WorldWideScience

Sample records for future llr waste

  1. Planning for the recreational end use of a future LLR waste mound in Canada - Leaving an honourable legacy

    International Nuclear Information System (INIS)

    Kleb, H.R.; Zelmer, R.L.

    2007-01-01

    The Low-Level Radioactive Waste Management Office was established in 1982 to carry out the federal government's responsibilities for low-level radioactive (LLR) waste management in Canada. In this capacity, the Office operates programs to characterize, delineate, decontaminate and consolidate historic LLR waste for interim and long-term storage. The Office is currently the proponent of the Port Hope Area Initiative; a program directed at the development and implementation of a safe, local long-term management solution for historic LLR waste in the Port Hope area. A legal agreement between the Government of Canada and the host community provides the framework for the implementation of the Port Hope Project. Specifically, the agreement requires that the surface of the long-term LLR waste management facility be 'conducive to passive and active recreational uses such as soccer fields and baseball diamonds'. However, there are currently no examples of licensed LLR waste management facilities in Canada that permit recreational use. Such an end use presents challenges with respect to engineering and design, health and safety and landscape planning. This paper presents the cover system design, the environmental effects assessment and the landscape planning processes that were undertaken in support of the recreational end use of the Port Hope long-term LLR waste management facility. (authors)

  2. Remediating while preserving wetland habitat at an LLR waste site in Canada

    International Nuclear Information System (INIS)

    Kleb, H.R.; Zelmer, R.L.

    2007-01-01

    The Low-Level Radioactive Waste Management Office was established in 1982 to carry out the federal government's responsibilities for low-level radioactive (LLR) waste management in Canada. The Office operates programs to characterize, delineate, decontaminate and consolidate historic LLR waste for interim and long-term storage. In this capacity, the Office is currently considering the remediation of 9,000 cubic metres of contaminated sediment in a coastal marsh in the context of a major remediation project involving multiple urban sites. The marsh is situated between the Lake Ontario shoreline and the urban fringe of the Town of Port Hope. The marsh is designated a Cattail Mineral Shallow Marsh under the Ecological Land Classification system for Southern Ontario and was recently named the A.K. Sculthorpe Marsh in memory of a local community member. The marsh remediation will therefore require trade off between the disruption of a sensitive wetland and the removal of contaminated sediment. This paper discusses the issues and trade-off relating to the waste characterization, environmental assessment and regulatory findings and thus the remediation objectives for the marsh. Considerations include the spatial distribution of contaminated sediment, the bioavailability of contaminants, the current condition of the wetland and the predicted effects of remediation. Also considered is the significance of the wetland from provincial and municipal regulatory perspectives and the resulting directives for marsh remediation. (authors)

  3. LLR data analysis and impact on lunar dynamics from recent developments at OCA LLR Station

    Science.gov (United States)

    Viswanathan, Vishnu; Fienga, Agnes; Courde, Clement; Torre, Jean-Marie; Exertier, Pierre; Samain, Etienne; Feraudy, Dominique; Albanese, Dominique; Aimar, Mourad; Mariey, Hervé; Viot, Hervé; Martinot-Lagarde, Gregoire

    2016-04-01

    Since late 2014, OCA LLR station has been able to range with infrared wavelength (1064nm). IR ranging provides both temporal and spatial improvement in the LLR observations. IR detection also permits in densification of normal points, including the L1 and L2 retroreflectors due to better signal to noise ratio. This contributes to a better modelisation of the lunar libration. The hypothesis of lunar dust and environmental effects due to the chromatic behavior noticed on returns from L2 retroreflector is discussed. In addition, data analysis shows that the effect of retroreflector tilt and the use of calibration profile for the normal point deduction algorithm, contributes to improving the precision of normal points, thereby impacting lunar dynamical models and inner physics.

  4. arXiv Ergodicity of the LLR method for the Density of States

    CERN Document Server

    Cossu, Guido; Pellegrini, Roberto; Rago, Antonio

    2018-01-01

    The LLR method is a novel algorithm that enables us to evaluate the density of states in lattice gauge theory. We present our study of the ergodicity properties of the LLR algorithm for the model of Yang Mills SU(3). We show that the use of the replica exchange method alleviates significantly the topological freeze-out that severely affects other algorithms.

  5. Modified Decoding Algorithm of LLR-SPA

    Directory of Open Access Journals (Sweden)

    Zhongxun Wang

    2014-09-01

    Full Text Available In wireless sensor networks, the energy consumption is mainly occurred in the stage of information transmission. The Low Density Parity Check code can make full use of the channel information to save energy. Because of the widely used decoding algorithm of the Low Density Parity Check code, this paper proposes a new decoding algorithm which is based on the LLR-SPA (Sum-Product Algorithm in Log-Likelihood-domain to improve the accuracy of the decoding algorithm. In the modified algorithm, a piecewise linear function is used to approximate the complicated Jacobi correction term in LLR-SPA decoding algorithm. Construct the tangent by the tangency point to the function of Jacobi correction term, which is based on the first order Taylor Series. In this way, the proposed piecewise linear approximation offers almost a perfect match to the function of Jacobi correction term. Meanwhile, the proposed piecewise linear approximation could avoid the operation of logarithmic which is more suitable for practical application. The simulation results show that the proposed algorithm could improve the decoding accuracy greatly without noticeable variation of the computational complexity.

  6. A hybrid LLR-MHD model of kink perturbations in EXTRAP

    International Nuclear Information System (INIS)

    Lehnert, B.

    1987-07-01

    In high-beta systems, such as Extrap and other Z-pinch configurations, kinetic large Larmor radius (LLR) phenomena introduce strong phase-mixing and dispersive effects and a corresponding 'kinetic damping' which cannot be treated in terms of MHD theory. In this paper a first attempt is made to include these effects by proposing a hybrid LLR-MHD model in which the kinetic phenomena enter as constraints on the possible forms of the plasma perturbations. The latter then become restricted to a limited class which can be treated in terms of MHD theory. The present model does not claim to produce stability conditions which are exact in all details, but should merely provide a picture of the general relationship between the basic plasma parameters in a state of marginal stability. For kink perturbations in Extrap stability relations have thus been obtained between the pinch and conductor currents, the pinch radius and the axial conductor distance, and the number of contained ion Larmor radii. These relations appear to be consistent with so far obtained experimental data. A short discussion on the effects of a superimposed axial magnetic field has been included. At this stage only experiments can verify whether or not the present simple model becomes relevant to Extrap stability. (author)

  7. Model for future waste generation

    Energy Technology Data Exchange (ETDEWEB)

    Sundqvist, Jan-Olov; Stenmarck, Aasa; Ekvall, Tomas

    2010-06-15

    The research presented in this report is part of the effort to estimate future Swedish waste quantities in the research programme Towards Sustainable Waste Management. More specifically, we estimate future waste coefficients that are designed to be fed into EMEC, which describes the Swedish economy in terms of 26 industrial sectors, a public sector, and households. Production in the model of industry and public sector requires input of labour, capital, energy, and other commodities. With waste-intensity coefficients added to each production parameter in each sector, EMEC can calculate the future waste quantities generated in different economic scenarios. To produce the waste-intensity coefficients, we make a survey of the current Swedish waste statistics. For each waste category from each sector we estimate whether the quantity depends primarily on the production in the sector, on the inputs of commodities, on the depreciation of capital goods, or on the size of the workforce in the sector. We calculate current waste-intensity coefficients by dividing the waste quantities by the parameter(s) to which they are assigned. We also present five different scenarios to describe how the waste intensity can develop until the year 2030. As far as possible and when deemed to be relevant, we have set the industrial waste generation to depend on the use of a commodity or an energy carrier. The quantity of spent vehicles and most equipment is set to depend on the depreciation of capital goods. Some wastes have been allocated to the staff, for example household waste from business. The quantities of wastes from households have a similar approach where every waste category is assigned to a combination of 26 different commodities

  8. Alternatives for Future Waste Management in Denmark

    DEFF Research Database (Denmark)

    Møller Andersen, Frits; Cimpan, Ciprian; Dall, Ole

    The TOPWASTE project has addressed the challenges of planning robust solutions for future waste management. The purpose was to identify economic and environmentally optimal solutions ‐ taking into account different scenarios for the development of the surrounding systems, such as the energy syste......, environmental and resource efficiency of waste management solutions. The following chapters addresses these issues by answering some of the main research questions of the project.......The TOPWASTE project has addressed the challenges of planning robust solutions for future waste management. The purpose was to identify economic and environmentally optimal solutions ‐ taking into account different scenarios for the development of the surrounding systems, such as the energy system....... During the project, four decision support tools were developed:1. Frida ‐ The EPA's tool for forecasting future waste generation 2. OptiWaste ‐ a new tool for economic optimisation of investments and operation of the combined waste and energy system3. KISS ‐ a new lifecycle based model with focus...

  9. Tidal dissipation in the Moon. Learning from the "incorrect" frequency dependence measured by the LLR

    Science.gov (United States)

    Efroimsky, M.

    2012-09-01

    It was demonstrated back in 2001 that fitting of the LLR data results in the quality factor Q of the Moon scaling as the frequency ξ to a negative power [8]: Q ˜ ξp , where p = -0.19 . (1) At the same time, numerous measurements by various seismological teams agree on the exponent being positive, not negative [4]. The positive sign of the exponent stems also from geodetic measurements [1], and it finds its explanation within the theory of friction in minerals [5]. On all these grounds, the aforementioned finding by the LLR team appears to be implausible and to disagree with the conventional wisdom of solid state mechanics and seismology. A later reexamination in [9] rendered a less upsetting value, p = -0.09 , which was still negative and still seemed to contradict our knowledge of microphysical processes in solids. The authors later wrote [10]: "There is a weak dependence of tidal specific dissipation Q on period. The Q increases from ˜ 30 at a month to ˜ 35 at one year. Q for rock is expected to have a weak dependence on tidal period, but it is expected to decrease with period rather than increase. The frequency dependence of Q deserves further attention and should be improved." A possible explanation of this paradox comes from the observation that the LLR measurements provided information on the tidal and not seismic dissipation. The difference between these two processes comes from self-gravitation of the celestial body. To address the problem accurately, one has to calculate the tidal factors kl sin ɛl showing up in the Darwin-Kaula expansion for the tidal torque or force. Here kl is the degree-l Love number, while ɛl is the appropriate tidal lag. Sometimes sin ɛl is denoted with 1/Q , which is not recommended, because this notation does not distinguish between the tidal reaction appropriate to harmonics of different degree. This notation also puts one at risk of confusing the tidal damping with the seismic damping, two process that have much in common

  10. Potential future waste-to-energy systems

    OpenAIRE

    Thorin, Eva; Guziana, Bozena; Song, Han; Jääskeläinen, Ari; Szpadt, Ryszard; Vasilic, Dejan; Ahrens, Thorsten; Anne, Olga; Lõõnik, Jaan

    2012-01-01

    This report discusses potential future systems for waste-to-energy production in the Baltic Sea Region, and especially for the project REMOWE partner regions, the County of Västmanland in Sweden, Northern Savo in Finland, Lower Silesia in Poland, western part of Lithuania and Estonia. The waste-to-energy systems planned for in the partner regions are combustion of municipal solid waste (MSW) and solid recovered fuels from household and industry as well as anaerobic digestion of sewage sludge ...

  11. Estimation of future outflows of e-waste in India

    International Nuclear Information System (INIS)

    Dwivedy, Maheshwar; Mittal, R.K.

    2010-01-01

    The purpose of this study is to construct an approach and a methodology to estimate the future outflows of electronic waste (e-waste) in India. Consequently, the study utilizes a time-series multiple lifespan end-of-life model proposed by Peralta and Fontanos for estimating the current and future quantities of e-waste in India. The model estimates future e-waste generation quantities by modeling their usage and disposal. The present work considers two scenarios for the approximation of e-waste generation based on user preferences to store or to recycle the e-waste. This model will help formal recyclers in India to make strategic decisions in planning for appropriate recycling infrastructure and institutional capacity building. Also an extension of the model proposed by Peralta and Fontanos is developed with the objective of helping decision makers to conduct WEEE estimates under a variety of assumptions to suit their region of study. During 2007-2011, the total WEEE estimates will be around 2.5 million metric tons which include waste from personal computers (PC), television, refrigerators and washing machines. During the said period, the waste from PC will account for 30% of total units of WEEE generated.

  12. Wasting the Future: The Technological Sublime, Communications Technologies, and E-waste

    Directory of Open Access Journals (Sweden)

    Sebine Label

    2012-08-01

    Full Text Available Literally speaking, e-waste is the future of communications. E-waste is the fastest growing waste stream in the world, much of it communications technologies from cell phones to laptops, televisions to peripherals. As a result of policies of planned obsolescence working computers, cell phones, and tablets are routinely trashed. One of the most powerful and enduring discourses associated with emerging technologies is the technological sublime, in which technology is seen as intellectually, emotionally, or spiritually transcendent. It comprises a contradictory impulse that elevates technology with an almost religious fervor, while simultaneously overlooking some of the consequences of industrialism, as well as ignoring the necessity of social, economic, and governmental infrastructures necessary to the implementation and development of new technologies. The idea that a new technology will not pollute or harm the environment is a persistent, though often quickly passed over, theme in the technological sublime, echoed in discourses about emerging technologies such as the silicon chip, the internet, and other ICTs. In this paper, I make connections between the discourse of newness, the practice of planned obsolescence, and the mountains of trashed components and devices globally. Considering the global context demonstrates the realities of the penetration of ICTs and their enduring pollution and negative implications for the health of humans and nonhumans, including plants, animals, waterways, soil, air and so on. I use the discourse of the technological sublime to open up and consider the future of communications, to argue that this discourse not only stays with us but also contains within it two important and related components, the promise of ecological harmony and a future orientation. I argue that these lingering elements keep us from considering the real future of communications – e-waste – and that, as communications scholars, we must also

  13. Environmental Assessment of Possible Future Waste Management Scenarios

    Directory of Open Access Journals (Sweden)

    Yevgeniya Arushanyan

    2017-02-01

    Full Text Available Waste management has developed in many countries and will continue to do so. Changes towards increased recovery of resources in order to meet climate targets and for society to transition to a circular economy are important driving forces. Scenarios are important tools for planning and assessing possible future developments and policies. This paper presents a comprehensive life cycle assessment (LCA model for environmental assessments of scenarios and waste management policy instruments. It is unique by including almost all waste flows in a country and also allow for including waste prevention. The results show that the environmental impacts from future waste management scenarios in Sweden can differ a lot. Waste management will continue to contribute with environmental benefits, but less so in the more sustainable future scenarios, since the surrounding energy and transportation systems will be less polluting and also because less waste will be produced. Valuation results indicate that climate change, human toxicity and resource depletion are the most important environmental impact categories for the Swedish waste management system. Emissions of fossil CO2 from waste incineration will continue to be a major source of environmental impacts in these scenarios. The model is used for analyzing environmental impacts of several policy instruments including weight based collection fee, incineration tax, a resource tax and inclusion of waste in a green electricity certification system. The effect of the studied policy instruments in isolation are in most cases limited, suggesting that stronger policy instruments as well as combinations are necessary to reach policy goals as set out in for example the EU action plan on circular economy.

  14. Joint optimisation of the future Danish waste and energy system

    DEFF Research Database (Denmark)

    Münster, Marie; Pizarro, Amalia Rosa; Salvucci, Raffaele

    2015-01-01

    in future scenarios with higher biomass consumption, where the average heat prices are higher. In both scenarios, biogas produced from organic waste is upgraded and fed into the natural gas grid and waste is incinerated rather than being centrally sorted in a material recovery facility.......In this article the impact of the future development of the energy system on the feasibility of waste treatment options is analysed. In the article two different optimization tools are used: a regional electricity model (Balmorel) and a national waste treatment and district heating model (Opti......Waste). When performing optimization by minimizing the socio-economic costs, into future energy systems with high wind power production, it proves feasible primarily to incinerate waste in large scale combined heat and power (CHP) plants, whereas more incineration takes place in decentralized CHP plants...

  15. Future industrial and municipal waste management in poland the polish challenge

    International Nuclear Information System (INIS)

    Nowakowskl, J.; Sorum, L.; Hustad, J.E.

    1996-01-01

    Poland now face a very interesting discussion on modern waste treatment methods, although the waste problems are very oil. This paper presents a total waste management view from the formation process to recycling, utilisation and land filling. The average municipal solid waste (MSW) annual per capita generation in poland is 250 kg per person, which is half of the waste amount generated in norway and one third of the amount in Usa. The present low per capita generation, large variations in MSW properties and an expected growth in the standard of living make the decisions regarding future polish waste management systems very important. Waste management must be handled carefully to prevent a rapid growth of waste generation - this is the p olish challenge , both mow and for the future. Three different possibilities for future waste management systems for rural areas, small cities and larger cities are discussed in the paper. 4 figs., 1 tab

  16. Seletividade do Clomazone no Manejo Químico de Plantas Daninhas da Cultura do Algodão LL(r)

    OpenAIRE

    Arantes, J.G.Z.; Constantin, J.; Oliveira Jr., R.S.; Braz, G.B.P.; Takano, H.K.; Gemelli, A.; Oliveira Neto, A.M.; Brugnera, P.

    2015-01-01

    O amonio-glufosinate é um herbicida de amplo espectro de controle de plantas daninhas, porém não apresenta controle residual no solo, o que limita sua utilidade quando usado isoladamente na cultura do algodão, havendo a necessidade de combinar diferentes herbicidas em mais de uma modalidade de aplicação. O objetivo deste trabalho foi avaliar a seletividade de diferentes sistemas de controle químico de plantas daninhas contendo clomazone na cultura do algodão LL(r). As misturas triplas em pré-...

  17. Future scenario development within life cycle assessment of waste management systems

    DEFF Research Database (Denmark)

    Bisinella, Valentina

    Life Cycle Assessment (LCA) is an acknowledged tool for quantifying the sustainability of waste management solutions. However, the use of LCA for decision-making is hindered by the strong dependency of the LCA results on the assumptions regarding the future conditions in which the waste management...... solutions will operate. Future scenario methods from the management engineering field may provide valid approaches for formulating consistent assumptions on future conditions for the waste management system modelled with LCA. However, the standardized LCA procedure currently does not offer much guidance...... field. The quantitative modelling implications were tested within real-scale LCA models focusing on the management of residual waste in Denmark. In a wide range of scenarios, this thesis addressed the influence on the LCA model results of realistic technology and waste composition uncertainties, as well...

  18. Future trends in computer waste generation in India.

    Science.gov (United States)

    Dwivedy, Maheshwar; Mittal, R K

    2010-11-01

    The objective of this paper is to estimate the future projection of computer waste in India and to subsequently analyze their flow at the end of their useful phase. For this purpose, the study utilizes the logistic model-based approach proposed by Yang and Williams to forecast future trends in computer waste. The model estimates future projection of computer penetration rate utilizing their first lifespan distribution and historical sales data. A bounding analysis on the future carrying capacity was simulated using the three parameter logistic curve. The observed obsolete generation quantities from the extrapolated penetration rates are then used to model the disposal phase. The results of the bounding analysis indicate that in the year 2020, around 41-152 million units of computers will become obsolete. The obsolete computer generation quantities are then used to estimate the End-of-Life outflows by utilizing a time-series multiple lifespan model. Even a conservative estimate of the future recycling capacity of PCs will reach upwards of 30 million units during 2025. Apparently, more than 150 million units could be potentially recycled in the upper bound case. However, considering significant future investment in the e-waste recycling sector from all stakeholders in India, we propose a logistic growth in the recycling rate and estimate the requirement of recycling capacity between 60 and 400 million units for the lower and upper bound case during 2025. Finally, we compare the future obsolete PC generation amount of the US and India. Copyright © 2010 Elsevier Ltd. All rights reserved.

  19. Biomedical waste management in Ayurveda hospitals - current practices & future prospectives.

    Science.gov (United States)

    Rajan, Renju; Robin, Delvin T; M, Vandanarani

    2018-03-16

    Biomedical waste management is an integral part of traditional and contemporary system of health care. The paper focuses on the identification and classification of biomedical wastes in Ayurvedic hospitals, current practices of its management in Ayurveda hospitals and its future prospective. Databases like PubMed (1975-2017 Feb), Scopus (1960-2017), AYUSH Portal, DOAJ, DHARA and Google scholar were searched. We used the medical subject headings 'biomedical waste' and 'health care waste' for identification and classification. The terms 'biomedical waste management', 'health care waste management' alone and combined with 'Ayurveda' or 'Ayurvedic' for current practices and recent advances in the treatment of these wastes were used. We made a humble attempt to categorize the biomedical wastes from Ayurvedic hospitals as the available data about its grouping is very scarce. Proper biomedical waste management is the mainstay of hospital cleanliness, hospital hygiene and maintenance activities. Current disposal techniques adopted for Ayurveda biomedical wastes are - sewage/drains, incineration and land fill. But these methods are having some merits as well as demerits. Our review has identified a number of interesting areas for future research such as the logical application of bioremediation techniques in biomedical waste management and the usage of effective micro-organisms and solar energy in waste disposal. Copyright © 2017 Transdisciplinary University, Bangalore and World Ayurveda Foundation. Published by Elsevier B.V. All rights reserved.

  20. Disposal of radioactive waste in Romania. Present and future strategy

    International Nuclear Information System (INIS)

    Rodna, A.; Garlea, C.

    2002-01-01

    The paper begins with the presentation of the actual situation of radioactive waste management in Romania. The organizations responsible for radioactive waste management and their capabilities are described, including radioactive waste disposal. The main provisions of the 'Draft law regarding the management of nuclear spent fuel and radioactive waste, in view of their final disposal' are also presented, with accent on the responsibilities of the National Radioactive Waste Agency (ANDRAD) and on the fund for radioactive waste and spent fuel management and for decommissioning. The paper ends with the presentation of the future radioactive waste and spent fuel management strategy. (author)

  1. Future radioactive liquid waste streams study

    Energy Technology Data Exchange (ETDEWEB)

    Rey, A.S.

    1993-11-01

    This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup date for the RLWTF is estimated to be between 2002 and 2005, and the life span of the facility is estimated to be 40 years. The policies and requirements driving the replacement of the current RLW treatment facility are reviewed. Historical and current status of RLW generation at Los Alamos National Laboratory are provided. Laboratory Managers were interviewed to obtain their insights into future RLW activities at Los Alamos that might affect the amount of RLW generated at the Lab. Interviews, trends, and investigation data are analyzed and used to create scenarios. These scenarios form the basis for the predictions of future RLW generation and the level of RLW treatment capacity which will be needed at LANL.

  2. Future radioactive liquid waste streams study

    International Nuclear Information System (INIS)

    Rey, A.S.

    1993-11-01

    This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup date for the RLWTF is estimated to be between 2002 and 2005, and the life span of the facility is estimated to be 40 years. The policies and requirements driving the replacement of the current RLW treatment facility are reviewed. Historical and current status of RLW generation at Los Alamos National Laboratory are provided. Laboratory Managers were interviewed to obtain their insights into future RLW activities at Los Alamos that might affect the amount of RLW generated at the Lab. Interviews, trends, and investigation data are analyzed and used to create scenarios. These scenarios form the basis for the predictions of future RLW generation and the level of RLW treatment capacity which will be needed at LANL

  3. Future spent nuclear fuel and radioactive waste infrastructure in Norway

    International Nuclear Information System (INIS)

    Soerlie, A.A.

    2002-01-01

    In Norway a Governmental Committee was appointed in 1991 to make an evaluation of the future steps that need to be taken in Norway to find a final solution for the spent nuclear fuel and for some other radioactive waste for which a disposal option does not exist today. The report from the Committee is now undergoing a formal hearing process. Based on the Committees recommendation and comments during the hearing the responsible Ministry will take a decision on future infrastructure in Norway for the spent nuclear fuel. This will be decisive for the future management of spent nuclear fuel and radioactive waste in Norway. (author)

  4. Future-proof radioactive waste treatment technologies for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Buettner, Klaus; Braehler, Georg [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany)

    2014-08-15

    In order to select the optimal treatment method for radioactive waste three options can be considered. First, to treat the radioactive waste only to allow long term interim storage until the waste acceptance criteria are defined and the disposal sites are operable. Second, to select treatment methods just in compliance with the current state of discussion with the regard to the above. Third, taking also the future development in the field of waste acceptance criteria and disposal into account. When developing waste treatment systems for Nuclear Power Plants NUKEM Technologies follows the following targets, minimisation of the amount of radioactive waste, maximisation of free release material, volume reduction, avoidance of unwanted materials in the waste package, as well as efficient waste treatment solutions (low investment, high volume reduction). With its technologies produced waste packages fulfil the most stringent waste acceptance criteria.

  5. Hidden flows and waste processing--an analysis of illustrative futures.

    Science.gov (United States)

    Schiller, F; Raffield, T; Angus, A; Herben, M; Young, P J; Longhurst, P J; Pollard, S J T

    2010-12-14

    An existing materials flow model is adapted (using Excel and AMBER model platforms) to account for waste and hidden material flows within a domestic environment. Supported by national waste data, the implications of legislative change, domestic resource depletion and waste technology advances are explored. The revised methodology offers additional functionality for economic parameters that influence waste generation and disposal. We explore this accounting system under hypothetical future waste and resource management scenarios, illustrating the utility of the model. A sensitivity analysis confirms that imports, domestic extraction and their associated hidden flows impact mostly on waste generation. The model offers enhanced utility for policy and decision makers with regard to economic mass balance and strategic waste flows, and may promote further discussion about waste technology choice in the context of reducing carbon budgets.

  6. Specifying the Concept of Future Generations for Addressing Issues Related to High-Level Radioactive Waste.

    Science.gov (United States)

    Kermisch, Celine

    2016-12-01

    The nuclear community frequently refers to the concept of "future generations" when discussing the management of high-level radioactive waste. However, this notion is generally not defined. In this context, we have to assume a wide definition of the concept of future generations, conceived as people who will live after the contemporary people are dead. This definition embraces thus each generation following ours, without any restriction in time. The aim of this paper is to show that, in the debate about nuclear waste, this broad notion should be further specified and to clarify the related implications for nuclear waste management policies. Therefore, we provide an ethical analysis of different management strategies for high-level waste in the light of two principles, protection of future generations-based on safety and security-and respect for their choice. This analysis shows that high-level waste management options have different ethical impacts across future generations, depending on whether the memory of the waste and its location is lost, or not. We suggest taking this distinction into account by introducing the notions of "close future generations" and "remote future generations", which has important implications on nuclear waste management policies insofar as it stresses that a retrievable disposal has fewer benefits than usually assumed.

  7. Performance assessment for future low-level waste disposal facilities at ORNL

    International Nuclear Information System (INIS)

    Lee, D.W.; Kocher, D.C.

    1989-01-01

    This paper discusses the strategy for waste management on the Oak Ridge Reservation (ORR) and the approach to preparing future performance assessments that has evolved from previous performance assessment studies of low-level radioactive waste disposal on the ORR. The strategy for waste management is based on the concept that waste classification should be determined by performance assessment other than the sources of waste. This dose-based strategy for waste classification and management places special importance on the preparation and interpretation of waste disposal performance assessments for selecting appropriate disposal technologies and developing waste acceptance criteria. Additionally, the challenges to be overcome in the preparation of performance assessments are discussed. 7 refs

  8. Efficient use of shrimp waste: present and future trends.

    Science.gov (United States)

    Kandra, Prameela; Challa, Murali Mohan; Jyothi, Hemalatha Kalangi Padma

    2012-01-01

    The production of shrimp waste from shrimp processing industries has undergone a dramatic increase in recent years. Continued production of this biomaterial without corresponding development of utilizing technology has resulted in waste collection, disposal, and pollution problems. Currently used chemical process releases toxic chemicals such as HCl, acetic acid, and NaOH into aquatic ecosystem as byproducts which will spoil the aquatic flora and fauna. Environmental protection regulations have become stricter. Now, there is a need to treat and utilize the waste in most efficient manner. The shrimp waste contains several bioactive compounds such as chitin, pigments, amino acids, and fatty acids. These bioactive compounds have a wide range of applications including medical, therapies, cosmetics, paper, pulp and textile industries, biotechnology, and food applications. This current review article present the utilization of shrimp waste as well as an alternative technology to replace hazardous chemical method that address the future trends in total utilization of shrimp waste for recovery of bioactive compounds.

  9. The future of the civil nuclear industry: the challenge of nuclear wastes

    International Nuclear Information System (INIS)

    2001-01-01

    This research thesis first gives an overview of the nuclear waste processing and storage in France (reasons and future of this political choice, legal framework, storage means and sites, weaknesses of waste storage). Then it comments various aspects of the processing of foreign nuclear wastes in France: economy and media impact, law and contracts, waste transport, temporary storage in France

  10. TIME-TEMPERATURE-TRANSFORMATION (TTT) DIAGRAMS FOR FUTURE WASTE COMPOSITIONS

    International Nuclear Information System (INIS)

    Billings, A.; Edwards, T.

    2010-01-01

    As a part of the Waste Acceptance Product Specifications (WAPS) for Vitrified High-Level Waste Forms defined by the Department of Energy - Office of Environmental Management, the waste form stability must be determined for each of the projected high-level waste (HLW) types at the Savannah River Site (SRS). Specifically, WAPS 1.4.1 requires the glass transition temperature (T g ) to be defined and time-temperature-transformation (TTT) diagrams to be developed. The T g of a glass is an indicator of the approximate temperature where the supercooled liquid converts to a solid on cooling or conversely, where the solid begins to behave as a viscoelastic solid on heating. A TTT diagram identifies the crystalline phases that can form as a function of time and temperature for a given waste type or more specifically, the borosilicate glass waste form. In order to assess durability, the Product Consistency Test (PCT) was used and the durability results compared to the Environmental Assessment (EA) glass. The measurement of glass transition temperature and the development of TTT diagrams have already been performed for the seven Defense Waste Processing Facility (DWPF) projected compositions as defined in the Waste Form Compliance Plan (WCP) and in SRNL-STI-2009-00025. Additional phase transformation information exists for other projected compositions, but overall these compositions did not cover composition regions estimated for future waste processing. To develop TTT diagrams for future waste types, the Savannah River National Laboratory (SRNL) fabricated two caches of glass from reagent grade oxides to simulate glass compositions which would be likely processed with and without Al dissolution. These were used for glass transition temperature measurement and TTT diagram development. The glass transition temperatures of both glasses were measured using differential scanning calorimetry (DSC) and were recorded to be 448 C and 452 C. Using the previous TTT diagrams as guidance

  11. Evaluation of the ORNL area for future waste burial facilities

    International Nuclear Information System (INIS)

    Lomenick, T.F.; Byerly, D.W.; Gonzales, S.

    1983-10-01

    Additional waste-burial facilities will be needed at ORNL within this decade. In order to find environmentally acceptable sites, the ORNL area must be systematically evaluated. This document represents the first step in that selection process. Geologic and hydrologic data from the literature and minor field investigations are used to identify more favorable sites for Solid Waste Storage Area (SWSA) 7. Also underway at this time is a companion study to locate a Central Waste Storage Area which could be used in the future to accommodate wastes generated by the X-10, Y-12, and K-25 facilities. From the several watershed options available, the Whiteoak Creek drainage basin is selected as the most promising hydrologic regime. This area contains all past and present waste-disposal facilities and is thus already well monitored. The seven bedrock units within the ORNL area are evaluated as potential burial media. Shales of the Conasauga Group, which are currently used for waste burial in the Whiteoak Creek drainage basin, and the Knox Group are considered the leading candidates. Although the residuum derived from and overlying the Knox dolomite has many favorable characteristics and may be regarded as having a high potential for burial of low-level wastes, at the present it is unproven. Therefore, the Conasauga shales are considered a preferable option for SWSA 7 within the ORNL area. Since the Conasauga interval is currently used for waste burial, it is better understood. One tract in Melton Valley that is underlain by Conasauga shales is nominated for detailed site-characterization studies, and several other tracts are recommended for future exploratory drilling. Exploration is also suggested for a tract in the upper Whiteoak Creek basin where Knox residuum is the shallow subsurface material

  12. The concept of responsibility to future generations for the management and storage of radioactive waste

    International Nuclear Information System (INIS)

    Vial, E.

    2004-01-01

    Recognition of the concept of responsibility to future generations seems, to imply the need to assume responsibility today for radioactive waste legacy of the past as well as for the waste that is currently being generated. However, this view of things, or more precisely this interpretation, is clouded by the lack of a clear definition of the concept of responsibility towards future generations. The concept has been used mainly in connection with long-lived radioactive wastes, which pose the greatest management problem as it so so far exceeds any human scale of reference. Consideration for future generations has to be a factor in the management of all types of radioactive waste, be it short, medium or long-lived waste or very low, low, intermediate or highly radioactive waste. As a general rule the concept of responsibility has made focus on long lived waste, whatever its level of radioactivity. The current alternatives for the management of radioactive waste may be: interim storage, final disposal, incineration, transmutation, to lower the radioactivity of the wastes. These different alternatives are discussed because they are not all genuine solutions and need to be deepened. (N.C.)

  13. Compaction of solid wastes in countries without disposal facility: A prelude of future troubles

    International Nuclear Information System (INIS)

    Benitez-Navarro, J.C.; Salgado-Mojena, M.

    2002-01-01

    This paper is intended to launch a technical debate, which will lead up to simple recommendations on what to do with compactable solid wastes in countries without disposal facilities. The paper discusses the problems caused by some practical uncertainties in the long-term management of the radioactive solid wastes produced outside the nuclear fuel cycle, in countries belonging to Groups A, B and C. Compaction is the preferred volume reduction method. But the compacted solid wastes are very probably not in a suitable form for future disposal and would need to be processed again in the near future. (author)

  14. The new Waste Law: Challenging opportunity for future landfill operation in Indonesia.

    Science.gov (United States)

    Meidiana, Christia; Gamse, Thomas

    2011-01-01

    The Waste Law No. 18/2008 Article 22 and 44 require the local governments to run environmentally sound landfill. Due to the widespread poor quality of waste management in Indonesia, this study aimed to identify the current situation by evaluating three selected landfills based on the ideal conditions of landfill practices, which are used to appraise the capability of local governments to adapt to the law. The results indicated that the local governments have problems of insufficient budget, inadequate equipment, uncollected waste and unplanned future landfill locations. All of the selected landfills were partially controlled landfills with open dumping practices predominating. In such inferior conditions the implementation of sanitary landfill is not necessarily appropriate. The controlled landfill is a more appropriate solution as it offers lower investment and operational costs, makes the selection of a new landfill site unnecessary and can operate with a minimum standard of infrastructure and equipment. The sustainability of future landfill capacity can be maintained by utilizing the old landfill as a profit-oriented landfill by implementing a landfill gas management or a clean development mechanism project. A collection fee system using the pay-as-you-throw principle could increase the waste income thereby financing municipal solid waste management.

  15. Reducing the likelihood of future human activities that could affect geologic high-level waste repositories

    International Nuclear Information System (INIS)

    1984-05-01

    The disposal of radioactive wastes in deep geologic formations provides a means of isolating the waste from people until the radioactivity has decayed to safe levels. However, isolating people from the wastes is a different problem, since we do not know what the future condition of society will be. The Human Interference Task Force was convened by the US Department of Energy to determine whether reasonable means exist (or could be developed) to reduce the likelihood of future human unintentionally intruding on radioactive waste isolation systems. The task force concluded that significant reductions in the likelihood of human interference could be achieved, for perhaps thousands of years into the future, if appropriate steps are taken to communicate the existence of the repository. Consequently, for two years the task force directed most of its study toward the area of long-term communication. Methods are discussed for achieving long-term communication by using permanent markers and widely disseminated records, with various steps taken to provide multiple levels of protection against loss, destruction, and major language/societal changes. Also developed is the concept of a universal symbol to denote Caution - Biohazardous Waste Buried Here. If used for the thousands of non-radioactive biohazardous waste sites in this country alone, a symbol could transcend generations and language changes, thereby vastly improving the likelihood of successful isolation of all buried biohazardous wastes

  16. Reducing the likelihood of future human activities that could affect geologic high-level waste repositories

    Energy Technology Data Exchange (ETDEWEB)

    1984-05-01

    The disposal of radioactive wastes in deep geologic formations provides a means of isolating the waste from people until the radioactivity has decayed to safe levels. However, isolating people from the wastes is a different problem, since we do not know what the future condition of society will be. The Human Interference Task Force was convened by the US Department of Energy to determine whether reasonable means exist (or could be developed) to reduce the likelihood of future human unintentionally intruding on radioactive waste isolation systems. The task force concluded that significant reductions in the likelihood of human interference could be achieved, for perhaps thousands of years into the future, if appropriate steps are taken to communicate the existence of the repository. Consequently, for two years the task force directed most of its study toward the area of long-term communication. Methods are discussed for achieving long-term communication by using permanent markers and widely disseminated records, with various steps taken to provide multiple levels of protection against loss, destruction, and major language/societal changes. Also developed is the concept of a universal symbol to denote Caution - Biohazardous Waste Buried Here. If used for the thousands of non-radioactive biohazardous waste sites in this country alone, a symbol could transcend generations and language changes, thereby vastly improving the likelihood of successful isolation of all buried biohazardous wastes.

  17. Projecting future solid waste management requirements on the Hanford Site

    International Nuclear Information System (INIS)

    Shaver, S.R.; Stiles, D.L.; Holter, G.M.; Anderson, B.C.

