Hazardous waste research and development in the Pacific Basin

International Nuclear Information System (INIS)

Cirillo, R.R.; Carpenter, R.A.

1989-01-01

The effective management of hazardous waste is an issue that all countries of the Pacific Basin must address. By very rough estimates, almost 272 million metric tons of hazardous wastes are being generated every year in the region. While the data are not consistently defined and reported, they do indicate the extent of the problem. Increasing development brings along an increase in the rate of hazardous waste generation. On this basis, the developing countries of the region can be expected to experience some of the same problems of the developed countries as their economies become more industrialized. Fundamental problems are involved in the compilation of consistent hazardous-waste generation statistics in the Pacific Basin. One involves the definition of what constitutes hazardous waste

Hazardous waste treatment and environmental remediation research

International Nuclear Information System (INIS)

1989-01-01

Los Alamos National Laboratory (LANL) is currently evaluating hazardous waste treatment and environmental remediation technologies in existence and under development to determine applicability to remediation needs of the DOE facilities under the Albuquerque Operations Office and to determine areas of research need. To assist LANL is this effort, Science Applications International Corporation (SAIC) conducted an assessment of technologies and monitoring methods that have been demonstrated or are under development. The focus of this assessment is to: (1) identify existing technologies for hazardous waste treatment and environmental remediation of old waste sites; (2) identify technologies under development and the status of the technology; (3) assess new technologies that need development to provide adequate hazardous waste treatment and remedial action technologies for DOD and DOE sites; and (4) identify hazardous waste and remediation problems for environmental research and development. There are currently numerous research and development activities underway nationwide relating to environmental contaminants and the remediation of waste sites. To perform this effort, SAIC evaluated current technologies and monitoring methods development programs in EPA, DOD, and DOE, as these are the primary agencies through which developmental methods are being demonstrated. This report presents this evaluation and provides recommendations as to pertinent research needs or activities to address waste site contamination problems. The review and assessment have been conducted at a programmatic level; site-specific and contaminant-specific evaluations are being performed by LANL staff as a separate, related activity

Radioactive Waste Management Research Program Plan for high-level waste: 1987

International Nuclear Information System (INIS)

1987-05-01

This plan will identify and resolve technical and scientific issues involved in the NRC's licensing and regulation of disposal systems intended to isolate high level hazardous radioactive wastes (HLW) from the human environment. The plan describes the program goals, discusses the research approach to be used, lays out peer review procedures, discusses the history and development of the high level radioactive waste problem and the research effort to date and describes study objectives and research programs in the areas of materials and engineering, hydrology and geochemistry, and compliance assessment and modeling. The plan also details the cooperative interactions with international waste management research programs. Proposed Earth Science Seismotectonic Research Program plan for radioactive waste facilities is appended

Research and development and its importance for eco-efficient waste incineration - a review and an outlook

International Nuclear Information System (INIS)

Vehlow, Jurgen

2010-01-01

Research and development played a paramount role for waste incineration from the early beginning. The development of suited combustion systems, of measures to control dioxin formation in and emission from waste incineration plants, the simplification of gas cleaning processes while maintaining their environmental quality and the inertnesses of hazardous residues like filter ashes are few examples to illustrate this importance. There are still areas which need further research and development support, e.g. the optimisation of energy recovery or the final disposal of soluble APC residues. (author)

Management of Radioactive Wastes in Developing Countries

International Nuclear Information System (INIS)

Abdel Ghani, A.H.

1999-01-01

The management of radioactive wastes is one area of increasing interest especially in developing countries having more and more activities in the application of radioisotopes in medicine, research and industry. For a better understanding of radioactive waste management in developing countries this work will discuss the following items:Classification of countries with respect to waste management programs. Principal Radionuclides used in medicine, biological research and others and the range of radioactivity commonly used. Estimation of radioactive waste volumes and activities. Management of liquid wastes Collection. Treatment. Management of small volumes of organic liquid waste. Collection Treatment. Packaging and storage of radioactive wastes

Radioactive waste management in developing countries

International Nuclear Information System (INIS)

Thomas, K.T.; Baehr, W.; Plumb, G.R.

1989-01-01

The activities of the Agency in waste management have therefore laid emphasis on advising developing Member States on the management of wastes from the uses of radioactive materials. At the present time, developing countries are mostly concerned with the management of nuclear wastes generated from medical centres, research institutes, industrial facilities, mining operations, and research reactors. In certain instances, management of such wastes has lapsed causing serious accidents. Radiation source mismanagement has resulted in fatalities to the public in Mexico (1962), Algeria (1978), Morocco (1984), and Brazil (1987). The objective of these activities is to support the countries to develop the required expertise for self-sufficiency in safe management of radioactive wastes. What follows are details of the Agency mechanisms in place to meet the above objectives

Minutes from Department of Energy/Hazardous Waste Remedial Actions Program research and development technology needs assessment review meeting

International Nuclear Information System (INIS)

1989-01-01

On November 1--2, 1988, representatives of the Department of Energy (DOE) Headquarters, DOE Operations Offices, DOE contractors, and the Hazardous Waste Remedial Actions Program met in Salt Lake City, Utah, to select and prioritize candidate waste problems in need of research and development. The information gained will be used in planning for future research and development tasks and in restructuring current research activities to address the priority needs. All Operations Offices were represented by DOE staff and by contractor delegates from the area. This document summarizes the results of the meeting and lists the priority waste problems established

Global capacity, potentials and trends of solid waste research and management.

Science.gov (United States)

Nwachukwu, Michael A; Ronald, Mersky; Feng, Huan

2017-09-01

In this study, United States, China, India, United Kingdom, Nigeria, Egypt, Brazil, Italy, Germany, Taiwan, Australia, Canada and Mexico were selected to represent the global community. This enabled an overview of solid waste management worldwide and between developed and developing countries. These are countries that feature most in the International Conference on Solid Waste Technology and Management (ICSW) over the past 20 years. A total of 1452 articles directly on solid waste management and technology were reviewed and credited to their original country of research. Results show significant solid waste research potentials globally, with the United States leading by 373 articles, followed by India with 230 articles. The rest of the countries are ranked in the order of: UK > Taiwan > Brazil > Nigeria > Italy > Japan > China > Canada > Germany >Mexico > Egypt > Australia. Global capacity in solid waste management options is in the order of: Waste characterisation-management > waste biotech/composting > waste to landfill > waste recovery/reduction > waste in construction > waste recycling > waste treatment-reuse-storage > waste to energy > waste dumping > waste education/public participation/policy. It is observed that the solid waste research potential is not a measure of solid waste management capacity. The results show more significant research impacts on solid waste management in developed countries than in developing countries where economy, technology and society factors are not strong. This article is targeted to motivate similar study in each country, using solid waste research articles from other streamed databases to measure research impacts on solid waste management.

NDA generic research programme for higher activity waste management issues - 16390

International Nuclear Information System (INIS)

McKinney, James; Brownridge, Melanie

2009-01-01

NDA has a responsibility to ensure decommissioning activities are sufficiently technically underpinned and appropriate Research and Development (Rand D) is carried out. The NDA funds research and development (R and D) indirectly via the Site Licence Companies (SLCs) or directly. The main component of directly funded R and D is the NDA Direct Research Portfolio (DRP). The DRP is split into four framework areas: - University Interactions; - Waste Processing; - Material Characterisation; - Actinide and Strategic Nuclear Materials. These four framework areas were competed through an Official Journal of European Union (OJEU) process in 2008. Although all four areas involve waste management, Waste Processing and Material Characterisation specifically deal with Higher Activity Waste (HAW) waste management issues. The Waste Processing area was awarded to three groups: (i) National Nuclear Laboratory (NNL), (ii) Consortium led by Hyder Consulting Ltd, and (iii) Consortium led by UKAEA Ltd. The Material Characterisation area was awarded to three groups: (i) NNL, (ii) Serco, and (iii) Consortium led by UKAEA Ltd. The initial work in Waste Processing and Material Characterisation was centered on establishing a forward research programme to address the generic needs of the UK civil nuclear industry and the NDA strategic drivers for waste management and land quality. This has been achieved by the four main framework contractors from the Waste Processing and Materials Characterisation areas working together with the NDA to identify the key research themes and begin the development of the NDA's HAW Management Research Programme. The process also involves active engagement with both industry and regulators via the Nuclear Waste Research Forum (NWRF). The NDA's HAW Management Research Programme includes a number of themes: - Optimisation of Interim Store Operation and Design; - Alternative Waste Encapsulants; - Waste Package Integrity; - Alternative Waste treatment methods

Trend of the research on construction and demolition waste management

International Nuclear Information System (INIS)

Yuan Hongping; Shen Liyin

2011-01-01

Research interests in addressing construction and demolition (C and D) waste management issues have resulted in a large amount of publications during the last decade. This study demonstrates that there is no systematic examination on the research development in literature in the discipline of C and D waste management. This study presents the latest research trend in the discipline through analyzing the publications from 2000 to 2009 in eight major international journals. The analysis is conducted on the number of papers published annually, main authors' contributions, research methods and data analysis methods adopted, and research topics covered. The results exhibit an increasing research interest in C and D waste management in recent years. Researchers from developed economies have contributed significantly to the development of the research in the discipline. Some developing countries such as Malaysia and China have also been making good efforts in promoting C and D waste management research. The findings from this study also indicate that survey and case study are major methods for data collection, and the data are mostly processed through descriptive analysis. It is anticipated that more future studies on C and D waste management will be led by researchers from developing economies, where construction works will remain their major economic activities. On the other hand, more sophisticated modeling and simulating techniques have been used effectively in a number of studies on C and D waste management research, and this is considered a major methodology for future research in the discipline. C and D waste management will continue to be a hot research topic in the future, in particularly, the importance of human factors in C and D waste management has emerged as a new challenging topic.

Trend of the research on construction and demolition waste management.

Science.gov (United States)

Yuan, Hongping; Shen, Liyin

2011-04-01

Research interests in addressing construction and demolition (C&D) waste management issues have resulted in a large amount of publications during the last decade. This study demonstrates that there is no systematic examination on the research development in literature in the discipline of C&D waste management. This study presents the latest research trend in the discipline through analyzing the publications from 2000 to 2009 in eight major international journals. The analysis is conducted on the number of papers published annually, main authors' contributions, research methods and data analysis methods adopted, and research topics covered. The results exhibit an increasing research interest in C&D waste management in recent years. Researchers from developed economies have contributed significantly to the development of the research in the discipline. Some developing countries such as Malaysia and China have also been making good efforts in promoting C&D waste management research. The findings from this study also indicate that survey and case study are major methods for data collection, and the data are mostly processed through descriptive analysis. It is anticipated that more future studies on C&D waste management will be led by researchers from developing economies, where construction works will remain their major economic activities. On the other hand, more sophisticated modeling and simulating techniques have been used effectively in a number of studies on C&D waste management research, and this is considered a major methodology for future research in the discipline. C&D waste management will continue to be a hot research topic in the future, in particularly, the importance of human factors in C&D waste management has emerged as a new challenging topic. Copyright © 2010 Elsevier Ltd. All rights reserved.

The WIPP research and development program: providing the technical basis for defense waste disposal

International Nuclear Information System (INIS)

Hunter, Th.O.

1983-01-01

The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, is being developed by the US Department of Energy as a research and development facility to demonstrate the safe disposal of radioactive wastes from the defense programs of the United States. Underground workings are at a depth of 660 in a bedded-salt formation. Site investigations began in the early 1970s and are culminating with the completion of the Site and Preliminary Design Validation (SPDV) program in 1983 in which two shafts and several thousand feet of underground drifts are being constructed. The underground facility will be used for in situ tests and demonstrations that address technical issues associated with the disposal of transuranic and defense high-level wastes (DHLW) in bedded salt. These tests are based on several years of laboratory tests, field tests in mines, and analytical modeling studies. They primarily address repository development in bedded salt, including thermal-structural interactions plugging and sealing, and facility operations; and waste package interactions, including the effects of the waste on local rock salt and the evaluation of waste package materials. In situ testing began in the WIPP with the initiation of the SPDV program in 1981. In 1983, a major series of tests will begin to investigate the response of the rock salt without the use of any radioactivity

Proposed research and development plan for mixed low-level waste forms

Energy Technology Data Exchange (ETDEWEB)

O`Holleran, T.O.; Feng, X.; Kalb, P. [and others

1996-12-01

The objective of this report is to recommend a waste form program plan that addresses waste form issues for mixed low-level waste (MLLW). The report compares the suitability of proposed waste forms for immobilizing MLLW in preparation for permanent near-surface disposal and relates them to their impact on the U.S. Department of Energy`s mixed waste mission. Waste forms are classified into four categories: high-temperature waste forms, hydraulic cements, encapsulants, and specialty waste forms. Waste forms are evaluated concerning their ability to immobilize MLLW under certain test conditions established by regulatory agencies and research institutions. The tests focused mainly on leach rate and compressive strength. Results indicate that all of the waste forms considered can be tailored to give satisfactory performance immobilizing large fractions of the Department`s MLLW inventory. Final waste form selection will ultimately be determined by the interaction of other, often nontechnical factors, such as economics and politics. As a result of this report, three top-level programmatic needs have been identified: (1) a basic set of requirements for waste package performance and disposal; (2) standardized tests for determining waste form performance and suitability for disposal; and (3) engineering experience operating production-scale treatment and disposal systems for MLLW.

Proposed research and development plan for mixed low-level waste forms

International Nuclear Information System (INIS)

O'Holleran, T.O.; Feng, X.; Kalb, P.

1996-12-01

The objective of this report is to recommend a waste form program plan that addresses waste form issues for mixed low-level waste (MLLW). The report compares the suitability of proposed waste forms for immobilizing MLLW in preparation for permanent near-surface disposal and relates them to their impact on the U.S. Department of Energy's mixed waste mission. Waste forms are classified into four categories: high-temperature waste forms, hydraulic cements, encapsulants, and specialty waste forms. Waste forms are evaluated concerning their ability to immobilize MLLW under certain test conditions established by regulatory agencies and research institutions. The tests focused mainly on leach rate and compressive strength. Results indicate that all of the waste forms considered can be tailored to give satisfactory performance immobilizing large fractions of the Department's MLLW inventory. Final waste form selection will ultimately be determined by the interaction of other, often nontechnical factors, such as economics and politics. As a result of this report, three top-level programmatic needs have been identified: (1) a basic set of requirements for waste package performance and disposal; (2) standardized tests for determining waste form performance and suitability for disposal; and (3) engineering experience operating production-scale treatment and disposal systems for MLLW

Development of software for management of radioactive waste in biological research and clinical assistance

International Nuclear Information System (INIS)

Maciel, Bianca; Mattos, Maria Fernanda S.S.; Medeiros, Regina B.; Franca Junior, Jose Antonio de

2011-01-01

This paper describes the development of software which facilitates the automation of this process by mean of the Safety Analysis Report generating a data base allowing the statistic analysis and elaboration of radioactive wastes inventory. The software was developed in PHP language and the information is stored in a data base generated in Oracle and organized in different tables which allows to calculate the storage time of waste and to register the specificities of radioisotopes, cadastral data of the professionals which handle that radioisotope and also the characteristics of handling laboratories. That tool collaborates for a effective control on the use of radioisotopes in research laboratories and assistance areas as well

Radioactive wastes management development in Chile

International Nuclear Information System (INIS)

Mir, S.A.; Cruz, P.F.; Rivera, J.D.; Jorquera, O.H.

1994-01-01

A Facility for immobilizing and conditioning of radioactive wastes generated in Chile, has recently started in operation. It is a Radioactive Wastes Treatment Plant, RWTP, whose owner is Comision Chilena de Energia Nuclear, CCHEN. A Storgement Building of Conditioned Wastes accomplishes the facility for medium and low level activity wastes. The Project has been carried with participation of chilean professionals at CCHEN and Technical Assistance of International Atomic Energy Agency, IAEA. Processes developed are volume reduction by compaction; immobilization by cementation and conditioning. Equipment has been selected to process radioactive wastes into a 200 liters drum, in which wastes are definitively conditioned, avoiding exposition and contamination risks. The Plant has capacity to treat low and medium activity radioactive wastes produced in Chile due to Reactor Experimental No. 1 operation, and annex Laboratories in Nuclear Research Centers, as also those produced by users of nuclear techniques in Industries, Hospitals, Research Centers and Universities, in the whole country. With the infrastructure developed in Chile, a centralization of Radioactive Wastes Management activities is achieved. A data base system helps to control and register radioactive wastes arising in Chile. Generation of radioactive wastes in Chile, has found solution for the present production and that of near future

Vault sealing research and development for the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Lopez, R.S.; Johnson, L.H.

1986-08-01

The major research and development activities in the disposal vault sealing program are buffer development, backfill development, grouting, tunnel and shaft sealing development, and borehole sealing development. The buffer is likely to be a mixture of clay and sand surrounding the waste package and is intended, primarily, to minimize near-field mass transport. The backfill would fill the remainder of the underground workings and most of the volume of the access shafts. Its major component would be crushed rock or sand, or both, with sufficient clay added to achieve the required permeability specification. Boreholes would be sealed throughout their length with low-permeability materials. These may be cements or clays. Shaft seals would be emplaced at specific locations and, probably, would be composed of a low-permeability clay or concrete plug, together with grouting of the rock surrounding the plug. Progress to date and planned future activities for each major part of the program are described. The principal foci of the program are the research and development activities required to assess the concept of underground disposal in plutonic rock and the design and implementation of vault sealing experiments in the Underground Research Laboratory. Program plans are presented that describe the logical progression of each major component of the program, and that indicate the timing of major events that contribute to the final objective of the program, which is to develop engineering specifications for the buffer, backfill and seals, and to justify these specifications in terms of the performance of the waste disposal system. 131 refs

Institute of Energy and Climate Research IEK-6. Nuclear Waste Management report 2011/2012. Material science for nuclear waste management

International Nuclear Information System (INIS)

Klinkenberg, M.; Neumeier, S.; Bosbach, D.

2013-01-01

The nuclear waste management section of the Institute of Energy and Climate Research IEK-6 in Juelich is focused on research on radiochemistry aspects/materials science relevant for the long-term safety of nuclear waste storage and disposal. Studies on innovative waste management strategies include partitioning o actinides and the development of ceramic waste forms. Structural research is covering solid state chemistry, crystallography and computational science to model actinide containing compounds. With respect to waste management concepts nondestructive essay techniques, waste treatment procedures and product quality control strategies were developed.

Underlying chemistry research for the nuclear fuel waste management program

International Nuclear Information System (INIS)

Torgerson, D.F.; Sagert, N.H.; Shoesmith, D.W.; Taylor, P.

1984-04-01

This document reviews the underlying chemistry research part of the Canadian Nuclear Fuel Waste Management Program, carried out in the Research Chemistry Branch. This research is concerned with developing the basic chemical knowledge and under-standing required in other parts of the Program. There are four areas of underlying research: Waste Form Chemistry, Solute and Solution Chemistry, Rock-Water-Waste Interactions, and Abatement and Monitoring of Gas-Phase Radionuclides

US Department of Energy, Office of Technology Development, mixed-waste treatment research, development, demonstration, testing, and evaluation

International Nuclear Information System (INIS)

Berry, J.B.; Backus, P.M.; Conley, T.B.; Coyle, G.J.; Lurk, P.W.; Wolf, S.M.

1993-01-01

Department of Energy (DOE) mixed waste is contaminated with both chemically hazardous and radioactive species. The DOE is responsible for regulating radioactive species while the Environmental Protection Agency (EPA) is responsible for regulating hazardous species. Dual regulations establish treatment standards and therefore affect the treatment technologies used to process mixed waste. This duality is reflected in technology development initiatives. Significant technology development has been conducted for either radioactive or hazardous waste, but limited technology development, specifically addressing mixed waste treatment issues, has been completed. Technology has not been designed, developed, demonstrated, or tested to produce a low-risk final waste form that increases the probability that the final waste form will be disposed

Research program on development of advanced treatment technology for americium-containing aqueous waste in NUCEF

Energy Technology Data Exchange (ETDEWEB)

Mineo, Hideaki; Matsumura, Tatsuro; Tsubata, Yasuhiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1996-10-01

A research program was prepared on the development of an advanced treatment process for the americium-containing concentrated aqueous waste in NUCEF, than allows americium recovery for the reuse and the reduction of TRU waste generation. A preliminary analysis was conducted on the separation requirements based on the components estimated for the waste. An R and D strategy was proposed from the view to reduce TRU waste generated in the processing that the highest priority is given on the control of TRU leakage such as americium into the effluent stream after americium recovery and the minimization of salt used in the separation over the decontamination of impurities from americium. The extraction chromatographic method was selected as a candidate technology for americium separation under the principle to use reagents that are functional in acidic conditions such as bidentate extractants of DHEDECMP, CMPO or diamides, considering the larger flexibilities in process modification and possible multi-component separation with compact equipment and the past achievements on the recovery of kg quantities of americium. Major R and D items extracted are screening and evaluation of extractants for americium and plutonium, optimization of separation conditions, selection of denitration method, equipment developments and development of solidification methods of discarded americium after reuse and of various kinds of separation residues. In order to cope these items, four steps of R and D program were proposed, i.e., fundamental experiment in beaker-scale on screening and evaluation of extractants, flowsheet study in bench-scale using simulated and small amount of americium aqueous waste solution to evaluate candidate process, americium recovery test in iron-shielded cell to be installed in NUCEF. It is objected to make recovery of 100g orders of americium used for research on fundamental TRU fuel properties. (J.P.N.)

Idaho Nuclear Technology and Engineering Center Sodium-Bearing Waste Treatment Research and Development FY-2002 Status Report

Energy Technology Data Exchange (ETDEWEB)

Herbst, Alan Keith; Deldebbio, John Anthony; Mc Cray, John Alan; Kirkham, Robert John; Olson, Lonnie Gene; Scholes, Bradley Adams

2002-09-01

The Idaho National Engineering and Environmental Laboratory (INEEL) is considering several optional processes for disposal of liquid sodium-bearing waste. During fiscal year 2002, immobilization-related research included of grout formulation development for sodium-bearing waste, absorption of the waste on silica gel, and off-gas system mercury collection and breakthrough using activated carbon. Experimental results indicate that sodium-bearing waste can be immobilized in grout at 70 weight percent and onto silica gel at 74 weight percent. Furthermore, a loading of 11 weight percent mercury in sulfur-impregnated activated carbon was achieved with 99.8% off-gas mercury removal efficiency.

Approved reference and testing materials for use in Nuclear Waste Management Research and Development Programs

International Nuclear Information System (INIS)

Mellinger, G.B.; Daniel, J.L.

1984-12-01

This document, addressed to members of the waste management research and development community summarizes reference and testing materials available from the Nuclear Waste Materials Characterization Center (MCC). These materials are furnished under the MCC's charter to distribute reference materials essential for quantitative evaluation of nuclear waste package materials under development in the US. Reference materials with known behavior in various standard waste management related tests are needed to ensure that individual testing programs are correctly performing those tests. Approved testing materials are provided to assist the projects in assembling materials data base of defensible accuracy and precision. This is the second issue of this publication. Eight new Approved Testing Materials are listed, and Spent Fuel is included as a separate section of Standard Materials because of its increasing importance as a potential repository storage form. A summary of current characterization information is provided for each material listed. Future issues will provide updates of the characterization status of the materials presented in this issue, and information about new standard materials as they are acquired. 7 references, 1 figure, 19 tables

Institutional radioactive waste management in the Nuclear Research Institute Rez plc

International Nuclear Information System (INIS)

Kovarik, P.; Svoboda, K.; Podlaha, J.

2008-01-01

Nuclear research institute Rez, plc. (mentioned below as NRI) has had a dominant position in the area of the nuclear research and development in the Czech Republic, the Central and the Eastern Europe. Naturally, the radioactive waste management is an integral part of the nuclear industry, research and development. For that reason, there is Centre of the radioactive waste management (mentioned below as Centre) in the NRI. This Centre is engaged in the radioactive waste treatment, decontamination, characterisation, decommissioning and other relevant activities. This paper describes the system of technology and other information about institutional radioactive waste management in the NRI. (authors)

U.S. Department of Energy, Office of Technology Development, mixed-waste treatment research, development, demonstration, testing, and evaluation

International Nuclear Information System (INIS)

Berry, J.B.

1993-01-01

Both chemically hazardous and radioactive species contaminate mixed waste. Historically, technology has been developed to treat either hazardous or radioactive waste. Technology specifically designed to produce a low-risk final waste form for mixed low-level waste has not been developed, demonstrated, or tested. Site-specific solutions to management of mixed waste have been initiated; however, site-specific programs result in duplication of technology development effort between various sites. There is a clear need for technology designed to meet the unique requirements for mixed-waste processing and a system-wide integrated strategy for developing technology and managing mixed waste. This paper discusses the US Department of Energy (DOE) approach to addressing these unique requirements through a national technology development effort

Minimising food waste: a call for multidisciplinary research.

Science.gov (United States)

Alamar, Maria Del Carmen; Falagán, Natalia; Aktas, Emel; Terry, Leon A

2018-01-01

Food losses and waste have always been a significant global problem for mankind, and one which has become increasingly recognised as such by policy makers, food producers, processors, retailers, and consumers. It is, however, an emotive subject whereby the extent, accuracy and resolution of available data on postharvest loss and waste are questionable, such that key performance indicators on waste can be misinformed. The nature and extent of food waste differ among developed economies, economies in transition and developing countries. While most emphasis has been put on increasing future crop production, far less resource has been and is still channelled towards enabling both established and innovative food preservation technologies to reduce food waste while maintaining safety and quality. Reducing food loss and waste is a more tractable problem than increasing production in the short to medium term, as its solution is not directly limited, for instance, by available land and water resources. Here we argue the need for a paradigm shift of current funding strategies and research programmes that will encourage the development, implementation and translation of collective biological, engineering and management solutions to better preserve and utilise food. Such multidisciplinary thinking across global supply chains is an essential element in the pursuit of achieving sustainable food and nutritional security. The implementation of allied technological and management solutions is reliant on there being sufficient skilled human capital and resources. There is currently a lack of robust postharvest research networks outside of the developed world, and insufficient global funding mechanisms that can support such interdisciplinary collaborations. There is, thus, a collective need for schemes that encourage inter-supply chain research, knowledge exchange and capacity building to reduce food losses and waste. © 2017 Society of Chemical Industry. © 2017 Society of Chemical

Sponsored research on radioactive waste management. Progress report January 1981 - March 1982

Energy Technology Data Exchange (ETDEWEB)

1983-01-01

The report is in chapters entitled: introduction (background, responsibilities, options, structure of the programme); strategy development; disposal of accumulations; disposal of radioactive waste arisings; quality assurance for waste conditioning quality assurance related to radioactive waste disposal (effectiveness of different rock types as natural barriers to the movement of radioactivity, and non-site specific factors in the design of repositories; radiological assessment; environmental studies; research and development to meet requirements specific to UKAEA wastes; long term research (processes for the solidification of highly active liquid wastes); plutonium contamination waste minimisation.

Research programme on radioactive wastes

International Nuclear Information System (INIS)

Eckhardt, A.; Hufschmid, P.; Jordi, S.; Schanne, M.; Vigfusson, J.

2009-11-01

This report for the Swiss Federal Department of the Environment, Transport, Energy and Communication (DETEC) takes a look at work done within the framework of the research programme on radioactive wastes. The paper discusses the development of various projects and the associated organisations involved. Both long-term and short-term topics are examined. The long-term aspects of handling radioactive wastes include organisation and financing as well as the preservation of know-how and concepts for marking the repositories. Communication with the general public on the matter is looked at along with public perception, opinion-making and acceptance. Waste storage concepts are looked at in detail and aspects such as environmental protection, monitoring concepts, retrievability and encasement materials are discussed. Finally, ethical and legal aspects of radioactive waste repositories are examined. The paper is completed with appendixes dealing with planning, co-ordination and the responsibilities involved

Development of radioactive waste management at Japan Atomic Energy Research Institute

International Nuclear Information System (INIS)

Miyanaga, I.; Sakata, S.; Ito, A.; Amano, H.

1977-01-01

For low- and medium-level waste treatment, main efforts have been put on the reduction of waste volume. For high-level wastes, studies are being carried out on the solidification and partitioning techniques in preparation for completion of the fuel cycle in Japan. For sea disposal of low-level wastes planned by the JAEC, significant information has been obtained regarding integrity and leaching behavior of cement solidified wastes. This paper describes the present status of development of the techniques in the following sections; 1. Treatment of Low- and Medium-Level Wastes; an incinerator with two stage ceramic filters has been tested, and the decontamination factor was found to be 10 4 for various nuclides; reverse osmosis method with a cellulose acetate membrane has been tested for laundry liquid waste, and 60 Co was removed more than 99% together with detergents; and solidification products of spent ion-exchange resin with polyethylene have been proved to be superior in mechanical properties, water resistance and volume reduction to asphalt products. 2. Safety Evaluation of Cement Solidified Wastes for Sea Disposal; homogeneous cement-solidified wastes in 200 l sealed drums did not show any cracks or defects under high hydrostatic pressure; the leaching ratio of 137 Cs for the first one year was estimated to be lower than 0.3%. 3. Treatment of High-Level Wastes; vitrification using natural zeolite has been developed and properties of the products were proved to be excellent; and a partitioning procedure consisting mainly of solvent extraction and ion-exchange method has been studied; reduction of the amount of alkaline agent by introducing a denitration technique, and reduction of resin volume by adopting a porous type resin were achieved

Research of radioactive waste storage cask/canister materials, spent nuclear fuels and various radioactive waste forms and development of their assessment methods. Final report for Stage 3

International Nuclear Information System (INIS)

Dobrev, D.; Balek, V.; Červinka, R.; Večerník, P.; Člupek, M.; Kouřil, M.; Novák, P.; Stoulil, J.; Silber, R.

2013-08-01

The main topics treated are: Research and development of methodologies for canister/cask material degradation assessment; Laboratory research of selected materials of canister/cask with radioactive waste; and Research and assessment of canister/cask materials in natural granite rocks. Two additional documents are appended: Corrosion rate determination for samples in compacted bentonite in anaerobic conditions (methodology), and Roll test for corrosion test in an occluded solution at the interface between a radioactive waste disposal canister and the bentonite cover. (P.A.)

Development of waste management regulations

International Nuclear Information System (INIS)

Elnour, E.G.

2012-04-01

Radioactive wastes are generated during nuclear fuel cycle operation, production and application of radioisotope in medicine, industry, research, and agriculture, and as a by product of natural resource exploitation, which includes mining and processing of ores. To ensure the protection of human health and the environment from the hazard of these wastes, a planned integrated radioactive waste management practice should be applied. The purpose of this study is to develop regulations for radioactive waste management for low and intermediate radioactive level waste (LILW), and other purpose of regulations is to establish requirements with which all organizations must comply in Sudan from LILW in particular disused/spent sources, not including radioactive waste for milling and mining practices. The national regulations regarding the radioactive waste management, should prescribe the allocation of responsibilities and roles of the Country, the regulatory body, user/owner, waste management organization, including regulations on transport packaging of waste and applied a quality assurance programme, to ensure that radioactive waste management is done safely and securely. (author)

Belgian research on fusion beryllium waste

International Nuclear Information System (INIS)

Druyts, F.; Mallants, D.; Sillen, X.; Iseghem, P. Van

2004-01-01

Future fusion power plants will generate important quantities of neutron irradiated beryllium. Although recycling is the preferred management option for this waste, this may not be technically feasible for all of the beryllium, because of its radiological characteristics. Therefore, at SCK·CEN, we initiated a research programme aimed at studying aspects of the disposal of fusion beryllium, including waste characterisation, waste acceptance criteria, conditioning methods, and performance assessment. One of the main issues to be resolved is the development of fusion-specific waste acceptance criteria for surface or deep geological disposal, in particular with regard to the tritium content. In case disposal is the only solution, critical nuclides can be immobilised by conditioning the waste. As a first approach to immobilising beryllium waste, we investigated the vitrification of beryllium. Corrosion tests were performed on both metallic and vitrified beryllium to provide source data for performance assessment. Finally, a first step in performance assessment was undertaken. (author)

Waste management advisory missions to developing countries

International Nuclear Information System (INIS)

Thomas, K.T.

1990-01-01

The IAEA's Waste Management Advisory Programme (WAMAP) was initiated in 1987 as an interregional technical co-operation project to complement other activities in radioactive waste management. Its creation gave greater recognition to the importance of the safe management of radioactive wastes and promotion of long-term waste management technical assistance strategies for developing countries. Over the past 4 years, international experts have reviewed the radioactive waste management programmes of 29 developing countries. Missions have been conducted within the framework of the IAEA's Waste Management Advisory Programme (WAMAP). Ten of these countries have nuclear power plants in operation or under construction or have nuclear fuel cycle facilities. Altogether, 23 have research reactors or centres, eight have uranium or thorium processing programmes or wastes, and nine essentially have only isotope applications involving the use of radiation sources

Life-cycle assessment of municipal solid wastes: Development of the WASTED model

International Nuclear Information System (INIS)

Diaz, R.; Warith, M.

2006-01-01

This paper describes the development of the Waste Analysis Software Tool for Environmental Decisions (WASTED) model. This model provides a comprehensive view of the environmental impacts of municipal solid waste management systems. The model consists of a number of separate submodels that describe a typical waste management process: waste collection, material recovery, composting, energy recovery from waste and landfilling. These submodels are combined to represent a complete waste management system. WASTED uses compensatory systems to account for the avoided environmental impacts derived from energy recovery and material recycling. The model is designed to provide solid waste decision-makers and environmental researchers with a tool to evaluate waste management plans and to improve the environmental performance of solid waste management strategies. The model is user-friendly and compares favourably with other earlier models

Mixed Waste Integrated Program emerging technology development

International Nuclear Information System (INIS)

Berry, J.B.; Hart, P.W.

1994-01-01

The US Department of Energy (DOE) is responsible for the management and treatment of its mixed low-level wastes (MLLW). MLLW are regulated under both the Resource Conservation and Recovery Act and various DOE orders. Over the next 5 years, DOE will manage over 1.2 m 3 of MLLW and mixed transuranic (MTRU) wastes. In order to successfully manage and treat these mixed wastes, DOE must adapt and develop characterization, treatment, and disposal technologies which will meet performance criteria, regulatory approvals, and public acceptance. Although technology to treat MLLW is not currently available without modification, DOE is committed to developing such treatment technologies and demonstrating them at the field scale by FY 1997. The Office of Research and Development's Mixed Waste Integrated Program (MWIP) within the DOE Office of Environmental Management (EM), OfFice of Technology Development, is responsible for the development and demonstration of such technologies for MLLW and MTRU wastes. MWIP advocates and sponsors expedited technology development and demonstrations for the treatment of MLLW

Waste management research abstracts. Information on radioactive waste management research in progress or planned. Vol. 28

International Nuclear Information System (INIS)

2003-11-01

This issue contains 184 abstracts that describe research in progress in the field of radioactive waste management. The research abstracts contained in the Waste Management Research Abstracts Volume 28 (WMRA 28) were collected between October 1, 2002 and September 30, 2003. The abstracts reflect research in progress, or planned, in the field of radioactive waste management. They present ongoing work in various countries and international organizations. Although the abstracts are indexed by country, some programmes are actually the result of cooperation among several countries. Indeed, a primary reason for providing this compilation of programmes, institutions and scientists engaged in research into radioactive waste management is to increase international co-operation and facilitate communications

Transportation research activities in support of nuclear waste management programs

International Nuclear Information System (INIS)

Allen, G.C. Jr.; Cashwell, J.W.; Jefferson, R.M.

1983-01-01

Transportation Technology Center has been conducting a wide range of technical research activities to assure the ability to transport radioactive materials in a safe, reliable manner. These activities include tasks in basic, analysis methodology and system research areas. Recently, the requirements of defense waste shipments have served as a focal point for development tasks with the expectation that they would serve as a precursor for commercial activities. The passage of the Nuclear Waste Policy Act has placed additional responsibility on the Department of Energy for concerns involving the shipments of civilian materials. The development of additional research responsibilities is expected to proceed concurrently with the evolution of the transportation mission plan for civilian spent fuel and high-level wastes

Application and research of special waste plasma disposal technology

International Nuclear Information System (INIS)

Lan Wei

2007-12-01

The basic concept of plasma and the principle of waste hot plasma disposal technology are simply introduced. Several sides of application and research of solid waste plasma disposal technology are sumed up. Compared to the common technology, the advantages of waste hot plasma disposal technology manifest further. It becomes one of the most prospective and the most attended high tech disposal technology in particular kind of waste disposal field. The article also simply introduces some experiment results in Southwest Institute of Physics and some work on the side of importation, absorption, digestion, development of foreign plasma torch technology and researching new power sources for plasma torch. (authors)

Sustainable waste management research and development : a successful use of landfill tax credit funds?

International Nuclear Information System (INIS)

Read, A.D.

