be considered and that site-specific data on water, ecological, socioeconomic, and cultural resources; seismicity; and emergency planning and preparedness be considered explicitly in the site-specific EIS decision-making process. 7 refs., 1 fig.

  9. Waste disposal into the sea

    International Nuclear Information System (INIS)

    Ehlers, P.; Kunig, P.

    1987-01-01

    The waste disposal at sea is regulated for the most part by national administrative law, which mainly is based on international law rules supplemented by EC-law. The dumping of low-level radioactive waste into the sea is more and more called into question. The disposal of high-level radioactive waste into the subsoil of the sea does not correspond to the London Convention. (WG) [de

  10. Fate of circulating amino-terminal propeptide of type III procollagen in conscious pigs

    DEFF Research Database (Denmark)

    Jensen, L T; Henriksen, Jens Henrik Sahl; Risteli, J

    1993-01-01

    The amino-terminal propeptide of type III procollagen (PIIINP, M(r) 42,000) is a promising marker for the formation of type III collagen of granulation tissue in experimental and clinical studies. The disposal kinetics of circulating PIIINP is, however, almost unknown. In conscious pigs with a th......The amino-terminal propeptide of type III procollagen (PIIINP, M(r) 42,000) is a promising marker for the formation of type III collagen of granulation tissue in experimental and clinical studies. The disposal kinetics of circulating PIIINP is, however, almost unknown. In conscious pigs...... of the plasma disappearance curve originated from the formation and disappearance of a high and a low molecular weight (MW) fraction as part of the degradation of PIIINP. The high MW fraction (approximately M(r) 90,000) was similar to a previously described, but not further characterized, PIIINP immunoreactive...

  11. RA reactor safety analysis, Part II - Accident analysis; Analiza sigurnosti rada Reaktora RA I-III, Deo II - Analiza akcidenta

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Radanovic, Lj; Milovanovic, M; Afgan, N; Kulundzic, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This part of the RA reactor safety analysis includes analysis of possible accidents caused by failures of the reactor devices and errors during reactor operation. Two types of accidents are analyzed: accidents resulting from uncontrolled reactivity increase, and accidents caused by interruption of cooling.

  12. [Blood-brain barrier part III: therapeutic approaches to cross the blood-brain barrier and target the brain].

    Science.gov (United States)

    Weiss, N; Miller, F; Cazaubon, S; Couraud, P-O

    2010-03-01

    Over the last few years, the blood-brain barrier has come to be considered as the main limitation for the treatment of neurological diseases caused by inflammatory, tumor or neurodegenerative disorders. In the blood-brain barrier, the close intercellular contact between cerebral endothelial cells due to tight junctions prevents the passive diffusion of hydrophilic components from the bloodstream into the brain. Several specific transport systems (via transporters expressed on cerebral endothelial cells) are implicated in the delivery of nutriments, ions and vitamins to the brain; other transporters expressed on cerebral endothelial cells extrude endogenous substances or xenobiotics, which have crossed the cerebral endothelium, out of the brain and into the bloodstream. Recently, several strategies have been proposed to target the brain, (i) by by-passing the blood-brain barrier by central drug administration, (ii) by increasing permeability of the blood-brain barrier, (iii) by modulating the expression and/or the activity of efflux transporters, (iv) by using the physiological receptor-dependent blood-brain barrier transport, and (v) by creating new viral or chemical vectors to cross the blood-brain barrier. This review focuses on the illustration of these different approaches. Copyright (c) 2009 Elsevier Masson SAS. All rights reserved.

  13. Schinus terebinthifolius countercurrent chromatography (Part III): Method transfer from small countercurrent chromatography column to preparative centrifugal partition chromatography ones as a part of method development.

    Science.gov (United States)

    das Neves Costa, Fernanda; Hubert, Jane; Borie, Nicolas; Kotland, Alexis; Hewitson, Peter; Ignatova, Svetlana; Renault, Jean-Hugues

    2017-03-03

    Countercurrent chromatography (CCC) and centrifugal partition chromatography (CPC) are support free liquid-liquid chromatography techniques sharing the same basic principles and features. Method transfer has previously been demonstrated for both techniques but never from one to another. This study aimed to show such a feasibility using fractionation of Schinus terebinthifolius berries dichloromethane extract as a case study. Heptane - ethyl acetate - methanol -water (6:1:6:1, v/v/v/v) was used as solvent system with masticadienonic and 3β-masticadienolic acids as target compounds. The optimized separation methodology previously described in Part I and II, was scaled up from an analytical hydrodynamic CCC column (17.4mL) to preparative hydrostatic CPC instruments (250mL and 303mL) as a part of method development. Flow-rate and sample loading were further optimized on CPC. Mobile phase linear velocity is suggested as a transfer invariant parameter if the CPC column contains sufficient number of partition cells. Copyright © 2017 Elsevier B.V. All rights reserved.

  14. Normal and sonographic anatomy of selected peripheral nerves. Part III: Peripheral nerves of the lower limb

    Directory of Open Access Journals (Sweden)

    Berta Kowalska

    2012-06-01

    Full Text Available The ultrasonographic examination is currently increasingly used in imaging peripheral nerves, serving to supplement the physical examination, electromyography and magnetic resonance imaging. As in the case of other USG imaging studies, the examination of peripheral nerves is non-invasive and well-tolerated by patients. The typical ultrasonographic picture of peripheral nerves as well as the examination technique have been discussed in part I of this article series, following the example of the median nerve. Part II of the series presented the normal anatomy and the technique for examining the peripheral nerves of the upper limb. This part of the article series focuses on the anatomy and technique for examining twelve normal peripheral nerves of the lower extremity: the iliohypogastric and ilioinguinal nerves, the lateral cutaneous nerve of the thigh, the pudendal, sciatic, tibial, sural, medial plantar, lateral plantar, common peroneal, deep peroneal and superficial peroneal nerves. It includes diagrams showing the proper positioning of the sonographic probe, plus USG images of the successively discussed nerves and their surrounding structures. The ultrasonographic appearance of the peripheral nerves in the lower limb is identical to the nerves in the upper limb. However, when imaging the lower extremity, convex probes are more often utilized, to capture deeply-seated nerves. The examination technique, similarly to that used in visualizing the nerves of upper extremity, consists of locating the nerve at a characteristic anatomic reference point and tracking it using the “elevator technique”. All 3 parts of the article series should serve as an introduction to a discussion of peripheral nerve pathologies, which will be presented in subsequent issues of the “Journal of Ultrasonography”.

  15. Organizational Infrastructure in the Collegiate Athletic Training Setting, Part III: Benefits of and Barriers in the Medical and Academic Models

    Science.gov (United States)

    Eason, Christianne M.; Mazerolle, Stephanie M.; Goodman, Ashley

    2017-01-01

    Context: Academic and medical models are emerging as alternatives to the athletics model, which is the more predominant model in the collegiate athletic training setting. Little is known about athletic trainers' (ATs') perceptions of these models. Objective: To investigate the perceived benefits of and barriers in the medical and academic models. Design: Qualitative study. Setting: National Collegiate Athletic Association Divisions I, II, and III. Patients or Other Participants: A total of 16 full-time ATs (10 men, 6 women; age = 32 ± 6 years, experience = 10 ± 6 years) working in the medical (n = 8) or academic (n = 8) models. Data Collection and Analysis: We conducted semistructured telephone interviews and evaluated the qualitative data using a general inductive approach. Multiple-analyst triangulation and peer review were completed to satisfy data credibility. Results: In the medical model, role congruency and work-life balance emerged as benefits, whereas role conflict, specifically intersender conflict with coaches, was a barrier. In the academic model, role congruency emerged as a benefit, and barriers were role strain and work-life conflict. Subscales of role strain included role conflict and role ambiguity for new employees. Role conflict stemmed from intersender conflict with coaches and athletics administrative personnel and interrole conflict with fulfilling multiple overlapping roles (academic, clinical, administrative). Conclusions: The infrastructure in which ATs provide medical care needs to be evaluated. We found that the medical model can support better alignment for both patient care and the wellbeing of ATs. Whereas the academic model has perceived benefits, role incongruence exists, mostly because of the role complexity associated with balancing teaching, patient-care, and administrative duties. PMID:27977302

  16. Organizational Infrastructure in the Collegiate Athletic Training Setting, Part III: Benefits of and Barriers in the Medical and Academic Models.

    Science.gov (United States)

    Eason, Christianne M; Mazerolle, Stephanie M; Goodman, Ashley

    2017-01-01

     Academic and medical models are emerging as alternatives to the athletics model, which is the more predominant model in the collegiate athletic training setting. Little is known about athletic trainers' (ATs') perceptions of these models.  To investigate the perceived benefits of and barriers in the medical and academic models.  Qualitative study.  National Collegiate Athletic Association Divisions I, II, and III.  A total of 16 full-time ATs (10 men, 6 women; age = 32 ± 6 years, experience = 10 ± 6 years) working in the medical (n = 8) or academic (n = 8) models.  We conducted semistructured telephone interviews and evaluated the qualitative data using a general inductive approach. Multiple-analyst triangulation and peer review were completed to satisfy data credibility.  In the medical model, role congruency and work-life balance emerged as benefits, whereas role conflict, specifically intersender conflict with coaches, was a barrier. In the academic model, role congruency emerged as a benefit, and barriers were role strain and work-life conflict. Subscales of role strain included role conflict and role ambiguity for new employees. Role conflict stemmed from intersender conflict with coaches and athletics administrative personnel and interrole conflict with fulfilling multiple overlapping roles (academic, clinical, administrative).  The infrastructure in which ATs provide medical care needs to be evaluated. We found that the medical model can support better alignment for both patient care and the wellbeing of ATs. Whereas the academic model has perceived benefits, role incongruence exists, mostly because of the role complexity associated with balancing teaching, patient-care, and administrative duties.

  17. Ocean Disposal Site Monitoring

    Science.gov (United States)

    EPA is responsible for managing all designated ocean disposal sites. Surveys are conducted to identify appropriate locations for ocean disposal sites and to monitor the impacts of regulated dumping at the disposal sites.

  18. Waste disposal: preliminary studies

    International Nuclear Information System (INIS)

    Carvalho, J.F. de.

    1983-01-01

    The problem of high level radioactive waste disposal is analyzed, suggesting an alternative for the final waste disposal from irradiated fuel elements. A methodology for determining the temperature field around an underground disposal facility is presented. (E.G.) [pt

  19. The disposal of radioactive waste

    International Nuclear Information System (INIS)

    Ormai, P.

    2006-01-01

    The first part shows different ways of 'producing' radioactive wastes, defines the wastes of small, medium and high activity and gives estimation on the quantity of the necessary capacities of waste disposal facilities. The modern radioactive waste disposal that is the integrated processing of the form of waste, the package, the technical facility and the embedding geological environment that guarantee the isolation together. Another factor is the lifetime of radioactive waste which means that any waste containing long lifetime waste in higher concentration than 400-4000 kBq/kg should be disposed geologically. Today the centre of debate disposal of radioactive waste is more social than technical. For this reason not only geological conditions and technical preparations, but social discussions and accepting communities are needed in selecting place of facilities. Now, the focus is on long term temporary disposal of high activity wastes, like burnt out heating elements. The final part of the paper summarizes the current Hungarian situation of disposal of radioactive wastes. (T-R.A.)

  20. Geohydrology of industrial waste disposal site

    International Nuclear Information System (INIS)

    Gaynor, R.K.

    1984-01-01

    An existing desert site for hazardous chemical and low-level radioactive waste disposal is evaluated for suitability. This site is characterized using geologic, geohydrologic, geochemical, and other considerations. Design and operation of the disposal facility is considered. Site characteristics are also evaluated with respect to new and proposed regulatory requirements under the Resource Conservation and Recovery Act (1976) regulations, 40 CFR Part 264, and the ''Licensing Requirements for Landfill Disposal of Radioactive Waste,'' 10 CRF Part 61. The advantages and disadvantages of siting new disposal facilities in similar desert areas are reviewed and contrasted to siting in humid locations

  1. Disposal Site Information Management System

    International Nuclear Information System (INIS)

    Larson, R.A.; Jouse, C.A.; Esparza, V.

    1986-01-01

    An information management system for low-level waste shipped for disposal has been developed for the Nuclear Regulatory Commission (NRC). The Disposal Site Information Management System (DSIMS) was developed to provide a user friendly computerized system, accessible through NRC on a nationwide network, for persons needing information to facilitate management decisions. This system has been developed on NOMAD VP/CSS, and the data obtained from the operators of commercial disposal sites are transferred to DSIMS semiannually. Capabilities are provided in DSIMS to allow the user to select and sort data for use in analysis and reporting low-level waste. The system also provides means for describing sources and quantities of low-level waste exceeding the limits of NRC 10 CFR Part 61 Class C. Information contained in DSIMS is intended to aid in future waste projections and economic analysis for new disposal sites

  2. New 20-cm radio-continuum study of the small Magellanic cloud - part III: Compact Hii regions

    Directory of Open Access Journals (Sweden)

    Wong G.F.

    2012-01-01

    Full Text Available We present and discuss a new catalogue of 48 compact Hii regions in the Small Magellanic Cloud (SMC and a newly created deep 1420 MHz (λ=20 cm radio-continuum image of the N19 region located in the southwestern part of the SMC. The new images were created by merging 1420 MHz radiocontinuum archival data from the Australian Telescope Compact Array. The majority of these detected radio compact Hii regions have rather flat spectral indices which indicates, as expected, that the dominant emission mechanism is of thermal nature.

  3. Mammalian Toxicity of Munition Compounds. Phase II. Effects of Multiple Doses. Part III. 2,6-Dinitrotoluene

    Science.gov (United States)

    1976-07-01

    and the neuromuscular effects in these dogs were not due to hypocalcemia . The lowest serum calcium concen- tration in these dogs was 4.2 meq/liter...motor end plate might produce a local hypocalcemia . Such a mechanism is purely speculative. Qualitatively and quantitavely, most of the effects of 2,6...I ýNw,- -MIM I/ MIDWEST RESEARCH INS14ITUTE H0q .3L I LU -_ MAMMALIAN TOXICITY OF MUNITIONS COMPOUlNDSPHASE II: EFFECTS OF MiULTIPLE DOSES C* •PART

  4. LLNL Input to SNL L2 MS: Report on the Basis for Selection of Disposal Options

    International Nuclear Information System (INIS)

    Sutton, M.; Blink, J.A.; Halsey, W.G.

    2011-01-01

    This mid-year deliverable has two parts. The first part is a synopsis of J. Blink's interview of the former Nevada Attorney General, Frankie Sue Del Papa, which was done in preparation for the May 18-19, 2010 Legal and Regulatory Framework Workshop held in Albuquerque. The second part is a series of sections written as input for the SNL L2 Milestone M21UF033701, due March 31, 2011. Disposal of high-level radioactive waste is categorized in this review into several categories. Section II discusses alternatives to geologic disposal: space, ice-sheets, and an engineered mountain or mausoleum. Section III discusses alternative locations for mined geologic disposal: islands, coastlines, mid-continent, and saturated versus unsaturated zone. Section IV discusses geologic disposal alternatives other than emplacement in a mine: well injection, rock melt, sub-seabed, and deep boreholes in igneous or metamorphic basement rock. Finally, Secton V discusses alternative media for mined geologic disposal: basalt, tuff, granite and other igneous/metamorphic rock, alluvium, sandstone, carbonates and chalk, shale and clay, and salt.

  5. LLNL Input to SNL L2 MS: Report on the Basis for Selection of Disposal Options

    Energy Technology Data Exchange (ETDEWEB)

    Sutton, M; Blink, J A; Halsey, W G

    2011-03-02

    This mid-year deliverable has two parts. The first part is a synopsis of J. Blink's interview of the former Nevada Attorney General, Frankie Sue Del Papa, which was done in preparation for the May 18-19, 2010 Legal and Regulatory Framework Workshop held in Albuquerque. The second part is a series of sections written as input for the SNL L2 Milestone M21UF033701, due March 31, 2011. Disposal of high-level radioactive waste is categorized in this review into several categories. Section II discusses alternatives to geologic disposal: space, ice-sheets, and an engineered mountain or mausoleum. Section III discusses alternative locations for mined geologic disposal: islands, coastlines, mid-continent, and saturated versus unsaturated zone. Section IV discusses geologic disposal alternatives other than emplacement in a mine: well injection, rock melt, sub-seabed, and deep boreholes in igneous or metamorphic basement rock. Finally, Secton V discusses alternative media for mined geologic disposal: basalt, tuff, granite and other igneous/metamorphic rock, alluvium, sandstone, carbonates and chalk, shale and clay, and salt.

  6. Disposal phase experimental program plan

    International Nuclear Information System (INIS)

    1997-01-01

    The Waste Isolation Pilot Plant (WIPP) facility comprises surface and subsurface facilities, including a repository mined in a bedded salt formation at a depth of 2,150 feet. It has been developed to safely and permanently isolate transuranic (TRU) radioactive wastes in a deep geological disposal site. On April 12, 1996, the DOE submitted a revised Resource Conservation and Recovery Act (RCRA) Part B permit application to the New Mexico Environment Department (NMED). The DOE anticipates receiving an operating permit from the NMED; this permit is required prior to the start of disposal operations. On October 29, 1996, the DOE submitted a Compliance Certification Application (CCA) to the US Environmental Protection Agency (EPA) in accordance with the WIPP land Withdrawal Act (LWA) of 1992 (Public Law 102-579) as amended, and the requirements of Title 40 of the Code of Federal Regulations (40 CFR) Parts 191 and 194. The DOE plans to begin disposal operations at the WIPP in November 1997 following receipt of certification by the EPA. The disposal phase is expected to last for 35 years, and will include recertification activities no less than once every five years. This Disposal Phase Experimental Program (DPEP) Plan outlines the experimental program to be conducted during the first 5-year recertification period. It also forms the basis for longer-term activities to be carried out throughout the 35-year disposal phase. Once the WIPP has been shown to be in compliance with regulatory requirements, the disposal phase gives an opportunity to affirm the compliance status of the WIPP, enhance the operations of the WIPP and the national TRU system, and contribute to the resolution of national and international nuclear waste management technical needs. The WIPP is the first facility of its kind in the world. As such, it provides a unique opportunity to advance the technical state of the art for permanent disposal of long-lived radioactive wastes

  7. A-Part Gel, an adhesion prophylaxis for abdominal surgery: a randomized controlled phase I-II safety study [NCT00646412].

    Science.gov (United States)

    Lang, Reinhold; Baumann, Petra; Schmoor, Claudia; Odermatt, Erich K; Wente, Moritz N; Jauch, Karl-Walter

    2015-01-01

    Intra-abdominal surgical intervention can cause the development of intra-peritoneal adhesions. To reduce this problem, different agents have been tested to minimize abdominal adhesions; however, the optimal adhesion prophylaxis has not been found so far. Therefore, the A-Part(®) Gel was developed as a barrier to diminish postsurgical adhesions; the aim of this randomized controlled study was a first evaluation of its safety and efficacy. In this prospective, controlled, randomized, patient-blinded, monocenter phase I-II study, 62 patients received either the hydrogel A-Part-Gel(®) as an anti-adhesive barrier or were untreated after primary elective median laparotomy. Primary endpoint was the occurrence of peritonitis and/or wound healing impairment 28 ± 10 days postoperatively. As secondary endpoints anastomotic leakage until 28 days after surgery, adverse events and adhesions were assessed until 3 months postoperatively. A lower rate of wound healing impairment and/or peritonitis was observed in the A-Part Gel(®) group compared to the control group: (6.5 vs. 13.8 %). The difference between the two groups was -7.3%, 90 % confidence interval [-20.1, 5.4 %]. Both treatment groups showed similar frequency of anastomotic leakage but incidence of adverse events and serious adverse events were slightly lower in the A-Part Gel(®) group compared to the control. Adhesion rates were comparable in both groups. A-Part Gel(®) is safe as an adhesion prophylaxis after abdominal wall surgery but no reduction of postoperative peritoneal adhesion could be found in comparison to the control group. This may at least in part be due to the small sample size as well as to the incomplete coverage of the incision due to the used application. NCT00646412.

  8. Dental compensation for skeletal Class III malocclusion by isolated extraction of mandibular teeth. Part 1: Occlusal situation 12 years after completion of active treatment.

    Science.gov (United States)

    Zimmer, Bernd; Schenk-Kazan, Sarah

    2015-05-01

    The purpose of this work was to statistically evaluate the outcomes achieved by isolated extraction of mandibular teeth (second premolars or first molars) for Class III compensation. Part A of the study dealt with the quality of outcomes at the end of active treatment, using weighted Peer Assessment Rating (PAR) scores determined on the basis of casts for 25 (14 female and 11 male) consecutive patients aged 16 ± 1.7 years at the time of debonding. These results were compared to the scores in a randomly selected control group of 25 (14 female and 11 male) patients who were 14.7 ± 1.9 years old at debonding. Part B evaluated the long-term stability of the outcomes based on 12 (all of them female) patients available for examination after a mean of 11.8 years. The mean weighted PAR scores obtained in both study parts were analyzed for statistical differences using a two-tailed paired Student's t-test at a significance level of p ≤ 0.05. Mean weighted PAR scores of 4.76 ± 3.94 and 3.92 ± 3.44 were obtained in the Class III extraction group and the control group, respectively, at the end of active treatment. This difference was not significant (p = 0.49). Among the 12 longitudinal patients, the mean score increased from 4 ± 3.46 at debonding to 6.25 ± 3.67 by the end of the 11.8-year follow-up period. This difference was significant (p = 0.0008). Treatment of Class III anomalies by isolated extraction of lower premolars or molars can yield PAR scores similar to those achieved by standard therapies. These scores, while increasing significantly, remained at a clinically acceptable level over 11.8 years. Hence this treatment modality--intended for cases that border on requiring orthognathic surgery--may also be recommended from a long-term point of view.

  9. Use of rumination and activity monitoring for the identification of dairy cows with health disorders: Part III. Metritis.

    Science.gov (United States)

    Stangaferro, M L; Wijma, R; Caixeta, L S; Al-Abri, M A; Giordano, J O

    2016-09-01

    The objectives of this study were to evaluate (1) the performance of an automated health-monitoring system (AHMS) to identify cows with metritis based on an alert system (health index score, HIS) that combines rumination time and physical activity; (2) the number of days between the first HIS alert and clinical diagnosis (CD) of metritis by farm personnel; and (3) the daily rumination time, physical activity, and HIS patterns around CD. In this manuscript, the overall performance of HIS to detect cows with all disorders of interest in this study [ketosis, displaced abomasum, indigestion (companion paper, part I), mastitis (companion paper, part II), and metritis] is also reported. Holstein cattle (n=1,121; 451 nulliparous and 670 multiparous) were fitted with a neck-mounted electronic rumination and activity monitoring tag (HR Tags, SCR Dairy, Netanya, Israel) from at least -21 to 80 d in milk (DIM). Raw data collected in 2-h periods were summarized per 24 h as daily rumination and activity. An HIS (0 to 100 arbitrary units) was calculated daily for individual cows with an algorithm that used rumination and activity. A positive HIS outcome was defined as an HIS of cows (n=459) at -11±3, -4±3, 0, 3±1, 7±1, 14±1, and 28±1 DIM. The overall sensitivity of HIS was 55% for all cases of metritis (n=349), but it was greater for cows with metritis and another disorder (78%) than for cows with metritis only (53%). Cows diagnosed with metritis and flagged based on HIS had substantial alterations in their rumination, activity, and HIS patterns around CD, alterations of blood markers of metabolic and health status around calving, reduced milk production, and were more likely to exit the herd than cows not flagged based on the HIS and cows without disease, suggesting that cows flagged based on the HIS had a more severe episode of metritis. Including all disorders of interest for this study, the overall sensitivity was 59%, specificity was 98%, positive predictive value was

  10. Controlled production of camembert-type cheeses: part III role of the ripening microflora on free fatty acid concentrations.

    Science.gov (United States)

    Leclercq-Perlat, Marie-Noëlle; Corrieu, Georges; Spinnler, Henry-Eric

    2007-05-01

    Phenomena generating FFAs, important flavour precursors, are significant in cheese ripening. In Camembert-like cheeses, it was intended to establish the relationships between the dynamics of FFA concentrations changes and the succession of ripening microflora during ripening. Experimental Camembert-type cheeses were prepared in duplicate from pasteurised milk inoculated with Kluyveromyces lactis, Geotrichum candidum, Penicillium camemberti, and Brevibacterium aurantiacum under aseptic conditions. For each cheese and each cheesy medium, concentrations of FFAs with odd-numbered carbons, except for 9:0 and 13:0, did not change over time. For long-chain FFAs, concentrations varied with the given cheese part (rind or core). K. lactis produced only short or medium-chain FFAs during its growth and had a minor influence on caproic, caprylic, capric, and lauric acids in comparison with G. candidum, the most lipolytic of the strains used here. It generated all short or medium-chain FFAs (4:0-12:0) during its exponential and slowdown growth periods and only long-chain ones (14:0-18:0) during its stationary phase. Pen. camemberti produced more long-chain FFAs (14:0-18:0) during its sporulation. Brev. aurantiacum did not generate any FFAs. The evidence of links between specific FFAs and the growth of a given microorganism is shown.

  11. Commercial mixed waste treatment and disposal

    International Nuclear Information System (INIS)

    Vance, J.K.

    1994-01-01

    At the South Clive, Utah, site, Envirocare of Utah, Inc., (Envirocare), currently operates a commercial low-activity, low-level radioactive waste facility, a mixed waste RCRA Part B storage and disposal facility, and an 11e.(2) disposal facility. Envirocare is also in the process of constructing a Mixed Waste Treatment Facility. As the nation's first and only commercial treatment and disposal facility for such waste, the information presented in this segment will provide insight into their current and prospective operations

  12. Evaluation of pump pulsation in respirable size-selective sampling: Part III. Investigation of European standard methods.

    Science.gov (United States)

    Soo, Jhy-Charm; Lee, Eun Gyung; Lee, Larry A; Kashon, Michael L; Harper, Martin

    2014-10-01

    Lee et al. (Evaluation of pump pulsation in respirable size-selective sampling: part I. Pulsation measurements. Ann Occup Hyg 2014a;58:60-73) introduced an approach to measure pump pulsation (PP) using a real-world sampling train, while the European Standards (EN) (EN 1232-1997 and EN 12919-1999) suggest measuring PP using a resistor in place of the sampler. The goal of this study is to characterize PP according to both EN methods and to determine the relationship of PP between the published method (Lee et al., 2014a) and the EN methods. Additional test parameters were investigated to determine whether the test conditions suggested by the EN methods were appropriate for measuring pulsations. Experiments were conducted using a factorial combination of personal sampling pumps (six medium- and two high-volumetric flow rate pumps), back pressures (six medium- and seven high-flow rate pumps), resistors (two types), tubing lengths between a pump and resistor (60 and 90 cm), and different flow rates (2 and 2.5 l min(-1) for the medium- and 4.4, 10, and 11.2 l min(-1) for the high-flow rate pumps). The selection of sampling pumps and the ranges of back pressure were based on measurements obtained in the previous study (Lee et al., 2014a). Among six medium-flow rate pumps, only the Gilian5000 and the Apex IS conformed to the 10% criterion specified in EN 1232-1997. Although the AirChek XR5000 exceeded the 10% limit, the average PP (10.9%) was close to the criterion. One high-flow rate pump, the Legacy (PP=8.1%), conformed to the 10% criterion in EN 12919-1999, while the Elite12 did not (PP=18.3%). Conducting supplemental tests with additional test parameters beyond those used in the two subject EN standards did not strengthen the characterization of PPs. For the selected test conditions, a linear regression model [PPEN=0.014+0.375×PPNIOSH (adjusted R2=0.871)] was developed to determine the PP relationship between the published method (Lee et al., 2014a) and the EN methods

  13. UMTRA Project remedial action planning and disposal cell design to comply with the proposed EPA [Environmental Protection Agency] standards (40 CFR Part 192)

    International Nuclear Information System (INIS)

    1989-01-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project involves stabilizing 24 inactive uranium mill tailings piles in 10 states. Remedial work must meet standards established by the US Environmental Protection Agency (EPA). Remedial action must be designed and constructed to prevent dispersion of the tailings and other contaminated materials, and must prevent the inadvertent use of the tailings by man. This report is prepared primarily for distribution to parties involved in the UMTRA Project, including the US Nuclear Regulatory Commission (NRC), and states and tribes. It is intended to record the work done by the DOE since publication of the proposed EPA groundwater protection standards, and to show how the DOE has attempted to respond and react in a positive way to the new requirements that result from the proposed standards. This report discusses the groundwater compliance strategies now being defined and implemented by the DOE, and details the changes in disposal cell designs that result from studies to evaluate ways to facilitate compliance with the proposed EPA groundwater protection standards. This report also serves to record the technical advances, planning, and progress made on the UMTRA Project since the appearance of the proposed EPA groundwater protection standards. The report serves to establish, document, and disseminate technical approaches and engineering and groundwater information to people who may be interested or involved in similar or related projects. 24 refs., 27 figs., 8 tabs

  14. Verification study on technology for preliminary investigation for HLW geological disposal. Part 2. Verification of surface geophysical prospecting through establishing site descriptive models

    International Nuclear Information System (INIS)

    Kondo, Hirofumi; Suzuki, Koichi; Hasegawa, Takuma; Goto, Keiichiro; Yoshimura, Kimitaka; Muramoto, Shigenori

    2012-01-01

    The Yokosuka demonstration and validation project using Yokosuka CRIEPI site has been conducted since FY 2006 as a cooperative research between NUMO (Nuclear Waste Management Organization of Japan) and CRIEPI. The objectives of this project are to examine and to refine the basic methodology of the investigation and assessment of properties of geological environment in the stage of Preliminary Investigation for HLW geological disposal. Within Preliminary Investigation technologies, surface geophysical prospecting is an important means of obtaining information from deep geological environment for planning borehole surveys. In FY 2010, both seismic prospecting (seismic reflection and vertical seismic profiling methods) for obtaining information about geological structure and electromagnetic prospecting (magneto-telluric and time domain electromagnetic methods) for obtaining information about resistivity structure reflecting the distribution of salt water/fresh water boundary to a depth of over several hundred meters were conducted in the Yokosuka CRIEPI site. Through these surveys, the contribution of geophysical prospecting methods in the surface survey stage to improving the reliability of site descriptive models was confirmed. (author)

  15. Management strategies to effect change in intensive care units: lessons from the world of business. Part III. Effectively effecting and sustaining change.

    Science.gov (United States)

    Gershengorn, Hayley B; Kocher, Robert; Factor, Phillip

    2014-03-01

    Reaping the optimal rewards from any quality improvement project mandates sustainability after the initial implementation. In Part III of this three-part ATS Seminars series, we discuss strategies to create a culture for change, improve cooperation and interaction between multidisciplinary teams of clinicians, and position the intensive care unit (ICU) optimally within the hospital environment. Coaches are used throughout other industries to help professionals assess and continually improve upon their practice; use of this strategy is as of yet infrequent in health care, but would be easily transferable and potentially beneficial to ICU managers and clinicians alike. Similarly, activities focused on improving teamwork are commonplace outside of health care. Simulation training and classroom education about key components of successful team functioning are known to result in improvements. In addition to creating an ICU environment in which individuals and teams of clinicians perform well, ICU managers must position the ICU to function well within the hospital system. It is important to move away from the notion of a standalone ("siloed") ICU to one that is well integrated into the rest of the institution. Creating a "pull-system" (in which participants are active in searching out needed resources and admitting patients) can help ICU managers both provide better care for the critically ill and strengthen relationships with non-ICU staff. Although not necessary, there is potential upside to creating a unified critical care service to assist with achieving these ends.

  16. Dismantling and disposal of the Chisobox experimental irradiator

    International Nuclear Information System (INIS)

    Kriz, R.

    2005-01-01

    The Chisobox experimental irradiator was installed at the Faculty of Medicine in Hradec Kralove, Radioisotope Laboratories and Vivarium, for the purposes of the scientific research of ionizing radiation effects on the living organisms. The irradiator was put into operation in 1977. After 1989, its use has been - significantly reduced and it was only employed for the sterilization of medical materials and aids as well as for the radiation treatment of antique and museum things having wood-worm. In January 2001, its next operation was determined by the SUJB decision (i.e. The State Office for Nuclear Safety) in which the constancy tests for all individual ionizing radiation sources being part of the system were required. As the f constancy tests were not performed at that time, the Faculty Management decided for the -- decommissioning of the irradiator in June 2001. In 2003, the Faculty of Medicine announced a tender for the category III workplace disposal. Primarily, the VF, a.s. in cooperation with the SURAO Prague (i.e. the Radioactive Waste Repository Authority) were to have disposed this workplace, and a hot cell designed to be built in Litomerice by the SURAO was to have been used for this project. However, the Faculty of Medicine got a grant for the irradiator disposal in 2004 providing that the disposal had to be finished in the same year. For this reason, the complete project has been assigned to the VF, a.s. Company, which put its hot cell into operation in 2004. The VF, a.s. Company finished the disposal of the irradiator in October/November 2004. After the agreement with the SURAO in April 2005, the sealed sources placed in the storage baskets were put into a newly manufactured container -a non-standard storage unit -and transported to be stored in the URAO Richard in Litomerice. (authors)

  17. Extracción de cromo con disolventes orgánicos. III parte. Aplicación al tratamiento de residuos polimetálicos industriales

    Directory of Open Access Journals (Sweden)

    de Juan, D.

    1998-10-01

    Full Text Available The use of Primene 81R as extraction agent of chromium present in solid wastes containing nickel, iron and copper has been studied. The waste was leached with a sulphuric acid solution up to pH 3 and oxidation of Cr(III to Cr(VI with Caro acid was also studied. Because of the negative result of oxidation, the treatment was applied on Cr(III directly. Extraction/scrubbing/stripping process was studied in the leach. The composition of organic phase used in the extraction step was 10 % v/v Primene 81R, 10 % isodecanol and kerosene. All the iron, 91 % Cr, 10 % Ni and large part of the copper contained in the initial leach solution are recovered in the organic phase. In the scrubbing stage (with a sulphuric acid solution at pH 1,4, all the copper and nickel and 30 % Cr go to the washing liquor, while all the iron and 70 % Cr remained in the organic phase. In the stripping stage (with a 2N NH4OH or 2N NaOH solution all the iron and chromium are recovered as a precipitate of highly absorbent hydroxides. After the treatment mentioned, 63 % Cr and 100 % Fe are recovered as a mixture of hydroxides, and 28 % of the initial chromium, all the nickel and the copper are found in the washing liquor.

    Se estudia la aplicación del Primene 81R como agente de extracción del cromo presente en residuos sólidos que poseen níquel, hierro y cobre. El residuo se lixivió con disolución de ácido sulfúrico hasta pH 3 y se investigó la oxidación del Cr(III a Cr(VI con ácido de Caro. Ante el nulo resultado en la oxidación, se actuó directamente sobre el Cr(III. Se estudió el proceso de extracción/lavado/reextracción sobre la lejía de lixiviación. La fase orgánica empleada en la extracción estaba constituida por 10 % v/v de Primene 81R, 10 % de isodecanol y queroseno. En la fase orgánica se recupera todo el hierro, el 91 % Cr, el 10 % Ni y gran parte del cobre contenidos en la lejía de partida. En la etapa de lavado (con disolución de

  18. French surface disposal experience. The disposal of large waste

    International Nuclear Information System (INIS)

    Dutzer, Michel; Lecoq, Pascal; Duret, Franck; Mandoki, Robert

    2006-01-01

    More than 90 percent of the volume of radioactive waste that are generated in France can be managed in surface disposal facilities. Two facilities are presently operated by ANDRA: the Centre de l'Aube disposal facility that is dedicated to low and intermediate short lived waste and the Morvilliers facility for very low level waste. The Centre de l'Aube facility was designed at the end of the years 1980 to replace the Centre de la Manche facility that ended operation in 1994. In order to achieve as low external exposure as possible for workers it was decided to use remote handling systems as much as possible. Therefore it was necessary to standardize the types of waste containers. But taking into account the fact that these waste were conditioned in existing facilities, it was not possible to change a major part of existing packages. As a consequence, 6 mobile roofs were constructed to handle 12 different types of waste packages in the disposal vaults. The scope of Centre de l'Aube was mainly to dispose operational waste. However some packages, as 5 or 10 m 3 metallic boxes, could be used for larger waste generated by decommissioning activities. The corresponding flow was supposed to be small. After the first years of operations, it appeared interesting to develop special procedures to dispose specific large waste in order to avoid external exposure costly cutting works in the generating facilities. A 40 m 3 box and a large remote handling device were disposed in vaults that were currently used for other types of packages. Such a technique could not be used for the disposal of vessel heads that were replaced in 55 pressurised water power reactors. The duration of disposal and conditioning operation was not compatible with the flow of standard packages that were delivered in the vaults. Therefore a specific type of vault was designed, including handling and conditioning equipment. The first pressure vessel head was delivered on the 29 of July 2004, 6 heads have been

  19. Low level waste disposal

    International Nuclear Information System (INIS)

    Barthoux, A.