    1990-09-01

    The problem of treating and disposing of hazardous transuranic (TRU), low-level radioactive, and mixed waste has become a major concern of the public and the government. At the US Department of Energy's Hanford Site in Washington state, the problem is compounded by the need to characterize, retrieve, and treat the solid waste that was generated and stored for retrieval during the past 20 years. This paper discusses the development and application of a Solid Waste Projection Model that uses forecast volumes and characteristics of existing and future solid waste to address the treatment, storage, and disposal requirements at Hanford. The model uses a data-driven, object-oriented approach to assess the storage and treatment throughout requirements for each operation for each of the distinct waste classes and the accompanying cost of the storage and treatment operations. By defining the elements of each alternative for the total waste management system, the same database can be used for numerous analyses performed at different levels of detail. This approach also helps a variety of users with widely varying information requirements to use the model and helps achieve the high degree of flexibility needed to cope with changing regulations and evolving treatment and disposal technologies. 2 figs

  18. Food waste-to-energy conversion technologies: current status and future directions.

    Science.gov (United States)

    Pham, Thi Phuong Thuy; Kaushik, Rajni; Parshetti, Ganesh K; Mahmood, Russell; Balasubramanian, Rajasekhar

    2015-04-01

    Food waste represents a significantly fraction of municipal solid waste. Proper management and recycling of huge volumes of food waste are required to reduce its environmental burdens and to minimize risks to human health. Food waste is indeed an untapped resource with great potential for energy production. Utilization of food waste for energy conversion currently represents a challenge due to various reasons. These include its inherent heterogeneously variable compositions, high moisture contents and low calorific value, which constitute an impediment for the development of robust, large scale, and efficient industrial processes. Although a considerable amount of research has been carried out on the conversion of food waste to renewable energy, there is a lack of comprehensive and systematic reviews of the published literature. The present review synthesizes the current knowledge available in the use of technologies for food-waste-to-energy conversion involving biological (e.g. anaerobic digestion and fermentation), thermal and thermochemical technologies (e.g. incineration, pyrolysis, gasification and hydrothermal oxidation). The competitive advantages of these technologies as well as the challenges associated with them are discussed. In addition, the future directions for more effective utilization of food waste for renewable energy generation are suggested from an interdisciplinary perspective. Copyright © 2014 Elsevier Ltd. All rights reserved.

  19. Optimization of use of waste in the future energy system

    International Nuclear Information System (INIS)

    Muenster, Marie; Meibom, Peter

    2011-01-01

    Alternative uses of waste for energy production become increasingly interesting when considered from two perspectives, that of waste management and the energy system perspective. This paper presents the results of an enquiry into the use of waste in a future energy system. The analysis was performed using the energy system analysis model, Balmorel. The study is focused on Germany and the Nordic countries and demonstrates the optimization of both investments and production within the energy systems. The results present cost optimization excluding taxation concerning the use of waste for energy production in Denmark in a 2025 scenario with 48% renewable energy. Investments in a range of waste conversion technologies are facilitated, including waste incineration, co-combustion with coal, anaerobic digestion, and gasification. The most economically feasible solutions are found to be incineration of mixed waste, anaerobic digestion of organic waste, and gasification of part of the potential RDF (refuse derived fuel) for CHP (combined heat and power) production, while the remaining part is co-combusted with coal. Co-combustion mainly takes place in new coal-fired power plants, allowing investments to increase in comparison with a situation where only investments in waste incineration are allowed. -- Highlights: → The analysis is based on hourly chronological time steps, thereby taking dynamic properties of the energy system into account. → The system analyzed includes both the heat and the electricity market, which is important when analyzing e.g. CHP technologies. → The surrounding countries, which form part of the same electricity market, are included in the analysis. → New innovative Waste-to-Energy production plants have been modeled to allow for a more efficient and flexible use of waste. → The analysis includes economical optimization of operation and of investments in production and transmission of both electricity and heat.

  20. Existing and future international standards for the safety of radioactive waste disposal

    International Nuclear Information System (INIS)

    Linsley, G.

    1999-01-01

    In this paper the essential features of the current international safety standards are summarised and the issues being raised for inclusion in future standards are discussed. The safety standards of the IAEA are used as the basis for the review and discussion. The IAEA has established a process for establishing international standards of safety for radioactive waste management through its Radioactive Waste Safety Standards (RADWASS) programme. The RADWASS documents are approved by a comprehensive process involving regulatory and other experts from all concerned IAEA Member States. A system of committees for approving the IAEAs safety standards has been established. For radioactive waste safety the committee for review and approval is the Waste Safety Standards Advisory Committee (WASSAC). In 1995 the IAEA published 'The Principles of Radioactive Waste Management' as the top level document in the RADWASS programme. The report sets out the basis principles which most experts believe are fundamental to the safe management of radioactive wastes

  1. Current situation and future plans in radioactive waste management in Mexico

    International Nuclear Information System (INIS)

    Lopez, H.; Jimenez, M.

    1992-01-01

    A brief introduction is offered in this document in order to explain the importance which is given in Mexico to the safe management of radioactive wastes. The Secretaria de Energia, Minas e Industria Paraestatal is the organization responsible for this issue. Also, a brief historical background is offered so as to understand the evolution of these activities since they were originated. This background allows us to describe the present situation, which consists in a substantial change in the volume of produced radioactive wastes; in other words, before the present situation only the, nuclear wastes from the application of radioisotopes were generated whereas currently, with the starting of commercial operation of the first unit of Laguna Verde Nuclear Power Plant (LVNPP), large volumes of industrial radioactive wastes are being generated. A mention is given as well of the acquired experience during more than 20 years of waste management and of the technologies which have been applied or practiced in the use and disposal of such wastes. Finally, some general trends in relation to the future planning are indicated, which essentially consist in the siting and characterization of a site so as to, design and construct a permanent disposal facility in order to dispose the operational radioactive wastes from LVNPP

  2. Current and future prospects for heat recovery from waste in European district heating systems: A literature and data review

    International Nuclear Information System (INIS)

    Persson, Urban; Münster, Marie

    2016-01-01

    Municipal solid waste has seen increasing annual volumes for many decades in contemporary Europe and constitutes, if not properly managed, an environmental problem due to local pollution and greenhouse gas emissions. From an energy perspective, waste is also an alternative fuel for power and heat generation; energy recovery from waste represents an effective measure to reduce landfilling and avoid disposal emissions while simultaneously reducing the equivalent demand for primary energy supply. A key factor for obtaining the full synergetic benefits of this energy recovery is the presence of local heat distribution infrastructures, without which no large-scale recovery and utilisation of excess heat is possible. In this paper, which aims to estimate municipal solid waste volumes available for heat recovery in European district heating systems in 2030, a literature and data review is performed to establish and assess current and future EU (European Union) waste generation and management. Main conclusions are that more heat can be recovered from current Waste-to-Energy facilities operating at low average heat recovery efficiencies, that efficient incineration capacity is geographically concentrated, and that waste available for heat recovery in 2030 is equally determined by total generation volumes by this year as by future EU deployment levels of district heating. - Highlights: • European municipal solid waste time series data analysed from 1995 to 2012. • Review of modelling approaches to assess future European waste generation. • Weather corrected district heat data for EU Member States in 1995 and 2012. • Low average heat recovery efficiency in current European waste incineration. • Future heat recovery efficiencies as determinant as future generation volumes.

  3. Ethics Beyond Finitude: Responsibility towards Future Generations and Nuclear Waste Management

    International Nuclear Information System (INIS)

    Loefquist, Lars

    2008-01-01

    This dissertation has three aims: 1. To evaluate several ethical theories about responsibility towards future generations. 2. To construct a theory about responsibility towards future generations. 3. To carry out an ethical evaluation of different nuclear waste management methods. Five theories are evaluated with the help of evaluative criteria, primarily: A theory must provide future generations with some independent moral status. A theory should acknowledge moral pluralism. A theory should provide some normative claims about real-world problems. Derek Parfit's theory provides future generations with full moral status. But it is incompatible with moral pluralism, and does not provide reasonable normative claims about real-world problems. Brian Barry's theory provides such claims and a useful idea about risk management, but it does not provide an argument why future generations ought to exist. Avner de-Shalit's theory explains why they ought to exist; however, his theory can not easily explain why we ought to care for other people than those in our own community. Emmanuel Agius' theory gives an ontological explanation for mankind's unity, but reduces conflicts of interests to a common good. Finally, Hans Jonas' theory shifts the focus from the situation of future generations to the preconditions of human life generally. However, his theory presupposes a specific ontology, which might be unable to motivate people to act. The concluding chapters describe a narrative theory of responsibility. It claims that we should comprehend ourselves as parts of the common story of mankind and that we ought to provide future generations with equal opportunities. This implies that we should avoid transferring risks and focus on reducing the long-term risks associated with the nuclear waste

  4. ENGINEERING STUDY FOR THE 200 AREA EFFLUENT TREATMENT FACILITY (ETF) SECONDARY WASTE TREATMENT OF PROJECTED FUTURE WASTE FEEDS

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2004-01-01

    This report documents an engineering study conducted to evaluate alternatives for treating secondary waste in the secondary treatment train (STT) of the Hanford Site 200 Area Effluent Treatment Facility (ETF). The study evaluates ETF STT treatment alternatives and recommends preferred alternatives for meeting the projected future missions of the ETF. The preferred alternative(s) will process projected future ETF influents to produce a solid waste acceptable for final disposal on the Hanford Site. The main text of this report summarizes the ETF past and projected operations, lists the assumptions about projected operations that provide the basis for the engineering evaluation, and summarizes the evaluation process. The evaluation process includes identification of available modifications to the current ETF process, screens those modifications for technical viability, evaluates the technically viable alternatives, and provides conclusions and recommendations based on that evaluation

  5. Ethics Beyond Finitude: Responsibility towards Future Generations and Nuclear Waste Management

    Energy Technology Data Exchange (ETDEWEB)

    Loefquist, Lars

    2008-05-15

    This dissertation has three aims: 1. To evaluate several ethical theories about responsibility towards future generations. 2. To construct a theory about responsibility towards future generations. 3. To carry out an ethical evaluation of different nuclear waste management methods. Five theories are evaluated with the help of evaluative criteria, primarily: A theory must provide future generations with some independent moral status. A theory should acknowledge moral pluralism. A theory should provide some normative claims about real-world problems. Derek Parfit's theory provides future generations with full moral status. But it is incompatible with moral pluralism, and does not provide reasonable normative claims about real-world problems. Brian Barry's theory provides such claims and a useful idea about risk management, but it does not provide an argument why future generations ought to exist. Avner de-Shalit's theory explains why they ought to exist; however, his theory can not easily explain why we ought to care for other people than those in our own community. Emmanuel Agius' theory gives an ontological explanation for mankind's unity, but reduces conflicts of interests to a common good. Finally, Hans Jonas' theory shifts the focus from the situation of future generations to the preconditions of human life generally. However, his theory presupposes a specific ontology, which might be unable to motivate people to act. The concluding chapters describe a narrative theory of responsibility. It claims that we should comprehend ourselves as parts of the common story of mankind and that we ought to provide future generations with equal opportunities. This implies that we should avoid transferring risks and focus on reducing the long-term risks associated with the nuclear waste

  6. Nuclear Waste Vitrification in the U.S.: Recent Developments and Future Options

    International Nuclear Information System (INIS)

    Vienna, John D.

    2010-01-01

    Nuclear power plays a key role in maintaining current world wide energy growth while minimizing the greenhouse gas emissions. A disposition path for used nuclear fuel (UNF) must be found for this technology to achieve its promise. One likely option is the recycling of UNF and immobilization of the high-level waste (HLW) by vitrification. Vitrification is the technology of choice for immobilizing HLW from defense and commercial fuel reprocessing around the world. Recent advances in both recycling technology and vitrification show great promise in closing the nuclear fuel cycle in an efficient and economical fashion. This article summarizes the recent trends developments and future options in waste vitrification for both defense waste cleanup and closing the nuclear fuel cycle in the U.S.

  7. Future extension of the Swedish repository for low and intermediate level waste (SFR)

    International Nuclear Information System (INIS)

    Carlsson, Jan

    2006-01-01

    The existing Swedish repository for low and intermediate level waste (SFR) is licensed for disposal of short-lived waste originated from operation and maintenance of Swedish nuclear power plants. The repository is foreseen to be extended to accommodate short-lived waste from the future decommissioning of the Nuclear Power Plants. Long-lived waste from operation, maintenance and eventually decommissioning will be stored some years before disposal in a geological repository. This repository can be build either as a further extension of the SFR facility or as a separate repository. This paper discusses the strategy of a step-wise extended repository where the extensions are performed during operation of the existing parts of the repository. It describes the process for licensing new parts of the repository (and re-license of the existing parts). (author)

  8. Characterization and inventories of nuclear materials and wastes for possible future energy scenarios

    International Nuclear Information System (INIS)

    Arthur, E.D.

    1997-10-01

    Awareness of the total materials inventory and materials balance associated with differing methods for energy generation is part of present day concerns associated with disparate areas that include atmospheric emissions, resource utilization, health effects, and both current and long term hazards and risks. Nuclear energy, for a number of decades, has been the recipient of significant scrutiny concerning the materials and wastes it generates, particularly in the context of long term solutions to such issues. This paper examines the nuclear materials and waste generation for nuclear energy scenarios spanning the coming century. The paper also briefly addresses wastes (in the form of emissions) from other energy sources and examines requirements associated with backend energy system materials management. Possible future requirements pertaining to CO 2 management are found to place conditions upon waste management generally similar to those for nuclear waste. One example of material flows for the case of coal generation of electricity coupled with carbon sequestration is also given

  9. DOE waste management program-current and future

    International Nuclear Information System (INIS)

    Coleman, J.A.

    1993-01-01

    The back end of the nuclear fuel cycle, as well as many operations in the Department of Energy, involves management of radioactive and hazardous waste and spent nuclear fuel. Described herein is the current and anticipated Department's Waste Management Program and general information about the Program for managing and disposing of waste that will illustrate the importance of air cleaning and treatment in assuring protection of the public and our environment. The structure and responsibilities of the Office of Environmental Restoration and Waste Management (EM) are described. The categories of waste managed by the Office of Waste Management (OWM) are defined. The problems of waste management, waste minimization, and waste treatment, storage, and disposal are discussed. 4 figs

  10. Decommissioning and Waste Disposal Programme of NPP Krsko - How to Proceed in the Future

    International Nuclear Information System (INIS)

    Mele, I.; Zeleznik, N.; Levanat, I.; Lokner, V.

    2006-01-01

    By the agreement between Slovenia and Croatia on the ownership and exploitation of the NPP Krsko, which is effective since March 2003, the decommissioning and the disposal of spent fuel and low and intermediate level waste from NPP Krsko is the responsibility of both countries. In article 10 the agreement requires that within a year after putting it into force both parties jointly prepare a decommissioning and waste disposal programme with more detailed elaboration of these issues. According to these requirements such a programme was prepared by the waste management organisations from both countries - APO from Croatia and ARAO from Slovenia - and in March 2004 submitted to the Intergovernmental Commission for adoption. Later in 2004 the document was accepted also by both Governments and in Croatia also by the Parliament. By the agreement it is also anticipated that the decommissioning and waste disposal programmes be revised at least every 5 years. Such an approach is quite common and practiced in many countries, and some countries prepare revisions even more frequently. The purpose of these new revisions is two folded: on one hand to improve the technical solutions for the decommissioning as well as for waste disposal by including new or better known data and new technological developments and experience, and on the other hand to update the cost calculation of these future nuclear liabilities. Having in mind that these cost estimations are made for the rather distant future it is extremely important that regular updating and adjustment of estimates be performed in order to meet the future needs. Although the Decommissioning and Waste Disposal Programme has just recently passed the adoption procedure and its implementation has not yet been fully achieved, the time of the next revision is approaching fast. To make good progress in the next revision serious preparations including some strategic decisions should start immediately. The programme from 2004 was prepared

  11. Intended long term performances of cementitious engineered barriers for future storage and disposal facilities for radioactive wastes in Romania

    Directory of Open Access Journals (Sweden)

    Sociu F.

    2013-07-01

    Full Text Available Considering the EU statements, Romania is engaged to endorse in the near future the IAEA relevant publications on geological repository (CNCANa, to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Currently, for example, spent fuel is wet stored for 6 years and after this period it is transported to dry storage in MACSTOR-200 (a concrete monolithic module where it is intended to remain at least 50 years. The present situation for radioactive waste management in Romania is reviewed in the present paper. Focus will be done on existent disposal facilities but, also, on future facilities planned for storage / disposal of radioactive wastes. Considering specific data for Romanian radioactive waste inventory, authors are reviewing the advance in the radioactive waste management in Romania considering its particularities. The team tries to highlight the expected limitations and unknown data related with cementitious engineered barriers that has to be faced in the near future incase of interim storage or for the upcoming long periods of disposal.

  12. Experience gained and future activities in radioactive waste management in Uruguay

    International Nuclear Information System (INIS)

    Montanez, O.; Blanco, D.

    1996-01-01

    The origin and the characteristics of the radioactive waste produced in the Nuclear Research Center are described, as well as those resulting from the application of radioisotopes in different external institutions. The methods utilized in the waste management, and the future actions that will be performed, in order to solve the specific problems of the management are also explained. The Nuclear Research Center is a university institution that has many research opportunities in different applications of radioisotopes: in medicine, biology, industry, agronomy and radiochemistry, and beside that, was here where the 10 km research reactor, that nowadays is being decommissioned, was in operation. Due to the infrastructure of this center, it has been usually responsible for the waste management produced in other institutions, but at present the capacity was exceeded, so that a program was carried out in order to confront this problem. The program for the radioactive waste management qualifies the personnel in formation courses and receives the support of specialists of the IAEA. It also records the sealed radiation sources using a data base by means of a computer to exhausted sources, developed by the same organization. The country regulating organization is carrying out a study to establish a national policy related to the treatment and disposal of wastes. (authors). 4 refs. 1 tab

  13. Future health physics prospects in high-level nuclear waste management

    International Nuclear Information System (INIS)

    Waite, D.A.; Mayberry, J.J.

    1986-01-01

    The objective of this presentation is to provide an overview of health physics activities anticipated to be required at a high-level nuclear waste repository and to project the numbers of health physics personnel expected to be required to carry out these activities. Health physics personnel receiving consideration in the projections include the health physics manager, shift supervisors, area supervisors, health physicists, and technologists. Phases of the repository addressed are construction, operation, retrieval, and decommissioning. Specific topics discussed in the process of developing the projections are: (a) the basic features of a geologic repository, (b) the staffing requirements of such a repository, (c) health physics involvement in repository operations, and (d) the anticipated schedule for operation of repositories in the United States. A quantitative assessment of future health physics prospects in high-level nuclear waste management is included

  14. Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

    International Nuclear Information System (INIS)

    McAulay, I.R.

    1996-01-01

    Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials

  15. Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

    Energy Technology Data Exchange (ETDEWEB)

    McAulay, I R [Trinity Coll., Dublin (Ireland). Physical Lab.

    1996-10-01

    Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials.

  16. Informing future societies about nuclear waste repositories

    International Nuclear Information System (INIS)

    Jensen, M.

    1994-01-01

    In 1990 a working group of the NKS (the Nordic nuclear safety program) was formed and give the task of established a basis for a common Nordic view of the need for information conservation for nuclear waste repositories. The Group investigated what tipy of information should be conserved; in what form the information should be kept; the quality of the information; and the problems of future retrieval of information, including retrieval after very long periods of time. Topics covered include the following: scientific aspects including social context of scientific solutions; information management; systems for conservation and retrieval of information including the problems of prediction; archives, markers, archives vs. markers, and continuing processes in society; Archive media including paper documents, microfilm, digital media, media lifetimes; and finally conclusions and recommendations

  17. Implications of synergetic indirect effects and increased flexibility for municipal solid waste management within future framework conditions

    DEFF Research Database (Denmark)

    Cimpan, Ciprian; Rothmann, Marianne; Wenzel, Henrik

    and compared against a large variety of background system scenarios, consisting of the most probable future development of the Danish energy system (and surrounding countries) towards 2050. Specific focus was placed on identification and modelling of possible indirect effects on adjoining systems that would......Life cycle assessments addressing municipal solid waste management systems (MSWMS) most often represent and evaluate these systems or compare isolated technological and management solutions in a much too simplistic interaction with their surroundings, accounting for a minimum of probable future...... potential (GWP) of different waste management strategies. Within the study reported here, a number of alternative MSWMS were simulated and evaluated, comprising combinations of separate collection and different downstream treatment/handling approaches for remaining residual waste, including advanced...

  18. Persistent toxic substances released from uncontrolled e-waste recycling and actions for the future.

    Science.gov (United States)

    Man, Ming; Naidu, Ravi; Wong, Ming H

    2013-10-01

    The Basel Convention on the Control of Transboundary Movement of Hazardous Wastes and their Disposal was adopted on March 22, 1989 and enforced on May 5, 1992. Since then, the USA, one of the world's largest e-waste producers, has not ratified this Convention or the Basel Ban Amendment. Communities are still debating the legal loophole, which permits the export of whole products to other countries provided it is not for recycling. In January 2011, China's WEEE Directive was implemented, providing stricter control over e-waste imports to China, including Hong Kong, while emphasizing that e-waste recycling is the producers' responsibility. China is expected to supersede the USA as the principal e-waste producer, by 2020, according to the UNEP. Uncontrolled e-waste recycling activities generate and release heavy metals and POPs into the environment, which may be re-distributed, bioaccumulated and biomagnified, with potentially adverse human health effects. Greater efforts and scientific approaches are needed for future e-product designs of minimal toxic metal and compound use, reaping greater benefits than debating the definition and handling responsibilities of e-waste recycling. Copyright © 2012 Elsevier B.V. All rights reserved.

  19. Application of advanced remote systems technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at Oak Ridge National Laboratory (ORNL) has been advancing the technology of remote handling and remote maintenance for in-cell systems planned for future nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor is directly applicable to the proposed in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The application of teleoperated, force-reflecting servomanipulators with television viewing could be a major step forward in waste handling facility design. Primary emphasis in the current program is the operation of a prototype remote handling and maintenance system, the advanced servomanipulator (ASM), which specifically addresses the requirements of fuel reprocessing and waste handling with emphasis on force reflection, remote maintainability, reliability, radiation tolerance, and corrosion resistance. Concurrent with the evolution of dexterous manipulators, concepts have also been developed that provide guidance for standardization of the design of the remotely operated and maintained equipment, the interface between the maintenance tools and the equipment, and the interface between the in-cell components and the facility

  20. Towards Rational Decision-Making in Secondary Education.

    Science.gov (United States)

    Cohn, Elchanan

    Without a conscious effort to achieve optimum resource allocation, there is a real danger that educational resources may be wasted. This document uses input-output analysis to develop a model for rational decision-making in secondary education. (LLR)

  1. A systematic approach for future solid waste cleanup activities at the Hanford Site

    International Nuclear Information System (INIS)

    Dirks, L.L.; Konynenbelt, H.S.; Hladek, K.L.

    1995-02-01

    This paper describes the systematic approach to the treatment, storage, and disposal system (TSD) planning and management that has been developed and implemented by Hanford's Solid Waste Program. The systematic approach includes: collecting the forecast and waste inventory data; defining Hanford's TSD system; studying and refining the TSD system by using analysis tools; and documenting analysis results. The customers responsible for planning, funding, and managing future solid waste activities have driven the evolution of the solid waste system. Currently, all treatment facilities are several years from operating. As these facilities become closer to reality, more detailed systems analysis and modeling will be necessary to successfully remediate solid waste at the Site. The tools will continue to be developed in detail to address the complexities of the system as they become better defined. The tools will help determine which facility lay-outs are most optimal, will help determine what types of equipment should be used to optimize the transport of materials to and from each TSD facility, and will be used for performing life-cycle analysis. It is envisioned that in addition to developing the tools to be adapted to the more specific facility design issues, this approach will also be used as an example for other waste installations across the DOE complex

  2. Future waste treatment and energy systems – examples of joint scenarios

    DEFF Research Database (Denmark)

    Münster, Marie; Finnveden, G.; Wenzel, H.

    2013-01-01

    of scenarios is recommended, too, in order to adapt to the methods and tools of different disciplines, such as developing predictive scenarios with general equilibrium tools and analysing explorative scenarios with energy system analysis tools. Furthermore, as marginals identified in differing future......Development and use of scenarios for large interdisciplinary projects is a complicated task. This article provides practical examples of how it has been carried out in two projects addressing waste management and energy issues respectively. Based on experiences from the two projects......, recommendations are made for an approach concerning development of scenarios in projects dealing with both waste management and energy issues. Recommendations are given to develop and use overall scenarios for the project and leave room for sub-scenarios in parts of the project. Combining different types...

  3. PLASMA GASIFICATION – THE WASTE-to-ENERGY SOLUTION FOR THE FUTURE

    Directory of Open Access Journals (Sweden)

    Birsan N.

    2014-12-01

    Full Text Available Plasma WtE is currently subject of extensive research and a number of companies across the globe are trying to develop a suitable, eco-friendly and efficient WtE technology for the future. While all of these companies are still working on concept designs or small-scale prototypes, there is one company already building large industrial scale plasma gasifiers around the globe to treat MSW, Industrial and Toxic waste all together. In 1999 in Japan, Hitachi Metals and Westinghouse Plasma Corp (“WPC” built the World’s First commercial demonstration plasma WtE plant. Hitachi Metals operated the plant for one year on municipal solid waste and obtained a certification from the Japan Waste Research Foundation (JWRF. Subsequently, Hitachi Metals leveraged this success into the two commercial plants at Mihama-Mikata and Utashinai in Japan, both having at the very core the now proven Westinghouse Plasma gasification technology. For more than 20 years, Westinghouse Plasma Corp (WPC has been leading the technology platform for converting the world’s waste into clean energy for a healthier planet. The WPC technology makes landfills obsolete and replaces Incineration as the primary process for WtE. The WPC technology already operates in three reference plants around the world and other three new commercial plants are under construction (two plants of 1000 tons/day in UK and a 650 tons/day in China, all three designed to convert municipal solid waste to electricity and district heat, in the most efficient and environmental-friendly manner.

  4. 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.)

  5. Persistent toxic substances released from uncontrolled e-waste recycling and actions for the future

    International Nuclear Information System (INIS)

    Man, Ming; Naidu, Ravi; Wong, Ming H.

    2013-01-01

    The Basel Convention on the Control of Transboundary Movement of Hazardous Wastes and their Disposal was adopted on March 22, 1989 and enforced on May 5, 1992. Since then, the USA, one of the world's largest e-waste producers, has not ratified this Convention or the Basel Ban Amendment. Communities are still debating the legal loophole, which permits the export of whole products to other countries provided it is not for recycling. In January 2011, China's WEEE Directive was implemented, providing stricter control over e-waste imports to China, including Hong Kong, while emphasizing that e-waste recycling is the producers' responsibility. China is expected to supersede the USA as the principal e-waste producer, by 2020, according to the UNEP. Uncontrolled e-waste recycling activities generate and release heavy metals and POPs into the environment, which may be re-distributed, bioaccumulated and biomagnified, with potentially adverse human health effects. Greater efforts and scientific approaches are needed for future e-product designs of minimal toxic metal and compound use, reaping greater benefits than debating the definition and handling responsibilities of e-waste recycling. - Highlights: ► We recommended to ban uses of deca-BDE in addition to penta- and octa-BDEs. ► We suggested to replace PVC in electronic products with non-chlorinated polymers. ► Spend less time on debating responsibilities and definition of e-waste and recycling. ► Proposed to work more on eliminating sources and potentials of toxic substances

  6. Managing wastes from the atomic age and into the future: programs, plans and challenges

    International Nuclear Information System (INIS)

    Miller, J.M.

    2011-01-01

    implementation schedules to address the current waste inventory and future wastes from both AECL's operational and decommissioning activities. This paper provides an overview of AECL's waste management practices, AECL's low- and intermediate-level waste inventory, current activities for the management of those wastes, and the plans for moving forward. (author)

  7. Taxes on waste today - and in the future

    International Nuclear Information System (INIS)

    2002-01-01

    On 1 January 2000 a tax was introduced on waste disposed in landfill sites. The tax rate was set at SEK 250 per tonne of waste and was raised to SEK 288 per tonne on 1 January 2002. The purpose of the tax is to increase the economic incentives to use waste treatment methods that are preferable from environmental and natural resources perspectives. The evaluation comes to the conclusion that, on the whole, the waste tax functions in the manner expected. One year after the introduction of the tax there has been a reduction of approximately 300 k tonnes, which is about 6 per cent of the quantity of waste brought to taxable landfill sites in the year before the tax was introduced. In the same period, increased quantities of material have been recycled and more energy recovered from waste. Since the tax on waste is based on weight, there have been particularly striking reductions in the landfill disposal of heavy materials that can be used as filling and construction material. Energy taxation and waste tax have had the combined effect of making it possible to keep waste reception charges lower at waste incineration plants than at landfill sites. The extension of district heating networks provides a market outlet for virtually all the heat generated by waste incineration. The ban on landfill of sorted combustible waste, which has been in force since 1 January 2002, has great significance for the investments that are now being made in an expansion of incineration capacity. This is also true for biological treatment of waste, which has often received support via local investment programmes. The waste tax can also be expected to reinforce the effect of the landfill ban on organic waste that is due to be introduced on 1 January 2005. Waste tax is charged on landfilling of ash from incineration. This also applies to ash from the burning of biofuels. In the spring of 2001, the National Board of Forestry issued recommendations for extraction of forest fuels and compensatory

  8. Waste Crime – Waste Risks: Gaps in Meeting the Global Waste Challenge : A UNEP Rapid Response Assessment

    NARCIS (Netherlands)

    Ieva Rucevska; Christian Nelleman; Nancy Isarin; Wanhua Yang; Ning Liu; Kelly Yu; Siv Sandnaes; Katie Olley; Howard McCann; Leila Devia; L.C.J. Bisschop (Lieselot); Denise Soesilo; Tina Schoolmeester; Rune Hendriksen; Rannveig Nilsen; Claire Eamer

    2015-01-01

    markdownabstractMore than ever, our future depends upon how we manage the future of our waste. As an integrated part of sustainable development, effective waste management can reduce our global footprint. Ignoring or neglecting the challenges of waste, however, can lead to significant health,

  9. Future Shock in Nuclear Waste Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Frishman, Steve [Nevada Agency for Nuclear Projects, Carson City, NV (United States)

    2006-09-15

    The United States Environmental Protection Agency (EPA) astonished many in the high-level nuclear waste management community when it proposed, in August 2005, new Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada. The new standards set a compliance period of one million years for a Yucca Mountain high-level nuclear waste repository. The first 10,000 years after repository closure would be governed by a health-based individual dose limit of 15 millirems per year (0.15 mSv/year), with the remaining time period subject to a background-based individual dose limit of 350 millirems per year (3.5 mSv/year). EPA's proposed standards for a Yucca Mountain nuclear waste repository represent an astonishing break with principles embedded in regulatory policies for protection of the public from radiation effects imposed by activities such as generation of electricity from nuclear power reactors and storage and disposal of radioactive wastes.

  10. Specific transport and storage solutions: Waste management facing current and future stakes of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Deniau, Helene; Gagner, Laurent; Gendreau, Francoise; Presta, Anne

    2006-01-01

    development process; - Current solutions proposed by COGEMA LOGISTICS; - Transport of Low Level and Very Low Level waste (LLW and VLLW); - Shipment of large volumes; - Non-reusable transport packaging; - Packaging transport permit the storage in final disposal area; - A steep increase of transport flows in the next 10 years; - Future challenges, waste from dismantling operations; - Transport packaging of IP 2 type and IP 2 package; - Some examples of standardized packages; - DV78 Package; - CC102 over pack; - A solution for liquid waste from NPPs, TNTMCIEL; - Transport of Intermediate Level Waste (ILW) and High Level Waste (HLW); - Alpha waste (or TRU waste); - TNTMGEMINI; - RD 26 package; - Bituminized waste (ILW): the TNTM833; - Technological waste in CBFC'2 (ILW): the TNTM837; - Universal Canisters for Vitrified waste (HLW) and Compacted waste (ILW); - Vitrified waste (HLW); - Transport solutions for CSD-V canisters: the TNTM28 VT; - Dual purpose solutions for CSD-V canisters, the TS 28; - CSD-V programme of return; - Compacted waste (ILW): the TNTM843; - Some future stakes and new developments. The following conclusions completes the paper. COGEMA LOGISTICS experience in designing packages and transporting nuclear materials is part of the COGEMA / AREVA waste management policy, which aims to waste volume reduction through waste sorting and packaging in universal canisters or standard waste containers. For the design and manufacture of special shipping casks, as for nuclear transportation and storage, COGEMA LOGISTICS tailors its solutions to its international customers' requirements. Personnel safety, transportation safety and environmental protection are put first. These reasons have lead COGEMA LOGISTICS to become the world's leading designer of nuclear fuel packages, with unique expertise in designing packages for back-end transportation and storage of nuclear materials. Beyond being a transport company and packaging designer, COGEMA LOGISTICS is a partner implementing

  11. Persistent toxic substances released from uncontrolled e-waste recycling and actions for the future

    Energy Technology Data Exchange (ETDEWEB)

    Man, Ming [Croucher Institute for Environmental Sciences, Hong Kong Baptist University (Hong Kong); Naidu, Ravi [Cooperative Research Centre for Contamination Assessment and Remediation of Environments (CRC CARE), University of South Australia (Australia); Wong, Ming H., E-mail: mhwong@hkbu.edu.hk [Croucher Institute for Environmental Sciences, Hong Kong Baptist University (Hong Kong)

    2013-10-01

    The Basel Convention on the Control of Transboundary Movement of Hazardous Wastes and their Disposal was adopted on March 22, 1989 and enforced on May 5, 1992. Since then, the USA, one of the world's largest e-waste producers, has not ratified this Convention or the Basel Ban Amendment. Communities are still debating the legal loophole, which permits the export of whole products to other countries provided it is not for recycling. In January 2011, China's WEEE Directive was implemented, providing stricter control over e-waste imports to China, including Hong Kong, while emphasizing that e-waste recycling is the producers' responsibility. China is expected to supersede the USA as the principal e-waste producer, by 2020, according to the UNEP. Uncontrolled e-waste recycling activities generate and release heavy metals and POPs into the environment, which may be re-distributed, bioaccumulated and biomagnified, with potentially adverse human health effects. Greater efforts and scientific approaches are needed for future e-product designs of minimal toxic metal and compound use, reaping greater benefits than debating the definition and handling responsibilities of e-waste recycling. - Highlights: ► We recommended to ban uses of deca-BDE in addition to penta- and octa-BDEs. ► We suggested to replace PVC in electronic products with non-chlorinated polymers. ► Spend less time on debating responsibilities and definition of e-waste and recycling. ► Proposed to work more on eliminating sources and potentials of toxic substances.

  12. Heat supply from municipal solid waste incineration plants in Japan: Current situation and future challenges.

    Science.gov (United States)

    Tabata, Tomohiro; Tsai, Peii

    2016-02-01

    The use of waste-to-energy technology as part of a municipal solid waste management strategy could reduce the use of fossil fuels and contribute to prevention of global warming. In this study, we examined current heat and electricity production by incineration plants in Japan for external use. Herein, we discuss specific challenges to the promotion of heat utilisation and future municipal solid waste management strategies. We conducted a questionnaire survey to determine the actual conditions of heat production by incineration plants. From the survey results, information of about 498 incineration plants was extracted. When we investigated the relationship between heat production for external use and population density where incineration plants were located, we found that regions with a population density situation. © The Author(s) 2015.

  13. Hydrothermal liquefaction of agricultural and forestry wastes: state-of-the-art review and future prospects.

    Science.gov (United States)

    Cao, Leichang; Zhang, Cheng; Chen, Huihui; Tsang, Daniel C W; Luo, Gang; Zhang, Shicheng; Chen, Jianmin

    2017-12-01

    Hydrothermal liquefaction has been widely applied to obtain bioenergy and high-value chemicals from biomass in the presence of a solvent at moderate to high temperature (200-550°C) and pressure (5-25MPa). This article summarizes and discusses the conversion of agricultural and forestry wastes by hydrothermal liquefaction. The history and development of hydrothermal liquefaction technology for lignocellulosic biomass are briefly introduced. The research status in hydrothermal liquefaction of agricultural and forestry wastes is critically reviewed, particularly for the effects of liquefaction conditions on bio-oil yield and the decomposition mechanisms of main components in biomass. The limitations of hydrothermal liquefaction of agricultural and forestry wastes are discussed, and future research priorities are proposed. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. Nuclear wastes future: results and forecasting

    International Nuclear Information System (INIS)

    2001-01-01

    Since many years, the CEA is greatly involved in the research programs on the long-dated management of radioactive wastes. This document presents the CEA development in the following domains: the spent fuel processing, the high separation process, the environmental behavior of wastes packages, the glass performance and the apatites behavior in the new matrix. (A.L.B.)

  15. Waste biorefineries using filamentous ascomycetes fungi: Present status and future prospects.

    Science.gov (United States)

    Ferreira, Jorge A; Mahboubi, Amir; Lennartsson, Patrik R; Taherzadeh, Mohammad J

    2016-09-01

    Filamentous ascomycetes fungi have had important roles in natural cycles, and are already used industrially for e.g. supplying of citric, gluconic and itaconic acids as well as many enzymes. Faster human activities result in higher consumption of our resources and producing more wastes. Therefore, these fungi can be explored to use their capabilities to convert back wastes to resources. The present paper reviews the capabilities of these fungi in growing on various residuals, producing lignocellulose-degrading enzymes and production of organic acids, ethanol, pigments, etc. Particular attention has been on Aspergillus, Fusarium, Neurospora and Monascus genera. Since various species are used for production of human food, their biomass can be considered for feed applications and so biomass compositional characteristics as well as aspects related to culture in bioreactor are also provided. The review has been further complemented with future research avenues. Copyright © 2016 The Authors. Published by Elsevier Ltd.. All rights reserved.

  16. Radioactive waste management

    International Nuclear Information System (INIS)

    1984-07-01

    The purpose of this document is to set out the Government's current strategy for the long term in the management of radioactive wastes. It takes account of the latest developments, and will be subject to review in the light of future developments and studies. The subject is discussed under the headings: what are radioactive wastes; who is responsible; what monitoring takes place; disposal as the objective; low-level wastes; intermediate-level wastes; discharges from Sellafield; heat generating wastes; how will waste management systems and procedures be assessed; how much more waste is there going to be in future; conclusion. (U.K.)

  17. From weapons to waste: The future of the nuclear weapons complex

    International Nuclear Information System (INIS)

    Wasserman Goodman, Sherri

    1992-01-01

    This paper examines how decision-making power has shifted within the nuclear weapons complex, from the federal government operating agency, in which power was originally vested by the Atomic Energy Act, to the states and to regulatory authorities. Additionally, when the original operating agency, the Atomic Energy Commission (AEC), was abolished in the 1970s, substantial decision-making power shifted from Washington to the field sites. This paper identifies the needs for future materials and weapons production, and recommends that restart of old plants be abandoned as no longer militarily necessary. Instead, the U. S. should take advantage of what may be a unique opportunity to 'leapfrog' to new, smaller, technologically-advanced plants that will meet the needs of the nuclear arsenal in the post-Cold War world. This paper then looks at the current state of DOE's environmental restoration/waste management program, and the technological, legal and political problems it faces in trying to accomplish its mission of cleaning up all nuclear weapons sites. This paper argues that the U. S. government no longer has the exclusive authority to make and carry out critical decisions affecting a cleanup program that will cost the U. S. over $200 billion over the next 20-40 years. Moreover, there are competing theories about the principles that should guide the cleanup program. Finally, the author examines alternative futures for the DOE'S environmental restoration/waste management program. (author)

  18. Future waste treatment and energy systems – examples of joint scenarios

    International Nuclear Information System (INIS)

    Münster, M.; Finnveden, G.; Wenzel, H.