2000-01-01

A landfill tax was introduced to the United Kingdom in October 1996 to ensure that landfill waste disposal reflects its environmental cost. The tax system makes allowances so that some of the taxes raised can be used to encourage projects which reflect sustainable development in waste management. According to regulations, some of the projects deemed acceptable for tax credits are: (1) reclamation, remediation or restoration projects, (2) any operation that reduces the potential for pollution, (3) research, development and education of information about waste management practices, (4) improvements of public amenities in the vicinity of a landfill site, and (5) maintenance or repair of a historic building that is in the vicinity of a landfill site. The statistical data relating to the projects indicate a good response from landfill operators in the first two years, but since then, the proportional distribution of approved projects has remained static. This paper argues that the system is inadequately funded and focused in the wrong direction. The projects and contributions made under this new tax scheme were analyzed to determine if the system is capable of following a sustainable approach. 9 refs., 6 tabs

Mixed Waste Integrated Program emerging technology development

Energy Technology Data Exchange (ETDEWEB)

Berry, J.B. [Oak Ridge National Lab., TN (United States); Hart, P.W. [USDOE, Washington, DC (United States)

1994-06-01

The US Department of Energy (DOE) is responsible for the management and treatment of its mixed low-level wastes (MLLW). MLLW are regulated under both the Resource Conservation and Recovery Act and various DOE orders. Over the next 5 years, DOE will manage over 1.2 m{sup 3} of MLLW and mixed transuranic (MTRU) wastes. In order to successfully manage and treat these mixed wastes, DOE must adapt and develop characterization, treatment, and disposal technologies which will meet performance criteria, regulatory approvals, and public acceptance. Although technology to treat MLLW is not currently available without modification, DOE is committed to developing such treatment technologies and demonstrating them at the field scale by FY 1997. The Office of Research and Development`s Mixed Waste Integrated Program (MWIP) within the DOE Office of Environmental Management (EM), OfFice of Technology Development, is responsible for the development and demonstration of such technologies for MLLW and MTRU wastes. MWIP advocates and sponsors expedited technology development and demonstrations for the treatment of MLLW.

The European Community's research and development activities on the management of radioactive waste from decommissioning

International Nuclear Information System (INIS)

Huber, B.

1984-01-01

The Commission of the European Communities is conducting an R and D programme on the decommissioning of nuclear power plants. The activities carried out within this framework that concern, in particular, management of the radioactive waste arising from the decommissioning are outlined. Characterization of the radioactivity inventory of nuclear power plants at the end of their useful life is of fundamental importance in this context. Research in this field comprises analyses of the trace elements in reactor materials which are relevant for the formation of long-lived radionuclides by neutron activation, as well as examinations of samples taken from activated and contaminated plant components. Most of the radioactive plant components are only surface contaminated. Highly efficient decontamination techniques are being developed with the objective of achieving conditions permitting unrestricted release of the material treated. Other activities concern the conditioning of steel and concrete waste for disposal, and the management of graphite waste from gas-cooled reactors. Large containers are being developed for transport and disposal of radioactive components. Finally, the methods of radiological evaluation and measurement are being studied which are required to decide whether material from the dismantling of nuclear power plants has to be disposed of as radioactive waste or not. (author)

Research and development for DOE environmental restoration and waste management

International Nuclear Information System (INIS)

Erickson, M.D.; Borys, S.S.; Bugielski, D.; Lien, S.C.T.; Hain, K.E.

1991-01-01

The US Department of Energy (DOE) recently consolidated its environmental restoration and waste management activities. Within that new organization, DOE has committed to support Research, Development, Demonstration, Testing and Evaluation (RDDT ampersand E) activities with the following objectives: rapidly advance beyond currently available technologies; provide solutions to key technical issues that will improve effectiveness, efficiency, and safety; and enhance DOE's ability to meet its 30-year compliance and cleanup goals. DOE has already supported a number of R ampersand D activities in this area and plans to continue that support in the future. DOE's Office of Technology Development is interested in eliciting broad participation from qualified organizations who can contribute to RDDT ampersand E activities. This presentation addresses the on-going and future R ampersand D, with an emphasis on the private sector activities. To focus private sector capabilities on the high-priority needs of DOE, a series of competitive solicitations was started in FY 1990. On May 1, 1990, on behalf of DOE's Office of Technology Development, Argonne National Laboratory issued a Request for Proposals that solicited proposals for research and development in the areas of (1) groundwater remediation, (2) soil remediation, (3) characterization of contamination and geological and hydrological features, and (4) containment of contaminated sites. In response to this solicitation, Argonne National Laboratory received 147 proposals. Fifteen of the proposals totaling $5.7 million were funded in FY 1990. The scope of work and evaluation criteria used in the procurement and the workscope of the resultant contracts are reviewed in this paper. The FY 1991 plans for competitive private sector research and development activities will also be presented at the conference. Funding levels, technical workscope, evaluation criteria, and schedule for the FY 1991 Request for Proposals will be detailed. 2

Hanford Waste Simulants Created to Support the Research and Development on the River Protection Project - Waste Treatment Plant

Energy Technology Data Exchange (ETDEWEB)

Eibling, R.E.

2001-07-26

The development of nonradioactive waste simulants to support the River Protection Project - Waste Treatment Plant bench and pilot-scale testing is crucial to the design of the facility. The report documents the simulants development to support the SRTC programs and the strategies used to produce the simulants.

Transuranic waste management program waste form development

International Nuclear Information System (INIS)

Bennett, W.S.; Crisler, L.R.

1981-01-01

To ensure that all technology necessary for long term management of transuranic (TRU) wastes is available, the Department of Energy has established the Transuranic Waste Management Program. A principal focus of the program is development of waste forms that can accommodate the very diverse TRU waste inventory and meet geologic isolation criteria. The TRU Program is following two approaches. First, decontamination processes are being developed to allow removal of sufficient surface contamination to permit management of some of the waste as low level waste. The other approach is to develop processes which will allow immobilization by encapsulation of the solids or incorporate head end processes which will make the solids compatible with more typical waste form processes. The assessment of available data indicates that dewatered concretes, synthetic basalts, and borosilicate glass waste forms appear to be viable candidates for immobilization of large fractions of the TRU waste inventory in a geologic repository

Research program on radioactive wastes - Overview report 2012

International Nuclear Information System (INIS)

Brander, S.

2013-01-01

This short report issued by the Swiss Federal Office of Energy (SFOE) takes a look at the work done within the framework of the Swiss Research Program on Radioactive Wastes. The program was developed in 2006/2007 by the various federal institutes and commissions involved together with an university of applied sciences. Points investigated included long-term aspects, the planning of deep repositories, opinion building and acceptance as well as depository concepts. Highlights in the research and development areas are discussed, including knowledge conservation, marking concepts, storage of radioactive wastes, repository conception, monitoring and sociological aspects. National and international co-operation in these areas are reported on

Analysis of Uranium and Thorium in Waste Water from Rare Earth Research and Development by ICP Spectrometry

International Nuclear Information System (INIS)

Pichestapong, Pipat; Injareon, Uthaiwan

2007-08-01

Full text: Waste water from Rare Earth Research and Development Center (RRDC) was analyzed to determine uranium and thorium concentration using ICP spectrometry. RRDC processes monazite ore to separate uranium, thorium and rare earth elements from the ore. Water samples from the ditch surrounding the center and from the canal nearby were also analyzed. Matrix spike technique was applied in this analysis. It was found that the highest concentration of uranium and thorium in the waste water samples were 3028±11 and 439±7 ppb, respectively. The concentration of uranium and thorium in the waste water samples were higher than those in water samples from the ditch and canal

Scientific research - support for achieving the national strategy for radioactive waste management

International Nuclear Information System (INIS)

Ionita, Gheorghe

2008-01-01

Full text: The lecture contains an overview on current status of research activity in Romania and especially, the organizing and development of research activity in nuclear field. The main characteristics for fundamental and applied research, for technological development and for innovation and technological transfer are presented beside of the evolution of legislative framework, the dynamics of research and development institutions and of number of scientific researchers. The main modalities for financing of research activities in nuclear field based on Governmental Decision No. 144/1998, Technical Cooperation Program with AIEA, Phare projects and the second National Program for Research, Development and Innovation are discussed. Aspects concerning the selection and financing of research topics in correlation with the requirements of National Strategy for the Safety Management of Radioactive Waste in cooperation with radioactive waste producers are discussed. Current and future requirements, concerning the near-surface and geological disposal of radioactive waste and resized of Research National Program in nuclear field according to the provisions of the new National Energy Strategy have to be taken into consideration. The present material and human resources and the infrastructure and ascending financing of research activities in nuclear field constitutes a guaranty that the main objectives of national strategy for safety management of spent fuel and radioactive waste can be achieved. (author)

Development of a Radioactive Waste Assay System

Energy Technology Data Exchange (ETDEWEB)

Kang, Duck Won; Song, Myung Jae; Shin, Sang Woon; Sung, Kee Bang; Ko, Dae Hach [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Kil Jeong; Park, Jong Mook; Jee, Kwang Yoong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-12-31

Nuclear Act of Korea requires the manifest of low and intermediate level radioactive waste generated at nuclear power plants prior to disposal sites.Individual history records of the radioactive waste should be contained the information about the activity of nuclides in the drum, total activity, weight, the type of waste. A fully automated nuclide analysis assay system, non-destructive analysis and evaluation system of the radioactive waste, was developed through this research project. For the nuclides that could not be analysis directly by MCA, the activities of the representative {gamma}-emitters(Cs-137, Co-60) contained in the drum were measured by using that system. Then scaling factors were used to calculate the activities of {alpha}, {beta}-emitters. Furthermore, this system can automatically mark the analysis results onto the drum surface. An automated drum handling system developed through this research project can reduce the radiation exposure to workers. (author). 41 refs., figs.

Research and development needs in a step-wise process for the nuclear waste programme in Sweden

International Nuclear Information System (INIS)

Ström, A.; Andersson, J.; Ekeroth, E.; Hedin, A.; Pers, K.

2016-01-01

Concluding remarks: • The SKB RD&D Programme 2016 − contains an overview of all the measures that may be necessary for treatment and final disposal of nuclear waste from Swedish nuclear reactors and SKB's facilities; − clarifies how research and technology development are justified and evaluated in a step-wise procedure on the basis of the measures planned; − presents a strategic plan for the research and development necessary to establish and implement future activities; − Published as SKB TR 16-15 in December 2016

Low-level waste management at the Nuclear Research Center

International Nuclear Information System (INIS)

Montanez, O.; Blanco, D.; Vallarino, V.; Calisto, W.

1986-01-01

A general overview of low-level radioactive waste management at the Nuclear Investigation Centre (CIN) of Uruguay is presented. The CIN is a pilot centre of research and development of techniques for implementing measurements for radioactive waste storage and control. (M.C.K.) [pt

Hazardous-waste landfill research, US EPA (United States Environmental Protection Agency) program

Energy Technology Data Exchange (ETDEWEB)

Schomaker, N.B.

1988-08-01

The Land Pollution Control Division (LPCD), Hazardous Waste Engineering Research Lab. (HWERL), U.S. Environmental Protection Agency, in Cincinnati, Ohio, has responsibility for research in solid- and hazardous-waste management with respect to land disposal of wastes. To fulfill the responsibility, the LPCD is developing concepts and is documenting the environmental effects of various waste-disposal practices; and is collecting data necessary to support implementation of disposal guidelines mandated by the Hazardous and Solid Waste Amendments of 1984 (HSWA). This paper presents an overview of the land-disposal research associated with the LPCD hazardous waste program plan and will report the current status of work in the following categorical areas: Hazardous-waste facilities - landfills and surface impoundments; Non-Hazardous waste facilities; and Technology transfer.

Minutes from Department of Energy/Hazardous Waste Remedial Actions Program, research and development technology needs assessment review meeting for FY 1990, September 1989, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

1990-08-01

On September 20--21, 1989, representatives of the Department of Energy (DOE) Headquarters, DOE Operations Offices, DOE contractors, and the Hazardous Waste Remedial Actions Program met in Oak Ridge, Tennessee, to select and prioritize candidate waste problems in need of research and development. The information gained will be used in planning for future research and development tasks and in restructuring current research activities to address the priority needs. Consistent with the ongoing reevaluation of DOE's plans for environmental restoration and waste management, an attempt was made to relate the needs developed in this meeting to the needs expressed in the draft Applied Research, Development, Demonstration, Testing, and Evaluation Plan. Operations Offices were represented either by DOE staff or by contractor delegates from the area. This document summarizes the results of the meeting and lists the priority waste problems established.

Directions of development of research methods in the assessment of leaching of heavy metals from mineral waste

Directory of Open Access Journals (Sweden)

Król Anna

2016-01-01

Full Text Available There are many test methods to assess the level of the release of heavy metals into the environment from mineral waste materials. Leaching methods can be different depending on the leaching time periods, leaching dynamics, sample preparation method or the pH of the elution medium. In Poland, little attention is paid to the research on the relationship between the leaching of particular heavy metals from mineral wastes and changes in environmental conditions, including the pH of the environment. Tests being carried out abroad have started to pay great attention to the pH-dependent impact of the environment and the liquid being in contact with the material on the degree of leaching contaminants from wastes. The solubility of all metals depends on the value of the pH. Authors of the paper will try to prove that Polish methods of waste characterization is incomplete and inconsistent with opinions prevailing in the global literature. The procedure described in the Polish standards are insufficient to determine the actual level of leaching of heavy metals having regard to the impact of multiple external conditions on the level of leaching of heavy metals. Paper will present a directions of development of research methods in the assessment of leaching of heavy metals from mineral waste.

Geoscience research for the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Whitaker, S.H.

1987-01-01

The Canadian Nuclear Fuel Waste Management Program is assessing the concept of deep disposal of nuclear fuel waste in plutonic rock. As part of that assessment, a broad program of geoscience and geotechnical work has been undertaken to develop methods for characterizing sites, incorporating geotechnical data into disposal facility design, and incorporating geotechnical data into environmental and safety assessment of the disposal system. General field investigations are conducted throughout the Precambrian Shield, subsurface investigations are conducted at designated field research areas, and in situ rock mass experiments are being conducted in an Underground Research Laboratory. Samples from the field research areas and elsewhere are subjected to a wide range of tests and experiments in the laboratory to develop an understanding of the physical and chemical processes involved in ground-water-rock-waste interactions. Mathematical models to simulate these processes are developed, verified and validated. 114 refs.; 13 figs

Solid waste management challenges for cities in developing countries

Energy Technology Data Exchange (ETDEWEB)

Abarca Guerrero, Lilliana, E-mail: l.abarca.guerrero@tue.nl [Built Environment Department, Eindhoven University of Technology, Den Dolech, 25612 AZ Eindhoven (Netherlands); Maas, Ger, E-mail: g.j.maas@tue.nl [Built Environment Department, Eindhoven University of Technology, Den Dolech, 25612 AZ Eindhoven (Netherlands); Hogland, William, E-mail: william.hogland@lnu.se [School of Natural Sciences, Linnaeus University, SE-391 82 Kalmar (Sweden)

2013-01-15

Highlights: Black-Right-Pointing-Pointer Stakeholders. Black-Right-Pointing-Pointer Factors affecting performance waste management systems. Black-Right-Pointing-Pointer Questionnaire as Annex for waste management baseline assessment. - Abstract: Solid waste management is a challenge for the cities' authorities in developing countries mainly due to the increasing generation of waste, the burden posed on the municipal budget as a result of the high costs associated to its management, the lack of understanding over a diversity of factors that affect the different stages of waste management and linkages necessary to enable the entire handling system functioning. An analysis of literature on the work done and reported mainly in publications from 2005 to 2011, related to waste management in developing countries, showed that few articles give quantitative information. The analysis was conducted in two of the major scientific journals, Waste Management Journal and Waste Management and Research. The objective of this research was to determine the stakeholders' action/behavior that have a role in the waste management process and to analyze influential factors on the system, in more than thirty urban areas in 22 developing countries in 4 continents. A combination of methods was used in this study in order to assess the stakeholders and the factors influencing the performance of waste management in the cities. Data was collected from scientific literature, existing data bases, observations made during visits to urban areas, structured interviews with relevant professionals, exercises provided to participants in workshops and a questionnaire applied to stakeholders. Descriptive and inferential statistic methods were used to draw conclusions. The outcomes of the research are a comprehensive list of stakeholders that are relevant in the waste management systems and a set of factors that reveal the most important causes for the systems' failure. The information

Solid waste management challenges for cities in developing countries

International Nuclear Information System (INIS)

Abarca Guerrero, Lilliana; Maas, Ger; Hogland, William

2013-01-01

Highlights: ► Stakeholders. ► Factors affecting performance waste management systems. ► Questionnaire as Annex for waste management baseline assessment. - Abstract: Solid waste management is a challenge for the cities’ authorities in developing countries mainly due to the increasing generation of waste, the burden posed on the municipal budget as a result of the high costs associated to its management, the lack of understanding over a diversity of factors that affect the different stages of waste management and linkages necessary to enable the entire handling system functioning. An analysis of literature on the work done and reported mainly in publications from 2005 to 2011, related to waste management in developing countries, showed that few articles give quantitative information. The analysis was conducted in two of the major scientific journals, Waste Management Journal and Waste Management and Research. The objective of this research was to determine the stakeholders’ action/behavior that have a role in the waste management process and to analyze influential factors on the system, in more than thirty urban areas in 22 developing countries in 4 continents. A combination of methods was used in this study in order to assess the stakeholders and the factors influencing the performance of waste management in the cities. Data was collected from scientific literature, existing data bases, observations made during visits to urban areas, structured interviews with relevant professionals, exercises provided to participants in workshops and a questionnaire applied to stakeholders. Descriptive and inferential statistic methods were used to draw conclusions. The outcomes of the research are a comprehensive list of stakeholders that are relevant in the waste management systems and a set of factors that reveal the most important causes for the systems’ failure. The information provided is very useful when planning, changing or implementing waste management systems

Review of radioactive waste management research in the Agency

International Nuclear Information System (INIS)

2002-01-01

The report presents a concise summary of the Programme of Radioactive Waste Management Research carried out by the Agency in the period 1996 to 2001. It not only provides information, which is relevant to the Agency's responsibilities, but also offers an input to the government's development of a policy for managing solid radioactive waste in the UK. The research projects have included laboratory and field scientific studies, reviews of existing scientific data and understanding, development of assessment methodologies, and development of technical support software and databases. The Agency has participated widely in internationally-supported projects and on jointly-funded projects amongst UK regulators, advisory bodies and industry

Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

International Nuclear Information System (INIS)

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified

Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

Energy Technology Data Exchange (ETDEWEB)

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.

Summary of research and development activities in support of waste acceptance criteria for WIPP

International Nuclear Information System (INIS)

Hunter, T.O.

1979-11-01

The development of waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP) is summarized. Specifications for acceptable waste forms are included. Nine program areas are discussed. They are: TRU characterization, HLW interactions, thermal/structural interactions, nuclide migration, permeability, brine migration, borehole plugging, operation/design support, and instrumentation development. Recommendations are included

Waste management research abstracts volume 27. Information on radioactive waste management research in progress or planned

International Nuclear Information System (INIS)

2002-10-01

This issue of the Waste Management Research Abstracts (WMRA) contains 148 abstracts that describe research in progress in the field of radioactive waste management. The research abstracts contained in Volume 27 (WMRA 27) were collected between July 1, 2001 and September 30, 2002. The abstracts present ongoing work in various countries and international organizations. Although the abstracts are indexed by country, many programmes are actually the result of co-operation among several countries. Indeed, a primary reason for providing this compilation of programmes, institutions and scientists engaged in research into radioactive waste management is to increase international co-operation and facilitate communications

The conceptual design of waste repository for radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity

International Nuclear Information System (INIS)

Yamamoto, Masayuki; Hashimoto, Naro

2002-02-01

Advisory Committee on Nuclear Fuel Cycle Backend Policy reported the basic approach to the RI and Institute etc. wastes on March 2002. According to it, radioactive waste form medical, industrial and research facilities should be classified by their radioactivity properties and physical and chemical properties, and should be disposed in the appropriate types of repository with that classification. For the radioactive waste containing comparatively high radioactivity generated from reactors, NSC has established the Concentration limit for disposal. NSC is now discussing about the limit for the radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity. Japan Nuclear Cycle Development Institute (JNC) preliminary studied about the repository for radioactive waste from medical, industrial and research facilities and discussed about the problems for design on H12. This study was started to consider those problems, and to develop the conceptual design of the repository for radioactive waste from medical, industrial and research facilities. Safety assessment for that repository is also performed. The result of this study showed that radioactive waste from medical, industrial and research facilities of high activity should be disposed in the repository that has higher performance of barrier system comparing with the vault type near surface facility. If the conditions of the natural barrier and the engineering barrier are clearer, optimization of the design will be possible. (author)

Treatment and disposal of radioactive wastes from nuclear power plants. Research programs

International Nuclear Information System (INIS)

1992-09-01

The report presents programs for research, development and demonstration concerning radioactive waste disposal in underground facilities. The main topics are: Radioactive waste management, radioactive waste storage, capsules, environmental impacts, risk assessment, radionuclide migration, radioactive waste disposal, decommissioning, cost, and international cooperation. (129 refs.)

Research and development action of the Commission of the European Communities (CEC) in the field of radioactive waste management

International Nuclear Information System (INIS)

Orlowski, S.; Bresesti, M.

1983-01-01

The CEC R and D action, started in 1973, is carried out within the framework of cost-sharing contracts with Community organizations and in the laboratories of the Joint Research Centre, Ispra. About 350 research workers from 30 organizations within the Community are taking part. The R and D activities cover processing, conditioning, characterization, intermediate storage and final disposal of the radioactive wastes generated in reactors and in fuel reprocessing and fuel fabrication plants. In the Community, spent fuels are not considered as radioactive waste. About one half of the total effort has been devoted to the disposal of high-level and long-lived radioactive wastes in geological formations (granite, clay, salt) and to related studies. The sub-seabed disposal option is also being investigated with a more limited effort. The R and D activities on waste treatment cover low-level, alpha-bearing and gaseous wastes. An important activity has been developed on the characterization of vitrified HLW. A similar activity for the characterization of other types of conditioned wastes has been started. The R and D activity of the CEC is supported by the existence of a Community Plan of Action (1980-1992) which entrusts to the Commission a wider role in the development of waste management policies. The Plan assures in particular the continuity of the R and D work up to 1992. International co-operation is considered important; international symposia have been co-sponsored with the IAEA; co-operative agreements with non-Community countries are in force (such as with Canada) or in preparation (such as with the USA). (author)

Underground disposal of vitrified high level radioactive waste: a review of research and development

International Nuclear Information System (INIS)

1982-11-01

A review has been undertaken of the worldwide status of research and development related to the geological disposal of vitrified high level radioactive waste. The nature and quantities of vitrified high level waste that will arise from nuclear power generation in the UK have been estimated and considered. The safety case for establishing a geological repository would have to be based on predictive models, which could adequately represent the interactions and effects of a wide range of gradual processes and possible sudden events. No detailed repository design has yet been published, but the configuration currently favoured, in the UK and in most other countries, comprises a small number of vertical shafts, from which a network of horizontal tunnels would be excavated. Waste packages would be placed in holes drilled in the floors of the tunnels. The excavation of such a repository in hard crystalline rock, in a thick homogeneous formation of rock salt, or in the less plastic argillaceous formations, appears to be within the scope of present technology. Rock types available in the UK, which are likely to prove suitable for the accommodation of a repository, have been identified. The strategies and programmes for high level waste disposal in other countries have been reviewed. (U.K.)

U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990

Science.gov (United States)

Trask, N.J.; Stevens, P.R.

1991-01-01

The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research efforts are categorized according to whether they are related most directly to: (1) high-level wastes, (2) transuranic wastes, (3) low-level and mixed low-level and hazardous wastes, or (4) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, to development of techniques and methods for characterizing disposal sites, and to studies of geologic and hydrologic processes related to the transport and/or retention of waste radionuclides.

Transportation research activities in support of nuclear waste management programs

International Nuclear Information System (INIS)

Allen, G.C.; Luna, R.E.; Jefferson, R.M.; Wowak, W.E.

1983-01-01

The Transportation Technology Center has been conducting a wide range of technical and non-technical research activities to assure the ability to transport radioactive materials in a safe, reliable, and publicly acceptable manner. These activities include tasks in Information and Intergovernmental issues, Safety Assessment and Environmental Analysis and Technology Development. Until recently, the requirements of defense waste shipments have served as a focal point for development tasks with the expectation that they would serve as a precursor for commercial activities. The passage of the Nuclear Waste Policy Act has placed additional responsibility on DOE for concerns involving the shipments of civilian materials. The development of additional research responsibilities is expected to proceed concurrently with the evolution of the transportation mission plan for civilian spent fuel and high-level wastes

Research needs in cement-based waste forms

International Nuclear Information System (INIS)

McDaniel, E.W.; Spence, R.D.; Tallent, O.K.

1990-01-01

Cement-based waste forms are one of the most widely used waste disposal options, yet definitive knowledge of the fate of the waste species inside the waste form is lacking. A fundamental understanding of the chemistry and microstructure of the waste forms would lead to a better understanding of the mass transfer of the waste species, more confidence in predicting and extrapolating waste form performance, and design of better waste forms. Better and cheaper leach tests would lead to quicker and more cost effective screening of waste form alternatives. In addition, assessment of durability may be important to predicting waste form performance in the field. It should be noted that the research needs discussed in this report are from the perspective of investigators working in applied waste management areas, while the proposed investigations are fundamental or basic. Details as to experimental methods and tools to be used in achieving the objectives of the proposed are research beyond the scope of this paper and are better filled in by others. In broad terms, the research topics discussed are correlation of cement-based waste form physical properties to performance, waste-form fundamental chemistry and microstructure, and product performance testing

Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

International Nuclear Information System (INIS)

Klinkenberg, M.; Neumeier, S.; Bosbach, D.

2011-01-01

Due to the use of nuclear energy about 17.000 t (27.000 m 3 ) of high level waste and about 300.000 m 3 of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear graphite

Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

Energy Technology Data Exchange (ETDEWEB)

Klinkenberg, M; Neumeier, S; Bosbach, D [eds.

2011-07-01

Due to the use of nuclear energy about 17.000 t (27.000 m{sup 3}) of high level waste and about 300.000 m{sup 3} of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear

Interdisciplinary perspectives on dose limits in radioactive waste management : A research paper developed within the ENTRIA project

NARCIS (Netherlands)

Kalmbach, K.; Röhlig, K.-J.

2016-01-01

Within the ENTRIA project, an interdisciplinary group of scientists developed a research paper aiming at a synthesis of the technical, sociology of knowledge, legal, societal, and political aspects of dose limits within the field of radioactive waste management. In this paper, the ENTRIA project is

Development of treatment technology for radioactive concrete wastes

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y.; Choi, W. K.; Lee, K. W., E-mail: bymin@kaeri.re.k [Korea Atomic Energy Research Institute, 1045 Daeduk-daero, Yuseong-gu, Daejeon, 305-353 Republic of Korea (Korea, Republic of)

2010-10-15

The aim of this study was the separation of clean aggregates from contaminated dismantling concrete wastes by thermal and mechanical processes. In Korea, the decontamination and decommissioning of the retired Korea research reactor (KRR) and a uranium conversion plant (UCP) at the Korea Atomic Energy Research Institute (KAERI) has been under way. Hundreds of tons of concrete wastes are expected from these facilities. The KAERI has developed volume reduction technology applicable to an activated heavy concrete waste generated by dismantling KRR-2 and a uranium contaminated light weight concrete produced from a UCP. Contamination level of the gravel and sand aggregates was remarkably decreased by thermal and mechanical process. The volume reduction rate could be achieved above 70% for KRR-2 concrete waste and above to 80% for the UCP concrete waste. (Author)

HARVESTING EMSP RESEARCH RESULTS FOR WASTE CLEANUP

International Nuclear Information System (INIS)

Guillen, Donna Post; Nielson, R. Bruce; Phillips, Ann Marie; Lebow, Scott

2003-01-01

The extent of environmental contamination created by the nuclear weapons legacy combined with expensive, ineffective waste cleanup strategies at many U.S. Department of Energy (DOE) sites prompted Congress to pass the FY96 Energy and Water Development Appropriations Act, which directed the DOE to: ''provide sufficient attention and resources to longer-term basic science research, which needs to be done to ultimately reduce cleanup costs'', ''develop a program that takes advantage of laboratory and university expertise, and'' ''seek new and innovative cleanup methods to replace current conventional approaches which are often costly and ineffective.'' In response, the DOE initiated the Environmental Management Science Program (EMSP)-a targeted, long-term research program intended to produce solutions to DOE's most pressing environmental problems. EMSP funds basic research to lower cleanup cost and reduce risk to workers, the public, and the environment; direct the nation's scientific infrastructure towards cleanup of contaminated waste sites; and bridge the gap between fundamental research and technology development activities. EMSP research projects are competitively awarded based on the project's scientific, merit coupled with relevance to addressing DOE site needs. This paper describes selected EMSP research projects with long, mid, and short-term deployment potential and discusses the impacts, focus, and results of the research. Results of EMSP research are intended to accelerate cleanup schedules, reduce cost or risk for current baselines, provide alternatives for contingency planning, or provide solutions to problems where no solutions exist

Research on the drying kinetics of household food waste for the development and optimization of domestic waste drying technique.

Science.gov (United States)

Sotiropoulos, A; Malamis, D; Michailidis, P; Krokida, M; Loizidou, M

2016-01-01

Domestic food waste drying foresees the significant reduction of household food waste mass through the hygienic removal of its moisture content at source. In this manuscript, a new approach for the development and optimization of an innovative household waste dryer for the effective dehydration of food waste at source is presented. Food waste samples were dehydrated with the use of the heated air-drying technique under different air-drying conditions, namely air temperature and air velocity, in order to investigate their drying kinetics. Different thin-layer drying models have been applied, in which the drying constant is a function of the process variables. The Midilli model demonstrated the best performance in fitting the experimental data in all tested samples, whereas it was found that food waste drying is greatly affected by temperature and to a smaller scale by air velocity. Due to the increased moisture content of food waste, an appropriate configuration of the drying process variables can lead to a total reduction of its mass by 87% w/w, thus achieving a sustainable residence time and energy consumption level. Thus, the development of a domestic waste dryer can be proved to be economically and environmentally viable in the future.

Incorporating regulatory considerations into waste treatment technology development

International Nuclear Information System (INIS)

Siegel, M.R.; Powell, J.A.; Williams, T.A.; Kuusinen, T.L.; Lesperance, A.M.

1991-02-01

It is generally recognized that the development of new and innovative waste treatment technologies can significantly benefit the US Department of Energy's (DOE) environmental restoration and waste management program. DOE has established a research, development, demonstration, testing, and evaluation (RDDT ampersand E) program, managed by its Office of Technology Development, to encourage and direct the development of new waste treatment and management technologies. The treatment, storage, and disposal of hazardous and radioactive waste is heavily regulated both at the federal and state levels. In order to achieve the goals of applying the best new technologies in the fastest and most cost-effective manner possible, it is essential that regulatory factors be considered early and often during the development process. This paper presents a number of regulatory issues that are relevant to any program intended to encourage the development of new waste treatment and management technologies. It will also address how the use of these basic regulatory considerations can help ensure that technologies that are developed are acceptable to regulators and can therefore be deployed in the field. 2 refs

40 CFR 258.4 - Research, development, and demonstration permits.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Research, development, and...) SOLID WASTES CRITERIA FOR MUNICIPAL SOLID WASTE LANDFILLS General § 258.4 Research, development, and... State may issue a research, development, and demonstration permit for a new MSWLF unit, existing MSWLF...

Chemistry research for the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Vikis, A.C.; Garisto, F.; Lemire, R.J.; Paquette, J.; Sagert, N.H.; Saluja, P.P.S.; Sunder, S.; Taylor, P.

1988-01-01

This publication reviews chemical research in support of the Canadian Nuclear Fuel Waste Management Program. The overall objective of this research is to develop the fundamental understanding required to demonstrate the suitability of waste immobilization media and processes, and to develop the chemical information required to predict the long-term behaviour of radionuclides in the geosphere after the waste form and the various engineered barriers containing it have failed. Key studies towards the above objective include experimental and theoretical studies of uranium dioxide oxidation/dissolution; compilation of thermodynamic databases and an experimental program to determine unavailable thermodynamic data; studies of hydrothermal alteration of minerals and radionuclide interactions with such minerals; and a study examining actinide colloid formation, as well as sorption of actinides on groundwater colloids

Low-level radioactive waste research program plan

International Nuclear Information System (INIS)

O'Donnell, E.; Lambert, J.

1989-11-01

The Waste Management Branch, Division of Engineering, Office of Nuclear Regulatory Research, has developed a strategy for conducting research on issues of concern to the US Nuclear Regulatory Commission (NRC) in its efforts to ensure safe disposal of low-level radioactive waste (LLW). The resulting LLW research program plan provides an integrated framework for planning the LLW research program to ensure that the program and its products are responsive and timely for use in NRC's LLW regulatory program. The plan discusses technical and scientific issues and uncertainties associated with the disposal of LLW, presents programmatic goals and objectives for resolving them, establishes a long-term strategy for conducting the confirmatory and investigative research needed to meet these goals and objectives, and includes schedules and milestones for completing the research. Areas identified for investigation include waste form and other material concerns, failure mechanisms and radionuclide releases, engineered barrier performance, site characterization and monitoring, and performance assessment. The plan proposes projects that (1) analyze and test actual LLW and solidified LLW under laboratory and field conditions to determine leach rates and radionuclide releases, (2) examine the short- and long-term performance of concrete-enhanced LLW burial structures and high-integrity containers, and (3) attempt to predict water movement and contaminant transport through low permeability saturated media and unsaturated porous media. 4 figs., 3 tabs

Hazardous waste management in a developing economy

International Nuclear Information System (INIS)

Oladiran, M.T.

1995-01-01

Many developing countries are characterised by steady increase in population, low GNP and usually a single-source economy. These countries are principally situated in the 40degN/40degS window. In order to generate more wealth, there is a great desire for rapid industrialisation in these countries. However, modern technologies and processes are often associated with by-products and wastes which can be bulky, toxic, chemically unstable, corrosive, radio active and sometimes, at elevated temperatures. In this paper, a critical survey of the deleterious effects of hazardous wastes on man and environment is presented. Current disposal techniques and management principles are discussed Non-objectionable procedures and regulatory control mechanisms for dealing with these wastes are presented. Finally, the importance of research and development in handling these wastes are also highlighted. (author)

Development of thermal conditioning technology for Alpha-containment wastes: Alpha-contaminated waste incineration technology

Energy Technology Data Exchange (ETDEWEB)

Kim, Joon Hyung; Kim, Jeong Guk; Yang, Hee Chul; Choi, Byung Seon; Jeong, Myeong Soo

1999-03-01

As the first step of a 3-year project named 'development of alpha-contaminated waste incineration technology', the basic information and data were reviewed, while focusing on establishment of R and D direction to develop the final goal, self-supporting treatment of {alpha}- wastes that would be generated from domestic nuclear industries. The status on {alpha} waste incineration technology of advanced states was reviewed. A conceptual design for {alpha} waste incineration process was suggested. Besides, removal characteristics of volatile metals and radionuclides in a low-temperature dry off-gas system were investigated. Radiation dose assessments and some modification for the Demonstration-scale Incineration Plant (DSIP) at Korea Atomic Energy Research Institute (KAERI) were also done.

Development of thermal conditioning technology for Alpha-containment wastes: Alpha-contaminated waste incineration technology

International Nuclear Information System (INIS)

Kim, Joon Hyung; Kim, Jeong Guk; Yang, Hee Chul; Choi, Byung Seon; Jeong, Myeong Soo

1999-03-01

As the first step of a 3-year project named 'development of alpha-contaminated waste incineration technology', the basic information and data were reviewed, while focusing on establishment of R and D direction to develop the final goal, self-supporting treatment of α- wastes that would be generated from domestic nuclear industries. The status on α waste incineration technology of advanced states was reviewed. A conceptual design for α waste incineration process was suggested. Besides, removal characteristics of volatile metals and radionuclides in a low-temperature dry off-gas system were investigated. Radiation dose assessments and some modification for the Demonstration-scale Incineration Plant (DSIP) at Korea Atomic Energy Research Institute (KAERI) were also done

Systematic analysis method for radioactive wastes generated from nuclear research facilities

International Nuclear Information System (INIS)

Kameo, Yutaka; Ishimori, Ken-ichiro; Haraga, Tomoko; Shimada, Asako; Katayama, Atsushi; Nakashima, Mikio; Takahashi, Kuniaki

2011-01-01

Analytical methods have been developed for the simple and rapid determination of radioactive nuclides, which are selected as important nuclides for the safety assessment of the disposal of wastes generated from research facilities. We advanced the development of a high-efficiency nondestructive measurement technique for γ-ray-emitting nuclides, simple and rapid methods for the pretreatment of hard-to-dissolve samples and subsequent radiochemical separation, and rapid determination methods for long-lived nuclides. In order to establish a system to analyze the important nuclides in various kinds of sample, actual radioactive wastes such as concentrated liquid waste, activated concrete, and metal pipes were analyzed by the present method. The results showed that the present method was well suited for a rapid and simple determination of low-level radioactive wastes generated from research facilities. (author)

Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

Energy Technology Data Exchange (ETDEWEB)

Klinkenberg, M.; Neumeier, S.; Bosbach, D. (eds.)

2011-07-01

Due to the use of nuclear energy about 17.000 t (27.000 m{sup 3}) of high level waste and about 300.000 m{sup 3} of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear

Developing the Librarians' Role in Supporting Grant Applications and Reducing Waste in Research: Outcomes from a Literature Review and Survey in the NIHR Research Design Service

Science.gov (United States)

Edmunds Otter, Mary L.; Wright, Judy M.; King, Natalie V.

2017-01-01

Librarians and information specialists' involvement during the development of grant applications for external funding can save researchers' time, provide specialist support, and contribute to reducing avoidable waste in research. This article presents a survey of information specialists working for the National Institute for Health Research's…

Development of Municipal Solid Waste Management

OpenAIRE

Teibe, Inara

2015-01-01

This paper is based on an empirical work done by author on a series of case studies such us document studies and analyzing the best practices examples. The objective of this research is to find out barriers to reach regional waste management plan demands in three municipalities: Salacgriva, Saulkrasti and Ikskile. Author gives proposal with some recommendations for development of municipal waste management as well. There are several views and attitudes of local stakeholders such us municipali...