    1985-01-01

    Final disposal of low level wastes has been carried out for 15 years on the shallow land disposal of the Manche in the north west of France. Final participant in the nuclear energy cycle, ANDRA has set up a new waste management system from the production center (organization of the waste collection) to the disposal site including the setting up of a transport network, the development of assessment, additional conditioning, interim storage, the management of the disposal center, records of the location and characteristics of the disposed wastes, site selection surveys for future disposals and a public information Department. 80 000 waste packages representing a volume of 20 000 m 3 are thus managed and disposed of each year on the shallow land disposal. The disposal of low level wastes is carried out according to their category and activity level: - in tumuli for very low level wastes, - in monoliths, a concrete structure, of the packaging does not provide enough protection against radioactivity [fr

  20. Milliped Miscellany — Part III

    NARCIS (Netherlands)

    Jeekel, C.A.W.

    1956-01-01

    MATERIAL: Eritrea: Gula (15° 36’ N., 38° 21’ E.), 500 m., 19 July 1953, Coll. W. J. STOWER, 1 ♂ (holotype). COLOUR : Head, except the lower portion of the clypeus and a sharply demarcated spot at the medio-posterior side of the antennal sockets which are yellowish, very dark brown. Antennae and legs

  1. Tarski Geometry Axioms. Part III

    Directory of Open Access Journals (Sweden)

    Coghetto Roland

    2017-12-01

    Full Text Available In the article, we continue the formalization of the work devoted to Tarski’s geometry - the book “Metamathematische Methoden in der Geometrie” by W. Schwabhäuser, W. Szmielew, and A. Tarski. After we prepared some introductory formal framework in our two previous Mizar articles, we focus on the regular translation of underlying items faithfully following the abovementioned book (our encoding covers first seven chapters. Our development utilizes also other formalization efforts of the same topic, e.g. Isabelle/HOL by Makarios, Metamath or even proof objects obtained directly from Prover9. In addition, using the native Mizar constructions (cluster registrations the propositions (“Satz” are reformulated under weaker conditions, i.e. by using fewer axioms or by proposing an alternative version that uses just another axioms (ex. Satz 2.1 or Satz 2.2.

  2. Workshop 97. Part III. Proceedings

    International Nuclear Information System (INIS)

    1996-12-01

    This volume of the Proceedings covers the following branches of science and technology: power systems and electrical engineering, electronics and measuring and communication engineering, optics, quantum electronics and photonics, microelectronics, and biomedical engineering. Out of the contributions, 2 have been input to INIS. (P.A.)

  3. ASIST 2003: Part III: Posters.

    Science.gov (United States)

    Proceedings of the ASIST Annual Meeting, 2003

    2003-01-01

    Twenty-three posters address topics including access to information; metadata; personal information management; scholarly information communication; online resources; content analysis; interfaces; Web queries; information evaluation; informatics; information needs; search effectiveness; digital libraries; diversity; automated indexing; e-commerce;…

  4. MicroVent (part III)

    DEFF Research Database (Denmark)

    Dreau, Jerome Le; Heiselberg, Per Kvols; Jensen, Rasmus Lund

    This study aims at using the InVentilate unit in the cooling case, without heat recovery. It results in a relatively low inlet air temperature. Different solutions have been tested to decrease the risk of draught in the occupied zone: ‐ Using a mixer (2 designs) ‐ Using an inlet grille ‐ Using...

  5. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Petit, J.C.

    1998-04-01

    A deep gap, reflecting a persisting fear, separates the viewpoints of the experts and that of the public on the issue of the disposal of nuclear WASTES. The history of this field is that of the proliferation with time of spokesmen who pretend to speak in the name of the both humans and non humans involved. Three periods can be distinguished: 1940-1970, an era of contestation and confusion when the experts alone represents the interest of all; 1970-1990, an era of contestation and confusion when spokespersons multiply themselves, generating the controversy and the slowing down of most technological projects; 1990-, an era of negotiation, when viewpoints, both technical and non technical, tend to get closer and, let us be optimistic, leading to the overcome of the crisis. We show that, despite major differences, the options and concepts developed by the different actors are base on two categories of resources, namely Nature and Society, and that the consensus is built up through their 'hydridation'. we show in this part that the perception of nuclear power and, in particular of the underground disposal of nuclear wastes, involves a very deep psychological substrate. Trying to change mentalities in the domain by purely scientific and technical arguments is thus in vain. The practically instinctive fear of radioactivity, far from being due only to lack of information (and education), as often postulated by scientists and engineers, is rooted in archetypical structures. These were, without doubt, reactivated in the 40 s by the traumatizing experience of the atomic bomb. In addition, anthropological-linked considerations allow us to conclude that he underground disposal of wastes is seen as a 'rape' and soiling of Mother Earth. This contributes to explaining, beyond any rationality, the refusal of this technical option by some persons. However, it would naturally be simplistic and counter-productive to limit all controversy in this domain to these psychological aspects

  6. Institute for Nuclear Waste Disposal. Annual Report 2011

    International Nuclear Information System (INIS)

    Geckeis, H.; Stumpf, T.

    2012-01-01

    The R and D at the Institute for Nuclear Waste Disposal, INE, (Institut fuer Nukleare Entsorgung) of the Karlsruhe Institute of Technology (KIT) focuses on (i) long term safety research for nuclear waste disposal, (ii) immobilization of high level radioactive waste (HLW), (iii) separation of minor actinides from HLW and (iv) radiation protection.

  7. Underground radioactive waste disposal concept

    International Nuclear Information System (INIS)

    Frgic, L.; Tor, K.; Hudec, M.

    2002-01-01

    The paper presents some solutions for radioactive waste disposal. An underground disposal of radioactive waste is proposed in deep boreholes of greater diameter, fitted with containers. In northern part of Croatia, the geological data are available on numerous boreholes. The boreholes were drilled during investigations and prospecting of petroleum and gas fields. The available data may prove useful in defining safe deep layers suitable for waste repositories. The paper describes a Russian disposal design, execution and verification procedure. The aim of the paper is to discuss some earlier proposed solutions, and present a solution that has not yet been considered - lowering of containers with high level radioactive waste (HLW) to at least 500 m under the ground surface.(author)

  8. A slingram survey on the Nevada Test Site: part of an integrated geologic geophysical study of site evaluation for nuclear waste disposal

    Science.gov (United States)

    Flanigan, Vincent J.

    1979-01-01

    A slingram geophysical survey was made in early 1978 as part of the integrated geologlcal-geophysical study aimed at evaluating the Eleana Formation as a possible repository for nuclear waste. The slingram data were taken over an alluvial fan and pediments along the eastern flank of Syncline Ridge about 45 km north of Mercury, Nevada, on the Nevada Test Site. The data show that the more conductive argillaceous Eleana Formation varies in depth from 40 to 85 m from west to east along traverse lines. Northeast-trending linear anomalies suggest rather abrupt changes in subsurface geology that may be associated with faults and fractures. The results of the slingram survey will, when interpreted in the light of other geologic and geophysical evidence, assist in understanding the shallow parts of the geologic setting of the Eleana Formation.

  9. Treated Effluent Disposal Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Treated non-hazardous and non-radioactive liquid wastes are collected and then disposed of through the systems at the Treated Effluent Disposal Facility (TEDF). More...

  10. 41 CFR 301-76.2 - What is disposable pay?

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 4 2010-07-01 2010-07-01 false What is disposable pay... What is disposable pay? Disposable pay is the part of the employee's compensation remaining after the... deductions such as savings bonds, charitable contributions, etc. Deductions may be made from any type of pay...

  11. Problems and prospects of refuse disposal in nigerian urban centres ...

    African Journals Online (AJOL)

    Refuse disposal is one of the major environmental problems that developing ... The problem of waste management has two parts, that of collection and that of disposal. ... Disposal methods such as dumping sites, incineration, recycling, shipping ... citizenry has roles to play in adopting more suitable solutions to this problem.

  12. No nuclear power. No disposal facility?

    Energy Technology Data Exchange (ETDEWEB)

    Feinhals, J. [DMT GmbH und Co.KG, Hamburg (Germany)

    2016-07-01

    Countries with a nuclear power programme are making strong efforts to guarantee the safe disposal of radioactive waste. The solutions in those countries are large disposal facilities near surface or in deep geological layers depending on the activity and half-life of the nuclides in the waste. But what will happen with the radioactive waste in countries that do not have NPPs but have only low amounts of radioactive waste from medical, industrial and research facilities as well as from research reactors? Countries producing only low amounts of radioactive waste need convincing solutions for the safe and affordable disposal of their radioactive waste. As they do not have a fund by an operator of nuclear power plants, those countries need an appropriate and commensurate solution for the disposal of their waste. In a first overview five solutions seem to be appropriate: (i) the development of multinational disposal facilities by using the existing international knowhow; (ii) common disposal with hazardous waste; (iii) permanent storage; (iv) use of an existing mine or tunnel; (v) extension of the borehole disposal concept for all the categories of radioactive wastes.

  13. Reflecting Equity and Diversity. Part I: Guidelines and Procedure for Evaluating Bias in Instructional Materials. Part II: Bias Awareness Training Worksheets. Part III: Bias Awareness and Procedure Training Course.

    Science.gov (United States)

    Bebermeyer, Jim; Edmond, Mary, Ed.

    Reflecting a need to prepare students for working in diverse organizations, this document was developed to increase school officials' awareness of bias in instructional materials and help them select bias-free materials. A number of the examples illustrate situations dealing with diversity in the workplace. The guide is divided into three parts:…

  14. Disposal configuration options for future uses of greater confinement disposal at the Nevada Test Site

    International Nuclear Information System (INIS)

    Price, L.

    1994-09-01

    The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE's Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada Test Site (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS

  15. 'Reference Biospheres' for solid radioactive waste disposal. Report of BIOMASS Theme 1 of the BIOsphere Modelling and ASSessment (BIOMASS) Programme. Part of the IAEA Co-ordinated Research Project on Biosphere Modelling and Assessment (BIOMASS)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    The IAEA Programme on BIOsphere Modelling and ASSessment (BIOMASS) was launched in Vienna in October 1996. The programme was concerned with developing and improving capabilities to predict the transfer of radionuclides in the environment. The programme had three themes: Theme 1: Radioactive Waste Disposal. The objective was to develop the concept of a standard or reference biosphere for application to the assessment of the long-term safety of repositories for radioactive waste. Under the general heading of 'Reference Biospheres', six Task Groups were established: Task Group 1: Principles for the Definition of Critical and Other Exposure Groups. Task Group 2: Principles for the Application of Data to Assessment Models. Task Group 3: Consideration of Alternative Assessment Contexts. Task Group 4: Biosphere System Identification and Justification. Task Group 5: Biosphere System Descriptions. Task Group 6: Model Development. Theme 2: Environmental Releases. BIOMASS provided an international forum for activities aimed at increasing the confidence in methods and models for the assessment of radiation exposure related to environmental releases. Two Working Groups addressed issues concerned with the reconstruction of radiation doses received by people from past releases of radionuclides to the environment and the evaluation of the efficacy of remedial measures. Theme 3: Biosphere Processes. The aim of this Theme was to improve capabilities for modelling the transfer of radionuclides in particular parts of the biosphere identified as being of potential radiological significance and where there were gaps in modelling approaches. This topic was explored using a range of methods including reviews of the literature, model inter-comparison exercises and, where possible, model testing against independent sources of data. Three Working Groups were established to examine the modelling of: (1) long term tritium dispersion in the environment; (2) radionuclide uptake by fruits; and (3

  16. Role of an organic carbon-rich soil and Fe(III) reduction in reducing the toxicity and environmental mobility of chromium(VI) at a COPR disposal site.

    Science.gov (United States)

    Ding, Weixuan; Stewart, Douglas I; Humphreys, Paul N; Rout, Simon P; Burke, Ian T

    2016-01-15

    Cr(VI) is an important contaminant found at sites where chromium ore processing residue (COPR) is deposited. No low cost treatment exists for Cr(VI) leaching from such sites. This study investigated the mechanism of interaction of alkaline Cr(VI)-containing leachate with an Fe(II)-containing organic matter rich soil beneath the waste. The soil currently contains 0.8% Cr, shown to be present as Cr(III)(OH)3 in EXAFS analysis. Lab tests confirmed that the reaction of Cr(VI) in site leachate with Fe(II) present in the soil was stoichiometrically correct for a reductive mechanism of Cr accumulation. However, the amount of Fe(II) present in the soil was insufficient to maintain long term Cr(VI) reduction at historic infiltration rates. The soil contains a population of bacteria dominated by a Mangroviflexus-like species, that is closely related to known fermentative bacteria, and a community capable of sustaining Fe(III) reduction in alkaline culture. It is therefore likely that in situ fermentative metabolism supported by organic matter in the soil produces more labile organic substrates (lactate was detected) that support microbial Fe(III) reduction. It is therefore suggested that addition of solid phase organic matter to soils adjacent to COPR may reduce the long term spread of Cr(VI) in the environment. Copyright © 2015 The Authors. Published by Elsevier B.V. All rights reserved.

  17. Safety case for the disposal of spent nuclear fuel at Olkiluoto. Data basis for the Biosphere Assessment BSA-2012. Part 1-2, Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-01-15

    The purpose of the report is to document and justify the input data used in the models of the biosphere assessment. Methodology similar to that presented in the Models and Data for the Repository System report has been followed. After more introductory parts, chapter 3 lays the foundation of data selection by describing typical properties of the soil and sediment types and biotopes, and summarises the representative plants and animals selected in the Biosphere Description report. The conceptual models on pools and fluxes of elements in the ecosystems are presented in chapter 4. These, together with the more qualitative descriptions of the succession lines in the Biosphere Description report, are simplified into the actual assessment models (summarised in chapter 5) in an iterative manner. Chapter 6 briefly presents the scenarios and calculation cases of the biosphere assessment, detailed in the Formulation of Radionuclide Releases Scenarios report. The account of the actual input data to the assessment models begins in chapter 7 with the data needed to identify the biotopes and compartments common to all assessment models. Chapters 8 to 13, grouped by the sub-models, address the input data to the terrain and ecosystems development modelling (detailed in the Terrain and Ecosystems Development Modelling report), and chapter 14 those to the surface and near-surface hydrological model (the Surface and Near-Surface Hydrological Modelling report). Chapters 15 to 18 address the data to the radionuclide transport modelling in the biosphere, and chapter 19 those needed for the dose assessment for humans (the Biosphere Radionuclide Transport and Dose Assessment report). Finally, before conclusions in chapter 21, the input data specific to the dose assessment for plants and animals (the Dose Assessment for the Plants and Animals report) are addressed in chapter 20. However, several parameters are common to the assessment models and are presented in connection to the model

  18. Safety case for the disposal of spent nuclear fuel at Olkiluoto. Data basis for the Biosphere Assessment BSA-2012. Part 1-2, Appendices

    International Nuclear Information System (INIS)

    2014-01-01

    The purpose of the report is to document and justify the input data used in the models of the biosphere assessment. Methodology similar to that presented in the Models and Data for the Repository System report has been followed. After more introductory parts, chapter 3 lays the foundation of data selection by describing typical properties of the soil and sediment types and biotopes, and summarises the representative plants and animals selected in the Biosphere Description report. The conceptual models on pools and fluxes of elements in the ecosystems are presented in chapter 4. These, together with the more qualitative descriptions of the succession lines in the Biosphere Description report, are simplified into the actual assessment models (summarised in chapter 5) in an iterative manner. Chapter 6 briefly presents the scenarios and calculation cases of the biosphere assessment, detailed in the Formulation of Radionuclide Releases Scenarios report. The account of the actual input data to the assessment models begins in chapter 7 with the data needed to identify the biotopes and compartments common to all assessment models. Chapters 8 to 13, grouped by the sub-models, address the input data to the terrain and ecosystems development modelling (detailed in the Terrain and Ecosystems Development Modelling report), and chapter 14 those to the surface and near-surface hydrological model (the Surface and Near-Surface Hydrological Modelling report). Chapters 15 to 18 address the data to the radionuclide transport modelling in the biosphere, and chapter 19 those needed for the dose assessment for humans (the Biosphere Radionuclide Transport and Dose Assessment report). Finally, before conclusions in chapter 21, the input data specific to the dose assessment for plants and animals (the Dose Assessment for the Plants and Animals report) are addressed in chapter 20. However, several parameters are common to the assessment models and are presented in connection to the model

  19. Disposal of Radioactive Waste

    International Nuclear Information System (INIS)

    2011-01-01

    This Safety Requirements publication applies to the disposal of radioactive waste of all types by means of emplacement in designed disposal facilities, subject to the necessary limitations and controls being placed on the disposal of the waste and on the development, operation and closure of facilities. The classification of radioactive waste is discussed. This Safety Requirements publication establishes requirements to provide assurance of the radiation safety of the disposal of radioactive waste, in the operation of a disposal facility and especially after its closure. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. This is achieved by setting requirements on the site selection and evaluation and design of a disposal facility, and on its construction, operation and closure, including organizational and regulatory requirements.

  20. Theoretical analysis of nuclear reactors (Phase II), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (II faza) I-V, III Deo, Zatrovanje reaktora, II faza

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-10-15

    This phase is dealing with influence of all the fission products except Xe{sup 135} on the reactivity of a reactor, usually named as reactor poisoning. The first part of the report is a review of methods for calculation of reactor poisoning. The second part shows the most frequently used method for calculation of cross sections and yields of pseudo products (for thermal neutrons). The system of equations was adopted dependent on the conditions of the available computer system. It is described in part three. Detailed method for their application is described in part four and results obtained are presented in part five.

  1. Numerical study of the THM effects on the near-field safety of a hypothetical nuclear waste repository - BMT1 of the DECOVALEX III project. Part 1: conceptualization and characterization of the problems and summary of results

    International Nuclear Information System (INIS)

    Chijimatsu, M.; Nguyen, T.S.; Jing, L.; De Jonge, J.; Kohlmeier, M.; Millard, A.; Rejeb, A.; Rutqvist, J.; Souley, M.; Sugita, Y.

    2004-01-01

    Geological disposal of the spent nuclear fuel uses often the concept of multiple barrier systems. In order to predict the performance of these barriers, mathematical models have been developed, verified and validated against analytical solutions, laboratory tests and field experiments within the international DECOVALEX III project. These models in general consider the full coupling of thermal (T), hydraulic (H) and mechanical (M) processes that would prevail in the geological media around the repository. For Bench Mark Test no. 1 (BMT1) of the DECOVALEX III project, seven multinational research teams studied the implications of coupled THM processes on the safety of a hypothetical nuclear waste repository at the near-field and are presented in three accompany papers in this issue. This paper is the first of the three companion papers, which provides the conceptualization and characterization of the BMT1 as well as some general conclusions based on the findings of the numerical studies. It also shows the process of building confidence in the mathematical models by calibration with a reference T-H-M experiment with realistic rock mass conditions and bentonite properties and measured outputs of thermal, hydraulic and mechanical variables

  2. Radioactive waste disposal: an international law perspective

    International Nuclear Information System (INIS)

    Barrie, G.N.

    1989-01-01

    The question of radioactive waste disposal is the most intractable technical and political problem facing nuclear industry. Environmentalists world-wide demand a nuclear waste policy that must be ecologically acceptable internationally. Radioactive wastes and oil pollution were the first two types of marine pollution to receive international attention and various marine pollution controls were established. Ocean disposal was co-ordinated by the Nuclear Energy Agency and the Organization of Economic Co-operation and Development in 1967. The first treaty was the 1958 Convention on the High Seas (High Seas Convention). In response to its call for national co-operation the International Atomic Energy Agency (IAEA) established its Brynielson panel. The IAEA first issued guidelines on sea dumping in 1961. The London Dumping Convention, written in 1972, is the only global agreement concerned solely with the disposal of wastes in the marine environment by dumping. None of the global agreements make specific reference to sea-bed disposal of high-level radioactive wastes. Negotiations began at the Third UN Conference on the Law of the Sea (UNCLOS III) for the codification of a comprehensive treaty concerned with the protection, conservation, sustainable use and development of the marine environment. Burial in deep geological formations is a method of HLW disposal which decreases the chances of accidental intrusion by mankind and has little likelihood of malicious intrusion. National waste management programmes of different countries differ but there is agreement on the acceptable technical solutions to issues of waste management. The final disposition of HLW - storage or disposal - has not been decisively determined, but there is growing consensus that geological land-based disposal is the most viable alternative. Expanded international technical co-operation could well reduce the time needed to develop effective waste disposal mechanisms

  3. The removal of toxic metals from liquid effluents by ion exchange resins. Part IV: Chromium(III)/H+ /Lewatit SP112

    International Nuclear Information System (INIS)

    Alguacil, F.J.

    2017-01-01

    This investigation presented results on the removal of chromium(III), from aqueous solution in the 0-5 pH range, using Lewatit SP112 cationic exchange resin. Several aspects affecting the ion exchange process were evaluated, including: the influence of the stirring speed, temperature, pH of the solution, resin dosage and aqueous ionic strength. The selectivity of the system was tested against the presence of other metals in the aqueous solution, whereas the removal of chromium(III) from solutions was compared with results obtained using multiwalled carbon nanotubes as adsorbents. From the batch experimental data, best fit of the results is obtained with the Langmuir model, whereas the ion exchange process is best explained by the pseudo-second order model, moreover, experimental data responded well to the film-diffusion controlled model. Elution of the chromium(III) loaded into the resin is well accomplished by the use of sodium hydroxide solutions. [es

  4. Extracción de cromo con disolventes orgánicos. III parte. Aplicación al tratamiento de residuos polimetálicos industriales

    OpenAIRE

    de Juan, D.; Meseguer, V.; Lozano, L. J.

    1998-01-01

    The use of Primene 81R as extraction agent of chromium present in solid wastes containing nickel, iron and copper has been studied. The waste was leached with a sulphuric acid solution up to pH 3 and oxidation of Cr(III) to Cr(VI) with Caro acid was also studied. Because of the negative result of oxidation, the treatment was applied on Cr(III) directly. Extraction/scrubbing/stripping process was studied in the leach. The composition of organic phase used in the extraction step was 10 % v/v Pr...

  5. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Blomeke, J.O.

    1979-01-01

    Radioactive waste management and disposal requirements options available are discussed. The possibility of beneficial utilization of radioactive wastes is covered. Methods of interim storage of transuranium wastes are listed. Methods of shipment of low-level and high-level radioactive wastes are presented. Various methods of radioactive waste disposal are discussed

  6. Equity and nuclear waste disposal

    International Nuclear Information System (INIS)

    Shrader-Frechette, K.

    1994-01-01

    Following the recommendations of the US National Academy of Sciences and the mandates of the 1987 Nuclear Waste Policy Amendments Act, the US Department of Energy has proposed Yucca Mountain, Nevada as the site of the world's first permanent repository for high-level nuclear waste. The main justification for permanent disposal (as opposed to above-ground storage) is that it guarantees safety by means of waste isolation. This essay argues, however, that considerations of equity (safer for whom?) undercut the safety rationale. The article surveys some prima facie arguments for equity in the distribution of radwaste risks and then evaluates four objections that are based, respectively, on practicality, compensation for risks, scepticism about duties to future generations, and the uranium criterion. The conclusion is that, at least under existing regulations and policies, permanent waste disposal is highly questionable, in part, because it fails to distribute risk equitably or to compensate, in full, for this inequity

  7. RA Reactor operation and maintenance (I-IX), Part III, Task 3.08/04-02 Refurbishment of the electrical equipment; Pogon i odrzavanje reaktora RA (I-IX), III Deo, Zadatak 3.08/04-02 Remont elektro opreme

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Nikolic, M; Poznanovic, B; Rajic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    This volume contains detailed action plan for repair of electrical equipment of the RA reactor, the list of electrical equipment parts which were either repaired or exchanged for improvement of their performance. Detailed work describing the repair and maintenance work done of the listed equipment is part of this report. Equipment related to dosimetry and control systems are included as well.

  8. Spent nuclear fuel disposal liability insurance

    International Nuclear Information System (INIS)

    Martin, D.W.

    1984-01-01

    This thesis examines the social efficiency of nuclear power when the risks of accidental releases of spent fuel radionuclides from a spent fuel disposal facility are considered. The analysis consists of two major parts. First, a theoretical economic model of the use of nuclear power including the risks associated with releases of radionuclides from a disposal facility is developed. Second, the costs of nuclear power, including the risks associated with a radionuclide release, are empirically compared to the costs of fossil fuel-fired generation of electricity. Under the provisions of the Nuclear Waste Policy Act of 1982, the federally owned and operated spent nuclear fuel disposal facility is not required to maintain a reserve fund to cover damages from an accidental radionuclide release. Thus, the risks of a harmful radionuclide release are not included in the spent nuclear fuel disposal fee charged to the electric utilities. Since the electric utilities do not pay the full, social costs of spent fuel disposal, they use nuclear fuel in excess of the social optimum. An insurance mechanism is proposed to internalize the risks associated with spent fueled disposal. Under this proposal, the Federal government is required to insure the disposal facility against any liabilities arising from accidental releases of spent fuel radionuclides

  9. Pre-feasibility study for final disposal of radioactive waste. Disposal concepts. Main report

    International Nuclear Information System (INIS)

    Andersen, L.; Skov, C.; Kueter, A.; Schepper, L.; Gottberg Roemer, H.; Refsgaard, A.; Utko, M.; Kristiansen, Torben

    2011-05-01

    This prefeasibility study is part of the overall process related to the decision on placement and design of a repository for the Danish low and medium level radioactive waste primarily from the facilities at Risoe. The prefeasibility study encompasses the preliminary design of a number of repository types based on the overall types set out in the 'Parliamentary decision' together with a preliminary safety assessment of these repository types based on their possible placement in a set of typical Danish geologies. The report consists of three parts. Part I is the descriptive part containing information on the waste to be disposed of, the potential conditioning (packaging) possibilities for the waste before placement in a repository, the suggested preliminary design of the different repository types, and the suggested visual appearance of the repository. Part II is the assessment part. It contains an introduction to the concepts used in the preliminary safety assessment, which encompasses: the assessment of potential long term impact and the assessment of possible accidental incidents. The division of the preliminary safety assessment in to these two categories has several reasons. One is that the criteria to which impact is to be compared are different for the two types of impact, another is that while the possible variation in the long term impact is primarily due to the possible variation in the parameters influencing the impact, the impact from accidental incidents is governed by the probability of the occurrence of these incidents and the potential consequence of the impact, which calls for a different assessment approach. Since the suggestions for packaging of the different waste types is a result of both types of assessments, part II also contains a description of these suggestions based on the preliminary safety assessments. Finally part II contains the costs related to the different types of repositories and the suggested packaging. Part III of the report

  10. Pre-feasibility study for final disposal of radioactive waste. Disposal concepts. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Andersen, L.; Skov, C.; Kueter, A.; Schepper, L.; Gottberg Roemer, H.; Refsgaard, A.; Utko, M.; Kristiansen, Torben (COWI A/S, Kgs. Lyngby (Denmark))

    2011-05-15

    This prefeasibility study is part of the overall process related to the decision on placement and design of a repository for the Danish low and medium level radioactive waste primarily from the facilities at Risoe. The prefeasibility study encompasses the preliminary design of a number of repository types based on the overall types set out in the 'Parliamentary decision' together with a preliminary safety assessment of these repository types based on their possible placement in a set of typical Danish geologies. The report consists of three parts. Part I is the descriptive part containing information on the waste to be disposed of, the potential conditioning (packaging) possibilities for the waste before placement in a repository, the suggested preliminary design of the different repository types, and the suggested visual appearance of the repository. Part II is the assessment part. It contains an introduction to the concepts used in the preliminary safety assessment, which encompasses: the assessment of potential long term impact and the assessment of possible accidental incidents. The division of the preliminary safety assessment in to these two categories has several reasons. One is that the criteria to which impact is to be compared are different for the two types of impact, another is that while the possible variation in the long term impact is primarily due to the possible variation in the parameters influencing the impact, the impact from accidental incidents is governed by the probability of the occurrence of these incidents and the potential consequence of the impact, which calls for a different assessment approach. Since the suggestions for packaging of the different waste types is a result of both types of assessments, part II also contains a description of these suggestions based on the preliminary safety assessments. Finally part II contains the costs related to the different types of repositories and the suggested packaging. Part III of the

  11. Geology of quadrangles H-12, H-13, and parts of I-12 and I-13, (zone III) in northeastern Santander Department, Colombia

    Science.gov (United States)

    Ward, Dwight Edward; Goldsmith, Richard; Cruz, Jaime B.; Restrepo, Hernan A.

    1974-01-01

    A program of geologic mapping and mineral investigation in Colombia was undertaken cooperatively by the Colombian Instituto Nacional de Investigaciones Geologico-Mineras (formerly known as the Inventario Minero Nacional), and the U. S. Geological Survey; by the Government of Colombia and the Agency for International Development, U. S. Department of State. The purpose was to study, and evaluate mineral resources (excluding of petroleum, coal, emeralds, and alluvial gold) of four selected areas, designated Zones I to IV, that total about 70,000 km2. The work in Zone III, in the Cordillera Oriental, was done from 1965 to 1968. The northeast trend of the Cordillera Oriental of Colombia swings abruptly to north-northwest in the area of this report, and divides around the southern end of the Maracaibo Basin. This section of the Cordillera Oriental is referred to as the Santander Massif. Radiometric age determinations indicate that the oldest rocks of the Santander massif are Precambrian and include high-grade gneiss, schist, and migmatite of the Bucaramanga Formation. These rocks were probably part of the Precambrian Guayana Shield. Low- to medium-grade metamorphic rocks of late Precambrian to Ordovician age .include phyllite, schist, metasiltstone, metasandstone, and marble of the Silgara Formation, a geosynclinal series of considerable extent in the Cordillera Oriental and possibly the Cordillera de Merida of Venezuela. Orthogneiss ranging from granite to tonalite is widely distributed in the high- and medium-grade metamorphic rocks of the central core of the massif and probably represents rocks of two ages, Precambrian and Ordovician to Early Devonian. Younger orthogneiss and the Silgara are overlain by Middle Devonian beds of the Floresta Formation which show a generally low but varying degree of metamorphism. Phyllite and argillite are common, and infrequent marble and other calcareous beds are fossiliferous. Except for recrystallization in limestones of !the

  12. Minimizing generator liability while disposing hazardous waste

    International Nuclear Information System (INIS)

    Canter, L.W.; Lahlou, M.; Pendurthi, R.P.

    1991-01-01

    Potential liabilities associated with hazardous waste disposal are related to waste properties, disposal practices and the potential threat to people and the environment in case of a pollutant release. Based on various regulations, these liabilities are enforceable and longstanding. A methodology which can help hazardous waste generators select a commercial disposal facility with a relatively low risk of potential liability is described in this paper. The methodology has two parts. The first part has 8 categories encompassing 30 factors common to all facilities, and the second part includes one category dealing with 5 factors on specific wastes and treatment/disposal technologies. This two-part evaluation feature enables the user to adapt the methodology to any type of waste disposal. In determining the scores for the factors used in the evaluation. an unranked paired comparison technique with slight modifications was used to weight the relative importance of the individual factors. In the methodology it is possible for the user to redefine the factors and change the scoring system. To make the methodology more efficient, a user-friendly computer program has been developed; the computer program is written so that desired changes in the methodology can be readily implemented

  13. Disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-01-15

    The problem of disposal can be tackled in two ways: the waste can be diluted and dispersed so that the radiation to which any single individual would be subjected would be negligible, or it can be concentrated and permanently isolated from man and his immediate environment. A variety of methods for the discharge of radioactive waste into the ground were described at the Monaco conference. They range from letting liquid effluent run into pits or wells at appropriately chosen sites to the permanent storage of high activity material at great depth in geologically suitable strata. Another method discussed consists in the incorporation of high level fission products in glass which is either buried or stored in vaults. Waste disposal into rivers, harbours, outer continental shelves and the open sea as well as air disposal are also discussed. Many of the experts at the Monaco conference were of the view that most of the proposed, or actually applied, methods of waste disposal were compatible with safety requirements. Some experts, felt that certain of these methods might not be harmless. This applied to the possible hazards of disposal in the sea. There seemed to be general agreement, however, that much additional research was needed to devise more effective and economical methods of disposal and to gain a better knowledge of the effects of various types of disposal operations, particularly in view of the increasing amounts of waste material that will be produced as the nuclear energy industry expands

  14. Economic analysis of alternative LLW disposal methods

    International Nuclear Information System (INIS)

    Foutes, C.E.

    1987-01-01

    The Environmental Protection Agency (EPA) has evaluated the costs and benefits of alternative disposal technologies as part of its program to develop generally applicable environmental standards for the land disposal of low-level radioactive waste (LLW). Costs, population health effects and Critical Population Group (CPG) exposures resulting from alternative waste treatment and disposal methods were developed and input into the analysis. The cost-effectiveness analysis took into account a number of waste streams, hydrogeologic and climatic region settings, and waste treatment and disposal methods. Total costs of each level of a standard included costs for packaging, processing, transportation, and burial of waste. Benefits are defined in terms of reductions in the general population health risk (expected fatal cancers and genetic effects) evaluated over 10,000 years. A cost-effectiveness ratio, was calculated for each alternative standard. This paper describes the alternatives considered and preliminary results of the cost-effectiveness analysis

  15. Ethical aspects of final disposal. Final report

    International Nuclear Information System (INIS)

    Baltes, B.; Leder, W.; Achenbach, G.B.; Spaemann, R.; Gerhardt, V.

    2003-01-01

    In fulfilment of this task the Federal Environmental Ministry has commissioned GRS to summarise the current national and international status of ethical aspects of the final disposal of radioactive wastes as part of the project titled ''Final disposal of radioactive wastes as seen from the viewpoint of ethical objectives''. The questions arising from the opinions, positions and publications presented in the report by GRS were to serve as a basis for an expert discussion or an interdisciplinary discussion forum for all concerned with the ethical aspects of an answerable approach to the final disposal of radioactive wastes. In April 2001 GRS held a one-day seminar at which leading ethicists and philosophers offered statements on the questions referred to above and joined in a discussion with experts on issues of final disposal. This report documents the questions that arose ahead of the workshop, the specialist lectures held there and a summary of the discussion results [de

  16. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1982-01-01

    This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

  17. Subseabed disposal safety analysis

    International Nuclear Information System (INIS)

    Koplick, C.M.; Kabele, T.J.

    1982-01-01

    This report summarizes the status of work performed by Analytic Sciences Corporation (TASC) in FY'81 on subseabed disposal safety analysis. Safety analysis for subseabed disposal is divided into two phases: pre-emplacement which includes all transportation, handling, and emplacement activities; and long-term (post-emplacement), which is concerned with the potential hazard after waste is safely emplaced. Details of TASC work in these two areas are provided in two technical reports. The work to date, while preliminary, supports the technical and environmental feasibility of subseabed disposal of HLW

  18. A world's dilemma upon which the sun never sets. The nuclear waste management strategy: Western European nation states and the United States of America. Part I of III

    International Nuclear Information System (INIS)

    Sanders, Mark Callis; Sanders, Charlotta E.

    2016-01-01

    The management of spent nuclear fuel (SNF) and nuclear wastes demands a strategy to provide for the safe, secure, and permanent disposal of radioactive material from power generation, defense uses, and other activities. Nation states have taken different paths to nuclear waste management and are at various stages of the development of a nuclear waste management strategy. A strategy may include developing a geological repository, nuclear fuel reprocessing, interim storage, as well as discussions of the creation of a multinational storage facility. The paper provides an overview of the strategy used (or being developed) and its place within the legal framework. The paper concludes that though each nation state must look outward to its shared international obligations, there must also be an inward reflection of a nation state to its own traditions, customs, and legal/law making regimes.