    2013-01-01

    Highlights: • Approach for use of scenarios dealing with both waste management and energy issues. • Overall scenarios for the common project and sub-scenarios in parts of the project. • Combining different types of scenarios to the tools of different disciplines. • Use of explorative external scenarios based on marginals for consequential LCA. - Abstract: Development and use of scenarios for large interdisciplinary projects is a complicated task. This article provides practical examples of how it has been carried out in two projects addressing waste management and energy issues respectively. Based on experiences from the two projects, recommendations are made for an approach concerning development of scenarios in projects dealing with both waste management and energy issues. Recommendations are given to develop and use overall scenarios for the project and leave room for sub-scenarios in parts of the project. Combining different types of scenarios is recommended, too, in order to adapt to the methods and tools of different disciplines, such as developing predictive scenarios with general equilibrium tools and analysing explorative scenarios with energy system analysis tools. Furthermore, as marginals identified in differing future background systems determine the outcomes of consequential life cycle assessments (LCAs), it is considered advisable to develop and use explorative external scenarios based on possible marginals as a framework for consequential LCAs. This approach is illustrated using an on-going Danish research project

  19. Innovative waste management solutions: An outlook for the future

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    At a conference on various aspects of waste management, papers were presented on the effects of landfills, plastic debris in the marine environment, skills development and training in the waste industry, composting, remediation of contaminated soils, disposal methods, sludge derived byproducts, recycling, waste management economics, municipal solid waste management, ship-generated waste, managing waste in national parks, and septic tank sludge treatment. Separate abstracts have been prepared for five papers from this conference.

  20. The potential role of waste biomass in the future urban electricity system

    OpenAIRE

    Jiang, Yu; Werf, van der, Edwin; Ierland, van, Ekko C.; Keesman, Karel J.

    2017-01-01

    The share of intermittent renewable electricity (IRE) in the future urban electricity system is expected to increase significantly. Sufficient back-up capacity is needed in the period when IRE output is low. Bioenergy is both dispatchable and carbon-neutral, and can hence be a promising option to back up IRE. The objective of this study is to explore the potential of urban waste biomass in backing up IRE in an urban electricity system. An urban electricity system model is developed to project...

  1. Nuclear waste/nuclear power: their futures are linked

    International Nuclear Information System (INIS)

    Skoblar, L.T.

    1981-01-01

    This paper briefly reviews current aspects of radioactive waste disposal techniques and transportation. Addressed are high-level and low-level radioactive wastes, interim spent fuel storage and transportation. The waste options being explored by DOE are listed. Problems of public acceptance will be more difficult to overcome than technical problems

  2. Program planning for future improvement in managing ORNL's radioactive wastes

    International Nuclear Information System (INIS)

    1982-01-01

    This report is intended to serve as a reference document and guide in developing the long-term improvements section of ORNL's radioactive waste management plan. The report reviews ORNL's operations and future program needs in terms of currently applicable DOE regulations and also in terms of regulations and accepted practices of the commerical sector of the nuclear power industry so that the impact of potential future adoption of these regulations and standards on ORNL's operations can be fully evaluated. The principal conclusion reached after reviewing ORNL's waste management operations is that these operations are currently being conducted in a manner that does not endanger the health or safety of workers or the general public and that does not have an adverse effect on the environment. Although nineteen specific problem areas have been identified all of these problems can be attributed to one of the following: a) the legacy of past practices; b) gradual deterioration of systems which have reached (or are near to reaching) the end of their reasonable design lives; and c) potential changes in regulations applicable to ORNL. All of the programs designed to improve or correct these problem areas could be accomplished within a four year period. However, given current limitations on manpower and capital, these programs would more likely be spread out over a five to ten year period of time if they were all to be undertaken. The cost of undertaking all of these projects concurrently is estimated to be between 60 and 100 million dollars. Due to the many unknowns and uncertainties associated with the problem areas, actual total costs for specific projects could vary from those presented in this report by as much as 300 percent

  3. Current and future prospects for heat recovery from waste in European district heating systems: A literature and data review

    DEFF Research Database (Denmark)

    Persson, Urban; Münster, Marie

    2016-01-01

    Municipal solid waste has seen increasing annual volumes for many decades in contemporary Europe and constitutes, if not properly managed, an environmental problem due to local pollution and greenhouse gas emissions. From an energy perspective, waste is also an alternative fuel for power and heat...... to establish and assess current and future EU (European Union) waste generation and management. Main conclusions are that more heat can be recovered from current Waste-to-Energy facilities operating at low average heat recovery efficiencies, that efficient incineration capacity is geographically concentrated...... heat distribution infrastructures, without which no large-scale recovery and utilisation of excess heat is possible. In this paper, which aims to estimate municipal solid waste volumes available for heat recovery in European district heating systems in 2030, a literature and data review is performed...

  4. Waste management in future. Partitioning and transmutation (P and T)

    International Nuclear Information System (INIS)

    Calic, D.

    2005-01-01

    Current research and development (R and D) in radioactive waste management is mainly associated with the quantities and toxicity of high level waste and spent fuel. One of the solutions that already exists, but has not yet reached scientific and technological maturity, is the process of partitioning and transmutation (P and T). Partitioning is the selective separation of radiotoxic isotopes from reprocessing streams. After the successive partitioning has been done, the long-lived radionuclides are converted into shorter-lived or stable nuclides by process called transmutation. P and T can reduce the radiotoxic inventory of spent fuel by a factor of 100 to 1000 and can achieve the reduction of time needed to reach the radioactivity level of the uranium ore from 100,000 to 5000 years. To achieve this, the separation of plutonium, minor actinides and long-lived fission products has to be implemented as early as possible in the fuel cycle strategy. Currently, P and T is still at the research and development stage and it needs to be scaled up, before it can be introduced on an industrial scale, therefore the paper will present the current status of the development of P and T and plans for the future. (author)

  5. Social transactions with future generations for the management of high level radioactive waste in deep repositories: Reflections on institutional control and retrievability

    International Nuclear Information System (INIS)

    Heriard Dubreuil, G.; Schieber, C.; Schneider, T.; Viala, M.

    1999-01-01

    The management of high level radioactive waste and spent fuel is a key issue and one of the most sensitive aspect of radioactive waste management. Recognising that it is the responsibility of our generation to find a way to isolate the waste, deep geological disposals have been envisaged to provide a definitive solution to the problem, in order to avoid 'undue burden on future generations'. However, even if they are buried, the wastes still exist and human intrusion is still possible as well as releases into the environment in the very far future. At the same time, the ongoing reflections on the ethical aspects of disposals show that it is of great worth that we guarantee future generations the same right of control and responsibility that we ourselves enjoy. This paper presents some reflections on the social transactions associated with the management and design of geological repositories. It is focused on the mission of institutional control in the transmission to future generation of a safety patrimony, composed of the know-how and techniques that permit the human community to 'domesticate' and control the risk. As it appears that the efficiency and the confidence in the control system rely mainly on the capability of implementing corrective actions, some considerations on the role, the consequences and the implementation of retrievability are also presented

  6. The application of advanced remote systems technology to future waste handling facilities: Waste Systems Data and Development Program

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future US nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two FWMS major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment. 5 refs., 7 figs

  7. Operation of a low-level waste disposal facility and how to prevent problems in future facilities

    International Nuclear Information System (INIS)

    Di Sibio, R.

    1985-01-01

    Operation of a low-level waste facility is an ever increasing problem nationally, and specifically one that could grow to crisis proportion in Pennsylvania. There have been, nevertheless, a variety of changes over the years in the management of low level radioactive waste, particularly with regard to disposal facilities that can avert a crisis condition. A number of companies have been organized thru possible a broad range of services to the nuclear industry, including those that emphasize solidification of waste materials, engineering services, waste management, and transportation to disposal sites across the United States. This paper addresses one particular site and the problems which evolved at that site from an environmental perspective. It is important that it is clearly understood that, although these problems are resolvable, the lessons learned here are critical for the prevention of problems at future facilities. The focus of this paper is on the Maxey Flats, Kentucky disposal facility which was closed in 1977. It must be understood that the regulations for siting, management, burial techniques, waste classification, and the overall management of disposal sites were limited when this facility was in operation

  8. Energy need, energy production, waste heat quantities - the present state and a look into the future

    International Nuclear Information System (INIS)

    Schikarski, W.

    1975-01-01

    The possibilities and methods to keep the waste heat low in our society so dependent on energy, are manifold and they affect many aspects of our economic and social life. A society which shows concern for its environment will not hesitate to explore all possible avenues and to realize them. Nevertheless, one has to start from the assumption that the energy consumption, which is closely connected with the standard of living, will increase in the near future. Thus, we have to reckon with more waste heat. Therefore, on a medium-term basis, the amount of waste heat we will be confronted with and its distribution in the environment is to be investigated carefully in order that on the one hand hydrosphere and atmosphere, the limit load of which is given, are not burdened in excess, and that on the other hand the media taking up waste heat are utilized in an optimal way (cooling management). On a long-term basis, the limits of waste heat discharge into water and atmosphere have to be determined carefully, something which can probably be done on the basis of climatological consequences. (orig.) [de

  9. Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future US nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

  10. Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

    International Nuclear Information System (INIS)

    Kring, C.T.; Herndon, J.N.; Meacham, S.A.

    1987-01-01

    The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future U.S. nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

  11. Performance analysis of next-generation lunar laser retroreflectors

    Science.gov (United States)

    Ciocci, Emanuele; Martini, Manuele; Contessa, Stefania; Porcelli, Luca; Mastrofini, Marco; Currie, Douglas; Delle Monache, Giovanni; Dell'Agnello, Simone

    2017-09-01

    ) to GR tests and to constraints on new gravitational theories (like non-minimally coupled gravity and spacetime torsion), the description of the associated physics analysis and global LLR error budget is outside of the chosen scope of present paper. We note that, according to Reasenberg et al. (2016), software models used for LLR physics and lunar science cannot process residuals with an accuracy better than few centimeters and that, in order to process millimeter ranging data (or better) coming from (not only) future reflectors, it is necessary to update and improve the respective models inside the software package. The work presented here on results of the SCF-test thermal and optical analysis shows that a good performance is expected by MoonLIGHT-2 after its deployment on the Moon. This in turn will stimulate improvements in LLR ground segment hardware and help refine the LLR software code and models. Without a significant improvement of the LLR space segment, the acquisition of improved ground LLR hardware and challenging LLR software refinements may languish for lack of motivation, since the librations of the old generation LLR payloads largely dominate the global LLR error budget.

  12. 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

  13. ALTENER. Strategic framework municipal solid waste. Waste for energy network

    International Nuclear Information System (INIS)

    Kwant, K.W.; Van Halen, C.; Pfeiffer, A.E.

    1997-01-01

    General objective of European, national and regional waste for energy (WfE) policies is to support sustainable development. In each of the Altener WfE countries (Austria, Denmark, Finland, Italy, Netherlands, Portugal, Spain, Sweden and UK) general waste management strategies have been implemented. Common aspects are waste management hierarchies and general objectives such as: (1) to reduce the amount of wastes; (2) to make the best use of the wastes that are produced; and (3) to choose waste management practices, which (4) minimise the risks of immediate and future environmental pollution and harm to human health. All WfE countries have defined an order of preference for waste handling, starting with prevention as most preferred option, through re-use and recycling, thermal treatment with energy-recovery to landfill as a least desired option. In all Altener WfE countries, waste management structures are in a phase of transformation. At least three general transition processes can be recognized to take place, which are of great importance for the waste for energy future of the Altener countries: (1) increased energy recovery from MSW; (2) increased separation of MSW for recycling and recovery; and (3) reorganization of landfills. Two groups of instruments to stimulate the use of waste to energy are distinguished: (1) instruments, aiming to create improved WfE solutions; and (2) instruments, aiming to create a WfE market. In this framework document an overview is given of today's WfE situation in 9 European countries, as well as up-to-date national waste and energy policies, including the available instruments and future goals

  14. Financial provisions needed now to deal with future waste

    International Nuclear Information System (INIS)

    Olivier, J.-P.

    1978-01-01

    Some opinions, derived from a recent NEA/OECD report, are expressed on the financing of radioactive waste disposal. Waste disposal could represent 50% of total waste management costs but it will be some time before waste disposal must be paid for and accurate estimation of the costs is almost impossible. An international fund set up now would overcome many of the financing problems that are likely to arise

  15. Nuclear waste management: a perspective

    International Nuclear Information System (INIS)

    Leuze, R.E.

    1980-01-01

    The scope of our problems with nuclear waste management is outlined. Present and future inventories of nuclear wastes are assessed for risk. A discussion of what is presently being done to solve waste management problems and what might be done in the future are presented

  16. Transuranic waste management at Savannah River - past, present, and future

    International Nuclear Information System (INIS)

    D'Ambrosia, J.

    1985-01-01

    The major objective of the TRU program at Savannah River is to support the TRU National Program, which is dedicated to preparing waste for, and emplacing waste in, the Waste Isolation Pilot Plant, (WIPP). Thus, the Savannah River Program also supports WIPP operations. The Savannah River site specific goals to phase out the indefinite storage of TRU waste, which has been the mode of waste management since 1974, and to dispose of Savannah River's Defense TRU waste

  17. Low-level waste management

    International Nuclear Information System (INIS)

    Levin, G.B.

    1980-01-01

    An overview of the current situation in the United States and a look to the future of low-level waste management are presented. Current problems and challenges are discussed, such as: the need of additional disposal sites in the future; risks and costs involved in transport of low-level wastes; reduction of low-level waste volume through smelting, incineration, and storage for wastes containing nuclides with short half lives; development of a national policy for the management of low-level waste, and its implementation through a sensible system of regulations. Establishing a success with low-level waste management should provide the momentum and public confidence needed to continue on and to resolve the technical and politically more difficult low-level waste problems

  18. Indonesia municiple solid waste life cycle and environmental monitoring: current situation, before and future challenges

    Science.gov (United States)

    Susmono

    2017-03-01

    developed, some solid waste communal leaders were born, and solid waste handling motivation and participation of community are grown. To accelerate this situation, the government introduces many training and education to produce more municipal solid waste handling facilitators. Since 2007, environment sanitation motivation activities runs through the yearly Sanitation Jamboree that educate, short train, motivate junior school children and competition among other. Technology innovation. Local governments, with or without central government support, are being to make some improvement how to handle municipal solid waste and through Sister City Program, many innovations were developed such as in Surabaya City (home Takakura composter), Depok (waste separation and composting), Bogor City (management), Malang City, Makasar City and others. The new Closing the Loops of solid waste handling approaches should be introduced in the future to break the bottle neck that always happened in the past. Integration between solid waste management and the farming activities, land plantation rehabilitations, city landscaping and gardening is very urgent to develop, including integration of 3R stakeholders in the region. The challenges. The municipal solid waste problem in urban areas is relative more complicated compared with the same problem in the rural areas. Accurate data collection and analyzing periodically is very important. Road map development and mobilizing of all stake holders both in central government and in local government such as NGOs, private sectors, education and research institutions, civil societies and the community are very urgent. New research action is required to find our new urban municipal solid waste characteristic and our appropriate technology and management to give some input to the central government, local governments and the community or others who involve in the municipal solid waste handling due to the recent fast growing of urban people income and changing

  19. The Future: Innovative Technologies for Radioactive Waste Processing and Disposal

    International Nuclear Information System (INIS)

    Bychkov, Alexander V.

    2014-01-01

    Safe, proliferation resistant and economically efficient nuclear fuel cycles that minimize waste generation and environmental impacts are key to sustainable nuclear energy. Innovative approaches and technologies could significantly reduce the radiotoxicity, or the hazard posed by radioactive substances to humans, as well as the waste generated. Decreasing the waste volume, the heat load and the duration that the waste needs to be isolated from the biosphere will greatly simplify waste disposal concepts

  20. Material resources, energy, and nutrient recovery from waste: are waste refineries the solution for the future?

    DEFF Research Database (Denmark)

    Tonini, Davide; Martinez-Sanchez, Veronica; Astrup, Thomas Fruergaard

    2013-01-01

    Waste refineries focusing on multiple outputs of material resources, energy carriers, and nutrients may potentially provide more sustainable utilization of waste resources than traditional waste technologies. This consequential life cycle assessment (LCA) evaluated the environmental performance....... Overall, the waste refinery provided global warming (GW) savings comparable with efficient incineration, MBT, and bioreactor landfilling technologies. The main environmental benefits from waste refining were a potential for improved phosphorus recovery (about 85%) and increased electricity production (by...

  1. Wind Turbines’ End-of-Life: Quantification and Characterisation of Future Waste Materials on a National Level

    Directory of Open Access Journals (Sweden)

    Niklas Andersen

    2016-11-01

    Full Text Available Globally, wind power is growing fast and in Sweden alone more than 3000 turbines have been installed since the mid-1990s. Although the number of decommissioned turbines so far is few, the high installation rate suggests that a similarly high decommissioning rate can be expected at some point in the future. If the waste material from these turbines is not handled sustainably the whole concept of wind power as a clean energy alternative is challenged. This study presents a generally applicable method and quantification based on statistics of the waste amounts from wind turbines in Sweden. The expected annual mean growth is 12% until 2026, followed by a mean increase of 41% until 2034. By then, annual waste amounts are estimated to 240,000 tonnes steel and iron (16% of currently recycled materials, 2300 tonnes aluminium (4%, 3300 tonnes copper (5%, 340 tonnes electronics (<1% and 28,000 tonnes blade materials (barely recycled today. Three studied scenarios suggest that a well-functioning market for re-use may postpone the effects of these waste amounts until improved recycling systems are in place.

  2. Future strategic directions for radioactive waste management programmes

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    The NEA Radioactive Waste Management Committee (RWMC) has identified six strategic areas as priorities for work in the coming years. These strategic areas, listed in this paper, are described in a NEA publication (Strategic Areas in Waste Management: the viewpoint and work orientations of the NEA RWMC

  3. Financial provision for future nuclear waste management in Finland

    International Nuclear Information System (INIS)

    Vaeaetaeinen, Anne

    2003-01-01

    The main principle as regards nuclear waste management in Finland is that the operator that has produced nuclear waste is responsible for the management of all such nuclear waste. It has to take care of its waste (including that of decommissioning) until it has been disposed of in a manner accepted by the authorities. Spent nuclear fuel is considered to be nuclear waste subject to disposal into a final repository. According to the Nuclear Energy Act, all nuclear waste produced in Finland must be handled, stored and disposed of in Finland. The spent fuel and other nuclear wastes are stored at the power plant sites until they are disposed of. At the both two sites there already are the final repositories for low and intermediate level waste. The funding system is based on the principle that, if a nuclear facility would stop its operation and also stop to produce more waste, the money in the Fund and the securities given to the State would, together, always suffice to handle the situation and take care of the management of all the existing waste and dismantling and decommissioning of the plant. As the actual waste management measures would not be taken immediately, the interest accrued, in the meantime, by this existing capital is used to compensate for the inflation and cost escalation. The critical question is how the system takes into account the difficulty of arriving at reliable estimates. The Finnish funding system contains some built-in features to minimise the risk of the State having to contribute additional funds to carrying out these operations. The system continuously requires new updated estimates that must take into account the practical experience accumulating world-wide. The estimates must, however, always be based on technology currently available. Additionally, the law also requires that the uncertainty of available information about prices and costs shall be taken into account, in a reasonable manner, as raising the estimated liability. In the case

  4. Radioactive wastes

    International Nuclear Information System (INIS)

    Teillac, J.

    1988-01-01

    This study of general interest is an evaluation of the safety of radioactive waste management and consequently the preservation of the environment for the protection of man against ionizing radiations. The following topics were developed: radiation effects on man; radioactive waste inventory; radioactive waste processing, disposal and storage; the present state and future prospects [fr

  5. Waste-to-energy plants - a solution for a cleaner future

    International Nuclear Information System (INIS)

    Pfeiffer, J.

    2007-01-01

    Waste-to-energy plants reduce the municipal solid waste volume by about 80% and convert it into residue. The residue quality naturally depends on the burned waste quality and also on the combustion parameters. Hence, tighter control of the plant can improve the residue quality. The generated combustion energy is regarded as renewable energy and is typically used to feed a turbine to generate electricity. Waste-to-energy furnaces react slowly on changing waste charge, so they are not used for peak load generation. The generated electrical power is a plant by product and is sold as base load generation. Usually the waste is burned on a grate which limits the plant size to about 160,000 tons of waste per year or 20 tons of waste per hour or about 28 MW. More recent technology utilizes fluidized bed combustion, which allows larger plant sizes up to 50 MW. Due to the unknown waste composition and stringent environmental standards involved, waste-to-energy plants employ sophisticated flue gas cleaning devices for emission control. ABB's Performance Monitoring continuously compares actual plant and equipment performance to expected performance. This includes the on-line calculation of the waste calorific heat allowing operator decision support and automated control system responses. Dedicated reports offer detailed data on operations, maintenance and emissions to plant management staff. ABB combustion optimization solutions use model based predictive control techniques to reliably find the most suitable set-points for improving the heat rate and reducing emissions like NO x . (author)

  6. More reliable financing of future nuclear waste costs

    International Nuclear Information System (INIS)

    1994-01-01

    This appendix contains seven reports written by consultants to the Commission. The report titles are: Basic document regarding the inquiry on fund management; Scenarios for growth and real interest rates in a long perspective; Stability of the Swedish financing system; Report concerning the financing of nuclear waste management in Sweden and Finland and the cost control system in Sweden; Evaluation of the cost estimates and calculation methods of SKB; A study of the costs for nuclear waste - The basis for cost estimation; A review of scope and costs for the Swedish system for management of nuclear waste. The four last reports are separately indexed

  7. Radioactive waste management

    International Nuclear Information System (INIS)

    Alfredson, P.G.; Levins, D.M.

    1975-08-01

    Present and future methods of managing radioactive wastes in the nuclear industry are reviewed. In the stages from uranium mining to fuel fabrication, the main purpose of waste management is to limit and control dispersal into the environment of uranium and its decay products, particularly radium and radon. Nuclear reactors produce large amounts of radioactivity but release rates from commercial power reactors have been low and well within legal limits. The principal waste from reprocessing is a high activity liquid containing essentially all the fission products along with the transuranium elements. Most high activity wastes are currently stored as liquids in tanks but there is agreement that future wastes must be converted into solids. Processes to solidify wastes have been demonstrated in pilot plant facilities in the United States and Europe. After solidification, wastes may be stored for some time in man-made structures at or near the Earth's surface. The best method for ultimate disposal appears to be placing solid wastes in a suitable geological formation on land. (author)

  8. Partitioning-transmutation technology: a potential future nuclear waste management option

    International Nuclear Information System (INIS)

    Nakayama, S.; Morita, Y.; Nishihara, K.; Oigawa, H.

    2005-01-01

    Partitioning-transmutation technology (PT) will produce radioactive wastes of different physical and chemical properties and in different amounts from those generated in the current nuclear fuel cycle. To assess quantitatively the effects of PT on waste disposal, we first analyzed the amounts of the PT wastes, assumed conditioning for each type of the waste, and then made an attempt to estimate the repository area for disposal of the PT wastes. The properties of the hot Sr-Cs waste form are controlling factors in determining the size of the geologic repository. The disposal area could be reduced if the Sr-Cs fraction is disposed in a different subsurface repository or by long-term storage of the waste under institutional control. Disposal in a subsurface repository was found to comply with the Japanese law in terms of radioactivity constraint, through a performance assessment for disposal of the Sr-Cs fraction. (authors)

  9. Radioactive wastes: present problems and future prospects

    International Nuclear Information System (INIS)

    Gauvenet, Andre

    1975-01-01

    The main characteristics of radioactive wastes are described and the present problems arising from liquid or gas effluents are considered. It is concluded that nuclear power stations are considerably less pollutant, at equal capacity, than conventional power stations. Programs of investigation are now being developed to meet with the foreseeable increase of activity. The problem is: first, to maintain absorbed doses at their present level and second, to study the problem of long-lived elements the storage of which would, in the long run create a nuisance on a world scale. The different waste storage techniques now in use are described and current investigations and works are exposed some of which, like vitrification, have already begun to be put into application. After having noted that the problem of wastes constitutes doubtless a difficulty in the technical field and, maybe even more so in the psychological field, the conditions are defined which will have to be met in order that this problem should not hinder the short- and long-term development of nuclear energy [fr

  10. The future of very low level radioactive wastes in question

    International Nuclear Information System (INIS)

    Vignes, Emmanuelle

    2016-01-01

    After having recalled that nuclear plants produce various radioactive wastes, that the Cigeo project is the proposed solution to store these radioactive wastes, this article more particularly addresses the issue of very low level radioactive wastes which are now the main matter of concern for the IRSN as their quantity is expected to increase during the years to come (notably in relationship with nuclear reactor lifetime extension), and as present storage capacities will soon be saturated. The author first outlines that these wastes are not very dangerous but very cumbersome. Among these so-defined 'very low level' wastes, 30 to 50 per cent could be considered as harmless, but are now processed as dangerous wastes through costly processes. Various possibilities are then envisaged such as a diversification of storage options

  11. Radioactive waste management

    International Nuclear Information System (INIS)

    Pahissa Campa, Jaime; Pahissa, Marta H. de

    2000-01-01

    Throughout this century, the application of nuclear energy has produced many benefits, in industry, in research, in medicine, and in the generation of electricity. These activities generate wastes in the same way as do other human activities. The primary objective of radioactive waste management is to protect human health and environment now and in the future without imposing undue burden on future generations, through sound, safe and efficient radioactive waste management. This paper briefly describes the different steps of the management of short lived low and intermediate level wastes, and presents and overview of the state of art in countries involved in nuclear energy, describing their organizations, methodologies used in the processing of these wastes and the final disposal concepts. It also presents the Argentine strategy, its technical and legal aspects. Worldwide experience during the past 50 years has shown that short lived low and intermediate level wastes can be successfully isolated from human and environment in near surface disposal facilities. (author)

  12. Geological Disposal of Radioactive Waste

    International Nuclear Information System (INIS)

    Dody, A.; Klein, Ben; David, O.

    2014-01-01

    Disposal of radioactive waste imposes complicated constrains on the regulator to ensure the isolation of radioactive elements from the biosphere. The IAEA (1995) states that T he objective of radioactive waste management is to deal with radioactive waste in a manner that protects human health and the environment now and the future without imposing undue burdens on future generation . The meaning of this statement is that the operator of the waste disposal facilities must prove to the regulator that in routine time and in different scenarios the dose rate to the public will not exceed 0.3 mSv/y in the present and in the future up to 10,000 years

  13. Transuranic (TRU) waste management at Savannah River - past, present and future

    International Nuclear Information System (INIS)

    D'Ambrosia, J.T.

    1985-01-01

    Defense TRU waste at Savannah River (SR) results from the Department of Energy's (DOE) national defense activities, including the operation of production reactors and fuel reprocessing plants and research and development activities. TRU waste is material declared as having negligible economic value, contaminated with alpha-emitting radionuclides of atomic number greater than 92, and half-lives longer than 20 years, in concentrations greater than 100 nCi/g. TRU waste has been retrievably stored at SR since 1974 awaiting disposal. The Waste Isolation Pilot Plant (WIPP), now under construction in New Mexico, is a research and development facility for demonstrating the safe disposal of defense TRU waste, including that in storage at SR. The major objective of the TRU program at SR is to support the TRU National Program, which is dedicated to preparing waste for, and emplacing waste in, the WIPP. Thus, the SR Program also supports WIPP operations. The SR Site specific goals are to phase out the indefinite storage of TRU waste, which has been the mode of waste management since 1974, and to dispose of SR's Defense TRU waste

  14. Solid waste

    International Nuclear Information System (INIS)

    1995-01-01

    The article drawn up within the framework of 'the assessment of the state of the environment in Lebanon' provides an overview of solid waste management, and assesses future wastes volume and waste disposal issues.In particular it addresses the following concerns: - Long term projections of solid waste arisings (i.e. domestic, industrial, such commercial wastes, vehicle types, construction waste, waste oils, hazardous toxic wastes and finally hospital and clinical wastes) are described. - Appropriate disposal routes, and strategies for reducing volumes for final disposal - Balance between municipal and industrial solid waste generation and disposal/treatment and - environmental impacts (aesthetics, human health, natural environment )of existing dumps, and the potential impact of government plans for construction of solid waste facilities). Possible policies for institutional reform within the waste management sector are proposed. Tables provides estimations of generation rates and distribution of wastes in different regions of Lebanon. Laws related to solid waste management are summarized

  15. Program planning for future improvement in managing ORNL's radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    This report is intended to serve as a reference document and guide in developing the long-term improvements section of ORNL's radioactive waste management plan. The report reviews ORNL's operations and future program needs in terms of currently applicable DOE regulations and also in terms of regulations and accepted practices of the commerical sector of the nuclear power industry so that the impact of potential future adoption of these regulations and standards on ORNL's operations can be fully evaluated. The principal conclusion reached after reviewing ORNL's waste management operations is that these operations are currently being conducted in a manner that does not endanger the health or safety of workers or the general public and that does not have an adverse effect on the environment. Although nineteen specific problem areas have been identified all of these problems can be attributed to one of the following: a) the legacy of past practices; b) gradual deterioration of systems which have reached (or are near to reaching) the end of their reasonable design lives; and c) potential changes in regulations applicable to ORNL. All of the programs designed to improve or correct these problem areas could be accomplished within a four year period. However, given current limitations on manpower and capital, these programs would more likely be spread out over a five to ten year period of time if they were all to be undertaken. The cost of undertaking all of these projects concurrently is estimated to be between 60 and 100 million dollars. Due to the many unknowns and uncertainties associated with the problem areas, actual total costs for specific projects could vary from those presented in this report by as much as 300 percent. (DMC)

  16. Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 1. Revision 1

    International Nuclear Information System (INIS)

    1995-02-01

    This document provides baseline inventories of transuranic wastes for the WIPP facility. Information on waste forms, forecasting of future inventories, and waste stream originators is also provided. A diskette is provided which contains the inventory database

  17. Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 1. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    This document provides baseline inventories of transuranic wastes for the WIPP facility. Information on waste forms, forecasting of future inventories, and waste stream originators is also provided. A diskette is provided which contains the inventory database.

  18. Future prospects for the management of radioactive waste in greece

    International Nuclear Information System (INIS)

    Savidou, A.

    2015-01-01

    In Greece, there isn.t yet any decision for construction of a disposal facility. Since the predisposal management of radioactive waste should be aligned with the disposal solutions, the determination of the disposal options is essential for the selection of the technology needed for treatment and conditioning of the wastes. The scope of the present study is the investigation of the disposal options for Greece. Firstly, the study deals with the preliminary inventory as well as the classification of the existing radioactive waste and the prediction of the expected waste from decommissioning of the open pool type at 5 MW Greek Research Reactor (GRR-1). The existing radioactive waste includes the institutional waste from the operation of GRR-1 and associated facilities as well as orphan sources and other radioactive items collected in the frame of emergency by the Greek Atomic Energy Commission (GAEC) and kept at the interim storage of the National Centre for Scientific Research ''Demokritos'' NCSR ''D''. Based on the present inventory of radioactive waste, the establishment of a small scale and LILW geological repository seems to be the appropriate and most acceptable by the public disposal solution. (authors)

  19. Thirty Years of Social Science Research on High-Level Nuclear Waste: Achievements and Future Challenges

    International Nuclear Information System (INIS)

    Solomon, Barry D.; Andren, Mats; Strandberg, Urban

    2010-09-01

    Research on high-level nuclear waste management has focused on technical and scientific issues since the U.S. National Academy of Sciences first studied the problem in the mid 1950s and recommended long-term disposal in deep salt formations. In this review, we trace the development of the problem's definition and its associated research since socioeconomic, political and policy issues were first given consideration and nuclear waste management became recognized as more than a technical issue. Three time periods are identified. First, from the mid 1970s to early 1980s, initial research explored institutional dimensions of nuclear waste, including ethics. The second period began in the early 1980s with a concerted effort to solve the problem and site nuclear waste repositories, and ended in the mid 1990s with minimal progress in the U.S. and general stalemate in Asia and Europe (with the notable exception of Sweden). This phase accelerated research on risk perception and stigma of nuclear waste, and elevated a focus on public trust. Great attention was given to repository siting conflicts, while minimal attention was placed on ethics, equity, political systems, and public participation. The last period, since the mid 1990s, has been characterized by continuing political stalemate and increased attention to public participation, political systems and international solutions. Questions of ethics have been given renewed attention, while research on risk perceptions and siting conflicts continues. We frame these periods in a broader context of the shifting role of applied social scientists. The paper concludes with a general discussion of this research area and prospects for future research

  20. Thirty Years of Social Science Research on High-Level Nuclear Waste: Achievements and Future Challenges

    Energy Technology Data Exchange (ETDEWEB)

    Solomon, Barry D. (Dept. of Social Sciences, Michigan Technological Univ., Houghton (United States)), e-mail: bdsolomo@mtu.edu; Andren, Mats; Strandberg, Urban (Center for Public Sector Research, Univ. of Goeteborg, Goeteborg (Sweden))

    2010-09-15

    Research on high-level nuclear waste management has focused on technical and scientific issues since the U.S. National Academy of Sciences first studied the problem in the mid 1950s and recommended long-term disposal in deep salt formations. In this review, we trace the development of the problem's definition and its associated research since socioeconomic, political and policy issues were first given consideration and nuclear waste management became recognized as more than a technical issue. Three time periods are identified. First, from the mid 1970s to early 1980s, initial research explored institutional dimensions of nuclear waste, including ethics. The second period began in the early 1980s with a concerted effort to solve the problem and site nuclear waste repositories, and ended in the mid 1990s with minimal progress in the U.S. and general stalemate in Asia and Europe (with the notable exception of Sweden). This phase accelerated research on risk perception and stigma of nuclear waste, and elevated a focus on public trust. Great attention was given to repository siting conflicts, while minimal attention was placed on ethics, equity, political systems, and public participation. The last period, since the mid 1990s, has been characterized by continuing political stalemate and increased attention to public participation, political systems and international solutions. Questions of ethics have been given renewed attention, while research on risk perceptions and siting conflicts continues. We frame these periods in a broader context of the shifting role of applied social scientists. The paper concludes with a general discussion of this research area and prospects for future research

  1. Transportation considerations related to waste forms and canisters for Defense TRU wastes

    International Nuclear Information System (INIS)

    Schneider, K.J.; Andrews, W.B.; Schreiber, A.M.; Rosenthal, L.J.; Odle, C.J.

    1981-09-01

    This report identifies and discusses the considerations imposed by transportation on waste forms and canisters for contact-handled, solid transuranic wastes from the US Department of Energy (DOE) activities. The report reviews (1) the existing raw waste forms and potential immobilized waste forms, (2) the existing and potential future DOE waste canisters and shipping containers, (3) regulations and regulatory trends for transporting commercial transuranic wastes on the ISA, (4) truck and rail carrier requirements and preferences for transporting the wastes, and (5) current and proposed Type B external packagings for transporting wastes

  2. Future directions of defense programs high-level waste technology programs

    International Nuclear Information System (INIS)

    Chee, T.C.; Shupe, M.W.; Turner, D.A.; Campbell, M.H.

    1987-01-01

    The Department of Energy has been managing high-level waste from the production of nuclear materials for defense activities over the last forty years. An objective for the Defense Waste and Transportation Management program is to develop technology which ensures the safe, permanent disposal of all defense radioactive wastes. Technology programs are underway to address the long-term strategy for permanent disposal of high-level waste generated at each Department of Energy site. Technology is being developed for assessing the hazards, environmental impacts, and costs of each long-term disposal alternative for selection and implementation. This paper addresses key technology development areas, and consideration of recent regulatory requirements associated with the long-term management of defense radioactive high-level waste

  3. Optimization of use of waste in the future energy system

    DEFF Research Database (Denmark)

    Münster, Marie; Meibom, Peter

    2011-01-01

    of mixed waste, anaerobic digestion of organic waste, and gasification of part of the potential RDF (refuse derived fuel) for CHP (combined heat and power) production, while the remaining part is co-combusted with coal. Co-combustion mainly takes place in new coal-fired power plants, allowing investments...... production in Denmark in a 2025 scenario with 48% renewable energy. Investments in a range of waste conversion technologies are facilitated, including waste incineration, co-combustion with coal, anaerobic digestion, and gasification. The most economically feasible solutions are found to be incineration...

  4. Classification of solid wastes as non-radioactive wastes

    International Nuclear Information System (INIS)

    Suzuki, Masahiro; Tomioka, Hideo; Kamike, Kozo; Komatu, Junji

    1995-01-01

    The radioactive wastes generally include nuclear fuels, materials contaminated with radioactive contaminants or neutron activation to be discarded. The solid wastes arising from the radiation control area in nuclear facilities are used to treat and stored as radioactive solid wastes at the operation of nuclear facilities in Japan. However, these wastes include many non-radioactive wastes. Especially, a large amount of wastes is expected to generate at the decommissioning of nuclear facilities in the near future. It is important to classify these wastes into non-radioactive and radioactive wastes. The exemption or recycling criteria of radioactive solid wastes is under discussion and not decided yet in Japan. Under these circumstances, the Nuclear Safety Committee recently decided the concept on the category of non-radioactive waste for the wastes arising from decommissioning of nuclear facilities. The concept is based on the separation and removal of the radioactively contaminated parts from radioactive solid wastes. The residual parts of these solid wastes will be treated as non-radioactive waste if no significant difference in radioactivity between the similar natural materials and materials removed the radioactive contaminants. The paper describes the procedures of classification of solid wastes as non-radioactive wastes. (author)

  5. Australian Waste Wise Schools Program: Its Past, Present, and Future

    Science.gov (United States)

    Cutter-Mackenzie, Amy

    2010-01-01

    The Waste Wise Schools program has a longstanding history in Australia. It is an action-based program that encourages schools to move toward zero waste through their curriculum and operating practices. This article provides a review of the program, finding that it has had notable success in reducing schools' waste through a "reduce, reuse,…

  6. Selecting reasonable future land use scenarios

    Energy Technology Data Exchange (ETDEWEB)

    Allred, W.E.; Smith, R.W. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1995-12-31

    This paper examines a process to help select the most reasonable future land use scenarios for hazardous waste and/or low-level radioactive waste disposal sites. The process involves evaluating future land use scenarios by applying selected criteria currently used by commercial mortgage companies to determine the feasibility of obtaining a loan for purchasing such land. The basis for the process is that only land use activities for which a loan can be obtained will be considered. To examine the process, a low-level radioactive waste site, the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory, is used as an example. The authors suggest that the process is a very precise, comprehensive, and systematic (common sense) approach for determining reasonable future use of land. Implementing such a process will help enhance the planning, decisionmaking, safe management, and cleanup of present and future disposal facilities.