The Community's research and development programme on radioactive waste management and storage

International Nuclear Information System (INIS)

Orlowski, S.; Gandolfo, J.M.

1988-01-01

This is the first annual progress report of the European Community's 1985-89 programme of research on radioactive waste management and disposal, carried out by public organizations and private firms in the Community under cost-sharing contracts with the Commission of the European Communities. The 1985-89 programme is aiming at perfecting and demonstrating a system for managing the radioactive waste produced by the nuclear industry, ensuring at the various stages the best possible protection of man and the environment. This first report describes the work to be carried out under the research contracts already concluded before end of 1986 as well as the initial work performed and the first results obtained. For each contract, paragraph C ''Progress of work and obtained results'' was prepared by the contractor under the responsibility of the project leader

HARVESTING EMSP RESEARCH RESULTS FOR WASTE CLEANUP

Energy Technology Data Exchange (ETDEWEB)

Guillen, Donna Post; Nielson, R. Bruce; Phillips, Ann Marie; Lebow, Scott

2003-02-27

The extent of environmental contamination created by the nuclear weapons legacy combined with expensive, ineffective waste cleanup strategies at many U.S. Department of Energy (DOE) sites prompted Congress to pass the FY96 Energy and Water Development Appropriations Act, which directed the DOE to: ''provide sufficient attention and resources to longer-term basic science research, which needs to be done to ultimately reduce cleanup costs'', ''develop a program that takes advantage of laboratory and university expertise, and'' ''seek new and innovative cleanup methods to replace current conventional approaches which are often costly and ineffective.'' In response, the DOE initiated the Environmental Management Science Program (EMSP)-a targeted, long-term research program intended to produce solutions to DOE's most pressing environmental problems. EMSP funds basic research to lower cleanup cost and reduce risk to workers, the public, and the environment; direct the nation's scientific infrastructure towards cleanup of contaminated waste sites; and bridge the gap between fundamental research and technology development activities. EMSP research projects are competitively awarded based on the project's scientific, merit coupled with relevance to addressing DOE site needs. This paper describes selected EMSP research projects with long, mid, and short-term deployment potential and discusses the impacts, focus, and results of the research. Results of EMSP research are intended to accelerate cleanup schedules, reduce cost or risk for current baselines, provide alternatives for contingency planning, or provide solutions to problems where no solutions exist.

Hospital waste management in developing countries: A mini review.

Science.gov (United States)

Ali, Mustafa; Wang, Wenping; Chaudhry, Nawaz; Geng, Yong

2017-06-01

Health care activities can generate different kinds of hazardous wastes. Mismanagement of these wastes can result in environmental and occupational health risks. Developing countries are resource-constrained when it comes to safe management of hospital wastes. This study summarizes the main issues faced in hospital waste management in developing countries. A review of the existing literature suggests that regulations and legislations focusing on hospital waste management are recent accomplishments in many of these countries. Implementation of these rules varies from one hospital to another. Moreover, wide variations exist in waste generation rates within as well as across these countries. This is mainly attributable to a lack of an agreement on the definitions and the methodology among the researchers to measure such wastes. Furthermore, hospitals in these countries suffer from poor waste segregation, collection, storage, transportation and disposal practices, which can lead to occupational and environmental risks. Knowledge and awareness regarding proper waste management remain low in the absence of training for hospital staff. Moreover, hospital sanitary workers, and scavengers, operate without the provision of safety equipment or immunization. Unsegregated waste is illegally recycled, leading to further safety risks. Overall, hospital waste management in developing countries faces several challenges. Sustainable waste management practices can go a long way in reducing the harmful effects of hospital wastes.

Research and development of CRIEPI

International Nuclear Information System (INIS)

Akita, Shirabe

2008-01-01

Central Research Institute of Electric Power Industry (CRIEPI) reported its R and D of nuclear power technologies. The research results of light water reactor aging deterioration contain the estimation method of irradiation embrittlement of pressure vessel, stress corrosion cracking of piping and core internal structure, and pipe thinning. The backend project support researches include transpiration and storage of recycle fuel, the high-level radioactive waste disposal and low-level radioactive waste disposal. Safety of concrete cask storage was confirmed by the falling test, SCC test and vibration test. The researches for the next generation nuclear technologies have developed the pyrochemical reprocessing process for the metal fuel and oxide fuel, and development of metal fuel with U, Pu and Zr. Assist management of development of fast reactor is proceeding. One of researches of radiation safety is on low dose X-ray bystander effect on the diabetes mellitus of model mouse. (S.Y.)

Latest research progress on food waste management: a comprehensive review

Science.gov (United States)

Zhu, Shangzhen; Gao, Hetong; Duan, Lunbo

2018-05-01

Since a large amount of food supplying is provided as a basic line measuring increasing residents’ life standard, food waste has become progressively numeral considerable. Much attention has been drawn to this problem. This work gave an overview on latest researches about anaerobic digestion, composting, generalized management and other developments on management of food waste. Different technologies were introduced and evaluated. Further views on future research in such a field were proposed.

Research and development work on radioactive waste management and storage of chemical-toxic wastes - first half of 1992

International Nuclear Information System (INIS)

1992-10-01

This progress report covers the state and results of the projects undertaken in the area of waste management. In particular, results in the area of decommissioning and retreat of nuclear installations are documented. Furthermore, measures designed to increase environmental compatibility are taken into account. Experimental results regarding the concept, planning, construction, operation, decommissioning and post-operational phase of a repository or underground disposal of hazardous wastes are also described. Lists of formalized interim reports and research institutions involved are attached. (DG) [de

Nuclear wastes: research programs

International Nuclear Information System (INIS)

Anon.

2003-01-01

The management of long-living and high level radioactive wastes in France belongs to the framework of the December 30, 1991 law which defines three ways of research: the separation and transmutation of radionuclides, their reversible storage or disposal in deep geologic formations, and their processing and surface storage during long duration. Research works are done in partnership between public research and industrial organizations in many French and foreign laboratories. Twelve years after its enforcement, the impact of this law has overstepped the simple research framework and has led to a deep reflection of the society about the use of nuclear energy. This short paper presents the main results obtained so far in the three research ways, the general energy policy of the French government, the industrial progresses made in the framework of the 1991 law and the international context of the management of nuclear wastes. (J.S.)

Development of an incineration system for radioactive waste

International Nuclear Information System (INIS)

Chrubasik, A.

1989-01-01

NUKEM GmbH (W. Germany) has developed and built some plants for treatment of radioactive waste. In cooperation with Karlsruhe Nuclear Research Center and on the basis of non-nuclear incineration plants, NUKEM has designed and built a new incineration plant for low level radioactive solid waste. The main features of the plant are improvement of the waste handling during feeding, very low particulate load downstream the incinerator and simple flue-gas cleaning system. This process is suitable for treatment of waste generated above all in nuclear power plants. (author)

Structure of technical systems: interpersonal networks and performance in nuclear waste and photovoltaic research

International Nuclear Information System (INIS)

Shrum, W.M. Jr.

1982-01-01

The organization of scientific technology in modern, industrialized societies is examined by comparing two large-scale, multi-organizational, mission-oriented research networks. Using national data from personal interviews with 297 scientists, engineers, research managers, and policy makers from 97 organizations involved in nuclear waste management and solar-photovoltaic development, this study develops and tests hypotheses on the relationships among governmental, academic, private, and public interest sectors and the kinds of social linkages which are associated with technical performance. The principal finding is that in photovoltaic research, contacts with the research community are associated with high levels of performance, while for nuclear waste researchers, they are not. Instead, linkages to the governmental sector predict performance in nuclear waste research. This difference is explained by the governmental domination of the nuclear-waste system and the lack of private-sector involvement

Waste management research abstracts. Information on radioactive waste management research in progress or planned. Vol. 29

International Nuclear Information System (INIS)

2004-11-01

The twenty-ninth issue of the Waste Management Research Abstracts (WMRA) contains 96 abstracts that describe research in progress in the field of radioactive waste management. These abstracts were collected between May 1 and October 15, 2004 and present ongoing work in Brazil(1), Finland (1), Germany (7), India (11), Mauritius (1), republic of Korea (1), Russian Federation (1) and the United States of America (70). Although the abstracts are indexed by country, some programmes are actually the result of co-operation among several countries. Indeed, a primary reason for providing this compilation of programmes, institutions and scientists engaged in research into radioactive waste management is to increase international co-operation and facilitate communications

Development of iron phosphate ceramic waste form to immobilize radioactive waste solution

Energy Technology Data Exchange (ETDEWEB)

Choi, Jongkwon [Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), San 31, Hyoja-Dong, Pohang (Korea, Republic of); Um, Wooyong, E-mail: wooyong.um@pnnl.gov [Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), San 31, Hyoja-Dong, Pohang (Korea, Republic of); Pacific Northwest National Laboratory, Richland, WA 99354 (United States); Choung, Sungwook [Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), San 31, Hyoja-Dong, Pohang (Korea, Republic of)

2014-09-15

The objective of this research was to develop an iron phosphate ceramic (IPC) waste form using converter slag obtained as a by-product of the steel industry as a source of iron instead of conventional iron oxide. Both synthetic off-gas scrubber solution containing technetium-99 (or Re as a surrogate) and LiCl–KCl eutectic salt, a final waste solution from pyrochemical processing of spent nuclear fuel, were used as radioactive waste streams. The IPC waste form was characterized for compressive strength, reduction capacity, chemical durability, and contaminant leachability. Compressive strengths of the IPC waste form prepared with different types of waste solutions were 16 MPa and 19 MPa for LiCl–KCl eutectic salt and the off-gas scrubber simulant, respectively, which meet the minimum compressive strength of 3.45 MPa (500 psi) for waste forms to be accepted into the radioactive waste repository. The reduction capacity of converter slag, a main dry ingredient used to prepare the IPC waste form, was 4136 meq/kg by the Ce(IV) method, which is much higher than those of the conventional Fe oxides used for the IPC waste form and the blast furnace slag materials. Average leachability indexes of Tc, Li, and K for the IPC waste form were higher than 6.0, and the IPC waste form demonstrated stable durability even after 63-day leaching. In addition, the Toxicity Characteristic Leach Procedure measurements of converter slag and the IPC waste form with LiCl–KCl eutectic salt met the universal treatment standard of the leachability limit for metals regulated by the Resource Conservation and Recovery Act. This study confirms the possibility of development of the IPC waste form using converter slag, showing its immobilization capability for radionuclides in both LiCl–KCl eutectic salt and off-gas scrubber solutions with significant cost savings.

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1992-07-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1993-06-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1991-07-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

Hazardous waste management in research laboratories

International Nuclear Information System (INIS)

Sundstrom, G.

1989-01-01

Hazardous waste management in research laboratories benefits from a fundamentally different approach to the hazardous waste determination from industry's. This paper introduces new, statue-based criteria for identifying hazardous wastes (such as radiological mixed wastes and waste oils) and links them to a forward-looking compliance of laboratories, the overall system integrates hazardous waste management activities with other environmental and hazard communication initiatives. It is generalizable to other waste generators, including industry. Although only the waste identification and classification aspects of the system are outlined in detail here, four other components are defined or supported, namely: routine and contingency practices; waste treatment/disposal option definition and selection; waste minimization, recycling, reuse, and substitution opportunities; and key interfaces with other systems, including pollution prevention

Low-level radioactive waste management research and development

International Nuclear Information System (INIS)

DePoorter, G.L.; Abeele, W.V.; Hakonson, T.E.; Nyhan, J.W.; Perkins, B.A.; White, G.C.; Travis, B.J.; Lane, L.J.

1983-01-01

In previous years, a 21-acre field site has been developed in which large-scale, but well-controlled, field experiments are performed. Experiments are in progress to measure the effects of biological (plants and animals) intrusion on contaminant transport; to measure the movement of water and contaminants under unsaturated conditions; to field test configurations of natural materials to divert water away from the top of a waste disposal facility (wick effect); to measure the movement of contaminants from the subsurface to the surface caused by evaporation at the surface; to measure and quantify erosion, runoff, and infiltration; and to measure the effects of trench subsidence on some of the methods developed for improved burial facilities. An extensive modeling effort is combined with the large-scale field experiments

Waste disposal[1997 Scientific Report of the Belgian Nuclear Research Centre

Energy Technology Data Exchange (ETDEWEB)

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

1998-07-01

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.

Low-level waste research and development activities of the Department of Energy

International Nuclear Information System (INIS)

Barainca, M.J.

1986-01-01

This paper presents an overview of the technical activities of the Department of Energy's Defense and Nuclear Energy Low-Level Radioactive Waste Management Programs (LLWPs). Although each Program was established with a different purpose, the technologies developed and demonstrated by each are transferable for use in both the commercial and DOE sectors. This paper presents an overview of the technical activities being pursued through both the Defense and Nuclear Energy LLWP's. These technologies have been placed in the following categories; Criteria and Standards, Systems Analysis, Information and Technology Transfer, Waste Treatment and Wast Form, Improved Near Surface Disposal, Greater Confinement Disposal, Corrective Measures, and Monitoring

Waste water pilot plant research, development, and demonstration permit application

International Nuclear Information System (INIS)

1991-10-01

Waste waters have been generated as result of operations conducted at the Hanford Facility for over 40 years. These waste waters were previously discharged to cribs, ponds, or ditches. Examples of such waste waters include steam condensates and cooling waters that have not been in contact with dangerous or mixed waste and process condensates that may have been in contact with dangerous or mixed waste. Many measures have been taken to reduce the amount of contamination being discharged in these effluents. However, some of these waste waters still require additional treatment before release to the environment. Systems are being designed and built to treat these waste waters along with any future waste waters resulting from remediation activities on the Hanford Facility

Proceedings of the research conference on post-accident waste management safety (RCWM2016) and the technical seminar on safety research for radioactive waste storage

International Nuclear Information System (INIS)

Motooka, Takafumi; Yamagishi, Isao

2017-03-01

Collaborative Laboratories for Advanced Decommissioning Science (CLADS) is responsible to promote international cooperation in the R and D activities on the decommissioning of Fukushima Daiichi Nuclear Power Station and to develop the necessary human resources. CLADS held the Research Conference on Post-accident Waste Management Safety (RCWM2016) on 7th November, 2016 and the Technical Seminar on Safety Research for Radioactive Waste Storage on 8th November, 2016. This report compiles the abstracts and the presentation materials in the above conference and seminar. (author)

Development of a Comprehensive Radioactive Waste Management Program in the Kingdom of Morocco

International Nuclear Information System (INIS)

Abderrahim, Bouhi; Bouchta, Moussaif; El Maati, Mouldoura; Touria, Lambarki; Touria, El Ghailassai; Fischer, R.

2009-01-01

The Kingdom of Morocco has been a signatory of the International Atomic Energy Agency (IAEA) Joint Convention on the Management of Spent Fuel and Radioactive Waste since 1999. In fact Morocco was the first African country to ratify the joint convention. The Centre National de Energie des Sciences et des Techniques Nucleaires (CNESTEN) has been designated as the lead entity within the country for radioactive waste management. Morocco is in the process of receiving authorization to begin operating a new 2 MW MARK-II TRIGA research reactor at its Nuclear Energy Research Center (CENM) in Maamora. With the commissioning of the research reactor imminent, the waste management program has been preparing to disposition waste streams from the reactor, associated research operations, production of radioisotopes and anticipated future needs. The center is also the designated collection and storage facility for radioactive waste generated in the country, primarily spent sealed sources. This paper focuses on developing a radioactive waste management program that meets international standards in a class C country as described in Selection of Efficient Options for Processing and Storage of Radioactive Waste in Countries with Small Amounts of Waste Generation (class C countries are countries with research reactors but without nuclear power plants). In building their radioactive waste management program Morocco has made good use of experts from the IAEA and under a Sister Laboratory Agreement has worked with waste management personnel from the United States. This cooperative approach has provided assistance to Morocco in developing a safe and compliant program. Developing waste stream disposition pathways for all possible waste types can be especially challenging given the lack of commercial waste management infrastructure within the country. This paper will detail how waste management decisions are made, the waste management technology that was selected and how waste conditioning

Socio-technical systems analysis of waste to energy from municipal solid waste in developing economies: a case for Nigeria

Directory of Open Access Journals (Sweden)

Iyamu Hope O.

2017-01-01

Full Text Available Waste generation is an inevitable by-product of human activity, and it is on the rise due to rapid urbanisation, industrialisation, increased wealth and population. The composition of municipal solid waste (MSW in developed and developing economies differ, especially with the organic fraction. Research shows that the food waste stream of MSW in developing countries is over 50%. The case study for this investigation, Nigeria, has minimal formal recycling or resource recovery programs. The average composition of waste from previous research in the country is between 50–70% putrescible and 30–50% non-putrescible, presenting significant resource recovery potential in composting and biogas production. Waste-to-energy (WtE is an important waste management solution that has been successfully implemented and operated in most developed economies. This contribution reports the conditions that would be of interest before WtE potentials of MSW is harnessed, in an efficient waste management process in a developing economy like Nigeria. The investigation presents a set of socio-technical parameters and transition strategy model that would inform a productive MSW management and resource recovery, in which WtE can be part of the solution. This model will find application in the understanding of the interactions between the socio-economic, technical and environmental system, to promote sustainable resource recovery programs in developing economies, among which is WtE.

Study of research needs and priorities in radioactive waste management

International Nuclear Information System (INIS)

Carson, W.E.; Mitchell, W. III.

1984-02-01

This report presents the results of an assessment of long-range research needs in nuclear waste management. The purpose is to aid the Director of Energy Research in determining the health of DOE's research programs. The intent of the project reported here was to identify additional, basic research necessary in the 1980s and 1990s to develop an adequate scientific data base for nuclear waste management activities likely to be important around the turn of the century. The recommendations resulted from an overview of the entire area of nuclear waste management, not from focused examinations of narrow topics within that area. The suggested research may be the subject of future studies or more intense work by DOE. The recommendations presented in this report are not accompanied by designations of responsible program offices within DOE. It is anticipated that the contents of the report will be shared with the program offices involved and that those offices will recognize and respond to recommendations within their purviews

Handling and final disposal of nuclear waste. Programme for research development and other measures

International Nuclear Information System (INIS)

1989-09-01

The report is divided into two parts. Part 1 presents the premises for waste management in Sweden and the waste types that are produced in Sweden. A brief description is then provided of the measures required for the handling and disposal of the various waste forms. An account of measures for decommissioning of nuclear power plants is also included. Part 2 describes the research program for 1990-1995, which includes plans for siting, repository design; studies of rock properties and chemistry, biosphere, technological barriers. Activities within two large projects, the Stripa laboratory and Natural analogues are also described. 240 refs. 40 figs

Design and Development of a Smart Waste Bin

Directory of Open Access Journals (Sweden)

Michael E.

2017-10-01

Full Text Available For years waste bin has been part of our lives this has necessitated many inventions and innovations to make it automated. In this light much research was channeled towards the opening and closing of the bin when the presence of human is sensed. However this may be considered less smart since the bin will operate when the presence of human is sensed even though there is no intention to use it. To avert this ill this paper presents the design and development of a smart waste bin. The objective of this paper is to develop a smart waste bin that detects the presence of man at a particular distance 1 meter for usage so as not to spill the dirt and obeys voice command to open or close the lid. This is achieved by the use of PIR ultrasonic module voice recognition module Arduino and servo motor. Results gotten after testing the developed system shows that the performance of the waste bin attains a better level of smartness compared to existing waste bin.

Waste management research abstracts no. 21

International Nuclear Information System (INIS)

1992-12-01

The 21th issue of this publication contains over 700 abstracts from 35 IAEA Member Countries comprehending various aspects of radioactive waste management. Radioactive waste disposal, processing and storage, geochemical and geological investigations related to waste management, mathematical models and environmental impacts are reviewed. Many programs involve cooperation among several countries and further international cooperation is expected to be promoted through availability of compiled information on research programs, institutions and scientists engaged in waste management

Waste management research abstracts. No. 20

International Nuclear Information System (INIS)

1990-10-01

The 20th issue of this publication contains over 700 abstracts from 32 IAEA Member Countries comprehending various aspects of radioactive waste management. Radioactive waste disposal, processing and storage, geochemical and geological investigations related to waste management, mathematical models and environmental impacts are reviewed. Many programs involve cooperation among several countries and further international cooperation is expected to be promoted through availability of compiled information on research programs, institutions and scientists engaged in waste management

Safety research activities on radioactive waste management in JNES

International Nuclear Information System (INIS)

Otsuka, Ichiro; Aoki, Hiroomi; Suko, Takeshi; Onishi, Yuko; Masuda, Yusuke; Kato, Masami

2010-01-01

Research activities in safety regulation of radioactive waste management are presented. Major activities are as follows. As for the geological disposal, major research areas are, developing 'safety indicators' to judge the adequacy of site investigation results presented by an implementer (NUMO), compiling basic requirements of safety design and safety assessment needed to make a safety review of the license application and developing an independent safety assessment methodology. In proceeding research, JNES, Japan Atomic Energy Agency (JAEA) and the National Institute of Advanced Industrial Science and Technology (AIST) signed an agreement of cooperative study on geological disposal in 2007. One of the ongoing joint studies under this agreement has been aimed at investigating regional-scale hydrogeological modeling using JAEA's Horonobe Underground Research Center. In the intermediate depth disposal, JNES conducted example analysis of reference facility and submitted the result to Nuclear Safety Commission of Japan (NSC). JNES is also listing issues to be addressed in the safety review of the license application and tries to make criteria of the review. Furthermore, JNES is developing analysis tool to evaluate long term safety of the facility and conducting an experiment to investigate long term behavior of engineered barrier system. In the near surface disposal of waste package, it must be confirmed by a regulatory inspector whether each package meets safety requirements. JNES continuously updates the confirmation methodology depending on new processing technologies. The clearance system was established in 2005. Two stages of regulatory involvement were adapted, 1) approval for measurement and judgment methods developed by the nuclear operator and 2) confirmation of measurement and judgment results based on approved methods. JNES is developing verification methodology for each stage. As for decommissioning, based on the regulatory needs and a research program

Environmental development plan. LWR commercial waste management

International Nuclear Information System (INIS)

1980-08-01

This Environmental Development Plan (EDP) identifies the planning and managerial requirements and schedules needed to evaluate and assess the environmental, health and safety (EH and S) aspects of the Commercial Waste Management Program (CWM). Environment is defined in its broadest sense to include environmental, health (occupational and public), safety, socioeconomic, legal and institutional aspects. This plan addresses certain present and potential Federal responsibilities for the storage, treatment, transfer and disposal of radioactive waste materials produced by the nuclear power industry. The handling and disposal of LWR spent fuel and processed high-level waste (in the event reprocessing occurs) are included in this plan. Defense waste management activities, which are addressed in detail in a separate EDP, are considered only to the extent that such activities are common to the commercial waste management program. This EDP addresses three principal elements associated with the disposal of radioactive waste materials from the commercial nuclear power industry, namely Terminal Isolation Research and Development, Spent Fuel Storage and Waste Treatment Technology. The major specific concerns and requirements addressed are assurance that (1) radioactivity will be contained during waste transport, interim storage or while the waste is considered as retrievable from a repository facility, (2) the interim storage facilities will adequately isolate the radioactive material from the biosphere, (3) the terminal isolation facility will isolate the wastes from the biosphere over a time period allowing the radioactivity to decay to innocuous levels, (4) the terminal isolation mode for the waste will abbreviate the need for surveillance and institutional control by future generations, and (5) the public will accept the basic waste management strategy and geographical sites when needed

Impact assessment of the forest fires on Oarai Research and Development Center Waste Treatment Facility

International Nuclear Information System (INIS)

Shimomura, Yusuke; Kitamura, Ryoichi; Hanari, Akira; Sato, Isamu

2016-03-01

In response to new standards for regulating waste treatment facility ('new regulatory standards'; December 18, 2013 enforcement), it was carried out impact assessment of forest fires on the Waste Treatment Facility existed in Oarai Research and Development Center of Japan Atomic Energy Agency. At first, a fire spread scenario of forest fires was assumed. The intensity of forest fires was evaluated from field surveys, forest fire evaluation models and so on. As models of forest fire intensity evaluation, Rothermel Model and Canadian Forest Fire Behavior Prediction (FBP) System were used. Impact assessment of radiant heat to the facility was carried out, and temperature change of outer walls for the assumed forest fires was estimated. The outer wall temperature of facility was estimated around 160degC at the maximum, it was revealed that it doesn't reach allowable temperature limit. Consequently, it doesn't influence the strength of concrete. In addition, a probability of fire breach was estimated to be about 20%. This report illustrates an example of evaluation of forest fires for the new regulatory standards through impact assessment of the forest fires on the Waste Treatment Facility. (author)

Experience in radioactive waste management of research centre-CIAE

International Nuclear Information System (INIS)

Luo Shanggeng

2001-01-01

China Institute of Atomic Energy (CIAE) is the birthplace of China nuclear science and technology and the important base for nuclear science and technology implementing pioneering, basic and comprehensive studies. The major tasks and activities of CIAE are: (1) Fundamental research of nuclear science and technology; (2) Research and development of advanced nuclear energy; and (3) Application of nuclear technology. CIAE is equipped with three research reactors (15MW heavy water reactor, 3.5MW light water swimming pool reactor, 27kW neutron source reactor), four zero-power facilities, eleven accelerators, hot cells and a lot of glove boxes which produce various kinds of radioactive wastes. CIAE pays great attention to the safe management of radioactive waste. Many measurements were and are adopted. CIAE carries out the national policy of radioactive waste management and the international fundamental principles of radioactive waste management. To protect human body and environment both now and future generation minimizes the releasing amounts and activity, minimizes the solidified wastes to be disposed of. The principles of 'controlled generation, categorized collection, volume-reduction immobilization, reliable package, in-situ storage, safe transportation and disposal' are followed in managing LLW and ILW. The liquid wastes are separately treated by precipitation, evaporation, ion exchange or adsorption by organic or inorganic materials. The spent organic solvents are treated by incineration at a special incinerator. The low level radioactive gases and liquids can be discharged into the environment only when they are clean-up and permissible level is achieved. Such discharge is controlled by two factors: total discharge amount and specific activity. The solid wastes are separately collected in site according to their physical properties and specific activity. The storage waste is retrievable designed. The spent/sealed radiation sources are collected and stored with

Study of waste acceptance criteria for low-level radioactive waste from medical, industrial, and research facilities (Contract research)

International Nuclear Information System (INIS)

Koibuchi, Hiroto; Dohi, Terumi; Ishiguro, Hideharu; Hayashi, Masaru; Senda, Masaki

2008-12-01

Japan Atomic Energy Agency (JAEA) is supposed to draw up the plan for the disposal program of the very low-level radioactive waste and low-level radioactive waste generated from medical, industrial and research facilities. For instance, there are these facilities in JAEA, universities, private companies, and so on. JAEA has to get to know about the waste and its acceptance of other institutions described above because it is important for us to hold the licenses for the disposal program regarding safety assessment. This report presents the basic data concerning radioactive waste of research institutes etc. except RI waste, domestic and foreign information related to acceptance criteria for disposal of the low-level radioactive waste, the current status of foreign medical waste management, waste acceptance, and such. In this report, Japan's acceptance criteria were summarized on the basis of present regulation. And, the criteria of foreign countries, United States, France, United Kingdom and Spain, were investigated by survey of each reference. In addition, it was reported that the amount of waste from laboratories etc. for near-surface disposal and their characterization in our country. The Subjects of future work: the treatment of hazardous waste, the problem of the double-regulation (the Nuclear Reactor Regulation Law and the Law Concerning Prevention from Radiation Hazards due to Radioisotopes and Others) and the possession of waste were discussed here. (author)

Recent developments in the DOE Waste Minimization Pollution Prevention Program

International Nuclear Information System (INIS)

Hancock, J.K.

1993-01-01

The U.S. Department of Energy (DOE) is involved in a wide variety of research and development, remediation, and production activities at more than 100 sites throughout the United States. The wastes generated cover a diverse spectrum of sanitary, hazardous, and radioactive waste streams, including typical office environments, power generation facilities, laboratories, remediation sites, production facilities, and defense facilities. The DOE's initial waste minimization activities pre-date the Pollution Prevention Act of 1990 and focused on the defense program. Little emphasis was placed on nonproduction activities. In 1991 the Office of Waste Management Operations developed the Waste Minimization Division with the intention of coordinating and expanding the waste minimization pollution prevention approach to the entire complex. The diverse nature of DOE activities has led to several unique problems in addressing the needs of waste minimization and pollution prevention. The first problem is developing a program that addresses the geographical and institutional hurdles that exist; the second is developing a monitoring and reporting mechanism that one can use to assess the overall performance of the program

Material Recover and Waste Form Development--2016 Accomplishments

Energy Technology Data Exchange (ETDEWEB)

Todd, Terry A. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Vienna, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Paviet, Patricia [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-12-01

The Material Recovery and Waste Form Development (MRWFD) Campaign under the U.S. Department of Energy (DOE) Fuel Cycle Technologies (FCT) Program is responsible for developing advanced separation and waste form technologies to support the various fuel cycle options defined in the DOE Nuclear Energy Research and Development Roadmap, Report to Congress (April 2010). This MRWFD accomplishments report summarizes the results of the research and development (R&D) efforts performed within MRWFD in Fiscal Year (FY) 2016. Each section of the report contains an overview of the activities, results, technical point of contact, applicable references, and documents produced during the FY. This report briefly outlines campaign management and integration activities but primarily focuses on the many technical accomplishments of FY 2016. The campaign continued to use an engineering-driven, science-based approach to maintain relevance and focus.

The Nagra Research, Development and Demonstration (RD and D) plan for the disposal of radioactive waste in Switzerland

International Nuclear Information System (INIS)

2009-11-01

NAGRA's mission is to develop safe geological repositories for all radioactive wastes arising in Switzerland. Two types of repositories are foreseen, one for low and intermediate level waste (L/ILW) and one for spent fuel, vitrified high level waste and long-lived ILW (SF/HLW/ILW). Repository implementation involves a stepwise process that takes several decades, which is presented in the RD and D (research, development and demonstration) plan). The main objective of the RD and D Plan is to establish the purpose, scope, nature and timing of future RD and D activities. Chapter 1 presents the overall objectives of the report and a brief history of the steps leading to the present situation. NAGRA had shown in the project 'Entsorgungsnachweis' (disposal feasibility) that safe disposal of SF/HLW/ILW in Switzerland is technically feasible. Based on this result, the Federal Government initiated the Sectoral Plan for Geological Repositories. This Plan provides a framework within which specific objectives must be met for selecting suitable sites for disposal of both L/ILW and SF/HLW/ILW for which general licence applications are to be made. Stage 1 of the Sectoral Plan results in the selection of geologically suitable siting regions. Chapter 2 presents the overall planning premises for implementation of repositories for L/ ILW and SF/HLW/ILW including the assumed schedule, the waste types and quantities and the safety strategy for the repositories. The time plan includes the general licence procedure, construction and operation of Underground Research Laboratories at the sites, construction licence procedure and the operating licence procedure. It is expected that emplacement of L/ILW could begin in about 2035, whereas SF/HLW emplacement would begin about 2050. Waste emplacement is followed by a monitoring period (planning assumption of 50 years), at the end of which an application would be made for closure. The various waste types and quantities produced by nuclear power

Dossier: management of nuclear wastes. Research, results

International Nuclear Information System (INIS)

Anon.

2001-01-01

The researches carried out since many years on nuclear wastes have led to two main ways of management: the long-term conditioning of radio-elements and their advanced separation. The French atomic energy commission (CEA) has chosen to take up also the transmutation challenge, a way to transform long-living radioactive wastes into short-living radioactive wastes or stable compounds. The transmutation programs are based both on simulation and experiments with a huge international collaboration. This dossier presents in a digest way the research activity carried out on nuclear wastes processing and management at the CEA. (J.S.)

Quality assurance activities in nuclear research and development

Energy Technology Data Exchange (ETDEWEB)

Suzuki, Mitsutoshi; Ishikawa, Hirohisa [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

2001-03-01

A case study into the quality management system of the Associated Nuclear Research Association has been performed with reference to the fast breeder reactor (FBR) cycle and high-level waste management (HLWM) research fields. The Japan Nuclear Cycle Development Institute's major research and development projects are in these fields. Progress in the quality management system for research subjects has been compared and analyzed by comparing with both the development level of individual projects and the external environment. Computer-assisted performance assessment systems analysis (CAPASA) in high-level waste management is described as a practical example. (author)

Development of disposal technologies for radioactive waste generated from radioisotope users and research institutes

International Nuclear Information System (INIS)

Sakai, Akihiro; Yoshimori, Michiro

2001-01-01

In order to safely dispose of a radioactive waste, which is generated from radioisotope users and research institutes, investigation of characteristics of the waste and conceptual design of disposal facility were carried out. As a result of investigating JAERI that the waste has mainly been stored, it became clear that radioactivities of 19 nuclides are important from the viewpoint of the safety of the disposal. And the result of the conceptual design of disposal facilities on the assumption of 3 kinds of sites, the differences on the safety could not be recognized in either case, though the installation depth to construct the facilities influenced the economical efficiency. (author)

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-01-01

Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requirements of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs.

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

International Nuclear Information System (INIS)

1988-01-01

Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requiremenrs of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs

Research programme on radioactive wastes; Forschungsprogramm Radioaktive Abfaelle

Energy Technology Data Exchange (ETDEWEB)

Eckhardt, A. [Eidgenoessische Kommission fuer die Sicherheit der Kernanlagen (KSA), Brugg (Switzerland); Hufschmid, P. [Kommission Nukleare Entsorgung (KNE), Bern (Switzerland); Jordi, S. [Swiss Federal Office of Energy, Berne (Switzerland); Schanne, M. [Institut fuer Angewandte Medienwissenschaft (IAM), Zuercher Hochschule, Winterthur (Switzerland); Vigfusson, J. [Hauptabteilung fuer die Sicherheit der Kernanlagen (HSK), Brugg (Switzerland)

2009-11-15

This report for the Swiss Federal Department of the Environment, Transport, Energy and Communication (DETEC) takes a look at work done within the framework of the research programme on radioactive wastes. The paper discusses the development of various projects and the associated organisations involved. Both long-term and short-term topics are examined. The long-term aspects of handling radioactive wastes include organisation and financing as well as the preservation of know-how and concepts for marking the repositories. Communication with the general public on the matter is looked at along with public perception, opinion-making and acceptance. Waste storage concepts are looked at in detail and aspects such as environmental protection, monitoring concepts, retrievability and encasement materials are discussed. Finally, ethical and legal aspects of radioactive waste repositories are examined. The paper is completed with appendixes dealing with planning, co-ordination and the responsibilities involved

Office of River Protection Advanced Low-Activity Waste Glass Research and Development Plan

International Nuclear Information System (INIS)

Kruger, A. A.; Peeler, D. K.; Kim, D. S.; Vienna, J. D.; Piepel, G. F.; Schweiger, M. J.

2015-01-01

The U.S. Department of Energy Office of River Protection (ORP) has initiated and leads an integrated Advanced Waste Glass (AWG) program to increase the loading of Hanford tank wastes in glass while meeting melter lifetime expectancies and process, regulatory, and product performance requirements. The integrated ORP program is focused on providing a technical, science-based foundation for making key decisions regarding the successful operation of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) facilities in the context of an optimized River Protection Project (RPP) flowsheet. The fundamental data stemming from this program will support development of advanced glass formulations, key product performance and process control models, and tactical processing strategies to ensure safe and successful operations for both the low-activity waste (LAW) and high-level waste vitrification facilities. These activities will be conducted with the objective of improving the overall RPP mission by enhancing flexibility and reducing cost and schedule.

Office of River Protection Advanced Low-Activity Waste Glass Research and Development Plan

Energy Technology Data Exchange (ETDEWEB)

Kruger, A. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Peeler, D. K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kim, D. S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Vienna, J. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Piepel, G. F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Schweiger, M. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-11-23

The U.S. Department of Energy Office of River Protection (ORP) has initiated and leads an integrated Advanced Waste Glass (AWG) program to increase the loading of Hanford tank wastes in glass while meeting melter lifetime expectancies and process, regulatory, and product performance requirements. The integrated ORP program is focused on providing a technical, science-based foundation for making key decisions regarding the successful operation of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) facilities in the context of an optimized River Protection Project (RPP) flowsheet. The fundamental data stemming from this program will support development of advanced glass formulations, key product performance and process control models, and tactical processing strategies to ensure safe and successful operations for both the low-activity waste (LAW) and high-level waste vitrification facilities. These activities will be conducted with the objective of improving the overall RPP mission by enhancing flexibility and reducing cost and schedule.