  19. Air quality and climate change, Topic 3 of the Model Inter-Comparison Study for Asia Phase III (MICS-Asia IIIPart 1: Overview and model evaluation

    Directory of Open Access Journals (Sweden)

    M. Gao

    2018-04-01

    Full Text Available Topic 3 of the Model Inter-Comparison Study for Asia (MICS-Asia Phase III examines how online coupled air quality models perform in simulating high aerosol pollution in the North China Plain region during wintertime haze events and evaluates the importance of aerosol radiative and microphysical feedbacks. A comprehensive overview of the MICS-Asia III Topic 3 study design, including descriptions of participating models and model inputs, the experimental designs, and results of model evaluation, are presented. Six modeling groups from China, Korea and the United States submitted results from seven applications of online coupled chemistry–meteorology models. Results are compared to meteorology and air quality measurements, including data from the Campaign on Atmospheric Aerosol Research Network of China (CARE-China and the Acid Deposition Monitoring Network in East Asia (EANET. The correlation coefficients between the multi-model ensemble mean and the CARE-China observed near-surface air pollutants range from 0.51 to 0.94 (0.51 for ozone and 0.94 for PM2.5 for January 2010. However, large discrepancies exist between simulated aerosol chemical compositions from different models. The coefficient of variation (SD divided by the mean can reach above 1.3 for sulfate in Beijing and above 1.6 for nitrate and organic aerosols in coastal regions, indicating that these compositions are less consistent from different models. During clean periods, simulated aerosol optical depths (AODs from different models are similar, but peak values differ during severe haze events, which can be explained by the differences in simulated inorganic aerosol concentrations and the hygroscopic growth efficiency (affected by varied relative humidity. These differences in composition and AOD suggest that future models can be improved by including new heterogeneous or aqueous pathways for sulfate and nitrate formation under hazy conditions, a secondary organic aerosol (SOA

  20. DECOVALEX III/BENCHPAR PROJECTS. The Thermal-Hydro-Mechanical Responses to a Glacial Cycle and their Potential Implications for Deep Geological Disposal of Nuclear Fuel Waste in a Fractured Crystalline Rock Mass. Report of BMT3/WP4

    Energy Technology Data Exchange (ETDEWEB)

    Chan, T.; Stanchell, F.W. [Atomic Energy of Canada Ltd, Toronto (Canada); Christiansson, R. [Swedish Nuclear Fuel and Waste Management Co., Figeholm (Sweden); Boulton, G.S. [Univ. of Edinburgh (United Kingdom). School of GeoSciences; Eriksson, L.O.; Vistrand, P.; Wallroth, T. [Chalmers Univ. of Technology, Goeteborg (Sweden). Dept. of Geology; Hartikainen, J. [Helsinki Univ. of Technology (Finland). Inst. of Mathematics; Jensen, M.R. [0ntario Power Generation, Toronto (Canada); Mas lvars, D. [Royal Inst. of Technology, Stockholm (Sweden). Land and Water Resources engineering

    2005-02-15

    A number of studies related to past and on-going deep repository performance assessments have identified glaciation/deglaciation as major future events in the next few hundred thousand years capable of causing significant impact on the long term performance of the repository system. Benchmark Test 3 (BMT3) of the international DECOVALEX III project has been designed to provide an illustrative example that explores the mechanical and hydraulic response of a fractured crystalline rock mass to a period of glaciation. The primary purpose of this numerical study is to investigate whether transient events associated with a glacial cycle could significantly influence the performance of a deep geological repository in a crystalline shield setting. A conceptual site-scale (tens of kilometres) hydro-mechanical (HM) model was assembled based primarily on site-specific litho-structural, hydrogeological and geomechanical data from the Whiteshell Research Area in the Canadian Shield, with simplification and generalization. Continental glaciological modelling of the Laurentide ice sheet through the last glacial cycle lasting approximately 100,000 years suggests that this site was glaciated at about 60 ka and between about 22.5 ka and 11 ka before present with maximum ice sheet thickness reaching 2,500 m and maximum basal water pressure head reaching 2000 m. The ice-sheet/drainage model was scaled down to generate spatially and temporally variable hydraulic and mechanical glaciated surface boundary conditions for site-scale subsurface HM modelling and permafrost modelling. Under extreme periglacial conditions permafrost was able to develop down to the assumed 500-m repository horizon. Two- and three-dimensional coupled HM finite-element simulations indicate: during ice-sheet advance there is rapid rise in hydraulic head, high transient hydraulic gradients and high groundwater velocities 2-3 orders of magnitude higher than under nonglacial conditions; surface water recharges deeper

  1. DECOVALEX III/BENCHPAR PROJECTS. The Thermal-Hydro-Mechanical Responses to a Glacial Cycle and their Potential Implications for Deep Geological Disposal of Nuclear Fuel Waste in a Fractured Crystalline Rock Mass. Report of BMT3/WP4

    International Nuclear Information System (INIS)

    Chan, T.; Stanchell, F.W.; Christiansson, R.; Boulton, G.S.; Mas lvars, D.

    2005-02-01

    A number of studies related to past and on-going deep repository performance assessments have identified glaciation/deglaciation as major future events in the next few hundred thousand years capable of causing significant impact on the long term performance of the repository system. Benchmark Test 3 (BMT3) of the international DECOVALEX III project has been designed to provide an illustrative example that explores the mechanical and hydraulic response of a fractured crystalline rock mass to a period of glaciation. The primary purpose of this numerical study is to investigate whether transient events associated with a glacial cycle could significantly influence the performance of a deep geological repository in a crystalline shield setting. A conceptual site-scale (tens of kilometres) hydro-mechanical (HM) model was assembled based primarily on site-specific litho-structural, hydrogeological and geomechanical data from the Whiteshell Research Area in the Canadian Shield, with simplification and generalization. Continental glaciological modelling of the Laurentide ice sheet through the last glacial cycle lasting approximately 100,000 years suggests that this site was glaciated at about 60 ka and between about 22.5 ka and 11 ka before present with maximum ice sheet thickness reaching 2,500 m and maximum basal water pressure head reaching 2000 m. The ice-sheet/drainage model was scaled down to generate spatially and temporally variable hydraulic and mechanical glaciated surface boundary conditions for site-scale subsurface HM modelling and permafrost modelling. Under extreme periglacial conditions permafrost was able to develop down to the assumed 500-m repository horizon. Two- and three-dimensional coupled HM finite-element simulations indicate: during ice-sheet advance there is rapid rise in hydraulic head, high transient hydraulic gradients and high groundwater velocities 2-3 orders of magnitude higher than under nonglacial conditions; surface water recharges deeper

  2. Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

    International Nuclear Information System (INIS)

    1995-11-01

    In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ''Migration and Biological Transfer of Radionuclides from Shallow Land Burial'' during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs

  3. Safety assessment of near surface radioactive waste disposal facilities: Model intercomparison using simple hypothetical data (Test Case 1). First report of NSARS. Part of the co-ordinated research programme on the safety assessment of near surface radioactive waste disposal facilities (NSARS)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    In many countries near surface disposal is the preferred option for the comparatively large volumes of low and intermediate level wastes which arise during nuclear power plant operations, nuclear fuel reprocessing and also for the wastes arising from radionuclide applications in hospitals and research establishments. Near surface disposal is also widely practised in the case of hazardous wastes from chemical industries. It is obviously necessary to show that waste disposal methods are safe and that both man and the environment will be adequately protected. Following a previous related Co-ordinated Research Programme (CRP) on ``Migration and Biological Transfer of Radionuclides from Shallow Land Burial`` during 1985 to 1989 (IAEA-TECDOC-579, Vienna, 1990), the issue of reliability of safety assessments was identified as an important topic for further support and development. A new CRP was formulated with the acronym NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study). This technical document is the first report of from the CRP and contains the intercomparison of results of the first test exercise (Test Case 1) on modelling of potential radiation exposures as a result of near surface disposal. Test Case 1 is based on entirely hypothetical data and includes consideration of exposures due to leaching and as a result of human intrusion into the site. Refs, figs and tabs.

  4. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Merrett, G.J.; Gillespie, P.A.

    1983-07-01

    This report discusses events and processes that could adversely affect the long-term stability of a nuclear fuel waste disposal vault or the regions of the geosphere and the biosphere to which radionuclides might migrate from such a vault

  5. Disposal leachates treatment

    Energy Technology Data Exchange (ETDEWEB)

    Coulomb, I.; Renaud, P. (SITA, 75 - Paris (France)); Courant, P. (FD Conseil, 78 - Gargenville (France)); Manem, J.; Mandra, V.; Trouve, E. (Lyonnaise des Eaux-Dumez, 78 - Le Pecq (France))

    1993-12-01

    Disposal leachates are complex and variable effluents. The use of a bioreactor with membranes, coupled with a reverse osmosis unit, gives a new solution to the technical burying centers. Two examples are explained here.

  6. Safe Disposal of Pesticides

    Science.gov (United States)

    ... Toxics Environmental Information by Location Greener Living Health Land, Waste, and Cleanup Lead Mold Pesticides Radon Science ... or www.earth911.com . Think before disposing of extra pesticides and containers: Never reuse empty pesticide containers. ...

  7. Disposal of Iodine-129

    International Nuclear Information System (INIS)

    Morgan, M.T.; Moore, J.G.; Devaney, H.E.; Rogers, G.C.; Williams, C.; Newman, E.

    1978-01-01

    One of the problems to be solved in the nuclear waste management field is the disposal of radioactive iodine-129, which is one of the more volatile and long-lived fission products. Studies have shown that fission products can be fixed in concrete for permanent disposal. Current studies have demonstrated that practical cementitious grouts may contain up to 18% iodine as barium iodate. The waste disposal criterion is based on the fact that harmful effects to present or future generations can be avoided by isolation and/or dilution. Long-term isolation is effective in deep, dry repositories; however, since penetration by water is possible, although unlikely, release was calculated based on leach rates into water. Further considerations have indicated that sea disposal on or in the ocean floor may be a more acceptable alternative

  8. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Allan, C.J.

    1993-01-01

    The Canadian concept for nuclear fuel waste disposal is based on disposing of the waste in a vault excavated 500-1000 m deep in intrusive igneous rock of the Canadian Shield. The author believes that, if the concept is accepted following review by a federal environmental assessment panel (probably in 1995), then it is important that implementation should begin without delay. His reasons are listed under the following headings: Environmental leadership and reducing the burden on future generations; Fostering public confidence in nuclear energy; Forestalling inaction by default; Preserving the knowledge base. Although disposal of reprocessing waste is a possible future alternative option, it will still almost certainly include a requirement for geologic disposal

  9. Integrated Disposal Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Located near the center of the 586-square-mile Hanford Site is the Integrated Disposal Facility, also known as the IDF.This facility is a landfill similar in concept...

  10. Shallow land disposal technology

    Energy Technology Data Exchange (ETDEWEB)

    Pillette-Cousin, L. [Nuclear Environment Technology Insitute, Taejon (Korea, Republic of Korea )

    1997-12-31

    This paper covers the radioactive waste management policy and regulatory framework, the characteristics of low and intermediate level radioactive waste, the characteristics of waste package, the waste acceptance criteria, the waste acceptance and related activities, the design of the disposal system, the organization of waste transportation, the operation feature, the safety assessment of the Centre de L`Aube, the post closure measures, the closure of the Centre de la Mache disposal facility, the licensing issues. 3 tabs., 7 figs.

  11. Shallow land disposal technology

    International Nuclear Information System (INIS)

    Pillette-Cousin, L.

    1997-01-01

    This paper covers the radioactive waste management policy and regulatory framework, the characteristics of low and intermediate level radioactive waste, the characteristics of waste package, the waste acceptance criteria, the waste acceptance and related activities, the design of the disposal system, the organization of waste transportation, the operation feature, the safety assessment of the Centre de L'Aube, the post closure measures, the closure of the Centre de la Mache disposal facility, the licensing issues. 3 tabs., 7 figs

  12. Disposal Of Waste Matter

    International Nuclear Information System (INIS)

    Kim, Jeong Hyeon; Lee, Seung Mu

    1989-02-01

    This book deals with disposal of waste matter management of soiled waste matter in city with introduction, definition of waste matter, meaning of management of waste matter, management system of waste matter, current condition in the country, collect and transportation of waste matter disposal liquid waste matter, industrial waste matter like plastic, waste gas sludge, pulp and sulfuric acid, recycling technology of waste matter such as recycling system of Black clawson, Monroe and Rome.

  13. Data base for radioactive waste management: review of low-level radioactive waste disposal history

    International Nuclear Information System (INIS)

    Clancy, J.J.; Gray, D.F.; Oztunali, O.I.

    1981-11-01

    This document is prepared in three volumes and provides part of the technical support to the draft environmental impact statement (NUREG-0782) on a proposed regulation, 10CFR Part 61, setting forth licensing requirements for land disposal of low level radioactive waste. Volume 1 is a summary and analysis of the history of low level waste disposal at both commercial and government disposal facilities

  14. Operation for Rokkasho Low Level Radioactive Waste Disposal Center

    International Nuclear Information System (INIS)

    Kamizono, Hideki

    2008-01-01

    The Rokkasho Low Level Radioactive Waste (LLW) Disposal Center is located in Oishitai, Rokkasho-mura, Kamikitagun, of Aomori Prefecture. This district is situated in the southern part of Shimohita Peninsula in the northeastern corner of the prefecture, which lies at the northern tip of Honshu, Japan's main island. The Rokkasho LLW Disposal Center deals with only LLW generated by operating of nuclear power plants. The No.1 and No.2 disposal facility are now in operation. The disposal facilities in operation have a total dispose capacity of 80,000m 3 (equivalent to 400,000 drums). Our final business scope is to dispose of radioactive waste corresponding to 600,000 m 3 (equivalent to 3000,000 drums). For No.1 disposal facility, we have been disposing of homogeneous waste, including condensed liquid waste, spent resin, solidified with cement and asphalt, etc. For No.2 disposal facility, we can bury a solid waste solidified with mortar, such as activated metals and plastics, etc. Using an improved construction technology for an artificial barrier, the concrete pits in No.2 disposal facility could be constructed more economical and spacious than that of No.1. Both No.1 and No.2 facility will be able to bury about 200,000 waste packages (drums) each corresponding to 40,000 m 3 . As of March 17, 2008, Approximately 200,00 waste drums summing up No.1 and No.2 disposal facility have been received from Nuclear power plants and buried. (author)

  15. Engineering, environmental and economic planning for tailings disposal

    International Nuclear Information System (INIS)

    Poellot, J.H.

    1982-01-01

    There are two principal points made in this paper. First, mining waste materials, or tailings, are geotechnical materials. Their behavior follows the principles of soil mechanics and is predictable by these principles. Second, proper disposal, meaning safe, environmentally sound and economical disposal, requires planning and recognizing waste disposal as part of the total mining system and process. In the development of these two principles, planning, design, and economic considerations of mine tailings are discussed

  16. PACE. A Program for Acquiring Competence in Entrepreneurship. Part III: Being an Entrepreneur. Unit C: Keeping the Business Records. Research and Development Series No. 194 C-3.

    Science.gov (United States)

    Ohio State Univ., Columbus. National Center for Research in Vocational Education.

    This three-part curriculum for entrepreneurship education is primarily for postsecondary level, including four-year colleges and adult education, but can be adapted for special groups or vocational teacher education. The emphasis of the eight instructional units in Part II is operating a business. Unit C focuses on record keeping. It introduces…

  17. Design of the disposal facility 2012

    International Nuclear Information System (INIS)

    Saanio, T.; Ikonen, A.; Keto, P.; Kirkkomaeki, T.; Kukkola, T.; Nieminen, J.; Raiko, H.

    2013-11-01

    The spent nuclear fuel accumulated from the nuclear power plants in Olkiluoto in Eurajoki and in Haestholmen in Loviisa will be disposed of in Olkiluoto. A facility complex will be constructed at Olkiluoto, and it will include two nuclear waste facilities according to Government Degree 736/2008. The nuclear waste facilities are an encapsulation plant, constructed to encapsulate spent nuclear fuel and a disposal facility consisting of an underground repository and other underground rooms and above ground service spaces. The repository is planned to be excavated to a depth of 400 - 450 meters. Access routes to the disposal facility are an inclined access tunnel and vertical shafts. The encapsulated fuel is transferred to the disposal facility in the canister lift. The canisters are transferred from the technical rooms to the disposal area via central tunnel and deposited in the deposition holes which are bored in the floors of the deposition tunnels and are lined beforehand with compacted bentonite blocks. Two parallel central tunnels connect all the deposition tunnels and these central tunnels are inter-connected at regular intervals. The solution improves the fire safety of the underground rooms and allows flexible backfilling and closing of the deposition tunnels in stages during the operational phase of the repository. An underground rock characterization facility, ONKALO, is excavated at the disposal level. ONKALO is designed and constructed so that it can later serve as part of the repository. The goal is that the first part of the disposal facility will be constructed under the building permit phase in the 2010's and operations will start in the 2020's. The fuel from 4 operating reactors as well the fuel from the fifth nuclear power plant under construction, has been taken into account in designing the disposal facility. According to the information from TVO and Fortum, the amount of the spent nuclear fuel is 5,440 tU. The disposal facility is being excavated

  18. Peatlands as Filters for Polluted Mine Water?—A Case Study from an Uranium-Contaminated Karst System in South Africa—Part III: Quantifying the Hydraulic Filter Component

    Directory of Open Access Journals (Sweden)

    Frank Winde

    2011-03-01

    Full Text Available As Part III of a four-part series on the filter function of peat for uranium (U, this paper focuses on the hydraulic component of a conceptual filter model introduced in Part II. This includes the quantification of water flow through the wetland as a whole, which was largely unknown and found to be significantly higher that anticipated. Apart from subaquatic artesian springs associated with the underlying karst aquifer the higher flow volumes were also caused by plumes of polluted groundwater moving laterally into the wetland. Real-time, quasi-continuous in situ measurements of porewater in peat and non-peat sediments indicate that rising stream levels (e.g., during flood conditions lead to the infiltration of stream water into adjacent peat deposits and thus allow for a certain proportion of flood water to be filtered. However, changes in porewater quality triggered by spring rains may promote the remobilization of possibly sorbed U.

  19. Waste disposal technologies: designs and evaluations

    International Nuclear Information System (INIS)

    Shaw, R.A.

    1987-01-01

    Many states and compacts are presently in the throes of considering what technology to select for their low level waste disposal site. Both the technical and economic aspects of disposal technology are important considerations in these decisions. It is also important that they be considered in the context of the entire system. In the case of a nuclear power plant, that system encompasses the various individual waste streams that contain radioactivity, the processing equipment which reduces the volume and/or alters the form in which the radioisotopes are contained, the packaging of the processed wastes in shipment, and finally its disposal. One further part of this is the monitoring that takes place in all stages of this operation. This paper discusses the results of some research that has been sponsored by EPRI with the principal contractor being Rogers and Associates Engineering Corporation. Included is a description of the distinguishing features found in disposal technologies developed in a generic framework, designs for a selected set of these disposal technologies and the costs which have been derived from these designs. In addition, a description of the early efforts towards defining the performance of these various disposal technologies is described. 5 figures, 1 table

  20. The Effect of early physiotherapy on the recovery of mandibular function after orthognathic surgery for Class III correction: part I--jaw-motion analysis.

    Science.gov (United States)

    Teng, Terry Te-Yi; Ko, Ellen Wen-Ching; Huang, Chiung Shing; Chen, Yu-Ray

    2015-01-01

    The aim of this prospective study was to compare the mandibular range of motion in Class III patients with and without early physiotherapy after orthognathic surgery (OGS). This study consisted of 63 Class III patients who underwent 2-jaw OGS. The experimental group comprised 31 patients who received early systematic physical rehabilitation. The control group consisted of 32 patients who did not have physical rehabilitation. Twelve variables of 3-dimensional (3D) jaw-motion analysis (JMA) were recorded before surgery (T1) and 6 weeks (T2) and 6 months (T3) after surgery. A 2-sample t test was conducted to compare the JMA results between the two groups at different time points. At T2, the JMA data were measured to be 77.5%-145.7% of presurgical values in the experimental group, and 60.3%-90.6% in the control group. At T3, the measurements were 112.2%-179.2% of presurgical values in the experimental group, and 77.6%-157.2% in the control group. The patients in the experimental group exhibited more favorable recovery than did those in the control group, from T1 to T2 and T1 to T3. However, after termination of physiotherapy, no significant difference in the extent of recovery was observed between groups up to 6 months after OGS. Copyright © 2014 European Association for Cranio-Maxillo-Facial Surgery. Published by Elsevier Ltd. All rights reserved.

  1. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part III; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del III

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  2. Safety analysis of RA reactor operation, I-II, Part I - RA reactor technical and operation characteristics; Analiza sigurnosti rada reaktora RA - I-III, I deo - Tehnicke i pogonske karakteristike reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    RA research reactor is a thermal, heavy water moderated system with graphite reflector having nominal power 6.5 MW. The 2% enriched metal uranium fuel in the reactor core produces mean thermal neutron flux of 2.9 10{sup 13} neutrons/cm{sup 2} s, and maximum neutron flux 5.5 10{sup 13} neutrons/cm{sup 2} s. main components of the reactor described in this report are: rector core, reflector, biological shield, heavy water cooling system, ordinary water cooling system, helium system, reactor control system, reactor safety system, dosimetry system, power supply system, and fuel transport system. Detailed reactor properties and engineering drawings of all the system are part of this volume.

  3. Richard III

    DEFF Research Database (Denmark)

    Lauridsen, Palle Schantz

    2017-01-01

    Kort analyse af Shakespeares Richard III med fokus på, hvordan denne skurk fremstilles, så tilskuere (og læsere) langt henad vejen kan føle sympati med ham. Med paralleller til Netflix-serien "House of Cards"......Kort analyse af Shakespeares Richard III med fokus på, hvordan denne skurk fremstilles, så tilskuere (og læsere) langt henad vejen kan føle sympati med ham. Med paralleller til Netflix-serien "House of Cards"...

  4. Rise, fall and resurrection of chromosome territories: a historical perspective Part II. Fall and resurrection of chromosome territories during the 1950s to 1980s. Part III. Chromosome territories and the functional nuclear architecture: experiments and m

    OpenAIRE

    T Cremer; C Cremer

    2009-01-01

    Part II of this historical review on the progress of nuclear architecture studies points out why the original hypothesis of chromosome territories from Carl Rabl and Theodor Boveri (described in part I) was abandoned during the 1950s and finally proven by compelling evidence forwarded by laser-uvmicrobeam studies and in situ hybridization experiments. Part II also includes a section on the development of advanced light microscopic techniques breaking the classical Abbe limit written for reade...

  5. Combustion chemistry and flame structure of furan group biofuels using molecular-beam mass spectrometry and gas chromatography - Part III: 2,5-Dimethylfuran.

    Science.gov (United States)

    Togbé, Casimir; Tran, Luc-Sy; Liu, Dong; Felsmann, Daniel; Oßwald, Patrick; Glaude, Pierre-Alexandre; Sirjean, Baptiste; Fournet, René; Battin-Leclerc, Frédérique; Kohse-Höinghaus, Katharina

    2014-03-01

    This work is the third part of a study focusing on the combustion chemistry and flame structure of furan and selected alkylated derivatives, i.e. furan in Part I, 2-methylfuran (MF) in Part II, and 2,5-dimethylfuran (DMF) in the present work. Two premixed low-pressure (20 and 40 mbar) flat argon-diluted (50%) flames of DMF were studied with electron-ionization molecular-beam mass spectrometry (EI-MBMS) and gas chromatography (GC) under two equivalence ratios (φ=1.0 and 1.7). Mole fractions of reactants, products, and stable and radical intermediates were measured as a function of the distance to the burner. Kinetic modeling was performed using a reaction mechanism that was further developed in the present series, including Part I and Part II. A reasonable agreement between the present experimental results and the simulation is observed. The main reaction pathways of DMF consumption were derived from a reaction flow analysis. Also, a comparison of the key features for the three flames is presented, as well as a comparison between these flames of furanic compounds and those of other fuels. An a priori surprising ability of DMF to form soot precursors (e.g. 1,3-cyclopentadiene or benzene) compared to less substituted furans and to other fuels has been experimentally observed and is well explained in the model.

  6. Combustion chemistry and flame structure of furan group biofuels using molecular-beam mass spectrometry and gas chromatography – Part III: 2,5-Dimethylfuran

    Science.gov (United States)

    Togbé, Casimir; Tran, Luc-Sy; Liu, Dong; Felsmann, Daniel; Oßwald, Patrick; Glaude, Pierre-Alexandre; Sirjean, Baptiste; Fournet, René; Battin-Leclerc, Frédérique; Kohse-Höinghaus, Katharina

    2013-01-01

    This work is the third part of a study focusing on the combustion chemistry and flame structure of furan and selected alkylated derivatives, i.e. furan in Part I, 2-methylfuran (MF) in Part II, and 2,5-dimethylfuran (DMF) in the present work. Two premixed low-pressure (20 and 40 mbar) flat argon-diluted (50%) flames of DMF were studied with electron-ionization molecular-beam mass spectrometry (EI-MBMS) and gas chromatography (GC) under two equivalence ratios (φ=1.0 and 1.7). Mole fractions of reactants, products, and stable and radical intermediates were measured as a function of the distance to the burner. Kinetic modeling was performed using a reaction mechanism that was further developed in the present series, including Part I and Part II. A reasonable agreement between the present experimental results and the simulation is observed. The main reaction pathways of DMF consumption were derived from a reaction flow analysis. Also, a comparison of the key features for the three flames is presented, as well as a comparison between these flames of furanic compounds and those of other fuels. An a priori surprising ability of DMF to form soot precursors (e.g. 1,3-cyclopentadiene or benzene) compared to less substituted furans and to other fuels has been experimentally observed and is well explained in the model. PMID:24518851

  7. Standing on shaky ground- US patent-eligibility of isolated DNA and genetic diagnostics after AMP v. USPTO - Part III (unsolved questions & subsequent case law)

    DEFF Research Database (Denmark)

    Minssen, Timo; Nilsson, David

    2012-01-01

    invigorated U.S. debate on patent eligibility, referring inter alia to the 2010 U.S. Supreme Court decision in Bilski v. Kappos and the pending certiorari in Prometheus v. Mayo (1). Before this background, Part I recited the complex procedural history of AMP v. USPTO (2) and summarized the underpinnings...... of the outcome, i.e. the three different opinions of the Federal Circuit judges Lourie, Moore & Bryson who comprised the panel (3). Part II continued the tale with a detailed analysis of the decision's practical implications (4), which is followed by a closer look on the chances for an ultimate Supreme Court...... decision in Prometheus v. Mayo. Part IV, which is to be published in issue 4, will finally offer a broader discussion of the recent US patent-eligibility developments from an innovation policy perspective including brief references to recent European developments (7). This will provide the basis...

  8. Landfill disposal risk assessment

    International Nuclear Information System (INIS)

    Mininni, G.; Passino, R.; Spinosa, L.

    1993-01-01

    Landfill disposal is the most used waste disposal system in Italy, due to its low costs and also to the great opposition of populations towards new incineration plants and the adjustment of the existing ones. Nevertheless, landfills may present many environmental problems as far as leachate and biogas are concerned directly influencing water, air and soil. This paper shows the most important aspects to be considered for a correct evaluation of environmental impacts caused by a landfill of urban wastes. Moreover, detection systems for on site control of pollution phenomena are presented and some measures for an optimal operation of a landfill are suggested

  9. Disposal of hazardous wastes

    International Nuclear Information System (INIS)

    Barnhart, B.J.

    1978-01-01

    The Fifth Life Sciences Symposium entitled Hazardous Solid Wastes and Their Disposal on October 12 through 14, 1977 was summarized. The topic was the passage of the National Resources Conservation and Recovery Act of 1976 will force some type of action on all hazardous solid wastes. Some major points covered were: the formulation of a definition of a hazardous solid waste, assessment of long-term risk, list of specific materials or general criteria to specify the wastes of concern, Bioethics, sources of hazardous waste, industrial and agricultural wastes, coal wastes, radioactive wastes, and disposal of wastes

  10. Reversible deep disposal

    International Nuclear Information System (INIS)

    2009-10-01

    This presentation, given by the national agency of radioactive waste management (ANDRA) at the meeting of October 8, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), describes the concept of deep reversible disposal for high level/long living radioactive wastes, as considered by the ANDRA in the framework of the program law of June 28, 2006 about the sustainable management of radioactive materials and wastes. The document presents the social and political reasons of reversibility, the technical means considered (containers, disposal cavities, monitoring system, test facilities and industrial prototypes), the decisional process (progressive development and blocked off of the facility, public information and debate). (J.S.)

  11. Radioactive waste (disposal)

    International Nuclear Information System (INIS)

    Jenkin, P.

    1985-01-01

    The disposal of low- and intermediate-level radioactive wastes was discussed. The following aspects were covered: public consultation on the principles for assessing disposal facilities; procedures for dealing with the possible sites which the Nuclear Industry Radioactive Waste Executive (NIREX) had originally identified; geological investigations to be carried out by NIREX to search for alternative sites; announcement that proposal for a site at Billingham is not to proceed further; NIREX membership; storage of radioactive wastes; public inquiries; social and environmental aspects; safety aspects; interest groups; public relations; government policies. (U.K.)

  12. Swiss guideline: Protection objectives for the disposal of radioactive waste

    International Nuclear Information System (INIS)

    Zurkinden, A.

    1994-01-01

    The Swiss guideline R-21 establishing the protection objectives for the disposal of radioactive waste has been reviewed and amended in order to adapt it to improvements made in the field of radioactive waste disposal. In an introductory part, the new guideline states the overall objective of radioactive waste disposal and the associated principles which have to be observed. The guideline then establishes the safety requirements applied to a geological disposal facility. These safety requirements are formulated as protection goals for the whole disposal system and not as specific criteria applying to the system components. The guideline gives finally a series of explanatory comments and indications concerning the conduct of the safety assessment for a disposal facility

  13. Daily disposable contact lens prescribing around the world.

    Science.gov (United States)

    Efron, Nathan; Morgan, Philip B; Helland, Magne; Itoi, Motozumi; Jones, Deborah; Nichols, Jason J; van der Worp, Eef; Woods, Craig A

    2010-10-01

    Daily disposable contact lenses were introduced into the market 16 years ago. Data that we have gathered from annual contact lens fitting surveys conducted in Australia, Canada, Japan, The Netherlands, Norway, the UK and the USA between 2000 and 2008 indicates an overall increase in daily disposable lens fitting during this period. Daily disposable lenses are especially popular in Japan, Norway and the UK. There is a trend for these lenses to be fitted on a part-time basis. Males are over-represented in daily disposable lens fitting-a trend that is especially evident in Canada. Daily disposable lens wearers are about two years younger than wearers of reusable lenses in Japan and The Netherlands. The convenience and health benefits of daily disposable lenses are expected to fuel continued growth in this sector. Copyright (c) 2010 British Contact Lens Association. Published by Elsevier Ltd. All rights reserved.

  14. Disposal of slightly contaminated radioactive wastes from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Minns, J.L. [Nuclear Regulatory Commission, Washington, DC (United States)

    1995-02-01

    With regard to the disposal of solid wastes, nuclear power plants basically have two options, disposal in a Part 61 licensed low-level waste site, or receive approval pursuant to 20.2002 for disposal in a manner not otherwise authorized by the NRC. Since 1981, the staff has reviewed and approved 30 requests for disposal of slightly contaminated radioactive materials pursuant to Section 20.2002 (formerly 20.302) for nuclear power plants located in non-Agreement States. NRC Agreement States have been delegated the authority for reviewing and approving such disposals (whether onsite or offsite) for nuclear power plants within their borders. This paper describes the characteristics of the waste disposed of, the review process, and the staff`s guidelines.

  15. The Hazardous Waste/Mixed Waste Disposal Facility

    International Nuclear Information System (INIS)

    Bailey, L.L.

    1991-01-01

    The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996

  16. A complex study on the reliability assessment of the containment of a PWR. Part III.- Structural reliability assessment under internal and external loading conditions

    International Nuclear Information System (INIS)

    Bauer, J.; Schueller, G.I.

    1977-01-01

    The first part of the analysis is concerned with the determination of the failure probability of the steel hull under internal load conditions. Two independent failure criteria are the basis for this calculation; the first one being the ultimate yield which is actually an instability condition and the second one being the fracture condition as described in Part II of the paper. Both the global and the local failure probabilities are investigated. The second part of the analysis is concerned with the external load case of earthquake. As it has already been described in Part I the probability of occurrence of a LOCA, given an earthquake has been considered in connection with the probable damage which the steel hull might experience during the earthquake. In other words the survival probability of the hull with deteriorated resistance is calculated, taking into account the frequencies of occurrence of the various events. The third part of the analysis is concerned with the reliability determination of the reinforced concrete dome structure, which is supposed to protect, the steel hull against external load conditions such as airplane crash and external pressure waves (the latter covering the load case of tornado occurrence). The reliability analysis of the reinforced concrete structure under earthquake loading is performed by utilizing the time-history method. Some aspects of the drawbacks of the response spectra method -when used in a risk analysis- are pointed out. The probability distribution of the concrete strength as determined under intermediate strain rate as described in Part II is utilized in the analysis. Finally the remaining two external load cases are discussed in light of their use in a reliability analysis and with respect to their frequency of occurrence and the probability distribution of their load intensities. The reliability demonstration is performed using the containment structure of the PWR-plant 'Biblis B' which is locate

  17. PARDISEKO III

    International Nuclear Information System (INIS)

    Jordan, H.; Sack, C.

    1975-05-01

    This report gives a detailed description of the latest version of the PARDISEKO code, PARDISEKO III, with particular emphasis on the numerical and programming methods employed. The physical model and its relation to nuclear safety as well as a description and the results of confirming experiments are treated in detail in the Karlsruhe Nuclear Research Centre report KFK-1989. (orig.) [de

  18. Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part III : Radioactive Waste Management and Environment

    International Nuclear Information System (INIS)

    Kamsul Abraha; Yateman Arryanto; Sri Jauhari S; Agus Taftazani; Kris Tri Basuki; Djoko Sardjono, Ign.; Sukarsono, R.; Samin; Syarip; Suryadi, MS; Sardjono, Y.; Tri Mardji Atmono; Dwiretnani Sudjoko; Tjipto Sujitno, BA.

    2007-08-01

    The Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Accelerator Technology and Material Process, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. The Meeting was held in Yogyakarta on July 10, 2007. The proceedings contains papers presented on the meeting about Radioactive Waste Management and Environment and there are 25 papers which have separated index. The proceedings is the third part of the three parts which published in series. (PPIN)

  19. Children Who Desperately Want To Read, but Are Not Working at Grade Level: Use Movement Patterns as "Windows" To Discover Why. Part III: The Frontal Midline.

    Science.gov (United States)

    Corso, Marjorie

    A longitudinal research study observed 30 children between the ages of infancy and elementary age to determine if using large muscle motor patterns to master the three identified midlines that concur with the body planes used in anatomy is reflected in academic classroom learning levels. This third part of the study focused on the frontal midline.…

  20. Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

    International Nuclear Information System (INIS)

    2003-12-01

    Radioactive waste must be managed safely, consistent with internationally agreed safety standards. The disposal method chosen for the waste should be commensurate with the hazard and longevity of the waste. Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. The term 'near surface disposal' encompasses a wide range of design options, including disposal in engineered structures at or just below ground level, disposal in simple earthen trenches a few metres deep, disposal in engineered concrete vaults, and disposal in rock caverns several tens of metres below the surface. The use of a near surface disposal option requires design and operational measures to provide for the protection of human health and the environment, both during operation of the disposal facility and following its closure. To ensure the safety of both workers and the public (both in the short term and the long term), the operator is required to design a comprehensive waste management system for the safe operation and closure of a near surface disposal facility. Part of such a system is to establish criteria for accepting waste for disposal at the facility. The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures and in addition, to prevent or limit hazards, which could arise from non-radiological causes. Waste acceptance criteria include limits on radionuclide content concentration in waste materials, and radionuclide amounts in packages and in the repository as a whole. They also include limits on quantity of free liquids, requirements for exclusion of chelating agents and pyrophoric materials, and specifications of the characteristics of the waste containers. Largely as a result of problems encountered at some disposal facilities operated in the past, in 1985 the IAEA published guidance on generic acceptance

  1. A simple, fast, and accurate thermodynamic-based approach for transfer and prediction of gas chromatography retention times between columns and instruments Part III: Retention time prediction on target column.