  7. Selecting reasonable future land use scenarios

    International Nuclear Information System (INIS)

    Allred, W.E.; Smith, R.W.

    1995-01-01

    This paper examines a process to help select the most reasonable future land use scenario for hazardous waste and/or low-level radioactive waste disposal sites. The process involves evaluating future land use scenarios ab applying selected criteria currently used by commercial mortgage companies to determine the feasibility of obtaining a loan for purchasing such land. The basis for the process is that only land use activities for which a loan can be obtained well be considered. To examine the process, a low-level radioactive waste site, the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory, is used as an example. The authors suggest that the process is a very precise, comprehensive, and systematic approach for determining reasonable future use of land. Implementing such a process will help enhance the planning, decisionmaking, safe management, and cleanup of present and future disposal facilities

  8. Selecting reasonable future land use scenarios

    International Nuclear Information System (INIS)

    Allred, W.E.; Smith, R.W.

    1995-01-01

    This paper examines a process to help select the most reasonable future land use scenarios for hazardous waste and/or low-level radioactive waste disposal sites. The process involves evaluating future land use scenarios by applying selected criteria currently used by commercial mortgage companies to determine the feasibility of obtaining a loan for purchasing such land. The basis for the process is that only land use activities for which a loan can be obtained will be considered. To examine the process, a low-level radioactive waste site, the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory, is used as an example. The authors suggest that the process is a very precise, comprehensive, and systematic (common sense) approach for determining reasonable future use of land. Implementing such a process will help enhance the planning, decisionmaking, safe management, and cleanup of present and future disposal facilities

  9. Waste management experience during all the life cycle of treatment facilities from commissioning till decommissioning. Today's situation and future trends

    International Nuclear Information System (INIS)

    Decobert, Guy; Devezeaux de Lavergne, Jean-Guy; Maurin, Matthieu

    2005-01-01

    Over time, the concepts of waste management have deeply evolved. In the case of the earlier generation of treatment plants, on-line conditioning was generally not implemented. In several cases, the strategy was clearly set as promoting storage of 'interim' raw waste, and implementing long-run R and D programs for future conditioning. Thus, one of the main objectives of the last generation of plants was to implement on-line conditioning of all waste, i.e. including waste issued from the used fuel and also those issued from plant operation (technological waste and effluent treatment waste). These strategic issues are naturally part of the core of the design of every new plant, as part of the operating performance. The enormous amount of experience collected from previous generations of plants, and managed by AREVA, allows us to go one step further. Indeed, our target is to rely on a comprehensive vision of waste management best practices, from the plant design through its decommissioning. This will allow AREVA to think about the next plant generation when encompassing the whole life cycle of the plant, including its different steps: Conception and building, Operation, Decommissioning. The first part of the paper will go back to waste management lessons and achievements in the design-construction phase and the operating phases of past and present treatment plants. From the past till today's generation, a factor of reduction of 50 for the volume of HLW-ILW type of waste was achieved leading to a ratio of 0.0012 m 3 /GWhe for a burn-up of 45 000 MWd/t! With regards to the development of the next generation of reactors and associated back-end, future improvements appear still possible in waste volume reduction. The second part of the paper will focus on decommissioning, which is likely to generate significant amount of waste, whose removal, handling, sorting, measurement, treatment and conditioning represent a substantial part of the cost of the program. Starting from

  10. Radiation doses from the transport of radioactive waste to a future repository in Denmark. A model study

    International Nuclear Information System (INIS)

    2011-05-01

    The radiation doses modelled for transport of radioactive waste to a future repository in Denmark, demonstrates that the risk associated with road and sea transport should not limit the future selection of a location of the repository. From a safety perspective both road and sea transport seem to be feasible modes of transport. Although the modelling in most cases is performed conservatively, the modelled doses suggest that both transport methods can be carried out well within the national dose limits. Additionally, the dose levels associated with the modelled accident scenarios are low and the scenarios are thus found to be acceptable taken the related probabilities into account. (LN)

  11. Radiation doses from the transport of radioactive waste to a future repository in Denmark. A model study

    Energy Technology Data Exchange (ETDEWEB)

    2011-05-15

    The radiation doses modelled for transport of radioactive waste to a future repository in Denmark, demonstrates that the risk associated with road and sea transport should not limit the future selection of a location of the repository. From a safety perspective both road and sea transport seem to be feasible modes of transport. Although the modelling in most cases is performed conservatively, the modelled doses suggest that both transport methods can be carried out well within the national dose limits. Additionally, the dose levels associated with the modelled accident scenarios are low and the scenarios are thus found to be acceptable taken the related probabilities into account. (LN)

  12. Summary of Waste Calcination at INTEC

    Energy Technology Data Exchange (ETDEWEB)

    O' Brien, Barry Henry; Newby, Bill Joe

    2000-10-01

    Fluidized-bed calcination at the Idaho Nuclear Technologies and Engineering Center (INTEC, formally called the Idaho Chemical Processing Plant) has been used to solidify acidic metal nitrate fuel reprocessing and incidental wastes wastes since 1961. A summary of waste calcination in full-scale and pilot plant calciners has been compiled for future reference. It contains feed compositions and operating conditions for all the processing campaigns for the original Waste Calcining Facility (WCF), the New Waste Calcining Facility (NWCF) started up in 1982, and numerous small scale pilot plant tests for various feed types. This summary provides a historical record of calcination at INTEC, and will be useful for evaluating calcinability of future wastes.

  13. Radioactive waste management

    International Nuclear Information System (INIS)

    Morley, F.

    1980-01-01

    A summary is given of the report of an Expert Group appointed in 1976 to consider the 1959 White Paper 'The Control of Radioactive Wastes' in the light of the changes that have taken place since it was written and with the extended remit of examining 'waste management' rather than the original 'waste disposal'. The Group undertook to; review the categories and quantities present and future of radioactive wastes, recommend the principles for the proper management of these wastes, advise whether any changes in practice or statutory controls are necessary and make recommendations. (UK)

  14. Review of the nuclear waste disposal problem

    International Nuclear Information System (INIS)

    Poch, L.A.; Wolsko, T.D.

    1979-10-01

    Regardless of future nuclear policy, a nuclear waste disposal problem does exist and must be dealt with. Even a moratorium on new nuclear plants leaves us with the wastes already in existence and wastes yet to be generated by reactors in operation. Thus, technologies to effectively dispose of our current waste problem must be researched and identified and, then, disposal facilities built. The magnitude of the waste disposal problem is a function of future nuclear policy. There are some waste disposal technologies that are suitable for both forms of HLW (spent fuel and reprocessing wastes), whereas others can be used with only reprocessed wastes. Therefore, the sooner a decision on the future of nuclear power is made the more accurately the magnitude of the waste problem will be known, thereby identifying those technologies that deserve more attention and funding. It is shown that there are risks associated with every disposal technology. One technology may afford a higher isolation potential at the expense of increased transportation risks in comparison to a second technology. Establishing the types of risks we are willing to live with must be resolved before any waste disposal technology can be instituted for widespread commercial use

  15. Updated Liquid Secondary Waste Grout Formulation and Preliminary Waste Form Qualification

    Energy Technology Data Exchange (ETDEWEB)

    Saslow, Sarah A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Um, Wooyong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Russell, Renee L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wang, Guohui [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Asmussen, Robert M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sahajpal, Rahul [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-07-01

    This report describes the results from liquid secondary waste grout (LSWG) formulation and cementitious waste form qualification tests performed by Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions, LLC (WRPS). New formulations for preparing a cementitious waste form from a high-sulfate liquid secondary waste stream simulant, developed for Effluent Management Facility (EMF) process condensates merged with low activity waste (LAW) caustic scrubber, and the release of key constituents (e.g. 99Tc and 129I) from these monoliths were evaluated. This work supports a technology development program to address the technology needs for Hanford Site Effluent Treatment Facility (ETF) liquid secondary waste (LSW) solidification and supports future Direct Feed Low-Activity Waste (DFLAW) operations. High-priority activities included simulant development, LSWG formulation, and waste form qualification. The work contained within this report relates to waste form development and testing and does not directly support the 2017 integrated disposal facility (IDF) performance assessment (PA). However, this work contains valuable information for use in PA maintenance past FY17, and for future waste form development efforts. The provided data should be used by (i) cementitious waste form scientists to further understanding of cementitious dissolution behavior, (ii) IDF PA modelers who use quantified constituent leachability, effective diffusivity, and partitioning coefficients to advance PA modeling efforts, and (iii) the U.S. Department of Energy (DOE) contractors and decision makers as they assess the IDF PA program. The results obtained help fill existing data gaps, support final selection of a LSWG waste form, and improve the technical defensibility of long-term waste form performance estimates.

  16. Radioactive waste management perspectives in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Nurul Wahida Ahmad Khairuddin; Nik Marzukee Nik Ibrahim; Mat Bakar Mahusin; Mohamad Hakiman Mohamad Yusoff; Muhammad Zahid Azrmi

    2009-01-01

    Waste Technology Development Centre (WasTeC) has been mandated to carry out radioactive waste management activities since 1984. The main objective of WasTeC is to deal with radioactive waste in a manner that protects health and the environment now and in the future, without imposing undue burdens on the future generations. This centre provides services for waste generators within Nuclear Malaysia and also for external waste generators. Services provided include transportation of radioactive waste, decontamination, treatment and storage. This paper will discuss on procedure for applying for services, responsibility of waste generator, responsibility of waste operator, need to comply with waste acceptance criteria and regulations related to management of radioactive waste. (Author)

  17. Future land use plan

    International Nuclear Information System (INIS)

    1995-01-01

    The US Department of Energy's (DOE) changing mission, coupled with the need to apply appropriate cleanup standards for current and future environmental restoration, prompted the need for a process to determine preferred Future Land Uses for DOE-owned sites. DOE began the ''Future Land Use'' initiative in 1994 to ensure that its cleanup efforts reflect the surrounding communities' interests in future land use. This plan presents the results of a study of stakeholder-preferred future land uses for the Brookhaven National Laboratory (BNL), located in central Long Island, New York. The plan gives the Laboratory's view of its future development over the next 20 years, as well as land uses preferred by the community were BNL ever to cease operations as a national laboratory (the post-BNL scenario). The plan provides an overview of the physical features of the site including its history, topography, geology/hydrogeology, biological inventory, floodplains, wetlands, climate, and atmosphere. Utility systems and current environmental operations are described including waste management, waste water treatment, hazardous waste management, refuse disposal and ground water management. To complement the physical descriptions of the site, demographics are discussed, including overviews of the surrounding areas, laboratory population, and economic and non-economic impacts

  18. Future land use plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-31

    The US Department of Energy`s (DOE) changing mission, coupled with the need to apply appropriate cleanup standards for current and future environmental restoration, prompted the need for a process to determine preferred Future Land Uses for DOE-owned sites. DOE began the ``Future Land Use`` initiative in 1994 to ensure that its cleanup efforts reflect the surrounding communities` interests in future land use. This plan presents the results of a study of stakeholder-preferred future land uses for the Brookhaven National Laboratory (BNL), located in central Long Island, New York. The plan gives the Laboratory`s view of its future development over the next 20 years, as well as land uses preferred by the community were BNL ever to cease operations as a national laboratory (the post-BNL scenario). The plan provides an overview of the physical features of the site including its history, topography, geology/hydrogeology, biological inventory, floodplains, wetlands, climate, and atmosphere. Utility systems and current environmental operations are described including waste management, waste water treatment, hazardous waste management, refuse disposal and ground water management. To complement the physical descriptions of the site, demographics are discussed, including overviews of the surrounding areas, laboratory population, and economic and non-economic impacts.

  19. Radioactive waste assessment using 'minimum waste generation' scenario - summary report March 1984

    International Nuclear Information System (INIS)

    Richardson, J.A.; Goodill, D.R.; Tymons, B.J.

    1984-11-01

    This report describes an assessment of radioactive waste management arisings from a defined nuclear power generation - Scheme 1. Scheme 1 assumes a minimum waste generation scenario with raw waste arisings from 3 main groups; (i) existing and committed commercial reactors; (ii) fuel reprocessing plants, (iii) research, industry and medicine. No decommissioning wastes are considered except for arisings from the final fuel cores from decommissioned reactors. The study uses the SIMULATION2 code which models waste material flows through the system. With a knowledge of the accumulations and average production rates of the raw wastes and their isotopic compositions (or total activities), the rates at which conditioned wastes become available for transportation and disposal are calculated, with specific activity levels. The data bases for the inventory calculations and the assumptions concerning future operation of nuclear facilities were those current in 1983. Both the inventory data and plans for the future of existing nuclear installations have been updated since these calculations were completed. Therefore the results from this assessment do not represent the most up-to-date information available. The report does, however, illustrate the methodology of assessment and indicates the type of information that can be generated. (author)

  20. More reliable financing of future nuclear waste costs

    International Nuclear Information System (INIS)

    1994-01-01

    A commission of inquiry was established by Government in 1993 to review the management of capital funds according to the existing Act of the Financing of Future Expenses for Spent Nuclear Fuel etc. The commission proposes that: The funds which have been paid to the Swedish state to finance the costs arising in connection with the handling and final disposal of spent nuclear fuel etc, from the year 1995, should be invested in accordance with guidelines which aim at attaining a higher return than is currently possible; That an independent government body, called the Nuclear Waste Fund, should be assigned the task of managing the funds, in accordance with these guidelines; That the Swedish Nuclear Power Inspectorate should continue to examine and evaluate issues relating to the application of the funds and recommend the level of the fee to be paid; and That a system including additional measures for guaranteeing the availability of funds should be implemented from the year 1995, in order to improve the reliability of the financing system. Our proposal involves extensive amendments to the Financing Act. On the other hand, the basic stipulations concerning responsibilities under the Act on Nuclear Activities, are not affected. (Seven work documents produced by consulting firms are published in a separate volume; SOU 1994:108) 5 figs., 16 tabs

  1. The metallurgy dross of the past: analogues to forecast the behaviour of present wastes in the course of their future aging

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The production of wastes is continuously increasing. Since they are a potential source of pollution, they must be stabilised, generally by vitrification. In order to know the long term behavior of these new products, several ways have been investigated, and among them, the study of analogues, either natural or resulting from the human activity. In this paper, are studied metallurgy drosses of the past which are regularly found during archaeological excavations; their ages range from 100 to 4000 years. The mineralogical, macroscopical and chemical characterisation of these materials and of some vitrified present wastes (from municipal wastes incineration plants and nuclear wastes), showed a great analogy of chemical and mineralogical composition between these present wastes and these materials of the past. Both are generally made of similar mineral phases (spinels, silicates, sulfides, metallic alloys), surrounded by a glassy matrix, and containing in many cases high percentages of contaminants. This matrix being the main cohesion factor of these materials, which brings them to weathering resistance. This led to study the glass weathering mechanisms. The results have shown a continuous weathering in three successive steps: the departure of large glass cations (Ca, Mg), the dissolution of the glassy structure, the precipitation of new phases. The average speeds range from 20 to 180 mm/1000 years, showing a good resistance of these materials in a natural environment. Future investigations should concern the study of a global site including its surroundings, in order to know the behaviour of contaminants after weathering during a period of several hundred years. These metallurgical sites of the past may thus be considered as analogues to forecast the future behaviour of abandoned industrial sites. (authors)

  2. Memory for future generations. To preserve and to transmit the memory of radioactive wastes. Press file - September 2014

    International Nuclear Information System (INIS)

    2014-09-01

    This publication by the ANDRA describes the approach adopted to develop, to preserve and to transmit the memory about radioactive wastes. This approach comprises three components: messages (texts, archives, drawings...), physical supports (paper, disk, markers), and relays (institutions, companies, etc.). The publication describes how these components are already used or implemented for the different radioactive waste storage centres managed by the ANDRA. It also outlines that this memory is an issue of international concern. It evokes issues related to linguistics (how future generations will understand our messages?), to the ageing of materials used as physical support, to archaeology because of the evolution of landscapes, and to the evolution of archival systems. Some simple ideas and projects are briefly indicated which can be a support in memory building

  3. EPA's approach to regulation of mixed waste and status of future activities

    International Nuclear Information System (INIS)

    Shackleford, B.

    1988-01-01

    Regulation of radioactive mixed waste is a topic that has received much attention in the past several years. Much of the discussion and confusion stemmed from uncertainty about applicable regulatory authorities. On July 3, 1986, EPA clarified its position that the Resource Conservation and Recovery Act (RCRA) applied to the hazardous component of radioactive mixed waste. The Agency announced this clarification in the Federal Register and informed States that they must seek authority to regulate mixed waste in order to obtain or maintain RCRA authorization to administer and enforce a hazardous waste program in lieu of EPA. Since that time, five States have received authorization to regulate mixed waste: Colorado, South Carolina, Tennessee, Washington, and Georgia. Authorized States issue RCRA permits in lieu of EPA. Currently, 44 States have been authorized for the base RCRA program, Conversely, 12 States and Trust Territories have no RCRA authorization. In these States and territories, EPA administers that RCRA hazardous waste program. A more stringent State requirement occurs when a State allows less time for compliance than would be provided under Federal law, for example. There is a third authorization category with respect to mixed waste that I have yet to address. This category is made up of States which have EPA authorization to regulate hazardous waste but have yet to obtain mixed waste authorization. Most States fall into this category. In these States, of which there are 39, mixed wastes are not hazardous wastes and subject to Subtitle C regulations

  4. Effluent Management Facility Evaporator Bottom-Waste Streams Formulation and Waste Form Qualification Testing

    Energy Technology Data Exchange (ETDEWEB)

    Saslow, Sarah A.; Um, Wooyong; Russell, Renee L.

    2017-08-02

    This report describes the results from grout formulation and cementitious waste form qualification testing performed by Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions, LLC (WRPS). These results are part of a screening test that investigates three grout formulations proposed for wide-range treatment of different waste stream compositions expected for the Hanford Effluent Management Facility (EMF) evaporator bottom waste. This work supports the technical development need for alternative disposition paths for the EMF evaporator bottom wastes and future direct feed low-activity waste (DFLAW) operations at the Hanford Site. High-priority activities included simulant production, grout formulation, and cementitious waste form qualification testing. The work contained within this report relates to waste form development and testing, and does not directly support the 2017 Integrated Disposal Facility (IDF) performance assessment (PA). However, this work contains valuable information for use in PA maintenance past FY 2017 and future waste form development efforts. The provided results and data should be used by (1) cementitious waste form scientists to further the understanding of cementitious leach behavior of contaminants of concern (COCs), (2) decision makers interested in off-site waste form disposal, and (3) the U.S. Department of Energy, their Hanford Site contractors and stakeholders as they assess the IDF PA program at the Hanford Site. The results reported help fill existing data gaps, support final selection of a cementitious waste form for the EMF evaporator bottom waste, and improve the technical defensibility of long-term waste form risk estimates.

  5. Potential capabilities of lunar laser ranging for geodesy and relativity

    Science.gov (United States)

    Muller, Jurgen; Williams, James G.; Turshev, Slava G.; Shelus, Peter J.

    2005-01-01

    Here, we review the LLR technique focusing on its impact on Geodesy and Relativity. We discuss the modem observational accuracy and the level of existing LLR modeling. We present the near-term objectives and emphasize improvements needed to fully utilize the scientific potential of LLR.

  6. Alternatives for future land disposal of radioactive waste

    International Nuclear Information System (INIS)

    Mallory, C.W.

    1982-01-01

    Shallow land burial incorporating improvements to facilitate stabilization and decommissioning will continue to be the primary method of disposing of low level waste in areas where conditions are suitable for this type of disposal. The existing disposal sites should be closely monitored to assure that continued acceptance of this method of disposal. Plans for the decommissioning of the existing sites should be closely reviewed to assure that the planning is adequate and that adequate resources will be available to implement the decommissioning plan. For these areas where geological conditions are not suitable for shallow land burial and in situations where a higher degree of containment is desired, alternative disposal methods should be considered. Technology exists or is readily attainable to provide engineered disposal facilities which provide a higher degree of containment and can be readily decommissioned. The cost of disposal using these methods can be competitive with shallow land burial when the cost of environmental and hydrogeologic investigations and decommissioning are included. Disposal of radioactive waste having low activity in secure sanitary landfills could significantly reduce the transportation and disposal requirements for low level waste

  7. Preliminary assessment of geologic materials to minimize biological intrusion of low-level waste trench covers and plans for the future

    International Nuclear Information System (INIS)

    Hakonson, T.E.; White, G.C.; Gladney, E.S.; Muller, M.

    1981-01-01

    The long-term integrity of low-level waste shallow land burial sites is dependent on the interaction of physical, chemical, and biological factors that modify the waste containment system. Past research on low-level waste shallow land burial methods has emphasized physical (i.e., water infiltration, soil erosion) and chemical (radionuclide leaching) processes that can cause radionuclide transport from a waste site. Preliminary results demonstrate that a sandy backfill material offers little resistance to root and animal intrusion through the cover profile. However, bentonite clay, cobble, and cobble-gravel combinations do reduce plant root and animal intrusion through cover profiles compared with sandy backfill soil. However, bentonite clay barrier systems appear to be degraded by plant roots through time. Desiccation of the clay barrier by invading plant roots may limit the usefulness of bentonite clay as a moisture and/or biological carrier unless due consideration is given to this interaction. Future experiments are described that further examine the effect of plant roots on clay barrier systems and that determine the effectiveness of proposed biological barriers on larger scales and under various stress conditions

  8. Rethinking the waste hierarchy

    Energy Technology Data Exchange (ETDEWEB)

    Rasmussen, C; Vigsoe, D [eds.

    2005-03-01

    There is an increasing need to couple environmental and economic considerations within waste management. Consumers and companies alike generate ever more waste. The waste-policy challenges of the future lie in decoupling growth in waste generation from growth in consumption, and in setting priorities for the waste management. This report discusses the criteria for deciding priorities for waste management methods, and questions the current principles of EU waste policies. The basis for the discussion is the so-called waste hierarchy which has dominated the waste policy in the EU since the mid-1970s. The waste hierarchy ranks possible methods of waste management. According to the waste hierarchy, the very best solution is to reduce the amount of waste. After that, reuse is preferred to recycling which, in turn, is preferred to incineration. Disposal at a landfill is the least favourable solution. (BA)

  9. Transfer of radioactive waste disposal knowledge to future generations: A stiff challenge for universities

    International Nuclear Information System (INIS)

    Sabet, B.B.; Elorza, F.J.

    2007-01-01

    Full text: In general, effective knowledge management strategies rely on the capacity to perform a full range of allied functions, among which education and research are the key components. However, in most countries and notably in Europe, universities which have to conduct leading-edge research and to supply society with future skilled staffs on radioactive waste disposal, suffer from both the shortage of the institutional national support and the decline of interest among students. This paper gives an overview of the academic educational challenges in geological disposal of radioactive waste. Prior to presenting possible solutions to overcome difficulties encountered in this field, the causes of the present failure that seriously threaten the future provision of human resources are identified and analysed. Some of the main findings are: The poor image of nuclear issues in general and the lack of public confidence in the management and disposal of radioactive waste in particular; The smallness of the radwaste community and the narrowness of the job market at the national level; The organisational structure of most universities that inhibits partnerships with non-academic institutions and impedes collaborative activities; The reticence of most governments to invest public funds in the academic education on radwaste disposal. These particular motives added to the common problems shared by the whole nuclear sector such as the lack of educational programmes, the ageing of teachers, and the decline in academic R and D activities, bring about the need for collaborative actions. The paper gives an example of possible solutions through the development of a European academic initiative. In response to the rising alarm about the future shortage of expertise, EURATOM has launched the ENEN II (European Commission 6th FP project No. FP6-036414 for years 2007-2008) project. The goal of this project is to consolidate the European nuclear education, training and knowledge

  10. Conservation and retrieval of information - Elements of a strategy to inform future societies about nuclear waste repositories

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, M [ed.; National Inst. of Radiation Protection, Stockholm (Sweden)

    1996-12-01

    Two main strategies exist for long-term information transfer, one which links information through successive transfers of archived material and other forms of knowledge in society, and one - such as marking the site with a monument - relying upon a direct link from the present to the distant future. Digital methods are not recommended for long-term storage, but digital processing may be a valuable tool to structure information summaries, and in the creation of better long-lasting records. Advances in archive management should also be pursued to widen the choice of information carriers of high durability. In the Nordic countries, during the first few thousand years, and perhaps up to the next period of glaciation, monuments at a repository site may be used to warn the public of the presence of dangerous waste. But messages from such markers may pose interpretation problems as we have today for messages left by earlier societies such as rune inscriptions. Since the national borders may change in the time scale relevant for nuclear waste, the creation of an international archive for all radioactive wastes would represent an improvement as regards conservation and retrieval of information. (EG).

  11. Conservation and retrieval of information - Elements of a strategy to inform future societies about nuclear waste repositories

    International Nuclear Information System (INIS)

    Jensen, M.

    1996-01-01

    Two main strategies exist for long-term information transfer, one which links information through successive transfers of archived material and other forms of knowledge in society, and one - such as marking the site with a monument - relying upon a direct link from the present to the distant future. Digital methods are not recommended for long-term storage, but digital processing may be a valuable tool to structure information summaries, and in the creation of better long-lasting records. Advances in archive management should also be pursued to widen the choice of information carriers of high durability. In the Nordic countries, during the first few thousand years, and perhaps up to the next period of glaciation, monuments at a repository site may be used to warn the public of the presence of dangerous waste. But messages from such markers may pose interpretation problems as we have today for messages left by earlier societies such as rune inscriptions. Since the national borders may change in the time scale relevant for nuclear waste, the creation of an international archive for all radioactive wastes would represent an improvement as regards conservation and retrieval of information. (EG)

  12. Radioactive waste management

    International Nuclear Information System (INIS)

    Tang, Y.S.; Saling, J.H.

    1990-01-01

    The purposes of the book are: To create a general awareness of technologies and programs of radioactive waste management. To summarize the current status of such technologies, and to prepare practicing scientists, engineers, administrative personnel, and students for the future demand for a working team in such waste management

  13. Waste management progress report

    International Nuclear Information System (INIS)

    1997-06-01

    During the Cold War era, when DOE and its predecessor agencies produced nuclear weapons and components, and conducted nuclear research, a variety of wastes were generated (both radioactive and hazardous). DOE now has the task of managing these wastes so that they are not a threat to human health and the environment. This document is the Waste Management Progress Report for the U.S. Department of Energy dated June 1997. This progress report contains a radioactive and hazardous waste inventory and waste management program mission, a section describing progress toward mission completion, mid-year 1997 accomplishments, and the future outlook for waste management

  14. Software to support planning for future waste treatment, storage, transport, and disposal requirements

    International Nuclear Information System (INIS)

    Holter, G.M.; Shay, M.R.; Stiles, D.L.

    1990-04-01

    Planning for adequate and appropriate treatment, storage, transport and disposal of wastes to be generated or received in the future is a complex but critical task that can be significantly enhanced by the development and use of appropriate software. This paper describes a software system that has been developed at Pacific Northwest Laboratory to aid in such planning. The basic needs for such a system are outlined, and the approach adopted in developing the software is described. The individual components of the system, and their integration into a unified system, are discussed. Typical analytical applications of this type of software are summarized. Conclusions concerning the development of such software systems and the necessary supporting data are then presented. 2 figs

  15. Nuclear Waste and Ethics

    International Nuclear Information System (INIS)

    Damveld, Herman

    2003-01-01

    In the past years in almost all conferences on storage of nuclear waste, ethics has been considered as an important theme. But what is ethics? We will first give a sketch of this branch of philosophy. We will then give a short explanation of the three principal ethical theories. In the discussion about storage of nuclear waste, the ethical theory of utilitarianism is often implicitly invoked. In this system future generations weigh less heavily than the present generation, so that people of the future are not considered as much as those now living. We reject this form of reasoning. The discussion about nuclear waste is also sometimes pursued from ethical points of departure such as equality and justice. But many loose ends remain in these arguments, which gives rise to the question of whether the production and storage of nuclear waste is responsible

  16. Nuclear Waste and Ethics

    Energy Technology Data Exchange (ETDEWEB)

    Damveld, Herman [Groningen (Netherlands)

    2003-10-01

    In the past years in almost all conferences on storage of nuclear waste, ethics has been considered as an important theme. But what is ethics? We will first give a sketch of this branch of philosophy. We will then give a short explanation of the three principal ethical theories. In the discussion about storage of nuclear waste, the ethical theory of utilitarianism is often implicitly invoked. In this system future generations weigh less heavily than the present generation, so that people of the future are not considered as much as those now living. We reject this form of reasoning. The discussion about nuclear waste is also sometimes pursued from ethical points of departure such as equality and justice. But many loose ends remain in these arguments, which gives rise to the question of whether the production and storage of nuclear waste is responsible.

  17. Radioactive waste management - with evidence

    International Nuclear Information System (INIS)

    1988-01-01

    The select committee was appointed to report on the present (1988) situation and future prospects in the field of radioactive waste management in the European Community. The report covers all aspects of the subject. After an introduction the parts of the report are concerned with the control of radiation hazards, the nuclear fuel cycle and radioactive waste, the control of radioactive effluents, storage and disposal of solid radioactive wastes, research programmes, surface storage versus deep geological disposal of long-term wastes, the future of reprocessing and the public debate. Part 10 is a resume of the main conclusions and recommendations. It is recommended that the House of Lords debate the issue. The oral and written evidence presented to the committee is included in the report. (U.K.)

  18. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Allan, C.J.

    1993-01-01

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

  19. Solid waste as renewable source of energy. Current and future possibility in Algeria

    Energy Technology Data Exchange (ETDEWEB)

    Taqiy Eddine, Boukelia; Salah, Mecibah Med [Mentouri Univ., Constantine (Algeria). Mechanical Dept.

    2012-11-01

    Algeria has created a green momentum by launching an ambitious program to develop renewable energies and promote energy efficiency. Solid waste is one of most important sources of biomass potential in Algeria, which can be used as renewable energy sources. With economic development and the evolution of population, the quantity of solid waste is increasing rapidly in Algeria; according to the National Cadastre for Solid Waste Generation, the overall generation of municipal solid waste was more than 10.3 million tons per year, and the amount of industrial solid waste, including non-hazardous and inert industrial waste was 2,547,000 tons per year, with a stock quantity of 4,483,500 tons. The hazardous waste generated amounts to 325,100 tons per year; the quantities of waste in stock and awaiting a disposal solution amount to 2,008,500 tons. Healthcare waste reaches to 125,000 tons per year. The management of solid waste and its valorization is based on the understanding of solid waste composition by its categories and physicochemical characteristics. Elimination is the solution applied to 97% of waste produced in Algeria. Wastes are disposed in the following ways: open dumps (57%), burned in the open air in public dumps or municipal uncontrolled ones (30%), and controlled dumps and landfill (10%). On the other side, the quantities destined for recovery are too low: only 2% for recycling and 1% for composting. Waste to energy is very attractive option for elimination solid waste with energy recovery. In this paper, we give an overview for this technology, including its conversion options and its useful products (such as electricity, heat and transportation fuel), and waste to energy-related environmental issues and its challenges. (orig.)

  20. Radioactive wastes - inventories and classification

    International Nuclear Information System (INIS)

    Brennecke, P.; Hollmann, A.

    1992-01-01

    A survey is given of the origins, types, conditioning, inventories, and expected abundance of radioactive wastes in the future in the Federal Republic of Germany. The Federal Government's radioactive waste disposal scheme provides that radioactive wastes be buried in deep geological formations which are expected to ensure a maintenance-free, unlimited and safe disposal without intentional excavation of the wastes at a later date. (orig./BBR) [de

  1. Energy and solid/hazardous waste

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-12-01

    This report addresses the past and potential future solid and hazardous waste impacts from energy development, and summarizes the major environmental, legislation applicable to solid and hazardous waste generation and disposal. A glossary of terms and acronyms used to describe and measure solid waste impacts of energy development is included. (PSB)

  2. Energy and solid/hazardous waste

    International Nuclear Information System (INIS)

    1981-12-01

    This report addresses the past and potential future solid and hazardous waste impacts from energy development, and summarizes the major environmental, legislation applicable to solid and hazardous waste generation and disposal. A glossary of terms and acronyms used to describe and measure solid waste impacts of energy development is included

  3. Nuclear waste - perceptions and realities

    International Nuclear Information System (INIS)

    Wilkinson, D.

    1984-01-01

    This paper discusses the complex scientific, sociological, political and emotive aspects of nuclear waste. The public perception of the hazards and risks, to present and future generations, in the management of nuclear wastes are highlighted. The cost of nuclear waste management to socially acceptable and technically achievable standards is discussed. (UK)

  4. 17. Meeting municipal waste Magdeburg. Residual waste - recycling - resource; 17. Tagung Siedlungsabfallwirtschaft Magdeburg. Restabfall - Recycling - Ressource

    Energy Technology Data Exchange (ETDEWEB)

    Haase, Hartwig (ed.)

    2012-11-01

    Within the 17th meeting Waste Management at Residential Areas from 12th o 13th September, 2012 in Magdeburg (Federal Republic of Germany), the following lectures were held: (1) Opening Session - Waste management in Saxony-Anhalt (O. Aeikens); (2) World with future - the eco-social perspective (F.J. Radermacher); (3) Global commodity markets - rare earths and their recycling (I. Fahimi); (4) The further development of nearhousehold capture of recyclable materials (J. Seitel); (5) On the future of the disposal management (J. Balg); (6) Options for action for the future of the municipal waste management (A. Gosten); (7) Current models of the capture of recyclable materials in Germany (M. Kerkhoff); (8) The recycling bin as a pilot test in Hanover (R. Middendorf); (9) Position of BellandVision on the implementation of a unified recycling bin (J. Soelling); (10) What will change with the new Recycle Economy Law according to the material flows and waste treatment capacities? (H. Alwast); (11) Waste management plan Saxony-Anhalt - Current developments (S. Hagel); (12) Wastes from the thermal waste treatment - Risk potential and disposal (G.-R. Behr); (13) Landfill Mining - Contribution of the waste management to the securing of resources (K. Fricke); (14) Logistic process design and system design in the transport of wastes in developing countries using Serbia as an example (Z. Jovanovic); (15) Example of good practices in the subsequent use of landfills - Solar park Cracauer Anger (M. Harnack); (16) Ecoloop - energy efficient gasification in the limestone moving-bed (R. Moeller); (17) Utilization of waste and biomass as a resource? Only by means of an intelligent logistics. (S. Trojahn); (18) Renewable energy resources - Experiences of a network provider (J. Kempmann).

  5. The effects of transuranic separation on waste disposal

    International Nuclear Information System (INIS)

    1991-04-01

    Rogers and Associates Engineering has analyzed waste streams from fuel cycles involving actinide partitioning and transmutation to determine appropriate disposal facilities for the waste and the cost of disposal. The focus of the study is the economic impact of actinide partitioning and transmutation on waste disposal, although there is a qualitative discussion of the impacts of actinide burning on disposal risk. This effort is part of a multi-contractor task being coordinated by the Electric Power Research Institute to address the technical feasibility and economic impact of transuranic burning. Waste streams were defined by General Electric Corporation for eight alternative processing cases -- involving aqueous and pyrochemical processing of spent fuel from light water reactors and liquid metal reactors and for low-actinide-recovery and high-actinide-recovery technologies. Disposal options are determined for three possible futures: one involving the present socio-political-licensing environment and using cost estimates for existing or planned facilities, an optimistic future with lower siting and licensing costs, and a pessimistic future with high siting and licensing costs and some extraordinary measures to assure waste isolation. The optimistic future allows the disposal of certain types of waste in a facility that provides a degree of waste isolation that is intermediate between a repository and a low-level-waste facility. 30 refs., 18 figs., 45 tabs

  6. Radioactive waste storage issues

    International Nuclear Information System (INIS)

    Kunz, D.E.

    1994-01-01

    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state's boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected

  7. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Summary

    International Nuclear Information System (INIS)

    1997-05-01

    This Waste Management Programmatic Environmental Impact Statement (WM PEIS) is a nationwide study examining the environmental impacts of managing five types of radioactive and hazardous wastes generated by past and future nuclear defense and research activities at a variety of sites located around the United States. The five waste types are low-level mixed waste (LLMW), low-level waste (LLW), transuranic waste (TRUW), high-level waste (HLW), and hazardous waste (HW)

  8. Preserving the memory of waste disposal centres for the future generations

    International Nuclear Information System (INIS)

    2006-01-01

    Radioactive waste disposal and storage facilities are designed to be intrinsically safe (lowest possible impact) for a duration depending on the lifetime of wastes. The French national agency of waste management (ANDRA) wishes to preserve as long as possible the memory of its waste facilities taking into account a possible loss of this memory beyond the legal monitoring period. For this reason, the ANDRA has analyzed the means that have permitted the preservation of the historical heritage through the centuries. The conclusions show that it is possible to preserve with a good confidence a patrimony during long time scales providing some organizing and structuring of this memory (archiving on numerical media and on permanent paper). (J.S.)

  9. Approaches to the final storage of radioactive waste in the Federal Republic of Germany. Will responsibility be shifted to future generations?

    International Nuclear Information System (INIS)

    Thomauske, B.