Value Chain Development as Alternative Method For Mapping Waste Management

Directory of Open Access Journals (Sweden)

Muhammad Saiful Hakim

2017-06-01

Full Text Available Solid Waste management begin at the household as waste of consumption and ended as a new form of waste product or recycling. Based on its value chain the subsequent process will have distict differences with manufacturing product. Value chain of manufacturing product will characterize as value added chain along the chain, where every side of the chain will generate positive chain. In the other hand, some parties of waste management value chain will negative value existed. Some parties in this chain will generate negative value solely because they must establish some cost for wipe the waste. Dissimilarities between value chain on product and waste will contribute to discrepancy between parties. Main purpose of this research is to identify value chain from solid waste management using value chain development. Another purpose to accomplished is to resolve discrepancy in value chain.  Research results shown that household is the parties that experiences negative value. To minimize the discrepancies there should be an action towards household

Development and characterization of new high-level waste form containing LiCl KCl eutectic salts for achieving waste minimization from pyroprocessing

International Nuclear Information System (INIS)

Cho, Yong Zun; Kim, In Tae; Park, Hwan Seo; Ahn, Byeung Gil; Eun, Hee Chul; Son, Seock Mo; Ah, Su Na

2011-12-01

The purpose of this project is to develop new high level waste (HLW) forms and fabrication processes to dispose of active metal fission products that are removed from electrorefiner salts in the pyroprocessing based fuel cycle. The current technology for disposing of active metal fission products in pyroprocessing involves non selectively discarding of fission product loaded salt in a glass-bonded sodalite ceramic waste form. Selective removal of fission products from the molten salt would greatly minimize the amount of HLW generated and methods were developed to achieve selective separation of fission products during a previous I NERI research project (I NERI 2006 002 K). This I NERI project proceeds from the previous project with the development of suitable waste forms to immobilize the separated fission products. The Korea Atomic Energy Research Institute (KAERI) has focused primarily on developing these waste forms using surrogate waste materials, while the Idaho National Laboratory (INL) has demonstrated fabrication of these waste forms using radioactive electrorefiner salts in hot cell facilities available at INL. Testing and characterization of these radioactive materials was also performed to determine the physical, chemical, and durability properties of the waste forms

Development of thermal conditioning technology for alpha-contaminated wastes

International Nuclear Information System (INIS)

Kim, Joon Hyung; Kim, H. Y.; Kim, J. G.

2001-04-01

To develop a thermal conditioning technology for alpha-contaminated wastes, which are presumed to generate from pyrochemical processing of spent fuel, research on the three different fields have been performed; incineration, off-gas treatment, and vitrification/cementation technology. Through the assessment on the amount of alpha-contaminated waste and incineration characterises, an oxygen-enriched incineration process, which can greatly reduce the off-gas volume, was developed by our own technology. Trial burn test with paper waste resulted in a reduction of off-gas volume by 3.5. A study on the behavior and adsorption of nuclides/heavy metals at high-temperature was performed to develop an efficient removal technology. Off-gas treatment technologies for radioiodine at high-temperature and 14 CO 2 , acidic gases, and radioactive gaseous wastes such as Xe/Kr at room temperature were established. As a part of development of high-level waste solidification technology, manufacture of high-frequency induction melter, fabrication and characterization of base-glass media fabricated with spent HEPA filter medium, and development of titanate ceramic material as a precursor of SYNROC by a self-combustion method were performed. To develop alpha-contaminated waste solidification technology, a process to convert periodontal in the cement matrix to calcite with SuperCritical Carbon Dioxide (SCCD) was manufactured. The SCCD treatment enhanced the physicochemical properties of cement matrices, which increase the long-term integrity of cement waste forms during transportation and storage

Research, development and optimization of real time radioscopic characterization of remote handled waste and intermediate level waste, using X-ray imaging at MeV energies

International Nuclear Information System (INIS)

Halliwell, Stephen

2007-01-01

Available in abstract form only. Full text of publication follows: Real time radioscopy (RTR) using X-ray energies of up to 450 keV, is used extensively in the characterization of nuclear waste. The majority of LLW and some ILW in drums and boxes can be penetrated, for successful imaging, by X-rays with energies of up to 450 keV. However, the shielding of many waste packages, and the range of higher density waste matrices, require X-rays at MeV energies, for X-ray imaging to achieve the performance criteria. A broad imaging performance is required to enable the identification of a range of prohibited items, including the ability to see a moving liquid meniscus which indicates the presence of free liquid, in a high density or a waste matrix with substantial containment shielding. Enhanced, high energy X-ray imaging technology to meet the future characterization demands of the nuclear industry required the design and build of a high energy facility, and the implementation of a program of research and development. The initial phase of development has confirmed that digital images meeting the required performance criteria can be made using high energy X-rays. The evaluation of real time imaging and the optimization of imaging with high energy X-rays is currently in progress. (author)

Annual report on the development and characterization of solidified forms for nuclear wastes, 1979

International Nuclear Information System (INIS)

Chick, L.A.; McVay, G.L.; Mellinger, G.B.; Roberts, F.P.

1980-12-01

Development and characterization of solidified nuclear waste forms is a major continuing effort at Pacific Northwest Laboratory. Contributions from seven programs directed at understanding chemical composition, process conditions, and long-term behaviors of various nuclear waste forms are included in this report. The major findings of the report are included in extended figure captions that can be read as brief technical summaries of the research, with additional information included in a traditional narrative format. Waste form development proceeded on crystalline and glass materials for high-level and transuranic (TRU) wastes. Leaching studies emphasized new areas of research aimed at more basic understanding of waste form/aqueous solution interactions. Phase behavior and thermal effects research included studies on crystal phases in defense and TRU waste glasses and on liquid-liquid phase separation in borosilicate waste glasses. Radiation damage effects in crystals and glasses from alpha decay and from transmutation are reported

Cooperative Research Program in Coal-Waste Liquefaction

Energy Technology Data Exchange (ETDEWEB)

Gerald Huffman

2000-03-31

The results of a feasibility study for a demonstration plant for the liquefaction of waste plastic and tires and the coprocessing of these waste polymers with coal are presented. The study was conducted by a committee that included nine representatives from the CFFS, six from the U.S. Department of Energy - Federal Energy Technology Center (FETC), and four from Burns and Roe, Inc. The study included: (1) An assessment of current recycling practices, particularly feedstock recycling in Germany; (2) A review of pertinent research, and a survey of feedstock availability for various types of waste polymers; and (3) A conceptual design for a demonstration plant was developed and an economic analysis for various feedstock mixes. The base case for feedstock scenarios was chosen to be 200 tons per day of waste plastic and 100 tons per day of waste tires. For this base case with oil priced at $20 per barrel, the return on investment (ROI) was found to range from 9% to 20%, using tipping fees for waste plastic and tires typical of those existing in the U.S. The most profitable feedstock appeared to waste plastic alone, with a plant processing 300 t/d of plastic yielding ROI's from 13 to 27 %, depending on the tipping fees for waste plastic. Feedstock recycling of tires was highly dependent on the price that could be obtained for recovered carbon. Addition of even relatively small amounts (20 t/d) of coal to waste plastic and/or coal feeds lowered the ROI's substantially. It should also be noted that increasing the size of the plant significantly improved all ROI's. For example, increasing plant size from 300 t/d to1200 t/d approximately doubles the estimated ROI's for a waste plastic feedstock.

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2010-09-01

The RD and D programme 2010 gives an account of SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas - the programme for Low and Intermediate Level Waste (the Loma program) and the Nuclear Fuel Program. The RD and D Programme 2010 consists of five parts: Part I: Overall Plan, Part II: Loma program, Part III: Nuclear Fuel Program, Part IV: Research on analysis of long-term safety, Part V: Social Science Research. The 2007 RD and D programme was focused primarily on technology development to realize the final repository for spent nuclear fuel. The actions described were aimed at increasing awareness of long-term safety and to obtain technical data for application under the Nuclear Activities Act for the final repository for spent fuel and under the Environmental Code of the repository system. Many important results from these efforts are reported in this program. An overall account of the results will be given in the Licensing application in early 2011. The authorities' review of RD and D programme in 2007 and completion of the program called for clarification of plans and programs for the final repository for short-lived radioactive waste, SFR, and the final repository for waste, SFL. This RD and D program describes these plans in a more detailed way

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2010-09-01

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2010-09-15

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2010-09-15

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

Waste management research abstracts vols. 23/24. Information on radioactive waste management research in progress or planned

International Nuclear Information System (INIS)

1999-01-01

The research abstracts contained in this issue have been collected during recent months and cover the period between March 1994 - June 1998. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. This issue contains 678 abstracts that present ongoing work in 33 countries and an international organization

Waste management research abstracts vols. 23/24. Information on radioactive waste management research in progress or planned

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The research abstracts contained in this issue have been collected during recent months and cover the period between March 1994 - June 1998. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. This issue contains 678 abstracts that present ongoing work in 33 countries and an international organization.

Development and pilot demonstration program of a waste minimization plan at Argonne National Laboratory

International Nuclear Information System (INIS)

Peters, R.W.; Wentz, C.A.; Thuot, J.R.

1991-01-01

In response to US Department of Energy directives, Argonne National Laboratory (ANL) has developed a waste minimization plan aimed at reducing the amount of wastes at this national research and development laboratory. Activities at ANL are primarily research- oriented and as such affect the amount and type of source reduction that can be achieved at this facility. The objective of ANL's waste minimization program is to cost-effectively reduce all types of wastes, including hazardous, mixed, radioactive, and nonhazardous wastes. The ANL Waste Minimization Plan uses a waste minimization audit as a systematic procedure to determine opportunities to reduce or eliminate waste. To facilitate these audits, a computerized bar-coding procedure is being implemented at ANL to track hazardous wastes from where they are generated to their ultimate disposal. This paper describes the development of the ANL Waste Minimization Plan and a pilot demonstration of the how the ANL Plan audited the hazardous waste generated within a selected divisions of ANL. It includes quantitative data on the generation and disposal of hazardous waste at ANL and describes potential ways to minimize hazardous wastes. 2 refs., 5 figs., 8 tabs

Cementitious materials for radioactive waste management within IAEA coordinated research project - 59021

International Nuclear Information System (INIS)

Drace, Zoran; Ojovan, Michael I.

2012-01-01

materials and technologies; c) testing and waste acceptance criteria; and d) modelling long term behaviour. These themes as well as all contributions of participating organizations were further developed in the individual reports to be presented in the IAEA publication. The CRP facilitated the exchange of information and research co-operation in resolving similar problems between different institutions and contributed towards improving waste management practices, their efficiency and general enhancement of safety. (authors)

New developments and improvements in processing of 'problematic' radioactive waste. Results of a coordinated research project 2003-2007

International Nuclear Information System (INIS)

2007-12-01

This report addresses a category of wastes termed 'problematic wastes', wastes for which safe, efficient and cost effective methods for processing are not readily available. Processing options for many of these are identified and addressed. Results presented, illustrate the strategy for breaking 'problematic' waste streams down into a sequence of 'standard' issues which are amenable to solution. Decision makers and facility managers faced with problematic waste streams should be able to use this information to identify and pursue solutions to meet their needs. In this report, processing options for a total of 27 problematic waste streams that were identified and addressed by the individual laboratories participating in the Coordinated Research Project are discussed. These waste streams covered an extremely broad spectrum, ranging from simple, one component aqueous solutions originating from a research laboratory to very complex aqueous concentrates of waste resulting from reprocessing activities or reactor operation. These challenging wastes included: waste contaminated by tritium, wastes containing transuranic elements, and solid health care waste. The range of aqueous wastes included those contaminated by organic complexing agents and surfactants to pure organic waste such as contaminated oil. Correspondingly, the scale of approaches and technologies used to address these wastes is very broad. Use of this report is likely to be most effective as an initial screening tool to identify technologies best able to meet specific waste management objectives in terms of the waste generated, the technical complexity, the available economic resources, the environmental impact considerations, and the desired end product (output) of the technology. The report should assist the user to compare technologies and to reach an informed decision based on safety, technological maturity, economics, and other local needs

Sustainable recycling of municipal solid waste in developing countries

International Nuclear Information System (INIS)

Troschinetz, Alexis M.; Mihelcic, James R.

2009-01-01

This research focuses on recycling in developing countries as one form of sustainable municipal solid waste management (MSWM). Twenty-three case studies provided municipal solid waste (MSW) generation and recovery rates and composition for compilation and assessment. The average MSW generation rate was 0.77 kg/person/day, with recovery rates from 5-40%. The waste streams of 19 of these case studies consisted of 0-70% recyclables and 17-80% organics. Qualitative analysis of all 23 case studies identified barriers or incentives to recycling, which resulted in the development of factors influencing recycling of MSW in developing countries. The factors are government policy, government finances, waste characterization, waste collection and segregation, household education, household economics, MSWM (municipal solid waste management) administration, MSWM personnel education, MSWM plan, local recycled-material market, technological and human resources, and land availability. Necessary and beneficial relationships drawn among these factors revealed the collaborative nature of sustainable MSWM. The functionality of the factor relationships greatly influenced the success of sustainable MSWM. A correlation existed between stakeholder involvement and the three dimensions of sustainability: environment, society, and economy. The only factors driven by all three dimensions (waste collection and segregation, MSWM plan, and local recycled-material market) were those requiring the greatest collaboration with other factors

Research and development on low level liquid waste treatment in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sinakhom, F.; Punnachaiya, M.; Chantaraprachoom, N.; Srisorn, S.

1996-01-01

The studies have been directed towards several subjects concerning the treatment technologies of low level waste. The simple physico-chemical method has been studied for applying to many kind of waste streams such as reactor waste, isotope production waste and liquid waste from the hospital. The characterization of inorganic ion-exchangers including the effect of pH, equilibrium time, temperature and concentration of such ion-exchangers were tested and the optimum condition of the sorption of C x on the exchangers are reported. The results from the investigation on the efficiencies of detergents in the radioactive decontamination reveal that the local simple brand machine-washed detergents. which is very cheap, can be best used as the decontaminating agent instead of the more expensive imported one. It is found that chemical precipitation methods i.e. phosphate coagulation, copper ferrocyanide coagulation and cobalt precipitation method can be used for treating of the waste stream arising successfully. In considering of the immobilizing process of treated waste, cementation is advised to be used and, therefore, subjects to be evaluated. The basic properties of cement-waste products as well the leachability of a particular types of sludge waste at 15-40% waste loading were investigated. The result reveals that, cement waste forms of inorganic ion-exchanger and of sludge waste from chemical precipitation of decontamination waste, exhibit high compressive strength and a low leach rates. The compressive strength of 118-207 Kg/cm 2 were found for the optimum waste products originated from various exchangers and 15-20% loading of sludge waste. The leachability of Co-60, Cs-134 and Sr-85 from 15-40% loading of cement waste for 30 days were studied. The cumulative fraction leached rate of Cs-134 from sludge-cement wastes was found to be about 17 x 10 - 3 g/cm 2 for 25 degree C and 50 degree C at 30 days leaching time respectively, while there were no leaching of Sr-85 and

Development of the Plastic Melt Waste Compactor- Design and Fabrication of the Half-Scale Prototype

Science.gov (United States)

Pace, Gregory S.; Fisher, John

2005-01-01

A half scale version of a device called the Plastic Melt Waste Compactor prototype has been developed at NASA Ames Research Center to deal with plastic based wastes that are expected to be encountered in future human space exploration scenarios such as Lunar or Martian Missions. The Plastic Melt Waste Compactor design was based on the types of wastes produced on the International Space Station, Space Shuttle, MIR and Skylab missions. The half scale prototype unit will lead to the development of a full scale Plastic Melt Waste Compactor prototype that is representative of flight hardware that would be used on near and far term space missions. This report details the progress of the Plastic Melt Waste Compactor Development effort by the Solid Waste Management group at NASA Ames Research Center.

Research and development on treatment of liquid radioactive wastes in Thailand

Energy Technology Data Exchange (ETDEWEB)

Yamkate, P; Sinakhom, F; Punnachaiya, M; Ya-anan, N; Srisorn, S [Office of Atomic Energy for Peace, Bangkok (Thailand). Waste Management Div.

1997-02-01

The studies have been directed towards treatment technologies for low level waste. The simple physico-chemical method has been studied for applying to various kinds of waste streams such as reactor waste, isotope production waste and liquid waste from the hospitals. The characterization of inorganic ion exchangers including the effect of pH, equilibrium time, temperature and concentration of such exchangers were tested. The results revealed that the local simple brand-washed detergents, which are very cheap, can be successfully used for decontamination instead of a more expensive imported decontaminating agent. It was also revealed that chemical precipitation can be successfully used for the treatment of such wastes. In considering an immobilization process for the treated waste, cementation was selected. The basic properties of the cemented waste forms have been investigated including leachability of the cemented sludge resulted from the chemical precipitation of the decontamination waste. The results revealed that the cemented inorganic ion exchangers and the sludge waste exhibit high compressive strength and low leach rates. The compressive strength of 118-207 kg/cm{sup 2} and 15% and 20% waste loading was found to be optimum for the waste forms. A cumulative fraction leached rate from the cemented sludge was found to be about 30 x 10{sup -3} cm/day at 30 day leaching time. (author). 5 refs, 7 tabs.

Research and development on treatment of liquid radioactive wastes in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sinakhom, F.; Punnachaiya, M.; Ya-anan, N.; Srisorn, S.

1997-01-01

The studies have been directed towards treatment technologies for low level waste. The simple physico-chemical method has been studied for applying to various kinds of waste streams such as reactor waste, isotope production waste and liquid waste from the hospitals. The characterization of inorganic ion exchangers including the effect of pH, equilibrium time, temperature and concentration of such exchangers were tested. The results revealed that the local simple brand-washed detergents, which are very cheap, can be successfully used for decontamination instead of a more expensive imported decontaminating agent. It was also revealed that chemical precipitation can be successfully used for the treatment of such wastes. In considering an immobilization process for the treated waste, cementation was selected. The basic properties of the cemented waste forms have been investigated including leachability of the cemented sludge resulted from the chemical precipitation of the decontamination waste. The results revealed that the cemented inorganic ion exchangers and the sludge waste exhibit high compressive strength and low leach rates. The compressive strength of 118-207 kg/cm 2 and 15% and 20% waste loading was found to be optimum for the waste forms. A cumulative fraction leached rate from the cemented sludge was found to be about 30 x 10 -3 cm/day at 30 day leaching time. (author). 5 refs, 7 tabs

International Nuclear Energy Research Initiative Development of Computational Models for Pyrochemical Electrorefiners of Nuclear Waste Transmutation Systems

International Nuclear Information System (INIS)

Simpson, M.F.; Kim, K.-R.

2010-01-01

In support of closing the nuclear fuel cycle using non-aqueous separations technology, this project aims to develop computational models of electrorefiners based on fundamental chemical and physical processes. Spent driver fuel from Experimental Breeder Reactor-II (EBR-II) is currently being electrorefined in the Fuel Conditioning Facility (FCF) at Idaho National Laboratory (INL). And Korea Atomic Energy Research Institute (KAERI) is developing electrorefining technology for future application to spent fuel treatment and management in the Republic of Korea (ROK). Electrorefining is a critical component of pyroprocessing, a non-aqueous chemical process which separates spent fuel into four streams: (1) uranium metal, (2) U/TRU metal, (3) metallic high-level waste containing cladding hulls and noble metal fission products, and (4) ceramic high-level waste containing sodium and active metal fission products. Having rigorous yet flexible electrorefiner models will facilitate process optimization and assist in trouble-shooting as necessary. To attain such models, INL/UI has focused on approaches to develop a computationally-light and portable two-dimensional (2D) model, while KAERI/SNU has investigated approaches to develop a computationally intensive three-dimensional (3D) model for detailed and fine-tuned simulation.

Healthcare waste management research: A structured analysis and review (2005-2014).

Science.gov (United States)

Thakur, Vikas; Ramesh, A

2015-10-01

The importance of healthcare waste management in preserving the environment and protecting the public cannot be denied. Past research has dealt with various issues in healthcare waste management and disposal, which spreads over various journals, pipeline research disciplines and research communities. Hence, this article analyses this scattered knowledge in a systematic manner, considering the period between January 2005 and July 2014. The purpose of this study is to: (i) identify the trends in healthcare waste management literature regarding journals published; (ii) main topics of research in healthcare waste management; (iii) methodologies used in healthcare waste management research; (iv) areas most frequently researched by researchers; and (v) determine the scope of future research in healthcare waste management. To this end, the authors conducted a systematic review of 176 articles on healthcare waste management taken from the following eight esteemed journals: International Journal of Environmental Health Research, International Journal of Healthcare Quality Assurance, Journal of Environmental Management, Journal of Hazardous Material, Journal of Material Cycles and Waste Management, Resources, Conservations and Recycling, Waste Management, and Waste Management & Research. The authors have applied both quantitative and qualitative approaches for analysis, and results will be useful in the following ways: (i) results will show importance of healthcare waste management in healthcare operations; (ii) findings will give a comparative view of the various publications; (c) study will shed light on future research areas. © The Author(s) 2015.

E-WASTE: ETHICAL IMPLICATIONS FOR EDUCATION AND RESEARCH

Directory of Open Access Journals (Sweden)

MUAZ HAWARI

2010-09-01

Full Text Available “E-waste” is a popular, informal name for electronic products nearing the end of their “useful life”. This includes discarded computers, televisions, VCRs, stereos, copiers, fax machines, electric lamps, cell phones, audio equipment and batteries. E-wastes are considered dangerous, as certain components of some of these electronic products contain materials; such as lead; that are hazardous, depending on their condition and density. If improperly disposed, E-wastes can leach lead and other substances into soil and groundwater posing a threat to human health and environment. Many of these electronic products can be reused, refurbished, or recycled in an environmentally sound manner so that they are less harmful to the ecosystem. This paper highlights the types and hazards of E-wastes particularly the computers’ waste. The dimensions and ethicality of the problem in the third-world countries are reviewed. The needs for the appropriate management of e-waste and options that can be implemented are discussed. After reviewing the Islamic concepts for environmental protection, ethical implications for curriculum development as well research directions are highlighted. Elements for a course on e-waste as well as some across-the-curriculum topics are proposed. This is specially tailored to suit the faculty of Engineering at the International Islamic University-Malaysia.

Coupled processes in NRC high-level waste research

International Nuclear Information System (INIS)

Costanzi, F.A.

1987-01-01

The author discusses NRC research effort in support of evaluating license applications for disposal of nuclear waste and for promulgating regulations and issuing guidance documents on nuclear waste management. In order to do this they fund research activities at a number of laboratories, academic institutions, and commercial organizations. One of our research efforts is the coupled processes study. This paper discusses interest in coupled processes and describes the target areas of research efforts over the next few years. The specific research activities relate to the performance objectives of NRC's high-level waste (HLW) regulation and the U.S. Environmental Protection Agency (EPA) HLW standard. The general objective of the research program is to ensure the NRC has a sufficient independent technical base to make sound regulatory decisions

Initial robotics research for environmental restoration and waste management

International Nuclear Information System (INIS)

Hamel, W.R.; Mann, R.C.

1990-01-01

This paper describes the initial research and development activities at the Oak Ridge National Laboratory (ORNL) that will support the technology development component of the overall National Robotics Technology Development Program (NRTDP). The NRTDP is a subelement of the US Department of Energy's (DOE's) Environmental Restoration and Waste Management (ER and WM) 5-Year Applied Research, Development, Demonstration, Testing, and Evaluation Plan and of overall efforts at DOE operational sites around the country. ORNL research will focus on fundamental improvement of remote manipulation through enhancements of the human man/machine interface, integration of automated functions, and the incorporation of machine intelligence to increase productivity. Background and goals for these activities are presented in this paper

Planning the research and development necessary for accelerator transmutation of waste, leading to integrated proof of performance testing

International Nuclear Information System (INIS)

Bennett, D.R.; Pasamehmetoglu, K.; Finck, P.; Pitcher, E.; Khalil, H.; Todosow, M.; Hill, R.; Van Tuyle, G.; Laidler, J.; Crawford, D.; Thomas, K.

2001-01-01

The Research and Development (R and D) Plan for the Accelerator Transmutation of Waste (ATW) Program has been developed for the Department of Energy, Office of Nuclear Energy (DOE/NE) to serve as a focus and progressional guide in developing critical transmutation technologies. It is intended that the Plan will serve as a logical reference considering all elements of an integrated accelerator-driven transmutation system, and will maximize the use of resources by identifying and prioritizing research, design, development and trade activities. The R and D Plan provides a structured framework for identifying and prioritizing activities leading to technically-justifiable integrated Proof of Performance testing within ten years and ultimate demonstration of Accelerator Transmutation of Waste (ATW). The Plan builds from the decision objectives specified for ATW, utilizes informational input from the ATW Roadmap and programmatic System Point Design efforts, and employs the knowledge and expertise provided by professionals familiar with ATW technologies. With the firm intent of understanding what, why and when information is needed, including critical interfaces, the Plan then develops a progressional strategy for developing ATW technologies with the use of a Technology Readiness Level (TRL) scale. The TRL approach is first used to develop a comprehensive, yet generic, listing of experimental, analytical and trade study activities critical to developing ATW technologies. Technology-specific and concept-specific aspects are then laid over the generic mapping to gage readiness levels. Prioritization criteria for reducing technical uncertainty, providing information to decision points, and levering off of international collaborations are then applied to focus analytical, experimental and trade activities. (author)

Management of radioactive wastes in developing countries: Growing needs

International Nuclear Information System (INIS)

Thomas, K.T.

1992-01-01

Wide variations in the development and use of nuclear energy are evident in developing countries. A few have or are pursuing partial or complete nuclear fuel cycle activities. Eleven developing countries have nuclear power plants with a total installed capacity of 8600 megawatts-electric (MWe). Because of the increasing demand for electrical energy, more developing countries would like to have nuclear power. But most of them are constrained by lack of finances and technical expertise. Some have research reactors, and a few have uranium mining and milling operations. Most developing countries are using nuclear energy for applications in fields of medicine, agriculture, industry, and research. From all these uses, radioactive waste is produced that must be managed safely and efficiently. Increasingly in recent years, countries have turned to the IAEA for technical assistance and waste management services to address serious problems they are facing. 1 map

Research and development on the melting test of low-level radioactive miscellaneous solid waste

International Nuclear Information System (INIS)

Nakashio, Nobuyuki; Hoshi, Akiko; Kameo, Yutaka; Nakashima, Mikio

2007-02-01

The Nuclear Science Research Institute of the Japan Atomic Energy Agency constructed the Advanced Volume Reduction Facilities (AVRF) in February 2003 for treatment of low-level radioactive miscellaneous solid waste (LLW). The waste volume reduction is carried out by a high-compaction process or melting processes in the AVRF. In advance of operating the melting process in the AVRF, melting tests of simulated LLW with RI tracers ( 60 Co, 137 Cs and 152 Eu) have been conducted by using the plasma melter in pilot scale. Viscosity of molten waste, chemical composition and physical properties of solidified products and distribution of the tracers in each product were investigated in various melting conditions. It was confirmed that the viscosity of molten waste was able to be controlled by adjusting chemical composition of molten waste. The RI tracer were almost uniformly distributed in the solidified products. The retention of 137 Cs depended on the basicity (CaO/SiO 2 ) of the solidified products. The solidified product possessed satisfactory compressive strength. In the case of basicity less than 0.8, the leachability of RI tracers from the solidified products was less than or equal to that of a high-level vitrified waste. In this review, experimental results of the melting tests were discussed in order to contribute to actual treatment of LLW in the AVRF. (author)

Research and development on ultimate storage of radioactive wastes. Annual report, 1977

International Nuclear Information System (INIS)

The present deals with the activities of the Entwicklungsgemeinschaft Tieflagerung which was founded on 1 January 1978 and consists of institutes, branches and working groups both of the Gesellschaft fuer Strahlen- und Umweltforschung mbH Muenchen and the Kernforschungszentrum Karlsruhe which are engaged in the field of radioactive waste disposal. This report presents a survey of the work performed in that field in 1977. The mining and construction work is discussed, which was carried out both underground and above at the Asse Salt Mine near Remlingen and which was done for repair, maintenance, and expansion of operation in accordance with its future purpose. The experimental disposal of low-level wastes on the 750-m and 725-m level was continued in the time period under review. Only seven drums of intermediate-level waste were experimentally disposed of in 1977. The disposal field and the operational equipment for the single test disposal of spent fuel elements from the AVR reactor were completed and are ready for operation. Due to legal, political, and transport problems there is a delay of the start of the test disposal. The mining of the prototype cavity was finished reaching a fina depth of 996.1 m. Moreover, the report gives information on means for radiation protection and the results of the environmental surveillance program. Also the present status of the research activities and their results, especially in the field of disposal of high-level waste, rock mechanics, and safety studies is reported

Development of a teleoperated backhoe for buried waste excavation

International Nuclear Information System (INIS)

Burks, B.L.; Killough, S.M.; Thompson, D.H.

1992-01-01

For nearly five decades the United States (US) Department of Energy (DOE) and its predecessor agencies have engaged in broad-based research and development activities as well as nuclear weapons component production. As a by-product of these activities, large quantities of waste materials have been granted. One of the most common approaches used for solid waste storage was to bury waste containers in pits and trenches. With the current emphasis on environmental restoration, DOE now plans to either retrieve much of the legacy of buried waste or stabilize the waste in place via in situ vitrification or other means. Because of the variety of materials that have been buried over the years, the hazards of retrieval are significant if performed using conventional manned operations. The potential hazards, in addition to radiation exposure, include pyrophorics, toxic chemicals, and explosives. Although manifests exist for much of the buried waste, these records are often incomplete compared to today's requirements. Because of the potential hazards and uncertainty about waste contents and container integrity, it is highly desirable to excavate these wastes using remotely operated equipment. In this paper the authors describe the development of a teleoperated military tractor called the Small Emplacement Excavator (SEE). Development of the SEE is being funded jointly by both DOE and the US Army. The DOE sponsor is the Office of Technology Development (OTD) Robotics Program. The US Army sponsor is the Program Manager for Ammunition Logistics, Picatinny Arsenal. The primary interest for DOE is in the application to remote excavation of buried waste, while the primary emphasis for the US Army is in the remote retrieval of unexploded ordnance. Technical requirements for these two tasks are very similar and, therefore, justify a joint development project. 1 ref

Developing models for the prediction of hospital healthcare waste generation rate.

Science.gov (United States)

Tesfahun, Esubalew; Kumie, Abera; Beyene, Abebe

2016-01-01

An increase in the number of health institutions, along with frequent use of disposable medical products, has contributed to the increase of healthcare waste generation rate. For proper handling of healthcare waste, it is crucial to predict the amount of waste generation beforehand. Predictive models can help to optimise healthcare waste management systems, set guidelines and evaluate the prevailing strategies for healthcare waste handling and disposal. However, there is no mathematical model developed for Ethiopian hospitals to predict healthcare waste generation rate. Therefore, the objective of this research was to develop models for the prediction of a healthcare waste generation rate. A longitudinal study design was used to generate long-term data on solid healthcare waste composition, generation rate and develop predictive models. The results revealed that the healthcare waste generation rate has a strong linear correlation with the number of inpatients (R(2) = 0.965), and a weak one with the number of outpatients (R(2) = 0.424). Statistical analysis was carried out to develop models for the prediction of the quantity of waste generated at each hospital (public, teaching and private). In these models, the number of inpatients and outpatients were revealed to be significant factors on the quantity of waste generated. The influence of the number of inpatients and outpatients treated varies at different hospitals. Therefore, different models were developed based on the types of hospitals. © The Author(s) 2015.

FY-95 technology catalog. Technology development for buried waste remediation

International Nuclear Information System (INIS)

1995-01-01

The US Department of Energy's (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described

FY-95 technology catalog. Technology development for buried waste remediation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

The US Department of Energy`s (DOE) Buried Waste Integrated Demonstration (BWID) program, which is now part of the Landfill Stabilization Focus Area (LSFA), supports applied research, development, demonstration, and evaluation of a multitude of advanced technologies dealing with underground radioactive and hazardous waste remediation. These innovative technologies are being developed as part of integrated comprehensive remediation systems for the effective and efficient remediation of buried waste sites throughout the DOE complex. These efforts are identified and coordinated in support of Environmental Restoration (EM-40) and Waste Management (EM-30) needs and objectives. Sponsored by the DOE Office of Technology Development (EM-50), BWID and LSFA work with universities and private industry to develop technologies that are being transferred to the private sector for use nationally and internationally. This report contains the details of the purpose, logic, and methodology used to develop and demonstrate DOE buried waste remediation technologies. It also provides a catalog of technologies and capabilities with development status for potential users. Past FY-92 through FY-94 technology testing, field trials, and demonstrations are summarized. Continuing and new FY-95 technology demonstrations also are described.

Waste from decommissioning of research reactors and other small nuclear facilities

International Nuclear Information System (INIS)

Massaut, V.

2001-01-01

Full text: Small nuclear facilities were often built for research or pilot purposes. It includes the research reactors of various types and various aims (physics research, nuclear research, nuclear weapons development, materials testing reactor, isotope production, pilot plant, etc.) as well as laboratories, hot cells and accelerators used for a broad spectrum of research or production purposes. These installations are characterized not only by their size (reduced footprint) but also, and even mostly, by the very diversified type of materials, products and isotopes handled within these facilities. This large variety can sometimes enhance the difficulties encountered for the dismantling of such facilities. The presence of materials like beryllium, graphite, lead, PCBs, sodium, sometimes in relatively large quantities, are also challenges to be faced by the dismantlers of such facilities, because these types of waste are either toxic or no solutions are readily available for their conditioning or long term disposal. The paper will review what is currently done in different small nuclear facilities, and what are the remaining problems and challenges for future dismantling and waste management. The question of whether Research and Development for waste handling methods and processes is needed is still pending. Even for the dismantling operation itself, important improvements can be brought in the fields of characterization, decontamination, remote handling, etc. by further developments and innovative systems. The way of funding such facilities decommissioning will be reviewed as well as the very difficult cost estimation for such facilities, often one-of-a-kind. The aspects of radioprotection optimization (ALARA principle) and classical operators safety will also be highlighted, as well as the potential solutions or improvements. In fact, small nuclear facilities encounter often, when dismantling, the same problems as the large nuclear power plants, but have in

Radiant research prospects? A review of nuclear waste issues in social science research

International Nuclear Information System (INIS)

Bergquist, Ann-Kristin

2007-05-01

The present report has been put together on behalf of KASAM and constitutes a review of social science research and literature that been produced on the nuclear waste issue in Sweden, with focus on recent research. The aim with the investigation has been to map the scope of and the direction of the independent research about nuclear waste in Sweden, in relation to the research that has been initiated and financed by the stakeholders that are participating in the decision-making process in the nuclear waste issue. Another aim has been to point out areas that have not been taken into consideration

Annual report 1992 on research and development work by the IMF, Institute for Materials Research

International Nuclear Information System (INIS)

1993-03-01

The present annual report describes the activities undertaken by the IMF in the following areas: 1. Low-pollutant and low-waste techniques (treatment and utilization of special wastes); 2. Nuclear fusion (studies for NET/ITER; structural materials for fusion devices; superconducting magnets; plasmas heating technique; blanket development; component-related safety investigations); 3. Nuclear safety research (safety and materials of fast breeders; transient behaviour of fast breeder fuel elements; LWR-oriented safety research; containment concepts for PWR-plants); 4. Nuclear waste management (materials studies of waste forms); 5. Superconductivity (superconductor developments); 6. Microsystems engineering (development and testing of compact and laminated materials of microsystems engineering); 7. Handling technique (remote handling components for invasive surgery); 8. Materials and interfaces (inter alia high-performance ceramics, failure behaviour, LCP, biomechanics). The appendix lists all publications or primary reports by the IMF in 1992. (orig./HP) [de

Development of Characterization Protocol for Mixed Liquid Radioactive Waste Classification

International Nuclear Information System (INIS)

Norasalwa Zakaria; Syed Asraf Wafa; Wo, Y.M.; Sarimah Mahat; Mohamad Annuar Assadat Husain

2017-01-01

Mixed organic liquid waste generated from health-care and research activities containing tritium, carbon-14, and other radionuclide posed specific challenges in its management. Often, this waste becomes legacy waste in many nuclear facilities and being considered as 'problematic' waste. One of the most important recommendations made by IAEA is to perform multistage processes aiming at declassification of the waste. At this moment, approximately 3000 bottles of mixed liquid waste, with estimated volume of 6000 litres are currently stored at the National Radioactive Waste Management Centre, Malaysia and some have been stored for more than 25 years. The aim of this study is to develop a characterization protocol towards reclassification of these wastes. The characterization protocol entails waste identification, waste screening and segregation, and analytical radionuclides profiling using analytical procedures involving gross alpha beta, and gamma spectrometry. The results obtained from the characterization protocol are used to establish criteria for speedy classification of the waste. (author)

Development of characterization protocol for mixed liquid radioactive waste classification

Energy Technology Data Exchange (ETDEWEB)

Zakaria, Norasalwa, E-mail: norasalwa@nuclearmalaysia.gov.my [Waste Technology Development Centre, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Wafa, Syed Asraf [Radioisotop Technology and Innovation, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Wo, Yii Mei [Radiochemistry and Environment, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Mahat, Sarimah [Material Technology Group, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia)

2015-04-29

Mixed liquid organic waste generated from health-care and research activities containing tritium, carbon-14, and other radionuclides posed specific challenges in its management. Often, these wastes become legacy waste in many nuclear facilities and being considered as ‘problematic’ waste. One of the most important recommendations made by IAEA is to perform multistage processes aiming at declassification of the waste. At this moment, approximately 3000 bottles of mixed liquid waste, with estimated volume of 6000 litres are currently stored at the National Radioactive Waste Management Centre, Malaysia and some have been stored for more than 25 years. The aim of this study is to develop a characterization protocol towards reclassification of these wastes. The characterization protocol entails waste identification, waste screening and segregation, and analytical radionuclides profiling using various analytical procedures including gross alpha/ gross beta, gamma spectrometry, and LSC method. The results obtained from the characterization protocol are used to establish criteria for speedy classification of the waste.