    Science.gov (United States)

    Hou, Siyuan; Stevenson, Keisean A J M; Harynuk, James J

    2018-03-27

    This is the third part of a three-part series of papers. In Part I, we presented a method for determining the actual effective geometry of a reference column as well as the thermodynamic-based parameters of a set of probe compounds in an in-house mixture. Part II introduced an approach for estimating the actual effective geometry of a target column by collecting retention data of the same mixture of probe compounds on the target column and using their thermodynamic parameters, acquired on the reference column, as a bridge between both systems. Part III, presented here, demonstrates the retention time transfer and prediction from the reference column to the target column using experimental data for a separate mixture of compounds. To predict the retention time of a new compound, we first estimate its thermodynamic-based parameters on the reference column (using geometric parameters determined previously). The compound's retention time on a second column (of previously determined geometry) is then predicted. The models and the associated optimization algorithms were tested using simulated and experimental data. The accuracy of predicted retention times shows that the proposed approach is simple, fast, and accurate for retention time transfer and prediction between gas chromatography columns. © 2018 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  2. Regulatory control of solid low level radioactive waste disposal in the UK

    International Nuclear Information System (INIS)

    Newstead, S.; Schwemlein, P.

    1998-01-01

    The following topics are described: (i) regulatory authorities; (ii) inspection; (iii) waste categories; (iv) disposal routes for low level waste; (v) inspection of disposal routes; (vi) waste quality checking; (vii) reporting and application of results; and (viii) European Network activities. (P.A.)

  3. 36 CFR 6.5 - Solid waste disposal sites in operation on September 1, 1984.

    Science.gov (United States)

    2010-07-01

    ... Insecticide, Fungicide and Rodenticide Act (7 U.S.C. 136 et seq.); (vi) Sludge from a waste treatment plant... leased by the operator; and (iii) the solid waste disposal site lacks road, rail, or adequate water... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal sites in...

  4. Radioactive waste disposal package

    Science.gov (United States)

    Lampe, Robert F.

    1986-11-04

    A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

  5. Manufacture of disposal canisters

    International Nuclear Information System (INIS)

    Nolvi, L.

    2009-12-01

    The report summarizes the development work carried out in the manufacturing of disposal canister components, and present status, in readiness for manufacturing, of the components for use in assembly of spent nuclear fuel disposal canister. The disposal canister consist of two major components: the nodular graphite cast iron insert and overpack of oxygen-free copper. The manufacturing process for copper components begins with a cylindrical cast copper billet. Three different manufacturing processes i.e. pierce and draw, extrusion and forging are being developed, which produce a seamless copper tube or a tube with an integrated bottom. The pierce and draw process, Posiva's reference method, makes an integrated bottom possible and only the lid requires welding. Inserts for BWR-element are cast with 12 square channels and inserts for VVER 440-element with 12 round channels. Inserts for EPR-elements have four square channels. Casting of BWR insert type has been studied so far. Experience of casting inserts for PWR, which is similar to the EPR-type, has been got in co-operation with SKB. The report describes the processes being developed for manufacture of disposal canister components and some results of the manufacturing experiments are presented. Quality assurance and quality control in manufacture of canister component is described. (orig.)

  6. Oil ''rig'' disposal

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    A comparison of the environmental impacts of disposing of the Brent Spar oil platform on land and at sea is presented, with a view to establishing the best decommissioning option in the light of recent controversy. The document is presented as an aid to comprehension of the scientific and engineering issues involved for Members of Parliament. (UK)

  7. Nuclear waste disposal

    International Nuclear Information System (INIS)

    Lindblom, U.; Gnirk, P.

    1982-01-01

    The subject is discussed under the following headings: the form and final disposal of nuclear wastes; the natural rock and groundwater; the disturbed rock and the groundwater; long-term behavior of the rock and the groundwater; nuclear waste leakage into the groundwater; what does it all mean. (U.K.)

  8. Nanomaterial disposal by incineration

    Science.gov (United States)

    As nanotechnology-based products enter into widespread use, nanomaterials will end up in disposal waste streams that are ultimately discharged to the environment. One possible end-of-life scenario is incineration. This review attempts to ascertain the potential pathways by which ...

  9. Plumbing and Sewage Disposal.

    Science.gov (United States)

    Sutliff, Ronald D.; And Others

    This self-study course is designed to familiarize Marine enlisted personnel with the principles of plumbing and sewage disposal used by Marine Hygiene Equipment Operators to perform their mission. The course contains three study units. Each study unit begins with a general objective, which is a statement of what the student should learn from the…

  10. Radwaste treatment and disposal

    International Nuclear Information System (INIS)

    Ehn, L.; Breza, M.; Pekar, A.

    2000-01-01

    In this lecture is given the basic information, that is concerning on the RAW treatment and long term disposal of the treated RAW in repository at Mochovce. Then here is given the basic technical and technological information, that is concerning bituminization, plant, the vitrification unit, center for the RAW-treatment (BSC) and repository at Mochovce. (authors)

  11. Waste disposal package

    Science.gov (United States)

    Smith, M.J.

    1985-06-19

    This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

  12. Simulación de la fluencia en caliente de un acero microaleado con un contenido medio de carbono. III parte. Ecuaciones constitutivas

    Directory of Open Access Journals (Sweden)

    Cabrera, J. M.

    1997-08-01

    Full Text Available According to the part 1 of this work the constitutive equations of the hot flow behaviour of a commercial microalloyed steel have been obtained. For this purpose, the uniaxial hot compression tests described in the part 2 were employed. Tests were carried out over a range of 5 orders of magnitude in strain rate and 300 °C of temperature. Experimental results are compared with the theoretical model introduced in the first part of this study. It is concluded that deviations between experimental and theoretical curves are lower than 10 %. It is shown that the classical hiperbolic sine constitutive equation described accurately the experimental behaviour provided that stresses are normalized by the Young's modulus and strain rates by the self-diffusion coefficient. An internal stress must also be introduced in the latter equation when the initial grain size is fine enough.

    Siguiendo el planteamiento teórico efectuado en la I parte de este trabajo, se determinaron las ecuaciones constitutivas del comportamiento a la deformación en caliente de un acero comercial microaleado con un contenido medio de carbono. Para este objetivo se emplearon los ensayos de compresión uniaxial en caliente ya descritos en la II parte, los cuales se efectuaron en un rango de cinco órdenes de magnitud en velocidad de deformación y 300 °C de temperatura. Se comparan los resultados experimentales con el modelo teórico introducido en la I parte y se verifica que el error es inferior al 10 %. Se comprobó que la clásica ecuación del seno hiperbólico podía describir con precisión el comportamiento observado siempre y cuando las tensiones se normalicen por el módulo de Young, las velocidades de deformación por el coeficiente de autodifusión de la austenita, y se considere un efecto adicional sobre la tensión cuando el tamaño de grano inicial sea suficientemente fino.

  13. Mined Geologic Disposal System Requirements Document

    International Nuclear Information System (INIS)

    1993-01-01

    This Mined Geologic Disposal System Requirements document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) and commercial and defense high level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The development and control of the MGDS-RD is quality-affecting work and is subject to the Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) Quality Assurance Requirements Document (QARD). As part of the technical requirements baseline, it is also subject to Baseline Management Plan controls. The MGDS-RD and the other program-level requirements documents have been prepared and managed in accordance with the Technical Document Preparation Plan (TDPP) for the Preparation of System Requirements Documents

  14. Geological disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Sato, Tsutomu

    2000-01-01

    For disposing method of radioactive wastes, various feasibilities are investigated at every nations and international organizations using atomic energy, various methods such as disposal to cosmic space, disposal to ice sheet at the South Pole and so forth, disposal into ocean bed or its sediments, and disposal into ground have been examined. It is, however, impossible institutionally at present, to have large risk on accident in the disposal to cosmic space, to be prohibited by the South Pole Treaty on the disposal to ice sheet at the South Pole, and to be prohibited by the treaty on prevention of oceanic pollution due to the disposal of wastes and so forth on the disposal into oceanic bed or its sediments (London Treaty). Against them, the ground disposal is thought to be the most powerful method internationally from some reasons shown as follows: no burden to the next generation because of no need in long-term management by human beings; safety based on scientific forecasting; disposal in own nation; application of accumulated technologies on present mining industries, civil engineering, and so forth to construction of a disposal facility; and, possibility to take out wastes again, if required. For the ground disposal, wastes must be buried into the ground and evaluated their safety for long terms. It is a big subject to be taken initiative by engineers on geoscience who have quantified some phenomena in the ground and at ultra long term. (G.K.)

  15. The effect of early physiotherapy on the recovery of mandibular function after orthognathic surgery for class III correction. Part II: electromyographic activity of masticatory muscles.

    Science.gov (United States)

    Ko, Ellen Wen-Ching; Teng, Terry Te-Yi; Huang, Chiung Shing; Chen, Yu-Ray

    2015-01-01

    The study was conducted to evaluate the effect of early physical rehabilitation by comparing the differences of surface electromyographic (sEMG) activity in the masseter and anterior temporalis muscles after surgical correction of skeletal class III malocclusion. The prospective study included 63 patients; the experimental groups contained 31 patients who received early systematic physical rehabilitation; the control group (32 patients) did not receive physiotherapy. The amplitude of sEMG in the masticatory muscles reached 72.6-121.3% and 37.5-64.6% of pre-surgical values in the experimental and control groups respectively at 6 weeks after orthognathic surgery (OGS). At 6 months after OGS, the sEMG reached 135.1-233.4% and 89.6-122.5% of pre-surgical values in the experimental and control groups respectively. Most variables in the sEMG examination indicated that recovery of the masticatory muscles in the experimental group was better than the control group as estimated in the early phase (T1 to T2) and the total phase (T1 to T3); there were no significant differences between the mean recovery percentages in the later phase (T2 to T3). Early physical rehabilitative therapy is helpful for early recovery of muscle activity in masticatory muscles after OGS. After termination of physical therapy, no significant difference in recovery was indicated in patients with or without early physiotherapy. Copyright © 2014 European Association for Cranio-Maxillo-Facial Surgery. Published by Elsevier Ltd. All rights reserved.

  16. The removal of toxic metals from liquid effluents by ion exchange resins. Part IV: Chromium(III)/H+ /Lewatit SP112; La eliminación de metales tóxicos presentes en efluentes líquidos mediante resinas de cambio iónico. Parte IV: cromo(III)/H+/Lewatit SP112

    Energy Technology Data Exchange (ETDEWEB)

    Alguacil, F.J.

    2017-09-01

    This investigation presented results on the removal of chromium(III), from aqueous solution in the 0-5 pH range, using Lewatit SP112 cationic exchange resin. Several aspects affecting the ion exchange process were evaluated, including: the influence of the stirring speed, temperature, pH of the solution, resin dosage and aqueous ionic strength. The selectivity of the system was tested against the presence of other metals in the aqueous solution, whereas the removal of chromium(III) from solutions was compared with results obtained using multiwalled carbon nanotubes as adsorbents. From the batch experimental data, best fit of the results is obtained with the Langmuir model, whereas the ion exchange process is best explained by the pseudo-second order model, moreover, experimental data responded well to the film-diffusion controlled model. Elution of the chromium(III) loaded into the resin is well accomplished by the use of sodium hydroxide solutions. [Spanish] En este trabajo se presentan los resultados obtenidos en la eliminación de cromo(III) de disoluciones acuosas (pH 0-5) mediante la resina de intercambio catiónico Lewatit SP112. Se han investigado algunas variables que pueden afectar al sistema: influencia de la agitación, temperatura, pH y fuerza iónica del medio acuoso y cantidad de resina; también se ha investigado acerca de la selectividad del sistema cuando otros metales están presentes en el medio acuoso, comparándose los resultados de la eliminación del cromo(III) usando la resina con los resultados obtenidos cuando se emplea otro adsorbente como son los nanotubos de carbono de pared múltiple. Los resultados experimentales indican que la carga del cromo(III) en la resina responde mejor al modelo de Langmuir, mientras que los modelos cinéticos indican que la carga del metal en la resina responde al modelo de pseudo-segundo orden y difusión en la capa límite. La elución del cromo(III) se realiza con disoluciones de hidróxid.

  17. Fermilab III

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The total ongoing plans for Fermilab are wrapped up in the Fermilab III scheme, centrepiece of which is the proposal for a new Main Injector. The Laboratory has been awarded a $200,000 Illinois grant which will be used to initiate environmental assessment and engineering design of the Main Injector, while a state review panel recommended that the project should also benefit from $2 million of funding

  18. Fermilab III

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1990-09-15

    The total ongoing plans for Fermilab are wrapped up in the Fermilab III scheme, centrepiece of which is the proposal for a new Main Injector. The Laboratory has been awarded a $200,000 Illinois grant which will be used to initiate environmental assessment and engineering design of the Main Injector, while a state review panel recommended that the project should also benefit from $2 million of funding.

  19. HLW disposal dilemma

    International Nuclear Information System (INIS)

    Andrei, V.; Glodeanu, F.

    2003-01-01

    The radioactive waste is an inevitable residue from the use of radioactive materials in industry, research and medicine, and from the operation of generating electricity nuclear power stations. The management and disposal of such waste is therefore an issue relevant to almost all countries. Undoubtedly the biggest issue concerning radioactive waste management is that of high level waste. The long-lived nature of some types of radioactive wastes and the associated safety implications of disposal plans have raised concern amongst those who may be affected by such facilities. For these reasons the subject of radioactive waste management has taken on a high profile in many countries. Not one Member State in the European Union can say that their high level waste will be disposed of at a specific site. Nobody can say 'that is where it is going to go'. Now, there is a very broad consensus on the concept of geological disposal. The experts have little, if any doubt that we could safely dispose of the high level wastes. Large sectors of the public continue to oppose to most proposals concerning the siting of repositories. Given this, it is increasingly difficult to get political support, or even political decisions, on such sites. The failure to advance to the next step in the waste management process reinforces the public's initial suspicion and resistance. In turn, this makes the political decisions even harder. In turn, this makes the political decisions even harder. The management of spent fuel from nuclear power plant became a crucial issue, as the cooling pond of the Romanian NPP is reaching saturation. During the autumn of 2000, the plant owner proceeded with an international tendering process for the supply of a dry storage system to be implemented at the Cernavoda station to store the spent fuel from Unit 1 and eventually from Unit 2 for a minimum period of 50 years. The facility is now in operation. As concern the disposal of the spent fuel, the 'wait and see

  20. Salt disposal: Paradox Basin, Utah

    International Nuclear Information System (INIS)

    1983-04-01

    This report presents the findings of a study conducted for the National Waste Terminal Storage (NWTS) Program. Permanent disposal options are examined for salt resulting from the excavation of a waste repository in the bedded salt deposits of the Paradox Basin of southeastern Utah. The study is based on a repository salt backfill compaction of 60% of the original density which leaves a total of 8 million tons of 95% pure salt to be disposed of over a 30-year period. The feasibility, impacts, and mitigation methods are examined for five options: commercial disposal, permanent onsite surface disposal, permanent offsite disposal, deepwell injection, and ocean and Great Salt Lake disposal. The study concludes the following: Commercial marketing of all repository salt would require a subsidy for transportation to major salt markets. Permanent onsite surface storage is both economically and technically feasible. Permanent offsite disposal is technically feasible but would incur additional transportation costs. Selection of an offsite location would provide a means of mitigating impacts associated with surface storage at the repository site. Deepwell injection is an attractive disposal method; however, the large water requirement, high cost of development, and poor performance of similar operating brine disposal wells eliminates this option from consideration as the primary means of disposal for the Paradox Basin. Ocean disposal is expensive because of high transportation cost. Also, regulatory approval is unlikely. Ocean disposal should be eliminated from further consideration in the Paradox Basin. Great Salt Lake disposal appears to be technically feasible. Great Salt Lake disposal would require state approval and would incur substantial costs for salt transportation. Permanent onsite disposal is the least expensive method for disposal of all repository salt

  1. Method of disposing radioactive wastes

    International Nuclear Information System (INIS)

    Isozaki, Kei.

    1983-01-01

    Purpose : To enable safety ocean disposal of radioactive wastes by decreasing the leaching rate of radioactive nucleides, improving the quick-curing nature and increasing the durability. Method : A mixture comprising 2 - 20 parts by weight of alkali metal hydroxide and 100 parts by weight of finely powdered aqueous slags from a blast furnace is added to radioactive wastes to solidify them. In the case of medium or low level radioactive wastes, the solidification agent is added by 200 parts by weight to 100 parts by weight of the wastes and, in the case of high level wastes, the solidification agent is added in such an amount that the wastes occupy about 20% by weight in the total of the wastes and the solidification agent. Sodium hydroxide used as the alkali metal hydroxide is partially replaced with sodium carbonate, a water-reducing agent such as lignin sulfonate is added to improve the fluidity and suppress the leaching rate and the wastes are solidified in a drum can. In this way, corrosions of the vessel can be suppressed by the alkaline nature and the compression strength, heat stability and the like of the product also become excellent. (Sekiya, K.)

  2. Geological disposal of nuclear waste

    International Nuclear Information System (INIS)

    1979-01-01

    Fourteen papers dealing with disposal of high-level radioactive wastes are presented. These cover disposal in salt deposits, geologic deposits and marine disposal. Also included are papers on nuclear waste characterization, transport, waste processing technology, and safety analysis. All of these papers have been abstracted and indexed

  3. A Fully Nonmetallic Gas Turbine Engine Enabled by Additive Manufacturing of Ceramic Composites. Part III; Additive Manufacturing and Characterization of Ceramic Composites

    Science.gov (United States)

    Halbig, Michael C.; Grady, Joseph E.; Singh, Mrityunjay; Ramsey, Jack; Patterson, Clark; Santelle, Tom

    2015-01-01

    This publication is the third part of a three part report of the project entitled "A Fully Nonmetallic Gas Turbine Engine Enabled by Additive Manufacturing" funded by NASA Aeronautics Research Institute (NARI). The objective of this project was to conduct additive manufacturing to produce ceramic matrix composite materials and aircraft engine components by the binder jet process. Different SiC powders with median sizes ranging from 9.3 to 53.0 microns were investigated solely and in powder blends in order to maximize powder packing. Various infiltration approaches were investigated to include polycarbosilane (SMP-10), phenolic, and liquid silicon. Single infiltrations of SMP-10 and phenolic only slightly filled in the interior. When the SMP-10 was loaded with sub-micron sized SiC powders, the infiltrant gave a much better result of filling in the interior. Silicon carbide fibers were added to the powder bed to make ceramic matrix composite materials. Microscopy showed that the fibers were well distributed with no preferred orientation on the horizontal plane and fibers in the vertical plane were at angles as much as 45deg. Secondary infiltration steps were necessary to further densify the material. Two to three extra infiltration steps of SMP-10 increased the density by 0.20 to 0.55 g/cc. However, the highest densities achieved were 2.10 to 2.15 g/cc. Mechanical tests consisting of 4 point bend tests were conducted. Samples from the two CMC panels had higher strengths and strains to failure than the samples from the two nonfiber reinforced panels. The highest strengths were from Set N with 65 vol% fiber loading which had an average strength of 66 MPa. Analysis of the fracture surfaces did not reveal pullout of the reinforcing fibers. Blunt fiber failure suggested that there was not composite behavior. The binder jet additive manufacturing method was used to also demonstrate the fabrication of turbine engine vane components of two different designs and sizes. The

  4. The federal structure: Can Congress commmandeer Nevada to participate in its federal high level waste disposal program?

    International Nuclear Information System (INIS)

    Davenport, J.

    1993-01-01

    This article examines the national disposal system for nuclear waste under the Nuclear Waste Policy Act (NWPA), as enacted in 1982 and amended in 1987 and 1992, focusing particularly on the constitutionality of the Act's open-quotes notice of disapprovalclose quotes and open-quotes congressional overrideclose quotes provisions. Part I of this article describes the notice of disapproval and congressional override provisions of the NWPA, including a brief analysis of their legislative history. Part II discusses the advantages of the federal structure as a protection against the exercise of autocratic congressional power, and studies the United States Supreme Court's approach to federalism in two recent cases. Part III addresses Nevada's experience under the NWPA. Parts IV and V analyze the constitutionality of the notice of disapproval and congressional override provisions of the NWPA in light of these two Supreme Court holdings. Part VI discusses the open-quotes environmental subsidyclose quotes imposed by the NWPA. Part VII concludes the article with a more practical, workable and constitutionally-defensible alternative to the existing waste disposal siting process

  5. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part III

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  6. Stochastic foundations of undulatory transport phenomena: generalized Poisson-Kac processes—part III extensions and applications to kinetic theory and transport

    Science.gov (United States)

    Giona, Massimiliano; Brasiello, Antonio; Crescitelli, Silvestro

    2017-08-01

    This third part extends the theory of Generalized Poisson-Kac (GPK) processes to nonlinear stochastic models and to a continuum of states. Nonlinearity is treated in two ways: (i) as a dependence of the parameters (intensity of the stochastic velocity, transition rates) of the stochastic perturbation on the state variable, similarly to the case of nonlinear Langevin equations, and (ii) as the dependence of the stochastic microdynamic equations of motion on the statistical description of the process itself (nonlinear Fokker-Planck-Kac models). Several numerical and physical examples illustrate the theory. Gathering nonlinearity and a continuum of states, GPK theory provides a stochastic derivation of the nonlinear Boltzmann equation, furnishing a positive answer to the Kac’s program in kinetic theory. The transition from stochastic microdynamics to transport theory within the framework of the GPK paradigm is also addressed.

  7. Stochastic foundations of undulatory transport phenomena: generalized Poisson–Kac processes—part III extensions and applications to kinetic theory and transport

    International Nuclear Information System (INIS)

    Giona, Massimiliano; Brasiello, Antonio; Crescitelli, Silvestro

    2017-01-01

    This third part extends the theory of Generalized Poisson–Kac (GPK) processes to nonlinear stochastic models and to a continuum of states. Nonlinearity is treated in two ways: (i) as a dependence of the parameters (intensity of the stochastic velocity, transition rates) of the stochastic perturbation on the state variable, similarly to the case of nonlinear Langevin equations, and (ii) as the dependence of the stochastic microdynamic equations of motion on the statistical description of the process itself (nonlinear Fokker–Planck–Kac models). Several numerical and physical examples illustrate the theory. Gathering nonlinearity and a continuum of states, GPK theory provides a stochastic derivation of the nonlinear Boltzmann equation, furnishing a positive answer to the Kac’s program in kinetic theory. The transition from stochastic microdynamics to transport theory within the framework of the GPK paradigm is also addressed. (paper)

  8. The borehole disposal of spent sources (BOSS)

    International Nuclear Information System (INIS)

    Heard, R.G.

    2002-01-01

    is believed to be a more severe test of the disposal concept than any other type of spent source. Phase III, which has as yet not started will, look at developing guidelines for implementation of the concept and will end with a practical demonstration of the concept. (author)

  9. Preliminary disposal limits, plume interaction factors, and final disposal limits

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2018-01-11

    In the 2008 E-Area Performance Assessment (PA), each final disposal limit was constructed as the product of a preliminary disposal limit and a plume interaction factor. The following mathematical development demonstrates that performance objectives are generally expected to be satisfied with high confidence under practical PA scenarios using this method. However, radionuclides that experience significant decay between a disposal unit and the 100-meter boundary, such as H-3 and Sr-90, can challenge performance objectives, depending on the disposed-of waste composition, facility geometry, and the significance of the plume interaction factor. Pros and cons of analyzing single disposal units or multiple disposal units as a group in the preliminary disposal limits analysis are also identified.

  10. Disposal of fly ash

    International Nuclear Information System (INIS)

    Singh, B.; Foley, C.

    1991-01-01

    Theoretical arguments and pilot plant results have shown that the transport of fly-furnace ash from the power station to the disposal area as a high concentration slurry is technically viable and economically attractive. Further, lack of free water, when transported as a high concentration slurry, offers significant advantages in environmental management and rehabilitation of the disposal site. This paper gives a basis for the above observations and discusses the plans to exploit the above advantages at the Stanwell Power Station. (4 x 350 MWe). This will be operated by the Queensland Electricity Commission. The first unit is to come into operation in 1992 and other units are to follow progressively on a yearly basis

  11. Nuclear waste disposal

    International Nuclear Information System (INIS)

    Hare, Tony.

    1990-01-01

    The Save Our Earth series has been designed to appeal to the inquiring minds of ''planet-friendly'' young readers. There is now a greater awareness of environmental issues and an increasing concern for a world no longer able to tolerate the onslaught of pollution, the depletion of natural resources and the effects of toxic chemicals. Each book approaches a specific topic in a way that is exciting and thought-provoking, presenting the facts in a style that is concise and appropriate. The series aims to demonstrate how various environmental subjects relate to our lives, and encourages the reader to accept not only responsibility for the planet, but also for its rescue and restoration. This volume, on nuclear waste disposal, explains how nuclear energy is harnessed in a nuclear reactor, what radioactive waste is, what radioactivity is and its effects, and the problems and possible solutions of disposing of nuclear waste. An awareness of the dangers of nuclear waste is sought. (author)

  12. Reactor oscillator - I - III, Part III - Electronic device

    International Nuclear Information System (INIS)

    Lolic, B.; Jovanovic, S.

    1961-12-01

    This report describes functioning of the reactor oscillator electronic system. Two methods of oscillator operation were discussed. The first method is so called method of amplitude modulation of the reactor power, and the second newer method is phase method. Both methods are planned for the present reactor oscillator

  13. Whither nuclear waste disposal?

    International Nuclear Information System (INIS)

    Cotton, T.A.

    1990-01-01

    With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site

  14. Disposal of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-11-15

    A discussion on the disposal of radioactive wastes was held in Vienna on 20 September 1960. The three scientists who participated in the discussion were Mr. Harry Brynielsson (Sweden), Head of the Swedish Atomic Energy Company; Mr. H. J. Dunster (United Kingdom), Health Physics Adviser to the United Kingdom Atomic Energy Authority; and Mr. Leslie Silverman (United States), Professor of Harvard University, and Chairman of the US AEC Advisory Committee on Reactor Safeguards, as well as consultant on air cleaning

  15. Whither nuclear waste disposal?

    Energy Technology Data Exchange (ETDEWEB)

    Cotton, T A [JK Research Associates, Silver Spring, MD (United States)

    1990-07-01

    With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site.

  16. Disposal of radioactive waste

    International Nuclear Information System (INIS)

    Critchley, R.J.; Swindells, R.J.

    1984-01-01

    A method and apparatus for charging radioactive waste into a disposable steel drum having a plug type lid. The drum is sealed to a waste dispenser and the dispenser closure and lid are withdrawn into the dispenser in back-to-back manner. Before reclosing the dispenser the drum is urged closer to it so that on restoring the dispenser closure to the closed position the lid is pressed into the drum opening

  17. Radium bearing waste disposal

    International Nuclear Information System (INIS)

    Tope, W.G.; Nixon, D.A.; Smith, M.L.; Stone, T.J.; Vogel, R.A.; Schofield, W.D.

    1995-01-01

    Fernald radium bearing ore residue waste, stored within Silos 1 and 2 (K-65) and Silo 3, will be vitrified for disposal at the Nevada Test Site (NTS). A comprehensive, parametric evaluation of waste form, packaging, and transportation alternatives was completed to identify the most cost-effective approach. The impacts of waste loading, waste form, regulatory requirements, NTS waste acceptance criteria, as-low-as-reasonably-achievable principles, and material handling costs were factored into the recommended approach

  18. Disposing of fluid wastes

    International Nuclear Information System (INIS)

    Bradley, J.S.

    1984-01-01

    Toxic liquid waste, eg liquid radioactive waste, is disposed of by locating a sub-surface stratum which, before removal of any fluid, has a fluid pressure in the pores thereof which is less than the hydrostatic pressure which is normal for a stratum at that depth in the chosen area, and then feeding the toxic liquid into the stratum at a rate such that the fluid pressure in the stratum never exceeds the said normal hydrostatic pressure. (author)

  19. Rock disposal problems identified

    Energy Technology Data Exchange (ETDEWEB)

    Knox, R

    1978-06-01

    Mathematical models are the only way of examining the return of radioactivity from nuclear waste to the environment over long periods of time. Work in Britain has helped identify areas where more basic data is required, but initial results look very promising for final disposal of high level waste in hard rock repositories. A report by the National Radiological Protection Board of a recent study, is examined.

  20. Disposal of spent fuel

    International Nuclear Information System (INIS)

    Blomeke, J.O.; Ferguson, D.E.; Croff, A.G.

    1978-01-01

    Based on preliminary analyses, spent fuel assemblies are an acceptable form for waste disposal. The following studies appear necessary to bring our knowledge of spent fuel as a final disposal form to a level comparable with that of the solidified wastes from reprocessing: 1. A complete systems analysis is needed of spent fuel disposition from reactor discharge to final isolation in a repository. 2. Since it appears desirable to encase the spent fuel assembly in a metal canister, candidate materials for this container need to be studied. 3. It is highly likely that some ''filler'' material will be needed between the fuel elements and the can. 4. Leachability, stability, and waste-rock interaction studies should be carried out on the fuels. The major disadvantages of spent fuel as a disposal form are the lower maximum heat loading, 60 kW/acre versus 150 kW/acre for high-level waste from a reprocessing plant; the greater long-term potential hazard due to the larger quantities of plutonium and uranium introduced into a repository; and the possibility of criticality in case the repository is breached. The major advantages are the lower cost and increased near-term safety resulting from eliminating reprocessing and the treatment and handling of the wastes therefrom

  1. Greater-confinement disposal

    International Nuclear Information System (INIS)

    Trevorrow, L.E.; Schubert, J.P.

    1989-01-01

    Greater-confinement disposal (GCD) is a general term for low-level waste (LLW) disposal technologies that employ natural and/or engineered barriers and provide a degree of confinement greater than that of shallow-land burial (SLB) but possibly less than that of a geologic repository. Thus GCD is associated with lower risk/hazard ratios than SLB. Although any number of disposal technologies might satisfy the definition of GCD, eight have been selected for consideration in this discussion. These technologies include: (1) earth-covered tumuli, (2) concrete structures, both above and below grade, (3) deep trenches, (4) augered shafts, (5) rock cavities, (6) abandoned mines, (7) high-integrity containers, and (8) hydrofracture. Each of these technologies employ several operations that are mature,however, some are at more advanced stages of development and demonstration than others. Each is defined and further described by information on design, advantages and disadvantages, special equipment requirements, and characteristic operations such as construction, waste emplacement, and closure

  2. Waste and Disposal: Demonstration

    International Nuclear Information System (INIS)

    Neerdael, B.; Buyens, M.; De Bruyn, D.; Volckaert, G.

    2002-01-01

    Within the Belgian R and D programme on geological disposal, demonstration experiments have become increasingly important. In this contribution to the scientific report 2001, an overview is given of SCK-CEN's activities and achievements in the field of large-scale demonstration experiments. In 2001, main emphasis was on the PRACLAY project, which is a large-scale experiment to demonstrate the construction and the operation of a gallery for the disposal of HLW in a clay formation. The PRACLAY experiment will contribute to enhance understanding of water flow and mass transport in dense clay-based materials as well as to improve the design of the reference disposal concept. In the context of PRACLAY, a surface experiment (OPHELIE) has been developed to prepare and to complement PRACLAY-related experimental work in the HADES Underground Research Laboratory. In 2001, efforts were focussed on the operation of the OPHELIE mock-up. SCK-CEN also contributed to the SELFRAC roject which studies the self-healing of fractures in a clay formation

  3. Importance of characteristics and modalities of physical activity and exercise in the management of cardiovascular health in individuals with cardiovascular disease (Part III).

    Science.gov (United States)

    Vanhees, L; Rauch, B; Piepoli, M; van Buuren, F; Takken, T; Börjesson, M; Bjarnason-Wehrens, B; Doherty, P; Dugmore, D; Halle, M

    2012-12-01

    The beneficial effect of exercise training and exercise-based cardiac rehabilitation on symptom-free exercise capacity,cardiovascular and skeletal muscle function, quality of life, general healthy lifestyle, and reduction of depressive symptoms and psychosocial stress is nowadays well recognized. However, it remains largely obscure, which characteristics of physical activity (PA) and exercise training--frequency, intensity, time (duration), type (mode), and volume (dose: intensity x duration) of exercise--are the most effective. The present paper, therefore, will deal with these exercise characteristics in the management of individuals with cardiovascular disease, i.e. coronary artery disease and chronic heart failure patients, but also in patients with congenital or valvular heart disease. Based on the current literature, and if sufficient evidence is available, recommendations from the European Association on Cardiovascular Prevention and Rehabilitation are formulated regarding frequency, intensity, time and type of PA, and safety aspects during exercise inpatients with cardiovascular disease. This paper is the third in a series of three papers, all devoted to the same theme: the importance of the exercise characteristics in the management of cardiovascular health. Part I is directed to the general population and Part II to individuals with cardiovascular risk factors. In general, PA recommendations and exercise training programmes for patients with coronary artery disease or chronic heart failure need to be tailored to the individual's exercise capacity and risk profile, with the aim to reach and maintain the individually highest fitness level possible and to perform endurance exercise training 30–60 min daily (3–5 days per week) in combination with resistance training 2–3 times a week. Because of the frequently reported dose–response relationship between training effect and exercise intensity, one should seek sufficiently high training intensities

  4. The classification of the finite simple groups, number 7 part III, chapters 7-11 the generic case, stages 3b and 4a

    CERN Document Server

    Gorenstein, Daniel; Solomon, Ronald

    2018-01-01

    The classification of finite simple groups is a landmark result of modern mathematics. The multipart series of monographs which is being published by the AMS (Volume 40.1-40.7 and future volumes) represents the culmination of a century-long project involving the efforts of scores of mathematicians published in hundreds of journal articles, books, and doctoral theses, totaling an estimated 15,000 pages. This part 7 of the series is the middle of a trilogy (Volume 40.5, Volume 40.7, and forthcoming Volume 40.8) treating the Generic Case, i.e., the identification of the alternating groups of degree at least 13 and most of the finite simple groups of Lie type and Lie rank at least 4. Moreover, Volumes 40.4-40.8 of this series will provide a complete treatment of the simple groups of odd type, i.e., the alternating groups (with two exceptions) and the groups of Lie type defined over a finite field of odd order, as well as some of the sporadic simple groups. In particular, this volume completes the construction, be...

  5. Differences between easy- and difficult-to-mill chickpea (Cicer arietinum L.) genotypes. Part III: free sugar and non-starch polysaccharide composition.

    Science.gov (United States)

    Wood, Jennifer A; Knights, Edmund J; Campbell, Grant M; Choct, Mingan

    2014-05-01

    Parts I and II of this series of papers identified several associations between the ease of milling and the chemical compositions of different chickpea seed fractions. Non-starch polysaccharides were implicated; hence, this study examines the free sugars and sugar residues. Difficult milling is associated with: (1) lower glucose and xylose residues (less cellulose and xyloglucans) and more arabinose, rhamnose and uronic acid in the seed coat, suggesting a more flexible seed coat that resists cracking and decortication; (2) a higher content of soluble and insoluble non-starch polysaccharide fractions in the cotyledon periphery, supporting a pectic polysaccharide mechanism comprising arabinogalacturonan, homogalacturonan, rhamnogalalcturonan, and glucuronan backbone structures; (3) higher glucose and mannose residues in the cotyledon periphery, supporting a lectin-mediated mechanism of adhesion; and (4) higher arabinose and glucose residues in the cotyledon periphery, supporting a mechanism involving arabinogalactan-proteins. This series has shown that the chemical composition of chickpea does vary in ways that are consistent with physical explanations of how seed structure and properties relate to milling behaviour. Seed coat strength and flexibility, pectic polysaccharide binding, lectins and arabinogalactan-proteins have been implicated. Increased understanding in these mechanisms will allow breeding programmes to optimise milling performance in new cultivars. © 2013 Society of Chemical Industry.