    2004-01-01

    With respect to the management of high-level radioactive waste in Germany, there is agreement on these premises: - The waste is to be stored permanently in the Federal Republic of Germany. - A repository is to be operational by 2030. - Final storage is to be achieved in geologic formations. Differences of opinion exist about these questions: - Should there be only one repository for all types of radioactive waste, or would a breakdown into waste generating heat and waste generating only negligible amounts of heat in different repositories be useful under aspects of safety and requirement? - Will a new site selection procedure be required in an effort to find a suitable site, and would such a selection procedure be able to meet the deadline of 2030 for an operational repository? - After the end of legal proceedings, should the Konrad repository be revamped for waste generating negligible amounts of heat? The analysis presented shows that an operational repository for waste generating heat can be made available only in connection with continued exploration work at Gorleben and demonstration of the suitability of that site and subsequent construction of the repository. If the search for a repository site were started from scratch, the date of commissioning such a facility would be after 2050. In this way, that approach would miss the purpose of not shifting the waste management issue to future generations. Acting responsibly means to build the Konrad repository speedily after completion of the legal proceedings about a permit and, in this way, avoid the addition of more interim stores for waste generating negligible amounts of heat. Further exploration of Gorleben is the way agreed upon and necessary for the creation of a repository for high-level radioactive waste generating heat by 2030. For this purpose, the 'points of doubt' must be resolved speedily. (orig.) [de

  10. Agency practice and future policy in decay storage of radioactive wastes

    International Nuclear Information System (INIS)

    Mitchell, N.G.

    2002-01-01

    The Environment Agency issues authorisations under the Radioactive Substances Act 1993 for the accumulation of radioactive waste at non-nuclear sites prior to disposal. Radioactive decay during the accumulation period reduces the radioactive content of waste packages and provides a waste management option that has become known as decay-in-storage or decay storage. The project brief excluded nuclear licensed sites. A database of information in authorisations and application forms has been constructed. This information has been used alongside a literature review, international contacts, input from the Small Users Liaison Group and a dose assessment to look at the practice of decay storage. The basic principles behind decay storage are presented with specific sections on general safety, waste characterisation and segregation, storage containers, waste stores, and waste treatment and conditioning. The regulatory approach in seven other countries is described. The information collected from Agency public registers is summarised with particular attention given to storage periods of greater than 60 days and the corresponding information available from application forms. Operational experiences are presented. IAEA recommendations are compared with current practice based on the conditions found in authorisations, on the information from application forms and details provided by the Small Users Liaison Group

  11. MOONLIGHT: A NEW LUNAR LASER RANGING RETROREFLECTOR INSTRUMENT

    Directory of Open Access Journals (Sweden)

    M. Garattini

    2013-12-01

    Full Text Available Since 1969 Lunar Laser Ranging (LLR to the Apollo Cube Corner Reflector (CCR arrays has supplied several significant tests of gravity: Geodetic Precession, the Strong and Weak Equivalence Principle (SEP, WEP, the Parametrized Post Newtonian (PPN parameter , the time change of the Gravitational constant (G, 1/r2 deviations and new gravitational theories beyond General Relativity (GR, like the unified braneworld theory (G. Dvali et al., 2003. Now a new generation of LLR can do better using evolved laser retroreflectors, developed from tight collaboration between my institution, INFN–LNF (Istituto Nazionale di Fisica Nucleare – Laboratori Nazionali di Frascati, and Douglas Currie (University of Maryland, USA, one of the fathers of LLR. The new lunar CCR is developing and characterizing at the “Satellite/Lunar laser ranging Characterization Facility” (SCF, in Frascati, performing our new industry standard space test procedure, the “SCF-Test”; this work contains the experimental results of the SCF-Test applied to the new lunar CCR, and all the new payload developments, including the future SCF tests. The International Lunar Network (ILN research project considers our new retroreflector as one of the possible “Core Instruments”

  12. Integrated waste management and the tool of life cycle inventory : a route to sustainable waste management

    Energy Technology Data Exchange (ETDEWEB)

    McDougall, F.R.; White, P.R. [Procter and Gamble Newcastle Technical Centre, Newcastle (United Kingdom). Corporate Sustainable Development

    2000-07-01

    An overall approach to municipal waste management which integrates sustainable development principles was discussed. The three elements of sustainability which have to be balanced are environmental effectiveness, economic affordability and social acceptability. An integrated waste management (IWM) system considers different treatment options and deals with the entire waste stream. A life cycle inventory (LCI) and life cycle assessment (LCA) is used to determine the environmental burdens associated with IWM systems. LCIs for waste management are currently available for use in Europe, the United States, Canada and elsewhere. LCI is being used by waste management companies to assess the environmental attributes of future contract tenders. The models are used as benchmarking tools to assess the current environmental profile of a waste management system. They are also a comparative planning and communication tool. The authors are currently looking into publishing, at a future date, the experience of users of this LCI environmental management tool. 12 refs., 3 figs.

  13. Nuclear waste and hazardous waste in the public perception

    International Nuclear Information System (INIS)

    Kruetli, Pius; Seidl, Roman; Stauffacher, Michael

    2015-01-01

    The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

  14. Nuclear waste and hazardous waste in the public perception

    Energy Technology Data Exchange (ETDEWEB)

    Kruetli, Pius; Seidl, Roman; Stauffacher, Michael [ETH Zurich (Switzerland). Inst. for Environmental Decisions

    2015-07-01

    The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

  15. Exocrine and endocrine testicular function during the treatment of experimental orchitis and nonspecific orchoepididymitis by low-energy laser radiation

    Science.gov (United States)

    Reznikov, Leonid L.; Pupkova, Ludmila S.; Bell, H.; Murzin, Alexander G.

    1995-05-01

    Investigations into the biological effects of low-energy laser radiation (LLR) are characterized by a score of challenges, which are due primarily to a cascade of laser-induced and sometimes antagonistic processes. To investigate these processes on various biologic levels, we analyzed local and general effects of LLR on the exocrine and endocrine functions of the accessory sex glands in experimentally induced orchitis and orchoepididymitis in rabbits, and in clinical studies on male patients. The results indicate that LLR may alter the inflammatory response, including the exudative reaction, macrophage migration, and fibroblast activity. Furthermore, LLR may result in changes in serum concentrations of LH, FSH, and ACTH, prolactin, testosterone, cortisol and aldosterone. Some of these changes may be at least partially responsible for the well-known anti-inflammatory effects of LLR.

  16. Evaluation of Waste Arising from Future Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Jubin, Robert Thomas; Taiwo, Temitope; Wigeland, Roald

    2015-01-01

    A comprehensive study was recently completed at the request of the US Department of Energy Office of Nuclear Energy (DOE-NE) to evaluate and screen nuclear fuel cycles. The final report was issued in October 2014. Uranium- and thorium-based fuel cycles were evaluated using both fast and thermal spectrum reactors. Once-through, limited-recycle, and continuous-recycle cases were considered. This study used nine evaluation criteria to identify promising fuel cycles. Nuclear waste management was one of the nine evaluation criteria. The waste generation criterion from this study is discussed herein.

  17. Waste segregation

    International Nuclear Information System (INIS)

    Clark, D.E.; Colombo, P.

    1982-01-01

    A scoping study has been undertaken to determine the state-of-the-art of waste segregation technology as applied to the management of low-level waste (LLW). Present-day waste segregation practices were surveyed through a review of the recent literature and by means of personal interviews with personnel at selected facilities. Among the nuclear establishments surveyed were Department of Energy (DOE) laboratories and plants, nuclear fuel cycle plants, public and private laboratories, institutions, industrial plants, and DOE and commercially operated shallow land burial sites. These survey data were used to analyze the relationship between waste segregation practices and waste treatment/disposal processes, to assess the developmental needs for improved segregation technology, and to evaluate the costs and benefits associated with the implementation of waste segregation controls. This task was planned for completion in FY 1981. It should be noted that LLW management practices are now undergoing rapid change such that the technology and requirements for waste segregation in the near future may differ significantly from those of the present day. 8 figures

  18. Modern technologies of processing municipal solid waste: investing in the future

    Science.gov (United States)

    Rumyantseva, A.; Berezyuk, M.; Savchenko, N.; Rumyantseva, E.

    2017-06-01

    The problem of effective municipal solid waste (MSW) management is known to all the municipal entities of the Russian Federation. The problem is multifaceted and complex. The article analyzes the dynamics of municipal solid waste formation and its utilization within the territory of the EU and Russia. The authors of the paper suggest a project of a plant for processing municipal solid waste into a combustible gas with the help of high temperature pyrolysis. The main indicators of economic efficiency are calculated.

  19. Low and intermediate radioactive waste management at OPG's western waste management facility

    International Nuclear Information System (INIS)

    Ellsworth, M.

    2006-01-01

    'Full text:' This paper will discuss low and intermediate level radioactive waste operations at Ontario Power Generation's Western Waste Management Facility. The facility has been in operation since 1974 and receives about 5000 - 7000 m 3 of low and intermediate level radioactive waste per year from Ontario's nuclear power plants. Low-level radioactive waste is received at the Waste Volume Reduction Building for possible volume reduction before it is placed into storage. Waste may be volume reduced by one of two methods at the WWMF, through either compaction or incineration. The Compactor is capable of reducing the volume of waste by a factor up to 5:1 for most waste. The Radioactive Incinerator is capable of volume reducing incinerable material by a factor up to 70:1. After processing, low-level waste is stored in above ground concrete warehouse-like structures called Low Level Storage Buildings. Low-level waste that cannot be volume reduced is placed into steel containers and stored in the Low Level Storage Buildings. Intermediate level waste is stored mainly in steel lined concrete storage structures. WWMF has both above ground and in-ground storage structures for intermediate level waste. Intermediate level waste consists primarily of resin and filters used to keep reactor water systems clean, and some used reactor core components. All low and intermediate level waste storage at the WWMF is considered interim storage and the material can be retrieved for future disposal or permanent storage. Current improvement initiatives include the installation of a new radioactive incinerator and a shredder/bagger. The new incinerator is a continuous feed system that is expected to achieve volume reduction rates up to 70:1, while incinerating higher volumes of waste than its predecessor. The shredder will break down large/bulky items into a form, which can be processed for further volume reduction. A Refurbishment Waste Storage Project is underway in anticipation of the

  20. CEGB's radioactive waste management strategy

    International Nuclear Information System (INIS)

    Passant, F.H.; Maul, P.R.

    1989-01-01

    The Central Electricity Generating Board (CEGB) produces low-level and intermediate-level radioactive wastes in the process of operating its eight Magnox and five Advanced Gas Cooled Reactor (AGR) nuclear power stations. Future wastes will also arise from a programme of Pressurised Water Reactors (PWRs) and the decommissioning of existing reactors. The paper gives details of how the UK waste management strategy is put into practice by the CEGB, and how general waste management principles are developed into strategies for particular waste streams. (author)

  1. Nuclear waste landscapes

    International Nuclear Information System (INIS)

    Solomon, B.D.; Cameron, D.M.

    1990-01-01

    In this paper the authors explore the time dimension in nuclear waste disposal, with the hope of untangling future land use issues for a full range of radioactive waste facilities. The longevity and hazards presented by nuclear reactor irradiated (spent) fuel and liquid reprocessing waste are well known. Final repositories for these highly radioactive wastes, to be opened early in the 21st Century, are to be located deep underground in rural locations throughout the developed world. Safety concerns are addressed by engineered and geological barriers containing the waste containers, as well as through geographic isolation from heavily populated areas. Yet nuclear power plants (as well as other applications of atomic energy) produce an abundance of other types of radioactive wastes. These materials are generally known as low level wastes (LLW) in the United States, though their level of longevity and radioactivity can vary dramatically

  2. Well bore Flow Treatment Used to Predict Radioactive Brine Releases to the Surface from Future Drilling Penetrations into the Waste Isolation Pilot Plant (WIPP), New Mexico, USA

    International Nuclear Information System (INIS)

    Brien, D.G.O.; Stoelzel, D.M.; Hadgu, T.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is the U.S. Department of Energy's (DOE) mined geologic repository in southeastern New Mexico, USA.This site is designed for the permanent burial of transuranic radioactive waste generated by defense related activities.The waste produces gases when exposed to brine. This gas generation may result in increased pressures over time. Therefore, a future driller that unknowingly penetrates through the site may experience a blowout. This paper describes the methodology used to predict the resultant volumes of contaminated brine released

  3. Cost for the radioactive wastes from nuclear power

    International Nuclear Information System (INIS)

    1989-06-01

    The future cost for handling, storing and disposing of radioactive wastes from the Swedish nuclear power plants are calculated in this report. The following plants and systems are already operating: - Transportsystem for radioactive wastes. - A control spent fuel intermediate storage plant. - A repository for low and medium level wastes. These are planned: - A treatment plant for used fuels. A repository for high-level wastes and repository for decommissioning wastes. The costs include Rand D and decommissioning. Total future costs from 1990 are estimated to be 43 billion SEK (6,5 billion dollars), during 60 years. Up to 1990 7,4 billion SEK (1,1 billion dollars) have been spent. (L.E.)

  4. A strategy for analysis of TRU waste characterization needs

    International Nuclear Information System (INIS)

    Leigh, C.D.; Chu, M.S.Y.; Arvizu, J.S.; Marcinkiewicz, C.J.

    1994-01-01

    Regulatory compliance and effective management of the nation's TRU waste requires knowledge about the constituents present in the waste. With limited resources, the DOE needs a cost-effective characterization program. In addition, the DOE needs a method for predicting the present and future analytical requirements for waste characterization. Thus, a strategy for predicting the present and future waste characterization needs that uses current knowledge of the TRU inventory and prioritization of the data needs is presented

  5. Summary of International Waste Management Programs (LLNL Input to SNL L3 MS: System-Wide Integration and Site Selection Concepts for Future Disposition Options for HLW)

    Energy Technology Data Exchange (ETDEWEB)

    Greenberg, Harris R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Blink, James A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Halsey, William G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sutton, Mark [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2011-08-11

    The Used Fuel Disposition Campaign (UFDC) within the Department of Energy’s Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation’s spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. This Lessons Learned task is part of a multi-laboratory effort, with this LLNL report providing input to a Level 3 SNL milestone (System-Wide Integration and Site Selection Concepts for Future Disposition Options for HLW). The work package number is: FTLL11UF0328; the work package title is: Technical Bases / Lessons Learned; the milestone number is: M41UF032802; and the milestone title is: “LLNL Input to SNL L3 MS: System-Wide Integration and Site Selection Concepts for Future Disposition Options for HLW”. The system-wide integration effort will integrate all aspects of waste management and disposal, integrating the waste generators, interim storage, transportation, and ultimate disposal at a repository site. The review of international experience in these areas is required to support future studies that address all of these components in an integrated manner. Note that this report is a snapshot of nuclear power infrastructure and international waste management programs that is current as of August 2011, with one notable exception. No attempt has been made to discuss the currently evolving world-wide response to the tragic consequences of the earthquake and tsunami that devastated Japan on March 11, 2011, leaving more than 15,000 people dead and more than 8,000 people missing, and severely damaging the Fukushima Daiichi nuclear power complex. Continuing efforts in FY 2012 will update the data, and summarize it in an Excel spreadsheet for easy comparison and assist in the knowledge management of the study cases.

  6. FUTURE CLIMATE ANALYSIS

    International Nuclear Information System (INIS)

    R.M. Forester

    2000-01-01

    This Analysis/Model Report (AMR) documents an analysis that was performed to estimate climatic variables for the next 10,000 years by forecasting the timing and nature of climate change at Yucca Mountain (YM), Nevada (Figure l), the site of a potential repository for high-level radioactive waste. The future-climate estimates are based on an analysis of past-climate data from analog meteorological stations, and this AMR provides the rationale for the selection of these analog stations. The stations selected provide an upper and a lower climate bound for each future climate, and the data from those sites will provide input to the infiltration model (USGS 2000) and for the total system performance assessment for the Site Recommendation (TSPA-SR) at YM. Forecasting long-term future climates, especially for the next 10,000 years, is highly speculative and rarely attempted. A very limited literature exists concerning the subject, largely from the British radioactive waste disposal effort. The discussion presented here is one method, among many, of establishing upper and lower bounds for future climate estimates. The method used here involves selecting a particular past climate from many past climates, as an analog for future climate. Other studies might develop a different rationale or select other past climates resulting in a different future climate analog

  7. FUTURE CLIMATE ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    R.M. Forester

    2000-03-14

    This Analysis/Model Report (AMR) documents an analysis that was performed to estimate climatic variables for the next 10,000 years by forecasting the timing and nature of climate change at Yucca Mountain (YM), Nevada (Figure l), the site of a potential repository for high-level radioactive waste. The future-climate estimates are based on an analysis of past-climate data from analog meteorological stations, and this AMR provides the rationale for the selection of these analog stations. The stations selected provide an upper and a lower climate bound for each future climate, and the data from those sites will provide input to the infiltration model (USGS 2000) and for the total system performance assessment for the Site Recommendation (TSPA-SR) at YM. Forecasting long-term future climates, especially for the next 10,000 years, is highly speculative and rarely attempted. A very limited literature exists concerning the subject, largely from the British radioactive waste disposal effort. The discussion presented here is one method, among many, of establishing upper and lower bounds for future climate estimates. The method used here involves selecting a particular past climate from many past climates, as an analog for future climate. Other studies might develop a different rationale or select other past climates resulting in a different future climate analog.

  8. Waste from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Nielsen, P.O.

    1992-05-01

    This report is based on the assumption that all twelve nuclear power plants will be shut down no later than A.D. 2010, as was decided by the parliament after the referendum on the future of nuclear power in Sweden. The recent 'Party agreement on the energy policy' of January 15, 1991 does, indeed, leave the door open for an extension of the operational period for the nuclear reactors. This will, however, not change the recommendations and conclusions drawn in this report. The report consists of two parts. Part 1 discusses classification of waste from decommissioning and makes comparisons with the waste arising from reactor operation. Part 2 discusses the documentation required for decommissioning waste. Also this part of the report draws parallels with the documentation required by the authorities for the radioactive waste arising from operation of the nuclear power plants. To some extent these subjects depend on the future use of the nuclear power plant sites after decommissioning of the plants. The options for future site use are briefly discussed in an appendix to the report. There are many similarities between the waste from reactor operations and the waste arising from dismantling and removal of decommissioned nuclear power plants. Hence it seems natural to apply the same criteria and recommendations to decommissioning waste as those presently applicable to reactor waste. This is certainly true also with respect to documentation, and it is strongly recommended that the documentation requirements on decommissioning waste are made identical, or at least similar, to the documentation requirements for reactor waste in force today. (au)

  9. Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs

    International Nuclear Information System (INIS)

    Di Sanza, E.F.; Carilli, J.T.

    2006-01-01

    Waste Acceptance Criteria. The disposal operations previously mentioned take place at the NTS in two disposal facilities. The isolation protection and overall performance of the two LLW disposal facilities at the NTS transcend those of any federal radioactive waste disposal site in the United States. The first of the two disposal sites is the Area 5 Radioactive Waste Management Site (RWMS) which is situated on alluvial fan deposits in the Frenchman Flat basin, approximately 770 feet (235 meters) above the water table. The Area 5 RWMS utilizes a combination of engineered shallow land disposal cells and deep augured shafts for the disposal of a variety of waste streams. Fifteen miles (24 kilometers) north of the Area 5 RWMS is the Area 3 RWMS located approximately 1,600 feet (488 meters) above the water table in Yucca Flat. Disposal activities at the Area 3 RWMS center around the placement of bulk LLW in subsidence craters formed from underground testing of nuclear weapons. Native alluvium soil is used to cover waste placed in the disposal cells at both facilities. In addition, information on the technical attributes, facility performance, updates on waste disposal volumes and capabilities, and current and future disposal site requirements will also be described. (authors)

  10. Radioactive waste management

    International Nuclear Information System (INIS)

    Tsoulfanidis, N.

    1991-01-01

    The management of radioactive waste is a very important part of the nuclear industry. The future of the nuclear power industry depends to a large extent on the successful solution of the perceived or real problems associated with the disposal of both low-level waste (LLW) and high-level waste (HLW). All the activities surrounding the management of radioactive waste are reviewed. The federal government and the individual states are working toward the implementation of the Nuclear Waste Policy Act and the Low-Level Waste Policy Act. The two congressional acts are reviewed and progress made as of early 1990 is presented. Spent-fuel storage and transportation are discussed in detail as are the concepts of repositories for HLW. The status of state compacts for LLW is also discussed. Finally, activities related to the decommissioning of nuclear facilities are also described

  11. Tribal Decisions-Makers Guide to Solid Waste Management: Chapter 2 - Developing Solid Waste Management Plans

    Science.gov (United States)

    Solid waste management plans offer a host of benefits for tribes and Alaskan Native villages. Through the preparation of these plans, you can assess your cur-rent and future waste management needs, set priorities, and allocate resources accordingly.

  12. Addition of liquid waste incineration capability to the INEL's low-level waste incinerator

    International Nuclear Information System (INIS)

    Steverson, E.M.; Clark, D.P.; McFee, J.N.

    1986-01-01

    A liquid waste system has recently been installed in the Waste Experimental Reduction Facility (WERF) incinerator at the Idaho National Engineering Laboratory (INEL). In this paper, aspects of the incineration system such as the components, operations, capabilities, capital cost, EPA permit requirements, and future plans are discussed. The principal objective of the liquid incineration system is to provide the capability to process hazardous, radioactively contaminated, non-halogenated liquid wastes. The system consists primarily of a waste feed system, instrumentation and controls, and a liquid burner, which were procured at a capital cost of $115,000

  13. Integrated municipal solid waste scenario model using advanced pretreatment and waste to energy processes

    International Nuclear Information System (INIS)

    Ionescu, Gabriela; Rada, Elena Cristina; Ragazzi, Marco; Mărculescu, Cosmin; Badea, Adrian; Apostol, Tiberiu

    2013-01-01

    Highlights: • Appropriate solution for MSW management in new and future EU countries. • Decrease of landfill disposal applying an Integrated MSW approach. • Technological impediments and environmental assessment. - Abstract: In this paper an Integrated Municipal Solid Waste scenario model (IMSW-SM) with a potential practical application in the waste management sector is analyzed. The model takes into account quantification and characterization of Municipal Solid Waste (MSW) streams from different sources, selective collection (SC), advanced mechanical sorting, material recovery and advanced thermal treatment. The paper provides a unique chain of advanced waste pretreatment stages of fully commingled waste streams, leading to an original set of suggestions and future contributions to a sustainable IMSWS, taking into account real data and EU principles. The selection of the input data was made on MSW management real case studies from two European regions. Four scenarios were developed varying mainly SC strategies and thermal treatment options. The results offer useful directions for decision makers in order to calibrate modern strategies in different realities

  14. Future industrial issues for ANDRA

    International Nuclear Information System (INIS)

    Auverlot, D.

    1998-01-01

    ANDRA manages industrially 90 % in volume of radioactive waste produced in France. This is short life waste of low and medium activity. In compliance with the law of 1991, which transformed it into a public body with an industrial and commercial character, ANDRA also heads aspect 2 of the research into the 10 % of remaining highly active long life waste, by attempting to evaluate the possibilities of storing it in deep geological layers, either reversibly or irreversibly. The industrial issues of the future for ANDRA can be in different forms, following three meeting of major importance for ANDRA and for the producers of nuclear waste. These are: the meeting of 2006, at the end of which, in compliance with the law of 1991, the Parliament must re-examine the question of the management of highly active, long life waste; the renewal of nuclear facilities; the future meeting concerning future generations. However, whatever these different stage and whatever the different types of waste considered, the single and major challenge with which ANDRA is confronted is to prove that it is capable of providing a sure danger-free management of all radioactive waste. In this context, it appears necessary, today, to intensify research into aspects 1 and 3 of the law of 1991, to respect the balance of the three aspects. This in fact constitutes an essential pledge of the credibility of the procedure instituted by the law: at present, to clearly specify the research into surface storing in the short or long terms; building the three laboratories, the authorization for which has been subject to public inquiry. And also to keep, for 2006, the largest possible choice of the geological environment. (author)

  15. WASTE-ACC: A computer model for analysis of waste management accidents

    International Nuclear Information System (INIS)

    Nabelssi, B.K.; Folga, S.; Kohout, E.J.; Mueller, C.J.; Roglans-Ribas, J.

    1996-12-01

    In support of the U.S. Department of Energy's (DOE's) Waste Management Programmatic Environmental Impact Statement, Argonne National Laboratory has developed WASTE-ACC, a computational framework and integrated PC-based database system, to assess atmospheric releases from facility accidents. WASTE-ACC facilitates the many calculations for the accident analyses necessitated by the numerous combinations of waste types, waste management process technologies, facility locations, and site consolidation strategies in the waste management alternatives across the DOE complex. WASTE-ACC is a comprehensive tool that can effectively test future DOE waste management alternatives and assumptions. The computational framework can access several relational databases to calculate atmospheric releases. The databases contain throughput volumes, waste profiles, treatment process parameters, and accident data such as frequencies of initiators, conditional probabilities of subsequent events, and source term release parameters of the various waste forms under accident stresses. This report describes the computational framework and supporting databases used to conduct accident analyses and to develop source terms to assess potential health impacts that may affect on-site workers and off-site members of the public under various DOE waste management alternatives

  16. Hazardous Waste Remedial Actions Program: integrating waste management

    International Nuclear Information System (INIS)

    Petty, J.L.; Sharples, F.E.

    1986-01-01

    The Hazardous Waste Remedial Actions Program was established to integrate Defense Programs' activities in hazardous and mixed waste management. The Program currently provides centralized planning and technical support to the Office of the Assistant Secretary for Defense Programs. More direct project management responsibilities may be assumed in the future. The Program, under the direction of the ASDP's Office of Defense Waste and Transportation Management, interacts with numerous organizational entities of the Department. The Oak Ridge Operations Office has been designated as the Lead Field Office. The Program's four current components cover remedial action project identification and prioritization; technology adaptation; an informative system; and a strategy study for long-term, ''corporate'' project and facility planning

  17. Interim Hanford Waste Management Plan

    International Nuclear Information System (INIS)

    1985-09-01

    The September 1985 Interim Hanford Waste Management Plan (HWMP) is the third revision of this document. In the future, the HWMP will be updated on an annual basis or as major changes in disposal planning at Hanford Site require. The most significant changes in the program since the last release of this document in December 1984 include: (1) Based on studies done in support of the Hanford Defense Waste Environmental Impact Statement (HDW-EIS), the size of the protective barriers covering contaminated soil sites, solid waste burial sites, and single-shell tanks has been increased to provide a barrier that extends 30 m beyond the waste zone. (2) As a result of extensive laboratory development and plant testing, removal of transuranic (TRU) elements from PUREX cladding removal waste (CRW) has been initiated in PUREX. (3) The level of capital support in years beyond those for which specific budget projections have been prepared (i.e., fiscal year 1992 and later) has been increased to maintain Hanford Site capability to support potential future missions, such as the extension of N Reactor/PUREX operations. The costs for disposal of Hanford Site defense wastes are identified in four major areas in the HWMP: waste storage and surveillance, technology development, disposal operations, and capital expenditures

  18. Prediction equations for corrosion rates of a A-537 and A-516 steels in Double Shell Slurry, Future PUREX, and Hanford Facilities Wastes

    International Nuclear Information System (INIS)

    Divine, J.R.; Bowen, W.M.; Mackey, D.B.; Bates, D.J.; Pool, K.H.

    1985-06-01

    Even though the interest in the corrosion of radwaste tanks goes back to the mid-1940's when waste storage was begun, and a fair amount of corrosion work has been done since then, the changes in processes and waste types have outpaced the development of new data pertinent to the new double shell tanks. As a consequence, Pacific Northwest Laboratory (PNL) began a development of corrosion data on a broad base of waste compositions in 1980. The objective of the program was to provide operations personnel with corrosion rate data as a function of waste temperature and composition. The work performed in this program examined A-537 tank steel in Double Shell Slurry and Future PUREX Wastes, at temperatures between 40 and 180 0 C as well as in Hanford Facilities Waste at 25 and 50 0 C. In general, the corrosion rates were less than 1 mpy (0.001 in./y) and usually less than 0.5 mpy. Excessive corrosion rates (>1 mpy) were only found in dilute waste compositions or in concentrated caustic compositions at temperatures above 140 0 C. Stress corrosion cracking was only observed under similar conditions. The results are presented as polynomial prediction equations with examples of the output of existing computer codes. The codes are not provided in the text but are available from the authors. 12 refs., 5 figs., 19 tabs

  19. Cost for the radioactive wastes from nuclear power

    International Nuclear Information System (INIS)

    1992-06-01

    The future cost for handling, storing and disposing of radioactive wastes from the Swedish nuclear power plants are calculated in this report. The following plants and systems are already operating: * Transport system for radioactive wastes, * A control spent fuel intermediate storage plant, * A repository for low and medium level wastes. These are planned: * A treatment plant for used fuels, * A repository for high-level wastes, and * Repository for decommissioning wastes. The costs include R and D and decommissioning. Total future costs from 1993 are estimated to be 46.4 billion SEK (8.3 billion USD), during 60 years. Up to 1992 8.7 billion SEK (1.6 billion USD) have been spent

  20. Past and future cadmium emissions from municipal solid-waste incinerators in Japan for the assessment of cadmium control policy.

    Science.gov (United States)

    Ono, Kyoko

    2013-11-15

    Cadmium (Cd) is a harmful pollutant emitted from municipal solid-waste incinerators (MSWIs). Cd stack emissions from MSWIs have been estimated between 1970 and 2030 in Japan. The aims of this study are to quantify emitted Cd by category and to analyze Cd control policies to reduce emissions. Emissions were estimated using a dynamic substance flow analysis (SFA) that took into account representative waste treatment flows and historical changes in emission factors. This work revealed that the emissions peaked in 1973 (11.1t) and were ten times those in 2010 (1.2 t). Emission from MSWIs was two-thirds of that from non-ferrous smelting in 2010. The main Cd emission source was pigment use in the 1970s, but after 2000 it had shifted to nickel-cadmium (Ni-Cd) batteries. Future emissions were estimated for 2030. Compared to the business-as-usual scenario, an intensive collection of used Ni-Cd batteries and a ban on any future use of Ni-Cd batteries will reduce emissions by 0.09 and 0.3 1t, respectively, in 2030. This approach enables us to identify the major Cd emission source from MSWIs, and to prioritize the possible Cd control policies. Copyright © 2013 Elsevier B.V. All rights reserved.

  1. Political life and half-life: the future formulation of nuclear waste public policy in the United States.

    Science.gov (United States)

    Leroy, David

    2006-11-01

    The United States continues to need forward-thinking and revised public policy to assure safe nuclear waste disposal. Both the high- and low-level disposal plans enacted by Congress in the 1980's have been frustrated by practical and political interventions. In the interim, ad hoc solutions and temporary fixes have emerged as de facto policy. Future statutory, regulatory, and administrative guidance will likely be less bold, more narrowly focused, and adopted at lower levels of government, more informally, in contrast to the top-down, statutory policies of the 1980's.

  2. Basic approaches to the limitation of doses and radiological risks from surface disposal of long-lived radioactive waste for future generations

    International Nuclear Information System (INIS)

    Likhtarev, I.; Kovgan, L.; Berkovskiy, V.

    2001-01-01

    National radiation standards of Ukraine (NRSU-97/D-2000) recently put into force, which consider the basic principles of radiological protection from the sources of potential exposure, introduce four groups of potential exposure sources depending on types and scope of the consequences of occurrence of different critical events. In the third group are those occurrence which are associated with the events that can take place in the future (including the distant future) at the exempted from regulation facilities as a result of natural abnormal processes and catastrophes as well as inadvertent human intrusions. Future generations living at the moment of the event occurrence can become the subject of exposure. These sources must be taken into account at the stage of radioactive waste repositories designing. Taking into account the peculiarity of sources of the third group of potential, that they are associated with those critical events, which can take place in the distant future (in hundreds and thousands of years) and as a consequence may result in the exposure of future generations of people NRSU-97/D2000 sets an additional principle for potential exposure from sources of third group which requires that the future generations are guaranteed to have at least the same level of radiation protection against actions undertaken nowadays as the present generation. This principle is implemented through setting a requirement that harm for human health of future generation must not exceed the harm corresponding to negligible risk which is 5 x 10 -7 year -1 . NRSU-97/D-2000 establishes two reference dose levels A and B (50 and 1 mSv year -1 ) depending on which the acceptability of surface (or near-surface) disposals of long-lived radioactive waste is determined. In presentation the requirements on the critical events occurrence probability, two groups of scenario, which can lead to the critical event, and five reference scenarios of exposure and their parameters are discussed

  3. Waste Management During RA Reactor Decommissioning

    International Nuclear Information System (INIS)

    Markovic, M.; Avramovic, I.

    2008-01-01

    The objective of radioactive waste management during the RA reactor decommissioning is to deal with radioactive waste in a manner that protects human health and the environment now and in the future. The estimation of waste quantities to be expected during decommissioning is a very important step in the initial planning. (author)

  4. Alternative-waste-form evaluation for Savannah River Plant high-level waste

    International Nuclear Information System (INIS)

    Gould, T.H. Jr.; Crandall, J.L.

    1982-01-01

    Results of the waste form evaluation are summarized as: risks of human exposure are comparable and extremely small for either borosilicate glass or Synroc ceramic. Waste form properties are more than adequate for either form. The waste form decision can therefore be made on the basis of practicality and cost effectiveness. Synroc offers lower costs for transportation and emplacement. The borosilicate glass form offers the lowest total disposal cost, much simpler and less costly production, an established and proven process, lower future development costs, and an earlier startup of the DWPF

  5. Evolution in radioactive waste countermeasures

    International Nuclear Information System (INIS)

    Moriguchi, Yasutaka

    1984-01-01

    The establishment of radioactive waste management measures is important to proceed further with nuclear power development. While the storage facility projects by utilities are in progress, large quantity of low level wastes are expected to arise in the future due to the decommissioning of nuclear reactors, etc. An interim report made by the committee on radioactive waste countermeasures to the Atomic Energy Commission is described as follows: the land disposal measures of ultra-low level and low level radioactive wastes, that is, the concept of level partitioning, waste management, the possible practice of handling wastes, etc.; the treatment and disposal measures of high level radioactive wastes and transuranium wastes, including task sharing among respective research institutions, the solidification/storage and the geological formation disposal of high level wastes, etc. (Mori, K.)

  6. Hanford Waste Management Plan, 1987

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose of the Hanford Waste Management Plan (HWMP) is to provide an integrated plan for the safe storage, interim management, and disposal of existing waste sites and current and future waste streams at the Hanford Site. The emphasis of this plan is, however, on the disposal of Hanford Site waste. The plans presented in the HWMP are consistent with the preferred alternative which is based on consideration of comments received from the public and agencies on the draft Hanford Defense Waste Environmental Impact Statement (HDW-EIS). Low-level waste was not included in the draft HDW-EIS whereas it is included in this plan. The preferred alternative includes disposal of double-shell tank waste, retrievably stored and newly generated TRU waste, one pre-1970 TRU solid waste site near the Columbia River and encapsulated cesium and strontium waste

  7. Cosmic disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

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

    1975-03-01

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

  8. Environmental assessment of waste management in Greenland: current practice and potential future developments

    DEFF Research Database (Denmark)

    Eisted, Rasmus; Christensen, Thomas Højlund

    2013-01-01

    ) for a system serving 56 000 inhabitants), but significant environmental loads are caused by air emissions from the incinerators and leachate from the landfills. Several alternative management scenarios were modelled and results show that increased use of incineration, full utilization of the heat production...... for district heating and separation of hazardous waste probably could improve Greenland’s waste management system. Segregation of recyclable materials as paper, cardboard and biowaste will do little to environmentally improve the waste management system due to loss of energy recovery from incineration...... and the long transport of the recyclables to markets. Export of waste to Denmark for incineration at modern waste incinerators with advanced flue gas cleaning could also be considered as a means to achieve better environmental performance of the waste management system....

  9. Not from my world. Responsibility for future generations in the final disposal of nuclear waste; Nicht von meiner Welt. Zukunftsverantwortung bei der Endlagerung von radioaktiven Reststoffen

    Energy Technology Data Exchange (ETDEWEB)

    Ott, Konrad [Kiel Univ. (Germany). Philosophisches Seminar; Semper, Franziska [TU Braunschweig (Germany). Inst. fuer Rechtswissenschaften

    2017-09-01

    In Germany the decision on a final repository for nuclear wastes is intended for 2031. The consequences of this decision will concern many generations in the future. Today there is a contradiction between the request of reversibility of all measures and the avoidance of the necessity of continuous activities for future generations. There is no way for a simple solution. The interests of future generations have to be considered as well as the interests of the actual living society.

  10. Waste paper recycling opportunities for government action. Vol. 4, corrugated waste. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, J.; Love, P.

    1978-01-01

    This study analyzes current and expected corrugated waste market conditions in Canada, with the objective of identifying government initiatives which could permanently increase recovery levels. Short-term, practical measures are featured. National and regional demand, generation and recovery levels are examined, along with imports and exports to the USA. Over 70% of corrugated waste is consumed in Ontario and Quebec, and most of this waste is generated in those two provinces. Average recovery rates in most major urban areas are estimated at 30-40%. Future demand, generation, and recovery are estimated, and it is suggested that there will be enough domestic demand to permit reclamation of nearly 35% of Canada's total corrugated wastes. This potential level is not expected to change significantly, and new demand opportunities appear minimal. Examination of the potential for future imports from the USA indicates that availability will tighten over the medium term, necessitating a search for new corrugated waste supply sources. Possible sources include supermakets, retail chains and large assembly manufacturing establishments; one of the most promising of these sources is shopping malls, and a study is appended which examines the feasibility of a corrugated waste source separation program within a hypothetical mall. Possible government actions are outlined to improve reclamation and recycling of corrugated waste in Canada, including the improvement of local recovery capabilities in British Columbia, Ontario and Quebec, and the reduction of freight costs for moving corrugated waste from low-recovery areas to high-demand areas. 26 refs., 9 figs., 31 tabs.

  11. The future of thermal waste treatment; Zukunft der thermischen Restabfallbehandlung

    Energy Technology Data Exchange (ETDEWEB)

    Wiemer, K.; Kern, M. (eds.); Tappen, I.; Weber-Wied, R. (comps.)

    2001-07-01

    Contents: State of the art of energy-efficient thermal waste treatment processes and practical examples; Regional and economic aspects; Licensing problems of thermal waste treatment plants. [German] Der vorliegende Tagungsband zum 2. Stassfurter Abfall- und Energieforum beschreibt den aktuellen Stand energieeffizienter thermischer Abfallbehandlungsmethoden an praktischen Beispielen und stellt den Bezug dieser Massnahmen zum raeumlich-wirtschaftlichen Umfeld dar. Darueber hinaus werden vergaberechtliche Fragen im Zusammenhang mit der europaweiten Ausschreibungspflicht fuer die Errichtung thermischer Abfallbehandlungsanlagen aufgezeigt und eroertert. (orig.)