Waste management research abstracts. Information on radioactive waste management research in progress or planned. Vol. 30

International Nuclear Information System (INIS)

2005-11-01

This issue contains 90 abstracts that describe research in progress in the field of radioactive waste management. The abstracts present ongoing work in various countries and international organizations. Although the abstracts are indexed by country, some programmes are actually the result of co-operation among several countries. Indeed, a primary reason for providing this compilation of programmes, institutions and scientists engaged in research into radioactive waste management is to increase international co-operation and facilitate communications. Data provided by researchers for publication in WMRA 30 were entered into a research in progress database named IRAIS (International Research Abstracts Information System). The IRAIS database is available via the Internet at the following URL: http://www.iaea.org/programmes/irais/ This database will continue to be updated as new abstracts are submitted by researchers world-wide. The abstracts are listed by country (full name) in alphabetical order. All abstracts are in English. The volume includes six indexes: principal investigator, title, performing organization, descriptors (key words), topic codes and country

Results of research and development works 1981 of the Institute for Nuclear Waste Management Techniques

International Nuclear Information System (INIS)

1982-02-01

The emphasis of the work is on the development and characterization of waste products suitable for final storage, such as actinides and fission products from MAW/LAW, as well as on the development of methods for the treatment and solidification of radioactive wastes, e.g. wet chemical oxidation, vitrification and cementation. Investigations on the HAW-storage in salt are carried out in cooperation with the GSF. (HP) [de

NRI's research on radioactive wastes

International Nuclear Information System (INIS)

Alexa, J.; Dlouhy, Z.; Kepak, F.; Kourim, V.; Napravnik, J.; Razga, J.; Ralkova, J.; Uher, E.; Vojtech, O.

1976-01-01

A survey is given (including 41 references) of work carried out at the Nuclear Research Institute. Discussed are sorption processes (a selective sorbent for 90 Sr based on BaSO 4 , etc.), sorption on inorganic ion exchangers (heteropolyacid salts, ferrocyanides for 137 Cs capture), on organic cation exchangers (separation of lanthanides), electrocoagulation. The process is described of vitrification of highly radioactive wastes, the arrest of emissions, the deposition of radioactive wastes and surface decontamination. (M.K.)

Public sector's research programme on nuclear waste management

International Nuclear Information System (INIS)

Vuori, S.

2000-06-01

According to the Finnish nuclear energy legislation, each producer of nuclear waste is responsible for the safe handling, management and disposal of the waste as well as for the arising costs. Authorities supervise and control the implementation of the national waste management programme and set the necessary safety and other requirements. In these tasks the authorities are supported by a research programme on nuclear waste management that is independent of the implementing organisations and power companies. The main objective of the research programme has been to provide the authorities with information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into the following main topic areas: (1) Behaviour of bedrock (2) Geohydrology and geochemistry, (3) Release of radionuclides from repository and subsequent transport in bedrock, (4) Engineered safety barriers of the repository, system, (5) Performance and safety assessment of spent fuel disposal facilities, (6) Waste management technology and costs (7) Evaluation of the contents and scope of and observation of the realisation of the environmental impact assessment procedure for the siting of spent nuclear fuel disposal facility, and research on other societal and sociopolitical issues, and (8) Public information, attitude, and image issues for waste management facilities. The research programme has generated considerably increased information on the behaviour of the natural and technical release barriers of the disposal system and thereby contributed to building of confidence on the long-term safety of geological disposal of spent fuel. Furthermore, increased confidence among the public in the affected candidate municipalities has probably been achieved by the complementary studies conducted within the research programme on topics

Waste management research abstracts no. 13. Information on research in progress

Energy Technology Data Exchange (ETDEWEB)

NONE

1982-05-01

The 222 research abstracts contained in this issue have been collected during recent months ending 15 January 1982. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. The abstracts have been printed in the language and in the form of submittal and without any changes other than minor editorial ones.

Waste management research abstracts no. 13. Information on research in progress

International Nuclear Information System (INIS)

1982-05-01

The 222 research abstracts contained in this issue have been collected during recent months ending 15 January 1982. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. The abstracts have been printed in the language and in the form of submittal and without any changes other than minor editorial ones

Study on the development of safety regulations for geological disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Wei Fangxin

2012-01-01

The development of regulations under Regulations on Safety Management of Radioactive Waste has become necessary as the issuance of it. The regulations related to geological disposal of high-level radioactive waste can promote the progress of research and development on geological disposal of high-level radioactive waste in China. This paper has present suggestions on development of regulations on geological disposal of high-level radioactive waste by analyzing development of safety regulations on geological disposal of high-level radioactive waste in foreign countries and problems occurred in China and discussed important issues related to the development of safety regulations on geological disposal of high-level radioactive waste. (author)

IV meeting of R and D in research and technological development of radioactive waste management

International Nuclear Information System (INIS)

2001-01-01

These Technical Publications include the main papers presented during the IV R and D Symposium on Radioactive Wastes Management Technology, promoted by ENRESA and held in the Barcelona University during November 2000. The papers correspond both to the Technical Sessions and the Seminars and they are a document of inestimable value that indicates the high technological value reached in the radioactive waste management as a result of a clear and continuous R and D politics together with an intense and productive international collaboration. Throughout the papers of this document the technological status and the capacities developed in all different fields of the radioactive waste management are shown. The main subjects discussed include: low and medium activity wastes management, dismantling of nuclear plants, partitioning and transmutation of long life radionuclide and mainly deep geological disposal. Through the papers corresponding to the scientific sessions the state of the art in the mentioned areas is reviewed with special emphasis, as the achievements and developments reached in Spain. Through the seminars, many outstanding aspects of the R and D in radioactive wastes such as the biosphere role, the numerical modelling and the underground laboratories, can be studied in depth. (Author)

Treatment technologies for low and intermediate level waste from nuclear applications. Final report of a co-ordinated research programme 1991-1996

International Nuclear Information System (INIS)

1997-02-01

Low and intermediate level radioactive waste is generated from the use of radioactive materials in industrial applications, research and medicine. The waste management programmes and activities in many developing Member States have been reviewed through a Waste Management Advisory Programme (WAMAP) implemented by the IAEA in 1987-1995. One of the WAMAP objectives was to assist in practical development and implementation of safe and efficient waste treatment methods. In this context the IAEA has initiated a co-ordinated research programme on treatment technologies for institutional wastes covering the most important recurring problems in developing Member States. The programme was intended to cover the research and development required for reliable waste treatment operations, including the likely variations in institutional waste inputs using simple low cost processes. This co-ordinated research programme was initiated in 1991 and brought together 14 participants from 13 countries. The results of the studies were discussed at three research co-ordination meetings. This report summarizes the salient features and results obtained during five year investigations and provides recommendations for future work in this area. Refs, figs, tabs

Treatment technologies for low and intermediate level waste from nuclear applications. Final report of a co-ordinated research programme 1991-1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-02-01

Low and intermediate level radioactive waste is generated from the use of radioactive materials in industrial applications, research and medicine. The waste management programmes and activities in many developing Member States have been reviewed through a Waste Management Advisory Programme (WAMAP) implemented by the IAEA in 1987-1995. One of the WAMAP objectives was to assist in practical development and implementation of safe and efficient waste treatment methods. In this context the IAEA has initiated a co-ordinated research programme on treatment technologies for institutional wastes covering the most important recurring problems in developing Member States. The programme was intended to cover the research and development required for reliable waste treatment operations, including the likely variations in institutional waste inputs using simple low cost processes. This co-ordinated research programme was initiated in 1991 and brought together 14 participants from 13 countries. The results of the studies were discussed at three research co-ordination meetings. This report summarizes the salient features and results obtained during five year investigations and provides recommendations for future work in this area. Refs, figs, tabs.

The European Communities' research programme on management of low and intermediate level wastes

International Nuclear Information System (INIS)

Simon, R.; Cecille, L.

1989-01-01

In the European Communities' third R and D programme on Management and Disposal of Radioactive Wastes a large number of projects have been commissioned to develop treatment and conditioning processes for low and intermediate level wastes and to qualify the conditioned waste forms. The paper presents the main objectives of this research and summarizes some of the more important studies. In liquid waste treatment, the research includes processes to separate actinides by new extractive methods and application of selective inorganic ion exchangers as well as electrochemically controlled ion exchange processes and a series of purification methods involving membrane techniques. The most important issue of solid waste management in the programme is the treatment and conditioning of plutonium containing wastes, for which a strategic study had been commissioned to optimize the choice between different treatment and conditioning options. Processes being studied include two advanced decontamination techniques and a variety of conditioning methods for incinerator ash and fuel element hulls. Another task of the programme is devoted to the qualification of waste forms. This comprises the characterization of the most common low and intermediate level waste products with respect to leaching, waste form stability, radiation resistance and compatibility with the respective disposal environments. In the course of the programme, the development of methods for quality assurance and in particular quality control has become an important issue: the control of the nuclide inventory, of the chemical composition of the wastes and of the correct operation of treatment and conditioning processes is being investigated in special laboratories. (author). 21 refs, 4 tabs

Research on advanced technology of performance assessment for geological disposal of high-level radioactive waste (Joint research)

International Nuclear Information System (INIS)

2006-12-01

JAEA and RWMC have carried out a joint research program on advanced technologies that could be used to support performance assessments of geological disposal concepts for high-level radioactive waste. The following 5 items were considered in the program: 1) planning of a basic strategy for the development of analysis technologies on nuclide migration over various spatial and temporal scales; 2) development of analysis technologies for vitrified waste scale; 3) development of analysis technologies for repository scale; 4) development of integration technologies for geochemical information; and 5) development of technologies to promote the logical understanding of repository performance and safety. The above items were discussed in the context of technological experiences gained by JAEA and RWMC in previous repository-related studies. According to the results of these discussions, development strategies for each of the technology areas identified above were efficiently formulated by appropriate task allocations. Specific technical subjects requiring further investigation were also identified using this approach, and potential feed-backs from the results of these investigations into the overall research plan and strategy were considered. These specific research and development subjects in the overall strategy defined by this project should be implemented in the future. (author)

Commercial Nuclear Waste Research and Development Program. Annual report, fiscal year 1985

International Nuclear Information System (INIS)

1985-12-01

Nuclear waste handling, packaging, and dry storage testing for the Department of Energy (DOE) Commercial Nuclear Waste Research and Development Program are conducted at the E-MAD (Engine Maintenance, Assembly and Disassembly) facility in Area 25 of the Nevada Test Site. Brief discussions of E-MAD activities are included in this report. Significant accomplishments for this period are as follows: (1) Integrity monitoring of the 17 fuel assemblies located at E-MAD was performed to determine if handling, packaging, or storage had affected the overall integrity of the fuel. (2) The 24-month Dry Storage Fuel Integrity Demonstration Test being conducted at the E-MAD facility was completed. Two fuel rods, removed from the assembly prior to the test, were reinserted into the fuel assembly. (3) The remaining nine fuel assemblies were removed from their seal-welded canisters and characterized to verify their integrity following storage tests. (4) The decay heat rates of five fuel assemblies were measured using the E-MAD boiling water calorimeter. The measured decay heat rates were compared to predicted rates. (5) At DOE/NV request, plans were prepared and submitted to ship the 17 E-MAD fuel assemblies to the Idaho National Engineering Laboratory and then shut down the E-MAD facility. (6) The revised safety assessment document was approved and transmitted to DOE/NV. (7) Quality Assurance personnel assisted in the completion of the DOE/NV Quality Assurance Manual and it was approved and published. (8) Technical support was provided to Lawrence Livermore National Laboratories in the decontamination of electronic equipment

Establishment of cooperation basis of joint research on the mixed waste molten salt oxidation technology

International Nuclear Information System (INIS)

Yang, Hee Chul; Cho, Y. J.; Kim, J. H.; Yoo, J. H.; Yun, H. C.; Lee, D. G.

2005-08-01

Molten salt oxidation, MSO for short, is a robust technology that can effectively treat mixed waste (radioactive waste including hazardous metals or organics). It can safely and economically treat the difficult wastes such as not-easily destroyable toxic organic waste, medical waste, chemical warfare and energetic materials such as propellant and explosives, all of which are not easily treated by an incinerator or other currently existing thermal treatment system. Therefore, molten salt oxidation technology should be developed and utilized to treat a lot of niche waste stored in the nuclear and environmental industries. So, if we put the MSO technology to practical use by Korea-Vietnam joint research, we can reduce R and D fund for MSO technology by ourselves and we can expect an export of the outcome of nuclear R and D in Korea. For Establishment of cooperation basis of joint research concerning molten salt oxidation technology between KOREA and VIETNAM, in this research, We invited two Vietnamese researchers and we introduced our experimental scale molten salt oxidation system in order to let them understand molten salt oxidation technology. We also visited Viet man and we consulted about molten salt oxidation process. We held seminar on the mixed waste molten salt oxidation technology, discussed on the joint research on the mixed waste molten salt oxidation technology and finally we wrote MOU for joint research

Establishment of cooperation basis of joint research on the mixed waste molten salt oxidation technology

Energy Technology Data Exchange (ETDEWEB)

Yang, Hee Chul; Cho, Y. J.; Kim, J. H.; Yoo, J. H.; Yun, H. C.; Lee, D. G

2005-08-01

Molten salt oxidation, MSO for short, is a robust technology that can effectively treat mixed waste (radioactive waste including hazardous metals or organics). It can safely and economically treat the difficult wastes such as not-easily destroyable toxic organic waste, medical waste, chemical warfare and energetic materials such as propellant and explosives, all of which are not easily treated by an incinerator or other currently existing thermal treatment system. Therefore, molten salt oxidation technology should be developed and utilized to treat a lot of niche waste stored in the nuclear and environmental industries. So, if we put the MSO technology to practical use by Korea-Vietnam joint research, we can reduce R and D fund for MSO technology by ourselves and we can expect an export of the outcome of nuclear R and D in Korea. For Establishment of cooperation basis of joint research concerning molten salt oxidation technology between KOREA and VIETNAM, in this research, We invited two Vietnamese researchers and we introduced our experimental scale molten salt oxidation system in order to let them understand molten salt oxidation technology. We also visited Viet man and we consulted about molten salt oxidation process. We held seminar on the mixed waste molten salt oxidation technology, discussed on the joint research on the mixed waste molten salt oxidation technology and finally we wrote MOU for joint research.

Analysis on safeguard approach of radioactive waste at KIJANG research reactor

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyun Jo; Lee, Sung Ho; Lee, Byung Doo; Kim, In Chul; Kim, Hyun Sook; Jung, Juang [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-12-15

KIJANG Research Reactor (KJRR) will be constructed in Busan in order to provide the self-sufficiency of RI demand including Mo-99, to increase the neutron transmutation doping (NTD) capacity and to develop and validate technologies related to the research reactor. Considering the categorization of nuclear facility such as item counting and bulk facility, HANARO which is another research reactors in Korea is item counting facility because physical/chemical forms of nuclear material are not changes. During the dissolving process, radioactive wastes containing nuclear material are occurred at KJRR. In this paper, the features of the KJRR are described and safeguards approach on the radioactive wastes containing nuclear material occurred at KJRR are reviewed. This paper reviews the safeguards approach on radioactive wastes containing nuclear materials occurred during FM production at KJRR. Most uranium dissolved during FM production process are collected in U filter cakes and very tiny amount of uranium will be remained in the ILLW.

40 CFR 270.65 - Research, development, and demonstration permits.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Research, development, and... Special Forms of Permits § 270.65 Research, development, and demonstration permits. (a) The Administrator may issue a research, development, and demonstration permit for any hazardous waste treatment facility...

Development plan. High activity-long living wastes project. Abstract

International Nuclear Information System (INIS)

2007-01-01

This brochure presents the actions that the ANDRA (the French national agency of radioactive wastes) has to implement in the framework of the project of high activity-long living (HALL) radioactive wastes (HAVL project) conformably to the requirements of the program defined in the law from June 28, 2006 (law no 2006-739). This law precises the three, complementary, research paths to explore for the management of this type of wastes: separation and transmutation of long-living radioactive elements, reversible disposal in deep geologic underground, and long duration storage. The ANDRA's action concerns the geologic disposal aspect. The following points are presented: the HALL wastes and their containers, the reversible disposal procedure, the HAVL project: financing of researches, storage concepts, development plan of the project (dynamics, information and dialogue approach, input data, main steps, schedule); the nine programs of the HAVL project (laboratory experiments and demonstration tests, surface survey, scientific program, simulation program, surface engineering studies and technological tests, information and communication program, program of environment and facilities surface observation and monitoring, waste packages management, monitoring and transport program, disposal program); the five transverse technical and scientific activities (safety, reversibility, cost, health and occupational safety, impact study). (J.S.)

Bolivia | IDRC - International Development Research Centre

International Development Research Centre (IDRC) Digital Library (Canada)

... systems, mining policies, natural resource management, labour force development, waste management, and land use reforms. ... Total IDRC Support ... stimulate high-quality, policy-relevant research by Bolivians; test climate change ...

Progress report on safety research of high-level waste management for the period April, 1981 to March, 1982

International Nuclear Information System (INIS)

Tashiro, Shingo

1982-10-01

Main results obtained on Safety Research of High-Level Waste Management in 1981 were edited. The research tjeme are following. (1) Characterization of vitrified waste. (2) Alternative waste form development. (3) Durability tests for HLW storage facility. (4) Safety evaluation of geologic disposal. (5) Preparation for hot test. (author)

Radioactive waste management at the Paul Scherrer Institute, the largest Swiss national research centre

Directory of Open Access Journals (Sweden)

Beer Hans-Frieder

2009-01-01

Full Text Available This paper presents the current radioactive waste management practices at the Paul Scherrer Institute (PSI. The PSI contributes to waste related problems in two aspects, namely to the scientific basis of waste management and disposal, and to the practical treatment and storage of radioactive waste. In addition to the tasks of treating on-site generated waste, PSI manages the wastes from medicine, industry, and research throughout Switzerland on behalf of the government. Therefore the Dismantling and Waste Management Section is a part of the Logistics Department at PSI. Proved and accepted methods have to be developed for the safe conditioning and storage of radioactive waste. Various waste treatment facilities exist at PSI. The conditioning facility is dedicated to sorting, compaction by a 120 t press, solidification with special cement, and embedding in concrete. Specialized facilities were constructed for waste from the decommissioning of research reactors. Activated aluminum and its alloys were melted in crucibles and embedded in concrete in a concrete container. After dismantling the structural material of the reactors, it was embedded in concrete in the same manner. For the conditioning of activated reactor graphite, a dedicated method was developed. Graphite was crushed to replace sand in the grout, for embedding radioactive waste in concrete containers. For accelerator waste, a walk-in hot cell equipped with an electrically driven manipulator is available where the highly activated large components (targets, beam dump can be cut into pieces and embedded in concrete in containers. To guarantee the fulfillment of the demands of the regulators, the Dismantling and Waste Management Section applies an accredited quality management system for the safe collection, conditioning, and storage of radioactive waste.

Alpha waste management at the Valduc Research Center

International Nuclear Information System (INIS)

Jouan, A.; Cartier, R.; Durec, J.P.; Flament, T.

1995-01-01

Operation of the reprocessing facilities at the Valduc Research Center of the French Atomic Energy Commission (CEA) generates waste with a variety of characteristics. The waste compatible with surface storage requirements is transferred to the French Radioactive Waste Management Agency (ANDRA); rest is reprocessed under a program which enables storage in compliance with the requirements of permits issued by safety Authorities. The waste reprocessing program provides for the construction of an incinerator capable of handling nearly all of the combustible waste generated by the Center and vitrification facility for treating liquid waste generated by the plutonium handling plant. (authors)

Technical report from Radioactive Waste Management Funding and Research Center

International Nuclear Information System (INIS)

2007-10-01

As the only one Japanese organization specialized in radioactive waste, RWMC (Radioactive Waste Management Funding and Research Center) has been conducting the two major roles; R and D and the fund administration for radioactive waste management. The focus of its studies includes land disposal of LLW (Low-level radioactive wastes) and it has gradually extended to research on management and disposal techniques for high-level (HLW) and TRU wastes and studies on securing and managing the funds required for disposal of these wastes. The present document is the yearly progress report of 2006 and the main activities and research results are included on spent fuel disposal techniques including radon diffusion and emanation problem, performance studies on underground facilities for radioactive waste disposal and its management, technical assessment for geological environment, remote control techniques, artificial barrier systems proposed and its monitoring systems, and TRU disposals. (S. Ohno)

The development of a high level radioactive waste management strategy

International Nuclear Information System (INIS)

Beale, H.

1979-11-01

The management of high level radioactive waste, from the removal of spent fuel from reactors to final disposal of vitrified waste, involves a complex choice of operational variables which interact one with another. If the various operations are designed and developed in isolation it will almost certainly lead to suboptimal choice. Management of highly active waste should therefore be viewed as a complete system and analysed in such a way that account is taken of the interactions between the various operations. This system must have clearly defined and agreed objectives as well as criteria against which performance can be judged. A thorough analysis of the system will provide a framework within which the necessary research and development can be carried out in a co-ordinated fashion and lead to an optimised strategy for managing highly active wastes. (author)

Smart City Platform Development for an Automated Waste Collection System

Directory of Open Access Journals (Sweden)

Cicerone Laurentiu Popa

2017-11-01

Full Text Available Nowadays, governments and companies are looking for solutions to increase the collection level of various waste types by using new technologies and devices such as smart sensors, Internet of Things (IoT, cloud platforms etc. In order to fulfil this need, this paper presents solutions provided by a research project involving the design, development and implementation of fully automated waste collection systems with an increased usage degree, productivity and storage capacity. The paper will focus on the main results of this research project in turning the automated waste collection system into a smart system so that it can be easily integrated in any smart city infrastructure. For this purpose, the Internet of Things platform for the automated waste collection system provided by the project will allow real time monitoring and communication with central systems. Details about each module are sent to the central systems: various modules’ statuses (working, blocked, needs repairs or maintenance etc.; equipment status; storage systems status (allowing full reports for all waste types; the amount of waste for each module, allowing optimal discharging; route optimization for waste discharging etc. To do that, we describe here an IoT cloud solution integrating device connection, data processing, analytics and management.

Progress report on safety research on radioactive waste management for the period April 1996 to March 1998

International Nuclear Information System (INIS)

Ohnuki, Toshihiko; Muraoka, Susumu; Banba, Tsunetaka

1998-10-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research, JAERI during the fiscal year of 1996 and 1997 (April 1, 1996 - March 31, 1998). The topics are as follows: (1) In the research and development of waste forms and engineered barrier, studies on development of ceramic waste forms, the leaching behaviors from glass waste at reduced condition and sorption behaviors on backfill materials have been carried out. (2) In studies on shallow land disposal, studies on the migration behaviors of radionuclides in the presence of humic acid have been carried out. (3) In the studies on geological disposal, the studies on diffusivity in rock formation, in-situ migration and diffusion experiments, sorption mechanism, fixation mechanism, natural analogue study and geochronology have been carried out. (author)

Marketing aspects of development of medical waste management in health care institutions in Ukraine

Directory of Open Access Journals (Sweden)

Inesa Gurinа

2015-02-01

Full Text Available The concept of marketing approach to medical waste management in health care is suggested.The goal of research was to study the state of marketing activities of health care institutions on medical waste management and development trends of   resolution of outstanding issues.Methods. The methods, which were used in the research, are the methods of mathematical statistics, social studies and scientific knowledge.Results. Environmental marketing institutions of healthcare means perfectly safe for the environment provision of health services. The main directions of environmental marketing concept in health care institutions is the acceptance generally binding legal standards of Use Resources, strict control the formation and licensing of medical waste; economic incentives for workers, aimed at minimizing their interest in the volumes of medical waste; financing of R & D relative to the development of new waste and sound technologies; develop a system of taxes and penalties for polluting the environment and so on.Conclusions. As a result of the implementation of marketing strategies for managing medical waste of healthcare institutions are obtained strategic, social, environmental and economic benefits.

Technologies development for environmental restoration and waste management: International university and research institution and industry partnerships

International Nuclear Information System (INIS)

Herndon, R.C.; Moerlins, J.E.; Kuperberg, J.M.

1996-01-01

The Institute for Central and Eastern European Cooperative Environmental Research (ICEECER) at Florida State University was formed in 1990 soon after the end of the Cold War. ICEECER consists of a number of joint centers which link FSU, and US as well as international funding agencies, to academic and research institutions in Hungary, Poland, the Czech Republic, Russia, and the other countries of Central and Eastern Europe and the Newly Independent States. Areas of interest include risk assessment, toxicology, contaminated site remediation/characterization, waste management, emergency response, environmental technology development/demonstration/transfer, and some specialized areas of research (e.g., advanced chemical separations). Through ICEECER, numerous international conferences, symposia, training courses, and workshops have also been conducted on a variety of environmental topics. This paper summarizes the mission, structure, and administration of ICEECER and provides information on the projects conducted through this program at FSU

Waste management research abstracts no. 16. Information on radioactive waste programmes in progress

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-11-01

The research abstracts contained in this issue have been collected during recent months ending August 1985. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. The abstracts have been printed in the language and in the form of submittal and without any changes other than minor editorial ones.

Waste management research abstracts no. 16. Information on radioactive waste programmes in progress

International Nuclear Information System (INIS)

1985-11-01

The research abstracts contained in this issue have been collected during recent months ending August 1985. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. The abstracts have been printed in the language and in the form of submittal and without any changes other than minor editorial ones

Disposal of radioactive waste from nuclear research facilities

CERN Document Server

Maxeiner, H; Kolbe, E

2003-01-01

Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

Solid wastes research in South Africa

CSIR Research Space (South Africa)

Noble, RG

1976-06-01

Full Text Available The importance of solid wastes management in environmental pollution control cannot be over-emphasised. Increased socio-economic development in South Africa has brought with it increasing volumes of urban, industrial and agricultural wastes...

Radioactive waste management and its implications for environmental research

International Nuclear Information System (INIS)

Murray, C.N.; Girardi, F.; Bertozzi, G.; Myttenaere, C.

1980-01-01

Environmental mobility and biological availability of radioelements in the biosphere is one of the four barriers which assure the segregation of radioactivity when the radioactive wastes are disposed into geologic formations. In carrying out studies on long-term risk assessment associated with waste disposal of this type, the terrestrial and aquatic models are developed to represent the above mentioned barrier so that risk linked with this barrier is realistically evaluated. These models help in identifying areas of research in environmental field for proper assessment of risk and in optimizing the relationship between requirements of risk assessment and ecological investigations. The three basic areas identified for research are realistic transfer coefficients between various ecological compartments, transfer mechanisms, and long-term evolution of various environmental compartments. Both laboratory and in situ studies are carried out and their results are used in developing models. Various research projects in progress under the Radiological Protection Programme of the Commission of European Community (CEC) are mentioned. As expertise from various fields is required for this research and is not possibly available at a single place, CEC has given research contracts for certain projects to national laboratories so that expertise available with them is utilised and CEC also is engaged directly in research activities which are carried out at its Joint Research Centre. Advisory Committee for Programme Management of the CEC provides the link between various actions and the necessary flow of information between the CEC and the national research teams within the European Community. (M.G.B.)

Developing a scarifier to retrieve radioactive waste from Hanford single-shell tanks

International Nuclear Information System (INIS)

Bamberger, J.A.; Steele, D.E.

1993-08-01

Radioactive waste is stored in 149 3,785 m 3 (million gal) single-shell tanks on the US Department of Energy's Hanford Reservation in eastern Washington. To minimize leakage as the tanks age, the free liquid has been pumped out, leaving concentrated solidified salt cake and sludge deposits. Now methods to dislodge and remove this waste are being developed so that the waste can be retrieved and processed for permanent storage. This paper presents research and development on ultrahigh-pressure water-jet technology to fracture and dislodge the wastes in these tanks. A water-based prototype scarifier with an integral conveyance system is being developed, and its performance demonstrated in a coupled analytical and experimental investigation. This paper describes experimental objectives and approach and results of the single jet experiments. Previous testing indicates that the method can be readily applied to salt cake waste forms; retrieval and conveyance of sludge and viscous fluid waste forms may present additional challenges

Research and development for treatment and disposal technologies of TRU waste

International Nuclear Information System (INIS)

Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Nakanishi, Hiroshi; Sasaki, Ryoichi; Ichige, Satoru; Takahashi, Kuniaki; Meguro, Yoshihiro; Yamaguchi, Hiromi; Aoyama, Yoshio

2007-09-01

After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology. (author)

UJV line for research into radioactive wastes solidification

International Nuclear Information System (INIS)

Neumann, L.; Feist, I.; Kepak, F.; Nachmilner, L.; Napravnik, J.; Novak, M.; Pecak, V.; Vojtech, O.

1985-01-01

An experimental line with a capacity of 0.01 m 3 /h was developed and built for research of the solidification of liquid radioactive wastes at the Nuclear Research Institute. The line allows the research and pilot plant testing of processes based on vitrification but also on other procedures including calcination. It consists of a horizontal calciner, a resistance melting unit, a homogenization device for research into cementation of the calcinate, and equipment for the disposal of gaseous emissions. The facility is provided with a control console which allows remote control and the control of all basic operating parameters. The design of the line allows its eventual completion with other equipment. (Z.M.)

Announced document collection of the 3rd information exchange meeting on radioactive waste disposal research network

International Nuclear Information System (INIS)

2008-03-01

The 3rd meeting on 'Radioactive Waste Disposal Research Network' was held at the Ricotti techno community square of JAEA on September 3 and 4, 2007. The 'Radioactive Waste Disposal Research Network' was established in Interorganization Atomic Energy Research Program under academic collaborative agreement between Japan Atomic Energy Agency and the University of Tokyo. The objective is to bring both research infrastructures and human expertise in Japan to an adequate performance level, thereby contributing to the development of the fundamental research area in the field of radioactive waste disposal. This lecture material is a collection of presentations and discussions during the information exchange meeting. (author)

Research and Development of a New Silica-Alumina Based Cementitious Material Largely Using Coal Refuse for Mine Backfill, Mine Sealing and Waste Disposal Stabilization

Energy Technology Data Exchange (ETDEWEB)

Henghu Sun; Yuan Yao

2012-06-29

Coal refuse and coal combustion byproducts as industrial solid waste stockpiles have become great threats to the environment. To activate coal refuse is one practical solution to recycle this huge amount of solid waste as substitute for Ordinary Portland Cement (OPC). The central goal of this project is to investigate and develop a new silica-alumina based cementitious material largely using coal refuse as a constituent that will be ideal for durable construction, mine backfill, mine sealing and waste disposal stabilization applications. This new material is an environment-friendly alternative to Ordinary Portland Cement. The main constituents of the new material are coal refuse and other coal wastes including coal sludge and coal combustion products (CCPs). Compared with conventional cement production, successful development of this new technology could potentially save energy and reduce greenhouse gas emissions, recycle vast amount of coal wastes, and significantly reduce production cost. A systematic research has been conducted to seek for an optimal solution for enhancing pozzolanic reactivity of the relatively inert solid waste-coal refuse in order to improve the utilization efficiency and economic benefit as a construction and building material.

The challenge of electronic waste (e-waste) management in developing countries.

Science.gov (United States)

Osibanjo, O; Nnorom, I C

2007-12-01

Information and telecommunications technology (ICT) and computer Internet networking has penetrated nearly every aspect of modern life, and is positively affecting human life even in the most remote areas of the developing countries. The rapid growth in ICT has led to an improvement in the capacity of computers but simultaneously to a decrease in the products lifetime as a result of which increasingly large quantities of waste electrical and electronic equipment (e-waste) are generated annually. ICT development in most developing countries, particularly in Africa, depends more on secondhand or refurbished EEEs most of which are imported without confirmatory testing for functionality. As a result large quantities of e-waste are presently being managed in these countries. The challenges facing the developing countries in e-waste management include: an absence of infrastructure for appropriate waste management, an absence of legislation dealing specifically with e-waste, an absence of any framework for end-of-life (EoL) product take-back or implementation of extended producer responsibility (EPR). This study examines these issues as they relate to practices in developing countries with emphasis on the prevailing situation in Nigeria. Effective management of e-waste in the developing countries demands the implementation of EPR, the establishment of product reuse through remanufacturing and the introduction of efficient recycling facilities. The implementation of a global system for the standardization and certification/labelling of secondhand appliances intended for export to developing countries will be required to control the export of electronic recyclables (e-scarp) in the name of secondhand appliances.

Finnish Research Programme on Nuclear Waste Management (KYT). Framework Programme for 2002-2005

International Nuclear Information System (INIS)

Rasilainen, K.

2002-12-01

The new Finnish research programme on nuclear waste management (KYT) will be conducted in 2002 - 2005. This framework programme describes the starting point, the basic aims and the organisation of the research programme. The starting point of the KYT programme is derived from the present state and future challenges of Finnish nuclear waste management. The research programme is funded mainly by the Ministry of Trade and Industry (KTM), the Radiation and Nuclear Safety Authority (STUK), Posiva Oy, Fortum Oyj, Teollisuuden Voima Oy (TVO), and the National Technology Agency (Tekes). As both regulators and implementors are involved, the research programme concentrates on neutral research topics that must be studied in any case. Methods and tools for experimental and theoretical studies fall in this category. State of the art -reviews on relevant topics also create national know-how. Topics that directly belong to licensing activities of nuclear waste management are excluded from the research programme. KYT carries out technical studies that increase national know-how in the area of nuclear waste management. The aim is to maintain and develop basic expertise needed in the operations derived from the national nuclear waste management plan. The studies have been divided into strategic studies and studies enhancing the long-term safety of spent nuclear fuel disposal. Strategic studies support the overall feasibility of Finnish nuclear waste management. These studies include basic options and overall safety principles related to nuclear fuel cycle and nuclear waste management. In addition, general cost estimates as well as general safety considerations related to transportations, low- and medium level wastes, and decommissioning are included in strategic studies. Studies supporting the long-term safety of spent fuel disposal include issues related to performance assessment methodology, release of radionuclides from the repository, behaviour of bedrock and groundwater

Hazardous Waste Research Center

Data.gov (United States)

Federal Laboratory Consortium — The U.S. Army Engineer Waterways Experiment Station (WES) is playing a major role in development of technologies for cleanup of toxic and hazardous waste in military...

The Community's research and development programme on radioactive waste management and storage. Shared cost action. Annual progress report 1988. Volume 2

International Nuclear Information System (INIS)

Anon.

1989-01-01

Third annual progress report of the European Community's 1985-89 programme of research and development on radioactive waste management and disposal, carried out by public organizations and private firms in the Community under cost-sharing contracts with the Commission of the European Communities. This report describes the work to be carried out under research contracts already concluded before the end of 1988, as well as the work performed and the results obtained so far

The Community's research and development programme on radioactive waste management and storage. Shared cost action. Annual progress report 1988. Volume 1

International Nuclear Information System (INIS)

Anon.

1989-01-01

Third annual progress report of the European Community's 1985-89 programme of research and development on radioactive waste management and disposal, carried out by public organizations and private firms in the Community under cost-sharing contracts with the Commission of the European Communities. This report describes the work to be carried out under research contracts already concluded before the end of 1988, as well as the work performed and the results obtained so far

Basic research needs for management and disposal of DOE wastes

International Nuclear Information System (INIS)

Grazis, B.M.; Schulz, W.W.

1991-04-01

This document was chartered by the Department of Energy (DOE), Office of Energy Research. It identifies and describes 87 basic research needs in support of advanced technology for management and disposal of Department of Energy radioactive, hazardous chemical, and mixed wastes. A team of scientists and engineers from several DOE laboratories and sites, from academia, and from industry identified and described the basic research needs called out in this report. Special efforts were made to ensure that basic research needs related to management and disposal of any hazardous chemical wastes generated at nonnuclear DOE sites and facilities were properly identified. It is hoped that scientists in both DOE and nongovernment laboratories and institutions will find this document useful when formulating research efforts relevant to waste management and disposal. For management and disposal of DOE radioactive and mixed wastes, basic research needs are identified in nine separate action areas. Basic research needs for management and disposal of DOE hazardous chemical wastes are identified in five action areas. Sufficient description and background information are provided in the report for each particular research need to enable qualified and imaginative scientists to conceive research efforts and programs that will meet the need. 28 refs., 7 tabs

Material Recovery and Waste Form Development FY 2015 Accomplishments Report

Energy Technology Data Exchange (ETDEWEB)

Todd, Terry Allen [Idaho National Lab. (INL), Idaho Falls, ID (United States); Braase, Lori Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-11-01

The Material Recovery and Waste Form Development (MRWFD) Campaign under the U.S. Department of Energy (DOE) Fuel Cycle Technologies (FCT) Program is responsible for developing advanced separation and waste form technologies to support the various fuel cycle options defined in the DOE Nuclear Energy Research and Development Roadmap, Report to Congress, April 2010. The FY 2015 Accomplishments Report provides a highlight of the results of the research and development (R&D) efforts performed within the MRWFD Campaign in FY-14. Each section contains a high-level overview of the activities, results, technical point of contact, applicable references, and documents produced during the fiscal year. This report briefly outlines campaign management and integration activities, but primarily focuses on the many technical accomplishments made during FY-15. The campaign continued to utilize an engineering driven-science-based approach to maintain relevance and focus. There was increased emphasis on development of technologies that support near-term applications that are relevant to the current once-through fuel cycle.

Development of radioactive waste treatment technique

International Nuclear Information System (INIS)

Kikuchi, Makoto; Amamiya, Shigeru; Yusa, Hideo.