  6. Winter ecology of the Porcupine caribou herd, Yukon: Part III, Role of day length in determining activity pattern and estimating percent lying

    Directory of Open Access Journals (Sweden)

    D. E. Russell

    1986-06-01

    Full Text Available Data on the activity pattern, proportion of time spent lying and the length of active and lying periods in winter are presented from a 3 year study on the Porcupine caribou herd. Animals were most active at sunrise and sunset resulting in from one (late fall, early and mid winter to two (early fall and late winter to three (spring intervening lying periods. Mean active/lying cycle length decreased from late fall (298 mm to early winter (238 min, increased to a peak in mid winter (340 min then declined in late winter (305 min and again in spring (240 min. Mean length of the lying period increased throughout the 3 winter months from 56 min m early winter to 114 min in mid winter and 153 min in late winter. The percent of the day animals spent lying decreased from fall to early winter, increased throughout the winter and declined in spring. This pattern was related, in part, to day length and was used to compare percent lying among herds. The relationship is suggested to be a means of comparing quality of winter ranges.

  7. Acid-base titrations by stepwise addition of equal volumes of titrant with special reference to automatic titrations-III Presentation of a fully automatic titration apparatus and of results supporting the theories given in the preceding parts.

    Science.gov (United States)

    Pehrsson, L; Ingman, F

    1977-02-01

    This paper forms Part III of a series in which the first two parts describe methods for evaluating titrations performed by stepwise addition of equal volumes of titrant. The great advantage of these methods is that they do not require an accurate calibration of the electrode system. This property makes the methods very suitable for routine work. e.g., in automatic analysis. An apparatus for performing such titrations automatically is presented. Further, results of titrations of monoprotic acids, a diprotic acid, an ampholyte, a mixture of an acid with its conjugate base, and mixtures of two acids with a small difference between the stability constants are given. Most of these titrations cannot be evaluated by the Gran or Hofstee methods but yield results having errors of the order of 0.1% if the methods proposed in Parts I and II of this series are employed. The advantages of the method of stepwise addition of equal volumes of titrant combined with the proposed evaluation methods, in comparison with common methods such as titration to a preset pH, are that all the data are used in the evaluation, permitting a statistical treatment and giving better possibilities for tracing systematic errors.

  8. Device for the disposal of radioactive liquid wastes

    International Nuclear Information System (INIS)

    Tomizawa, Toshi; Inoue, Tadashi.

    1976-01-01

    Object: To adsorb and collect radioactive nuclide ions contained in the radioactive liquid waste to select and separate thereof. Structure: A unitary disposing tank comprises an insulative cylindrical tank, an unsoluble cathode plate positioned thereunder and formed with a number of liquid inlet holes, an adsorbent layer filled with unsoluble electrically conductive substances having a large surface area in contact with the cathode plate, and an unsoluble anode plate positioned at the upper part of the cylindrical disposing tank so as not to come into contact with the adsorbent layer and formed with a number of liquid inlets, whereby one or more disposing tanks are stacked in a layer fashion, and a DC voltage is applied between the anode and cathode plates to flow a liquid to be disposed into the disposing tanks so that the radioactive metal ion nuclide in the liquid may be adsorbed and collected by the cathode and the adsorbent layer for selection and separation. (Ohara, T.)

  9. Composite analysis E-area vaults and saltstone disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

  10. Composite analysis E-area vaults and saltstone disposal facilities

    International Nuclear Information System (INIS)

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public

  11. The development of safety assessment technology for the radwaste disposal

    International Nuclear Information System (INIS)

    Han, Kyong Won; Cho, Won Jin; Lee, Han Soo; Lee, Jai Wan; Park, Chung Kyun; Lee, Myun Joo; Cho, Young Hwan; Choi, Heui Joo; Lee, Youn Myoung; Park, Hee Sung

    1989-02-01

    This report is composed of three parts. In part I, an improved radwaste disposal safety assessment code named SADROCM, was developed by upgrading the existing SADROC. A numerical approach was adopted for the simulation of diffusion into rock pore and advection in the fracture. Also quantification of resaturation time in repository was obtained by introducing theoretical resaturation model and groundwater flow model. In radiation dose model the calculated dose by existing model was compared with that by LIMCAL code. Part II resulted in several findings. Regarding the leaching of radionuclide, two steps were observed. It was identified that in the initial step, radionuclide leaching occurred at the surface of solidified waste, and then leaching proceeded by dissolution and diffusion of radionuclide from inside of the solidified waste.The results of the sorption experiments on Cs, Co, Sr for the rock samples from four regions, showed that Kd value of F-site quartz-porphery was the lowest, and that of B-site Rhyolitic tuff the highest. E-site granite, M-site granite gneiss showed medium sorption capacities. The Kd values of each radionuclide were in the following order: Cs > Co > Sr . For the radionuclide migration through fractured rock, examination of hydraulic dispersion model and channeling model was carried out to simulate the dispersion phenomena through the fractured rock. In part III, optimum model was established which allows mathematical prediction of the container corrosion rate and leach rate.Based on this model, the equations were obtained to predict corrosion rate and radionuclide leach rate. A good agreement of these equations and existing experimental data was considered to be an indication that it can be used effectively for the estimation of long-term leaching. (Author)

  12. Shielding design of disposal container for disused sealed radioactive source

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Suk Hoon; Kim, Ju Youl [FNC Technology Co., Yongin (Korea, Republic of)

    2017-06-15

    Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised.

  13. Shielding design of disposal container for disused sealed radioactive source

    International Nuclear Information System (INIS)

    Kim, Suk Hoon; Kim, Ju Youl

    2017-01-01

    Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised

  14. Nuclear waste disposal site

    International Nuclear Information System (INIS)

    Mallory, C.W.; Watts, R.E.; Sanner, W.S. Jr.; Paladino, J.B.; Lilley, A.W.; Winston, S.J.; Stricklin, B.C.; Razor, J.E.

    1988-01-01

    This patent describes a disposal site for the disposal of toxic or radioactive waste, comprising: (a) a trench in the earth having a substantially flat bottom lined with a layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for obstructing any capillary-type flow of ground water to the interior of the trench; (b) a non-rigid, radiation-blocking cap formed from a first layer of alluvium, a second layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for blocking any capillary-type flow of water between the layer of alluvium and the rest of the cap, a layer of water-shedding silt for directing surface water away from the trench, and a layer of rip-rap over the silt layer for protecting the silt layer from erosion and for providing a radiation barrier; (c) a solidly-packed array of abutting modules of uniform size and shape disposed in the trench and under the cap for both encapsulating the wastes from water and for structurally supporting the cap, wherein each module in the array is slidable movable in the vertical direction in order to allow the array of modules to flexibly conform to variations in the shape of the flat trench bottom caused by seismic disturbances and to facilitate the recoverability of the modules; (d) a layer of solid, fluent, coarse, granular materials having a high hydraulic conductivity in the space between the side of the modules and the walls of the trench for obstructing any capillary-type flow of ground water to the interior of the trench; and (e) a drain and wherein the layer of silt is sloped to direct surface water flowing over the cap into the drain

  15. Municipal sludge disposal economics

    Energy Technology Data Exchange (ETDEWEB)

    Jones, J L [SRI International, Menlo Park, CA; Bomberger, Jr, D C; Lewis, F M

    1977-10-01

    Costs for disposal of sludges from a municipal wastewater treatment plant normally represents greater than or equal to 25% of the total plant operating cost. The following 5 sludge handling options are considered: chemical conditioning followed by vacuum filtration, and incineration; high-pressure wet-air oxidation and vacuum filtration or filter press prior to incineration; thermal conditioning, vacuum filtraton, and incineration; high-pressure wet-air oxidation and vacuum filtration, with ash to landfill; aerobic or anaerobic digestion, followed by chemical conditioning, vacuum filtration, and disposal on land; and chemical conditioning, followed by a filter press, flash dryer, and sale as fertilizer. The 1st 2 options result in the ultimate disposal of small amounts of ash in a landfill; the digestion options require a significant landfill; the fertilizer option requires a successful marketing and sales effort. To compare the economies of scale for the options, analyses were performed for 3 plant capacities - 10, 100, and 500 mgd; as plant size increases, the economies of scale for incineration system are quite favorable. The anaerobic digestion system has a poorer capital cost-scaling factor. The incinerator options which start with chemical conditioning consume much less electrical power at all treatment plant sizes; incinerator after thermal conditioning uses more electricity but less fuel. Digestion requires no direct external fossil fuel input. The relative use of fuel is constant at all plant sizes for other options. The incinerator options can produce a significant amount of steam which may be used. The anaerobic digestion process can be a significant net producer of fuel gas.

  16. Underground disposal of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-08-15

    Disposal of low- and intermediate-level radioactive wastes by shallow land burial, emplacement in suitable abandoned mines, or by deep well injection and hydraulic fracturing has been practised in various countries for many years. In recent years considerable efforts have been devoted in most countries that have nuclear power programmes to developing and evaluating appropriate disposal systems for high-level and transuranium-bearing waste, and to studying the potential for establishing repositories in geological formations underlaying their territories. The symposium, organized jointly by the IAEA and OECD's Nuclear Energy Agency in cooperation with the Geological Survey of Finland, provided an authoritative account of the status of underground disposal programmes throughout the world in 1979. It was evidence of the experience that has been gained and the comprehensive investigations that have been performed to study various options for the underground disposal of radioactive waste since the last IAEA/NEA symposium on this topic (Disposal of Radioactive Waste into the Ground) was held in 1967 in Vienna. The 10 sessions covered the following topics: National programme and general studies, Disposal of solid waste at shallow depth and in rock caverns, underground disposal of liquid waste by deep well injection and hydraulic fracturing, Disposal in salt formations, Disposal in crystalline rocks and argillaceous sediments, Thermal aspects of disposal in deep geological formations, Radionuclide migration studies, Safety assessment and regulatory aspects.

  17. The surface disposal concept for VLL waste

    International Nuclear Information System (INIS)

    2011-01-01

    offers 25 000 m 3 in a 26 m wide by 174 m long and up to 8.5 m deep structure. Cells are filled up in successive waste packages layers (about 10 on average), while void spaces between waste packages are gradually backfilled with sand. a 2-mm-thick high-density polyethylene (HDPE) geo-membrane is first fitted at the bottom and on the sides of the cell before emplacing the waste. Once each individual cell is filled up, an identical membrane is laid over it and thermo-welded to the first, in order to form a continuous and water-tight barrier around the waste. The geo-membrane is fully waterproof and is designed to prevent any dispersion of radioactivity and any seepage of external waters (rain, infiltrations) over several decades; a containment envelope made up of natural clay-based materials. The lower part of the envelope corresponds to the first 5 m of the clay layer located immediately under the geo-membrane and characterized by a very low permeability (at least 10 -9 m/s). The upper part is made of clay-based materials that were removed during cell excavation and consists of a layer measuring 1 to 5 m in thickness, shaped and compacted mechanically in order to restore its initial low permeability (at least 10 -9 m/s). Ultimately, a clay backfill, approximately 2.5-m in thickness, will isolate the clay-based containment layer from: - weathering (frost, draught); - burrowing animals, and - erosion. Lastly, a permanent 30-cm-thick layer of grass-covered topsoil will be laid over the entire structure. To provide its wide-ranging competences in the field of waste management and disposal, ANDRA offers multiple solutions, from consultancy and documents reviewing, to technology transfer and turnkey projects

  18. The surface disposal concept for VLL waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    offers 25 000 m{sup 3} in a 26 m wide by 174 m long and up to 8.5 m deep structure. Cells are filled up in successive waste packages layers (about 10 on average), while void spaces between waste packages are gradually backfilled with sand. a 2-mm-thick high-density polyethylene (HDPE) geo-membrane is first fitted at the bottom and on the sides of the cell before emplacing the waste. Once each individual cell is filled up, an identical membrane is laid over it and thermo-welded to the first, in order to form a continuous and water-tight barrier around the waste. The geo-membrane is fully waterproof and is designed to prevent any dispersion of radioactivity and any seepage of external waters (rain, infiltrations) over several decades; a containment envelope made up of natural clay-based materials. The lower part of the envelope corresponds to the first 5 m of the clay layer located immediately under the geo-membrane and characterized by a very low permeability (at least 10{sup -9} m/s). The upper part is made of clay-based materials that were removed during cell excavation and consists of a layer measuring 1 to 5 m in thickness, shaped and compacted mechanically in order to restore its initial low permeability (at least 10{sup -9} m/s). Ultimately, a clay backfill, approximately 2.5-m in thickness, will isolate the clay-based containment layer from: - weathering (frost, draught); - burrowing animals, and - erosion. Lastly, a permanent 30-cm-thick layer of grass-covered topsoil will be laid over the entire structure. To provide its wide-ranging competences in the field of waste management and disposal, ANDRA offers multiple solutions, from consultancy and documents reviewing, to technology transfer and turnkey projects

  19. Radioactive waste material disposal

    Science.gov (United States)

    Forsberg, Charles W.; Beahm, Edward C.; Parker, George W.

    1995-01-01

    The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

  20. Disposal - practical problems

    International Nuclear Information System (INIS)

    Hycnar, J.; Pinko, L.

    1995-01-01

    Most Polish power plants have stockyards for storage of fly ash and slag. This paper describes the: methods of fly ash and slag storage used, methods of conveying the waste to the stockpiles (by railway cars, trucks, belt conveyors or hydraulically); construction of wet stockyards and dry stockyards and comparison of the ash dumped, development of methods of ash disposal in mine workings; composition and properties of fly ash and slag from hard coal; and the effects of ash storage yards on the environment (by leaching of trace elements, dust, effect on soils, and noise of machinery). 16 refs., 3 figs., 6 tabs

  1. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    1982-01-01

    This film for a general audience deals with nuclear fuel waste management in Canada, where research is concentrating on land based geologic disposal of wastes rather than on reprocessing of fuel. The waste management programme is based on cooperation of the AECL, various universities and Ontario Hydro. Findings of research institutes in other countries are taken into account as well. The long-term effects of buried radioactive wastes on humans (ground water, food chain etc.) are carefully studied with the help of computer models. Animated sequences illustrate the behaviour of radionuclides and explain the idea of a multiple barrier system to minimize the danger of radiation hazards

  2. Waste disposal experts meet

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-01-15

    Problems connected with the disposal into the sea of radioactive wastes from peaceful uses of atomic energy are being examined by a panel of experts, convened by the International Atomic Energy Agency. These experts from eight different countries held a first meeting at IAEA headquarters in Vienna from 4-9 December 1958, under the chairmanship of Dr. Harry Brynielsson, Director General of the Swedish Atomic Energy Company. The countries represented are: Canada, Czechoslovakia, France, Japan, Netherlands, United Kingdom and United States. The group will meet again in 1959. (author)

  3. HLW Disposal System Development

    Energy Technology Data Exchange (ETDEWEB)

    Choi, J. W.; Choi, H. J.; Lee, J. Y. (and others)

    2007-06-15

    A KRS is suggested through design requirement analysis of the buffer and the canister which are the constituent of disposal system engineered barrier and HLW management plans are proposed. In the aspect of radionuclide retention capacity, the thickness of the buffer is determined 0.5m, the shape to be disc and ring and the dry density to be 1.6 g/cm{sup 3}. The maximum temperature of the buffer is below 100 .deg. which meets the design requirement. And bentonite blocks with 5 wt% of graphite showed more than 1.0 W/mK of thermal conductivity without the addition of sand. The result of the thermal analysis for proposed double-layered buffer shows that decrease of 7 .deg. C in maximum temperature of the buffer. For the disposal canister, the copper for the outer shell material and cast iron for the inner structure material is recommended considering the results analyzed in terms of performance of the canisters and manufacturability and the geochemical properties of deep groundwater sampled from the research area with granite, salt water intrusion, and the heavy weight of the canister. The results of safety analysis for the canister shows that the criticality for the normal case including uncertainty is the value of 0.816 which meets subcritical condition. Considering nation's 'Basic Plan for Electric Power Demand and Supply' and based on the scenario of disposing CANDU spent fuels in the first phase, the disposal system that the repository will be excavated in eight phases with the construction of the Underground Research Laboratory (URL) beginning in 2020 and commissioning in 2040 until the closure of the repository is proposed. Since there is close correlation between domestic HLW management plans and front-end/back-end fuel cycle plans causing such a great sensitivity of international environment factor, items related to assuring the non-proliferation and observing the international standard are showed to be the influential factor and acceptability

  4. Economic analysis of alternative LLW disposal methods

    International Nuclear Information System (INIS)

    Foutes, C.E.; Queenan, C.J. III

    1987-01-01

    The Environmental Protection Agency (EPA) has evaluated the costs and benefits of alternative disposal technologies as part of its program to develop generally applicable environmental standards for the land disposal of low-level radioactive waste (LLW). Costs, population health effects and Critical Population Group (CPG) exposures resulting from alternative waste treatment and disposal methods were evaluated both in absolute terms and also relative to a base case (current practice). Incremental costs of the standard included costs for packaging, processing, transportation, and burial of waste. Benefits are defined in terms of reductions in the general population health risk (expected fatal cancers and genetic effects) evaluated over 10,000 years. A cost-effectiveness ratio, defined as the incremental cost per avoided health effect, was calculated for each alternative standard. The cost-effectiveness analysis took into account a number of waste streams, hydrogeologic and climatic region settings, and waste treatment and disposal methods. This paper describes the alternatives considered and preliminary results of the cost-effectiveness analysis. 15 references, 7 figures, 3 tables

  5. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Science.gov (United States)

    2010-01-01

    ... DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.52 Land disposal... wastes by placing in disposal units which are sufficiently separated from disposal units for the other... between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer zone...

  6. Borehole disposal design concept

    International Nuclear Information System (INIS)

    RANDRIAMAROLAHY, J.N.

    2007-01-01

    In Madagascar, the sealed radioactive sources are used in several socioeconomic sectors such as medicine, industry, research and agriculture. At the end of their useful lives, these radioactive sources become radioactive waste and can be still dangerous because they can cause harmful effects to the public and the environment. This work entitled 'Borehole disposal design concept' consists in putting in place a site of sure storage of the radioactive waste, in particular, sealed radioactive sources. Several technical aspects must be respected to carry out such a site like the geological, geomorphologic, hydrogeologic, geochemical, meteorological and demographic conditions. This type of storage is favorable for the developing countries because it is technologically simple and economic. The cost of construction depends on the volume of waste to store and the depth of the Borehole. The Borehole disposal concept provides a good level of safety to avoid the human intrusion. The future protection of the generations against the propagation of the radiations ionizing is then assured. [fr

  7. Research on geological disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The aims of this research are to develop criteria for reviewing reliability and suitability of the result from Preliminary Investigations to be submitted by the implementer, and to establish a basic policy for safety review. For development of reliability and suitability criteria for reviewing the result of Preliminary Investigations, we evaluated the uncertainties and their influence from limited amount of investigations, as well as we identified important procedures during investigations and constructions of models, as follows: (1) uncertainties after limited amount of geological exploration and drilling, (2) influence of uncertainties in regional groundwater flow model, (3) uncertainties of DFN (Discrete Fracture Network) models in the fractured rock, (4) analyzed investigation methods described in implementer's report, and (5) identified important aspects in investigation which need to be reviewed and follow QA (Quality Assurance). For development of reliability and suitability criteria for reviewing the result of Detailed Investigations, we analyzed important aspects in investigation which supplies data to design and safety assessment, as well as studied the applicability of pressure interference data during excavation to verify hydrogeological model. Regarding the research for safety review, uncertainties of geologic process in long time-scale was studied. In FY2012, we started to evaluate the structural stabilities of concrete and bentonite in disposal environment. Finally, we continued to accumulate the knowledge on geological disposal into the database system. (author)

  8. Geoenvironment and waste disposal

    International Nuclear Information System (INIS)

    1983-07-01

    Within the activities planned by UNESCO in its Water and Earth Science programme, an interdisciplinary meeting on geology and environment was scheduled by this organization to be held by the beginning of 1983. At this meeting it was intended to consider geological processes in the light of their interaction and influence on the environment with special emphasis on the impact of various means of waste disposal on geological environment and on man-induced changes in the geological environment by mining, human settlements, etc. Considering the increasing interest shown by the IAEA in the field, through environmental studies, site studies, and impact studies for nuclear facilities and particularly nuclear waste disposal, UNESCO expressed the wish to organize the meeting jointly so as to take into account the experience gained by the Agency, and in order to avoid any duplication in the activities of the two organizations. This request was agreed to by the IAEA Secretariat and as a result, the meeting was organized by both organizations and held at IAEA Headquarters in Vienna from 21-23 March 1983. The report of this meeting is herewith presented

  9. Mine tailings disposal

    International Nuclear Information System (INIS)

    Gonzales, P.A.; Adams, B.J.

    1980-06-01

    The hydrologic evaluation of mine tailings disposal sites after they are abandoned is considered in relation to their potential environmental impact on a long term basis. There is a direct relation between the amounts and types of water leaving a disposal site and the severity of the potential damage to the environment. The evaluation of the relative distribution of the precipitation reaching the ground into evaporation, runoff and infiltration is obtained for a selected site and type of tailings material whose characteristics and physical properties were determined in the soils laboratory. A conceptual model of the hydrologic processes involved and the corresponding mathematical model were developed to simulate the physical system. A computer program was written to solve the set of equations forming the mathematical model, considering the physical properties of the tailings and the rainfall data selected. The results indicate that the relative distribution of the precipitation depends on the surface and upper layer of the tailings and that the position of the groundwater table is governed by the flow through the bottom of the profile considered. The slope of the surface of the mass of tailings was found to be one of the principal factors affecting the relative distribution of precipitation and, therefore, the potential pollution of the environment

  10. The aminoterminal propeptide of type III procollagen. Studies on physiology and pathophysiology

    DEFF Research Database (Denmark)

    Jensen, L T

    1997-01-01

    receiving growth hormone therapy. We conclude: 1) That, for our purpose, the best method of determining PIIINP is the PIIINP RIA, owing to the profile of the substances determined. It was possible to improve the quality of the tracer and to increase sensitivity by changing the assay procedure. 2...... of peaks B and C (intact PIIINP) may, owing to the disposal rate, reflect changes in type III collagen turnover over one day (6 half-lives). The liver and kidneys actively take part in the degradation of circulating PIIINP. Serum concentrations of PIIINP in the presence of changing body composition (weight...... disappears when the body is in a catabolic state. Anabolic states give rise to increased serum concentrations of PIIINP as compared with normals states. The general conclusion is that serum PIIINP is a marker of type III collagen turnover under well-defined conditions. Serum PIIINP, mainly consisting...

  11. Disposal of radioactive waste material

    International Nuclear Information System (INIS)

    Cairns, W.J.; Burton, W.R.

    1984-01-01

    A method of disposal of radioactive waste consists in disposing the waste in trenches dredged in the sea bed beneath shallow coastal waters. Advantageously selection of the sites for the trenches is governed by the ability of the trenches naturally to fill with silt after disposal. Furthermore, this natural filling can be supplemented by physical filling of the trenches with a blend of absorber for radionuclides and natural boulders. (author)

  12. Ecological questions on the disposal of radioactive waste

    International Nuclear Information System (INIS)

    Brenner, A.; Kägi, W.; Marugg, F.; Bellmann, R.; Giaquinto, K.

    2014-10-01

    This comprehensive paper elaborated for the Swiss Federal Office of Energy (SFOE) discusses six central key questions on the disposal of radioactive wastes. Various factors in the philosophical-ethics area are discussed including disposal and responsibility, disposal and social justness, co-operation, trusteeship, nature and ecocide and questions of guilt. The ethics part of the report is dedicated to conflict management. The second part of the report deals with environmental policy. Aspects dealt with include sustainability, the principles of provision, participation and the cost-by-cause principle. Efficiency and newer developments in environmental policy are discussed. The disposal of radioactive waste is reviewed together with the effects of discussions on this topic and related developments

  13. Sodium cleaning and disposal methods in experimental facilities

    International Nuclear Information System (INIS)

    Rajan, K.K.; Gurumoorthy, K.; Rajan, M.; Kale, R.D.

    1997-01-01

    At Indira Gandhi Centre for Atomic Research, major sodium facilities are designed and operated at Engineering Development Group as a part of development programme towards experimental and Prototype Fast Reactor. After the test programme many equipment and components were removed from the sodium facilities and sodium removal and disposal was carried out. The experience gained in different cleaning methods and waste sodium disposal are discussed. (author)

  14. Fourier Transform Infrared Spectroscopy Part III. Applications.

    Science.gov (United States)

    Perkins, W. D.

    1987-01-01

    Discusses the use of the FT-IR spectrometer in analyses that were previously avoided. Examines some of the applications of this spectroscopy with aqueous solutions, circular internal reflection, samples with low transmission, diffuse reflectance, infrared emission, and the infrared microscope. (TW)

  15. [Medicine in notafilia--Part III].

    Science.gov (United States)

    Babić, Rade R; Babić, Gordana Stanković

    2013-01-01

    Notafilia is the study of paper money. Only a few countries in the world have issued banknotes with portraits of well-known scientists who brought international fame to their own people and medicine. PORTRAITS OF SCIENTISTS ON THE BANKNOTES OF YUGOSLAVIA, SERBIA AND MONTENEGRO AND SERBIA. Nikola Tesla and Mihailo Pupin Idvorski were the ingenious inventors and scientists of our time who made special contributions to radiology. Nikola Tesla (1856-1943) pioneered the use of X-rays for medical purposes, thus effectively laying the foundations of radiology and radiography, and revealed the existence of harmful effects of X-rays on the human body. Mihailo Pupin Idvorski (1854-1935) was worldwide famous for applying physics in practice, as well as in the basis of telephone and telegraph transmissions. He also studied the nature of X-rays and contributed to establishing of radiology. PORTRAITS OF SCIENTISTS ON THE BANKNOTES OF THE WORLD: Maria Sklodowska Curie (1867-1934) was the first woman to gain the academic title of the Academy of Medicine, Paris. Together with her husband Pierre Curie (1859-1906) she gave an outstanding contribution to science and medicine. The discovery of the radioactive elements introduced the concept of "radioactivity" into physics and "radiotherapy" as a new discipline in medicine, thus creating the conditions for the development of nuclear medicine, oncology, and mobile diagnostic radiology. This paper presents the banknotes featuring the portraits of Nikola Tesla, Mihailo Pupin Idvorski, Maria Sklodowska Curie and Pierre Curie, the world renowned scientists, who made enormous contributions to medicine and laid the foundation for radiology.

  16. 'Riesenrad' ion gantry for hadrontherapy: Part III

    International Nuclear Information System (INIS)

    Benedikt, M.; Bryant, P.; Holy, P.; Pullia, M.

    1999-01-01

    When using accelerator beams for cancer therapy, the three-dimensional freedom afforded by a gantry helps the treatment planner to spread out surface doses, avoid directions that intercept vital organs and irradiate a volume that is conformal with the tumour. The general preference is for an iso-centric gantry turning 360 deg. in the vertical plane around the patient bed with sufficient space to be able to orientate the patient through 360 deg. in the horizontal plane. For hadrontherapy, gantries are impressive structures of the order of 10 m in diameter and 100 ton in weight and to date only proton gantries have been demonstrated to operate satisfactorily. The increased magnetic rigidity of say carbon ions will make ion gantries more difficult and costly to build. For this reason, exo-centric gantries and, in particular the so-called 'Riesenrad' gantry with a single 90 deg. bending magnet, merit further attention. The power consumption is reduced and the heavy magnets with their counterbalance weight are reduced and are kept close to the axis. The treatment room, which is lighter, is positioned at a larger radius, but only the patient bed requires careful alignment. An optics module called a 'rotator' is needed to match an incoming dispersion vector to the gantry in order to have an achromatic beam at the patient. A practical design is described that assumes the beam is derived from a slow-extraction scheme in a synchrotron and that the beam sizes are controlled by modules in the transfer line. Magnetic scanning is integrated into the gantry optics for both transverse directions

  17. Reactor oscillator - I - III, Part I

    International Nuclear Information System (INIS)

    Lolic, B.

    1961-12-01

    Project 'Reactor oscillator' covers the following activities: designing reactor oscillators for reactors RA and RB with detailed engineering drawings; constructing and mounting of the oscillator; designing and constructing the appropriate electronic equipment for the oscillator; measurements at the RA and RB reactors needed for completing the oscillator construction

  18. `Riesenrad' ion gantry for hadrontherapy: Part III

    Science.gov (United States)

    Benedikt, M.; Bryant, P.; Holy, P.; Pullia, M.

    1999-07-01

    When using accelerator beams for cancer therapy, the three-dimensional freedom afforded by a gantry helps the treatment planner to spread out surface doses, avoid directions that intercept vital organs and irradiate a volume that is conformal with the tumour. The general preference is for an iso-centric gantry turning 360° in the vertical plane around the patient bed with sufficient space to be able to orientate the patient through 360° in the horizontal plane. For hadrontherapy, gantries are impressive structures of the order of 10 m in diameter and 100 ton in weight and to date only proton gantries have been demonstrated to operate satisfactorily. The increased magnetic rigidity of say carbon ions will make ion gantries more difficult and costly to build. For this reason, exo-centric gantries and, in particular the so-called `Riesenrad' gantry with a single 90° bending magnet, merit further attention. The power consumption is reduced and the heavy magnets with their counterbalance weight are reduced and are kept close to the axis. The treatment room, which is lighter, is positioned at a larger radius, but only the patient bed requires careful alignment. An optics module called a `rotator' is needed to match an incoming dispersion vector to the gantry in order to have an achromatic beam at the patient. A practical design is described that assumes the beam is derived from a slow-extraction scheme in a synchrotron and that the beam sizes are controlled by modules in the transfer line. Magnetic scanning is integrated into the gantry optics for both transverse directions.

  19. Topics in Finance Part III--Leverage

    Science.gov (United States)

    Laux, Judy

    2010-01-01

    This article investigates operating and financial leverage from the perspective of the financial manager, accenting the relationships to stockholder wealth maximization (SWM), risk and return, and potential agency problems. It also covers some of the pertinent literature related specifically to the implications of operating and financial risk and…

  20. Multibarrier waste forms. Part III: Process considerations

    International Nuclear Information System (INIS)

    Lokken, R.O.

    1979-10-01

    The multibarrier concept for the solidification and storage of radioactive waste utilizes up to three barriers to isolate radionuclides from the environment: a solidified waste inner core, an impervious coating, and a metal matrix. The coating and metal matrix give the composite waste form enhanced inertness with improvements in thermal stability, mechanical strength, and leach resistance. Preliminary process flow rates and material costs were evaluated for four multibarrier waste forms with the process complexity increasing thusly: glass marbles, uncoated supercalcine, glass-coated supercalcine, and PyC/Al 2 O 3 -coated supercalcine. This report discusses the process variables and their effect on optimization of product quality, processing simplicity, and material cost. 11 figures, 2 tables

  1. Macrobenthic succession following the cessation of sewage sludge disposal

    Science.gov (United States)

    Birchenough, Silvana N. R.; Frid, Chris L. J.

    2009-11-01

    Half a million tonnes of sewage sludge was disposed annually over an 18-yr period at a licensed area off the Northumberland coast, UK. The disposal operation ceased in December 1998, providing the ecological opportunity to study macrobenthic changes in relation to theoretical succession models. A transect from the centre of the disposal site to a control station was monitored three times a year (i.e. March, August and December). This study provides a description of the changes in the macrobenthos and physical environment in the initial '3 years' (i.e. 1999 - 2001). During the period of sewage sludge disposal there were indications of an impact on the macrobenthic community with a high total abundance of individuals ( N) and high total number of species ( S) at the stations located in the centre of the disposal ground. During the immediate post-disposal phase the site continued to show a localised increased of individuals and species in the disposal area. Over time the communities showed signs of successional changes when the reduction of organic matter source was eliminated from the natural system. Multivariate analysis demonstrated a clear gradient of change in the community composition between impacted and control stations. While most benthic studies assess re-colonisation and succession stages of macrobenthos by using manipulative field experiments, this study provides an in situ long-term assessment in the offshore environment. This study contributes with information on: i) initial colonization and succession of macrobenthic communities over a large scale and real world data; ii) macrobenthic data into existing successional models and iii) resilience of benthic communities following the cessation of sewage sludge disposal. This information has the potential to contribute to an effective management of the marine communities in the North Sea.

  2. Curriculum and instruction in nuclear waste disposal

    International Nuclear Information System (INIS)

    Robinson, M.; Lugaski, T.; Pankratius, B.

    1991-01-01

    Curriculum and instruction in nuclear waste disposal is part of the larger problem of curriculum and instruction in science. At a time when science and technological literacy is crucial to the nation's economic future fewer students are electing to take needed courses in science that might promote such literacy. The problem is directly related to what science teachers teach and how they teach it. Science content that is more relevant and interesting to students must be a part of the curriculum. Science instruction must allow students to be actively involved in investigating or playing the game of science

  3. Radioactive mixed waste disposal

    International Nuclear Information System (INIS)

    Jasen, W.G.; Erpenbeck, E.G.

    1993-02-01

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste

  4. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Bohm, H.; Closs, K.D.; Kuhn, K.

    1981-01-01

    The solutions to the technical problem of the disposal of radioactive waste are limited by a) the state of knowledge of reprocessing possibilites, b) public acceptance of the use of those techniques which are known, c) legislative procedures linking licensing of new nuclear power plants to the solution of waste problems, and d) other political constraints. Wastes are generated in the mining and enriching of radioactive elements, and in the operation of nuclear power plants as well as in all fields where radioactive substances may be used. Waste management will depend on the stability and concentration of radioactive materials which must be stored, and a resolution of the tension between numerous small storage sites and a few large ones, which again face problems of public acceptability

  5. Disposal of tritiated effluents

    International Nuclear Information System (INIS)

    Hartmann, K.; Bruecher, H.

    1981-06-01

    After some introductory remarks on the origin of tritium, its properties and its behaviour in a reprocessing plant three alternative methods for the disposal of tritiated effluents produced during reprocessing are described (deep well injection, in-situ solidification, deep-sea dumping) and compared with each other under various aspects. The study is based on the concept of a 1400 t/a reprocessing plant for LWR fuel, which annually produces 3000 m 3 of tritiated waste water with a tritium content of 6.5 x 10 12 Bq/m 3 as well as a residual fission product and actinide content. An assessment of the three methods under the aspects of simplicity, reliability, safety, costs, state of development and materials handling revealed advantages in favour of 'injection', followed by 'dumping' and 'in-situ solidification'. (orig./HP) [de

  6. Toxic waste liquor disposal

    International Nuclear Information System (INIS)

    Burton, W.R.

    1985-01-01

    Toxic waste liquors, especially radio active liquors, are disposed in a sub-zone by feeding down a bore hole a first liquid, then a buffer liquid (e.g. water), then the toxic liquors. Pressure variations are applied to the sub-zone to mix the first liquid and liquors to form gels or solids which inhibit further mixing and form a barrier between the sub-zone and the natural waters in the environment of the sub-zone. In another example the location of the sub-zone is selected so that the environement reacts with the liquors to produce a barrier around the zone. Blind bore holes are used to monitor the sub-zone profile. Materials may be added to the liquor to enhance barrier formation. (author)

  7. Radwaste Disposal Safety Analysis

    International Nuclear Information System (INIS)

    Hwang, Yong Soo; Kang, C. H.; Lee, Y. M.; Lee, S. H.; Jeong, J. T.; Choi, J. W.; Park, S. W.; Lee, H. S.; Kim, J. H.; Jeong, M. S.

    2010-02-01

    For the purpose of evaluating annual individual doses from a potential repository disposing of radioactive wastes from the operation of the prospective advanced nuclear fuel cycle facilities in Korea, the new safety assessment approaches are developed such as PID methods. The existing KAERI FEP list was reviewed. Based on these new reference and alternative scenarios are developed along with a new code based on the Goldsim. The code based on the compartment theory can be applied to assess both normal and what if scenarios. In addition detailed studies on THRC coupling is studied. The oriental biosphere study ends with great success over the completion of code V and V with JAEA. The further development of quality assurance, in the form of the CYPRUS+ enables handy use of it for information management

  8. Covering soils and vegetations during decommissioning disposal of a uranium mine

    International Nuclear Information System (INIS)

    Feng Weihua

    2010-01-01

    The disposals of waste ore dumps and tailings are an important part in the decommissioning disposal of uranium mines. Important indexes of the disposal include stabilization, harmlessness, rehabilitation and improvement of the ecological environment. These are closely related with vegetations. Taking example of decommissioning disposal of a uranium mine in Guizhou province, the selection of grasses and effects after covering soils and planting grasses are introduced. It is pointed out that covering soils and vegetations play an important role in decommissioning disposal of uranium mines. (authors)

  9. Crystalline ceramics: Waste forms for the disposal of weapons plutonium

    International Nuclear Information System (INIS)

    Ewing, R.C.; Lutze, W.; Weber, W.J.