  12. Preparing Los Alamos National Laboratory's Waste Management Program for the Future - 12175

    Energy Technology Data Exchange (ETDEWEB)

    Jones, Scotty W.; Dorries, Alison M.; Singledecker, Steven [Los Alamos National Laboratory, PO Box 1663, Los Alamos, NM 87545 (United States); Henckel, George [Los Alamos Site Office, MS-A316, Los Alamos, NM 87544 (United States)

    2012-07-01

    The waste management program at Los Alamos National Laboratory (LANL) is undergoing significant transition to establish a lean highly functioning waste management program that will succeed the large environmental cleanup waste management program. In the coming years, the environmental cleanup activities will be mostly completed and the effort will change to long-term stewardship. What will remain in waste management is a smaller program focused on direct off-site shipping to cost-effectively enable the enduring mission of the laboratory in support of the national nuclear weapons program and fundamental science and research. It is essential that LANL implement a highly functioning efficient waste management program in support of the core missions of the national weapons program and fundamental science and research - and LANL is well on the way to that goal. As LANL continues the transition process, the following concepts have been validated: - Business drivers including the loss of onsite disposal access and completion of major environmental cleanup activities will drive large changes in waste management strategies and program. - A well conceived organizational structure; formal management systems; a customer service attitude; and enthusiastic managers are core to a successful waste management program. - During times of organizational transition, a project management approach to managing change in a complex work place with numerous complex deliverables is successful strategy. - Early and effective engagement with waste generators, especially Project Managers, is critical to successful waste planning. - A well-trained flexible waste management work force is vital. Training plans should include continuous training as a strategy. - A shared fate approach to managing institutional waste decisions, such as the LANL Waste Management Recharge Board is effective. - An efficient WM program benefits greatly from modern technology and innovation in managing waste data and

  13. Tank waste concentration mechanism study

    International Nuclear Information System (INIS)

    Pan, L.C.; Johnson, L.J.

    1994-09-01

    This study determines whether the existing 242-A Evaporator should continue to be used to concentrate the Hanford Site radioactive liquid tank wastes or be replaced by an alternative waste concentration process. Using the same philosophy, the study also determines what the waste concentration mechanism should be for the future TWRS program. Excess water from liquid DST waste should be removed to reduce the volume of waste feed for pretreatment, immobilization, and to free up storage capacity in existing tanks to support interim stabilization of SSTS, terminal cleanout of excess facilities, and other site remediation activities

  14. Recent Trends in Sustainable Textile Waste Recycling Methods: Current Situation and Future Prospects.

    Science.gov (United States)

    Pensupa, Nattha; Leu, Shao-Yuan; Hu, Yunzi; Du, Chenyu; Liu, Hao; Jing, Houde; Wang, Huaimin; Lin, Carol Sze Ki

    2017-08-16

    In recent years, there have been increasing concerns in the disposal of textile waste around the globe. The growth of textile markets not only depends on population growth but also depends on economic and fashion cycles. The fast fashion cycle in the textile industry has led to a high level of consumption and waste generation. This can cause a negative environmental impact since the textile and clothing industry is one of the most polluting industries. Textile manufacturing is a chemical-intensive process and requires a high volume of water throughout its operations. Wastewater and fiber wastes are the major wastes generated during the textile production process. On the other hand, the fiber waste was mainly created from unwanted clothes in the textile supply chain. This fiber waste includes natural fiber, synthetic fiber, and natural/synthetic blends. The natural fiber is mostly comprised of cellulosic material, which can be used as a resource for producing bio-based products. The main challenge for utilization of textile waste is finding the method that is able to recover sugars as monosaccharides. This review provides an overview of valorization of textile waste to value-added products, as well as an overview of different strategies for sugar recovery from cellulosic fiber and their hindrances.

  15. The future supply of and demand for candidate materials for the fabrication of nuclear fuel waste disposal containers

    International Nuclear Information System (INIS)

    Grover, L.K.

    1990-01-01

    This report summarizes the findings of a literature survey carried out to assess the future world supply of and demand for titanium, copper and lead. These metals are candidate materials for the fabrication of containers for the immobilization and disposal of Canada's nuclear used-fuel waste for a reference Used-fuel Disposal Centre. Such a facility may begin operation by approximately 2020, and continue for about 40 years. The survey shows that the world has abundant supplies of titanium minerals (mostly in the form of ilmenite), which are expected to last up to at least 2110. However, for copper and lead the balance between supply and demand may warrant increased monitoring beyond the year 2000. A number of factors that can influence future supply and demand are discussed in the report

  16. Large local reactions to insect stings.

    Science.gov (United States)

    Golden, David B K

    2015-01-01

    Large local reactions (LLRs) are IgE-mediated late-phase inflammatory reactions that can cause great morbidity but are associated with a relatively low risk of future anaphylaxis. Patients with LLR may benefit from consultation with an allergist to help clarify the relative risk, to plan the best treatment for future stings, and to determine whether or not to pursue testing or venom immunotherapy (VIT). The chance of anaphylaxis to future stings is Immunology. Published by Elsevier Inc. All rights reserved.

  17. A Quantitative Analysis of the Reversibility of Nuclear Waste Storage: Waste Re-utilization

    International Nuclear Information System (INIS)

    Gollier, Christian; Devezeaux de Lavergne, Jean-Guy

    2001-01-01

    The reversibility of nuclear waste storage can be justified on various economic grounds, including the eventuality that future generations may wish to recover this waste in order to re-utilise it. Real options theory is used to cost this option. By including the value of this option in the cost/benefit analysis, it is possible to determine what present generations should spend to organise this reversibility. Taking current values of the materials contained in the waste, and taking into account the low growth trend of such values, we show that the reversibility value of a waste storage site is derisory

  18. Potential use of Plastic Waste as Construction Materials: Recent Progress and Future Prospect

    Science.gov (United States)

    Kamaruddin, M. A.; Abdullah, M. M. A.; Zawawi, M. H.; Zainol, M. R. R. A.

    2017-11-01

    Plastic associates products based have been considered as the world most consumer packaging solution. However, substantial quantities of plastic consumption have led to exponential increase of plastic derived waste. Recycling of plastic waste as valued added product such as concrete appears as one of promising solution for alternative use of plastic waste. This paper summarized recent progress on the development of concrete mixture which incorporates plastic wastes as partial aggregate replacement during concrete manufacturing. A collection of data from previous studies that have been researched which employed plastic waste in concrete mixtures were evaluated and conclusions are drawn based on the laboratory results of all the mentioned research papers studied.

  19. CURRENT STATUS AND FUTURE CHALLENGES OF HEALTHCARE WASTE MANAGEMENT IN INDONESIA

    Directory of Open Access Journals (Sweden)

    Sri Irianti

    2013-07-01

    Full Text Available Abstrak Latar belakang: Dalam memberikan pelayanan kesehatan, rumah sakit maupun sarana pelayanan kesehatan lainnya menghasilkan limbah medik yang mempunyai risiko menularkan penyakit-penyakit  tular darah dan penyakit lainnya  apabila tidak dikelola secara aman. Tujuan:Diperolehnya gambaran tentang kondisi dan praktik Pengelolaan Limbah Layanan Kesehatan (PLLK di beberapa rumah sakit umum (RSU di Indonesia, agar dapat digunakan oleh RSU dan sarana pelayanan kesehatan lainnya untuk melaksanakan PLLK secara aman. Bahan dan Cara: Kajian berupa survei dilakukan oleh Direktorat Penyehatan Lingkungan dengan cara mengirimkan kuesioner terstruktur di100 RSU pada tahun 2004. Hanya 76 RSU yang mengisi kuesioner. Lingkup survei meliputi aspek sanitasi RSU, di antaranya PLLK yang meliputi variabel ketersedian unit organisasi yang bertanggungjawab dalam PLLK, rencana pengelolaan limbah medik , ketersediaan pedoman PLLK, praktik pemilahan dan teknologi pengolahan limbah medik. Hasil: Sebagian besar RSU telah mempunyai unit yang bertanggungjawab dalam PLLK, namun hanya sekitar 33% yang mempunyai rencana PLLK. Demikian pula hanya sekitar 30% RSU yang memilah limbahnya menjadi tiga kategori sesuai pedomanPLLK, walaupun lebih dari 60% RSU telah mempunyai buku pedoman PLLK sesuai dengan Keputusan Menteri Kesehatan No. 1204/2004. Insinerasi merupakan cara pemusnahan limbah yang dipilih oleh mayoritas RSU. Kesimpulan: Masih banyak RSU yang disurvei belum mengelola limbahnya sesuai dengan Keputusan Menteri Kesehatan No. 1204/2004 seperti diamanatkan oleh Peraturan Pemerintah tentang Pengelolaan Limbah Berbahaya dan Beracun termasuk  limbah layanan kesehatan. Kata kunci: fasilitas kesehatan, pengelolaan limbah layanan kesehatan, kebijakan, risiko kesehatan Abstract Background: In providing healthcare services, hospitals and other healthcare facilities generate medical wastes which can spread blood-borne diseases and other waste diseases if they do not manage their

  20. ZeroWaste BYG: Redesigning construction materials towards zero waste society

    DEFF Research Database (Denmark)

    Kirkelund, Gunvor Marie; Schmidt, Jacob Wittrup; Ottosen, Lisbeth M.

    2014-01-01

    material. The physical‐chemical characteristics of fly ash, such as large uniformity coefficient, clay‐sized particles and rich in some metal elements and salts, show the possibility ofbeing a raw material also for bricks and lightweight aggregates. In the future we expect increasing political pressure......The ZeroWaste research group (www.zerowaste.byg.dtu.dk) at the Department of Civil Engineering was established in 2012 and covers the broad range of expertise required for turning waste materials into attractive, new materials. Members of the group have developed methods for removal of heavy metals...... and phosphorous from waste incineration, sewage sludge and other bio ashes [1], providing the basis to make these ash types an attractive, new material for the building sector.The amount of waste increases and it is both difficult and expensive to handle many waste types as e.g.different ashes. At the same time...

  1. The OTD Robotics Waste Minimization Program

    International Nuclear Information System (INIS)

    Couture, S.A.

    1992-04-01

    The danger to human health and safety posed by exposure to transuranic (TRU) and Pu contaminated materials necessitates remote processing in confined environments. Currently these operations are carried out in gloveboxes and hot-cells by human operators using lead- lined gloves or teleoperated manipulators. Protective clothing worn by operators during gloved operations has contributed significantly to the waste problems currently facing site remediators. The DOE Environmental Restoration and Waste Management (ER/WM) Program is in the process of developing and demonstrating technologies to assist in the remediation of sites that have accumulated wastes generated using these processes over the past five decades. Recognizing that continued use of existing production, recovery and waste treatment systems will compound the remediation problem, DOE has made a commitment to waste minimization. To reduce waste generation during weapons production and waste processing operations, automated processes are being developed and demonstrated for use in future DOE processing facilities as part of OTD's Robotics Technology Development Program. These technologies are currently being applied to pyrochemical processing systems to demonstrate conversion of plutonium oxide to metal. However, these technologies are expected to have applications in a variety of waste processing systems including those used to treat high-level tank wastes, buried wastes requiring remote processing, mixed wastes, and unknown hazardous materials. In addition to reducing the future waste burden of DOE, automated processes are an effective way to comply with existing and anticipated federal, state, and local regulations related to personal health and safety and the health of the environment

  2. Accelerated cardiac cine MRI using locally low rank and finite difference constraints.

    Science.gov (United States)

    Miao, Xin; Lingala, Sajan Goud; Guo, Yi; Jao, Terrence; Usman, Muhammad; Prieto, Claudia; Nayak, Krishna S

    2016-07-01

    To evaluate the potential value of combining multiple constraints for highly accelerated cardiac cine MRI. A locally low rank (LLR) constraint and a temporal finite difference (FD) constraint were combined to reconstruct cardiac cine data from highly undersampled measurements. Retrospectively undersampled 2D Cartesian reconstructions were quantitatively evaluated against fully-sampled data using normalized root mean square error, structural similarity index (SSIM) and high frequency error norm (HFEN). This method was also applied to 2D golden-angle radial real-time imaging to facilitate single breath-hold whole-heart cine (12 short-axis slices, 9-13s single breath hold). Reconstruction was compared against state-of-the-art constrained reconstruction methods: LLR, FD, and k-t SLR. At 10 to 60 spokes/frame, LLR+FD better preserved fine structures and depicted myocardial motion with reduced spatio-temporal blurring in comparison to existing methods. LLR yielded higher SSIM ranking than FD; FD had higher HFEN ranking than LLR. LLR+FD combined the complimentary advantages of the two, and ranked the highest in all metrics for all retrospective undersampled cases. Single breath-hold multi-slice cardiac cine with prospective undersampling was enabled with in-plane spatio-temporal resolutions of 2×2mm(2) and 40ms. Highly accelerated cardiac cine is enabled by the combination of 2D undersampling and the synergistic use of LLR and FD constraints. Copyright © 2016 Elsevier Inc. All rights reserved.

  3. Nuclear waste disposal: technology and environmental hazards

    International Nuclear Information System (INIS)

    Hare, F.K.; Aikin, A.M.

    1980-01-01

    The subject is discussed under the headings: introduction; the nature and origin of wastes (fuel cycles; character of wastes; mining and milling operations; middle stages; irradiated fuel; reprocessing (waste generation); reactor wastes); disposal techniques and disposal of reprocessing wastes; siting of repositories; potential environmental impacts (impacts after emplacement in a rock repository; catastrophic effects; dispersion processes (by migrating ground water); thermal effects; future security; environmental survey, monitoring and modelling); conclusion. (U.K.)

  4. Principles and guidelines for radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    1988-06-01

    Four basic principles relevant to radioactive waste disposal identified. These principles cover the justification of the activity giving rise to the waste, the consideration of risk to present and future generations, the minimization of the need for intervention in the future, and the financial obligations of the licensee. The use of risk limits as opposed to dose limits associated with disposal is discussed, as are the concepts of critical group, de minimis, and ALARA, in the context of a waste disposal facility. Guidance is given on the selection of the preferred waste disposal concept from among several alternatives, and for judging proposed design improvements to the chosen concept

  5. Radioactive waste management in an Australian state - IAEA style

    International Nuclear Information System (INIS)

    Shields, B.; Newbery, S.M.

    1999-01-01

    The IAEA have produced a series of publications within the RADWASS programme. These publications are comprehensive in their coverage and are applicable to all aspects of radioactive waste management - from the individual user level to State and National level. Adherence to the principles contained in these publications is advocated in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The publications provide a useful check list against which to determine the current status of radioactive management, at various levels (individual level, State, National) and also provide a basis for planning future waste management requirements. In Tasmania, these publications have been utilised to assess the current radioactive waste management system and to determine future management requirements, particularly for storage of radioactive waste. This paper illustrates the application of the publications for auditing individual users' waste management status and for determining future State storage requirements for radioactive waste. A brief outline of the process used and the main issues identified as a result, will be presented. These issues include some requiring a National approach for their resolution. Copyright (1999) Australasian Radiation Protection Society Inc

  6. Prediction of combustible waste generation and estimate of potential energy by applying waste to energy technologies in Korea

    International Nuclear Information System (INIS)

    Lee, Jang-Soo; Cho, Sung-Jin; Jung, Hae-Young; Lee, Ki-Bae; Seo, Yong-Chil

    2010-01-01

    In 2007 total waste generation rate in Korea was 318,670 ton,day. In general waste generation rate shows rising trend since 2000. Wastes are composed of municipal waste 14.9 % industrial waste 34.1 % and construction waste 51.0 %. Treatment of wastes by recycling was 81.1 % landfill 11.1 % incineration 5.3 % and ocean dumping 2.4 %. National waste energy policies have been influenced by various factors such as environmental problem economy technology level (could be made energy), and so on. Korea has the worlds third dense population density environmental pollution load per unit land area is the highest in OECD countries caused due to the fast development in economy, industrialization and urbanization in recent. Also, land area per person is just 2,072 m 2 . Landfill capacity reaches the upper limit, industrial waste generation is increasing. Searching new-renewable energy is vital to substitute fossil fuel considering its increasing price. Korea is the world's 10th biggest energy consuming country and 97% of energy depends on importing. Korea aims to increases supply of new-renewable energy by 5% until the 2011. In this study, we computed the amount of combustible waste from municipality generated by the multiple regression analysis. The existing technologies for converting waste to energy were surveyed and the technologies under development or utilizing in future were also investigated. Based on the technology utilization, the amount of energy using waste to energy technology could be estimated in future. (author)

  7. OPTION WEALTH AND BEQUEST VALUES: THE VALUE OF PROTECTING FUTURE GENERATIONS FROM THE HEALTH RISKS OF NUCLEAR WASTE STORAGE

    OpenAIRE

    Riddel, Mary C.; Shaw, W. Douglass

    2002-01-01

    We devise a simple model of intergenerational altruism under uncertainty. We present an estimable form of the model that relies on a few, plausible, assumptions. We apply the model to data collected in a survey of Southern Nevadans concerning the proposed Yucca Mountain Nuclear Waste Repository in Nye County, NV. We find strong evidence of a bequest motive. Approximately one third of the option wealth lost by households near the repository can be attributed to costs to future generations.

  8. Radioactive waste disposal programme 2008 of the waste-management-compelled bodies. Technical report 08-01

    International Nuclear Information System (INIS)

    2008-10-01

    Important steps in the management of radioactive waste have already been implemented in Switzerland and there is now wide experience in carrying out the associated activities. In terms of preparing for deep geological disposal, the necessary scientific and technical work is well advanced and the feasibility of implementing geological repositories that provide the required long-term safety has been successfully demonstrated for all wastes arising in Switzerland. Test feasibility demonstrations have also been approved by the Federal Council. Sufficient knowledge is available to allow the next steps in the selection of repository sites to be performed. The legal framework and organisational measures are also in place. The conceptual part of the Sectoral Plan for deep geological repositories regulates the details of the site selection process to be conducted over the next years. The origin, types and volumes of radioactive waste to be disposed of in Switzerland are known. The reference case assumes operation of the existing nuclear power plants for a period of 50 years and a collection period up to around 2050 for radioactive waste from medicine, industry and research. The types and volumes of radioactive waste that would arise in the case of extension of the operating lifetime of the existing power plants and the collection period for waste from medicine, industry and research by 10 years are included for planning purposes. Also considered are the wastes to be expected in the case of an additional production of 5 GW e for a period of 60 years. The resulting wastes are conditioned, characterised and inventoried on an ongoing basis. Before conditioning of a waste stream begins, the proposed conditioning procedure is evaluated by Nagra in terms of the suitability for disposal of the resulting waste packages. A model inventory of waste that will arise in the future has also been compiled. This provides a reliable basis for planning and implementing geological repositories

  9. Effectiveness of the live attenuated rotavirus vaccine produced by a domestic manufacturer in China studied using a population-based case-control design.

    Science.gov (United States)

    Zhen, Shan-Shan; Li, Yue; Wang, Song-Mei; Zhang, Xin-Jiang; Hao, Zhi-Yong; Chen, Ying; Wang, Dan; Zhang, Yan-Hong; Zhang, Zhi-Yong; Ma, Jing-Chen; Zhou, Peng; Zhang, Zhen; Jiang, Zhi-Wei; Zhao, Yu-Liang; Wang, Xuan-Yi

    2015-10-01

    A universal rotavirus (RV) immunization program is a potentially cost-effective measure for preventing RV infection in China. However, the efficacy of the only licensed RV vaccine (Lanzhou lamb rotavirus vaccine, LLR), which is made by a domestic manufacturer, has not been proven by a properly designed clinical trial. In October 2011 to March 2012, to measure the potential protection provided by LLR, a case-control study nested in a population-based active diarrhea surveillance study of children control study comparing non-RV viral diarrheal cases with non-diarrheal controls in the same population found that the RV vaccine offered no protection against non-RV diarrhea. Even under a less ideal immunization schedule, the oral LLR conferred a certain level of protection against RV gastroenteritis. However, further studies are needed to understand the full characteristics of the LLR, including its efficacy when administered following the optimal regimen, the potential risk of inducing intussusception, and the direct and indirect protective effects of LLR.

  10. Aspects of nuclear waste management

    International Nuclear Information System (INIS)

    Moberg, L.

    1990-10-01

    Six areas of concern in nuclear waste management have been dealt with in a four-year Nordic research programme. They include work in two international projects, Hydrocoin dealing with modelling of groundwater flow in crystalline rock, and Biomovs, concerned with biosphere models. Geologic questions of importance to the prediction of future behaviour are examined. Waste quantities from the decommissioning of nuclear power stations are estimated, and total amounts of waste to be transported in the Nordic countries are evaluated. Waste amounts from a hypothetical reactor accident are also calculated. (au)

  11. An interim report of the Subcommittee on Radioactive Waste Countermeasures: measures for radioactive waste treatment and disposal

    International Nuclear Information System (INIS)

    1984-01-01

    The Subcommittee on Radioactive Waste Countermeasures has studied on the measures for land disposal of low-level radioactive wastes and ultra-low-level radioactive wastes and the measures for treatment and disposal of high-level radioactive wastes and transuranium wastes. The results of studies so far are presented as an interim report. In disposal of low-level radioactive wastes, the land disposal is being required increasingly. The measures according to the levels of radioactivity are necessary. For the ultra-low-level radioactive wastes, their occurrence in large quantities is expected along with reactor decommissioning. In disposal of the high-level radioactive wastes, the present status is a transition toward the practical stages. Transuranium wastes should increase in their arising in the future. (Mori, K.)

  12. Spent fuel and waste inventories and projections

    International Nuclear Information System (INIS)

    Carter, W.L.; Finney, B.C.; Alexander, C.W.; Blomeke, J.O.; McNair, J.M.

    1980-08-01

    Current inventories of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled, based on judgments of the most reliable information available from Government sources and the open literature. Future waste generation rates and quantities to be accumulated over the remainder of this century are also presented, based on a present projection of US commercial nuclear power growth and expected defense-related activities. Spent fuel projections are based on the current DOE/EIA estimate of nuclear growth, which projects 180 GW(e) in the year 2000. It is recognized that the calculated spent fuel discharges are probably high in view of recent reactor cancellations; hence adjustments will be made in future updates of this report. Wastes considered, on a chapter-by-chapter basis, are: spent fuel, high-level wastes, transuranic wastes, low-level wastes, mill tailings (active sites), and remedial action wastes. The latter category includes mill tailings (inactive sites), surplus facilities, formerly utilized sites, and the Grand Junction Project. For each category, waste volume inventories and projections are given through the year 2000. The land usage requirements are given for storage/disposal of low-level and transuranic wastes, and for present inventories of mill tailings

  13. ERDA's long-term waste management goals and programs

    International Nuclear Information System (INIS)

    Perge, A.F.; Trice, V.G. Jr.; Walton, R.D. Jr.

    1976-01-01

    This paper presents an overview of the ERDA's major program for the long-term waste management of radioactive waste and provides a perspective for symposium participants with regard to the interrelationship of specific components of the program that are discussed in detail in other ERDA-sponsored papers. Needs, goals, and plans are reviewed for ERDA's management of the commercially generated wastes which are expected to be delivered to ERDA in accordance with Federal regulations. At present, ERDA responsibilities include long-term management of commercial-level wastes. Possible future regulations may give ERDA responsibility for the long-term management of commercial low-level solid wastes contaminated with transuranic nuclides. Primary planning goals and programs for the development of terminal storage facilities and waste processing technology to produce acceptable waste forms for long-term management are reviewed for each of the waste types identified above. The status of development programs for the long-term management of airborne radionuclides, which may be required at some time in the future, is also reviewed. (author)

  14. Low- and intermediate-level waste management practices in Canada

    International Nuclear Information System (INIS)

    Charlesworth, D.H.

    1982-05-01

    Low- and intermediate-level wastes arise in Canada from the operation of nuclear power stations, nuclear research establishments, nuclear fuel and radioisotope production facilities, as well as from many medical, research and industrial organizations. Essentially all of the solid radioactive wastas are stored in a retrievable fashion at five waste management areas from which a portion is expected to be transferred to future disposal facilities. Waste processing for volume reduction and stabilization is becoming an increasingly important part of low-level waste management because of the advantages it provides for both interim storage currently, and permanent disposal in the future

  15. Indian programme on radioactive waste management

    International Nuclear Information System (INIS)

    Wattal, P.K.

    2013-01-01

    The primary objective of radioactive waste management is protection of human health, environment and future generation. This article describes, briefly, the Indian programme on management of different radioactive wastes arising in the entire nuclear fuel cycle adhering to this objective. (author)

  16. WEB TECHNOLOGIES USED TO FORECAST FUTURE WASTE QUANTITIES

    Directory of Open Access Journals (Sweden)

    Valeriu LUPU

    2014-06-01

    Full Text Available In this article the authors propose a modality of prognosis of the quantities of waste generated in a certain period. The proposition was finalized by achieving a model of prognosis present on a site hosted by a Web server. The software solve the problem for the general case, depending on the input data after analysis. After analyzing input data sets are used with one, two or three components (trend, seasonality and residual variable. According to the input data the adjustment model regarding the description of the analyzed phenomenon (additive and multiplying is chosen. If the chronogram of the analyzed phenomenon indicates an oscillating evolution, of sinusoidal nature, the additive model (+ is chosen, otherwise the multiplying model (  is chosen. The seasonal component is estimated and the deseasonalized chronological series is determined. The seasonality is determined by: the procedure of arithmetical means, the procedure of moving averages and the procedure of analytical tendency. The adjustment function is specified regarding the tendency of the phenomenon and its parameters are estimated. The significance of the adjustment function is verified specifying the significance threshold with which it may be accepted as significant. The estimation of the parameters of the adjustment function is made on the basis of the application of the method of least squares. The values of the phenomenon on two or three trimesters/ months are estimated for the processed data (by using time series with two or three steps ahead. Several types of waste specified by the value of the meter for waste from the database may be accepted. The model proposed makes decisions and justifies if the data prognosticated is accepted or not. All information from the input data to the final data is stored in a MySQL database.

  17. NUCLEAR WASTE state-of-the-art reports 2004

    International Nuclear Information System (INIS)

    2004-01-01

    nuclear waste question and the future' is the third and last part. Here the question about long-term responsibility is discussed for the different choices we have to do in handling the nuclear wastes. The the first chapter, 'Transmutation - an alternative to waste disposal' treats the question about transmutation from a scenario perspective and questions the realism in this technology. The last chapter 'Nuclear waste, ethics and the responsibility for future generations' focuses on the question about our responsibility for future generations when it comes to different choices for nuclear waste handling. Here, the importance of different ethical attitudes for the decisions that we make is discussed - not only in the nuclear waste question. Thereby KASAM hopes to open a discussion in view of the decisions we have to take in the near future

  18. One Company's Waste, Another's Wealth

    Science.gov (United States)

    Hastings, Lana

    1977-01-01

    This article discusses the first U.S. exchange for industrial wastes. In its first year of operation, the exchange listed 115 waste materials for sale or wanted, some of which resulted in sales. In the future, the exchange may become a clearinghouse for recycling and polluction control technology information. (MA)

  19. Waste washing pre-treatment of municipal and special waste.

    Science.gov (United States)

    Cossu, Raffaello; Lai, Tiziana; Pivnenko, Kostyantyn

    2012-03-15

    Long-term pollution potential in landfills is mainly related to the quality of leachate. Waste can be conveniently treated prior to landfilling with an aim to minimizing future emissions. Washing of waste represents a feasible pre-treatment method focused on controlling the leachable fraction of residues and relevant impact. In this study, non-recyclable plastics originating from source segregation, mechanical-biological treated municipal solid waste (MSW), bottom ash from MSW incineration and automotive shredder residues (ASR) were treated and the removal efficiency of washing pre-treatment prior to landfilling was evaluated. Column tests were performed to simulate the behaviour of waste in landfill under aerobic and anaerobic conditions. The findings obtained revealed how waste washing treatment (WWT) allowed the leachability of contaminants from waste to be reduced. Removal rates exceeding 65% were obtained for dissolved organic carbon (DOC), chemical oxygen demand (COD) and Total Kjeldahl Nitrogen (TKN). A percentage decrease of approximately 60% was reached for the leachable fraction of chlorides, sulphates, fluoride and metals, as proved by a reduction in electric conductivity values (70%). Copyright © 2011 Elsevier B.V. All rights reserved.

  20. Nuclear waste disposal: two social criteria

    International Nuclear Information System (INIS)

    Rochlin, G.I.

    1977-01-01

    Two criteria--technical irreversibility and site multiplicity--have been suggested for use in establishing standards for the disposal of nuclear wastes. They have been constructed specifically to address the reduction of future risk in the face of inherent uncertainty concerning the social and political developments that might occur over the required periods of waste isolation, to provide for safe disposal without the requirement of a guaranteed future ability to recognize, detect, or repair errors and failures. Decisions as to how to apply or weigh these criteria in conjunction with other waste management goals must be made by societies and their governments. The purpose of this paper was not to preempt this process, but to construct a framework that facilitates consideration of the ethical and normative components of the problem of nuclear waste disposal. The minimum ethical obligation of a waste disposal plan is to examine most thoroughly the potential consequences of present actions, to acknowledge them openly, and to minimize the potential for irremediable harm. An ethically sound waste management policy must reflect not only our knowledge and skills, but our limitations as well

  1. Nuclear waste issue

    International Nuclear Information System (INIS)

    Ryhanen, V.

    2000-01-01

    A prerequisite for future use of nuclear energy in electricity production is safe management of the radioactive wastes generated by nuclear power industry. A number of facilities have been constructed for different stages of nuclear waste management around the world, for example for conditioning of different kind of process wastes and for intermediate storage of spent nuclear fuel. Difficulties have often been encountered particularly when trying to advance plans for final stage of waste management, which is permanent disposal in stable geological formations. The main problems have not been technical, but poor public acceptance and lack of necessary political decisions have delayed the progress in many countries. However, final disposal facilities are already in operation for low- and medium-level nuclear wastes. The most challenging task is the development of final disposal solutions for long-lived high-level wastes (spent fuel or high-level reprocessing waste). The implementation of deep geological repositories for these wastes requires persistent programmes for technology development, siting and safety assessments, as well as for building public confidence in long-term safety of the planned repositories. Now, a few countries are proceeding towards siting of these facilities, and the first high-level waste repositories are expected to be commissioned in the years 2010 - 2020. (author)

  2. Radioactive waste management the new French way: An approach to the future

    International Nuclear Information System (INIS)

    Allegre, M.

    1994-01-01

    France has a consistent nuclear energy policy. France must have a consistent nuclear waste policy, too. Andra, since last year a wholly-owned company of the state, is now resuming field work in for Departments (France is divided into 95 territorial administrative departments), all of which have unanimously voted in favor of hosting one of the two underground laboratories that Andra plans to create. This was a real success for Christian Bataille - the French mediator appointed by the government - who selected those four areas. In early January 1994, the French government gave Andra the green light, thus putting an end to the 1990 moratorium. Andra is starting a fifteen year, phased program established by the 1991 Waste Act. After the year 2006, a decision can be made on whether to convert one of the two laboratories into a real waste repository, subject to positive laboratory testing results. Stating that he is a newcomer to the club, the author also emphasizes some truths that should be spoken: showing for instance that men in charge of radioactive waste management must still improve their method of explaining the type of waste involved to the public

  3. Radiation-protection standards and waste management

    International Nuclear Information System (INIS)

    Rowe, W.D.

    1976-01-01

    This paper reviews some of the difficult questions to be addressed in the development of fundamental environmental criteria and standards for radioactive waste management. A short discussion is included of the need to develop more precise definitions of terminology, better conceptualization of long-term problems, and new concepts to express risks from waste management and to evaluate the ability of proposed technical alternatives to control such risks. EPA's plans to develop fundamental environmental criteria and generally applicable environmental radiation-protection standards for waste disposal are summarized. Finally, the principal projects in EPA's planned near-future programs are reviewed in the areas of high-level waste, transuranic solid waste, low-level waste, residual decommissioning waste, ocean disposal, and wastes containing natural radioactivity

  4. Low level waste disposal

    International Nuclear Information System (INIS)

    Barthoux, A.

    1985-01-01

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

  5. Charging for waste motivates generators to optimize waste control at the source

    International Nuclear Information System (INIS)

    Berry, J.B.; Homan, F.J.

    1988-01-01

    The Department of Energy (DOE) has recognized the need for waste management that incorporates improved waste-handling techniques and more stringent regulatory requirements to prevent future liabilities such as Superfund sites. DOE-Oak Ridge Operations (DOE-ORO) has recognized that an effective waste management program focuses on control at the source and that the burden for responsible waste management can be placed on generators by charging for waste management costs. The principle of including the waste management costs in the total cost of the product, even when the product is research and development, is being implemented at Oak Ridge National Laboratory (ORNL). Charging waste management costs to generators creates an incentive to optimize processes so that less waste is produced, and it provides a basis for determining the cost effectiveness of capital improvements so that the mature phase of waste management can be attained. Improving waste management practices requires a long-range commitment and consistent administration. Making this commitment and providing adequate funding for proper waste disposal are most cost-effective measures than the alternative of paying for remedial actions after improper disposal. This paper summarizes a plan to charge waste generators, the administrative structure of the plan, a comparison between the rate structure and changes in waste disposal operations, and issues that have surfaced as the plan is implemented

  6. Wastes from plutonium conversion and scrap recovery operations

    Energy Technology Data Exchange (ETDEWEB)

    Christensen, D.C.; Bowersox, D.F.; McKerley, B.J.; Nance, R.L.

    1988-03-01

    This report deals with the handling of defense-related wastes associated with plutonium processing. It first defines the different waste categories along with the techniques used to assess waste content. It then discusses the various treatment approaches used in recovering plutonium from scrap. Next, it addresses the various waste management approaches necessary to handle all wastes. Finally, there is a discussion of some future areas for processing with emphasis on waste reduction. 91 refs., 25 figs., 4 tabs.

  7. Wastes from plutonium conversion and scrap recovery operations

    International Nuclear Information System (INIS)

    Christensen, D.C.; Bowersox, D.F.; McKerley, B.J.; Nance, R.L.

    1988-03-01

    This report deals with the handling of defense-related wastes associated with plutonium processing. It first defines the different waste categories along with the techniques used to assess waste content. It then discusses the various treatment approaches used in recovering plutonium from scrap. Next, it addresses the various waste management approaches necessary to handle all wastes. Finally, there is a discussion of some future areas for processing with emphasis on waste reduction. 91 refs., 25 figs., 4 tabs

  8. United Kingdom government policy towards radioactive waste

    International Nuclear Information System (INIS)

    Pritchard, G.

    1986-01-01

    There are three areas of radioactive waste management which exemplify, beyond any reasonable doubt, that the United Kingdom has in the past (and intends in the future), to pursue a policy of dispersal and disposal of radioactive wastes: These are: (I) dumping of low-level waste in the deep ocean and, on a parallel, seabed emplacement of highly active waste; (II) the liquid discharges from Windscale into the Irish Sea; and (III) land dumping of low- and intermediate-level waste

  9. Mixed Waste Management Facility

    International Nuclear Information System (INIS)

    Brummond, W.; Celeste, J.; Steenhoven, J.

    1993-08-01

    The DOE has developed a National Mixed Waste Strategic Plan which calls for the construction of 2 to 9 mixed waste treatment centers in the Complex in the near future. LLNL is working to establish an integrated mixed waste technology development and demonstration system facility, the Mixed Waste Management Facility (MWMF), to support the DOE National Mixed Waste Strategic Plan. The MWMF will develop, demonstrate, test, and evaluate incinerator-alternatives which will comply with regulations governing the treatment and disposal of organic mixed wastes. LLNL will provide the DOE with engineering data for design and operation of new technologies which can be implemented in their mixed waste treatment centers. MWMF will operate under real production plant conditions and process samples of real LLNL mixed waste. In addition to the destruction of organic mixed wastes, the development and demonstration will include waste feed preparation, material transport systems, aqueous treatment, off-gas treatment, and final forms, thus making it an integrated ''cradle to grave'' demonstration. Technologies from offsite as well as LLNL's will be tested and evaluated when they are ready for a pilot scale demonstration, according to the needs of the DOE

  10. Understanding the role of waste prevention in local waste management: A literature review.

    Science.gov (United States)

    Zacho, Kristina O; Mosgaard, Mette A

    2016-10-01

    Local waste management has so far been characterised by end-of-pipe solutions, landfilling, incineration, and recycling. End-of-pipe solutions build on a different mind-set than life cycle-based approaches, and for this reason, local waste managers are reluctant to consider strategies for waste prevention. To accelerate the transition of waste and resource management towards a more integrated management, waste prevention needs to play a larger role in the local waste management. In this review article, we collect knowledge from the scientific community on waste prevention of relevance to local waste management. We analyse the trends in the waste prevention literature by organising the literature into four categories. The results indicate an increasing interest in waste prevention, but not much literature specifically concerns the integration of prevention into the local waste management. However, evidence from the literature can inform local waste management on the prevention potential; the environmental and social effects of prevention; how individuals in households can be motivated to reduce waste; and how the effects of prevention measures can be monitored. Nevertheless, knowledge is still lacking on local waste prevention, especially regarding the methods for monitoring and how local waste management systems can be designed to encourage waste reduction in the households. We end the article with recommendations for future research. The literature review can be useful for both practitioners in the waste sector and for academics seeking an overview of previous research on waste prevention. © The Author(s) 2016.