1984-01-01

The techniques of radioactive waste treatment are generally reviewed, placing emphasis on volume reduction and solidification techniques. After a brief description on the general process of radioactive waste treatment, some special technologies being developed by Hitachi Ltd. are explained. From the viewpoints of the volume reduction, long term management and final disposal of wastes, the pelletization of dried waste and the solidification with inorganic substances are considered. One of the features of the pelletization system is to treat various kinds of wastes such as concentrated liquid wastes and used resins by the same system. The flow diagram of the system and its special features are shown. The volume reduction achieved by this system as compared to the conventional method is about 1/7. The first commercial plant for the treatment of concentrated liquid waste is scheduled to begin operation in June, 1984. As for the solidification technique for waste disposal, the use of cement glass is considered. The solidification system being developed is shortly described. (Aoki, K.)

Simple and rapid determination methods for low-level radioactive wastes generated from nuclear research facilities. Guidelines for determination of radioactive waste samples

International Nuclear Information System (INIS)

Kameo, Yutaka; Shimada, Asako; Ishimori, Ken-ichiro; Haraga, Tomoko; Katayama, Atsushi; Nakashima, Mikio; Hoshi, Akiko

2009-10-01

Analytical methods were developed for simple and rapid determination of U, Th, and several nuclides, which are selected as important nuclides for safety assessment of disposal of wastes generated from research facilities at Nuclear Science Research Institute and Oarai Research and Development Center. The present analytical methods were assumed to apply to solidified products made from miscellaneous wastes by plasma melting in the Advanced Volume Reduction Facilities. In order to establish a system to analyze the important nuclides in the solidified products at low cost and routinely, we have advanced the development of a high-efficiency non-destructive measurement technique for γ-ray emitting nuclides, simple and rapid methods for pretreatment of solidified product samples and subsequent radiochemical separations, and rapid determination methods for long-lived nuclides. In the present paper, we summarized the methods developed as guidelines for determination of radionuclides in the low-level solidified products. (author)

Current policy and research on radioactive waste management in the European Union

International Nuclear Information System (INIS)

Forsstroem, H.; Taylor, D.M.

2000-01-01

Each Member State of the European Union is responsible for the safe management and disposal of the radioactive waste produced on its own territory. This includes setting the policy and taking the necessary steps to ensure that the radioactive waste does not constitute a threat to the health of workers and to the general public. For the practical implementation of the policy, specific waste management organizations have been established. Extensive cooperation, not least in the area of research, is taking place between these organizations and between the regulatory authorities, both bilaterally and through the European Commission. Cooperation takes place through the European Commission by two different mechanisms, the Community Plan of Action in the field of radioactive waste and the EURATOM framework programme on research and training. In view of the future enlargement of the European Union, the Commission is also actively involved in the development of waste management practices in the Central and Eastern European countries. Waste management is also an important aspect of the Tacis and other nuclear safety support programmes to the States of the former Soviet Union. The general policies for waste management in all Member States are in harmony with the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The specific policies are, however, dependent on the specific conditions of that State, e.g. the existence, size and time perspective of the nuclear power programme, the geological formations available for disposal (clay, salt, crystalline rock), etc. The management of short lived waste is an established practice in many Member States and the research needs are consequently low. Most of the policy efforts and research are thus dedicated to the management, treatment, conditioning and geological disposal of long lived waste and spent fuel. Each Member State with a nuclear power programme also has an important

Development of vitrified waste storage system

International Nuclear Information System (INIS)

Namiki, S.; Tani, Y.

1993-01-01

The authors have developed the radioactive waste vitrification technology and the vitrified waste storage technology. Regarding the vitrified waste storage system development, the authors have completed the design of two types of storage systems. One is a forced convection air cooling system, and the other is a natural convection air cooling system. They have carried out experiments and heat transfer analysis, seismic analysis, vitrified waste dropping and radiation shielding, etc. In this paper, the following three subjects, are discussed: the cooling air flow experiment, the wind effect experiment on the cooling air flow pattern, using a wind tunnel apparatus and the structural integrity evaluation on the dropping vitrified waste

Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

International Nuclear Information System (INIS)

Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

2001-03-01

Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

Radioactive waste management research at CEGB Berkeley nuclear laboratories

International Nuclear Information System (INIS)

Bradbury, D.

1988-01-01

The CEGB is the major electric utility in the United Kingdom. This paper discusses how, at the research laboratories at Berkeley (BNL), several programs of work are currently taking place in the radioactive waste management area. The theme running through all this work is the safe isolation of radionuclides from the environment. Normally this means disposal of waste in solid form, but it may also be desirable to segregate and release nonradioactive material from the waste to reduce volume or improve the solid waste characteristics (e.g., the release of liquid or gaseous effluents after treatment to convert the radioactivity to solid form). The fuel cycle and radioactive waste section at BNL has a research program into these aspects for wastes arising from the operation or decommissioning of power stations. The work is done both in-house and on contract, with primarily the UKAEA

Waste generated by the future decommissioning of the Magurele VVR-S Research Reactor

International Nuclear Information System (INIS)

Dragolici, F.; Turcanu, C.N.; Dragolici, A.C.

2001-01-01

Nuclear Research Reactor WWR-S from the National Institute of Research and Development for Physics and Nuclear Engineering 'Horia Hulubei', Bucharest-Magurele, was commissioned in July 1957 and it was shut down in December 1997. At the moment the reactor is in conservation state. During its operation this reactor worked at an average power of 2MW, almost 3216 h/year, producing a total thermal power of 230 x 10 3 MWh. No major modifications or improvements were made during the 40 years of operation to the essential parts of the reactor, respective to the primary cooling system, reactor vessel, active core and electronic devices. So, all components of the measure, control and protection systems are old, generally at the technical level of the 1950s, therefore a reason why in December 1997 the operation was ceased. At present, the reactor can be considered, by IAEA definition in the first stage (reactor shut down, but the vital functions are maintained and monitored). The survey is related to the second stage - restrictive use of the area. To develop a real decommissioning project, it was first necessary to evaluate the volume and the characteristics of the radioactive waste which will be generated. Radioactive waste generated during the decommissioning of Magurele WR-S research reactor may be classified as: Activated wastes (internal structures, horizontal channels and thermal column, biological shield); Contaminated wastes (primary circuit non-activated components, hot cells, some technological rooms as main hall, pumps room, radioactive material transfer areas, ventilation building and stack); Possibly contaminated materials from any area of reactor building and ventilation building. After 40 years of nuclear research activities, all such areas are suspected of contamination. The volume of wastes that will result from WWR-S Research Reactor decommissioning is summarized

Investigating factors influencing construction waste management efforts in developing countries: an experience from Thailand.

Science.gov (United States)

Manowong, Ektewan

2012-01-01

Rapid economic growth and urbanization in developing countries lead to extensive construction activities that generate a large amount of waste. A challenge is how to manage construction waste in the most sustainable way. In the developing world, research on construction waste management is scarce and such academic knowledge needs to be responsive to actual practices in the industry in order to be implemented. As construction projects involve a number of participants and stakeholders, their participation and commitment can have a major influence on the goals of green and sustainable construction for urban development. This study provides a significant step in conducting a very first research of this kind in Thailand by aiming to investigate the level of construction stakeholders' commitment as well as the achievement of construction waste management in order to improve short-term practices and to establish a long-term strategic construction waste management plan. In this study, a structural equation model was employed to investigate the influence of factors that are related to environmental aspects, social aspects, and economic aspect of construction waste management. Concern about health and safety was found to be the most significant and dominant influence on the achievement of sustainable construction waste management. Other factors affecting the successful management of construction waste in Thai construction projects were also identified. It is perceived that this study has potential to contribute useful guidelines for practitioners both in Thailand and other developing countries with similar contexts.

Materials and Waste Management Research

Science.gov (United States)

EPA is developing data and tools to reduce waste, manage risks, reuse and conserve natural materials, and optimize energy recovery. Collaboration with states facilitates assessment and utilization of technologies developed by the private sector.

Waste management research abstracts vol. 25. Information on radioactive waste management research in progress or planned

International Nuclear Information System (INIS)

2000-01-01

The research abstracts contained in this issue have been collected during recent months and cover the period between January 1 and June 30, 2000. The abstracts reflect research currently in progress in the field of radioactive waste management. This issue contains 297 abstracts that present ongoing work in 33 countries and an international organization

Waste management research abstracts vol. 25. Information on radioactive waste management research in progress or planned

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

The research abstracts contained in this issue have been collected during recent months and cover the period between January 1 and June 30, 2000. The abstracts reflect research currently in progress in the field of radioactive waste management. This issue contains 297 abstracts that present ongoing work in 33 countries and an international organization.

High-level Waste Long-term management technology development

International Nuclear Information System (INIS)

Choi, Jong Won; Kang, C. H.; Ko, Y. K.

2012-02-01

The purpose of this project is to develop a long-term management system(A-KRS) which deals with spent fuels from domestic nuclear power stations, HLW from advanced fuel cycle and other wastes that are not admitted to LILW disposal site. Also, this project demonstrate the feasibility and reliability of the key technologies applied in the A-KRS by evaluating them under in-situ condition such as underground research laboratory and provide important information to establish the safety assessment and long-term management plan. To develop the technologies for the high level radioactive wastes disposal, demonstrate their reliability under in-situ condition and establish safety assessment of disposal system, The major objects of this project are the following: Ο An advanced disposal system including waste containers for HLW from advanced fuel cycle and pyroprocess has been developed. Ο Quantitative assessment tools for long-term safety and performance assessment of a radwaste disposal system has been developed. Ο Hydrological and geochemical investigation and interpretation methods has been developed to evaluate deep geological environments. Ο The THMC characteristics of the engineered barrier system and near-field has been evaluated by in-situ experiments. Ο The migration and retardation of radionuclides and colloid materials in a deep geological environment has been investigated. The results from this project will provide important information to show HLW disposal plan safe and reliable. The knowledge from this project can also contribute to environmental conservation by applying them to the field of oil and gas industries to store their wastes safe

Sustainable waste management through end-of-waste criteria development.

Science.gov (United States)

Zorpas, Antonis A

2016-04-01

The Waste Framework Directive 2000/98 (WFD) contains specific requirements to define end-of-waste criteria (EWC). The main goal of EWC is to remove and eliminate the administrative loads of waste legislation for safe and high-quality waste materials, thereby facilitating and assisting recycling. The target is to produce effective with high quality of recyclables materials, promoting product standardization and quality and safety assurance, and improving harmonization and legal certainty in the recyclable material markets. At the same time, those objectives aim to develop a plan in order to improve the development and wider use of environmental technologies, which reduce pressure on environment and at the same time address the three dimensions of the Lisbon strategy: growth, jobs and environment. This paper presents the importance of EWC, and the approach of setting EWC as EWC affect several management systems as well as sustainable and clean technologies.

Waste management research abstracts no. 14

International Nuclear Information System (INIS)

1983-04-01

The present 14th issue is the second of the new series of Waste Management Research Abstracts, which are reappearing after a three-year suspension. The new series appears in a substantially innovated form. Although the objective of the publication is the same as before, namely to collect and disseminate information on research in progress in the field of nuclear waste management, the format for presentation of the information is a new data sheet in a standardized form, access to which will be made possible by different indexes. The 408 research data sheets contained in this issue have been collected during recent months, ending 15 January 1983, and reflect research currently in progress. They were sent by the Governments of twenty-five Member States, by the International Atomic Energy Agency, and by the Commission of the European Communities. Though the information contained in this publication covers a wide range of subjects in various countries, the WMRA should not be interpreted as providing a complete survey of on-going research in IAEA Member States

Historical research in the Hanford site waste cleanup

International Nuclear Information System (INIS)

Gerber, Michele S.

1992-01-01

This paper will acquaint the audience with role of historical research in the Hanford Site waste cleanup - the largest waste cleanup endeavor ever undertaken in human history. There were no comparable predecessors to this massive waste remediation effort, but the Hanford historical record can provide a partial road map and guide. It can be, and is, a useful tool in meeting the goal of a successful, cost-effective, safe and technologically exemplary waste cleanup. The Hanford historical record is rich and complex. Yet, it poses difficult challenges, in that no central and complete repository or data base exists, records contain obscure code words and code numbers, and the measurement systems and terminology used in the records change many times over the years. Still, these records are useful to the current waste cleanup in technical ways, and in ways that extend beyond a strictly scientific aspect. Study and presentations of Hanford Site history contribute to the huge educational and outreach tasks of helping the Site's work force deal with 'culture change' and become motivated for the cleanup work that is ahead, and of helping the public and the regulators to place the events at Hanford in the context of WWII and the Cold War. This paper traces historical waste practices and policies as they changed over the years at the Hanford Site, and acquaints the audience with the generation of the major waste streams of concern in Hanford Site cleanup today. It presents original, primary-source research into the waste history of the Hanford Site. The earliest, 1940s knowledge base, assumptions and calculations about radioactive and chemical discharges, as discussed in the memos, correspondence and reports of the original Hanford Site (then Hanford Engineer Works) builders and operators, are reviewed. The growth of knowledge, research efforts, and subsequent changes in Site waste disposal policies and practices are traced. Examples of the strengths and limitations of the

Collaboration of the Dutch research program for radioactive waste disposal (OPERA) and TU Delft

International Nuclear Information System (INIS)

Bykov, D.M.; Kloosterman, J.L.

2015-01-01

Radioactive waste in the Netherlands is collected, treated and stored by COVRA (Centrale Organisatie Voor Radioactief Afval) in the interim storage facility for at least 100 a. After this period of long-term storage, geological disposal is foreseen. The policy is based on a step-wise decision process in which all decisions are taken to ensure safe disposal in a repository, but without excluding unforeseen alternative solutions that might develop in the future. OPERA is the Dutch acronym for research program into geological disposal of radioactive waste. It started in 2011 and is running for five years. The OPERA Research plan is developed by NRG in close collaboration with COVRA. Radioactive waste disposal in the Netherlands is at an early, conceptual phase. The aim of Opera is to develop a first preliminary safety case to structure the research necessary for the eventual deployment of a repository in the Netherlands. The OPERA research program aims at a close cooperation with the Belgian research program on radioactive waste disposal. The result of OPERA will be to detail a first roadmap for the long-term research on geological disposal of radioactive waste in the Netherlands, based initially on a re-evaluation of existing safety and feasibility studies conducted more than ten years ago, making use of present international and, wherever possible, national knowledge. This will be done by developing initial and conditional safety cases for generic GDFs in Zechstein rock salt and Boom Clay formations in the Netherlands. The goal in OPERA is to develop initial safety cases that are intended to mark the start of the research development process and to iterate these as knowledge grows to new developed insights. The safety case is conditional since plausible assumptions must later be confirmed in a safety case e.g. for site selection. Dutch, Belgian, German, English and French organizations participate in OPERA. These organizations can be found in the two documents with

Collaboration of the Dutch research program for radioactive waste disposal (OPERA) and TU Delft

Energy Technology Data Exchange (ETDEWEB)

Bykov, D.M.; Kloosterman, J.L. [TU Delft (Netherlands). Reactor Inst. Delft; Neeft, E.A.C.; Verhoef, E.V. [COVRA N.V., Nieuwdorp (Netherlands)

2015-07-01

Radioactive waste in the Netherlands is collected, treated and stored by COVRA (Centrale Organisatie Voor Radioactief Afval) in the interim storage facility for at least 100 a. After this period of long-term storage, geological disposal is foreseen. The policy is based on a step-wise decision process in which all decisions are taken to ensure safe disposal in a repository, but without excluding unforeseen alternative solutions that might develop in the future. OPERA is the Dutch acronym for research program into geological disposal of radioactive waste. It started in 2011 and is running for five years. The OPERA Research plan is developed by NRG in close collaboration with COVRA. Radioactive waste disposal in the Netherlands is at an early, conceptual phase. The aim of Opera is to develop a first preliminary safety case to structure the research necessary for the eventual deployment of a repository in the Netherlands. The OPERA research program aims at a close cooperation with the Belgian research program on radioactive waste disposal. The result of OPERA will be to detail a first roadmap for the long-term research on geological disposal of radioactive waste in the Netherlands, based initially on a re-evaluation of existing safety and feasibility studies conducted more than ten years ago, making use of present international and, wherever possible, national knowledge. This will be done by developing initial and conditional safety cases for generic GDFs in Zechstein rock salt and Boom Clay formations in the Netherlands. The goal in OPERA is to develop initial safety cases that are intended to mark the start of the research development process and to iterate these as knowledge grows to new developed insights. The safety case is conditional since plausible assumptions must later be confirmed in a safety case e.g. for site selection. Dutch, Belgian, German, English and French organizations participate in OPERA. These organizations can be found in the two documents with

Japan-Australia co-operative program on research and development of technology for the management of high level radioactive wastes. Final report 1985 to 1998

Energy Technology Data Exchange (ETDEWEB)

Hart, K.; Vance, E.; Lumpkin, G. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia); Mitamura, H.; Banba, T. [Japan Atomic Energy Research Inst. Tokai, Ibaraki (Japan)

1998-12-01

The overall aim of the Co-operative Program has been to promote the exchange of information on technology for the management of High-Level Wastes (HLW) and to encourage research and development relevant to such technology. During the 13 years that the Program has been carried out, HLW management strategies have matured and developed internationally, and Japan has commenced construction of a domestic reprocessing and vitrification facility for HLW. The HLW management strategy preferred is a national decision. Many countries are using vitrification, direct disposal of spent fuel or a combination of both to handle their existing wastes whereas others have deferred the decision. The work carried out in the Co-operative Program provides strong scientific evidence that the durability of ceramic waste forms is not significantly affected by radiation damage and that high loadings of actinide elements can be incorporated into specially designed ceramic waste forms. Moreover, natural minerals have been shown to remain as closed systems for U and Th for up to 2.5 b y. All of these results give confidence in the ability of second generation waste forms, such as Synroc, to handle future waste arisings that may not be suitable for vitrification 87 refs., 15 tabs., 22 figs.

Publications | Page 8 | IDRC - International Development Research ...

International Development Research Centre (IDRC) Digital Library (Canada)

Results 71 - 80 of 6341 ... Through books, articles, research publications, and studies, we aim to widen the impact of our investment and advance development research. ... Brazil, metal waste and mud flowed downstream, contaminating the water and wreaking havoc as the worst environmental disaster in the nation's history.

Current research and development at the Nuclear Research Center Karlsruhe

International Nuclear Information System (INIS)

Kuesters, H.

1982-01-01

The Nuclear Research Center Karlsruhe (KfK) is funded to 90% by the Federal Republic of Germany and to 10% by the State of Baden-Wuerttemberg. Since its foundation in 1956 the main objective of the Center is research and development (R and D) in the aera of the nuclear technology and about 2/3 of the research capacity is now devoted to this field. Since 1960 a major activity of KfK is R and D work for the design of fast breeder reactors, including material research, physics, and safety investigations; a prototype of 300 MWe is under construction now in the lower Rhine Valley. For enrichment of 235 U fissile material KfK developed the separation nozzle process; its technical application is realized within an international contract between the Federal Republic of Germany and Brazil. Within the frame of the European Programme on fusion technology KfK develops and tests superconducting magnets for toroidal fusion systems; a smaller activity deals with research on inertial confinement fusion. A broad research programme is carried through for safety investigations of nuclear installations, especially for PWRs; this activity is supplemented by research and development in the field of nuclear materials' safeguards. Development of fast reactors has to initiate research for the reprocessing of spent fuel and waste disposal. In the pilot plant WAK spent fuel from LKWs is reprocessed; research especially tries e.g. to improve the PUREX-process by electrochemical means, vitrification of high active waste is another main activity. First studies are being performed now to clarify the necessary development for reprocessing fast reactor fuel. About 1/3 of the research capacity of KfK deals with fundamental research in nuclear physics, solid state physics, biology and studies on the impact of technology on environment. Promising new technologies as e.g. the replacement of gasoline by hydrogen cells as vehicle propulsion are investigated. (orig.)

PROGER - radioactive waste management in Brazilian research institutions

International Nuclear Information System (INIS)

Pontedeiro, E.; Ramos, A.C.; Reis e Vaz, S.; Ferreira, R.S.

1998-01-01

This article demonstrates the feasibility of a programme, called PROGER, which is aimed at improving the radioactive waste management activities of research institutions in Brazil. PROGER involves the implementation, correction and updating of waste management techniques in those institutions where a waste management system is already being carried out or the introduction and full deployment of such a system in those where a system does not exist. The methodology utilized by the PROGER programme is discussed, and partial results are presented bearing in mind the characteristics and quantities of wastes. (author)

Waste management at the Karlsruhe Nuclear Research Center

International Nuclear Information System (INIS)

Hoehlein, G.; Lins, W.

1982-01-01

In the Karlsruhe Nuclear Research Center the responsibility for waste management is concentrated in the Decontamination Department which serves to collect and transport all liquid waste and solid material from central areas in the center for further waste treatment, clean radioactive equipment for repair and re-use or for recycling of material, remove from the liquid effluents any radioactive and chemical pollutants as specified in legislation on the protection of waters, convert radioactive wastes into mechanically and chemically stable forms allowing them to be transported into a repository. (orig./RW)

Development of drying and pelletizing system for concentrated waste

International Nuclear Information System (INIS)

Horiuchi, Susumu; Saito, Toru; Hirano, Mikio; Kikuchi, Makoto; Takamura, Yoshiyuki.

1980-01-01

Volume reduction is strongly required for the radioactive liquid waste generated in nuclear power plants because its storing space has increased with the operating years of the plants, though it has temporarily been stored in drum cans within the plant sites after concentrated by evaporation. The drying and pelletizing system developed by Hitachi, Ltd. in cooperation with Tokyo Electric Power Co. aims at the final disposal by solidifying stored waste after drying, pulverizing, and pelletizing concentrated liquid waste, and storing it in tanks to reduce its radioactivity for the predetermined period. The outstanding features of the system are to be capable of realizing drastic volume reduction and of storing waste as the stable solid in the form flexibly adaptable to any disposing method. The system, to which the new concepts of pulverizing by drying and pelletizing concentrated liquid waste were applied, has been subjected to various fundamental tests and the demonstration tests in a pilot plant during the research and development for 7-years, consequently it was confirmed that the system can be used practically, and the data for designing the equipment for practical use were collected. The items to be considered in designing the equipment for practical use are also mentioned. (Wakatsuki, Y.)

Waste management technology development and demonstration programs at Brookhaven National Laboratory

Science.gov (United States)

Kalb, Paul D.; Colombo, Peter

1991-01-01

Two thermoplastic processes for improved treatment of radioactive, hazardous, and mixed wastes were developed from bench scale through technology demonstration: polyethylene encapsulation and modified sulfur cement encapsulation. The steps required to bring technologies from the research and development stage through full scale implementation are described. Both systems result in durable waste forms that meet current Nuclear Regulatory Commission and Environmental Protection Agency regulatory criteria and provide significant improvements over conventional solidification systems such as hydraulic cement. For example, the polyethylene process can encapsulate up to 70 wt pct. nitrate salt, compared with a maximum of about 20 wt pct. for the best hydraulic cement formulation. Modified sulfur cement waste forms containing as much as 43 wt pct. incinerator fly ash were formulated, whereas the maximum quantity of this waste in hydraulic cement is 16 wt pct.

Advanced waste forms research and development. Final report, October 1, 1978-September 30, 1979

International Nuclear Information System (INIS)

McCarthy, G.J.

1979-08-01

Research on supercalcine-ceramics was conducted with the objectives of characterizing the phases and of applying them to fluorine-containing Thorex wastes. This report is concerned with quantitative phase analysis of complex ceramics using x-ray powder diffraction methods and with scanning transmission electron microscopy of these ceramics and its correlation with fluorite structure solid solution phase diagrams

Mixed waste focus area Department of Energy technology development needs identification and prioritization

International Nuclear Information System (INIS)

Roach, J.A.

1995-11-01

The Assistant Secretary for the Office of Environmental Management (EM) at the US DOE initiated a new approach in August, 1993 to environmental research and technology development. The key features of this new approach included establishment of five focus areas and three crosscutting technology programs, which overlap the boundaries of the focus areas. The five focus areas include the Contaminant Plumes Containment and Remediation; Mixed Waste Characterization, Treatment, and Disposal; High-Level Waste Tank Remediation, Landfill Stabilization, and Decontamination and Decommissioning Focus Areas. The three crosscutting technologies programs include Characterization, Monitoring, and Sensor Technology; Efficient Separations and Processing; and Robotics. The DOE created the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet its commitments for treatment of mixed wastes. To accomplish this goal, the technology deficiencies must be identified and categorized, the deficiencies and needs must be prioritized, and a technical baseline must be established that integrates the requirements associated with these needs into the planned and ongoing environmental research and technology development activities supported by the MWFA. These steps are described

The role of research in the development of radioactive waste disposal strategies and routes for the future

International Nuclear Information System (INIS)

Orlowski, S.

1993-01-01

Hazardous radioactive waste containing natural radionuclides have been generated for nearly a century. The volume cumulated of radioactive wastes over the years has been evaluated at some 2.5 million cubic meters for the USA alone. The electro-nuclear industry, adds to this picture significant amounts of industrial radioactive waste from the early seventies onwards. The volume of these industrial radioactive wastes cumulated since 1960 in the 24 countries concerned worldwide is today reaching the same order of magnitude as the Defence and R and D waste volume. The difference of objectives and a 20 to 30 years delay between the first occurrence of waste produced by the defence and electricity sectors, the emergence of the environmental concern in the early 70's, and last but not least the continuous wastes piling up are among the main circumstances which explain and lead to the following needs: a need for the environmental restoration of old disposal sites, a need for waste minimization to limit the disposal burden under the aspects of safety, and environmental protection, and economies; and finally, a need for an ability - technical and non technical - to dispose of all types of waste. R and D programmes on radioactive waste management and disposal have been heavily financed in most nuclear countries for at least two decades. The role of research for the future shall therefore be carefully considered. Safety and environmental concerns are widespread in the public and should be mitigated by providing additional confidence in existing strategies. 13 refs

A study for the safety evaluation of geological disposal of TRU waste and influence on disposal site design by change of amount of TRU waste (Joint research)

International Nuclear Information System (INIS)

Hasegawa, Makoto; Kondo, Hitoshi; Takahashi, Kuniaki; Funabashi, Hideaki; Kawatsuma, Shinji; Kamei, Gento; Hirano, Fumio; Mihara, Morihiro; Ueda, Hiroyoshi; Ohi, Takao; Hyodo, Hideaki

2011-02-01

In the safety evaluation of the geological disposal of the TRU waste, it is extremely important to share the information with the Research and development organization (JAEA: that is also the waste generator) by the waste disposal entrepreneur (NUMO). In 2009, NUMO and JAEA set up a technical commission to investigate the reasonable TRU waste disposal following a cooperation agreement between these two organizations. In this report, the calculation result of radionuclide transport for a TRU waste geological disposal system was described, by using the Tiger code and the GoldSim code at identical terms. Tiger code is developed to calculate a more realistic performance assessment by JAEA. On the other hand, GoldSim code is the general simulation software that is used for the computation modeling of NUMO TRU disposal site. Comparing the calculation result, a big difference was not seen. Therefore, the reliability of both codes was able to be confirmed. Moreover, the influence on the disposal site design (Capacity: 19,000m 3 ) was examined when 10% of the amount of TRU waste increased. As a result, it was confirmed that the influence of the site design was very little based on the concept of the Second Progress Report on Research and Development for TRU Waste Disposal in Japan. (author)

Research and development activities of the Joint Research Centre -JRC and its involvement in the development of future nuclear energy systems

International Nuclear Information System (INIS)

Schenkel, R.

2007-01-01

Besides the policy driven support which the JRC gives to the European Commission and its Member States, the nuclear activities of the JRC also fulfil the Research and Development obligations as enshrined in the EURATOM Treaty. These have for objectives to develop and assemble knowledge in the field of nuclear energy and concern basic actinide research, nuclear data and nuclear measurements, radiation monitoring and radionuclides in the environment, health and nuclear medicine, management of spent fuel and waste, safety of reactors and fuel cycle and nuclear safeguards and non proliferation. The European Union currently imports 50% of its energy and, going by the present trend, this may increase to 70% within 20 years. One third of the electricity in Europe is currently been produced via nuclear fission and the move to innovative reactor systems holds great promise. In May 2006, the European Atomic Energy Community became a Party to the Framework Agreement for International Collaboration on Research and Development of Generation IV Nuclear Energy Systems (GIF Framework Agreement). The 'Generation IV' initiative concerns concepts for nuclear energy systems that can be operated in a manner that will provide a competitive and reliable supply of energy, while satisfactorily addressing nuclear safety, waste, proliferation and public perception concerns. The JRC with its strong international dimension is not only the implementing agent for EURATOM in the Generation IV international forum, but also participates actively in related Research and Development projects. The Research and Development projects are focused on fuel development, reprocessing and irradiation testing, fuel cladding interaction and corrosion, basic data for fuel and reprocessing, reprocessing and waste treatment. In this paper the Research and Development the nuclear activities of the JRC will be presented especially those related to its participation to GIF

Development of Specifications for Radioactive Waste Packages

International Nuclear Information System (INIS)

2006-10-01

The main objective of this publication is to provide guidelines for the development of waste package specifications that comply with waste acceptance requirements for storage and disposal of radioactive waste. It will assist waste generators and waste package producers in selecting the most significant parameters and in developing and implementing specifications for each individual type of waste and waste package. This publication also identifies and reviews the activities and technical provisions that are necessary to meet safety requirements; in particular, selection of the significant safety parameters and preparation of specifications for waste forms, waste containers and waste packages using proven approaches, methods and technologies. This report provides guidance using a systematic, stepwise approach, integrating the technical, organizational and administrative factors that need to be considered at each step of planning and implementing waste package design, fabrication, approval, quality assurance and control. The report reflects the considerable experience and knowledge that has been accumulated in the IAEA Member States and is consistent with the current international requirements, principles, standards and guidance for the safe management of radioactive waste

Development of Specifications for Radioactive Waste Packages

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-10-15

The main objective of this publication is to provide guidelines for the development of waste package specifications that comply with waste acceptance requirements for storage and disposal of radioactive waste. It will assist waste generators and waste package producers in selecting the most significant parameters and in developing and implementing specifications for each individual type of waste and waste package. This publication also identifies and reviews the activities and technical provisions that are necessary to meet safety requirements; in particular, selection of the significant safety parameters and preparation of specifications for waste forms, waste containers and waste packages using proven approaches, methods and technologies. This report provides guidance using a systematic, stepwise approach, integrating the technical, organizational and administrative factors that need to be considered at each step of planning and implementing waste package design, fabrication, approval, quality assurance and control. The report reflects the considerable experience and knowledge that has been accumulated in the IAEA Member States and is consistent with the current international requirements, principles, standards and guidance for the safe management of radioactive waste.

Institute of Nuclear Waste Management Technology (INE). 1994 progress report on research and development

International Nuclear Information System (INIS)

1995-01-01

In 1994 INE worked on the following research projects: radionuclide behaviour during corrosion of high-level radioactive COGEMA glass; studies of glassy basalt of the Werra-Fulda salt deposit as a natural analogue of the corrosion of HAW glass; corrosion studies of high burnup LWR fuels in brine; chemical behaviour of Tc in aqueous, chloride systems; corrosion studies of waste container materials; solution chemistry of U; thermodynamics of Np(V) in concentrated brines; radiation-chemical effects in the vicinity of repositories; laser spectroscopic speciation and thermodynamics of Cm(III); development of laser spectroscopic methods; radiochemical and chemical analyses of nuclear samples; solid-state and surface analyses; coupling of transport and speciation models; influence of colloid formation on the migration behaviour of long-lived radionuclides; studies of the consolidation behaviour of filling material; thermomechanical effects of inhomogeneities in the salt dome; basic studies and process engineering developments in the field of solidification of high-level radioactive fission product solutions; corrosion behaviour of WAK-HAW containing glass products in brines. (orig./HP) [de

Information basis for developing comprehensive waste management system. US-Japan joint nuclear energy action plan waste management working group phase I report (Joint research)

International Nuclear Information System (INIS)

Yui, Mikazu; Ishikawa, Hirohisa; Umeki, Hiroyuki; Hioki, Kazumasa; Naito, Morimasa; Makino, Hitoshi; Oda, Chie; Tachi, Yukio; Mitsui, Seiichiro; Shibata, Masahiro; Watanabe, Atsuo; Yoshino, Kyoji; Seo, Toshihiro; Miyamoto, Yoichi; Nutt, Mark; Peters, Mark; Bresee, James; Lesica, Sue; Schwab, Patrick; Gomberg, Steve; Jones, Jay; Halsey, Bill; Marra, John; Vienna, John; Gombert, Drik; McMahon, Kevin; James, Scott; Caporuscio, Florie

2010-05-01

The activity of Phase I of the Waste Management Working Group under the United States - Japan Joint Nuclear Energy Action Plan started in 2007. The US-Japan JNEAP is a bilateral collaborative framework to support the global implementation of safe, secure, and sustainable, nuclear fuel cycles (referred to in this document as fuel cycles). The Waste Management Working Group was established by strong interest of both parties, which arise from the recognition that development and optimization of waste management and disposal system(s) are central issues of the present and future nuclear fuel cycles. This report summarizes the activity of the Waste Management Working Group that focused on consolidation of the existing technical basis between the U.S. and Japan and the joint development of a plan for future collaborative activities. Firstly, the political/regulatory frameworks related to nuclear fuel cycles in both countries were reviewed. The various advanced fuel cycle scenarios that have been considered in both countries were then surveyed and summarized. The working group established the working reference scenario for the future cooperative activity that corresponds to a fuel cycle scenario being considered both in Japan and the U.S. This working scenario involves transitioning from a once-through fuel cycle utilizing light water reactors to a one-pass uranium-plutonium fuel recycle in light water reactors to a combination of light water reactors and fast reactors with plutonium, uranium, and minor actinide recycle, ultimately concluding with multiple recycle passes primarily using fast reactors. Considering the scenario, current and future expected waste streams, treatment and inventory were discussed, and the relevant information was summarized. Second, the waste management/disposal system optimization was discussed. Repository system concepts were reviewed, repository design concepts for the various classifications of nuclear waste were summarized, and the factors

The KNOO research consortium: work package 3 - an integrated approach to waste immobilisation and management - 16375

International Nuclear Information System (INIS)

Biggs, Simon; Fairweather, Michael; Young, James; Grimes, Robin W.; Milestone, Neil; Livens, Francis

2009-01-01

The Keeping the Nuclear Option Open (KNOO) research consortium is a four-year research council funded initiative addressing the challenges related to increasing the safety, reliability and sustainability of nuclear power in the UK. Through collaboration between key industrial and governmental stakeholders, and with international partners, KNOO was established to maintain and develop skills relevant to nuclear power generation. Funded by a research grant of Pounds 6.1 M from the 'Towards a Sustainable Energy Economy Programme' of the UK Research Councils, it represents the single largest university-based nuclear research programme in the UK for more than 30 years. The programme is led by Imperial College London, in collaboration with the universities of Manchester, Sheffield, Leeds, Bristol, Cardiff and the Open University. These universities are working with the UK nuclear industry, who contributed a further Pounds 0.4 M in funding. The industry/government stakeholders include AWE, British Energy, the Department for Environment, Food and Rural Affairs, the Environment Agency, the Health and Safety Executive, Doosan Babcock, the Ministry of Defence, Nirex, AMEC NNC, Rolls-Royce PLC and the UK Atomic Energy Authority. Work Package 3 of this consortium, led by the University of Leeds, concerns 'An Integrated Approach to Waste Immobilisation and Management', and involves Imperial College London, and the Universities of Manchester and Sheffield. The aims of this work package are: to study the re-mobilisation, transport, solid-liquid separation and immobilisation of particulate wastes; to develop predictive models for particle behaviour based on atomic scale, thermodynamic and process scale simulations; to develop a fundamental understanding of selective adsorption of nuclides onto filter systems and their immobilisation; and to consider mechanisms of nuclide leaving and transport. The paper describes highlights from this work in the key areas of multi-scale modeling

Nuclear waste - research and technique development. KASAMS's Review of the Swedish Nuclear Fuel and Waste Management Co's (SKB's) RD and D Programme 2001

International Nuclear Information System (INIS)

2002-01-01

This report is KASAM's review statement to the Government on the Swedish Nuclear Fuel and Waste Management Co's (SKB's) RD and D Programme 2001. KASAM's review was primarily conducted through work by KASAM's members, special adviser, experts and secretary. In KASAM's opinion, the reactor owners, through RD and D Programme 2001, have complied with the requirements of paragraph 12 of the Act on Nuclear Activities. In KASAM's opinion, SKB's research and development programme shows great merit. This applies to both what SKB has done and what it intends to do. The report is well-structured and clear. RD and D Programme 2001 shows that there is still a considerable need for development work in a number of important technical areas. This applies, for example, to the fabrication and sealing of canisters as well as control methods for these activities. Within other areas, for example, geology, chemistry, hydrology, biology and rock mechanics, there is also a great need for further research and development work, and for practical demonstrations of technical applications. In KASAM's opinion, humanities and social science issues, that are of importance for the disposal of nuclear waste, should be accorded greater attention. In Chapter 14, KASAM has presented a proposal for how research in these areas can be organised and financed. KASAM emphasizes that future RD and D programmes should have a broad scientific basis in order to comply with the requirements of the Act on Nuclear Activities regarding comprehensiveness. In their review statements on RD and D Programme 2001, the Swedish Nuclear Power Inspectorate (SKI) and the Swedish Radiation Protection Authority (SSI) have proposed that SKB should be required to present a strategy document which should be kept updated. In KASAM's opinion, such a report of current strategic issues should be made available to the public and other parties concerned. KASAM also believes that such a documentation of strategy issues should be

Assessment report of research and development on 'geological disposal of high-level radioactive waste' (Interim report)

International Nuclear Information System (INIS)

Notoya, Shin; Shimizu, Kazuhiko; Ota, Kunio; Sasao, Eiji

2010-08-01

Japan Atomic Energy Agency (JAEA) consulted an assessment committee, 'Evaluation Committee of Research and Development (R and D) Activities for Geological Disposal of High-Level Radioactive Waste', for interim assessment of R and D on high-level radioactive waste disposal in accordance with 'General Guideline for Evaluation of Government R and D Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by Japan. In response to JAEA's request, the Committee assessed mainly the progress of the R and D project according to guidelines, which addressed the rationale behind the R and D project, the relevance of the project outcome and the efficiency of the project implementation during the period of the first midterm plan. As a result, the Committee concluded that the progress of the R and D project is satisfactory. In addition, the Committee provided a couple of issues and suggestions to be addressed in the implementation of the project during the period of the second midterm. A CD-ROM is attached as an appendix. (J.P.N.)

Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-01

The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs.

Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

International Nuclear Information System (INIS)

1994-12-01

The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs

Summary of INEL research on the iron-enriched basalt waste form

International Nuclear Information System (INIS)

Reimann, G.A.; Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

1992-01-01

This report summarizes the knowledge base on the iron-enriched basalt (IEB) waste form developed at the Idaho National Engineering Laboratory (INEL) during 1979--1982. The results presented discuss the applicability of IEB in converting retrieved transuranic (TRU) waste from INEL's Radioactive Waste Management Complex (RWMC) into a vitreous/ceramic (glassy/rock) stable waste form suitable for permanent disposal in an appropriate repository, such as the Waste Isolation Pilot Plant (WIPP) in New Mexico. Borosilicate glass (BSG), the approved high-level waste form, appears unsuited for this application. Melting the average waste-soil mix from the RWMC produces the IEB composition and attempting to convert IEB to the BSG composition would require additions of substantial B 2 0 3 , Na, and SiO 2 (glass frit). IEB requires processing temperatures of 1400 to 1600 degrees C, depending upon the waste composition. Production of the IEB waste form, using Joule heated melters, has proved difficult in the past because of electrode and refractory corrosion problems associated with the high temperature melts. Higher temperature electric melters (arc and plasma) are available to produce this final waste form. Past research focused on extensive slag property measurements, waste form leachability tests, mechanical, composition, and microstructure evaluations, as well as a host of experiments to improve production of the waste form. Past INEL studies indicated that the IEB glass-ceramic is a material that will accommodate and stabilize a wide range of heterogeneous waste materials, including long lived radionuclides and scrap metals, while maintaining a superior level of chemical and physical performance characteristics. Controlled cooling of the molten IEB and subsequent heat treatment will produce a glass-ceramic waste form with superior leach resistance

Mixed Waste Integrated Program -- Problem-oriented technology development

International Nuclear Information System (INIS)

Hart, P.W.; Wolf, S.W.; Berry, J.B.

1994-01-01

The Mixed Waste Integrated Program (MWIP) is responding to the need for DOE mixed waste treatment technologies that meet these dual regulatory requirements. MWIP is developing emerging and innovative treatment technologies to determine process feasibility. Technology demonstrations will be used to determine whether processes are superior to existing technologies in reducing risk, minimizing life-cycle cost, and improving process performance. Technology development is ongoing in technical areas required to process mixed waste: materials handling, chemical/physical treatment, waste destruction, off-gas treatment, final forms, and process monitoring/control. MWIP is currently developing a suite of technologies to process heterogeneous waste. One robust process is the fixed-hearth plasma-arc process that is being developed to treat a wide variety of contaminated materials with minimal characterization. Additional processes encompass steam reforming, including treatment of waste under the debris rule. Advanced off-gas systems are also being developed. Vitrification technologies are being demonstrated for the treatment of homogeneous wastes such as incinerator ash and sludge. An alternative to conventional evaporation for liquid removal--freeze crystallization--is being investigated. Since mercury is present in numerous waste streams, mercury removal technologies are being developed

Research of the cost-benefit evaluation for reprocessing research and development and high-level radioactive waste disposal research and development. Establishing R and D scenarios and extracting their effects

International Nuclear Information System (INIS)

Sugihara, K; Miura, N; Arii, Y

2004-02-01

This report is intended to explain the outline of research in the FY 2003 on cost-benefit evaluation for Reprocessing R and D and High-Level Radioactive Waste Disposal R and D. We decided to apply the Method of Cost-Benefit Analysis, based on cost-benefit analysis for Fast Reactor cycle system R and D, to Reprocessing R and D and High-Level Radioactive Waste Disposal R and D, and to compare with the results of cost-benefit analysis for both the JNC R and D scenario and the other optional scenarios. In this year, we first thought out all R and D scenarios in the future for Reprocessing R and D and High-Level Radioactive Waste Disposal R and D, and rejected difficult scenarios technically and impossible scenarios socially. Finally, the reasonable R and D scenarios were established. Besides, we thought out the effects (merits) by carrying out the R and D, and separated out them from economical view, environmental view, view of nuclear non-proliferation and so on. (author)

What we do | Page 90 | IDRC - International Development Research ...

International Development Research Centre (IDRC) Digital Library (Canada)

Results 891 - 900 of 1605 ... IDRC funds research in developing countries to create lasting ... Regions and countries ... --Faroe Islands, --Finland, --France, --Germany, --Gibraltar .... Carbon Market and Integrated Waste Solutions : a Case Study of Indonesia ... Topic(s): RESEARCH NETWORKS, RESEARCH METHODS, ...

Waste collection : a new topic for research in city logistics

NARCIS (Netherlands)

de Rijke, Simon; Colstee, Jan-Willem

2017-01-01

Waste collection is an important volume in city logistics today. In the LEVV-LOGIC project the Amsterdam University of Applied Sciences (NL) performed research on waste and the potential use of light commercial vehicles for waste collection in cities.

Development of new waste form for treatment and disposal of concentrated liquid radioactive waste

International Nuclear Information System (INIS)

Kwak, Kyung Kil; Ji, Young Yong

2010-12-01

The radioactive waste form should be meet the waste acceptance criteria of national regulation and disposal site specification. We carried out a characterization of rad waste form, especially the characteristics of radioactivity, mechanical and physical-chemical properties in various rad waste forms. But asphalt products is not acceptable waste form at disposal site. Thus we are change the product materials. We select the development of the new process or new materials. The asphalt process is treatment of concentrated liquid and spent-resin and that we decide the Development of new waste form for treatment and disposal of concentrated liquid radioactive waste

Optimizing Urban Material Flows and Waste Streams in Urban Development through Principles of Zero Waste and Sustainable Consumption

Directory of Open Access Journals (Sweden)

Steffen Lehmann

2011-01-01

designers, industrial designers, and so on. How must urban development and construction change and evolve to automatically embed sustainability in the way we design, build, operate, maintain and renew/recycle cities? One of the findings of this paper is that embedding zero-waste requires strong industry leadership, new policies and effective education curricula, as well as raising awareness (through research and education and refocusing research agendas to bring about attitudinal change and the reduction of wasteful consumption.

Multibarrier waste forms. Part I. Development

International Nuclear Information System (INIS)

Rusin, J.M.; Lokken, R.O.; Lukacs, J.M.; Sump, K.R.; Browning, M.F.; McCarthy, G.J.

1978-09-01

The multibarrier concept produces a composite waste form with enhanced inertness through improvements in thermal stability, mechanical strength, and leachability by the use of coatings and metal matrices. This report describes research and development activities resulting in the demonstration of the multibarrier concept for nonradioactive simulated waste compositions. The multibarrier concept is to utilize up to three barriers to isolate radionuclides from the environment: a solid waste inner core, an impervious coating, and a metal matrix. Two inner core materials, sintered supercalcine and glass marbles, have been demonstrated. The coating barrier provides enhanced leach, impact, and oxidation resistance as well as thermal protection during encapsulation in the metal matrix. Py/Al 2 O 3 coatings deposited by chemical vapor deposition (CVD) and glass coatings have been applied to supercalcine cores to improve inertness. The purpose of the metal matrix is to improve impact resistance, protect the inner core rom any adverse environments, provide radiation shielding, and increase thermal conductivity, yielding lower internal temperatures. The development of gravity sintering and vacuum casting techniques for matrix encapsulation are discussed. Four multibarrier products were demonstrated: (1) Glass marbles encapsulated in vacuum-cast Pb-10Sn; (2) uncoated, sintered supercalcine pellets encapsulated in vacuum-cast Al-12Si; (3) glass-coated, sintered supercalcine pellets encapsulated in vacuum-cast Al-12Si; and (4) PyC/Al 2 O 3 -coated supercalcine encapsulated in gravity-sintered Cu. 23 figs., 20 tables

PROGER - Management program for radioactive wastes in research institutions

International Nuclear Information System (INIS)

Ferreira, Rubemar S.; Costa, Maria Regina Ferro; Ramos Junior, Anthenor C.; Esposito, Irapoan; Vaz, Solange dos Reis e; Pontedeiro, Elizabeth May; Gomes, Carlos de Almeida

1997-01-01

This article demonstrates the feasibility of a program, denominated PROGER, and aimed at the improvement of radioactive waste management activities in research institutions in Brazil. This program involves implementation, correction and updating of waste management techniques in those institutions that already possess a waste management system or its full set-up for the institutions where it is non-existent. Partial results are presented, concerning characteristics and quantities of wastes, and the methodology utilized by PROGER discussed

Research challenges in municipal solid waste logistics management.

Science.gov (United States)

Bing, Xiaoyun; Bloemhof, Jacqueline M; Ramos, Tania Rodrigues Pereira; Barbosa-Povoa, Ana Paula; Wong, Chee Yew; van der Vorst, Jack G A J

2016-02-01

During the last two decades, EU legislation has put increasing pressure on member countries to achieve specified recycling targets for municipal household waste. These targets can be obtained in various ways choosing collection methods, separation methods, decentral or central logistic systems, etc. This paper compares municipal solid waste (MSW) management practices in various EU countries to identify the characteristics and key issues from a waste management and reverse logistics point of view. Further, we investigate literature on modelling municipal solid waste logistics in general. Comparing issues addressed in literature with the identified issues in practice result in a research agenda for modelling municipal solid waste logistics in Europe. We conclude that waste recycling is a multi-disciplinary problem that needs to be considered at different decision levels simultaneously. A holistic view and taking into account the characteristics of different waste types are necessary when modelling a reverse supply chain for MSW recycling. Copyright © 2015 Elsevier Ltd. All rights reserved.

IV meeting of R and d in research and technological development of radioactive waste management. Vol. 3

International Nuclear Information System (INIS)

2001-01-01

These Technical Publications include the main papers presented during the IV R and D symposium on Radioactive Wastes Management Technology, promoted by ENRESA and held in the Barcelona University during November 2001. The papers correspond both to the Technical Sessions and the Seminars and they are a document of inestimable value that indicates the high technological value reached in the radioactive waste management as a result of a clear and continuous R and D politics together with an intense and productive international collaboration. Throughout the papers of this document the technological status and the capacities developed in all different fields of the radioactive waste management are shown. The main subjects discussed include: low and medium activity wastes management, dismantling of nuclear plants, partitioning and transmutation of long life radionuclide and mainly deep geological disposal. Through the papers corresponding to the scientific sessions the state of the art in the mentioned areas is reviewed with special emphasis, as the achievements and developments reached in Spain. Through the seminars, many outstanding aspects of the R and D in radioactive wastes such as the biosphere role, the numerical modelling and the underground laboratories, can be studied in depth. (Author)

IV meeting of R and D in research and technological development of radioactive waste management. Vol. 4

International Nuclear Information System (INIS)

2001-01-01

These Technical Publications include the main papers presented during the IV R and d Symposium on Radioactive Wastes Management Technology, promoted by ENRESA and held in the Barcelona University during November 2001. The papers correspond both to the technical Sessions and the Seminars and they are a document of inestimable value that indicates the high technological value reached in the radioactive waste management as a result of a clear and continuous R and D politics together with an intense and productive international collaboration. Throughout the papers of this document the technological status and the capacities developed in all different fields of the radioactive waste management are shown. the main subjects discussed include: low and medium activity wastes management, dismantling of nuclear plants, partitioning and transmutation of long life radionuclide and mainly deep geological disposal. Through the papers corresponding to the scientific sessions the state of the art in the mentioned areas is reviewed with special emphasis as the achievements and developments reached in Spain. Through the seminars, many outstanding aspects of the R and D in radioactive wastes such as the biosphere role, the numerical modelling and the underground laboratories, can be studied in depth. (Author)

IV meeting of R and D in research and technological development of radioactive waste management. Vol. 1

International Nuclear Information System (INIS)

2001-01-01

These Technical Publications include the main papers presented during the IV R and D Symposium on Radioactive Wastes management Technology, promoted by ENRESA and held in the Barcelona University during November 2001. The papers correspond both to the Technical Sessions and the Seminars and they are a document of inestimable value that indicates the high technological value reached in the radioactive waste management as a result of a clear and continuous R and D politics together with in intense and productive international collaboration. Throughout the papers of this document the technological status and the capacities developed in all different fields of the radioactive waste management are shown. The main subjects discussed include: low and medium activity wastes management, dismantling of nuclear plants, partitioning and transmutation of long life radionuclide and mainly deep geological disposal. Through the papers corresponding to the scientific sessions the state of the art in the mentioned areas is reviewed with special emphasis, as the achievements and developments reached in Spain. Through the seminars, many outstanding aspects of the R and D in radioactive wastes such as the biosphere role, the numerical modelling and the underground laboratories, can be studies in depth. (Author)

Municipal solid waste development phases: Evidence from EU27.

Science.gov (United States)

Vujić, Goran; Gonzalez-Roof, Alvaro; Stanisavljević, Nemanja; Ragossnig, Arne M

2015-12-01

Many countries in the European Union (EU) have very developed waste management systems. Some of its members have managed to reduce their landfilled waste to values close to zero during the last decade. Thus, European Union legislation is very stringent regarding waste management for their members and candidate countries, too. This raises the following questions: Is it possible for developing and developed countries to comply with the European Union waste legislation, and under what conditions? How did waste management develop in relation to the economic development in the countries of the European Union? The correlation between waste management practices and economic development was analysed for 27 of the European Union Member States for the time period between 1995 and 2007. In addition, a regression analysis was performed to estimate landfilling of waste in relation to gross domestic product for every country. The results showed a strong correlation between the waste management variables and the gross domestic product of the EU27 members. The definition of the municipal solid waste management development phases followed a closer analysis of the relation between gross domestic product and landfilled waste. The municipal solid waste management phases are characterised by high landfilling rates at low gross domestic product levels, and landfilling rates near zero at high gross domestic product levels. Hence the results emphasize the importance of wider understanding of what is required for developing countries to comply with the European Union initiatives, and highlight the importance of allowing developing countries to make their own paths of waste management development. © The Author(s) 2015.

Management of historical waste from research reactors: the Dutch experience

International Nuclear Information System (INIS)

Van Heek, Aliki; Metz, Bert; Janssen, Bas; Groothuis, Ron

2013-01-01

Most radioactive waste emerges as well-defined waste streams from operating power reactors. The management of this is an on-going practice, based on comprehensive (IAEA) guidelines. A special waste category however consists of the historical waste from research reactors, mostly originating from various experiments in the early years of the nuclear era. Removal of the waste from the research site, often required by law, raises challenges: the waste packages must fulfill the acceptance criteria from the receiving storage site as well as the criteria for nuclear transports. Often the aged waste containers do not fulfill today's requirements anymore, and their contents are not well documented. Therefore removal of historical waste requires advanced characterization, sorting, sustainable repackaging and sometimes conditioning of the waste. This paper describes the Dutch experience of a historical waste removal campaign from the Petten High Flux research reactor. The reactor is still in operation, but Dutch legislation asks for central storage of all radioactive waste at the COVRA site in Vlissingen since the availability of the high- and intermediate-level waste storage facility HABOG in 2004. In order to comply with COVRA's acceptance criteria, the complex and mixed inventory of intermediate and low level waste must be characterized and conditioned, identifying the relevant nuclides and their activities. Sorting and segregation of the waste in a Hot Cell offers the possibility to reduce the environmental footprint of the historical waste, by repackaging it into different classes of intermediate and low level waste. In this way, most of the waste volume can be separated into lower level categories not needing to be stored in the HABOG, but in the less demanding LOG facility for low-level waste instead. The characterization and sorting is done on the basis of a combination of gamma scanning with high energy resolution of the closed waste canister and low

Development of a working set of waste package performance criteria for deepsea disposal of low-level radioactive waste. Final report

International Nuclear Information System (INIS)

Columbo, P.; Fuhrmann, M.; Neilson, R.M. Jr; Sailor, V.L.

1982-11-01

The United States ocean dumping regulations developed pursuant to PL92-532, the Marine Protection, Research, and Sanctuaries Act of 1972, as amended, provide for a general policy of isolation and containment of low-level radioactive waste after disposal into the ocean. In order to determine whether any particular waste packaging system is adequate to meet this general requirement, it is necessary to establish a set of performance criteria against which to evaluate a particular packaging system. These performance criteria must present requirements for the behavior of the waste in combination with its immobilization agent and outer container in a deepsea environment. This report presents a working set of waste package performance criteria, and includes a glossary of terms, characteristics of low-level radioactive waste, radioisotopes of importance in low-level radioactive waste, and a summary of domestic and international regulations which control the ocean disposal of these wastes

Research programme on radioactive wastes - Synthesis report 2009

International Nuclear Information System (INIS)

Brander, S.

2010-02-01

This short synthesis report for the Swiss Federal Office of Energy (SFOE) issued by the head of the programme on radioactive wastes reports on activities during the year 2009. Background information on the definition of topics to be focussed on is briefly presented. In particular, topics such as communication with the general public, knowledge-saving and marking concepts for radioactive wastes are noted. Work done in these areas as well as on waste management in general are discussed. Conferences held and the transfer of know-how are noted, as is cooperation with foreign organisations active in the area of nuclear research and waste management. Finally, work planned for 2010 is noted

Universities in capacity building in sustainable development: focus on solid waste management and technology.

Science.gov (United States)

Agamuthu, P; Hansen, Jens Aage

2007-06-01

This paper analyses some of the higher education and research capacity building experiences gained from 1998-2006 by Danish and Malaysian universities. The focus is on waste management, directly relating to both the environmental and socio-economic dimensions of sustainable development. Primary benefits, available as an educational legacy to universities, were obtained in terms of new and enhanced study curricula established on Problem-oriented Project-based Learning (POPBL) pedagogy, which strengthened academic environmental programmes at Malaysian and Danish universities. It involved more direct and mutually beneficial cooperation between academia and businesses in both countries. This kind of university reach-out is considered vital to development in all countries actively striving for global and sustainable development. Supplementary benefits were accrued for those involved directly in activities such as the 4 months of field studies, workshops, field courses and joint research projects. For students and academics, the gains have been new international dimensions in university curricula, enhanced career development and research collaboration based on realworld cases. It is suggested that the area of solid waste management offers opportunities for much needed capacity building in higher education and research, contributing to sustainable waste management on a global scale. Universities should be more actively involved in such educational, research and innovation programmes to make the necessary progress. ISWA can support capacity building activities by utilizing its resources--providing a lively platform for debate, securing dissemination of new knowledge, and furthering international networking beyond that which universities already do by themselves. A special challenge to ISWA may be to improve national and international professional networks between academia and business, thereby making education, research and innovation the key driving mechanisms in

Waste management research abstracts No. 17

International Nuclear Information System (INIS)

1986-11-01

The research data sheets contained in this issue have been collected during the period ending August 1986, and reflect research currently in progress in the field of radioactive waste management. This publication covers a wide range of programmes in the IAEA Member States. Abstracts intended for inclusion in this publication were submitted in the English, French, Russian or Spanish language

Experience and related research and development in applying corrective measures at the major low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Rose, R.R.; Mahathy, J.M.; Epler, J.S.; Boing, L.E.; Jacobs, D.G.

1983-07-01

A review was conducted of experience in responding to problems encountered in shallow land burial of low-level radioactive waste and in research and development related to these problems. The operating histories of eleven major disposal facilities were examined. Based on the review, it was apparent that the most effective corrective measures administered were those developed from an understanding of the site conditions which caused the problems. Accordingly, the information in this document has been organized around the major conditions which have caused problems at existing sites. These include: (1) unstable trench cover, (2) permeable trench cover, (3) subsidence, (4) ground water entering trenches, (5) intrusion by deep-rooted plants, (6) intrusion by burrowing animals, and (7) chemical and physical conditions in trench. Because the burial sites are located in regions that differ in climatologic, geologic, hydrologic, and biologic characteristics, there is variation in the severity of problems among the sites and in the nature of information concerning corrective efforts. Conditions associated with water-related problems have received a great deal of attention. For these, corrective measures have ranged from the creation of diversion systems for reducing the contact of surface water with the trench cover to the installation of seals designed to prevent infiltration from reaching the buried waste. On the other hand, corrective measures for conditions of subsidence or of intrusion by burrowing animals have had limited application and are currently under evaluation or are subjects of research and development activities. 50 references, 20 figures, 10 tables

RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-09-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another new

RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

International Nuclear Information System (INIS)

2004-09-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another new

Waste dumps in local communities in developing countries and hidden danger to health.

Science.gov (United States)

Anetor, Gloria O

2016-07-01

The rapid industrialisation and urbanisation fuelled by a fast-growing population has led to the generation of a huge amount of waste in most communities in developing countries. The hidden disorders and health dangers in waste dumps are often ignored. The waste generated in local communities is usually of a mixed type consisting of domestic waste and waste from small-scale industrial activities. Among these wastes are toxic metals, lead (Pb), cadmium (Cd), arsenic (As), mercury (Hg), halogenated organic compounds, plastics, remnants of paints that are themselves mixtures of hazardous substances, hydrocarbons and petroleum product-contaminated devices. Therefore, there is the urgent need to create an awareness of the harmful health effect of toxic wastes in developing countries, especially Nigeria. This is a review aimed at creating awareness on the hidden dangers of waste dumps to health in local communities in developing countries. Many publications in standard outlets use the following keywords: cancer, chemical toxicity, modern environmental health hazards, waste management and waste speciation in PubMed, ISI, Toxbase environmental digest, related base journals, and some standard textbooks, as well as the observation of the researcher between 1959 and 2014. Studies revealed the preponderance of toxic chemicals such as Pb, Cd, As and Hg in dump sites that have the risk of entering food chain and groundwater supplies, and these can give rise to endemic malnutrition and may also increase susceptibility to mutagenic substances, thereby increasing the incidence of cancer in developing countries. Industrialisation and urbanisation have brought about a change in the waste that is generated in contemporary communities in developing countries. Therefore, there is the need to embrace speciation and sound management of waste, probably including bioremediation. The populations in the local communities need regulatory agencies who are health educators as positive change

Development of a comprehensive radioactive waste classification system

International Nuclear Information System (INIS)

Smith, C.F.; Cohen, J.J.

1989-01-01

Several previous studies have been conducted with the intent of developing a rational system for classification of radioactive wastes. Although none of the proposed systems has gained general acceptance, certain waste classes, specifically high-level waste and low-level waste suitable for shallow land burial have been essentially defined by regulation. Wastes which remain undefined include: those intermediate level wastes which require more restrictive controls than that provided by shallow land burial but not the high degree of isolation needed for high level wastes, and wastes below regulatory concern (BRC) which entail so low a radiological risk that they can be managed according to their nonradiological properties. This study has developed a framework within which the complete spectrum of radioactive wastes can be defined

Development of the inventory for existing and future radioactive wastes in Switzerland. ISRAM and MIRAM

International Nuclear Information System (INIS)

Maxeiner, Harald; Vespa, Marika; Volmert, Ben; Pantelias, Manuel; Caruso, Stefano; Mueller, Tom

2013-01-01

Radioactive waste in Switzerland arises from the 5 nuclear power plants and from the use of radioactive materials in medicine, industry and research. The waste has to be conditioned for interim storage and later deep geological disposal, which requires extensive research and development work. The production of waste packages is supported by quality assurance checks and characterisation and inventorying programmes. The management of all produced waste packages together with the associated key data is done with the computer-based 'Information System for Radioactive Materials (ISRAM)'. This also ensures complete tracking of all existing waste packages from their production to their final disposal in a deep geological repository. For planning purposes and for design studies for the planned repositories in Switzerland, waste that will arise in the future also has to be taken into consideration. Using ISRAM as a basis, a 'Model Inventory for Radioactive Materials (MIRAM)' was also developed; this contains all the key data required for safety analysis and facility planning. Together, these tools (ISRAM und MIRAM) form the basis for complete and comprehensive documentation and tracking of radioactive wastes up to the time of their geological disposal. (orig.)

Waste into Fuel—Catalyst and Process Development for MSW Valorisation

Directory of Open Access Journals (Sweden)

Izabela S. Pieta

2018-03-01

Full Text Available The present review paper highlights recent progress in the processing of potential municipal solid waste (MSW derived fuels. These wastes come from the sieved fraction (∅ < 40 mm, which, after sorting, can differ in biodegradable fraction content ranging from 5–60%. The fuels obtained from these wastes possess volumetric energy densities in the range of 15.6–26.8 MJL−1 and are composed mainly of methanol, ethanol, butanol, and carboxylic acids. Although these waste streams are a cheap and abundant source (and decrease the fraction going to landfills, syngas produced from MSW contains various impurities such as organic compounds, nitrogen oxides, sulfur, and chlorine components. These limit its use for advanced electricity generation especially for heat and power generation units based on high temperature fuel cells such as solid oxide fuel cells (SOFC or molten carbonate fuel cells (MCFC. In this paper, we review recent research developments in the continuous MSW processing for syngas production specifically concentrating on dry reforming and the catalytic sorbent effects on effluent and process efficiency. A particular emphasis is placed on waste derived biofuels, which are currently a primary candidate for a sustainable biofuel of tomorrow, catalysts/catalytic sorbents with decreased amounts of noble metals, their long term activity, and poison resistance, and novel nano-sorbent materials. In this review, future prospects for waste to fuels or chemicals and the needed research to further process technologies are discussed.

Handling e-waste in developed and developing countries: Initiatives, practices, and consequences

Energy Technology Data Exchange (ETDEWEB)

Sthiannopkao, Suthipong, E-mail: suthisuthi@gmail.com [Department of Environmental Engineering, College of Engineering, Dong-A University, 37 Nakdong-Daero 550 beon-gil Saha-gu, Busan (Korea, Republic of); Wong, Ming Hung [Croucher Institute for Environmental Sciences, Hong Kong Baptist University, Hong Kong (China)

2013-10-01

Discarded electronic goods contain a range of toxic materials requiring special handling. Developed countries have conventions, directives, and laws to regulate their disposal, most based on extended producer responsibility. Manufacturers take back items collected by retailers and local governments for safe destruction or recovery of materials. Compliance, however, is difficult to assure, and frequently runs against economic incentives. The expense of proper disposal leads to the shipment of large amounts of e-waste to China, India, Pakistan, Nigeria, and other developing countries. Shipment is often through middlemen, and under tariff classifications that make quantities difficult to assess. There, despite the intents of national regulations and hazardous waste laws, most e-waste is treated as general refuse, or crudely processed, often by burning or acid baths, with recovery of only a few materials of value. As dioxins, furans, and heavy metals are released, harm to the environment, workers, and area residents is inevitable. The faster growth of e-waste generated in the developing than in the developed world presages continued expansion of a pervasive and inexpensive informal processing sector, efficient in its own way, but inherently hazard-ridden. - Highlights: ► Much e-waste, expensive to process safely, illegally goes to developing countries. ► E-waste processing in developing countries pollutes with heavy metals and dioxins. ► Well-conceived developing world waste regulations lack enforceability. ► Crude e-waste processing cannot recover several rare materials. ► The amount of e-waste unsafely processed will continue to grow.

Handling e-waste in developed and developing countries: Initiatives, practices, and consequences

International Nuclear Information System (INIS)

Sthiannopkao, Suthipong; Wong, Ming Hung

2013-01-01

Discarded electronic goods contain a range of toxic materials requiring special handling. Developed countries have conventions, directives, and laws to regulate their disposal, most based on extended producer responsibility. Manufacturers take back items collected by retailers and local governments for safe destruction or recovery of materials. Compliance, however, is difficult to assure, and frequently runs against economic incentives. The expense of proper disposal leads to the shipment of large amounts of e-waste to China, India, Pakistan, Nigeria, and other developing countries. Shipment is often through middlemen, and under tariff classifications that make quantities difficult to assess. There, despite the intents of national regulations and hazardous waste laws, most e-waste is treated as general refuse, or crudely processed, often by burning or acid baths, with recovery of only a few materials of value. As dioxins, furans, and heavy metals are released, harm to the environment, workers, and area residents is inevitable. The faster growth of e-waste generated in the developing than in the developed world presages continued expansion of a pervasive and inexpensive informal processing sector, efficient in its own way, but inherently hazard-ridden. - Highlights: ► Much e-waste, expensive to process safely, illegally goes to developing countries. ► E-waste processing in developing countries pollutes with heavy metals and dioxins. ► Well-conceived developing world waste regulations lack enforceability. ► Crude e-waste processing cannot recover several rare materials. ► The amount of e-waste unsafely processed will continue to grow

R and D developments on the disposal of radioactive wastes recently carried out at CEA (France)

International Nuclear Information System (INIS)

Petit, J.C.

1993-01-01

Since the law of december 31, 1991 voted by the French Parliament, disposal in geological formations is not the sole option considered for the management of radioactive wastes. Scientists and engineers, notably within the 'Commissariat a l'Energie Atomique' (CEA), must investigate in parallel two other options, namely i. advanced separation of long-lived radioisotopes and transmutation, and ii. improvement of radioactive waste matrices and long-term storage. Still, the geological disposal of radioactive wastes, which has generated within the last decade an immense amount of Research and Development, remains a major proposed solution to the long-term management of transuranic and high-level wastes. In this paper, we will describe some of the Research and Development carried out within CEA, avoiding the industrial and engineering aspects of the issues dealt with. Rather, we will illustrate major points of our basic research, underlining in particular methodological considerations

Developing technologies for conditioning the liquid organic radioactive wastes from Cernavoda NPP

International Nuclear Information System (INIS)

Deneanu, N.; Popescu, I. V.; Teoreanu, I.

2004-01-01

The Institute for Nuclear Research (INR)-Pitesti has developed technologies for conditioning liquid organic radioactive wastes (oils, miscellaneous solvent and liquid scintillation cocktail) for Cernavoda NPP. This paper describes the new and viable solidification technology to convert liquid organic radioactive wastes into a stable monolithic form, which minimizes the probability to release tritium in the environment during interim storage, transportation and final disposal. These are normally LLW containing only relatively small quantities of beta/gamma emitting radionuclides and variable amounts of tritium with activity below E+08Bq/l. The INR research staff in the radwaste area developed treatment/conditioning techniques and also designed and tested the containers for the final disposal, following the approach in the management of radwaste related to the nuclear fuel cycle. Thus, the INR focused this type of activity on treating and conditioning the wastes generated at Cernavoda Nuclear Power Plant consisting of lubricants from primary fuelling machines and turbine, the miscellaneous solvent from decontamination operation and the liquid scintillation cocktail used in radiochemical analysis. Laboratory studies on cementation of liquid organic radioactive wastes have been undertaken at INR Pitesti. One simple system, similar to a conventional cement solidification unit, can treat radioactive liquid wastes, which are the major components of low- and medium-level radioactive wastes generated by a Nuclear Power Plant. It was proved that the solidified waste could meet the Waste Acceptance Criteria of the disposal site, in this case Baita-Bihor National Repository, as follows: - The wastes are deposited in type A packages; - The maximum expected quantities of this waste stream that will be produced in the future are 50 drums per year. The maximum specific tritium activity per drum is 10 9 Bq/m 3 ; - Compressive strengths of the samples should be greater than 50 MPa

Research Priorities on the Relationship between Wasting and Stunting.

Directory of Open Access Journals (Sweden)

Chloe Angood

Full Text Available Wasting and stunting are global public health problems that frequently co-exist. However, they are usually separated in terms of policy, guidance, programming and financing. Though both wasting and stunting are manifestations of undernutrition caused by disease and poor diet, there are critical gaps in our understanding of the physiological relationship between them, and how interventions for one may affect the other. The aim of this exercise was to establish research priorities in the relationships between wasting and stunting to guide future research investments.We used the CHNRI (Child Health and Nutrition Research Initiative methodology for setting research priorities in health. We utilised a group of experts in nutrition, growth and child health to prioritise 30 research questions against three criteria (answerability, usefulness and impact using an online survey. Eighteen of 25 (72% experts took part and prioritised research directly related to programming, particularly at the public health level. The highest-rated questions were: "Can interventions outside of the 1000 days, e.g. pre-school, school age and adolescence, lead to catch-up in height and in other developmental markers?"; "What timely interventions work to mitigate seasonal peaks in both wasting and stunting?"; and "What is the optimal formulation of ready-to-use foods to promote optimal ponderal growth and also support linear growth during and after recovery from severe acute malnutrition?" There was a high level of agreement between experts, particularly for the highest ranking questions.Increased commitment to rigorous evaluations of treatment and prevention interventions at the public health level, addressing questions of the timing of intervention, and the extent to which impacts for both wasting and stunting can be achieved, is needed to inform global efforts to tackle undernutrition and its consequences.

Vitrification development for mixed wastes

International Nuclear Information System (INIS)

Merrill, R.; Whittington, K.; Peters, R.

1995-02-01

Vitrification is a promising approach to waste-form immobilization. It destroys hazardous organic compounds and produces a durable and highly stable glass. Vitrification tests were performed on three surrogate wastes during fiscal year 1994; 183-H Solar Evaporation Basin waste from Hanford, bottom ash from the Oak Ridge TSCA incinerator, and saltcrete from Rocky Flats. Preliminary glass development involved melting trials followed by visual homogeneity examination, short-duration leach tests on glass specimens, and long-term leach tests on selected glasses. Viscosity and electrical conductivity measurements were taken for the most durable glass formulations. Results for the saltcrete are presented in this paper and demonstrate the applicability of vitrification technology to this mixed waste

What we do | Page 90 | IDRC - International Development Research ...

International Development Research Centre (IDRC) Digital Library (Canada)

Results 891 - 900 of 1605 ... IDRC funds research in developing countries to create lasting ... Urban agriculture ... Carbon Market and Integrated Waste Solutions : a Case Study of Indonesia ... Region(s): Asia, China, Far East Asia, India, South and Central Asia ... Topic(s): RESEARCH NETWORKS, RESEARCH METHODS, ...

Multiparameter optimisation of dismantling activities and waste management at a research centre

International Nuclear Information System (INIS)

Andres, Roger

2001-01-01

Full text: The Paul Scherrer Institute (PSI) is a multi-disciplinary research centre for natural sciences and technology. The institute is active in solid-state physics, materials sciences, elementary particle physics, life sciences, nuclear and non-nuclear energy research, and energy-related ecology. PSI develops and operates complex research installations such as nuclear reactors and particle accelerators. These produce ionising radiation and major quantities of radioactive materials. The optimal handling of decommissioning and dismantling projects and radioactive waste treatment at PSI represents a complex management task, and is determined by many parameters that are only partially identical to those in the energy producing industry. Some of the major issues are addressed below. Management: The research community often requires rapid changes of experimental equipment. This necessitates that the four steps of decommissioning, removal, dismantling and conditioning of waste are spatially and temporally separated. The availability of a great scientific knowledge pool is instrumental for innovative solutions for the complex problems encountered. The accessibility of a modem hardware park (instruments, workshops etc.), sophisticated computer systems and modelling know how can facilitate the work considerably. The lack of a dedicated pool of decommissioning funds and the need for rapid response (see above) necessitate flexibility of the decommissioning crew and constant coordination and optimisation of the work packages with the institute's top management. The product of a research centre in general is not a tradable commodity and does not result in a direct return of money. Financial mechanisms such as the accumulation of funds for future liabilities are not an option. Since PSI - as probably most research institutes - is funded on a yearly basis, long term cost optimisations processes are in competition with legitimate short-term research needs. The benefits of

Nuclear Waste Separation and Transmutation Research with Special Focus on Russian Transmutation Projects Sponsored by ISTC

International Nuclear Information System (INIS)

Conde, Henri; Blomgren, Jan; Olsson, Nils

2003-03-01

High-level nuclear reactor waste is made up of relatively few long-lived radioactive species, among them plutonium, that contribute to difficulties with its storage and disposal. Separation of these species from larger waste volumes mainly constituting of uranium (about 95 %) coupled with nuclear incineration to fission products of plutonium and the so called minor actinides (Neptunium, Americium, and Curium) and transmutation of some of the long lived fission products to short lived or stable isotopes represents a viable nuclear waste management strategy to drastically reduce the time and space requirements for a bed-rock repository of the remaining waste. A remarkable increase in the international research and development on partitioning and transmutation has occurred during the recent years. The road-map report published in April 2001 by The European Technical Working Group on ADS for the development of a European demonstration facility for nuclear waste transmutation has high-lighted the ongoing European research and pointed out the need for further research. The road-map has given the different research activities a position in the ultimate goal of producing an ADS demonstrator and is guiding research planning on the national as well as on the EU level. The Advanced Accelerator Application (3A) program in the US, with the long term goals to enhance long term public safety, provide benefits for the repository, reduce proliferation risks and improve prospects for nuclear power has focused the research on nuclear waste transmutation. The reports on the 3A program indicates a change of the US former abandonment position towards reprocessing and fast reactors due to a strong incentive to eliminate the reactor plutonium and to lower the amount of high level reactor waste for the Yucca Mountain repository. The SKB's proposed research and development program for the next 3 years (FUD01) was presented by SKB in September 2001. It is proposed that the research program

Focus on CSIR research in pollution and waste: Integrated waste management

CSIR Research Space (South Africa)

Godfrey, Linda K

2007-08-01

Full Text Available Research into integrated waste management is undertaken in view of the impact of increasing populations and a strong national focus on industrial, agricultural and urban growth that is likely to result in the increase of human induced pressures...