    1995-05-01

    At present, there are three seriously considered options for the disposition of excess weapons plutonium: (i) incorporation, partial burn-up and direct disposal of MOX-fuel; (ii) vitrification with defense waste and disposal as glass ''logs''; (iii) deep borehole disposal (National Academy of Sciences Report, 1994). The first two options provide a safeguard due to the high activity of fission products in the irradiated fuel and the defense waste. The latter option has only been examined in a preliminary manner, and the exact form of the plutonium has not been identified. In this paper, we review the potential for the immobilization of plutonium in highly durable crystalline ceramics apatite, pyrochlore, monazite and zircon. Based on available data, we propose zircon as the preferred crystalline ceramic for the permanent disposition of excess weapons plutonium

  10. Cost effective disposal of whey

    Energy Technology Data Exchange (ETDEWEB)

    Zall, R R

    1980-01-01

    Means of reducing the problem of whey disposal are dealt with, covering inter alia the pre-treatment of cheese milk e.g., by ultrafiltration to lower the whey output, utilization of whey constituents, use of liquid whey for feeding, fermenting whey to produce methane and alcohol, and disposal of whey by irrigation of land or by purification in sewage treatment plants.

  11. Melter Disposal Strategic Planning Document

    Energy Technology Data Exchange (ETDEWEB)

    BURBANK, D.A.

    2000-09-25

    This document describes the proposed strategy for disposal of spent and failed melters from the tank waste treatment plant to be built by the Office of River Protection at the Hanford site in Washington. It describes program management activities, disposal and transportation systems, leachate management, permitting, and safety authorization basis approvals needed to execute the strategy.

  12. Korean Reference HLW Disposal System

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heui Joo; Lee, J. Y.; Kim, S. S. (and others)

    2008-03-15

    This report outlines the results related to the development of Korean Reference Disposal System for High-level radioactive wastes. The research has been supported around for 10 years through a long-term research plan by MOST. The reference disposal method was selected via the first stage of the research during which the technical guidelines for the geological disposal of HLW were determined too. At the second stage of the research, the conceptual design of the reference disposal system was made. For this purpose the characteristics of the reference spent fuels from PWR and CANDU reactors were specified, and the material and specifications of the canisters were determined in term of structural analysis and manufacturing capability in Korea. Also, the mechanical and chemical characteristics of the domestic Ca-bentonite were analyzed in order to supply the basic design parameters of the buffer. Based on these parameters the thermal and mechanical analysis of the near-field was carried out. Thermal-Hydraulic-Mechanical behavior of the disposal system was analyzed. The reference disposal system was proposed through the second year research. At the final third stage of the research, the Korean Reference disposal System including the engineered barrier, surface facilities, and underground facilities was proposed through the performance analysis of the disposal system.

  13. Disposal options for radioactive waste

    International Nuclear Information System (INIS)

    Olivier, J.P.

    1991-01-01

    On the basis of the radionuclide composition and the relative toxicity of radioactive wastes, a range of different options are available for their disposal. Practically all disposal options rely on confinement of radioactive materials and isolation from the biosphere. Dilution and dispersion into the environment are only used for slightly contaminated gaseous and liquid effluents produced during the routine operation of nuclear facilities, such as power plants. For the bulk of solid radioactive waste, whatever the contamination level and decay of radiotoxicity with time are, isolation from the biosphere is the objective of waste disposal policies. The paper describes disposal approaches and the various techniques used in this respect, such as shallow land burial with minimum engineered barriers, engineered facilities built at/near the surface, rock cavities at great depth and finally deep geologic repositories for long-lived waste. The concept of disposing long-lived waste into seabed sediment layers is also discussed, as well as more remote possibilities, such as disposal in outer space or transmutation. For each of these disposal methods, the measures to be adopted at institutional level to reinforce technical isolation concepts are described. To the extent possible, some comments are made with regard to the applicability of such disposal methods to other hazardous wastes. (au)

  14. Underground disposal of radioactive wastes

    International Nuclear Information System (INIS)

    1981-01-01

    This report is an overview document for the series of IAEA reports dealing with underground waste disposal to be prepared in the next few years. It provides an introduction to the general considerations involved in implementing underground disposal of radioactive wastes. It suggests factors to be taken into account for developing and assessing waste disposal concepts, including the conditioned waste form, the geological containment and possible additional engineered barriers. These guidelines are general so as to cover a broad range of conditions. They are generally applicable to all types of underground disposal, but the emphasis is on disposal in deep geological formations. Some information presented here may require slight modifications when applied to shallow ground disposal or other types of underground disposal. Modifications may also be needed to reflect local conditions. In some specific cases it may be that not all the considerations dealt with in this book are necessary; on the other hand, while most major considerations are believed to be included, they are not meant to be all-inclusive. The book primarily concerns only underground disposal of the wastes from nuclear fuel cycle operations and those which arise from the use of isotopes for medical and research activities

  15. Nuclear waste disposal in space

    Science.gov (United States)

    Burns, R. E.; Causey, W. E.; Galloway, W. E.; Nelson, R. W.

    1978-01-01

    Work on nuclear waste disposal in space conducted by the George C. Marshall Space Flight Center, National Aeronautics and Space Administration, and contractors are reported. From the aggregate studies, it is concluded that space disposal of nuclear waste is technically feasible.

  16. Chemical Waste Management and Disposal.

    Science.gov (United States)

    Armour, Margaret-Ann

    1988-01-01

    Describes simple, efficient techniques for treating hazardous chemicals so that nontoxic and nonhazardous residues are formed. Discusses general rules for management of waste chemicals from school laboratories and general techniques for the disposal of waste or surplus chemicals. Lists specific disposal reactions. (CW)

  17. Safe disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Hooker, P.; Metcalfe, R.; Milodowski, T.; Holliday, D.

    1997-01-01

    A high degree of international cooperation has characterized the two studies reported here which aim to address whether radioactive waste can be disposed of safely. Using hydrogeochemical and mineralogical surveying techniques earth scientists from the British Geological Survey have sought to identify and characterise suitable disposal sites. Aspects of the studies are explored emphasising their cooperative nature. (UK)

  18. Argentina's radioactive waste disposal policy

    International Nuclear Information System (INIS)

    Palacios, E.

    1986-01-01

    The Argentina policy for radioactive waste disposal from nuclear facilities is presented. The radioactive wastes are treated and disposed in confinement systems which ensure the isolation of the radionucles for an appropriate period. The safety criteria adopted by Argentina Authorities in case of the release of radioactive materials under normal conditions and in case of accidents are analysed. (M.C.K.) [pt

  19. Environmental Restoration Disposal Facility Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    Dronen, V.R.

    1998-06-01

    The Hanford Site is operated by the U. S. Department of Energy (DOE) with a primary mission of environmental cleanup and restoration. The Environmental Restoration Disposal Facility (ERDF) is an integral part of the DOE environmental restoration effort at the Hanford Site. The purpose of this document is to establish the ERDF waste acceptance criteria for disposal of materials resulting from Hanford Site cleanup activities. Definition of and compliance with the requirements of this document will enable implementation of appropriate measures to protect human health and the environment, ensure the integrity of the ERDF liner system, facilitate efficient use of the available space in the ERDF, and comply with applicable environmental regulations and DOE orders. To serve this purpose, the document defines responsibilities, identifies the waste acceptance process, and provides the primary acceptance criteria and regulatory citations to guide ERDF users. The information contained in this document is not intended to repeat or summarize the contents of all applicable regulations

  20. Radioactive waste disposal and public acceptance aspects

    Energy Technology Data Exchange (ETDEWEB)

    Ulhoa, Barbara M.A.; Aleixo, Bruna L.; Mourao, Rogerio P.; Ferreira, Vinicius V.M., E-mail: mouraor@cdtn.b, E-mail: vvmf@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

  1. Radioactive waste disposal and public acceptance aspects

    International Nuclear Information System (INIS)

    Ulhoa, Barbara M.A.; Aleixo, Bruna L.; Mourao, Rogerio P.; Ferreira, Vinicius V.M.

    2011-01-01

    Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

  2. Marine disposal of radioactive wastes - the debate

    International Nuclear Information System (INIS)

    Blair, I.

    1985-01-01

    The paper defends the case for marine disposal of radioactive wastes. The amount of packaged waste disposed; the site for marine disposal; the method of disposal; the radioactivity arising from the disposal; and safety factors; are all briefly discussed. (U.K.)

  3. Rise, fall and resurrection of chromosome territories: a historical perspective. Part II. Fall and resurrection of chromosome territories during the 1950s to 1980s. Part III. Chromosome territories and the functional nuclear architecture: experiments and models from the 1990s to the present.

    Science.gov (United States)

    Cremer, T; Cremer, C

    2006-01-01

    Part II of this historical review on the progress of nuclear architecture studies points out why the original hypothesis of chromosome territories from Carl Rabl and Theodor Boveri (described in part I) was abandoned during the 1950s and finally proven by compelling evidence forwarded by laser-uv-microbeam studies and in situ hybridization experiments. Part II also includes a section on the development of advanced light microscopic techniques breaking the classical Abbe limit written for readers with little knowledge about the present state of the theory of light microscopic resolution. These developments have made it possible to perform 3D distance measurements between genes or other specifically stained, nuclear structures with high precision at the nanometer scale. Moreover, it has become possible to record full images from fluorescent structures and perform quantitative measurements of their shapes and volumes at a level of resolution that until recently could only be achieved by electron microscopy. In part III we review the development of experiments and models of nuclear architecture since the 1990s. Emphasis is laid on the still strongly conflicting views about the basic principles of higher order chromatin organization. A concluding section explains what needs to be done to resolve these conflicts and to come closer to the final goal of all studies of the nuclear architecture, namely to understand the implications of nuclear architecture for nuclear functions.

  4. radioactive waste disposal standards abroad

    International Nuclear Information System (INIS)

    Lu Yan; Xin Pingping; Wu Jian; Zhang Xue

    2012-01-01

    With the world focus on human health and environmental protection, the problem of radioactive waste disposal has gradually become a global issue, and the focus of attention of public. The safety of radioactive waste disposal, is not only related to human health and environmental safety, but also an important factor of affecting the sustainable development of nuclear energy. In recent years the formulation of the radioactive waste disposal standards has been generally paid attention to at home and abroad, and it has made great progress. In China, radioactive waste management standards are being improved, and there are many new standards need to be developed. The revised task of implement standards is very arduous, and there are many areas for improvement about methods and procedures of the preparation of standards. This paper studies the current situation of radioactive waste disposal standards of the International Atomic Energy Agency, USA, France, Britain, Russia, Japan, and give some corresponding recommendations of our radioactive waste disposal standards. (authors)

  5. Engineering geology of waste disposal

    International Nuclear Information System (INIS)

    Bentley, S.P.

    1996-01-01

    This volume covers a wide spectrum of activities in the field of waste disposal. These activities range from design of new landfills and containment properties of natural clays to investigation, hazard assessment and remediation of existing landfills. Consideration is given to design criteria for hard rock quarries when used for waste disposal. In addition, an entire section concerns the geotechnics of underground repositories. This covers such topics as deep drilling, in situ stress measurement, rock mass characterization, groundwater flows and barrier design. Engineering Geology of Waste Disposal examines, in detail, the active role of engineering geologists in the design of waste disposal facilities on UK and international projects. The book provides an authoritative mix of overviews and detailed case histories. The extensive spectrum of papers will be of practical value to those geologists, engineers and environmental scientists who are directly involved with waste disposal. (UK)

  6. A prospective, randomised, controlled, double-blind phase I-II clinical trial on the safety of A-Part® Gel as adhesion prophylaxis after major abdominal surgery versus non-treated group

    Directory of Open Access Journals (Sweden)

    Weis Christine

    2010-07-01

    Full Text Available Abstract Background Postoperative adhesions occur when fibrous strands of internal scar tissue bind anatomical structures to one another. The most common cause of intra-abdominal adhesions is previous intra-abdominal surgical intervention. Up to 74% of intestinal obstructions are caused by post surgical adhesions. Although a variety of methods and agents have been investigated to prevent post surgical adhesions, the problem of peritoneal adhesions remains largely unsolved. Materials serving as an adhesion barrier are much needed. Methods/Design This is a prospective, randomised, controlled, patient blinded and observer blinded, single centre phase I-II trial, which evaluates the safety of A-Part® Gel as an adhesion prophylaxis after major abdominal wall surgery, in comparison to an untreated control group. 60 patients undergoing an elective median laparotomy without prior abdominal surgery are randomly allocated into two groups of a 1:1- ratio. Safety parameter and primary endpoint of the study is the occurrence of wound healing impairment or peritonitis within 28 (+10 days after surgery. The frequency of anastomotic leakage within 28 days after operation, occurrence of adverse and serious adverse events during hospital stay up to 3 months and the rate of adhesions along the scar within 3 months are defined as secondary endpoints. After hospital discharge the investigator will examine the enrolled patients at 28 (+10 days and 3 months (±14 days after surgery. Discussion This trial aims to assess, whether the intra-peritoneal application of A-Part® Gel is safe and efficacious in the prevention of post-surgical adhesions after median laparotomy, in comparison to untreated controls. Trial registration NCT00646412

  7. Cetuximab in combination with irinotecan/5-fluorouracil/folinic acid (FOLFIRI) in the initial treatment of metastatic colorectal cancer: a multicentre two-part phase I/II study

    International Nuclear Information System (INIS)

    Raoul, Jean-Luc; Van Laethem, Jean-Luc; Peeters, Marc; Brezault, Catherine; Husseini, Fares; Cals, Laurent; Nippgen, Johannes; Loos, Anja-Helena; Rougier, Philippe

    2009-01-01

    This study was designed to investigate the efficacy and safety of the epidermal growth factor receptor (EGFR) inhibitor cetuximab combined with irinotecan, folinic acid (FA) and two different doses of infusional 5-fluorouracil (5-FU) in the first-line treatment of EGFR-detectable metastatic colorectal cancer. The 5-FU dose was selected on the basis of dose-limiting toxicities (DLTs) during part I of the study. Patients received cetuximab (400 mg/m 2 initial dose and 250 mg/m 2 /week thereafter) and every 2 weeks irinotecan (180 mg/m 2 ), FA (400 mg/m 2 ) and 5-FU (either low dose [LD], 300 mg/m 2 bolus plus 2,000 mg/m 2 46-hour infusion, n = 7; or, high-dose [HD], 400 mg/m 2 bolus plus 2,400 mg/m 2 ; n = 45). Only two DLTs occurred in the HD group, and HD 5-FU was selected for use in part II. Apart from rash, commonly observed grade 3/4 adverse events such as leucopenia, diarrhoea, vomiting and asthenia occurred within the expected range for FOLFIRI. Among 52 patients, the overall response rate was 48%. Median progression-free survival (PFS) was 8.6 months (counting all reported progressions) and the median overall survival was 22.4 months. Treatment facilitated the resection of initially unresectable metastases in fourteen patients (27%): of these, 10 patients (71%) had no residual tumour after surgery, and these resections hindered the estimation of PFS. The combination of cetuximab and FOLFIRI was active and well tolerated in this setting. Initially unresectable metastases became resectable in one-quarter of patients, with a high number of complete resections, and these promising results formed the basis for the investigation of FOLFIRI with and without cetuximab in the phase III CRYSTAL trial

  8. Cetuximab in combination with irinotecan/5-fluorouracil/folinic acid (FOLFIRI in the initial treatment of metastatic colorectal cancer: a multicentre two-part phase I/II study

    Directory of Open Access Journals (Sweden)

    Cals Laurent

    2009-04-01

    Full Text Available Abstract Background This study was designed to investigate the efficacy and safety of the epidermal growth factor receptor (EGFR inhibitor cetuximab combined with irinotecan, folinic acid (FA and two different doses of infusional 5-fluorouracil (5-FU in the first-line treatment of EGFR-detectable metastatic colorectal cancer. Methods The 5-FU dose was selected on the basis of dose-limiting toxicities (DLTs during part I of the study. Patients received cetuximab (400 mg/m2 initial dose and 250 mg/m2/week thereafter and every 2 weeks irinotecan (180 mg/m2, FA (400 mg/m2 and 5-FU (either low dose [LD], 300 mg/m2 bolus plus 2,000 mg/m2 46-hour infusion, n = 7; or, high-dose [HD], 400 mg/m2 bolus plus 2,400 mg/m2; n = 45. Results Only two DLTs occurred in the HD group, and HD 5-FU was selected for use in part II. Apart from rash, commonly observed grade 3/4 adverse events such as leucopenia, diarrhoea, vomiting and asthenia occurred within the expected range for FOLFIRI. Among 52 patients, the overall response rate was 48%. Median progression-free survival (PFS was 8.6 months (counting all reported progressions and the median overall survival was 22.4 months. Treatment facilitated the resection of initially unresectable metastases in fourteen patients (27%: of these, 10 patients (71% had no residual tumour after surgery, and these resections hindered the estimation of PFS. Conclusion The combination of cetuximab and FOLFIRI was active and well tolerated in this setting. Initially unresectable metastases became resectable in one-quarter of patients, with a high number of complete resections, and these promising results formed the basis for the investigation of FOLFIRI with and without cetuximab in the phase III CRYSTAL trial.

  9. Mine waste disposal and managements

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, Young Wook; Min, Jeong Sik; Kwon, Kwang Soo; Kim, Ok Hwan; Kim, In Kee; Song, Won Kyong; Lee, Hyun Joo [Korea Institute of Geology Mining and Materials, Taejon (Korea)

    1998-12-01

    Acid Rock Drainage (ARD) is the product formed by the atmospheric oxidation of the relatively common pyrite and pyrrhotite. Waste rock dumps and tailings containing sulfide mineral have been reported at toxic materials producing ARD. Mining in sulphide bearing rock is one of activity which may lead to generation and release of ARD. ARD has had some major detrimental affects on mining areas. The purpose of this study was carried out to develop disposal method for preventing contamination of water and soil environment by waste rocks dump and tailings, which could discharge the acid drainage with high level of metals. Scope of this study was as following: environmental impacts by mine wastes, geochemical characteristics such as metal speciation, acid potential and paste pH of mine wastes, interpretation of occurrence of ARD underneath tailings impoundment, analysis of slope stability of tailings dam etc. The following procedures were used as part of ARD evaluation and prediction to determine the nature and quantities of soluble constituents that may be washed from mine wastes under natural precipitation: analysis of water and mine wastes, Acid-Base accounting, sequential extraction technique and measurement of lime requirement etc. In addition, computer modelling was applied for interpretation of slope stability od tailings dam. (author). 44 refs., 33 tabs., 86 figs.

  10. Borehole disposal of spent radiation sources: 1. Principles

    International Nuclear Information System (INIS)

    Blerk, J.J. van; Kozak, M.W.

    2000-01-01

    Large numbers of spent radiation sources from the medical and other technical professions exist in many countries, even countries that do not possess facilities related to the nuclear fuel cycle, that have to be disposed. This is particularly the case in Africa, South America and some members of the Russian Federation. Since these sources need to be handled separately from the other types of radioactive waste, mainly because of their activity to volume ratio, countries (even those with access to operational repositories) find it difficult to manage and dispose this waste. This has led to the use of boreholes as disposal units for these spent sources by some members of the Russian Federation and in South Africa. However, the relatively shallow boreholes used by these countries are not suitable for the disposal of isotopes with long half-lifes, such as 226 Ra and 241 Am. With this in mind the Atomic Energy Corporation of South Africa initiated the development of the BOSS disposal concept - an acronym for Borehole disposal Of Spent Sources - as part of an International Atomic Energy Agency (IAEA) AFRA I-14 Technical Corporation (TC) project. In this paper, the principles of this disposal concept, which is still under development, will be discussed. (author)

  11. Psychological impact of colostomy pouch change and disposal.

    Science.gov (United States)

    McKenzie, Frances; White, Craig A; Kendall, Sally; Finlayson, Aileen; Urquhart, Mary; Williams, Isabel

    This article presents some of the findings from a multicentre cross-sectional correlational study to evaluate the relationship between colostomy pouch change and disposal practices and the patient's psychological wellbeing. Five questionnaires were used in a one-off interview with 86 patients. Patients were assessed at between one and four months postoperatively. Results from the Pouch Change and Disposal questionnaire showed that only 25% of patients found disposal of used appliances the most difficult part of their pouch change and disposal routine. Half felt that their body was out of their control and 33% reported avoiding social and leisure activities due to what was involved in their pouch change and disposal routine. Patients cited several factors, such as minimizing odour and having an appliance that could flush away, as factors which would help them to stop avoiding these activities. Stoma care nurses have a unique opportunity to improve the psychological wellbeing of their patients by considering the aspects of pouch change and disposal that pose the greatest challenge to individuals. Use of a modified version of the Pouch Change and Disposal questionnaire may be a useful tool in identifying those at risk of impaired quality of life.

  12. Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3

    Energy Technology Data Exchange (ETDEWEB)

    Hamm, L. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

    2013-07-29

    Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

  13. Disposal of spent fuel from German nuclear power plants - 16028

    International Nuclear Information System (INIS)

    Graf, Reinhold; Brammer, Klaus-Juergen; Filbert, Wolfgang; Bollingerfehr, Wilhelm

    2009-01-01

    The 'direct disposal of spent fuel' as a part of the current German reference concept was developed as an alternative to spent fuel reprocessing and vitrified HLW disposal. The technical facilities necessary for the implementation of this part of the reference concept, the so called POLLUX R concept, i.e. interim storage buildings for casks containing spent fuel, a pilot conditioning facility, and a special cask 'POLLUX' for final disposal have been built. With view to a geological salt formation all handling procedures for the direct disposal of spent fuel were tested aboveground in full-scale test facilities. To optimise the reference concept, all operational steps have been reviewed for possible improvements. The two additional concepts for the direct disposal of SF are the BSK 3 concept and the DIREGT concept. Both concepts rely on borehole emplacement technology, vertical boreholes for the BSK 3 concept und horizontal boreholes for the DIREGT concept. Supported by the EU and the German Federal Ministry of Economics and Technology (BMWi), DBE TECHNOLOGY built an aboveground full-scale test facility to simulate all relevant handling procedures for the BSK 3 disposal concept. GNS (Company for Nuclear Service), representing the German utilities, provided the main components and its know-how concerning cask design and manufacturing. The test program was concluded recently after more than 1.000 emplacement operations had been performed successfully. The BSK 3 emplacement system in total comprises an emplacement device, a borehole lock, a transport cart, a transfer cask which will shuttle between the aboveground conditioning facility and the underground repository, and the BSK 3 canister itself, designed to contain the fuel rods of three PWR-fuel assemblies with a total of about 1.6 tHM. The BSK 3 concept simplifies the operation of the repository because the handling procedures and techniques can also be applied for the disposal of reprocessing residues. In addition

  14. Geological disposal system development

    International Nuclear Information System (INIS)

    Kang, Chul Hyung; Kuh, J. E.; Kim, S. K. and others

    2000-04-01

    Spent fuel inventories to be disposed of finally and design base spent fuel were determined. Technical and safety criteria for a geological repository system in Korea were established. Based on the properties of spent PWR and CANDU fuels, seven repository alternatives were developed and the most promising repository option was selected by the pair-wise comparison method from the technology point of view. With this option preliminary conceptual design studies were carried out. Several module, e.g., gap module, congruent release module were developed for the overall assessment code MASCOT-K. The prominent overseas databases such as OECD/NEA FEP list were are fully reviewed and then screened to identify the feasible ones to reflect the Korean geo-hydrological conditions. In addition to this the well known scenario development methods such as PID, RES were reviewed. To confirm the radiological safety of the proposed KAERI repository concept the preliminary PA was pursued. Thermo-hydro-mechanical analysis for the near field of repository were performed to verify thermal and mechanical stability for KAERI repository system. The requirements of buffer material were analyzed, and based on the results, the quantitative functional criteria for buffer material were established. The hydraulic and swelling property, mechanical properties, and thermal conductivity, the organic carbon content, and the evolution of pore water chemistry were investigated. Based on the results, the candidate buffer material was selected

  15. Research on geological disposal

    International Nuclear Information System (INIS)

    Uchida, Masahiro

    2011-01-01

    The aims of this research are to develop criteria for reviewing acceptability of the adequacy of the result of Preliminary and Detailed Investigations submitted by the implementor, and to establish a basic policy to secure safety for safety review. In FY 2010, 13 geology/climate related events for development of acceptance criteria for reviewing the adequacy of the result of Preliminary and Detailed Investigations were extracted. And the accuracy of geophysical exploration methods necessary for the Preliminary Investigation was evaluated. Regarding the research for safety review, we developed an idea of safety concept of Japanese geological disposal, and analyzed basic safety functions to secure safety. In order to verify the groundwater flow evaluation methods developed in regulatory research, the hydrological and geochemical data at Horonobe, northern Hokkaido were obtained, and simulated result of regional groundwater flow were compared with measured data. And we developed the safety scenario of geology/climate related events categorized by geological and geomorphological properties. Also we created a system to check the quality of research results in Japan and other countries in order to utilize for safety regulation, and developed a database system to compile them. (author)

  16. Researching radioactive waste disposal

    International Nuclear Information System (INIS)

    Feates, F.; Keen, N.

    1976-01-01

    At present it is planned to use the vitrification process to convert highly radioactive liquid wastes, arising from nuclear power programme, into glass which will be contained in steel cylinders for storage. The UKAEA in collaboration with other European countries is currently assessing the relative suitability of various natural geological structures as final repositories for the vitrified material. The Institute of Geological Sciences has been commissioned to specify the geological criteria that should be met by a rock structure if it is to be used for the construction of a repository though at this stage disposal sites are not being sought. The current research programme aims to obtain basic geological data about the structure of the rocks well below the surface and is expected to continue for at least three years. The results in all the European countries will then be considered so that the United Kingdom can choose a preferred method for isolating their wastes. It is only at that stage that a firm commitment may be made to select a site for a potential repository, when a far more detailed scientific research study will be instituted. Heat transfer problems and chemical effects which may occur within and around repositories are being investigated and a conceptual design study for an underground repository is being prepared. (U.K.)

  17. Geological disposal system development

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Chul Hyung; Kuh, J. E.; Kim, S. K. and others

    2000-04-01

    Spent fuel inventories to be disposed of finally and design base spent fuel were determined. Technical and safety criteria for a geological repository system in Korea were established. Based on the properties of spent PWR and CANDU fuels, seven repository alternatives were developed and the most promising repository option was selected by the pair-wise comparison method from the technology point of view. With this option preliminary conceptual design studies were carried out. Several module, e.g., gap module, congruent release module were developed for the overall assessment code MASCOT-K. The prominent overseas databases such as OECD/NEA FEP list were are fully reviewed and then screened to identify the feasible ones to reflect the Korean geo-hydrological conditions. In addition to this the well known scenario development methods such as PID, RES were reviewed. To confirm the radiological safety of the proposed KAERI repository concept the preliminary PA was pursued. Thermo-hydro-mechanical analysis for the near field of repository were performed to verify thermal and mechanical stability for KAERI repository system. The requirements of buffer material were analyzed, and based on the results, the quantitative functional criteria for buffer material were established. The hydraulic and swelling property, mechanical properties, and thermal conductivity, the organic carbon content, and the evolution of pore water chemistry were investigated. Based on the results, the candidate buffer material was selected.

  18. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Cluchet, J.; Roger, B.

    1975-10-01

    After mentioning the importance of the problem of the disposal of wastes produced in the electro-nuclear industry, a short reminder on a few laws of radioactivity (nature and energy of radiations, half-life) and on some basic dosimetry is given. The conditioning and storage procedures are then indicated for solid wastes. The more active fractions of liquid wastes are incorporated into blocks of glass, whereas the less active are first concentrated by chemical treatments or by evaporation. The concentrates are then embedded into concrete, asphalt or resins. Storage is done according to the nature of each type of wastes: on a hard-surfaced area or inside concrete-lined trenches for the lowest radioactivity, in pits for the others. Transuranium elements with very long half-lives are buried in very deep natural cavities which can shelter them for centuries. From the investigations conducted so far and from the experience already gained, it can be concluded that safe solutions are within our reach [fr

  19. Radwaste disposal drum centrifuge

    International Nuclear Information System (INIS)

    Rubin, L.S.; Deltete, C.P.; Crook, M.R.

    1988-01-01

    The drum or processing bowl of the DDC becomes the disposal container when the filling operation is completed. Rehandling of the processed resin is eliminated. By allowing the centrifugally compacted resin to remain in the processing container, extremely efficient waste packaging can be achieved. The dewatering results and volume reductions reported during 1986 were based upon laboratory scale testing sponsored by the Electric Power Research Institute (EPRI) and the Department of Energy (DOE). Since the publication of these preliminary results, additional testing using a full-scale prototype DDC has been completed, again under the auspices of the DOE. Full-scale testing has substantiated the results of earlier testing and has formed the basis for preliminary discussions with the U.S. Nuclear Regulatory Commission (NRC) regarding DDC licensing for radioactive applications. A comprehensive Topical Report and Process Control Program is currently being prepared for submittal to the NRC for review under a utility licensing action. Detailed cost-benefit analyses for actual plant operations have been prepared to substantiate the attractiveness of the DDC. Several methods to physically integrate a DDC into a nuclear power plant have also been developed

  20. Performance assessment strategy for low-level waste disposal sites

    International Nuclear Information System (INIS)

    Starmer, R.J.; Deering, L.G.; Weber, M.F.

    1988-01-01

    This paper describes US Nuclear Regulatory Commission (NRC) staff views on predicting the performance of low-level radioactive waste disposal facilities. Under the Atomic Energy Act, as amended, and the Low Level Radioactive Waste Policy Act, as amended, the NRC and Agreement States license land disposal of low-level radioactive waste (LLW) using the requirements in 10 CFR Part 61 or comparable state requirements. The purpose of this paper is to briefly describe regulatory requirements for performance assessment in low-level waste licensing, a strategy for performance assessments to support license applications, and NRC staff licensing evaluation of performance assessments. NRC's current activities in developing a performance assessment methodology will provide an overall systems modeling approach for assessing the performance of LLW disposal facilities. NRC staff will use the methodology to evaluate performance assessments conducted by applicants for LLW disposal facilities. The methodology will be made available to states and other interested parties

  1. Scenarios of the TWRS low-level waste disposal program

    International Nuclear Information System (INIS)

    1994-10-01

    As a result of past Department of Energy (DOE) weapons material production operations, Hanford now stores nuclear waste from processing facilities in underground tanks on the 200 Area plateau. An agreement between the DOE, the Environmental Protection Agency (EPA), and the Washington state Department of Ecology (the Tri-Party Agreement, or TPA) establishes an enforceable schedule and a technical framework for recovering, processing, solidifying, and disposing of the Hanford tank wastes. The present plan includes retrieving the tank waste, pretreating the waste to separate into low level and high level streams, and converting both streams to a glass waste form. The low level glass will represent by far the largest volume and lowest quantity of radioactivity (i.e., large volume of waste chemicals) of waste requiring disposal. The low level glass waste will be retrievably stored in sub-surface disposal vaults for several decades. If the low level disposal system proves to be acceptable, the disposal site will be closed with the low level waste in place. If, however, at some time the disposal system is found to be unacceptable, then the waste can be retrieved and dealt with in some other manner. WHC is planning to emplace the waste so that it is retrievable for up to 50 years after completion of the tank waste processing. Acceptability of disposal of the TWRS low level waste at Hanford depends on technical, cultural, and political considerations. The Performance Assessment is a major part of determining whether the proposed disposal action is technically defensible. A Performance Assessment estimates the possible future impact to humans and the environment for thousands of years into the future. In accordance with the TPA technical strategy, WHC plans to design a near-surface facility suitable for disposal of the glass waste

  2. Aspectos da Reologia e da Estabilidade de Suspensões Cerâmicas. Parte III: Mecanismo de Estabilização Eletroestérica de Suspensões com Alumina Aspects of Rheology and Stability of Ceramic Suspensions. Part III: Electrosteric Stabilization Mechanism of Alumina Suspensions

    Directory of Open Access Journals (Sweden)

    F. S. Ortega

    1997-08-01

    Full Text Available Esta terceira e última parte da revisão sobre os aspectos reológicos e de estabilização de suspensões com pós cerâmicos vem reunir a aplicação dos conhecimentos adquiridos nas primeiras duas partes publicadas anteriormente. Aqui, os fenômenos eletrostático devido à dupla camada elétrica, e estérico, relacionado à adsorção de moléculas poliméricas, são combinados para explicar o mecanismo eletroestérico de estabilização de suspensões cerâmicas. Os defloculantes que atuam através desse mecanismo abrangem uma classe específica de polímero denominada polieletrólitos, a qual é constituída por macromoléculas ionizáveis quando em solução. O estudo da forma com que os polieletrólitos atuam justifica-se devido à larga utilização desta classe de polímeros na indústria cerâmica. Os ácidos poliacrílico (PAA e polimetacrílico (PMAA são exemplos de polieletrólitos amplamente utilizados no processo de materiais à base de alumina. Dá-se destaque à influência do pH do meio e da presença de íons, sendo novamente aqui importante o conceito de força iônica da suspensão. Como aplicação prática, apresenta-se a estabilidade do sistema alumina-PMAA, reportando-se sobre o comportamento da viscosidade e da efetiva defloculação da suspensão. Este estudo é concluído apresentando resultados do efeito do peso molecular sobre a viscosidade, chamando atenção para o fato de que não basta definir apenas a classe de polímero a ser usada, sendo também fundamental especificar o peso molecular médio do polímero selecionado.The third and last part of this review about stabilization and rheological aspects of ceramic suspension gathers the knowledge in the two parts previously published. Here, the electrostatic and steric phenomena, related to the electrical double layer and polymeric molecules adsorption, respectively, are combined to explain the electrosteric stabilization mechanism of ceramic suspensions. The

  3. Recycling And Disposal Of Waste

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ui So

    1987-01-15

    This book introduces sewage disposal sludge including properties of sludge and production amount, stabilization of sludge by anaerobic digestion stabilization of sludge by aerobic digestion, stabilization of sludge by chemical method, and dewatering, water process sludge, human waste and waste fluid of septic tank such as disposal of waste fluid and injection into the land, urban waste like definition of urban waste, collection of urban waste, recycling, properties and generation amount, and disposal method and possibility of injection of industrial waste into the ground.

  4. FFTF disposable solid waste cask

    Energy Technology Data Exchange (ETDEWEB)

    Thomson, J. D.; Goetsch, S. D.

    1983-01-01

    Disposal of radioactive waste from the Fast Flux Test Facility (FFTF) will utilize a Disposable Solid Waste Cask (DSWC) for the transport and burial of irradiated stainless steel and inconel materials. Retrievability coupled with the desire for minimal facilities and labor costs at the disposal site identified the need for the DSWC. Design requirements for this system were patterned after Type B packages as outlined in 10 CFR 71 with a few exceptions based on site and payload requirements. A summary of the design basis, supporting analytical methods and fabrication practices developed to deploy the DSWC is provided in this paper.

  5. FFTF disposable solid waste cask

    International Nuclear Information System (INIS)

    Thomson, J.D.; Goetsch, S.D.