  11. Hanford Waste Transfer Planning and Control - 13465

    Energy Technology Data Exchange (ETDEWEB)

    Kirch, N.W.; Uytioco, E.M.; Jo, J. [Washington River Protection Solutions, LLC, Richland, Washington (United States)

    2013-07-01

    Hanford tank waste cleanup requires efficient use of double-shell tank space to support single-shell tank retrievals and future waste feed delivery to the Waste Treatment and Immobilization Plant (WTP). Every waste transfer, including single-shell tank retrievals and evaporator campaign, is evaluated via the Waste Transfer Compatibility Program for compliance with safety basis, environmental compliance, operational limits and controls to enhance future waste treatment. Mixed radioactive and hazardous wastes are stored at the Hanford Site on an interim basis until they can be treated, as necessary, for final disposal. Implementation of the Tank Farms Waste Transfer Compatibility Program helps to ensure continued safe and prudent storage and handling of these wastes within the Tank Farms Facility. The Tank Farms Waste Transfer Compatibility Program is a Safety Management Program that is a formal process for evaluating waste transfers and chemical additions through the preparation of documented Waste Compatibility Assessments (WCA). The primary purpose of the program is to ensure that sufficient controls are in place to prevent the formation of incompatible mixtures as the result of waste transfer operations. The program defines a consistent means of evaluating compliance with certain administrative controls, safety, operational, regulatory, and programmatic criteria and specifies considerations necessary to assess waste transfers and chemical additions. Current operations are most limited by staying within compliance with the safety basis controls to prevent flammable gas build up in the tank headspace. The depth of solids, the depth of supernatant, the total waste depth and the waste temperature are monitored and controlled to stay within the Compatibility Program rules. Also, transfer planning includes a preliminary evaluation against the Compatibility Program to assure that operating plans will comply with the Waste Transfer Compatibility Program. (authors)

  12. Waste biorefinery models towards sustainable circular bioeconomy: Critical review and future perspectives.

    Science.gov (United States)

    Venkata Mohan, S; Nikhil, G N; Chiranjeevi, P; Nagendranatha Reddy, C; Rohit, M V; Kumar, A Naresh; Sarkar, Omprakash

    2016-09-01

    Increased urbanization worldwide has resulted in a substantial increase in energy and material consumption as well as anthropogenic waste generation. The main source for our current needs is petroleum refinery, which have grave impact over energy-environment nexus. Therefore, production of bioenergy and biomaterials have significant potential to contribute and need to meet the ever increasing demand. In this perspective, a biorefinery concept visualizes negative-valued waste as a potential renewable feedstock. This review illustrates different bioprocess based technological models that will pave sustainable avenues for the development of biobased society. The proposed models hypothesize closed loop approach wherein waste is valorised through a cascade of various biotechnological processes addressing circular economy. Biorefinery offers a sustainable green option to utilize waste and to produce a gamut of marketable bioproducts and bioenergy on par to petro-chemical refinery. Copyright © 2016 Elsevier Ltd. All rights reserved.

  13. Radioactive waste management in Korea

    International Nuclear Information System (INIS)

    Lee, Ik Hwan

    1997-01-01

    In order to meet the increasing energy demand in Korea, continuous promotion of nuclear power program will be inevitable in the future. However, the use of nuclear energy eventually requires effective and reliable radioactive waste management. For the safe and economical management of radioactive waste, first of all, volume reduction is essentially required and hence the development of related technologies continuously be pursued. A site for overall radioactive waste management has to be secured in Korea. KEPCO-NETEC will improve public understanding by reinforcing PA and will maintain transparency of radioactive waste management. (author). 1 fig

  14. Time scales and the problem of radioactive waste

    International Nuclear Information System (INIS)

    Goble, R.L.

    1984-01-01

    The author argues that decisions about future nuclear development can be made essentially independent of waste management considerations for the next 20 years. His arguments are based on five propositions: 1 Risks and costs of storing spent fuel or high-level waste and transuranics are lower than other directly comparable risks and costs of operating a reactor. 2 Storage of mill tailings is the most serious long-term waste problem; it is not serious enough to rule out the use of nuclear power. 3 There are compelling reasons for beginning to implement a waste management program now. 4 It is important to separate the problem of providing temporary storage from that of finding permanent repositories. 5 A prudent waste management strategy, by 2000, will have identified and evaluated more than enough repository space for the waste generated by that time, independent of the decision made about nuclear futures. 13 references, 4 figures, 4 tables

  15. Waste management strategy for nuclear fusion power systems from a regulatory perspective

    Energy Technology Data Exchange (ETDEWEB)

    Heckman, R.A.

    1977-12-06

    A waste management strategy for future nuclear fusion power systems is developed using existing regulatory methodology. The first step is the development of a reference fuel cycle. Next, the waste streams from such a facility are identified. Then a waste management system is defined to safely handle and dispose of these wastes. The future regulator must identify the decisions necessary to establish waste management performance criteria. The data base and methodologies necessary to make these decisions must then be developed. Safe management of nuclear fusion wastes is not only a technological challenge, but encompasses significant social, political, and ethical questions as well.

  16. Waste management strategy for nuclear fusion power systems from a regulatory perspective

    International Nuclear Information System (INIS)

    Heckman, R.A.

    1977-01-01

    A waste management strategy for future nuclear fusion power systems is developed using existing regulatory methodology. The first step is the development of a reference fuel cycle. Next, the waste streams from such a facility are identified. Then a waste management system is defined to safely handle and dispose of these wastes. The future regulator must identify the decisions necessary to establish waste management performance criteria. The data base and methodologies necessary to make these decisions must then be developed. Safe management of nuclear fusion wastes is not only a technological challenge, but encompasses significant social, political, and ethical questions as well

  17. Rock solid: the geology of nuclear waste disposal

    International Nuclear Information System (INIS)

    Reid, Elspeth.

    1990-01-01

    With a number of nuclear submarines and power stations due to be decommissioned in the next decade, stores of radioactive waste, and arguments about storage increase. Whatever the direction taken by the nuclear industry in Britain, the legacy of waste remains for the foreseeable future. Geology is at the heart of the safety argument for nuclear wastes. It is claimed that rocks should act as the main safety barrier, protecting present and future generations from radiation. Rock Solid presents a clear, accessible and up to date account of the geological problems involved in building a nuclear waste repository. The author describes the geology of some of the possible UK repository sites (Sellafield, Dounreay, Altnabreac, Billingham), explains how sites are investigated (including computer models), and finally considers the crucial question: 'would geological containment of radioactive waste actually work?'. (author)

  18. Fiscal implications of a 1-mill/kWh waste management fee

    International Nuclear Information System (INIS)

    Engel, R.L.; White, M.K.

    1982-12-01

    The variations in parameters and uncertainties that can affect future waste management program costs are examined. Costs were estimated for both spent fuel and reprocessing waste disposal. Costs for repository site exploration and development, construction and operation of the first two repositories, and waste transportation of either spent fuel or reprocessing waste to the repository were included in the estimate of program costs. Costs for disposing of either spent fuel or reprocessing wastes in four generic geologic media (domed salt, bedded salt, tuff, and granite) were estimated considering uncertainties in package design waste preparation, mining cost, repository layout, repository startup date, and waste shipment distance. The range of these costs is then compared with estimated revenues from the proposed 1-mill/kWh fee to determine whether that fee would provide sufficient funds to meet waste management program needs. The estimated revenues and the range of program cost estimates in 1982 dollar resulting from these variations and uncertainties are shown graphically. The figure shows that the assumed 1-mill/kWh fee provides sufficient revenues to meet program costs for the range of conditions considered. Collection of a 1-mill/kWh fee at the time fuel is irradiated will result in the federal government precollecting for future waste management services. The relationship between funds accumulated to offset future waste management liabilities and the estimated cost of these liabilities will depend on the inflation rate and on the interest the federal government earns on the accumulated funds. If inflation continues, future fee adjustments will be required to assure that adequate funds are available to dispose of wastes when they are received

  19. Future directions for the US Nuclear Regulatory Commission's low-level waste management program

    International Nuclear Information System (INIS)

    Starmer, R.J.

    1986-01-01

    The Low-Level Radioactive Waste Policy Act envisioned that all states would be able to dispose of commercial low-level waste generated within their borders by 1986, either individually or through interstate compacts. Based on the current status of state and compact efforts, it is clear that no new disposal sites will be available by 1986 or for some period thereafter. In the short-term, there is uncertainty that the existing disposal sites will remain open after January 1, 1986, or if restrictions will apply after that time. If restrictions occur, storage, treatment or even curtailed generation may result for individual waste producers. Other uncertainties clouding implementation of the Policy Act include the final configuration of regional compacts - in the northeast in particular - clear assignment of responsibility for disposal of classes of waste, the method of disposal - shallow land burial or alternatives - that will be employed for low-level waste, and regulation of mixed wastes, wastes which have both radioactive and non-radioactive hazardous constituents. The NRC strategy for low-level waste management aims to resolve or reduce these uncertainties, and to encourage transition to a stable, national system based on timely state action. NRC will continue development of regulatory and technical guidance for disposal site licensing and build on its capabilities to address specific areas of state concern, such as alternatives to shallow land burial, and site characterization and modeling. NRC also plans to expand state and compact outreach efforts to help ensure that our technical work is properly focused. The authors will also be directly assisting those states and compacts on technical matters they confront in actual disposal site development and licensing

  20. E-waste: Environmental Problems and Current Management

    Directory of Open Access Journals (Sweden)

    D. Aktsoglou

    2010-01-01

    Full Text Available In this paper the environmental problems related with the discarded electronic appliances, known as e-waste, are reviewed.Moreover, the current and the future production of e-waste, the potential environmental problems associated with theirdisposal and management practices are discussed whereas the existing e-waste management schemes in Greece and othercountries (Japan, Switzerland are also quoted.

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

    Energy Technology Data Exchange (ETDEWEB)

    Nutt, M.; Nuclear Engineering Division

    2010-05-25

    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

  2. Strategic areas in radioactive waste management. The viewpoint and work orientations of the Nea radioactive waste management committee

    International Nuclear Information System (INIS)

    1999-01-01

    The NEA Radioactive Waste Management Committee (RWMC) is a forum of senior operators, regulators, policy makers, and senior representatives of R and D institutions in the field of radioactive waste management. The Committee assists Member countries by providing objective guidance on the solution of radioactive waste problems, and promotes Safety in the short- and long-term management of radioactive waste. This report identifies some of the major challenges currently faced by national waste management programmes, and describes the strategic areas in which the RWMC should focus its efforts in future years. (author)

  3. Uranium mine tailings and obligations to future generations

    International Nuclear Information System (INIS)

    Brook, A.

    1980-01-01

    Low-level wastes from uranium mine/mill operations, because of their huge volume, are a serious problem, yet relatively little attention has been paid to them. Management of tailings piles and waste liquids in the short term is fairly effective. However these management techniques involve continuous, active treatment of the wastes, which may not continue after operations shut down, and rely on containment structures with a short effective life. Tailings can probably be rendered safe for future generations if sufficient resources are devoted to the task. The central moral question is whether we are obligated to assume the costs of tailings management, or whether it is permissible to pass them on to future generations. The basic moral principle that each person has the same value as any other implies that the generation that reaps the benefits of nuclear power must assume the costs of managing mine tailings and not discriminate in favour of one group of persons, our own generation. The argument that people who may exist in the future have intrinsically less value than people currently alive is not accepted by the author. The methodology for determining obligations to future generations which has been applied to mine/mill wastes could be applied to other nuclear issues, too. (LL)

  4. Waste management

    International Nuclear Information System (INIS)

    Dworschak, H.; Mannone, F.; Rocco, P.

    1995-01-01

    The presence of tritium in tritium-burning devices to be built for large scale research on thermonuclear fusion poses many problems especially in terms of occupational and environmental safety. One of these problems derives from the production of tritiated wastes in gaseous, liquid and solid forms. All these wastes need to be adequately processed and conditioned to minimize tritium releases to an acceptably low occupational and environmental level and consequently to protect workers and the public against the risks of unacceptable doses from exposure to tritium. Since all experimental thermonuclear fusion devices of the Tokomak type to be built and operated in the near future as well as all experimental activities undertaken in tritium laboratories like ETHEL will generate tritiated wastes, current strategies and practices to be applied for the routine management of these wastes need to be defined. Adequate background information is provided through an exhaustive literature survey. In this frame alternative tritiated waste management options so far investigated or currently applied to this end in Europe, USA and Canada have been assessed. The relevance of tritium in waste containing gamma-emitters, originated by the neutron activation of structural materials is assessed in relation to potential final disposal options. Particular importance has been attached to the tritium retention efficiency achievable by the various waste immobilization options. 19 refs., 2 figs., 1 tab

  5. Liquid secondary waste: Waste form formulation and qualification

    Energy Technology Data Exchange (ETDEWEB)

    Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hill, K. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nichols, R. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-07-31

    and water characteristic curves) were comparable to the properties measured on the Savannah River Site (SRS) Saltstone waste form. Future testing should include efforts to first; 1) determine the rate and amount of ammonia released during each unit operation of the treatment process to determine if additional ammonia management is required, then; 2) reduce the ammonia content of the ETF concentrated brine prior to solidification, making the waste more amenable to grouting, or 3) manage the release of ammonia during production and ongoing release during storage of the waste form, or 4) develop a lower pH process/waste form thereby precluding ammonia release.

  6. The future since Chernobyl

    International Nuclear Information System (INIS)

    Warnock, Mary.

    1986-01-01

    The author reviews three books about energy policy, particularly in relation to nuclear energy. From these, which were all published before the Chernobyl disaster, the reviewer identifies two main problems relating to nuclear energy - immediate safety and disposal of nuclear waste. Risk analysis is seen as unhelpful in allaying public fears as it is the nature of the risk of nuclear accidents, rather than its numerical probability, that is frightening. A paper on the assessment of Best Practical Environmental Options (BPEO) for management of low and intermediate-level solid radioactive waste, is referred to when commenting on nuclear waste disposal. Ordinary people have two political obligations with respect to nuclear energy - first to demand knowledge and examine further reassuring information. Risks taken will then be taken with proper information obtained first. Secondly, to look beyond the short-term consequences of a nuclear programme. To fulfill these obligations policy-makers have to be educated to be open and honest about the nuclear future and to be seen to be looking further ahead than the immediate future. (U.K.)

  7. Interim Hanford Waste Management Technology Plan

    International Nuclear Information System (INIS)

    1985-09-01

    The Interim Hanford Waste Management Technology Plan (HWMTP) is a companion document to the Interim Hanford Waste Management Plan (HWMP). A reference plan for management and disposal of all existing and certain projected future radioactive Hanford Site Defense Wastes (HSDW) is described and discussed in the HWMP. Implementation of the reference plan requires that various open technical issues be satisfactorily resolved. The principal purpose of the HWMTP is to present detailed descriptions of the technology which must be developed to close each of the technical issues associated with the reference plan identified in the HWMP. If alternative plans are followed, however, technology development efforts including costs and schedules must be changed accordingly. Technical issues addressed in the HWMTP and HWMP are those which relate to disposal of single-shell tank wastes, contaminated soil sites, solid waste burial sites, double-shell tank wastes, encapsulated 137 CsCl and 90 SrF 2 , stored and new solid transuranic (TRU) wastes, and miscellaneous wastes such as contaminated sodium metal. Among the high priority issues to be resolved are characterization of various wastes including early determination of the TRU content of future cladding removal wastes; completion of development of vitrification (Hanford Waste Vitrification Plant) and grout technology; control of subsidence in buried waste sites; and development of criteria and standards including performance assessments of systems proposed for disposal of HSDW. Estimates of the technology costs shown in this report are made on the basis that all identified tasks for all issues associated with the reference disposal plan must be performed. Elimination of, consolidation of, or reduction in the scope of individual tasks will, of course, be reflected in corresponding reduction of overall technology costs

  8. Report: future industrial solid waste management in pars Special Economic Energy Zone (PSEEZ), Iran.

    Science.gov (United States)

    Mokhtarani, Babak; Moghaddam, Mohammad Reza Alavi; Mokhtarani, Nader; Khaledi, Hossein Jomeh

    2006-06-01

    The Pars Special Economic Energy Zone (PSEEZ) is located in the south of Iran, on the northern coastline of the Persian Gulf. This area was established in 1998 for the utilization of south Pars field oil and gas resources. This field is one of the largest gas resources in the world and contains about 6% of the total fossil fuels known. Petrochemical industries, gas refineries and downstream industries are being constructed in this area. At present there are three gas refineries in operation and five more gas refineries are under construction. In this study, different types of solid waste including municipal solid waste (MSW) and industrial wastes were investigated separately. The aim of the study was to focus on the management of the industrial wastes in order to minimize the environmental impact. In the first stage, the types and amounts of industrial waste in PSEEZ were evaluated by an inventory. The main types of industrial waste are oil products (fuel oil, light oil, lubricating oil), spent catalysts, adsorbents, resins, coke, wax and packaging materials. The waste management of PSEEZ is quite complex because of the different types of industry and the diversity of industrial residues. In some cases recycling/reuse of waste is the best option, but treatment and disposal are also necessary tools. Recently a design has been prepared for a disposal site in PSEEZ for the industrial waste that cannot be reused or recycled. The total surface area of this disposal site where the industrial waste should be tipped for the next 20 years was estimated to be about 42 000 m2.

  9. Issues and Experiences on Radioactive Waste Quality Control / Quality Assurance with Regard to Future Disposal

    International Nuclear Information System (INIS)

    Beckmerhagen, I.; Brennecke, P.; Steyer, S.; Bandt, G.

    2006-01-01

    In the Federal Republic of Germany all types of radioactive waste (short-lived, long-lived) are to be disposed of in deep geological formations. Thus, the safe management of radioactive waste presupposes an appropriate conditioning of primary waste-to-waste packages suitable for emplacement in a repository as well as the documentation of pre-treatment, processing and packaging steps and the waste package characteristics being relevant for disposal. Due to the operation, decommissioning and dismantling of nuclear facilities as well as the application of radioisotopes in industry, medicine and research and development radioactive waste continuously arises in Germany. In order to manage this waste different measures and procedures regarding its conditioning and quality control/quality assurance were introduced and since many years successfully applied. Waste conditioning is especially characterized by a flexible application of the Konrad waste acceptance requirements. The rationale for this approach is due to the present non-availability of a repository in Germany. Several examples of a 'tailor-made' application of the waste acceptance requirements in treatment, conditioning and documentation processes as well as the quality assurance/quality control processes illustrate the current German approach. (authors)

  10. A brief analysis and description of transuranic wastes in the subsurface disposal area of the radioactive waste management complex at INEL

    International Nuclear Information System (INIS)

    Arrenholz, D.A.; Knight, J.L.

    1991-02-01

    This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area during the period 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and special-case wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and makes recommendations for future efforts at waste characterization. 20 refs., 3 figs., 17 tabs

  11. Analysis of the Institutional Framework For Radioactive Waste Management in Indonesia

    Directory of Open Access Journals (Sweden)

    D.S. Wisnubroto

    2009-07-01

    Full Text Available The analysis of the infrastructure for radioactive waste management in Indonesia has been studied using several parameters, i.e. policy, regulatory authorities and their regulations, implementing organizations and financial system. By considering the international trends and the Indonesian program to utilize nuclear power, the infrastructure of radioactive waste management needs to be improved. The Act No. 10/1997 on Nuclear Energy for the future beneficence will have to be amended to incorporate several missing key points on waste management, such as definition of radioactive waste, disposal of Low and Intermediate Level Waste (LILW, and classification of waste. Full involvement of some important stakeholders, especially the State Ministry of Environment, on the radioactive waste management infrastructure is required since some radioactive waste is generated from non nuclear waste. Assigning full authority to the State Ministry of Environment for regulating radioactive waste generated by non nuclear facilities may be more effective, whereas BAPETEN is still holding onto control over the waste generated from nuclear facilities. In the near future, several regulations on clearance level, classification of waste, NORM/TENORM, and financial system are expected to be set up for urgent need. By considering the high risk for handling of radioactivity, including for transportation and storage, the liability or assurance of the safety for such activities must be accounted for. Finally, establishment of financial system for long term waste management in Indonesia needs to be implemented to ensure that the radioactive waste will not be the burden on future generations.

  12. Analysis of the Institutional Framework For Radioactive Waste Management in Indonesia

    International Nuclear Information System (INIS)

    Wisnubroto, D.S.

    2009-01-01

    The analysis of the infrastructure for radioactive waste management in Indonesia has been studied using several parameters, i.e. policy, regulatory authorities and their regulations, implementing organizations and financial system. By considering the international trends and the Indonesian program to utilize nuclear power, the infrastructure of radioactive waste management needs to be improved. The Act No. 10/1997 on Nuclear Energy for the future beneficence will have to be amended to incorporate several missing key points on waste management, such as definition of radioactive waste, disposal of Low and Intermediate Level Waste (LILW), and classification of waste. Full involvement of some important stakeholders, especially the State Ministry of Environment, on the radioactive waste management infrastructure is required since some radioactive waste is generated from non nuclear waste. Assigning full authority to the State Ministry of Environment for regulating radioactive waste generated by non nuclear facilities may be more effective, whereas BAPETEN is still holding onto control over the waste generated from nuclear facilities. In the near future, several regulations on clearance level, classification of waste, NORM/TENORM, and financial system are expected to be set up for urgent need. By considering the high risk for handling of radioactivity, including for transportation and storage, the liability or assurance of the safety for such activities must be accounted for. Finally, establishment of financial system for long term waste management in Indonesia needs to be implemented to ensure that the radioactive waste will not be the burden on future generations (author)

  13. Low-level radioactive wastes managements in universities, institutes and hospitals

    International Nuclear Information System (INIS)

    Kato, Sadatake

    1979-01-01

    Japan Radioisotope Association, which is distributing radioisotopes, also is collecting radioactive wastes from hospitals and other establishments using radioisotopes across the country. These wastes are then transferred to Japan Atomic Energy Research Institute for treatment. However, the capacity of JAERI is currently insufficient for the quantities transferred from JRA. A main cause for such difficulty as above is the increase in medical isotopes, i.e. radiopharmaceuticals, which are used in vivo and in vitro. From the RI consumptions thus far, the future demands and waste quantities are estimated for the purpose of establishing an overall joint treatment system. The following matters are described; the present situation of waste management in JRA and JAERI; current transitional phase; and radiopharmaceutical wastes (radiopharmaceuticals, their consumptions and future demands, and resultant waste RIs). (J.P.N.)

  14. Prediction of radionuclide inventory for the low-and intermediated-level radioactive waste disposal facility the radioactive waste classification

    International Nuclear Information System (INIS)

    Jung, Kang Il; Jeong, Noh Gyeom; Moon, Young Pyo; Jeong, Mi Seon; Park, Jin Beak

    2016-01-01

    To meet nuclear regulatory requirements, more than 95% individual radionuclides in the low- and intermediate-level radioactive waste inventory have to be identified. In this study, the radionuclide inventory has been estimated by taking the long-term radioactive waste generation, the development plan of disposal facility, and the new radioactive waste classification into account. The state of radioactive waste cumulated from 2014 was analyzed for various radioactive sources and future prospects for predicting the long-term radioactive waste generation. The predicted radionuclide inventory results are expected to contribute to secure the development of waste disposal facility and to deploy the safety case for its long-term safety assessment

  15. In-situ thermeolectric stabilization of radioactive wastes

    International Nuclear Information System (INIS)

    Brouns, R.A.; Timmerman, C.L.

    1982-01-01

    Current analysis indicates that in situ vitrification is applicable to many wastes and soil types at a cost an order of magnitude less than exhumation, processing, and transportation to a deep geological disposal site. Once the waste materials have been solidified, future ground subsidence, wind erosion and plant or animal intrusion are virtually eliminated. Furthermore, the waste form is extremely durable

  16. A brief analysis and description of transuranic wastes in the Subsurface Disposal Area of the radioactive waste management complex at INEL

    International Nuclear Information System (INIS)

    Arrenholz, D.A.; Knight, J.L.

    1991-08-01

    This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area of the radioactive waste management complex at Idaho National Engineering Laboratory from 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and atypical wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and make recommendations for future efforts at waste characterization. 19 refs., 3 figs., 17 tabs

  17. A brief analysis and description of transuranic wastes in the Subsurface Disposal Area of the radioactive waste management complex at INEL

    Energy Technology Data Exchange (ETDEWEB)

    Arrenholz, D.A.; Knight, J.L.

    1991-08-01

    This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area of the radioactive waste management complex at Idaho National Engineering Laboratory from 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and atypical wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and make recommendations for future efforts at waste characterization. 19 refs., 3 figs., 17 tabs.

  18. The view of the geotechnical engineering on the radioactive waste disposal

    International Nuclear Information System (INIS)

    Komada, Hiroya

    2004-01-01

    The state of radioactive waste disposal produced by the nuclear fuel cycle facilities and the future problems of geotechnical engineering are stated. Concept of classification of radioactive waste and their disposal, the present state of operating waste and TRU waste in the low level radioactive waste and the high level radioactive waste are explained. On the future problems, evaluation of ground water flow, long period estimation of natural phenomena, mixed earth with bentonite as a buffer and cement materials are discussed. The geological disposal of radioactive waste, which kept them at more than 200 m underground, has two important different points from the general geotechnical engineering such as a system covered inhomogeneous large space of natural geological features and very long time (some million year) considered. (S.Y.)

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

    International Nuclear Information System (INIS)

    1997-05-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type. This information includes the cumulative impacts of combining future siting configurations for the five waste types and the collective impacts of other past, present, and reasonably foreseeable future activities. The selected waste management facilities being considered for these different waste types are treatment and disposal facilities for low-level mixed waste; treatment and disposal facilities for low-level waste; treatment and storage facilities for transuranic waste in the event that treatment is required before disposal; storage facilities for treated (vitrified) high-level waste canisters; and treatment of nonwastewater hazardous waste by DOE and commercial vendors. In addition to the no action alternative, which includes only existing or approved waste management facilities, the alternatives for each of the waste type configurations include decentralized, regionalized, and centralized alternatives for using existing and operating new waste management facilities. However, the siting, construction and operations of any new facility at a selected site will not be decided until completion of a sitewide or project-specific environmental impact review

  20. Technologies to remediate hazardous waste sites

    International Nuclear Information System (INIS)

    Falco, J.W.

    1990-03-01

    Technologies to remediate hazardous wastes must be matched with the properties of the hazardous materials to be treated, the environment in which the wastes are imbedded, and the desired extent of remediation. Many promising technologies are being developed, including biological treatment, immobilization techniques, and in situ methods. Many of these new technologies are being applied to remediate sites. The management and disposal of hazardous wastes is changing because of federal and state legislation as well as public concern. Future waste management systems will emphasize the substitution of alternatives for the use of hazardous materials and process waste recycling. Onsite treatment will also become more frequently adopted. 5 refs., 7 figs

  1. Radioactive waste management practices in India

    International Nuclear Information System (INIS)

    Raj, Kanwar

    2012-01-01

    Different countries around the globe, especially those involved in nuclear power plant operation, spent fuel reprocessing, nuclear research activities and diverse nuclear applications; generate large inventory of radioactive wastes. These waste streams generated during various stages of nuclear fuel cycle are of different categories, which require special care for handling, treatment and conditioning. Conventional treatment and conditioning methods may not be efficient for various type of waste; therefore special options may be required to manage these waste streams. Presently, Indian waste management fraternity is focused to minimize the volume of the waste to be finally disposed off, by partitioning radionuclides, regenerating separation media and re-using as much of the waste components as possible and economically feasible. This approach, together with the reuse/recycling strategy, seems to represent a robust waste treatment strategy for the future

  2. Charging generators for waste management costs

    International Nuclear Information System (INIS)

    Berry, J.B.; Homan, F.J.

    1988-01-01

    The Department of Energy (DOE) has recognized the need for waste management that incorporates improved waste-handling techniques and more stringent regulatory requirements to prevent future liabilities such as Superfund sites. DOE-Oak Ridge Operations (DOE-ORO) has recognized that an effective waste management program focuses on control at the source and that the burden for responsible waste management can be placed on generators by charging for waste management costs. The principle of including the waste management costs in the total cost of the product, even when the product is research and development, is being implemented at Oak Ridge National Laboratory (ORNL). This paper summarizes a plan to charge waste generators, the administrative structure of the plan, a comparison between the rate structure and changes in waste disposal operations, and issues that have surfaced as the plan is implemented

  3. Descriptive catalogue of radioactive waste families

    International Nuclear Information System (INIS)

    2004-01-01

    This document describes the different types of radioactive wastes produced in France or which are expected to be produced in the future. The wastes have been shared into different families having similar characteristics. A description is made for each family: general presentation, photos, position of the family in the French classification, industrial origin, status of production. Some informations about the raw waste and its conditioning process are also given. The qualitative description is completed by some numerical data like: the quantity produced in the past and to be produced in the future, the evaluation of the radioactivity in 2002 and 2020, and the evaluation of the thermal power when it exists. Finally, some informations are given about the risk of toxicity of some chemical species or compounds. (J.S.)

  4. Transportation of radioactive wastes from nuclear fuel cycles

    International Nuclear Information System (INIS)

    1979-09-01

    This paper discusses current and foreseen radioactive waste transportation systems as they apply to the INFCE Working Group 7 study. The types of wastes considered include spent fuel, which is treated as a waste in once-through fuel cycles; high-, medium-, and low-level waste; and gaseous waste. Regulatory classification of waste quantities and containers applicable to these classifications are discussed. Radioactive wastes are presently being transported in a safe and satisfactory manner. None of the INFCE candidate fuel cycles pose any extraordinary problems to future radioactive waste transportation and such transportation will not constitute a decisive factor in the choice of a preferred fuel cycle

  5. Integrated water and waste management system for future spacecraft

    Science.gov (United States)

    Ingelfinger, A. L.; Murray, R. W.

    1974-01-01

    Over 200 days of continuous testing have been completed on an integrated waste management-water recovery system developed by General Electric under a jointly funded AEC/NASA/AF Contract. The 4 man system provides urine, feces, and trash collection; water reclamation; storage, heating and dispensing of the water; storage and disposal of the feces and urine residue and all of other nonmetallic waste material by incineration. The heat required for the 1200 deg F purification processes is provided by a single 420-w radioisotope heater. A second 836-w radioisotope heater supplemented by 720 w of electrical heat provides for distillation and water heating. Significant test results are no pre-or-post treatment, greater than 98 per cent potable water recovery, approximately 95 per cent reduction in solids weight and volume, all outflows are sterile with the water having no bacteria or virus, and the radioisotope capsule radiation level is only 7.9 mrem/hr unshielded at 1 m (neutrons and gamma).

  6. Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2001-12-01

    The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities: Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular Development of the short and long-term safety analysis of the Baldone repository, including: the planned increasing of capacity for disposal and long term storage, the radiological analysis for the post-closure period Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components Proposal of recommendations for future updating of radioactive waste acceptance criteria Proposal of recommendations for safety upgrades to the facility. The work programme has been developed in phases and main tasks as follows. Phase 0: Project inception, Phase 1: Establishment of current status, plans and practices (Legislation, regulation and standards, Radioactive waste management, Waste acceptance criteria), Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements. The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterization requirements), the design of an engineered cap and strategies for capping. (author)

  7. Managing America`s solid waste

    Energy Technology Data Exchange (ETDEWEB)

    1998-03-02

    This report presents an historical overview of the federal role in municipal solid waste management from 1965 to approximately 1995. Attention is focuses on the federal role in safeguarding public health, protecting the environment, and wisely using material and energy resources. It is hoped that this report will provide important background for future municipal solid waste research and development initiatives.

  8. The 1985 United Kingdom radioactive waste inventory

    International Nuclear Information System (INIS)

    Fletcher, A.M.; Wear, F.J.; Haselden, H.; Shepherd, J.; Tymons, B.J.

    1986-07-01

    This report provides a compilation of stocks of radioactive wastes in the UK by volume, as at 1 January 1985, and estimates of future arisings to the year 2030. It includes radionuclide contents as available, together with specific activities, notional conditioning factors and disposal routes. In the main the stock volumes are given as unconditioned waste. However for clarity and precision some of the data relates to treated wastes (ie compacted wastes, incinerator ash, etc). These are clearly marked in the Tables. (author)

  9. Technological progress in the management of radioactive waste

    International Nuclear Information System (INIS)

    Proost, J.; Frognet, J.P.

    1980-01-01

    The expansion of industrial nuclear activities gives rise to increasing amounts of radioactive waste. In addition criticisms on nuclear energy are being focused on the management of radioactive waste. In this context the Commission of European Communities has set up major 'indirect' programmes for the promotion, financial support and coordination of various R and D activities for the period 1975-1979. For the definition of its future policies in this field, it is interesting to evaluate the state of the art and the impact of present and future development work. The study should help in selecting those areas where further research is necessary and in defining priorities for developing new waste disposal techniques. The present report, gives a review of the present situation in Europe. It covers: - general considerations on waste management and policies adopted or proposed in various countries; - major sources of radioactive waste with detailed analysis of the quantities and types of waste generated by reference facilities for the LWR fuel cycle; - evaluation of the techniques as applied at present on an industrial scale in Europe at reactor plants or waste handling centres

  10. STORAGE AND RECOVERY OF SECONDARY WASTE COMING FROM MUNICIPAL WASTE INCINERATION PLANTS IN UNDERGROUND MINE

    Directory of Open Access Journals (Sweden)

    Waldemar Korzeniowski

    2016-09-01

    Full Text Available Regarding current and planned development of municipal waste incineration plants in Poland there is an important problem of the generated secondary waste management. The experience of West European countries in mining shows that waste can be stored successfully in the underground mines, but especially in salt mines. In Poland there is a possibility to set up the underground storage facility in the Salt Mine “Kłodawa”. The mine today is capable to locate over 3 million cubic meters and in the future it can increase significantly. Two techniques are proposed: 1 – storage of packaged waste, 2 – waste recovery as selfsolidifying paste with mining technology for rooms backfilling. Assuming the processing capacity of the storage facility as 100 000 Mg of waste per year, “Kłodawa” mine will be able to accept around 25 % of currently generated waste coming from the municipal waste incineration plants and the current volume of the storage space is sufficient for more than 20 years. Underground storage and waste recovery in mining techniques are beneficial for the economy and environment.

  11. Maintenance of records for radioactive waste disposal

    International Nuclear Information System (INIS)

    1999-07-01

    The safety of the radioactive waste disposal concepts does not rely on long term institutional arrangements. However, future generations may need information related to repositories and the wastes confined in them. The potentially needed information therefore has to be identified and collected. A suitable system for the preservation of that information needs to be created as a part of the disposal concept beginning with the planning phase. The IAEA has prepared this technical report to respond to the needs of Member States having repositories or involved in or considering the development of repositories. In many countries policies and systems for record keeping and maintenance of information related to disposal are the subjects of current interest. This report describes the requirements for presenting information about repositories for radioactive waste including long lived and transuranic waste and spent fuel if it is declared as a waste. The report discussed topics of identification, transfer and long term retention of high level information pertaining to the repository in a records management system (RMS) for retrieval if it becomes necessary in the future

  12. Hanford's self-assessment of the solid waste forecast process

    International Nuclear Information System (INIS)

    Hauth, J.; Skumanich, M.; Morgan, J.

    1996-01-01

    In fiscal year (FY) 1995 the forecast process used at Hanford to project future solid waste volumes was evaluated. Data on current and future solid waste generation are used by Hanford site planners to determine near-term and long-term planning needs. Generators who plan to ship their waste to Hanford's Solid Waste Program for treatment, storage, and disposal provide volume information on the types of waste that could be potentially generated, waste characteristics, and container types. Generators also provide limited radionuclide data and supporting assumptions. A self-assessment of the forecast process identified many effective working elements, including a well-established and systematic process for data collection, analysis and reporting; sufficient resources to obtain the necessary information; and dedicated support and analytic staff. Several areas for improvement were identified, including the need to improve confidence in the forecast data, integrate forecast data with other site-level and national data calls, enhance the electronic data collection system, and streamline the forecast process

  13. 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

  14. Issues in the management of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Ashbrook, A.W.

    1984-01-01

    All industry finds itself today enmeshed in a morass of regulation, political apathy and public antagonism when it comes to hazardous industrial waste. Our industry is a world-class leader on all three fronts. There are no disposal facilities in Canada for radioactive wastes and the prognosis for the future is bleak. As the industry gets older, more and more facilities will be closed and require decommissioning. New facilities require plans for the long-term management of their wastes. Indeed, one major public issue with the nuclear industry is the fate of the wastes produced. In looking at the situation in which we find ourselves today with respect to the long-term management of naturally-occurring low-level radioactive wastes, one must wonder where we are going in the future, and whether indeed is an end in sight

  15. Final disposal of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Kroebel, R [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Wiederaufarbeitung und Abfallbehandlung; Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Abt. zur Behandlung Radioaktiver Abfaelle

    1978-08-01

    This paper discusses the final disposal possibilities for radioactive wastes in the Federal Republic of Germany and the related questions of waste conditioning, storage methods and safety. The programs in progress in neighbouring CEC countries and in the USA are also mentioned briefly. The autors conclude that the existing final disposal possibilities are sufficiently well known and safe, but that they could be improved still further by future development work. The residual hazard potential of radioactive wastes from fuel reprocessing after about 1000 years of storage is lower that of known inorganic core deposits.

  16. Radioactive waste programme in Latvia

    International Nuclear Information System (INIS)

    Salmins, A.

    2000-01-01

    An overview is made on the use of radioactive sources and waste management in Latvia. Brief overview of the development of national legal documents - the framework law of environmental protection; international agreements; the new law on radiation safety and nuclear safety; regulation of the Cabinet of Ministers - is given. The regulatory infrastructure in the nearest future is outlined. The institutional framework for radioactive waste management is described. Basic design of the repository and radioactive waste inventory are also given. The activities on the EU DG Environment project CASIOPEE are reported

  17. Management of Radioactive Wastes

    International Nuclear Information System (INIS)

    Tchokosa, P.

    2010-01-01

    Management of Radioactive Wastes is to protect workers and the public from the radiological risk associated with radioactive waste for the present and future. It application of the principles to the management of waste generated in a radioisotope uses in the industry. Any material that contains or is contaminated with radionuclides at concentrations or radioactivity levels greater than ‘exempt quantities’ established by the competent regulatory authorities and for which no further use is foreseen or intended. Origin of the Radioactive Waste includes Uranium and Thorium mining and milling, nuclear fuel cycle operations, Operation of Nuclear power station, Decontamination and decommissioning of nuclear facilities and Institutional uses of isotopes. There are types of radioactive waste: Low-level Waste (LLW) and High-level Waste. The Management Options for Radioactive Waste Depends on Form, Activity, Concentration and half-lives of the radioactive waste, Storage and disposal methods will vary according to the following; the radionuclides present, and their concentration, and radio toxicity. The contamination results basically from: Contact between radioactive materials and any surface especially during handling. And it may occur in the solid, liquid or gas state. Decontamination is any process that will either reduce or completely remove the amount of radionuclides from a contaminated surface

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

    International Nuclear Information System (INIS)

    1997-01-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear energy research and the development, production, and testing of nuclear weapons at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives, which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type. This information includes the cumulative impacts of combining future siting configurations for the five waste types and the collective impacts of other past, present, and reasonably foreseeable future activities. The selected waste management facilities being considered for these different waste types are treatment and disposal facilities for low-level mixed waste; treatment and disposal facilities for low-level waste; treatment and storage facilities for transuranic waste in the event that treatment is required before disposal; storage facilities for created (vitrified) high-level waste canisters; and treatment of nonwastewater hazardous waste by DOE and commercial vendors. In addition to the No Action Alternative, which includes only existing of approved waste management facilities, the alternatives for each of the waste-type configurations include Decentralized, Regionalized, and Centralized Alternatives for using existing and operating new waste management facilities. However, the siting, construction, and operations of any new facility at a selected site will not be decided until completion of a sitewide or project-specific environmental impact review

  19. Proceedings of waste stream minimization and utilization innovative concepts: An experimental technology exchange. Volume 1, Industrial solid waste processing municipal waste reduction/recycling

    Energy Technology Data Exchange (ETDEWEB)

    Lee, V.E. [ed.; Watts, R.L.