Nuclear waste repository research at the micro- to nanoscale

Science.gov (United States)

Schäfer, T.; Denecke, M. A.

2010-04-01

Micro- and nano-focused synchrotron radiation techniques to investigate determinant processes in contaminant transport in geological media are becoming especially an increasingly used tool in nuclear waste disposal research. There are a number of reasons for this but primarily they are driven by the need to characterize actinide speciation localized in components of heterogeneous natural systems. We summarize some of the recent research conducted by researchers of the Institute of Nuclear Waste Disposal (INE) at the Karlsruhe Institute of Technology using micro- and nano-focused X-ray beams for characterization of colloids and their interaction with minerals and of elemental and phase distributions in potential repository host rocks and actinide speciation in a repository natural analogues sample. Such investigations are prerequisite to ensuring reliable assessment of the long term radiological safety for proposed nuclear waste disposal sites.

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.)

Nuclear fuel cycle waste recycling technology deverlopment - Radioactive metal waste recycling technology development

International Nuclear Information System (INIS)

Oh, Won Zin; Moon, Jei Kwon; Jung, Chong Hun; Park, Sang Yoon

1998-08-01

With relation to recycling of the radioactive metal wastes which are generated during operation and decommissioning of nuclear facilities, the following were described in this report. 1. Analysis of the state of the art on the radioactive metal waste recycling technologies. 2. Economical assessment on the radioactive metal waste recycling. 3. Process development for radioactive metal waste recycling, A. Decontamination technologies for radioactive metal waste recycling. B. Decontamination waste treatment technologies, C. Residual radioactivity evaluation technologies. (author). 238 refs., 60 tabs., 79 figs

New developments in low level radioactive waste management in Spain

International Nuclear Information System (INIS)

Zuloaga, P.

2006-01-01

El Cabril disposal facility was commissioned in 1992 and is a key element in LILW Management in Spain. It is a vault-type surface disposal facility with a total internal volume of 100,000 m 3 . The installation also has facilities for waste treatment and conditioning, verification and characterisation, interim storage and other ancillary equipment. This paper includes a brief description of the facility, the operational experience, the design improvements and new developments in waste acceptance procedures, safety assessment and the related research programme. The paper also refers to the new disposal facility intended for very low activity waste, under construction at the same site. This facility, a part of El Cabril nuclear installation, will have a maximum capacity for 130,000 m 3 of very low activity waste. Its construction started in February 2006, after the evaluation of the nuclear safety authority and the environmental impact statement procedure. (author)

Dismantling and waste management: CEA's strategy and research programs

International Nuclear Information System (INIS)

Behar, C.

2012-01-01

There are 3 main dismantling operations in CEA. First, the dismantling of the UP1 facility in the Marcoule site. UP1 was a reprocessing plant of nuclear fuels that operated from 1958 to 1997 and is now the biggest dismantling operation in the world. Its dismantling operation follows a 6-step scheme that will end in 2050. Secondly, the Passage project on the Grenoble site that concerns the dismantling of 3 research reactors (Siloette, Melusine and Siloe), of a laboratory dedicated to the analysis of active materials (Lama) and of a station for the processing of waste (Sted). Thirdly the Aladin project that concerns the installations of the Fontenay-aux-Roses site. The dismantling operations are complex because all the first research programs on high activity chemistry and on transuranium elements were performed in Fontenay-aux-Roses facilities and because ancient activities have to leave a clean place to be replaced by new ones. The radioactive waste produced by CEA enter the flow of waste that is normally processed and managed by ANDRA. Only high-activities waste have not yet a definitive solution, they are stored in waiting the opening of a geological repository. CEA leads research programs on the separation and transmutation of minor actinides and on the long-term behaviour of waste packages put in deep geological layers. (A.C.)

Karlsruhe Nuclear Research Center. Research and development program 1992

International Nuclear Information System (INIS)

1991-01-01

The KfK R and D activities are classified by ten point-of-main-effort projects: 1) low-pollution/low-waste methods, 2) environmental energy and mass transfers, 3) nuclear fusion, 4) nuclear saftey research, 5) radioactive waste management, 6) superconduction, 7) microtechnics, 8) materials handling, 9) materials and interfaces, 10) basic physical research. (orig.) [de

Research and development plans for disposal of high-level and transuranic wastes

International Nuclear Information System (INIS)

Bartlett, J.W.; Platt, A.M.

1978-09-01

This plan recommends a 20-year, 206 million (1975 $'s) R and D program on geologic structures in the contiguous U.S. and on the midplate Pacific seabed with the objective of developing an acceptable method for disposal of commercial high-level and transuranic wastes by 1997. No differentiation between high-level and transuranic waste disposal is made in the first 5 years of the program. A unique application of probability theory to R and D planning establishes, at a 95% confidence level, that the program objective will be met if at least fifteen generic options and five specific disposal sites are explored in detail and at least two pilot plants are constructed and operated. A parallel effort on analysis and evaluation maximizes information available for decisions on the acceptability of the disposal techniques. Based on considerations of technical feasibility, timing and technical risk, the other disposal concepts, e.g., ice sheets, partitioning, transmutation and space disposal cited in BNWL-1900 are not recommended for near future R and D

Solid Waste Management In Kosova

OpenAIRE

, F. Tahiri; , A. Maçi; , V. Tahiri; , K. Tahiri

2016-01-01

Waste management accordingly from concept and practices that are used in different countries there are differences, particularly between developed and developing countries. Our country takes part in the context of small developing countries where waste management right is almost at the beginning. In order to have better knowledge about waste management in Kosovo is done a research. The research has included the institutions that are responsible for waste management, including central and loca...

Talking Trash: Bringing Research into Action while Reducing Household Solid Waste

Science.gov (United States)

O'Connell, Elizabeth J.

2012-01-01

This dissertation was an exploration of how changing the waste system is a necessary part of achieving sustainable human systems and how transforming consumer attitudes towards waste is a vital piece of sustainable waste management. This research was also an exploration of the attitudes and beliefs that promote and prohibit waste reduction…

Development of radiometric methods for radioactive waste characterization

International Nuclear Information System (INIS)

Tessaro, Ana Paula Gimenes

2015-01-01

The admission of radioactive waste in a final repository depends among other things on the knowledge of the radioisotopic inventory of the waste. To obtain this information it is necessary make the primary characterization of the waste so that it is composition is known, to guide the next steps of radioactive waste management. Filter cartridges that are used in the water polishing system of IEA-R1 research reactor is one of these wastes. The IEA-R1 is a pool-type research reactor, operating between 2 and 5 MW that uses water as coolant, moderator and biological shield. Besides research, it is used for production of radioisotopes and irradiation of samples with neutron and gamma beams. It is located in the Nuclear and Energy Research Institute at the University of Sao Paulo campus. The filter cartridges are used to retain particles that are suspended in the cooling water. When filters become saturated and are unable to maintain the flow within the established limits, they are replaced and disposed of as radioactive waste. After a period of decay, they are sent to the Radioactive Waste Management Department. The aim of this work is to present the studies to determine the activity of gamma emitters present in the cartridge filters. The activities were calculated using the dose rates measured with hand held detectors, after the ratios of the emission rates of photons were evaluated by gamma spectrometry, by the Point Kernel method, which correlates the activity of a source with dose rates at various distances. The method described can be used to determine routinely the radioactive inventory of these filters, avoiding the necessity of destructive radiochemical analysis, or the necessity of calibrating the geometry of measurement. (author)

Waste biorefineries: Enabling circular economies in developing countries.

Science.gov (United States)

Nizami, A S; Rehan, M; Waqas, M; Naqvi, M; Ouda, O K M; Shahzad, K; Miandad, R; Khan, M Z; Syamsiro, M; Ismail, I M I; Pant, Deepak

2017-10-01

This paper aims to examine the potential of waste biorefineries in developing countries as a solution to current waste disposal problems and as facilities to produce fuels, power, heat, and value-added products. The waste in developing countries represents a significant source of biomass, recycled materials, chemicals, energy, and revenue if wisely managed and used as a potential feedstock in various biorefinery technologies such as fermentation, anaerobic digestion (AD), pyrolysis, incineration, and gasification. However, the selection or integration of biorefinery technologies in any developing country should be based on its waste characterization. Waste biorefineries if developed in developing countries could provide energy generation, land savings, new businesses and consequent job creation, savings of landfills costs, GHG emissions reduction, and savings of natural resources of land, soil, and groundwater. The challenges in route to successful implementation of biorefinery concept in the developing countries are also presented using life cycle assessment (LCA) studies. Copyright © 2017 Elsevier Ltd. All rights reserved.

Progress report on research and development work 1991 of the Department of Hot Chemistry, Karlsruhe Nuclear Research Center

International Nuclear Information System (INIS)

1991-03-01

In the year under review, the Institute of Hot Chemistry (IHCH) was in the midst of a thematic reorientation process. The priority of future chemical-technical work will be in the field of the development of supercriticality processes. The objective of such work consists in seeking new ways for getting rid of resistant chemical pollutants (halogenated organic compounds). The following projects are presented in detail: 1) Waste control in the environment (communal waste management; water and soil; emission-reducing processes; highly polluted soils); 2) Solid state and materials research (chemistry of materials research); basic physical research (neutrino and particle physics); 3) Nuclear waste management (concluding work on reprocessing technology), and 4) Other research projects (Institute-related research). The Annex lists the publications made by the IHCH staff. (BBR) [de

Publicly administrated nuclear waste management research programme 1994-1996. General plan for the research programme and research plan for 1994

International Nuclear Information System (INIS)

1994-01-01

The nuclear energy legislation of Finland includes detailed stipulations concerning nuclear waste management. Each producer of nuclear waste is responsible for the safe handling, management and disposal of the waste, and for the financing of these operations. The authorities supervise and control the implementation of the national waste management programme and set the necessary safety and other requirements. The principal goal of the JYT programme is to provide the authorities with information and research results relevant for the safety of nuclear waste management in order to support the various activities of the authorities. The whole field of the research programme is subdivided into the following main topic areas: (1) bedrock structure and stability, rock investigation methods, and characteristics and flow of groundwater, (2) release of radionuclides from a repository and subsequent migration in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management (4) natural analogue studies, (5) waste management technology and costs and (6) sociopolitical and other societal issues and environmental impact assessment

The Research Results of Radioactive Waste Management Technology Center Year 1997/1998

International Nuclear Information System (INIS)

1998-12-01

The research results of Radioactive Waste Management Technology Center, National Atomic Energy Agency of Indonesia year 1997/1998 contain paper as form of research results on radioactive waste management related fields. There were included many aspects such as radioactive waste processing, storage, decontamination, decommissioning, safety and environmental aspects. There are 26 papers indexed individually (ID)

Palm Oil Milling Wastes and Sustainable Development

OpenAIRE

A. C. Er; Abd. R.M. Nor; Katiman Rostam

2011-01-01

Problem statement: Palm oil milling generates solid wastes, effluent and gaseous emissions. The aim of this study is to assess the progress made in waste management by the Malaysian palm oil milling sector towards the path of sustainable development. Sustainable development is defined as the utilization of renewable resources in harmony with ecological systems. Inclusive in this definition is the transition from low value-added to higher value-added transformation of waste...

Low-level radioactive waste management technology development

International Nuclear Information System (INIS)

Coleman, J.A.

1985-01-01

Although reviews of disposal practices and site performance indicated that there were no releases to the environment that would affect public health and safety, it became clear that: (a) several burial grounds were not performing as expected; (b) long-term maintenance of closed trenches could be a costly problem, and (c) more cost-effective methods could be developed for the treatment, packing, and disposal of low-level waste. As a result of these reviews, the Department of Energy developed the Low-level Waste Management Program to seek improvements in existing practices, correct obvious deficiencies, and develop site closure techniques that would avoid expensive long-term maintenance and monitoring. Such technology developments provide a better understanding of the physical and technical mechanisms governing low-level waste treatment and disposal and lead to improvement in the performance of disposal sites. The primary means of disposal of low-level waste has been the accepted and regulated practice of shallow land disposal, i.e., placement of low-level waste in trenches 5 to 10 meters deep with several meters of special soil cover. Department of Energy waste is primarily disposed at six major shallow land disposal sites. Commercial waste is currently disposed of at three major sites in the nation - Barnwell, South Carolina; Richland, Washington; and Beatty, Nevada. In the late 1970's public concern arose regarding the management practices of sites operated by the civilian sector and by the Department of Energy

U.S. advanced accelerator applications program: plans to develop and test waste transmutation technologies

International Nuclear Information System (INIS)

Van Tuyle, G.; Bennett, D.; Arthur, E.; Cappiello, M.; Finck, P.; Hill, D.; Herczeg, J.; Goldner, F.

2001-01-01

The primary mission of the U.S. Advanced Accelerator Applications (AAA) Program is to establish a national nuclear technology research capability that can demonstrate accelerator-based transmutation of waste and conduct transmutation research while at the same time providing a capability for the production of tritium if required. The AAA Program was created during fiscal year 2001 from the Accelerator Transmutation of Waste (ATW) Program and the Accelerator Production of Tritium (APT) Project. This paper describes the new AAA Program, as well as its two major components: development and testing of waste transmutation technologies and construction of an integrated accelerator-driven test facility (ADTF). (author)

Development of TRU waste mobile analysis methods for RCRA-regulated metals

International Nuclear Information System (INIS)

Mahan, C.A.; Villarreal, R.; Drake, L.; Figg, D.; Wayne, D.; Goldstein, S.

1998-01-01

This is the final report of a one-year, Laboratory Directed Research and Development (LDRD) project at Los Alamos National Laboratory (LANL). Glow-discharge mass spectrometry (GD-MS), laser-induced breakdown spectroscopy (LIBS), dc-arc atomic-emission spectroscopy (DC-ARC-AES), laser-ablation inductively-coupled-plasma mass spectrometry (LA-ICP-MS), and energy-dispersive x-ray fluorescence (EDXRF) were identified as potential solid-sample analytical techniques for mobile characterization of TRU waste. Each technology developers was provided with surrogate TRU waste samples in order to develop an analytical method. Following successful development of the analytical method, five performance evaluation samples were distributed to each of the researchers in a blind round-robin format. Results of the round robin were compared to known values and Transuranic Waste Characterization Program (TWCP) data quality objectives. Only two techniques, DC-ARC-AES and EDXRF, were able to complete the entire project. Methods development for GD-MS and LA-ICP-MS was halted due to the stand-down at the CMR facility. Results of the round-robin analysis are given for the EDXRF and DCARC-AES techniques. While DC-ARC-AES met several of the data quality objectives, the performance of the EDXRF technique by far surpassed the DC-ARC-AES technique. EDXRF is a simple, rugged, field portable instrument that appears to hold great promise for mobile characterization of TRU waste. The performance of this technique needs to be tested on real TRU samples in order to assess interferences from actinide constituents. In addition, mercury and beryllium analysis will require another analytical technique because the EDXRF method failed to meet the TWCP data quality objectives. Mercury analysis is easily accomplished on solid samples by cold vapor atomic fluorescence (CVAFS). Beryllium can be analyzed by any of a variety of emission techniques

RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-09-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another

The Research Results of Radioactive Waste Management Technology Center Year 1996/1997

International Nuclear Information System (INIS)

Budiman, P.; Martono, H.; Las, T.; Lubis, E.; Mulyanto; Wisnubroto, D. S.; Sucipta

1997-12-01

The research results of Radioactive Waste Management Technology Center, National Atomic Energy Agency of Indonesia year 1996/1997 contain paper as form of research results on radioactive waste management related fields. There were included many aspects such as radioactive waste processing, storage, decontamination, decommissioning, safety and environmental aspects. There are 24 papers and 12 short communications indexed individually(ID)

Annual plan of research on safety techniques against low level radioactive wastes, 1984-1988

International Nuclear Information System (INIS)

1984-01-01

The establishment of the countermeasures for treating and disposing radioactive wastes has become an important subject for promoting the utilization of atomic energy. Especially as to low level radioactive wastes, the cumulative quantity has reached about 460,000 in terms of 200 l drums as of the end of March, 1983, and accompanying the development of the utilization of atomic energy, its rapid increase is expected. So far, as for the disposal of low level radioactive wastes, the research and development and the preparation of safety criteria and safety evaluation techniques have been carried out, following the basic policy of the Atomic Energy Commission to execute land disposal and ocean disposal in combination, first to make the test disposal after preliminary safety evaluation, and to shift to the full scale disposal based on the results. The annual plan was decided on July 22, 1983, and the first revision was carried out this time, therefore, it is reported here. The basic policy of establishing this annual plan, and the annual plan for safety technique research are described. (Kako, I.)

Healthcare waste management practice in the West Black Sea Region, Turkey: A comparative analysis with the developed and developing countries.

Science.gov (United States)

Ciplak, Nesli; Kaskun, Songul

2015-12-01

The need for proper healthcare waste management has been a crucial issue in many developing countries as it is in Turkey. The regulation regarding healthcare wastes in Turkey was updated in 2005 in accordance with the European Union (EU) waste directives, but it still falls behind meeting the requirements of current waste treatment technologies. Therefore, this study aims to reveal deficiencies, inconsistencies, and improper applications of healthcare waste management in the western part of the Turkish Black Sea Region. In this study, it was revealed that nearly 1 million people live in the region, resulting in 5 million hospital admissions annually. All the healthcare waste produced (1000 tons yr(-1)) is treated in an autoclave plant. However, treating some categories of healthcare wastes in autoclave units mismatches with the EU waste regulations, as alternative treatment technologies are not technically able to treat all types of healthcare wastes. A proper waste management system, therefore, requires an internal segregation scheme to divert these wastes from the main healthcare waste stream. The existing malpractice in the region could cause serious health problems if no measure is taken urgently. It is expected that healthcare waste management in the region and then all across Turkey will be improved with the significant deficiencies and inconsistencies pointed out in this research. In developed countries, specific rules and regulations have already been implemented along with the recommendations for handling of healthcare waste. However, in Turkey, these wastes are treated in autoclave units, which mismatches with the European Union waste regulations, as alternative treatment technologies are not technically capable to treat all types of healthcare wastes. The existing malpractice could cause serious health problems if no measure is taken urgently. The authors demonstrated the existing status of Turkish waste management and revealed deficiencies

Waste management research abstracts no. 22. Information on radioactive waste programmes in progress

International Nuclear Information System (INIS)

1995-07-01

The research abstracts contained in this issue have been collected during recent months and cover the period between January 1992 - February 1994 (through July 1994 for abstracts from the United States). The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. Though the information contained in this publication covers a wide range of programmes in many countries, the WMRA should not be interpreted as providing a complete survey of on-going research and IAEA Member States. For the first time, the abstracts published in document are only in English language. In addition, the abstracts received for this issue have been assigned INIS subject category codes and thesaurus terms to facilitate searches and also to fully utilize established sets of technical categories and terms

Improved low-level radioactive waste management practices for hospitals and research institutions

International Nuclear Information System (INIS)

1983-07-01

This report provides a general overview and a compendium of source material on low-level radioactive waste management practices in the institutional sector. Institutional sector refers to hospitals, universities, clinics, and research facilities that use radioactive materials in scientific research and the practice of medicine, and the manufacturers of radiopharmaceuticals and radiography devices. This report provides information on effective waste management practices for institutional waste to state policymakers, regulatory agency officials, and waste generators. It is not intended to be a handbook for actual waste management, but rather a sourcebook of general information, as well as a survey of the more detailed analysis

Researches on nuclear wastes. Knowledge gained and perspectives at the 2006 date line

International Nuclear Information System (INIS)

2006-01-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. The responsibility of these researches is given to the French atomic energy commission (CEA) and to the national agency for radioactive wastes (ANDRA) who have to coordinate their works with other research organizations and industrialists. The aim of this colloquium is to make a status of the scientific knowledge gained before the implementation of the public and parliamentary debates on nuclear wastes management. This document gathers the presentations (slides) given at the colloquium and dealing with: separation/transmutation, storage and conditioning of waste packages; geologic disposal, the inter-disciplinary PACE program of the CNRS; synthesis of the researches evaluation process; general principles for a sustainable management of radioactive wastes; technical experience implemented by industrialists since 15 years; point of view of the nuclear safety authority; international context of nuclear waste management and related researches; a sociological enlightening: researches advance as seen by the public. (J.S.)

Hanford Tank Waste Treatment and Immobilization Plant (WTP) Waste Feed Qualification Program Development Approach - 13114

Energy Technology Data Exchange (ETDEWEB)

Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G. [Hanford Tank Waste Treatment and Immobilization Plant Project, Richland, WA 99354 (United States); Adamson, Duane J.; Herman, Connie C.; Peeler, David K. [Savannah River National Laboratory, Aiken, SC 29808 (United States)

2013-07-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a nuclear waste treatment facility being designed and constructed for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (under contract DE-AC27-01RV14136 [1]) to process and vitrify radioactive waste that is currently stored in underground tanks at the Hanford Site. A wide range of planning is in progress to prepare for safe start-up, commissioning, and operation. The waste feed qualification program is being developed to protect the WTP design, safety basis, and technical basis by assuring acceptance requirements can be met before the transfer of waste. The WTP Project has partnered with Savannah River National Laboratory to develop the waste feed qualification program. The results of waste feed qualification activities will be implemented using a batch processing methodology, and will establish an acceptable range of operator controllable parameters needed to treat the staged waste. Waste feed qualification program development is being implemented in three separate phases. Phase 1 required identification of analytical methods and gaps. This activity has been completed, and provides the foundation for a technically defensible approach for waste feed qualification. Phase 2 of the program development is in progress. The activities in this phase include the closure of analytical methodology gaps identified during Phase 1, design and fabrication of laboratory-scale test apparatus, and determination of the waste feed qualification sample volume. Phase 3 will demonstrate waste feed qualification testing in support of Cold Commissioning. (authors)

Development of nuclear waste concrete drum

International Nuclear Information System (INIS)

Wen Yinghui

1995-06-01

The raw materials selection and the properties for nuclear waste concrete drum, the formula and properties of the concrete, the specification and technical quality requirement of the drum were described. The manufacture essentials and technology, the experiments and checks as well as the effective quality control and quality assurance carried out in the course of production were presented. The developed nuclear waste drum has a simple structure, easily available raw materials and rational formula for concrete. The compressive strength of the drum is more than 70 MPa, the tensile strength is more than 5 MPa, the nitrogen permeability is (2.16∼3.6) x 10 -18 m 2 . The error of the drum in dimensions is +-2 mm. The external surface of the drum is smooth. The drum accords with China standards in the sandy surface, void and crack. The results shows China has the ability to develop and manufacture nuclear waste concrete container and lays the foundation for standardization and series of the nuclear waste container for packing and transporting nuclear wastes in China. (5 figs., 10 tabs.)

Low-level radioactive waste from commercial nuclear reactors. Volume 4. Proceedings of the workshop on research and development needs for treatment of low-level radioactive waste from commercial nuclear reactors

International Nuclear Information System (INIS)

Godbee, H.W.; Frederick, E.J.; Jolley, R.L.; Kibbey, A.H.; 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. As part of this program, a workshop was conducted for determining research and development needs in LLRW treatment. Volume 4, the proceedings of this workshop, includes the formal presentations and both panel and general discussions dealing with such issues as disposal, compaction, and the ''below regulatory concern'' philosophy. Summaries of individual workshops dealing with specific aspects of LLRW treatment are also presented in this volume

Development of Spherical Near Field Model for Geological Radioactive Waste Repository

International Nuclear Information System (INIS)

Kim, S. Y.; Lee, K. J.; Chang, S. H.; Lee, K. J.; Chang, S. H.

2012-01-01

Modeling for geological radioactive waste repository can be divided into 3 parts. They are near field modeling related to engineered barrier, far field modeling related to natural barrier and biosphere modeling. In order to make the general application for safety assessment of geological waste repository, spherical geometry near field model has been developed. This model can be used quite extensively when users calculate equivalent spherical geometry for specific engineered barrier like equivalent waste radius, equivalent barrier radius and etc. Only diffusion was considered for general purpose but advection part can be updated. Goldsim and Goldsim Radionuclide Transport (RT) module were chosen and used as developing tool for the flexible modeling. Developer can freely make their own model with developer friendly graphic interface by using Goldsim. Furthermore, model with user friendly graphic interface can be developed by using Goldsim Dashboard Authoring module. The model has been validated by comparing the result with that of another model, inserting similar inputs and conditions. The model has been proved to be reasonably operating from the comparison result by validation process. Cylindrical model can be developed as a further work based on the knowledge and experience from this research

Development of Spherical Near Field Model for Geological Radioactive Waste Repository

Energy Technology Data Exchange (ETDEWEB)

Kim, S. Y.; Lee, K. J.; Chang, S. H. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Lee, K. J.; Chang, S. H. [Khalifa Univ. of Science/Technology and Research, Abu Dhabi (United Arab Emirates)

2012-03-15

Modeling for geological radioactive waste repository can be divided into 3 parts. They are near field modeling related to engineered barrier, far field modeling related to natural barrier and biosphere modeling. In order to make the general application for safety assessment of geological waste repository, spherical geometry near field model has been developed. This model can be used quite extensively when users calculate equivalent spherical geometry for specific engineered barrier like equivalent waste radius, equivalent barrier radius and etc. Only diffusion was considered for general purpose but advection part can be updated. Goldsim and Goldsim Radionuclide Transport (RT) module were chosen and used as developing tool for the flexible modeling. Developer can freely make their own model with developer friendly graphic interface by using Goldsim. Furthermore, model with user friendly graphic interface can be developed by using Goldsim Dashboard Authoring module. The model has been validated by comparing the result with that of another model, inserting similar inputs and conditions. The model has been proved to be reasonably operating from the comparison result by validation process. Cylindrical model can be developed as a further work based on the knowledge and experience from this research.

Research program on radioactive wastes - Overview report for 2011

International Nuclear Information System (INIS)

Brander, S.

2012-01-01

This report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest and the work done in the year 2011 along with the results obtained. The aims of the program are recapitulated. The research program is co-ordinated by a working group comprising the Swiss Federal Office of Energy, the Swiss Federal Nuclear Safety Inspectorate ENSI, the Commission on Nuclear Waste Disposal and the Commission for Safety in Nuclear Installations, Some highlights of the research program are briefly described and discussed. Topics covered concern the marking of nuclear waste repositories, value judgement and opinion building, waste management as well as repository design, including dimensioning and monitoring systems, National and international co-operation is also discussed

Development of Ceramic Coating on Metal Substrate using Industrial Waste and Ore Minerals

Science.gov (United States)

Bhuyan, S. K.; Thiyagarajan, T. K.; Mishra, S. C.

2017-02-01

The technological advancement in modern era has a boon for enlightening human life; but also is a bane to produce a huge amount of (industrial) wastes, which is of great concern for utilization and not to create environmental threats viz. polution etc. In the present piece of research work, attempts have been made to utilize fly ash (wastes of thermal power plants) and along with alumina bearing ore i.e. bauxite, for developing plasma spray ceramic coatings on metals. Fly ash and with 10 and 20% bauxite addition is used to deposit plasma spray coatings on a metal substrate. The surface morphology of the coatings deposited at different power levels of plasma spraying investigated through SEM and EDS analysis. The coating thickness is measured. The porosity levels of the coatings are evaluated. The coating hardness isalso measured. This piece of research work will be beneficial for future development and use of industrial waste and ore minerals for high-valued applications.

Development and demonstration of treatment technologies for the processing of US Department of Energy Mixed Waste

International Nuclear Information System (INIS)

Bloom, G.A.; Berry, J.B.

1994-01-01

Mixed waste is defined as ''waste contaminated with chemically hazardous and radioactive species.'' The Mixed Waste Integrated Program (MWIP) was established in response to the need for a unified, DOE complexwide solution to issues of mixed waste treatment that meets regulatory requirements. MWIP is developing treatment technologies that reduce risk, minimize life-cycle cost, and improve process performance as compared to existing technologies. Treatment for waste streams for which no current technology exists, and suitable waste forms for disposal, will be provided to improve operations of the DOE Office of Waste Management. MWIP is composed of six technical areas within a mixed-waste treatment system: (1) systems analysis, (2) materials handling, (3) chemical/physical separation, (4) waste destruction and stabilization, (5) off-gas treatment, and (6) final waste form stabilization. The status of the technical initiatives and the current research, development, and demonstration in each of these areas are described in this paper

Technical development for geological disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Asano, Hidekazu; Sugino, Hiroyuki; Kawakami, Susumu; Yamanaka, Yumiko

1997-01-01

Technical developments for geological disposal of high-level radioactive wastes materials research and design technique for engineered barriers (overpack and buffer material) were studied to evaluate more reliable disposal systems for high-level radioactive wastes. A lifetime prediction model for the maximum corrosion depth of carbon steel was developed. A preferable alloys evaluation method for crevice corrosion was established for titanium. Swelling pressure and water permeability of bentonite as a buffer material was measured, and coupled hydro-thermo-mechanical analysis code for bentonite was also studied. The CIP (cold isostatic pressing) method for monolithically formed buffer material was tested. A concept study on operation equipment for the disposal site was performed. Activities of microorganisms involved in underground performance were investigated. (author)

Waste incineration industry and development policies in China.

Science.gov (United States)

Li, Yun; Zhao, Xingang; Li, Yanbin; Li, Xiaoyu

2015-12-01

The growing pollution from municipal solid waste due to economic growth and urbanization has brought great challenge to China. The main method of waste disposal has gradually changed from landfill to incineration, because of the enormous land occupation by landfills. The paper presents the results of a study of the development status of the upstream and downstream of the waste incineration industry chain in China, reviews the government policies for the waste incineration power industry, and provides a forecast of the development trend of the waste incineration industry. Copyright © 2015 Elsevier Ltd. All rights reserved.

FY 1999 report on the result for research and development of instantaneously effective and innovative energy and environment technology. Development of technology to use combustible wastes as resources and fuels; 1999 nendo sokkoteki kakushinteki energy kankyo gijutsu kenkyu kaihatsu kanengomi saishigen nenryoka gijutsu kaihatsu

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-03-01

Manufacturing compressed fuel, or refuse paper and plastic fuel (RPF) from combustible wastes such as used papers and waste plastics to utilize them effectively as a fuel to substitute fossil fuels is regarded as a promising engagement. However, this process indispensably requires removal of chlorine contained in used papers and waste plastics to a degree that they do not impede the combustion. The present research and development is intended to develop a PRF pretreatment technology and a dechlorination technology, and establish a technology to utilize the materials as resources and fuels as thermal recycling of combustible wastes. The current fiscal year has performed research and development on the following themes: development of a sorting system and a crushing system in developing the pretreatment technology, whereas for the former system, sorting tests were carried out by using a vibration type wind power sorting machine and an inertia force wind power sorting machine, and for the latter system, data were obtained on the crushing characteristics; dechlorination tests, in which it was discovered that the mixing ratio of used paper in the material affects the chlorine concentration; research on combustion characteristics, in which fundamental combustion tests using a small fluidized bed, combustion tests using a bench scale fluidized bed, and stoker fired furnace combustion tests were performed; and demonstrative operation researches. (NEDO)

High-level waste management research and development program at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Blomeke, J.O.; Bond, W.D.

1976-01-01

Projections of wastes to be generated through the year 2000 portend a problem of impressive size and complexity but one which can be handled within the framework of current and planned investigative programs. Investigations of the technical feasibility of removing actinide elements from wastes to render the residuals more manageable in terms of hazards and storage requirements indicate that they can be removed from wastes by the minimally desired factors of 10 2 to 10 4 ; however, demonstrations and engineering assessments of chemical flowsheets have yet to be made. Natural salt formations are believed to offer the best prospects for disposal of high-level wastes; other promising geological formations are also being evaluated for their suitability for use in the disposal of wastes

Advanced waste form and Melter development for treatment of troublesome high-level wastes

Energy Technology Data Exchange (ETDEWEB)

Marra, James [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Kim, Dong -Sang [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Maio, Vincent [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-10-01

A number of waste components in US defense high level radioactive wastes (HLW) have proven challenging for current Joule heated ceramic melter (JHCM) operations and have limited the ability to increase waste loadings beyond already realized levels. Many of these “troublesome" waste species cause crystallization in the glass melt that can negatively impact product quality or have a deleterious effect on melter processing. Recent efforts at US Department of Energy laboratories have focused on understanding crystallization behavior within HLW glass melts and investigating approaches to mitigate the impacts of crystallization so that increases in waste loading can be realized. Advanced glass formulations have been developed to highlight the unique benefits of next-generation melter technologies such as the Cold Crucible Induction Melter (CCIM). Crystal-tolerant HLW glasses have been investigated to allow sparingly soluble components such as chromium to crystallize in the melter but pass out of the melter before accumulating.The Hanford site AZ-101 tank waste composition represents a waste group that is waste loading limited primarily due to high concentrations of Fe₂O₃ (also with high Al₂O₃ concentrations). Systematic glass formulation development utilizing slightly higher process temperatures and higher tolerance to spinel crystals demonstrated that an increase in waste loading of more than 20% could be achieved for this waste composition, and by extension higher loadings for wastes in the same group. An extended duration CCIM melter test was conducted on an AZ-101 waste simulant using the CCIM platform at the Idaho National Laboratory (INL). The melter was continually operated for approximately 80 hours demonstrating that the AZ-101 high waste loading glass composition could be readily processed using the CCIM technology. The resulting glass was close to the targeted composition and exhibited excellent durability in both

RDandD Programme 2007. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2007-09-01

The programme describes in general terms the planned measures and the facilities that are needed for the task, with a focus on the plans for the period 2008-2013. The period of immediate concern is 2008-2010. The level of detail for the three subsequent years is naturally lower. The programme provides a basis for designing systems to manage and dispose of the radioactive waste from the nuclear power plants. SKB intends to dispose of the spent nuclear fuel in accordance with the KBS-3 method. In the RDandD Programme we describe our activities and the planning for it. We also deal with societal research and other methods for disposal of spent nuclear fuel. The planning for low- and intermediate-level waste, as well as for the societal research, is presented in separate parts. The upcoming review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they view different parts of the activity. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government. The most important milestone during the coming three-year period is to submit applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. RDandD programme 2007 therefore focuses on the technology development that is needed to realize the final repository for spent nuclear fuel. The site investigations in Forsmark and Laxemar will be concluded in 2007. The work of compiling the applications for the final repository is under way. In contrast to the immediately preceding programmes, RDandD Programme 2007 therefore also contains a summary of the site investigation phase and a look ahead at the steps that remain before the final repository can be put into operation. RDandD Programme 2007 consists of six parts: Part I SKB's plan of action; Part II Final repository for spent

RDandD Programme 2007. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2007-09-15

The programme describes in general terms the planned measures and the facilities that are needed for the task, with a focus on the plans for the period 2008-2013. The period of immediate concern is 2008-2010. The level of detail for the three subsequent years is naturally lower. The programme provides a basis for designing systems to manage and dispose of the radioactive waste from the nuclear power plants. SKB intends to dispose of the spent nuclear fuel in accordance with the KBS-3 method. In the RDandD Programme we describe our activities and the planning for it. We also deal with societal research and other methods for disposal of spent nuclear fuel. The planning for low- and intermediate-level waste, as well as for the societal research, is presented in separate parts. The upcoming review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they view different parts of the activity. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government. The most important milestone during the coming three-year period is to submit applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. RDandD programme 2007 therefore focuses on the technology development that is needed to realize the final repository for spent nuclear fuel. The site investigations in Forsmark and Laxemar will be concluded in 2007. The work of compiling the applications for the final repository is under way. In contrast to the immediately preceding programmes, RDandD Programme 2007 therefore also contains a summary of the site investigation phase and a look ahead at the steps that remain before the final repository can be put into operation. RDandD Programme 2007 consists of six parts: Part I SKB's plan of action; Part II Final repository for spent

RDandD Programme 2007. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2007-09-15

The programme describes in general terms the planned measures and the facilities that are needed for the task, with a focus on the plans for the period 2008-2013. The period of immediate concern is 2008-2010. The level of detail for the three subsequent years is naturally lower. The programme provides a basis for designing systems to manage and dispose of the radioactive waste from the nuclear power plants. SKB intends to dispose of the spent nuclear fuel in accordance with the KBS-3 method. In the RDandD Programme we describe our activities and the planning for it. We also deal with societal research and other methods for disposal of spent nuclear fuel. The planning for low- and intermediate-level waste, as well as for the societal research, is presented in separate parts. The upcoming review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they view different parts of the activity. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government. The most important milestone during the coming three-year period is to submit applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. RDandD programme 2007 therefore focuses on the technology development that is needed to realize the final repository for spent nuclear fuel. The site investigations in Forsmark and Laxemar will be concluded in 2007. The work of compiling the applications for the final repository is under way. In contrast to the immediately preceding programmes, RDandD Programme 2007 therefore also contains a summary of the site investigation phase and a look ahead at the steps that remain before the final repository can be put into operation. RDandD Programme 2007 consists of six parts: Part I SKB's plan of action; Part II Final repository for

Development and demonstration of treatment technologies for the processing of US Department of Energy mixed waste

International Nuclear Information System (INIS)

Berry, J.B.; Bloom, G.A.; Kuchynka, D.J.

1994-01-01