    1983-01-01

    Disposal of radioactive waste from the Fast Flux Test Facility (FFTF) will utilize a Disposable Solid Waste Cask (DSWC) for the transport and burial of irradiated stainless steel and inconel materials. Retrievability coupled with the desire for minimal facilities and labor costs at the disposal site identified the need for the DSWC. Design requirements for this system were patterned after Type B packages as outlined in 10 CFR 71 with a few exceptions based on site and payload requirements. A summary of the design basis, supporting analytical methods and fabrication practices developed to deploy the DSWC is provided in this paper

  6. Study on the background information for the geological disposal concept

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Murano, Tohru; Hirusawa, Shigenobu; Komoto, Harumi

    1999-11-01

    Japan Nuclear Cycle Development Institute (JNC) has published the first R and D progress report in 1992. In which the fruits of the R and D works were compiled. Since then the next step of R and D has been developing progressively in Japan. Now JNC has a plan to make the second R and D progress report until before 2000, in which information on the geological disposal of high level radioactive waste(HLW) will be presented to show the technical reliability and technical basis to contribute for the site selection or the safety-standard developments. Recognizing the importance of the social consensus to the geological disposal of international discussions in 1990's, understanding and consensus by the society are essential to the development and realization of the geological disposal of HLW. For getting social understanding and consensus, it is quite important to present the broad basis background information on the geological disposal of HLW, together with the technical basis and also the international discussion of the issues. In this report, the following studies have been done to help to prepare the background information for the 2nd R and D progress report, based on the recent informations and research and assessment works of last 2 years. These are, (1) As the part of general discussion, characteristics of HLW disposal and several issues to be considered for establishing the measures of the disposal of HLW were identified and analyzed from both practical and logical points of view. Those issues were the concept and image of the long term safety measures, the concept and criteria of geological disposal, and, safety assessment and performance assessment. (2) As the part of specific discussion, questions and concerns frequently raised by the non-specialists were taken up and 10 topics in relation to the geological disposal have been identified based on the discussion. Scientific and technical facts, consensus by the specialists on the issues, and international

  7. Waste isolation pilot plant disposal room model

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, B.M.

    1997-08-01

    This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the {open_quotes}Disposal Room Model,{close_quotes} describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized.

  8. Maintenance of records for radioactive waste disposal

    International Nuclear Information System (INIS)

    1999-07-01

    The safety of the radioactive waste disposal concepts does not rely on long term institutional arrangements. However, future generations may need information related to repositories and the wastes confined in them. The potentially needed information therefore has to be identified and collected. A suitable system for the preservation of that information needs to be created as a part of the disposal concept beginning with the planning phase. The IAEA has prepared this technical report to respond to the needs of Member States having repositories or involved in or considering the development of repositories. In many countries policies and systems for record keeping and maintenance of information related to disposal are the subjects of current interest. This report describes the requirements for presenting information about repositories for radioactive waste including long lived and transuranic waste and spent fuel if it is declared as a waste. The report discussed topics of identification, transfer and long term retention of high level information pertaining to the repository in a records management system (RMS) for retrieval if it becomes necessary in the future

  9. Waste isolation pilot plant disposal room model

    International Nuclear Information System (INIS)

    Butcher, B.M.

    1997-08-01

    This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the open-quotes Disposal Room Model,close quotes describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized

  10. Ocean disposal of radioactive waste: Status report

    International Nuclear Information System (INIS)

    Calmet, D.P.

    1989-01-01

    For hundreds of years, the seas have been used as a place to dispose of wastes resulting from human activities and although no high level radioactive waste (HLW) has been disposed of into the sea, variable amounts of packaged low level radioactive waste (LLW) have been dumped at more than 50 sites in the northern part of the Atlantic and Pacific oceans. So far, samples of sea water, sediments and deep sea organisms collected on the various sites have not shown any excess in the levels of radionuclides above those due to nuclear weapons fallout except on certain occasions where caesium and plutonium were detected at higher levels in samples taken close to packages at the dumping site. Since 1957, the date of its first meeting to design methodologies to assess the safety of ''radioactive waste disposal into the sea'', the IAEA has provided guidance and recommendations for ensuring that disposal of radioactive wastes into the sea will not result in unacceptable hazards to human health and marine organisms, damage to amenities or interference with other legitimate uses of the sea. Since the Convention for the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (referred to as the London Dumping Convention) came into force in 1975, the dumping of waste has been regulated on a global scale. The London Dumping Convention entrusted IAEA with specific responsibilities for the definition of high level radioactive wastes unsuitable for dumping at sea, and for making recommendations to national authorities for issuing special permits for ocean dumping of low level radioactive wastes. This paper presents a status report of immersion operations of low-level radioactive waste and the current studies the IAEA is undertaking on behalf of the LDC

  11. Spent fuel disposal problem in Bulgaria

    Energy Technology Data Exchange (ETDEWEB)

    Milanov, M; Stefanova, I [Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika

    1994-12-31

    The internationally agreed basic safety principles and criteria for spent fuel (SF) and high level waste (HLW) disposal are outlined. In the framework of these principles the specific problems of Bulgaria described in the `National Concept for Radioactive Waste Management and Disposal in Republic of Bulgaria` are discussed. The possible alternatives for spent fuel management are: (1) sending the spent fuel for disposal in other country; (2) once-through cycle and (3) closed fuel cycle. A mixed solution of the problem is implemented in Bulgaria. According to the agreement between Bulgaria and former Soviet Union a part of the spent fuel has been returned to Russia. The once-through and closed-fuel cycle are also considered. The projected cumulated amount of spent fuel is estimated for two cases: (1) the six units of Kozloduy NPP are in operation till the end of their lifetime (3300 tHM) and (2) low estimate (2700 tHM) - only units 5 and 6 are operated till the end of their lifetime. The reprocessing of the total amount of 3300 tHM will lead to the production of about 370 m{sup 3} vitrified high level wastes. Together with the HLW about 1850 m{sup 3} cladding hulls and 7800 m{sup 3} intermediate-level wastes will be generated, which should be disposed off in deep geological repository. The total production of radioactive waste in once-through cycle is 181 000 m{sup 3}, and in closed cycle - 190 000 m{sup 3}. Geological investigations are performed resulting in categorization of the territory of the country based on geological, geotechnical and hydrogeological conditions. This will facilitate the choice of the most suitable location for deep geological repository. 7 figs., 11 refs.

  12. Disposal of old printed journals

    Indian Academy of Sciences (India)

    2018-02-21

    Feb 21, 2018 ... Notice inviting Tender for Disposal of Old Printed Journals & Old News Papers. Indian Academy of ... The competent authority also reserves the right to reject any or all the tenders without assigning any reason thereof. 19.

  13. Radioactive waste processing and disposal

    International Nuclear Information System (INIS)

    1980-01-01

    This compilation contains 4144 citations of foreign and domestic reports, journal articles, patents, conference proceedings, and books pertaining to radioactive waste processing and disposal. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

  14. The Remote Handled Immobilization Low-Activity Waste Disposal Facility Environmental Permits and Approval Plan

    International Nuclear Information System (INIS)

    DEFFENBAUGH, M.L.

    2000-01-01

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational

  15. Universal storage/transport/disposal packages

    International Nuclear Information System (INIS)

    Smith, M.L.

    1992-01-01

    In this paper a concept for a more robust Engineered Barrier System (EBS) that is part of an integrated waste management system is presented. This integrated system uses a thick walled metal package as the basic component of an integrated system for utility site storage, MRS storage, transportation, and disposal. Overpacks are used where necessary to supplement the basic package in each application. This integrated system combines the advantages of a robust EBS (improved margin and confidence in the repository) with a systems approach that can simplify the waste management system and reduce costs

  16. Americium product solidification and disposal

    International Nuclear Information System (INIS)

    Mailen, J.C.; Campbell, D.O.; Bell, J.T.; Collins, E.D.

    1987-01-01

    The americium product from the TRUEX processing plant needs to be converted into a form suitable for ultimate disposal. An evaluation of the disposal based on safety, number of process steps, demonstrated operability of the processes, production of low-level alpha waste streams, and simplicity of maintenance with low radiation exposures to personnel during maintenance, has been made. The best process is to load the americium on a cation exchange resin followed by calcination or oxidation of the resin after loading

  17. Financing of radioactive waste disposal

    International Nuclear Information System (INIS)

    Reich, J.

    1989-01-01

    Waste disposal is modelled as a financial calculus. In this connection the particularity is not primarily the dimension to be expected of financial requirement but above all the uncertainty of financial requirement as well as the ecological, socio-economic and especially also the temporal dimension of the Nuclear Waste Disposal project (disposal of spent fuel elements from light-water reactors with and without reprocessing, decommissioning = safe containment and disposal of nuclear power plants, permanent isolation of radioactive waste from the biosphere, intermediate storage). Based on the above mentioned factors the author analyses alternative approaches of financing or financial planning. He points out the decisive significance of the perception of risks or the evaluation of risks by involved or affected persons - i.e. the social acceptance of planned and designed waste disposal concepts - for the achievement and assessment of alternative solutions. With the help of an acceptance-specific risk measure developed on the basis of a mathematical chaos theory he illustrates, in a model, the social influence on the financing of nuclear waste disposal. (orig./HP) [de

  18. Near-surface land disposal

    International Nuclear Information System (INIS)

    Kittel, J.H.

    1989-01-01

    The Radioactive Waste Management Handbook provides a comprehensive, systematic treatment of nuclear waste management. Near-Surface Land Disposal, the first volume, is a primary and secondary reference for the technical community. To those unfamiliar with the field, it provides a bridge to a wealth of technical information, presenting the technology associated with the near-surface disposal of low or intermediate level wastes. Coverage ranges from incipient planning to site closure and subsequent monitoring. The book discusses the importance of a systems approach during the design of new disposal facilities so that performance objectives can be achieved; gives an overview of the radioactive wastes cosigned to near-surface disposal; addresses procedures for screening and selecting sites; and emphasizes the importance of characterizing sites and obtaining reliable geologic and hydrologic data. The planning essential to the development of particular sites (land acquisition, access, layout, surface water management, capital costs, etc.) is considered, and site operations (waste receiving, inspection, emplacement, closure, stabilization, etc.) are reviewed. In addition, the book presents concepts for improved confinement of waste, important aspects of establishing a monitoring program at the disposal facility, and corrective actions available after closure to minimize release. Two analytical techniques for evaluating alternative technologies are presented. Nontechnical issues surrounding disposal, including the difficulties of public acceptance are discussed. A glossary of technical terms is included

  19. Republic of Korea. Closure concept development for LILW disposal facility in Republic of Korea

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear Environment Technology Institute (NETEC) of Korea Electric Power Corporation (KEPCO) is developing near surface disposal concepts for both a rock cavern type disposal facility, and a vault type facility; two types of facility are being considered to provide more options for LILW repository siting. The conceptual design for the vault type facility will be completed in 1999. As a part of conceptual design effort, a preliminary concept for the disposal facility closure has been identified

  20. Current direction, marine toxic substances, and other data from current meters and grab casts from the GUSS III and other platforms in support of the Brine Disposal project from 1977-10-20 to 1979-04-16 (NODC Accession 8000029)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, marine toxic substances, and other data from were collected from current meters and grab casts from the GUSS III and other platforms from 20...

  1. Oral Assessment Kit, Levels II & III. Draft.

    Science.gov (United States)

    Agrelo-Gonzalez, Maria; And Others

    The assessment packet includes a series of oral tests to help develop speaking as an integral part of second language instruction at levels II and III. It contains: 8 mini-tests for use at level II; 9 mini-tests for use at level III; a rating scale and score sheet masters for evaluating performance on these tests; and a collection of suggested…

  2. DISPOSABLE CANISTER WASTE ACCEPTANCE CRITERIA

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2001-07-30

    The purpose of this calculation is to provide the bases for defining the preclosure limits on radioactive material releases from radioactive waste forms to be received in disposable canisters at the Monitored Geologic Repository (MGR) at Yucca Mountain. Specifically, this calculation will provide the basis for criteria to be included in a forthcoming revision of the Waste Acceptance System Requirements Document (WASRD) that limits releases in terms of non-isotope-specific canister release dose-equivalent source terms. These criteria will be developed for the Department of Energy spent nuclear fuel (DSNF) standard canister, the Multicanister Overpack (MCO), the naval spent fuel canister, the High-Level Waste (HLW) canister, the plutonium can-in-canister, and the large Multipurpose Canister (MPC). The shippers of such canisters will be required to demonstrate that they meet these criteria before the canisters are accepted at the MGR. The Quality Assurance program is applicable to this calculation. The work reported in this document is part of the analysis of DSNF and is performed using procedure AP-3.124, Calculations. The work done for this analysis was evaluated according to procedure QAP-2-0, Control of Activities, which has been superseded by AP-2.21Q, Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities. This evaluation determined that such activities are subject to the requirements of DOE/RW/0333P, Quality Assurance Requirements and Description (DOE 2000). This work is also prepared in accordance with the development plan titled Design Basis Event Analyses on DOE SNF and Plutonium Can-In-Canister Waste Forms (CRWMS M&O 1999a) and Technical Work Plan For: Department of Energy Spent Nuclear Fuel Work Packages (CRWMS M&O 2000d). This calculation contains no electronic data applicable to any electronic data management system.

  3. Effects of post-disposal gas generation in a repository for spent fuel, high-level waste and long-lived intermediate level waste sited in opalinus clay

    International Nuclear Information System (INIS)

    Johnson, L.; Marschall, P.; Zuidema, P.; Gribi, P.

    2004-07-01

    This comprehensive report issued by the Swiss National Cooperative for the Disposal of Radioactive Waste NAGRA takes a look at post-disposal gas generation in a repository for spent fuel and highly radioactive wastes in Opalinus clay strata. This study provides a comprehensive treatment of the issue of gas generation in a repository for spent fuel (SF), vitrified high-level waste (HLW) and long-lived intermediate-level waste (ILW), sited in the Opalinus clay of the Zuercher Weinland in northern Switzerland. The issue of how gas generation in and transport from waste repositories may influence disposal system performance has been under study for many years, both at Nagra and internationally. The report consists of three main parts: (i) A synthesis of basic information on the host rock and on details of repository construction; (ii) A discussion on gas transport characteristics of the engineered barrier system and the geosphere; (iii) A discussion on the effects of gas on system performance, based on the available information on gas generation, gas transport properties and gas pathways provided in the previous parts of the report. Simplified model calculations based on a mass balance approach for the gas generated within the repository are presented and discussed

  4. The effects of transuranic separation on waste disposal

    International Nuclear Information System (INIS)

    1991-04-01

    Rogers and Associates Engineering has analyzed waste streams from fuel cycles involving actinide partitioning and transmutation to determine appropriate disposal facilities for the waste and the cost of disposal. The focus of the study is the economic impact of actinide partitioning and transmutation on waste disposal, although there is a qualitative discussion of the impacts of actinide burning on disposal risk. This effort is part of a multi-contractor task being coordinated by the Electric Power Research Institute to address the technical feasibility and economic impact of transuranic burning. Waste streams were defined by General Electric Corporation for eight alternative processing cases -- involving aqueous and pyrochemical processing of spent fuel from light water reactors and liquid metal reactors and for low-actinide-recovery and high-actinide-recovery technologies. Disposal options are determined for three possible futures: one involving the present socio-political-licensing environment and using cost estimates for existing or planned facilities, an optimistic future with lower siting and licensing costs, and a pessimistic future with high siting and licensing costs and some extraordinary measures to assure waste isolation. The optimistic future allows the disposal of certain types of waste in a facility that provides a degree of waste isolation that is intermediate between a repository and a low-level-waste facility. 30 refs., 18 figs., 45 tabs

  5. Waste management and the land disposal restriction storage prohibition

    International Nuclear Information System (INIS)

    1992-05-01

    RCRA Sect. 3004(j) prohibits storage of wastes that have been prohibited from land disposal, unless that storage is for the purpose of accumulating sufficient quantities of hazardous wastes to facilitate proper recovery, treatment, or disposal. This requirement was incorporated as part of the Land Disposal Restriction (LDR) regulations. Under the LDR storage prohibition, facilities may only store restricted wastes in containers and tanks. As stated in the Third LDR rule, storage of prohibited waste is only allowed in non-land based storage units since land-based storage is a form of disposal. The EPA has recognized that generators and storers of radioactive mixed waste (RMW) may find it impossible to comply with storage prohibition in cases where no available treatment capacity exists. Additionally, under the current regulatory interpretation, there is no provision that would allow for storage of wastes for which treatment capacity and capability are not available, even where capacity is legitimately being developed. Under the LDR program, restricted wastes that are disposed of, or placed into storage before an LDR effective date, are not subject to the LDR requirements. However, if such wastes are removed from a storage or disposal site after the effective date, such wastes would be subject to LDR requirements. The purpose of this information brief is to clarify what waste management practices constitute removal from storage

  6. Review of available options for low level radioactive waste disposal

    International Nuclear Information System (INIS)

    1992-07-01

    The scope of this report includes: descriptions of the options available; identification of important elements in the selection process; discussion and assessment of the relevance of the various elements for the different options; cost data indicating the relative financial importance of different parts of the systems and the general cost level of a disposal facility. An overview of the types of wastes included in low level waste categories and an approach to the LLW management system is presented. A generic description of the disposal options available and the main activities involved in implementing the different options are described. Detailed descriptions and cost information on low level waste disposal facility concepts in a number of Member States are given. Conclusions from the report are summarized. In addition, this report provides a commentary on various aspects of land disposal, based on experience gained by IAEA Member States. The document is intended to complement other related IAEA publications on LLW management and disposal. It also demonstrates that alternatives solutions for the final disposal of LLW are available and can be safely operated but the choice of an appropriate solution must be a matter for national strategy taking into account local conditions. 18 refs, 16 figs, 1 tab

  7. Liquid metal coolant disposal from UKAEA reactors at Dounreay

    International Nuclear Information System (INIS)

    Adam, E.R.

    1997-01-01

    As part of the United Kingdom's Fast Reactor Development programme two reactors were built and operated at Dounreay in the North of Scotland. DFR (Dounreay Fast Reactor) was operated from 1959-1977 and PFR (Prototype Fast Reactor) was operated from 1974-1994. Both reactors are currently undergoing Stage 1 Decommissioning and are installing plant to dispose of the bulk coolant (DFR ∼ 60 tonne; PFR ∼ 1500 tonne). The coolant (NaK) remaining at DFR is mainly in the primary circuit which contains in excess of 500 TBq of Cs137. Disposal of 40 tonnes of secondary coolant has already been carried out. The paper will describe the processes used to dispose of this secondary circuit coolant and how it is intended the remaining primary circuit coolant will be handled. The programme to process the primary coolant will also be described which involves the conversion of the liquid metal to caustic and its decontamination. No PFR coolant Na has been disposed off to date. The paper will describe the current decommissioning programme activities relating to liquid metal disposal and treatment describing the materials to be disposed of and the issue of decontamination of the effluents. (author)

  8. Sub-seabed disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Sivintsaev, Yu.V.

    1990-01-01

    The first stage of investigations of possibility of sub-seabed disposal of long-living intermediate-level radioactive wastes carried out by NIREX (UK) is described. Advantages and disadvantages of sub-seabed disposal of radioactive wastes are considered; regions suitable for disposal, transport means for marine disposal are described. Three types of sub-seabed burials are characterized

  9. Waste Water Disposal Design And Management I

    International Nuclear Information System (INIS)

    Yang, Sang Hyeon; Lee, Jung Su

    2004-04-01

    This book gives descriptions of waste water disposal, design and management, which includes design of waterworks and sewerage facility such as preparatory work and building plan, used waste water disposal facilities, waste water disposal plant and industrial waste water disposal facilities, water use of waste water disposal plant and design of pump and pump facilities such as type and characteristic, selection and plan, screening and grit.

  10. The legislation of nuclear disposal. Text booklet with an introduction

    International Nuclear Information System (INIS)

    Smeddinck, Ulrich

    2014-01-01

    The book on the legislation of nuclear waste disposal covers the following issues: Part A: Introduction in the site selection law. Part B: Set of regulations: Constitutional law of the Federal Republic of Germany (extract), Guideline 2011/70 EURATOM on the responsible and safe disposal of spent fuel elements, common agreement on the safety of spent fuel treatment and on the safety of radioactive waste conditioning, law on search and selection of final repository site for heat generating radioactive wastes (site selection law), law on the civil use of nuclear energy and the protection against its hazards (Atomic Law AtG), federal mining act (BBergG), law on environmental impact assessment (UVPG), Law on supplementary regulations and legal remedies in environmental matters according EU guideline 2003/35EG, law on the construction of a Federal authority for nuclear disposal (BfkEEG), regulation on the protection against ionizing radiation hazards (Strahlenschutzverordnung), regulation on the transport of radioactive wastes or spent fuel elements. Regulation on the commissioning processes of facilities according paragraph 7 Atomic law, regulation on the definition of a development freeze for site protection for a final disposal, regulation on the warranty of nuclear safety and radiation protection, implementing rule for the nuclear safety warranty, regulation on the advance financing for the construction of Federal facilities for safeguarding and final disposal of radioactive wastes. Cost regulation for the Atomic Law.

  11. 47 CFR 25.283 - End-of-life disposal.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false End-of-life disposal. 25.283 Section 25.283 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS... satellite orbit under this part shall be relocated, at the end of its useful life, barring catastrophic...

  12. Hazardous Waste Disposal Costs for The Defense Logistics Agency

    National Research Council Canada - National Science Library

    1999-01-01

    This audit is part of the overall audit, "DoD Hazardous Waste Disposal Costs," (Project No. 9CK-5021). The overall audit was jointly conducted by the Inspector General, DoD, and the Army, Navy, and Air Force audit agencies...

  13. Issues related to the USEPA probabilistic standard for geologic disposal of high-level radioactive waste

    International Nuclear Information System (INIS)

    Okrent, D.

    1993-01-01

    This paper asks whether some of the fundamental bases for the 1985 USEPA standard on disposal of high level radioactive wastes (40 CFR Part 191) warrant re-examination. Similar questions also apply to the bases for the radioactive waste disposal requirements proposed by most other countries. It is suggested that the issue of intergenerational equity has been dealt with from too narrow a perspective. Not only should radioactive and nonradioactive hazardous waste disposal be regulated from a consistent philosophic basis, but the regulation of waste disposal itself should be embedded in the broader issues of intergenerational conservation of options, conservation of quality, and conservation of access. (author). 25 refs

  14. Technical support document for the surface disposal of sewage sludge. Final report

    International Nuclear Information System (INIS)

    1992-11-01

    The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the surface disposal of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in sewage sludge placed on surface disposal sites. The management practices associated with surface disposal are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through surface disposal are discussed

  15. Technical support document for the surface disposal of sewage sludge. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1992-11-01

    The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the surface disposal of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in sewage sludge placed on surface disposal sites. The management practices associated with surface disposal are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through surface disposal are discussed.

  16. Vault submodel for the second interim assessment of the Canadian concept for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    LeNeveu, D.M.

    1986-02-01

    The consequences to man and the environment of the disposal of nuclear fuel waste are being studied within the Canadian Nuclear Fuel Waste Management Program. The concept being assessed is that of a sealed disposal vault at a depth of 1000 m in plutonic rock in the Canadian Shield. To determine the consequences, the vault and its environment are simulated using a SYstem Variability Analysis Code (SYVAC), a stochastic model of the disposal system. SYVAC contains three submodels that represent the three major parts of the disposal system: the vault, the geosphere and the biosphere. This report documents the conceptual and mathematical framework of the vault submodel

  17. Depleted uranium disposal options evaluation

    International Nuclear Information System (INIS)

    Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D.

    1994-05-01

    The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ''waste,'' but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity

  18. Waste disposal into the ground

    Energy Technology Data Exchange (ETDEWEB)

    Mawson, C A

    1955-07-01

    The establishment of an atomic energy project is soon followed by the production of a variety of radioactive wastes which must be disposed of safely, quickly and cheaply. Experience has shown that much more thought has been devoted to the design of plant and laboratories than to the apparently dull problem of what to do with the wastes, but the nature of the wastes which will arise from nuclear power production calls for a change in this situation. We shall not be concerned here with power pile wastes, but disposal problems which have occurred in operation of experimental reactors have been serious enough to show that waste disposal should be considered during the early planning stages. (author)

  19. Deep borehole disposal of plutonium

    International Nuclear Information System (INIS)

    Gibb, F. G. F.; Taylor, K. J.; Burakov, B. E.

    2008-01-01

    Excess plutonium not destined for burning as MOX or in Generation IV reactors is both a long-term waste management problem and a security threat. Immobilisation in mineral and ceramic-based waste forms for interim safe storage and eventual disposal is a widely proposed first step. The safest and most secure form of geological disposal for Pu yet suggested is in very deep boreholes and we propose here that the key to successful combination of these immobilisation and disposal concepts is the encapsulation of the waste form in small cylinders of recrystallized granite. The underlying science is discussed and the results of high pressure and temperature experiments on zircon, depleted UO 2 and Ce-doped cubic zirconia enclosed in granitic melts are presented. The outcomes of these experiments demonstrate the viability of the proposed solution and that Pu could be successfully isolated from its environment for many millions of years. (authors)

  20. Disposal facility for radioactive wastes

    International Nuclear Information System (INIS)

    Utsunomiya, Toru.

    1985-01-01

    Purpose: To remove heat generated from radioactive wastes thereby prevent the working circumstances from being worsened in a disposal-facility for radioactive wastes. Constitution: The disposal-facility comprises a plurality of holes dug out into the ground inside a tunnel excavated for the storage of radioactive wastes. After placing radioactive wastes into the shafts, re-filling materials are directly filled with a purpose of reducing the dosage. Further, a plurality of heat pipes are inserted into the holes and embedded within the re-filling materials so as to gather heat from the radioactive wastes. The heat pipes are connected to a heat exchanger disposed within the tunnel. As a result, heating of the solidified radioactive wastes itself or the containing vessel to high temperature can be avoided, as well as thermal degradation of the re-filling materials and the worsening in the working circumstance within the tunnel can be overcome. (Moriyama, K.)

  1. Antithrombin III blood test

    Science.gov (United States)

    ... medlineplus.gov/ency/article/003661.htm Antithrombin III blood test To use the sharing features on this page, ... a protein that helps control blood clotting. A blood test can determine the amount of AT III present ...

  2. Waste disposal developments within BNFL

    International Nuclear Information System (INIS)

    Johnson, L.F.

    1989-01-01

    British Nuclear Fuels plc has broad involvement in topics of radioactive waste generation, treatment, storage and disposal. The Company's site at Drigg has been used since 1959 for the disposal of low level waste and its facilities are now being upgraded and extended for that purpose. Since September 1987, BNFL on behalf of UK Nirex Limited has been managing an investigation of the Sellafield area to assess its suitability for deep underground emplacement of low and intermediate level radioactive wastes. An approach will be described to establish a partnership with the local community to work towards a concept of monitored, underground emplacement appropriate for each waste category. (author)

  3. Radioactive waste disposal and constitution

    International Nuclear Information System (INIS)

    Stober, R.

    1983-01-01

    The radioactive waste disposal has many dimensions with regard to the constitutional law. The central problem is the corret delimitation between adequate governmental precautions against risks and or the permitted risk which the state can impose on the citizen, and the illegal danger which nobody has to accept. The solution requires to consider all aspects which are relevant to the constitutional law. Therefore, the following analysis deals not only with the constitutional risks and the risks of the nuclear energy, but also with the liberal, overall-economic, social, legal, and democratic aspects of radioactive waste disposal. (HSCH) [de

  4. TMI abnormal wastes disposal options

    International Nuclear Information System (INIS)

    Ayers, A.L. Jr.

    1984-03-01

    A substantial quantity of high beta-gamma/high-TRU contaminated wastes are expected from cleanup activities of Unit 2 of the Three Mile Island Nuclear Power Station. Those wastes are not disposable because of present regulatory constraints. Therefore, they must be stored temporarily. This paper discusses three options for storage of those wastes at the Idaho National Engineering Laboratory: (1) storage in temporary storage casks; (2) underground storage in vaults; and (3) storage in silos at a hot shop. Each option is analyzed and evaluated. Also included is a discussion of future disposal strategies, which might be pursued when a suitable federal or commercial repository is built

  5. Sewage sludge disposal in Austria

    International Nuclear Information System (INIS)

    Koch, F.

    1997-01-01

    Sewage systems serve about 70% of the Austrian population, producing 6 million m 3 of sewage sludge per year with a dry matter content of 4-5%. At present about 52% of this sludge is disposed of in land fills, 33% is incinerated, and only about 15 % is used in agriculture. Although agricultural utilization is becoming increasingly important, several problems, especially those related to public opinion, need to be resolved before increased use will be possible. In this paper, wastewater treatment and sewage-sludge production in Austria, and problems associated with sludge disposal are discussed. (author)

  6. Final disposal of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Kroebel, R [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Wiederaufarbeitung und Abfallbehandlung; Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Abt. zur Behandlung Radioaktiver Abfaelle

    1978-08-01

    This paper discusses the final disposal possibilities for radioactive wastes in the Federal Republic of Germany and the related questions of waste conditioning, storage methods and safety. The programs in progress in neighbouring CEC countries and in the USA are also mentioned briefly. The autors conclude that the existing final disposal possibilities are sufficiently well known and safe, but that they could be improved still further by future development work. The residual hazard potential of radioactive wastes from fuel reprocessing after about 1000 years of storage is lower that of known inorganic core deposits.

  7. Disposal of Hanford defense waste

    International Nuclear Information System (INIS)

    Holten, R.A.; Burnham, J.B.; Nelson, I.C.

    1986-01-01

    An Environmental Impact Statement (EIS) on the disposal of Hanford Defense Waste is scheduled to be released near the end of March, 1986. This EIS will evaluate the impacts of alternatives for disposal of high-level, tank, and transuranic wastes which are now stored at the Department of Energy's Hanford Site or will be produced there in the future. In addition to releasing the EIS, the Department of Energy is conducting an extensive public participation process aimed at providing information to the public and receiving comments on the EIS

  8. Salt formations offer disposal alternative

    International Nuclear Information System (INIS)

    Funderburk, R.

    1990-01-01

    This paper discusses how three U.S. firms are spending millions to permit and build underground disposal sites in salt formations. These companies claim salt is the ideal geological medium for holding hazardous wastes. Two Texas locations and one in Michigan have been targeted as future sites for hazardous waste disposal. The Michigan site, outside Detroit, is a former salt mine 2,000 feet beneath the Ford Motor Co. (Detroit) assembly works in Dearborn. Both Texas sites are atop salt domes---one east and one west of Houston

  9. Iron oxide redox chemistry and nuclear fuel disposal

    International Nuclear Information System (INIS)

    Jobe, D.J.; Lemire, R.J.; Taylor, P.

    1997-04-01

    Solubility and stability data for iron (III) oxides and aqueous Fe(II) and Fe(III) species are reviewed, and selected values are used to calculate potential-pH diagrams for the iron system at temperatures of 25 and 100 deg C, chloride activities {C1 - } = 10 -2 and 1 mol/kg, total carbonate activity {C T } = 10 -3 mol/kg, and iron(III) oxide/oxyhydroxide solubility products (25 deg C values) K sp = {Fe 3+ }{OH - } 3 = 10 -38.5 , 10 -40 and 10 -42 . The temperatures and anion concentrations bracket the range of conditions expected in a Canadian nuclear fuel waste disposal vault. The three solubility products represent a conservative upper limit, a most probable value, and a minimum credible value, respectively, for the iron oxides likely to be important in controlling redox conditions in a disposal vault for CANDU nuclear reactor fuel. Only in the first of these three cases do the calculated redox potentials significantly exceed values under which oxidative dissolution of the fuel may occur. (author)

  10. Disposal modelling-dose and risk to man

    International Nuclear Information System (INIS)

    Lever, D.A.

    1988-01-01

    The disposal of radioactive wastes in geological formations is being considered throughout the world. There is widespread agreement that this is feasible using conventional technology and that it can be accomplished to the same high standards applicable to other parts of the nuclear industry. The safety philosophy is one of containment by multiple barriers, which are to a large extent independent of one another. The consequences for these barriers and the overall assessment of having a substantial organic component in ILW that has been encapsulated in cement before being disposed into a deep underground repository is reviewed. (author)

  11. Swiss projects for the final disposal of radioactive wastes

    International Nuclear Information System (INIS)

    McCombie, C.

    1987-01-01

    At present, the major part of the discussion does not focus on technical assessment methodology and data, but rather on interpretation of the available geologic data for high-level waste disposal planning. Meanwhile, plans for the implementation of repositories have to be developed. Accordingly, the longer-term studies on high-level waste disposal are proceeding at a pace appropriate for their relatively far-future timescales, and intensified efforts are being put into projects for design, siting, safety assessment and construction of the more urgently required repository for low and intermediate level waste. (orig./PW) [de

  12. Treatment and disposal techniques of dangerous municipal solid wastes

    International Nuclear Information System (INIS)

    Beone, G.; Carbone, A.I.; Zagaroli, M.

    1989-01-01

    This paper describes the qualitative and quantitative features of the different types of dangerous municipal solid wastes, according to Italian law. In the second part the impact on environment and man health is presented. This impact should be minimized by suitable controlled disposal techniques, which differ from other municipal waste treatments. Finally, the paper deals with the most appropriate systems for treatment and disposal of such kind of waste. Particularly, some research activities in the field of metal recovery from used batteries, sponsored by ENEA, and carrying out by private companies, are described. (author)

  13. Process for preparing wastes for non-pollutant disposal

    International Nuclear Information System (INIS)

    Rosenstiel, T.L.; Debus, A.A.G.

    1984-01-01

    In disposing of wastes, particularly toxic wastes, containing organic liquids, i.e. solvents or oil, which may be radio-active a non-ionic surface active agent which is a polyoxy alkylphenol is added to the oily material and then calcium sulphate hemihydrate and water are added. This forms part of a process in which a melamine resin is also added to the mix which is then allowed to harden and the hardened mass disposed of. The use of polyoxyethylene glycol soaps as emulsifying agents is also referred to. Preferred soaps are tallates and preferred alkyl groups in the alkylphenol are octyl and ronyl. (author)

  14. Summary of EPA's risk assessment results from the analysis of alternative methods of low-level waste disposal

    International Nuclear Information System (INIS)

    Bandrowski, M.S.; Hung, C.Y.; Meyer, G.L.; Rogers, V.C.

    1987-01-01

    Evaluation of the potential health risk and individual exposure from a broad number of disposal alternatives is an important part of EPA's program to develop generally applicable environmental standards for the land disposal of low-level radioactive wastes (LLW). The Agency has completed an analysis of the potential population health risks and maximum individual exposures from ten disposal methods under three different hydrogeological and climatic settings. This paper briefly describes the general input and analysis procedures used in the risk assessment for LLW disposal and presents their preliminary results. Some important lessons learned from simulating LLW disposal under a large variety of methods and conditions are identified

  15. Update of Part 61 impacts analysis methodology

    International Nuclear Information System (INIS)

    Oztunali, O.I.; Roles, G.W.

    1986-01-01

    The US Nuclear Regulatory Commission is expanding the impacts analysis methodology used during the development of the 10 CFR Part 61 rule to allow improved consideration of costs and impacts of disposal of waste that exceeds Class C concentrations. The project includes updating the computer codes that comprise the methodology, reviewing and updating data assumptions on waste streams and disposal technologies, and calculation of costs for small as well as large disposal facilities. This paper outlines work done to date on this project

  16. Update of Part 61 impacts analysis methodology

    International Nuclear Information System (INIS)

    Oztunali, O.I.; Roles, G.W.; US Nuclear Regulatory Commission, Washington, DC 20555)

    1985-01-01

    The US Nuclear Regulatory Commission is expanding the impacts analysis methodology used during the development of the 10 CFR Part 61 regulation to allow improved consideration of costs and impacts of disposal of waste that exceeds Class C concentrations. The project includes updating the computer codes that comprise the methodology, reviewing and updating data assumptions on waste streams and disposal technologies, and calculation of costs for small as well as large disposal facilities. This paper outlines work done to date on this project

  17. A critical evaluation of subtalar joint arthrosis associated with middle facet talocalcaneal coalition in 21 surgically managed patients: a retrospective computed tomography review. Investigations involving middle facet coalitions-part III.

    Science.gov (United States)

    Kernbach, Klaus J; Barkan, Howard; Blitz, Neal M

    2010-01-01

    Symptomatic middle facet talocalcaneal coalition is frequently associated with rearfoot arthrosis that is often managed surgically with rearfoot fusion. However, no objective method for classifying the extent of subtalar joint arthrosis exists. No study has clearly identified the extent of posterior facet arthrosis present in a large cohort treated surgically for talocalcaneal coalition through preoperative computerized axial tomography. The authors conducted a retrospective review of 21 patients (35 feet) with coalition who were surgically treated over a 12-year period for coalition on at least 1 foot. Using a predefined original staging system, the extent of the arthrosis was categorized into normal or mild (Stage I), moderate (Stage II), and severe (Stage III) arthrosis. The association of stage and age is statistically significant. All of the feet with Stage III arthrosis had fibrous coalitions. No foot with osseous coalition had Stage III arthrosis. The distribution of arthrosis staging differs between fibrous and osseous coalitions. Only fibrous coalitions had the most advanced arthrosis (Stage III), whereas osseous coalitions did not. This suggests that osseous coalitions may have a protective effect in the prevention of severe degeneration of the subtalar joint. Concomitant subtalar joint arthrosis severity progresses with age; surgeons may want to consider earlier surgical intervention to prevent arthrosis progression in patients with symptomatic middle facet talocalcaneal coalition.

  18. Self-disposal option for heat-generating waste - 59182

    International Nuclear Information System (INIS)

    Ojovan, Michael I.; Poluektov, Pavel P.; Kascheev, Vladimir A.

    2012-01-01

    Self-descending heat generating capsules can be used for disposal of dangerous radioactive wastes in extremely deep layers of the Earth preventing any release of radionuclides into the biosphere. Self-disposal option for heat-generating radioactive waste such as spent fuel, high level reprocessing waste or spent sealed radioactive sources, known also as rock melting concept, was considered in the 70's as a viable alternative disposal option by both Department of Energy in the USA and Atomic Industry Ministry in the USSR. Self-disposal is currently reconsidered as a potential alternative route to existing options for solving the nuclear waste problem and is associated with the renaissance of nuclear industry. Self- disposal option utilises the heat generated by decaying radionuclides of radioactive waste inside a heavy and durable capsule to melt the rock on its way down. As the heat from radionuclides within the capsule partly melts the enclosing rock, the relatively low viscosity and density of the silicate melt allow the capsule to be displaced upwards past the heavier capsule as it sinks. Eventually the melt cools and solidifies (e.g. vitrifies or crystallizes), sealing the route along which the capsule passed. Descending or self-disposal continues until enough heat is generated by radionuclides to provide partial melting of surrounding rock. Estimates show that extreme depths of several tens and up to hundred km can be reached by capsules which could never be achieved by other techniques. Self- disposal does not require complex and expensive disposal facilities and provides a minimal footprint used only at operational stage. It has also an extremely high non- proliferation character and degree of safety. Utilisation of heat generated by relatively short-lived radionuclides diminishes the environmental uncertainties of self-disposal and increases the safety of this concept. Self-sinking heat-generating capsules could be launched from the bottom of the sea as

  19. 17 CFR Table III to Subpart E of... - Civil Monetary Penalty Inflation Adjustments

    Science.gov (United States)

    2010-04-01

    ... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Civil Monetary Penalty Inflation Adjustments III Table III to Subpart E of Part 201 Commodity and Securities Exchanges SECURITIES..., Table III Table III to Subpart E of Part 201—Civil Monetary Penalty Inflation Adjustments U.S. Code...

  20. Nuclear waste disposal in subseabed geologic formatons: the Seabed Disposal Program

    International Nuclear Information System (INIS)

    Anderson, D.R.

    1979-05-01

    The goal of the Seabed Disposal Program is to assess the technical and environmental feasibility of using geologic formations under the sea floor for the disposal of processed high-level radioactive wastes or repackaged spent reactor fuel. Studies are focused on the abyssal hill regions of the sea floors in the middle of tectonic plates and under massive surface current gyres. The red-clay sediments here are from 50 to 100 meters thick, are continuously depositional (without periods of erosion), and have been geologically and climatologically stable for millions of years. Mineral deposits and biological activity are minimal, and bottom currents are weak and variable. Five years of research have revealed no technological reason why nuclear waste disposal in these areas would be impractical. However, scientific assessment is not complete. Also, legal political, and sociological factors may well become the governing elements in such use of international waters. These factors are being examined as part of the work of the Seabed Working Group, an international adjunct of the Seabed Program, with members from France, England, Japan, Canada, and the United States

  1. Nuclear waste disposal in subseabed geologic formatons: the Seabed Disposal Program

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, D.R.

    1979-05-01

    The goal of the Seabed Disposal Program is to assess the technical and environmental feasibility of using geologic formations under the sea floor for the disposal of processed high-level radioactive wastes or repackaged spent reactor fuel. Studies are focused on the abyssal hill regions of the sea floors in the middle of tectonic plates and under massive surface current gyres. The red-clay sediments here are from 50 to 100 meters thick, are continuously depositional (without periods of erosion), and have been geologically and climatologically stable for millions of years. Mineral deposits and biological activity are minimal, and bottom currents are weak and variable. Five years of research have revealed no technological reason why nuclear waste disposal in these areas would be impractical. However, scientific assessment is not complete. Also, legal political, and sociological factors may well become the governing elements in such use of international waters. These factors are being examined as part of the work of the Seabed Working Group, an international adjunct of the Seabed Program, with members from France, England, Japan, Canada, and the United States.

  2. Safe disposal of surplus plutonium

    Science.gov (United States)

    Gong, W. L.; Naz, S.; Lutze, W.; Busch, R.; Prinja, A.; Stoll, W.

    2001-06-01

    About 150 tons of weapons grade and weapons usable plutonium (metal, oxide, and in residues) have been declared surplus in the USA and Russia. Both countries plan to convert the metal and oxide into mixed oxide fuel for nuclear power reactors. Russia has not yet decided what to do with the residues. The US will convert residues into a ceramic, which will then be over-poured with highly radioactive borosilicate glass. The radioactive glass is meant to provide a deterrent to recovery of plutonium, as required by a US standard. Here we show a waste form for plutonium residues, zirconia/boron carbide (ZrO 2/B 4C), with an unprecedented combination of properties: a single, radiation-resistant, and chemically durable phase contains the residues; billion-year-old natural analogs are available; and criticality safety is given under all conceivable disposal conditions. ZrO 2/B 4C can be disposed of directly, without further processing, making it attractive to all countries facing the task of plutonium disposal. The US standard for protection against recovery can be met by disposal of the waste form together with used reactor fuel.

  3. General Instructions for Disposable Respirators

    Centers for Disease Control (CDC) Podcasts

    2009-04-09

    This podcast, intended for the general public, demonstrates how to put on and take off disposable respirators that are to be used in areas affected by the influenza outbreak.  Created: 4/9/2009 by CDC, National Institute for Occupational Safety and Health (NIOSH).   Date Released: 4/29/2009.

  4. Ocean Disposal of Dredged Material

    Science.gov (United States)

    Permits and authorizations for the ocean dumping of dredged material is issued by U.S. Army Corps of Engineers. Information is provided about where to dispose dredged material and the process for obtaining an ocean dumping permit for dredged material.

  5. Final disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Anon,

    1995-10-01

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK).

  6. Final disposal of nuclear waste

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK)

  7. Policies on radioactive waste disposal in the Netherlands

    International Nuclear Information System (INIS)

    Selling, H.A.

    1999-01-01

    An outline is given of the policy in the Netherlands on radioactive waste management, with an emphasis on the preferred disposal strategies. A description is given of the siting and licensing process for the waste treatment and storage facility of COVRA, which is in many respects expected to be comparable with that for a disposal site in due course. Immediate disposal of radioactive waste is not envisaged. Instead, the government has opted for long term interim storage in an engineered facility until sufficient confidence has been obtained on the safety performance of a geological repository over long time periods. In the previous decade research has mostly focused on the exploration of the suitability of existing salt formations in the northern part of the country as host rock for a radioactive waste repository. Although so far no in situ research was carried out, it could be demonstrated by utilising values of the relevant parameters from other rock salt formations that, in principle, deep underground disposal of radioactive waste is safe. This assessment was made by comparing both with common radiation protection criteria and with risk criteria over long periods of time. However, a decision to proceed with in situ research was postponed in view of the strong opposition from the local population against underground disposal. Instead, the scope of the research was extended to other host rock materials (clay). Additionally, from a sustainability point of view it was demanded that disposal should be conceived as an irreversible process. This means that the waste should be disposed of in such a way that it is retrievable in case better processing methods for the waste would become available. This demand of retrievability derives from the general waste policy to close the life-cycles of raw materials in order not to deprive future generations from their benefits. Consequently, much of the sequential research is now focused on the safety and financial impact of

  8. Evaluation of Proposed New LLW Disposal Activity: Disposal of Aqueous PUREX Waste Stream in the Saltstone Disposal Facility

    International Nuclear Information System (INIS)

    Cook, J.R.

    2003-01-01

    The Aqueous PUREX waste stream from Tanks 33 and 35, which have been blended in Tank 34, has been identified for possible processing through the Saltstone Processing Facility for disposal in the Saltstone Disposal Facility

  9. Low and medium activity nuclear waste disposal characterisation laboratory. Example of Spanish E1 Cabril Disposal Centre Laboratory

    International Nuclear Information System (INIS)

    Boulanger, G.; Augustin, X.

    1993-01-01

    Low and medium activity radioactive waste generated in Spain by power reactors, research laboratories, etc. is stored in the E1 Cabril Disposal Centre. This Centre, based on a French design, provides a characterisation function for the stored waste and corresponding containers. Technicatome, prime contractor for the French disposal centre, and contributing to the design and construction of the E1 Cabril Centre, played an important part in the R and D work for this laboratory, and the manufacture of certain items of equipment. This laboratory, applying experience acquired in France by the CEA, comprises a set of buildings providing for active and inactive test operations

  10. Low level radioactive waste disposal

    International Nuclear Information System (INIS)

    Balaz, J.; Chren, O.

    2015-01-01

    The Mochovce National Radwaste Repository is a near surface multi-barrier disposal facility for disposal of processed low and very low level radioactive wastes (radwastes) resulting from the operation and decommissioning of nuclear facilities situated in the territory of the Slovak Republic and from research institutes, laboratories, hospitals and other institutions (institutional RAW) which are in compliance with the acceptance criteria. The basic safety requirement of the Repository is to avoid a radioactive release to the environment during its operation and institutional inspection. This commitment is covered by the protection barrier system. The method of solution designed and implemented at the Repository construction complies with the latest knowledge and practice of the repository developments all over the world and meets requirements for the safe radwaste disposal with minimum environmental consequences. All wastes are solidified and have to meet the acceptance criteria before disposal into the Repository. They are processed and treated at the Bohunice RAW Treatment Centre and Liquid RAW Final Treatment Facility at Mochovce. The disposal facility for low level radwastes consists of two double-rows of reinforced concrete vaults with total capacity 7 200 fibre reinforced concrete containers (FCCs) with RAW. One double-row contains 40 The operation of the Repository was started in year 2001 and after ten years, in 2011 was conducted the periodic assessment of nuclear safety with positive results. Till the end of year 2014 was disposed to the Repository 11 514 m 3 RAW. The analysis of total RAW production from operation and decommissioning of all nuclear installation in SR, which has been carried out in frame of the BIDSF project C9.1, has showed that the total volume estimation of conditioned waste is 108 thousand m 3 of which 45.5 % are low level waste (LLW) and 54,5 % very low level waste (VLLW). On the base of this fact there is the need to build 7

  11. Oklahoma’s recent earthquakes and saltwater disposal

    Science.gov (United States)

    Walsh, F. Rall; Zoback, Mark D.

    2015-01-01

    Over the past 5 years, parts of Oklahoma have experienced marked increases in the number of small- to moderate-sized earthquakes. In three study areas that encompass the vast majority of the recent seismicity, we show that the increases in seismicity follow 5- to 10-fold increases in the rates of saltwater disposal. Adjacent areas where there has been relatively little saltwater disposal have had comparatively few recent earthquakes. In the areas of seismic activity, the saltwater disposal principally comes from “produced” water, saline pore water that is coproduced with oil and then injected into deeper sedimentary formations. These formations appear to be in hydraulic communication with potentially active faults in crystalline basement, where nearly all the earthquakes are occurring. Although most of the recent earthquakes have posed little danger to the public, the possibility of triggering damaging earthquakes on potentially active basement faults cannot be discounted. PMID:26601200

  12. Analysis of Gas Vent System in Overseas LILW Disposal Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ju Yub; Kim, Ju Youl [FNC Technology Co., Yongin (Korea, Republic of); Jung, Hae Ryong; Ha, Jae Chul [Korea Radioactive Waste Management Corporation, Daejeon (Korea, Republic of)

    2012-05-15

    A Low- and Intermediate-Level Radioactive Waste (LILW) disposal facility is currently under construction in Korea. It is located in the aquifer, 80{approx}130 m below the ground surface. Thus, it is expected that disposal facility will be saturated after closure and various gases will be generated from metal corrosion, microbial degradation of organic materials and radiolysis. Generated gases will move up to the upper part of the silo, and it will increase the pressure of the silo. Since the integrity of the engineered barrier could be damaged, development of effective gas vent system which can prevent the gas accumulation in the silo is essential. In order to obtain basic data needed to develop site-specific gas vent system, gas vent systems of Sweden, Finland and Switzerland, which have the disposal concept of underground facility, were analyzed

  13. Optimizing High Level Waste Disposal

    International Nuclear Information System (INIS)

    Dirk Gombert

    2005-01-01

    If society is ever to reap the potential benefits of nuclear energy, technologists must close the fuel-cycle completely. A closed cycle equates to a continued supply of fuel and safe reactors, but also reliable and comprehensive closure of waste issues. High level waste (HLW) disposal in borosilicate glass (BSG) is based on 1970s era evaluations. This host matrix is very adaptable to sequestering a wide variety of radionuclides found in raffinates from spent fuel reprocessing. However, it is now known that the current system is far from optimal for disposal of the diverse HLW streams, and proven alternatives are available to reduce costs by billions of dollars. The basis for HLW disposal should be reassessed to consider extensive waste form and process technology research and development efforts, which have been conducted by the United States Department of Energy (USDOE), international agencies and the private sector. Matching the waste form to the waste chemistry and using currently available technology could increase the waste content in waste forms to 50% or more and double processing rates. Optimization of the HLW disposal system would accelerate HLW disposition and increase repository capacity. This does not necessarily require developing new waste forms, the emphasis should be on qualifying existing matrices to demonstrate protection equal to or better than the baseline glass performance. Also, this proposed effort does not necessarily require developing new technology concepts. The emphasis is on demonstrating existing technology that is clearly better (reliability, productivity, cost) than current technology, and justifying its use in future facilities or retrofitted facilities. Higher waste processing and disposal efficiency can be realized by performing the engineering analyses and trade-studies necessary to select the most efficient methods for processing the full spectrum of wastes across the nuclear complex. This paper will describe technologies being

  14. Columnar modelling of nucleation burst evolution in the convective boundary layer – first results from a feasibility study Part III: Preliminary results on physicochemical model performance using two "clean air mass" reference scenarios

    Directory of Open Access Journals (Sweden)

    O. Hellmuth

    2006-01-01

    Full Text Available In Paper I of four papers, a revised columnar high-order model to investigate gas-aerosol-turbulence interactions in the convective boundary layer (CBL was proposed. In Paper II, the model capability to predict first-, second- and third-order moments of meteorological variables in the CBL was demonstrated using available observational data. In the present Paper III, the high-order modelling concept is extended to sulphur and ammonia chemistry as well as to aerosol dynamics. Based on the previous CBL simulation, a feasibility study is performed using two "clean air mass" scenarios with an emission source at the ground but low aerosol background concentration. Such scenarios synoptically correspond to the advection of fresh post-frontal air in an anthropogenically influenced region. The aim is to evaluate the time-height evolution of ultrafine condensation nuclei (UCNs and to elucidate the interactions between meteorological and physicochemical variables in a CBL column. The scenarios differ in the treatment of new particle formation (NPF, whereas homogeneous nucleation according to the classical nucleation theory (CNT is considered. The first scenario considers nucleation of a binary system consisting of water vapour and sulphuric acid (H2SO4 vapour, the second one nucleation of a ternary system additionally involving ammonia (NH3. Here, the two synthetic scenarios are discussed in detail, whereas special attention is payed to the role of turbulence in the formation of the typical UCN burst behaviour, that can often be observed in the surface layer. The intercomparison of the two scenarios reveals large differences in the evolution of the UCN number concentration in the surface layer as well as in the time-height cross-sections of first-order moments and double correlation terms. Although in both cases the occurrence of NPF bursts could be simulated, the burst characteristics and genesis of the bursts are completely different. It is demonstrated

  15. Deep geological disposal research in Argentina

    International Nuclear Information System (INIS)

    Ninci Martinez, Carlos A.; Ferreyra, Raul E.; Vullien, Alicia R.; Elena, Oscar; Lopez, Luis E.; Maloberti, Alejandro; Nievas, Humberto O.; Reyes, Nancy C.; Zarco, Juan J.; Bevilacqua, Arturo M.; Maset, Elvira R.; Jolivet, Luis A.

    2001-01-01

    Argentina shall require a deep geological repository for the final disposal of radioactive wastes, mainly high-level waste (HLW) and spent nuclear fuel produced at two nuclear power plants and two research reactors. In the period 1980-1990 the first part of feasibility studies and a basic engineering project for a radioactive high level waste repository were performed. From the geological point of view it was based on the study of granitic rocks. The area of Sierra del Medio, Province of Chubut, was selected to carry out detailed geological, geophysical and hydrogeological studies. Nevertheless, by the end of the eighties the project was socially rejected and CNEA decided to stop it at the beginning of the nineties. That decision was strongly linked with the little attention paid to social communication issues. Government authorities were under a strong pressure from social groups which demanded the interruption of the project, due to lack of information and the fear it generated. The lesson learned was: social communication activities shall be carried out very carefully in order to advance in the final disposal of HLW at deep geological repositories (author)

  16. Present status of research and development on underground disposal

    International Nuclear Information System (INIS)

    1994-11-01

    Power Reactor and Nuclear Fuel Development Corporation published the technical report 'Research and development of the formation disposal of high level radioactive waste' 1991 in 1992, summarizing the results of the research and development of the formation disposal which have been advanced by dividing into three parts, that is, the investigation and research of geological environment conditions, the research and development of disposal technologies, and the research on the performance evaluation. Based on the subjects pointed out during the process of making the technical report, the results of evaluation by the state, and the opinions of those concerned, the efforts are exerted toward the second summarization expected in about 2000. By informing the present state of the research and development, in order to accept the criticism and advice, this book was published. The way of thinking and the method of advancing of the research and development of formation disposal, the present state of the research on geological environment conditions, disposal technologies and the performance evaluation are described. Also the present state of the research on stratum science in Tono and Kamaishi mines and others is reported. (K.I.)

  17. Disposal of mixed waste: Technical, institutional, and policy factors

    International Nuclear Information System (INIS)

    Waters, R.D.; Gruebel, M.M.; Letourneau, M.J.; Case, J.T.

    1996-01-01

    In conjunction with the affected States as part of their interactions required by the Federal Facilities Compliance Act, the Department of Energy has been developing a process for a disposal configuration for its mixed low-level waste (MLLW). This effort, spanning more than two years, has reduced the potential disposal sites from 49 to 15. The remaining 15 sites have been subjected to a performance evaluation to determine their strengths and weaknesses for disposal of MLLW. The process has included institutional and policy factors as well as strictly technical analyses, and technical analyses must be supported by technical analyses, and technical analyses must be performed within a framework which includes some institutional considerations, with the institutional considerations selected for inclusion largely a matter of policy. While the disposal configuration process is yet to be completed, the experience to date offers a viable approach for solving some of these issues. Additionally, several factors remain to be addressed before an MLLW disposal configuration can be developed

  18. Integrated Disposal Facility FY2011 Glass Testing Summary Report

    International Nuclear Information System (INIS)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

    2011-01-01

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10 5 m 3 of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10 14 Bq total activity) of long-lived radionuclides, principally 99 Tc (t 1/2 = 2.1 x 10 5 ), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

  19. Integrated Disposal Facility FY2011 Glass Testing Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

    2011-09-29

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10{sup 5} m{sup 3} of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10{sup 14} Bq total activity) of long-lived radionuclides, principally {sup 99}Tc (t{sub 1/2} = 2.1 x 10{sup 5}), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

  20. Present status of research and development on underground disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-11-01

    Power Reactor and Nuclear Fuel Development Corporation published the technical report `Research and development of the formation disposal of high level radioactive waste` 1991 in 1992, summarizing the results of the research and development of the formation disposal which have been advanced by dividing into three parts, that is, the investigation and research of geological environment conditions, the research and development of disposal technologies, and the research on the performance evaluation. Based on the subjects pointed out during the process of making the technical report, the results of evaluation by the state, and the opinions of those concerned, the efforts are exerted toward the second summarization expected in about 2000. By informing the present state of the research and development, in order to accept the criticism and advice, this book was published. The way of thinking and the method of advancing of the research and development of formation disposal, the present state of the research on geological environment conditions, disposal technologies and the performance evaluation are described. Also the present state of the research on stratum science in Tono and Kamaishi mines and others is reported. (K.I.).

  1. Plasma separation process: Disposal of PSP radioactive wastes

    International Nuclear Information System (INIS)

    1989-07-01

    Radioactive wastes, in the form of natural uranium contaminated scrap hardware and residual materials from decontamination operations, were generated in the PSP facilities in buildings R1 and 106. Based on evaluation of the characteristics of these wastes and the applicable regulations, the various options for the processing and disposal of PSP radioactive wastes were investigated and recommended procedures were developed. The essential features of waste processing included: (1) the solidification of all liquid wastes prior to shipment; (2) cutting of scrap hardware to fit 55-gallon drums and use of inerting agents (diatomaceous earth) to eliminate pyrophoric hazards; and (3) compaction of soft wastes. All PSP radioactive wastes were shipped to the Hanford Site for disposal. As part of the waste disposal process, a detailed plan was formulated for handling and tracking of PSP radioactive wastes, from the point of generation through shipping. In addition, a waste minimization program was implemented to reduce the waste volume or quantity. Included in this document are discussions of the applicable regulations, the types of PSP wastes, the selection of the preferred waste disposal approach and disposal site, the analysis and classification of PSP wastes, the processing and ultimate disposition of PSP wastes, the handling and tracking of PSP wastes, and the implementation of the PSP waste minimization program. 9 refs., 1 fig., 8 tabs

  2. Radiological assessments of land disposal options: recent model developments

    International Nuclear Information System (INIS)

    Fearn, H.S.; Pinner, A.V.; Hemming, C.R.

    1984-10-01

    This report describes progress in the development of methodologies and models for assessing the radiological impact of the disposal of low and intermediate level wastes by (i) shallow land burial in simple trenches (land 1), (ii) shallow land burial in engineered facilities (land 2), and (iii) emplacement in mined repositories or existing cavities (land 3/4). In particular the report describes wasteform leaching models, for unconditioned and cemented waste, the role of engineered barriers of a shallow land burial facility in reducing the magnitude of doses arising from groundwater contact and a detailed consideration of the interactions between radioactive carbon and various media. (author)

  3. Radioactive waste disposal and political aspects

    International Nuclear Information System (INIS)

    Blanc, M.

    1992-01-01

    The difficulties presented by the current atomic energy law for the nuclear waste disposal in Switzerland are shown. It is emphasised how important scientific information is in the political solutions for nuclear disposal

  4. 48 CFR 245.603 - Disposal methods.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Disposal methods. 245.603 Section 245.603 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT... Contractor Inventory 245.603 Disposal methods. ...

  5. Energy uses and recovery in sludge disposal, Part 2

    Energy Technology Data Exchange (ETDEWEB)

    Jones, J L [Stanford Research Inst., Menlo Park, CA; Bomberger, D C; Lewis, F M

    1977-08-01

    Capital and operating costs were compared for 3 plant capacities having average dry weather flows of 10, 100, and 500 mgd. Five sludge handling options were considered. They were chemical conditioning with vacuum filtration, low pressure wet air oxidation, high pressure wet air oxidation aerobic and anaerobic digestion, and chemical oxidation with filter press dewatering. The plant sizes considered generated 11.5, 77, and 384 TPD of sludge. High pressure wet air oxidation and aerobic digestion operating costs were the most sensitive to electrical power costs, while the 2 incineration options without heat treatment were the least sensitive. Sludge drying and incineration of a 20% solids cake were the most sensitive to fuel costs, while aerobic and anaerobic digestion were not directly affected. Heat treatment of sludge and dewatering to a 40% cake had the lowest fuel requirements of the 3 incineration options but increased the total plant electric power consumption by >25%. The net Btus consumed were compared. The net consumption was lowest for anaerobic digestion, filter press plus incineration, and heat treatment plus incineration. Excluding heat recovery credit except for steam required in sludge heat treating, these 3 options are still lowest in net Btus consumed.

  6. A Disposable Tear Glucose Biosensor—Part 4

    Science.gov (United States)

    Engelschall, Erica; Lan, Kenneth; Shah, Pankti; Saez, Neil; Maxwell, Stephanie; Adamson, Teagan; Abou-Eid, Michelle; McAferty, Kenyon; Patel, Dharmendra R.; Cook, Curtiss B.

    2014-01-01

    Objective: A prototype tear glucose (TG) sensor was tested in New Zealand white rabbits to assess eye irritation, blood glucose (BG) and TG lag time, and correlation with BG. Methods: A total of 4 animals were used. Eye irritation was monitored by Lissamine green dye and analyzed using image analysis software. Lag time was correlated with an oral glucose load while recording TG and BG readings. Correlation between TG and BG were plotted against one another to form a correlation diagram, using a Yellow Springs Instrument (YSI) and self-monitoring of blood glucose as the reference measurements. Finally, TG levels were calculated using analytically derived expressions. Results: From repeated testing carried over the course of 12 months, little to no eye irritation was detected. TG fluctuations over time visually appeared to trace the same pattern as BG with an average lag times of 13 minutes. TG levels calculated from the device current measurements ranged from 4 to 20 mg/dL and correlated linearly with BG levels of 75-160 mg/dL (TG = 0.1723 BG = 7.9448 mg/dL; R2 = .7544). Conclusion: The first steps were taken toward preliminary development of a sensor for self-monitoring of tear glucose (SMTG). No conjunctival irritation in any of the animals was noted. Lag time between TG and BG was found to be noticeable, but a quantitative modeling to correlate lag time in this study is unnecessary. Measured currents from the sensors and the calculated TG showed promising correlation to BG levels. Previous analytical bench marking showed BG and TG levels consistent with other literature. PMID:24876546

  7. JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Refinement of thermodynamic data for trivalent actinoids and samarium

    International Nuclear Information System (INIS)

    Kitamura, Akira; Fujiwara, Kenso; Yui, Mikazu

    2010-01-01

    Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level radioactive and TRU wastes, the refinement of the thermodynamic data for the inorganic compounds and complexes of trivalent actinoids (actinium(III), plutonium(III), americium(III) and curium(III)) and samarium(III) was carried out. Refinement of thermodynamic data for these elements was based on the thermodynamic database for americium published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Based on the similarity of chemical properties among trivalent actinoids and samarium, complementary thermodynamic data for their species expected under the geological disposal conditions were selected to complete the thermodynamic data set for the performance assessment of geological disposal of radioactive wastes. (author)

  8. Disposable products in the hospital waste stream.

    OpenAIRE

    Gilden, D. J.; Scissors, K. N.; Reuler, J. B.

    1992-01-01

    Use of disposable products in hospitals continues to increase despite limited landfill space and dwindling natural resources. We analyzed the use and disposal patterns of disposable hospital products to identify means of reducing noninfectious, nonhazardous hospital waste. In a 385-bed private teaching hospital, the 20 disposable products of which the greatest amounts (by weight) were purchased, were identified, and total hospital waste was tabulated. Samples of trash from three areas were so...

  9. The management of uncertainties in the French regulation on deep disposal: the development of a non-risk based approach

    International Nuclear Information System (INIS)

    Raimbault, P.

    2004-01-01

    The development of a safety case for disposal of high level and medium level long-lived waste in a geological formation has to handle two main difficulties: - uncertainties associated to natural systems; - uncertainties associated to the consideration of long time scales. Licensing of the different steps leading to geological disposal implies thus that a sufficient level of confidence in the safety case will be obtained, at each step, among the different stakeholders. The confidence in the safety case relies on the whole set of arguments of different natures which complement each other and build up the file. This means that, to be defensible, the safety case should be organised in such a way that it can be reviewed and scrutinized in a structured manner. This also means that individual elements of the safety case will have to be considered separately even if all elements should fit well in the integrated safety case. This segregation implies some inherent decoupling of parts of the system, of its evolution over time and of the events that may impact on it. This decoupling will thus introduce inherent uncertainties that risk or non-risk based approaches have to deal with since both approaches have to introduce transparency in the analysis. In the non-risk based or deterministic approach this segregation is pushed further in order to put into perspective the different elements of appreciation that allow to judge the safety case as a whole. The French regulation on deep disposal presented in the basic safety rule RFS III.3.f, issued in 1991, takes these points into consideration to set the basis for the safety case in the framework of a deterministic approach. This basic safety rule is currently being revised in order to clarify some concepts and to take account evolution of ideas at the national and international level. However the basic rationale behind the safety assessment methodology will remain the same. The approach presented in RFS III.2.f implies that at

  10. Very Low Activity Waste Disposal Facility Recently Commissioned as an Extension of El Cabril LILW Disposal Facility in Spain

    International Nuclear Information System (INIS)

    Zuloaga, P.; Navarro, M.

    2009-01-01

    This paper describes the Very Low Activity Radioactive Waste (VLLW) disposal facility, designed, built and operated by ENRESA as a part of El Cabril LILW disposal facility. El Cabril facility was commissioned in 1992 and has 28 concrete vaults with an internal volume of 100,000 m 3 , as well as waste treatment systems and waste characterization laboratories. The total needs identified in Spain for LILW disposal are of some 176,000 m 3 , of which around 120,000 m3 might be classified as VLLW This project was launched in 2003 and the major licensing steps have been town planning license (2003), construction authorization (after Environmental Impact Statement and report from Nuclear Safety Council-CSN, 2006), and Operations Authorization (after report from CSN, July 2008). The new VLLW disposal facility has a capacity for 130,000 meters cube in four disposal cells of approximately the same size. Only the first cell has been built. The design of the barriers is based on the European Directive for elimination of dangerous waste and consists of a clay layer 1 m, 3 cm geo-bentonite films, and 4 mm HDPE film. In order to minimize leachate volumes collected and help a good monitoring of the site, each cell is divided into different sections, which are protected during operation -before placing a provisional HDPE capping- by a light shelter and where leachate collection is segregated from other sections. (authors)

  11. Safety case for the disposal of spent nuclear fuel at Olkiluoto. Description of the disposal system 2012

    International Nuclear Information System (INIS)

    2012-12-01

    Description of the Disposal System sits within Posiva Oy's Safety Case 'TURVA-2012' report portfolio and has the objective presenting the initial state of the disposal system for the safety case for the disposal of spent nuclear fuel at Olkiluoto, Finland. Disposal system is an entity composed of a repository system and surface environment. The repository system includes the spent nuclear fuel, canister, buffer, backfill, and closure components as well as the host rock. The repository system components have assigned safety functions (except for the spent nuclear fuel) and are subject to requirements. The initial state is presented for each component, and references to the main supporting reports are given to guide the reader for more details. Conditions for each component vary in time and space, due to the time of emplacement and due to the tolerances set for the compositions, geometries and other properties depending on the component. The disposal operation is foreseen to commence ∼ 2020. At the beginning of the postclosure period, around 2120, all the engineered components have been installed and the operation is finalised. The system evolution during the operational phase is discussed in detail in Performance Assessment. The initial state for the host rock is defined to be essentially equal to the baseline conditions prior to starting the construction of the underground characterisation facility ONKALO. For the surface environment, the initial state is the present conditions prevailing. For any other component of the disposal system, the initial state is defined as the state it has when the direct control over that specific part of the system ceases and only limited information can be made available on the subsequent development of conditions in that part of the system or its near field. (orig.)

  12. Safety case for the disposal of spent nuclear fuel at Olkiluoto. Description of the disposal system 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-12-15

    Description of the Disposal System sits within Posiva Oy's Safety Case 'TURVA-2012' report portfolio and has the objective presenting the initial state of the disposal system for the safety case for the disposal of spent nuclear fuel at Olkiluoto, Finland. Disposal system is an entity composed of a repository system and surface environment. The repository system includes the spent nuclear fuel, canister, buffer, backfill, and closure components as well as the host rock. The repository system components have assigned safety functions (except for the spent nuclear fuel) and are subject to requirements. The initial state is presented for each component, and references to the main supporting reports are given to guide the reader for more details. Conditions for each component vary in time and space, due to the time of emplacement and due to the tolerances set for the compositions, geometries and other properties depending on the component. The disposal operation is foreseen to commence {approx} 2020. At the beginning of the postclosure period, around 2120, all the engineered components have been installed and the operation is finalised. The system evolution during the operational phase is discussed in detail in Performance Assessment. The initial state for the host rock is defined to be essentially equal to the baseline conditions prior to starting the construction of the underground characterisation facility ONKALO. For the surface environment, the initial state is the present conditions prevailing. For any other component of the disposal system, the initial state is defined as the state it has when the direct control over that specific part of the system ceases and only limited information can be made available on the subsequent development of conditions in that part of the system or its near field. (orig.)

  13. Ocean disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    1984-07-01

    This report is based on an emplacement techniques review prepared for the Department of the Environment in February 1983, which appeared as Chapter III of the Nuclear Energy Agency, Seabed Working Group's Status Report. The original document (DOE/RW/83.032) has been amended to take account of the results of field trials carried out in March 1983 and to better reflect current UK Government policy on ocean disposal of HGW. In particular Figure 7 has been redrawn using more realistic drag factors for the calculation of the terminal velocity in water. This report reviews the work conducted by the SWG member countries into the different techniques of emplacing heat generating radioactive waste into the deep ocean sediments. It covers the waste handling from the port facilities to final emplacement in the seabed and verification of the integrity of the canister isolation system. The two techniques which are currently being considered in detail are drilled emplacement and the free fall penetrator. The feasibility study work in progress for both techniques as well as the mathematical and physical modelling work for embedment depth and hole closure behind the penetrator are reviewed. (author)

  14. Waste disposal options report. Volume 1

    International Nuclear Information System (INIS)

    Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

    1998-02-01

    This report summarizes the potential options for the processing and disposal of mixed waste generated by reprocessing spent nuclear fuel at the Idaho Chemical Processing Plant. It compares the proposed waste-immobilization processes, quantifies and characterizes the resulting waste forms, identifies potential disposal sites and their primary acceptance criteria, and addresses disposal issues for hazardous waste

  15. Oil statistics 1976: supply and disposal

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    Summary tables are included for the period 1960 to 1976. The detailed tables for 1976 cover production, supply and disposal; supply and disposal by product; imports by sources; imports from member countries; exports by destination; exports to member countries; consumption by end-use sectors; and supply and disposal of finished products by country (1975 and 1976). (DLC)

  16. Disposal of radioactive wastes. Chapter 11

    International Nuclear Information System (INIS)

    Skitt, J.

    1979-01-01

    An account is given of the history and present position of legislation in the United Kingdom on the disposal of radioactive wastes. The sections are headed: introduction and definitions; history; the Radioactive Substances Act 1960; disposal of solid radioactive wastes through Local Authority services; function of Local Authorities; exemptions; national radioactive waste disposal service; incidents involving radioactivity. (U.K.)

  17. 7 CFR 2902.21 - Disposable containers.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 15 2010-01-01 2010-01-01 false Disposable containers. 2902.21 Section 2902.21... Items § 2902.21 Disposable containers. (a) Definition. Products designed to be used for temporary... paragraph (d): Disposable containers can include boxes and packaging made from paper. Under the Resource...

  18. Solid waste disposal into salt mines

    International Nuclear Information System (INIS)

    Repke, W.

    1981-01-01

    The subject is discussed as follows: general introduction to disposal of radioactive waste; handling of solid nuclear waste; technology of final disposal, with specific reference to salt domes; conditioning of radioactive waste; safety barriers for radioactive waste; practice of final disposal in other countries. (U.K.)

  19. Concept for Underground Disposal of Nuclear Waste

    Science.gov (United States)

    Bowyer, J. M.

    1987-01-01

    Packaged waste placed in empty oil-shale mines. Concept for disposal of nuclear waste economically synergistic with earlier proposal concerning backfilling of oil-shale mines. New disposal concept superior to earlier schemes for disposal in hard-rock and salt mines because less uncertainty about ability of oil-shale mine to contain waste safely for millenium.

  20. Radioactive wastes storage and disposal. Chapter 8

    International Nuclear Information System (INIS)

    2002-01-01

    The Chapter 8 is essentially dedicated to radioactive waste management - storage and disposal. The management safety is being provided due to packages and facilities of waste disposal and storage. It is noted that at selection of sites for waste disposal it is necessary account rock properties and ways of the wastes delivery pathways