    1993-04-01

    This two-volume proceedings summarizes the results of fifteen innovations that were funded through the US Department of Energy`s Innovative Concept Program. The fifteen innovations were presented at the sixth Innovative Concepts Fair, held in Austin, Texas, on April 22--23, 1993. The concepts in this year`s fair address innovations that can substantially reduce or use waste streams. Each paper describes the need for the proposed concept, the concept being proposed, and the concept`s economics and market potential, key experimental results, and future development needs. The papers are divided into two volumes: Volume 1 addresses innovations for industrial solid waste processing and municipal waste reduction/recycling, and Volume 2 addresses industrial liquid waste processing and industrial gaseous waste processing. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  20. Municipal waste - management and treatment

    International Nuclear Information System (INIS)

    Paudel, E.S.R.

    2005-01-01

    Though per capita waste generation in Nepalese urban cities is not so high, the lack of proper waste management is considered one of the severe problems to be faced by urban people in future. With rapid urbanization, life style of people is changing their habits and consuming more materials and producing a large volume of waste in urban areas in Nepal. The nature and amount of waste generated in municipality is dependent of demography and geography. But most common aspect of municipal waste in Nepal is more than 60% of the waste biodegradable. Whatever the nature and amount of waste generated, the most common practice of managing municipal waste is to dispose in the riverside nearby or dumped elsewhere. The involvement of private sector in waste management is a new concept adopted by many municipalities in Nepal. One of the most progress approaches, 4R (reduces, reuse, recycle and refuse) principle is being practiced. The need of awareness progressive like segregation of wastes at collection point also being practiced in Nepal. Finally, Proper formulation of program and legislation and its application is one of the major challenges for local authorities in Nepal. (author)

  1. Concrete waste reduction of 50%

    International Nuclear Information System (INIS)

    Vos, R.M. de; Van der Wagt, K.M.; Van der Kruk, E.; Meeussen, H.W.

    2016-01-01

    During decommissioning quite a volume of concrete waste is produced. The degree of activation of the waste can range from clearly activated material to slightly activated or contaminated concrete. The degree of activation influences the applicable waste management processes that can be applied. The subsequent waste management processes can be identified for concrete waste are; disposal, segregation, re-use, conditional release and release. With each of these steps, the footprint of radioactive decommissioning waste is reduced. Future developments for concrete waste reduction can be achieved by applying smart materials in new build facilities (i.e. fast decaying materials). NRG (Nuclear Research and consultancy Group) has investigated distinctive waste management processes to reduce the foot-print of concrete waste streams resulting from decommissioning. We have investigated which processes can be applied in the Netherlands, both under current legislation and with small changes in legislation. We have also investigated the separation process in more detail. Pilot tests with a newly patented process have been started in 2015. We expect that our separation methods will reduce the footprint reduction of concrete waste by approximately 50% due to release or re-use in the nuclear sector or in the conventional industry. (authors)

  2. Risk management for noncombustion wastes

    International Nuclear Information System (INIS)

    Connor, K.K.; Rice, J.S.

    1991-01-01

    The Noncombustion Waste Risk Management Project is designed to incorporate the insights and information developed in these projects into tools that will help utilities make better noncombustion waste management decisions. Specific project goals are to synthesize information useful to utilities on noncombustion wastes, emphasize waste reduction as a priority over end-of-pipe management, develop methods to manage the costs and risks associated with noncombustion wastes (e.g., direct costs, permitting costs, liability costs, public relations costs), develop software and documentation to deliver the information and analysis methods to the industry. This project was initiated EPRI's Environment Division in late 1988. The early phases of the project involved gathering information on current noncombustion waste management practices, specific utility problems and concerns with respect to these wastes, current and potential future regulations, and current and emerging management options. Recent efforts have focused on characterizing the direct and indirect (e.g., lawsuits, remedial action) costs of managing these wastes and on developing and implementing risk management methods for a subset of wastes. The remainder of this paper describes the specific issues addressed by and the results and insights from the three completed waste-specific studies

  3. Assessing the disposal of wastes containing NORM in nonhazardous waste landfills

    International Nuclear Information System (INIS)

    Smith, K. P.; Blunt, D. L.; Williams, G. P.; Arnish, J. J.; Pfingston, M. R.; Herbert, J.

    1999-01-01

    In the past few years, many states have established specific regulations for the management of petroleum industry wastes containing naturally occurring radioactive material (NORM) above specified thresholds. These regulations have limited the number of disposal options available for NORM-containing wastes, thereby increasing the related waste management costs. In view of the increasing economic burden associated with NORM management, industry and regulators are interested in identifying cost-effective disposal alternatives that still provide adequate protection of human health and the environment. One such alternative being considered is the disposal of NORM-containing wastes in landfills permitted to accept only nonhazardous wastes. The disposal of petroleum industry wastes containing radium-226 and lead-210 above regulated levels in nonhazardous landfills was modeled to evaluate the potential radiological doses and associated health risks to workers and the general public. A variety of scenarios were considered to evaluate the effects associated with the operational phase (i.e., during landfill operations) and future use of the landfill property. Doses were calculated for the maximally exposed receptor for each scenario. This paper presents the results of that study and some conclusions and recommendations drawn from it

  4. The effect of vibration on alpha radiolysis of transuranic (TRU) waste

    International Nuclear Information System (INIS)

    Zerwekh, A.; Kosiewicz, S.; Warren, J.

    1993-01-01

    This paper reports on previously unpublished scoping work related to the potential for vibration to redistribute radionuclides on transuranic (TRU) waste. If this were to happen, the amount of gases generated, including hydrogen, could be increased above the undisturbed levels. This could be an important consideration for transport of TRU wastes either at DOE sites or from them to a future repository, e.g., the Waste Isolation Pilot Plant (WIPP). These preliminary data on drums of real waste seem to suggest that radionuclide redistribution does not occur. However improvements in the experimental methodology are suggested to enhance safety of future experiments on real wastes as well as to provide more rigorous data

  5. Thirty-year solid waste generation forecast for facilities at SRS

    International Nuclear Information System (INIS)

    1994-07-01

    The information supplied by this 30-year solid waste forecast has been compiled as a source document to the Waste Management Environmental Impact Statement (WMEIS). The WMEIS will help to select a sitewide strategic approach to managing present and future Savannah River Site (SRS) waste generated from ongoing operations, environmental restoration (ER) activities, transition from nuclear production to other missions, and decontamination and decommissioning (D ampersand D) programs. The EIS will support project-level decisions on the operation of specific treatment, storage, and disposal facilities within the near term (10 years or less). In addition, the EIS will provide a baseline for analysis of future waste management activities and a basis for the evaluation of the specific waste management alternatives. This 30-year solid waste forecast will be used as the initial basis for the EIS decision-making process. The Site generates and manages many types and categories of waste. With a few exceptions, waste types are divided into two broad groups-high-level waste and solid waste. High-level waste consists primarily of liquid radioactive waste, which is addressed in a separate forecast and is not discussed further in this document. The waste types discussed in this solid waste forecast are sanitary waste, hazardous waste, low-level mixed waste, low-level radioactive waste, and transuranic waste. As activities at SRS change from primarily production to primarily decontamination and decommissioning and environmental restoration, the volume of each waste s being managed will change significantly. This report acknowledges the changes in Site Missions when developing the 30-year solid waste forecast

  6. Methodology for generating waste volume estimates

    International Nuclear Information System (INIS)

    Miller, J.Q.; Hale, T.; Miller, D.

    1991-09-01

    This document describes the methodology that will be used to calculate waste volume estimates for site characterization and remedial design/remedial action activities at each of the DOE Field Office, Oak Ridge (DOE-OR) facilities. This standardized methodology is designed to ensure consistency in waste estimating across the various sites and organizations that are involved in environmental restoration activities. The criteria and assumptions that are provided for generating these waste estimates will be implemented across all DOE-OR facilities and are subject to change based on comments received and actual waste volumes measured during future sampling and remediation activities. 7 figs., 8 tabs

  7. Facts and Figures about Materials, Waste and Recycling

    Science.gov (United States)

    The area will transform MSW info included in our Advancing SMM report to better serve our audience’s needs and will also hold data on certain industrial wastes, related job creation, and in the future, hazardous waste.

  8. Management of liquid radioactive wastes at PNRI

    International Nuclear Information System (INIS)

    Garcia, C.M.

    1994-10-01

    Liquid wastes accepted at PNRI waste management facility are generated by hospitals and research institutions from all over the country including those generated from the research laboratories within the PNRI. The operation of the Philippine TRIGA Research Reactor is also a potential source of liquid waste to be handled and managed by the facility in the future. This technical report is a result of the study of the present status and development of the management of liquid wastes at PNRI. (auth.). 8 refs.; 3 figs.; 4 tabs

  9. The future market for biogas from waste - Sub-Project 3; Framtida marknaden foer biogas fraan avfall - Delprojekt 3 inom projektet Perspektiv paa framtida avfallsbehandling

    Energy Technology Data Exchange (ETDEWEB)

    Holmstroem, David; Bisaillon, Mattias; Eriksson, Ola; Hellstroem, Hanna; Nilsson, Karolina

    2013-09-01

    The overall aim of the project was to study the conditions, opportunities and constraints for the development of the market for biogas from waste in Sweden. Seven areas of importance to the development have been identified in previous projects. The areas are: market and competition, supply and demand for waste, environmental benefits of biogas utilization, technology development, economic value of biogas, political instruments and the handling of digestate. The ambition has been to create a fact and market report for these areas for stake holders such as operators, representatives of authorities and decision makers. The project is a sub-project of 'Perspectives on future waste treatment'. The goal achievement of the project is expected to be good. During the project, there has also been considerable interest in the results, which is already used by a number of operators, both within and outside the project. Thereby, the results have a good spread, even before the project is completed.

  10. Long term radioactive waste management

    International Nuclear Information System (INIS)

    Lavie, J.M.

    1984-01-01

    In France, waste management, a sensitive issue in term of public opinion, is developing quickly, and due to twenty years of experience, is now reaching maturity. With the launching of the French nuclear programme, the use of radioactive sources in radiotherapy and industry, waste management has become an industrial activity. Waste management is an integrated system dealing with the wastes from their production to the long term disposal, including their identification, sortage, treatment, packaging, collection and transport. This system aims at guaranteing the protection of present and future populations with an available technology. In regard to their long term management, and the design of disposals, radioactive wastes are divided in three categories. This classification takes into account the different radioisotopes contained, their half life and their total activity. Presently short-lived wastes are stored in the shallowland disposal of the ''Centre de la Manche''. Set up within the French Atomic Energy Commission (CEA), the National Agency for waste management (ANDRA) is responsible within the framework of legislative and regulatory provisions for long term waste management in France [fr

  11. Nuclear waste management at DOE

    International Nuclear Information System (INIS)

    Perge, A.F.

    1979-01-01

    DOE is responsible for interim storage for some radioactive wastes and for the disposal for most of them. Of the wastes that have to be managed a significant part are a result of treatment systems and devices for cleaning gases. The long term waste management objectives place minimal reliance on surveillance and maintenance. Thus, the concerns about the chemical, thermal, and radiolytic degradation of wastes require technology for converting the wastes to forms acceptable for long term isolation. The strategy of the DOE airborne radioactive waste management program is to increase the service life and reliability of filters; to reduce filter wastes; and in anticipation of regulatory actions that would require further reductions in airborne radioactive releases from defense program facilities, to develop improved technology for additional collection, fixation, and long-term management of gaseous wastes. Available technology and practices are adequate to meet current health and safety standards. The program is aimed primarily at cost effective improvements, quality assurance, and the addition of new capability in areas where more restrictive standards seem likely to apply in the future

  12. Contribution to draft generic environmental impact statement on commercial waste management: radioactive waste isolation in geologic formations

    International Nuclear Information System (INIS)

    1978-04-01

    This document concentrates on deep geologic isolation of wastes in bedded salt, granite, shale, and basalt with emphasis on wastes from three fuel cycles: reprocessing wastes from uranium and plutonium recycling, reprocessing wastes from uranium-only recycling, and spent unreprocessed fuel with no recycling. The analyses presented in this document are based on preconceptual repository designs. As the repository designs progress through future phases, refinements will occur which might modify some of these results. The 12 sections in the report are: introduction; selection and description of generic repository sites; LWR wastes to be isolated in geologic formations; description of waste isolation facilities; effluents from the waste isolation facility; assessment of environment impacts for various geographical locations of a waste isolation facility; environmental monitoring; decommissioning; mine decommissioning site restoration; deep geologic alternative actions; potential mechanisms of containment failure; and considerations relevant to provisional versus final storage

  13. Requirements for a radioactive waste data base

    International Nuclear Information System (INIS)

    Sato, Y.; Kobayashi, I.; Kikuchi, M.

    1990-01-01

    With the progress of nuclear fuel cycle in Japan, various types of radioactive waste will generate at each nuclear facility in the cycle. Therefor generated volume and stored quantity of waste will be supposed to increase. From the viewpoints of safety and public acceptance, by using mainframe computer it is necessary that the treatment of historical waste data, the estimation of generated waste volume and stored quantity and the investigation of research and development status of waste processing and disposal are carried out. This paper proposes design and development of the radioactive waste data base which is able to properly and correctly manage and grasp numerical and/or documentary information for generated radioactive waste. So the data base will be expected to use for planning the future management of radioactive waste. (author)

  14. Hanford long-term high-level waste management program overview

    International Nuclear Information System (INIS)

    Reep, I.E.

    1978-05-01

    The objective is the long-term disposition of the defense high-level radioactive waste which will remain upon completion of the interim waste management program in the mid-1980s, plus any additional high-level defense waste resulting from the future operation of N Reactor and the Purex Plant. The high-level radioactive waste which will exist in the mid-1980s and is addressed by this plan consists of approximately 3,300,000 ft 3 of damp salt cake stored in single-shell and double-shell waste tanks, 1,500,000 ft 3 of damp sludge stored in single-shell and double-shell waste tanks, 11,000,000 gallons of residual liquor stored in double-shell waste tanks, 3,000,000 gallons of liquid wastes stored in double-shell waste tanks awaiting solidification, and 2,900 capsules of 90 SR and 137 Cs compounds stored in water basins. Final quantities of waste may be 5 to 10% greater, depending on the future operation of N Reactor and the Purex Plant and the application of waste treatment techniques currently under study to reduce the inventory of residual liquor. In this report, the high-level radioactive waste addressed by this plan is briefly described, the major alternatives and strategies for long-term waste management are discussed, and a description of the long-term high-level waste management program is presented. Separate plans are being prepared for the long-term management of radioactive wastes which exist in other forms. 14 figures

  15. Radioactive waste mangement in Canada

    International Nuclear Information System (INIS)

    Didyk, J.P.

    1976-01-01

    The objectives of the Canadian radioactive waste management program are to manage the wastes so that the potential hazards of the material are minimized, and to manage the wastes in a manner which places the minimum possible burden on future generations. The Atomic Energy Control Board regulates all activities in the nuclear field in Canada, including radioactive waste management facility licensing. The Atomic Energy Control Act authorizes the Board to make rules for regulating its proceedings and the performance of its functions. The Atomic Energy Control Regulations define basic regulatory requirements for the licensing of facilities, equipment and materials, including requirements for records and inspection, for security and for health and safety

  16. Plasma technology for waste treatment

    International Nuclear Information System (INIS)

    Cohn, D.R.

    1995-01-01

    Improved environmental cleanup technology is needed to meet demanding goals for remediation and treatment of future waste streams. Plasma technology has unique features which could provide advantages of reduced secondary waste, lower cost, and onsite treatment for a wide variety of applications. Plasma technology can provide highly controllable processing without the need for combustion heating. It can be used to provide high temperature processing (∼10,000 degrees C). Plasma technology can also be employed for low temperature processing (down to room temperature range) through selective plasma chemistry. A graphite electrode arc plasma furnace at MIT has been used to investigate high temperature processing of simulated solid waste for Department of Energy environmental cleanup applications. Stable, non-leachable glass has been produced. To ensure reliable operation and to meet environmental objectives, new process diagnostics have been developed to measure furnace temperature and to determine metals emissions in the gaseous effluent. Selective plasma destruction of dilute concentrations of hazardous compounds in gaseous waste streams has been investigated using electron beam generated plasmas. Selective destruction makes it possible to treat the gas steam at relatively low temperatures in the 30-300 degrees C range. On-line infrared measurements have been used in feedback operation to maximize efficiency and ensure desired performance. Plasma technology and associated process diagnostics will be used in future studies of a wide range of waste streams

  17. Hanford Tank Waste - Near Source Treatment of Low Activity Waste

    International Nuclear Information System (INIS)

    Ramsey, William Gene

    2013-01-01

    Abstract only. Treatment and disposition of Hanford Site waste as currently planned consists of 100+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory of this waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most of the leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper

  18. Evaluation and review of alternative waste forms for immobilization of high level radioactive wastes

    International Nuclear Information System (INIS)

    1979-01-01

    Objective was to review the relative merits and potential of eleven alternative waste forms being considered for the solidification and disposal of radioactive wastes. A numerical rating of the alternative waste forms was arrived at individually by peer review panel members taking into consideration nine scientific and nine engineering parameters affecting the long-term performance and production of waste forms. A group rating for the alternative forms was achieved by averaging the individiual scores and discussing the available data base. Three final ranking lists comparing: (A) Present Scientific Merits or Least Risk for Use Today; (B) Research Priority; and (3) Present and Potential Engineering Practicality were prepared by the Panel. Each waste form in the lists is assigned a value of either (1) Top Rank, (2) Intermediate Rank, or is assigned a value of either (1) Top Rank, (2) Intermediate Rank, or (3) Bottom Rank. Relative strengths and weaknesses of the alternative waste forms and recommendations for future program directions are discussed

  19. Waste reduction at the Savannah River Site

    International Nuclear Information System (INIS)

    Stevens, W.E.; Lee, R.A.; Reynolds, R.W.

    1990-01-01

    The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site's operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities

  20. Radioactive waste management in European Union countries

    International Nuclear Information System (INIS)

    Vico, E.

    2002-01-01

    Although the Euratom Treaty does not assign direct authorities to the European Union in the Field of radioactive waste, the Commission has developed a series of activities related to this type of waste. The article deals with these Community initiatives, and the problems of radioactive waste management in the different Member States, and future plans in the field in the light of forthcoming European Union enlargement in 2004. (Author)

  1. Solid waste management complex site development plan

    International Nuclear Information System (INIS)

    Greager, T.M.

    1994-01-01

    The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated

  2. Solid waste management complex site development plan

    Energy Technology Data Exchange (ETDEWEB)

    Greager, T.M.

    1994-09-30

    The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated.

  3. Perspective of metal encapsulation of waste

    International Nuclear Information System (INIS)

    Jardine, L.J.; Steindler, M.J.

    1978-01-01

    A conceptual flow sheet is presented for encapsulating solid, stabilized calcine (e.g., supercalcine) in a solid lead alloy, using existing or developing technologies. Unresolved and potential problem areas of the flow sheet are outlined and suggestions are made as how metal encapsulation might be applied to other solid wastes from the fuel cycle. It is concluded that metal encapsulation is a technique applicable to many forms of solid wastes and is likely to meet future waste isolation criteria and regulations

  4. Log-Likelihood Ratio Calculation for Iterative Decoding on Rayleigh Fading Channels Using Padé Approximation

    Directory of Open Access Journals (Sweden)

    Gou Hosoya

    2013-01-01

    Full Text Available Approximate calculation of channel log-likelihood ratio (LLR for wireless channels using Padé approximation is presented. LLR is used as an input of iterative decoding for powerful error-correcting codes such as low-density parity-check (LDPC codes or turbo codes. Due to the lack of knowledge of the channel state information of a wireless fading channel, such as uncorrelated fiat Rayleigh fading channels, calculations of exact LLR for these channels are quite complicated for a practical implementation. The previous work, an LLR calculation using the Taylor approximation, quickly becomes inaccurate as the channel output leaves some derivative point. This becomes a big problem when higher order modulation scheme is employed. To overcome this problem, a new LLR approximation using Padé approximation, which expresses the original function by a rational form of two polynomials with the same total number of coefficients of the Taylor series and can accelerate the Taylor approximation, is devised. By applying the proposed approximation to the iterative decoding and the LDPC codes with some modulation schemes, we show the effectiveness of the proposed methods by simulation results and analysis based on the density evolution.

  5. Energy recovery from municipal solid wastes in Italy: Actual study and perspective for future

    International Nuclear Information System (INIS)

    Brunetti, N.; Ciampa, F.; De Cecco, C.

    1992-01-01

    Materials and energy recovery from municipal solid wastes (MSW) and assimilable waste, and their re-use is one of strong points of current regulations and tendencies, both at the national and at community level in Europe. In Italy, the interest in energy recovery from renewable sources has been encouraged by energy-savings law which included financial incentives for thermal plant building if low grade fuels such as MSW were employed. New electric power prices imposed by Italian Electric Power Authority, ENEL, encourage energy recovery from waste burners. This paper aims to point out the present state of energy recovery from wastes in Italy, trends and prospects to satisfy, with new plants, the need for waste thermal destruction and part of the demand for energy in the different Italian regions: only about 10% of MSW are burned and just a small percentage of the estimated amount of recoverable energy (2 MTOE/y) is recuperated. Different technological cycles are discussed: incineration of untreated wastes and energy recovery; incineration (or gasification) of RDF (refuse derived fuels) and heat-electricity co-generation; burning of RDF in industrial plants, in addition to other fuels

  6. Waste management study: Process development at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    1984-12-01

    This report presents the results of an evaluation of the present Toxic Waste Control Operations at the Lawrence Livermore National Laboratory, evaluates the technologies most applicable to the treatment of toxic and hazardous wastes and presents conceptual designs of processes for the installation of a new decontamination and waste treatment facility (DWTF) for future treatment of these wastes

  7. Energy futures-2

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    This book covers the proceedings of the Symposium on Energy Futures II. Topics covered include: The National Energy Strategy; The Gas and petroleum industry; energy use in the paper industry; solar energy technology; hydroelectric power; biomass/waste utilization; engine emissions testing laboratories; integrated coal gassification-combined-cycle power plants

  8. Waste immobilization demonstration program for the Hanford Site's Mixed Waste Facility

    International Nuclear Information System (INIS)

    Burbank, D.A.; Weingardt, K.M.

    1994-05-01

    This paper presents an overview of the Waste Receiving and Processing facility, Module 2A> waste immobilization demonstration program, focusing on the cooperation between Hanford Site, commercial, and international participants. Important highlights of the development and demonstration activities is discussed from the standpoint of findings that have had significant from the standpoint of findings that have had significant impact on the evolution of the facility design. A brief description of the future direction of the program is presented, with emphasis on the key aspects of the technologies that call for further detailed investigation

  9. Amount of radioactive wastes in the Federal Republic of Germany. Waste inventory for the year 1984

    International Nuclear Information System (INIS)

    Brennecke, P.; Schuhmacher, J.

    1986-03-01

    On December 31, 1984, about 53 200 waste packages were stored in intermediate storage facilities. The unconditioned radioactive wastes amounted to about 7 000 m 3 . The volume of the conditioned radioactive wastes amounted to about 25 100 m 3 . Thereof the waste from nuclear research establishments made up about 10 000 m 3 , the waste from the operation of nuclear power plants about 7 400 m 3 and the waste from spent fuel reprocessing about 5 100 m 3 . In addition the future amount of conditioned radioactive wastes with negligible heat generation was prognosticated. Due to this forecast an amount of about 238 000 m 3 of these wastes is expected in the year 2000. In 1984 a capacity of about 87 800 m 3 for the intermediate storage of radioactive wastes was available. On December 31, 1984, this capacity was utilized by unconditioned and conditioned radioactive wastes to about 37%. It may be concluded from the data on the expected amount of radioactive wastes with negligible heat generation and on the utilization factor of the intermediate storage facilities that no bottlenecks are to be assumed up to the planned operation of the Konrad repository. (orig./HP) [de

  10. Tank Farm Waste Transfer Compatibility Program

    International Nuclear Information System (INIS)

    FOWLER, K.D.

    2001-01-01

    The compatibility program described in this document formalizes the process for determining waste compatibility. The primary goal of the program is to ensure that sufficient controls are in place to prevent the formation of incompatible mixtures during future operations. The process described involves characterizing waste, comparing characteristics with criteria, resolving potential incompatibilities and documenting the process

  11. Tank Farm Waste Transfer Compatibility Program

    International Nuclear Information System (INIS)

    FOWLER, K.D.

    2000-01-01

    The compatibility program described in this document formalizes the process for determining waste compatibility. The primary goal of the program is to ensure that sufficient controls are in place to prevent the formation of incompatible mixtures during future operations. The process described involves characterizing waste, comparing characteristics with criteria, resolving potential incompatibilities and documenting the process

  12. Supplemental Information Source Document Waste Management

    Energy Technology Data Exchange (ETDEWEB)

    Wood, Craig [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Halpern, Jonathan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wrons, Ralph [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Reiser, Anita [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mond, Michael du [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Shain, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-12-01

    This Supplemental Information Source Document for Waste Management was prepared in support of future analyses including those that may be performed as part of the Sandia National Laboratories, New Mexico (SNL/NM) Site-Wide Environmental Impact Statement. This document presents information about waste management practices at SNL/NM, including definitions, inventory data, and an overview of current activities.

  13. The legacy and future of radioactive waste management at the Millenium

    International Nuclear Information System (INIS)

    Martin, J.E.; Lee, C.

    2000-01-01

    Wastes containing radioactive materials have been produced ever since ore recovery and processing began; however, such materials did not become of public concern until the large-scale activities involving uranium and thorium ores and nuclear fission during and after World War II. Efforts to provide disposal sites for radioactive wastes, especially those associated with nuclear weapons and nuclear energy, have been largely unsuccessful for the past 40 years or so and are nearing crisis proportions as the new millenium begins - its eventual resolution is believed to require greater reliance on stewardship and a larger governmental presence. (author)

  14. Ethical aspects of nuclear waste

    International Nuclear Information System (INIS)

    Persson, L.

    1988-01-01

    The reasoning made by us leads to a double conclusion: a repository should be constructed so that controls and corrective measures are unnecessary, while at the same time not making them impossible. In other words, our generation should neither put the entire responsibility for maintenance of repositories in future generations' hands; nor should we deny future generations the possibility of taking control. By means of different formulations and by proceeding from various basic ideas, a dual objective is established about repository facilities: safety in operation combined with ease of service ability without mandatory but executable control. Prerequisities are the continued advancement of knowledge and refinement of the qualifications required to deal with nuclear waste. The ethical considerations should be included in the bases for future legislation on radioactive waste. Nuclear scientists should consider these points before they can form a foundation to the legislation process

  15. Characteristics of solidified high-level waste products

    International Nuclear Information System (INIS)

    1979-01-01

    The object of the report is to contribute to the establishment of a data bank for future preparation of codes of practice and standards for the management of high-level wastes. The work currently in progress on measuring the properties of solidified high-level wastes is being studied

  16. Germany: Management of decommissioning waste in Germany

    International Nuclear Information System (INIS)

    Borrmann, F.; Brennecke, P.; Koch, W.; Kugel, K.; Steyer, S.

    2007-01-01

    Over the past two decades, Germany has gained a substantial amount of experience in the decommissioning of nuclear facilities of different types and sizes. Many research reactors and all prototype nuclear power plants, as well as a few larger nuclear power plants and fuel cycle facilities, are currently at varying stages of decommissioning. Several facilities have been fully dismantled and the sites have been cleared for reuse. The decommissioning projects comprise 18 power and prototype reactors, 33 research reactors and 11 fuel cycle facilities which are being or have been decommissioned. In the future, further nuclear power plants will be shut down and decommissioned in accordance with Germany?s energy policy to phase out the use of nuclear power for commercial electricity generation as given in the April 2002 amendment of the Atomic Energy Act. Radioactive waste, from operations as well as from decommissioning activities, is to be conditioned in such a way as to comply with the waste acceptance requirements of a repository. In Germany, all types of radioactive waste (i.e., short-lived and long-lived) are to be disposed of in deep geological formations. A distinction is being made for heat generating waste (i.e., high level waste) and waste with negligible heat generation (i.e., low level and intermediate level waste). Radioactive decommissioning waste is waste with negligible heat generation. Waste acceptance requirements of a repository are of particular importance for the conditioning of radioactive waste, including decommissioning waste. The waste acceptance requirements, as they resulted from the Konrad licensing procedure, are being applied by the waste generators for the conditioning of decommissioning waste. Compliance with these requirements must be demonstrated through the waste package quality control, even if the waste will be disposed of in the future. In 2002 the Konrad repository was licensed for the disposal of all types of waste with negligible

  17. Significance of waste incineration in Germany; Stellenwert der Abfallverbrennung in Deutschland

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-10-15

    The report on the relevance of waste incineration in Germany is covering the following issues: change of the issue waste incineration in the last century, the controversy on waste incineration in the 80ies; environmental relevance of waste incineration; utilization of incineration residues; contribution to environmental protection; possible hazards for human health due are waste incinerator plants; the central challenges of waste incineration today; potential restraints to energy utilization in thermal waste processing; optimization of the energetic utilization of municipal wastes; future of the waste management and the relevance of waste incineration.

  18. A comparative assessment of alternative waste management procedures for selected reprocessing wastes

    International Nuclear Information System (INIS)

    Hickford, G.E.; Plews, M.J.

    1983-07-01

    This report, which has been prepared by Associated Nuclear Services for the Department of the Environment, presents the results of a study and comparative assessment of management procedures for low and intermediate level solid waste streams arising from current and future fuel reprocessing operations on the Sellafield site. The characteristics and origins of the wastes under study are discussed and a reference waste inventory is presented, based on published information. Waste management strategy in the UK and its implications for waste conditioning, packaging and disposal are discussed. Wastes currently arising which are not suitable for Drigg burial or sea dumping are stored in an untreated form. Work is in hand to provide additional and improved disposal facilities which will accommodate all the waste streams under study. For each waste stream viable procedures are identified for further assessment. The procedures comprise a series of on-site operations-recovery from storage, pre-treatment, treatment, encapsulation, and packaging, prior to storage or disposal of the conditioned waste form. Assessments and comparisons of each procedure for each waste are presented. These address various process, operational, economic, radiological and general safety factors. The results are presented in a series of tables with supporting text. For the majority of wastes direct encapsulation with minimal treatment appears to be a viable procedure. Occupational exposure and general safety are not identified as significant factors governing the choice of procedures. The conditioned wastes meet the general requirements for safe handling during storage and transportation. The less active wastes suitable for disposal by currently available routes meet the appropriate disposal criteria. It is not possible to consider in detail the suitability for disposal of the more active wastes for which disposal facilities are not yet available. (Author)

  19. Preserving the memory of waste disposal centres for the future generations; Preserver la memoire des centre de stockage pour les generations futures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    Radioactive waste disposal and storage facilities are designed to be intrinsically safe (lowest possible impact) for a duration depending on the lifetime of wastes. The French national agency of waste management (ANDRA) wishes to preserve as long as possible the memory of its waste facilities taking into account a possible loss of this memory beyond the legal monitoring period. For this reason, the ANDRA has analyzed the means that have permitted the preservation of the historical heritage through the centuries. The conclusions show that it is possible to preserve with a good confidence a patrimony during long time scales providing some organizing and structuring of this memory (archiving on numerical media and on permanent paper). (J.S.)

  20. Management of radioactive waste from 99Mo production

    International Nuclear Information System (INIS)

    1998-11-01

    99m Tc used for labelling different pharmaceuticals is the most important radionuclide in nuclear medicine practice, and probably will continue to play this important role for the foreseeable future. 99m Tc is the short lived daughter product of the parent 99 Mo, which is mainly produced by the nuclear fission of 235 U. Recognizing the importance of the waste management issue associated with 99 Mo production the IAEA initiated preparation of this report to provide Member States and existing and potential producers of 99 Mo with practical approaches and the available information on the subject. Waste management in the context of this report encompasses all waste-related aspects, for example, handling, treatment, conditioning, storage, transport, and disposal. The document is organized in several chapters giving the following information: short description of the basic nuclear and physical properties of 99 Mo and 99m Tc; an overview of past, present and possible future production methods; characteristics of the various waste streams produced in the aforementioned processes; description of the necessary waste management practices needed to handle the relevant waste streams in a responsible and internationally-accepted manner; conclusion and recommendations

  1. Methods for maintaining a record of waste packages during waste processing and storage

    International Nuclear Information System (INIS)

    2005-01-01

    During processing, radioactive waste is converted into waste packages, and then sent for storage and ultimately for disposal. A principal condition for acceptance of a waste package is its full compliance with waste acceptance criteria for disposal or storage. These criteria define the radiological, mechanical, physical, chemical and biological properties of radioactive waste that can, in principle, be changed during waste processing. To declare compliance of a waste package with waste acceptance criteria, a system for generating and maintaining records should be established to record and track all relevant information, from raw waste characteristics, through changes related to waste processing, to final checking and verification of waste package parameters. In parallel, records on processing technology and the operational parameters of technological facilities should adhere to established and approved quality assurance systems. A records system for waste management should be in place, defining the data to be collected and stored at each step of waste processing and using a reliable selection process carried over into the individual steps of the waste processing flow stream. The waste management records system must at the same time ensure selection and maintenance of all the main information, not only providing evidence of compliance of waste package parameters with waste acceptance criteria but also serving as an information source in the case of any future operations involving the stored or disposed waste. Records generated during waste processing are a constituent part of the more complex system of waste management record keeping, covering the entire life cycle of radioactive waste from generation to disposal and even the post-closure period of a disposal facility. The IAEA is systematically working on the preparation of a set of publications to assist its Member States in the development and implementation of such a system. This report covers all the principal

  2. Radioactive and hazardous chemical wastes: A challenge for the future: [Final report

    International Nuclear Information System (INIS)

    Wymer, R.G.

    1986-01-01

    The author focuses attention on serious and widespread problems of environmental pollution, and points out that there are worthwhile problems to work on which are both important and professionally rewarding. A major opportunity exists to reduce the amounts of the wastes or to eliminate them at their sources by changing manufacturing methods or by developing new processes or products. However, there will always be wastes of some sort, and they must be dealt with

  3. Proposed methods for treating high-level pyrochemical process wastes

    International Nuclear Information System (INIS)

    Johnson, T.R.; Miller, W.E.; Steunenberg, R.K.

    1985-01-01

    This survey illustrates the large variety and number of possible techniques available for treating pyrochemical wastes; there are undoubtedly other process types and many variations. The choice of a suitable process is complicated by the uncertainty as to what will be an acceptable waste form in the future for both TRU and non-TRU wastes

  4. Mixed low-level waste form evaluation

    International Nuclear Information System (INIS)

    Pohl, P.I.; Cheng, Wu-Ching; Wheeler, T.; Waters, R.D.

    1997-01-01

    A scoping level evaluation of polyethylene encapsulation and vitreous waste forms for safe storage of mixed low-level waste was performed. Maximum permissible radionuclide concentrations were estimated for 15 indicator radionuclides disposed of at the Hanford and Savannah River sites with respect to protection of the groundwater and inadvertent intruder pathways. Nominal performance improvements of polyethylene and glass waste forms relative to grout are reported. These improvements in maximum permissible radionuclide concentrations depend strongly on the radionuclide of concern and pathway. Recommendations for future research include improving the current understanding of the performance of polymer waste forms, particularly macroencapsulation. To provide context to these estimates, the concentrations of radionuclides in treated DOE waste should be compared with the results of this study to determine required performance

  5. Current status of radioactive waste management in Japan

    International Nuclear Information System (INIS)

    Amanuma, Tsuyoshi

    1985-01-01

    In Japan the nuclear power generation capacity now exceeds the level of 20,000 MW, 24.3 % of the total power generation. It constitutes the major position of energy source, a substitute for a petroleum. In the nuclear power, chemical engineering contributes significantly to treatment and disposal of the radioactive wastes. In the interim report by an ad hoc committee in the Atomic Energy Commission, for the future, rational grouping of the wastes and the direction of land disposal are stated. Contents are the following: basic ideas for the radioactive wastes, radioactive wastes countermeasures in Japan (wastes classification, low and high level and transuranic wastes), radioactive wastes in the nuclear fuel cycle (reactor and fuel reprocessing and reactor dismantling wastes). (Mori, K.)

  6. 1995 Solid Waste 30-year volume summary

    International Nuclear Information System (INIS)

    Valero, O.J.; DeForest, T.J.; Templeton, K.J.

    1995-06-01

    This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford's Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford

  7. 242-A evaporator dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-01-01

    The 242-A Evaporator is a waste management unit within the Hanford Facility that consists of process vessels and support systems for heating, evaporating, and condensing double-shell tank (DST) waste generated by Hanford Site operations. Operation of the 242-A Evaporator serves to reduce the volume of waste solutions within the DSTs that do not self-boil, while separating inorganic and radionuclide constituents from organic constituents. This operation reduces the number of underground DSTs required for waste storage and also makes the mixed waste more suitable for future treatment and disposal (i.e., grouting and vitrification). The 242-A Evaporator receives mixed-waste streams from the DSTs that contain organic and inorganic constituents and radionuclides. The waste is a dangerous waste (DW) because of corrosivity, reactivity, and toxicity characteristics, and is an extremely hazardous waste (EHW) as a result of toxicity (state criteria only), carcinogenicity, and persistence under the state mixture rule. The waste also contains spent nonhalogenated solvents

  8. 1995 Solid Waste 30-year volume summary

    Energy Technology Data Exchange (ETDEWEB)

    Valero, O.J. [Westinghouse Hanford Co., Richland, WA (United States); DeForest, T.J.; Templeton, K.J. [Pacific Northwest Lab., Richland, WA (United States)

    1995-06-01

    This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford`s Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford.

  9. An informal judgment assessment of subsidence mitigation options for low-level radioactive waste management on the Nevada Test Site

    International Nuclear Information System (INIS)

    Crowe, B.M.; Besinger, H.; Dolenc, M.

    1999-01-01

    An assessment of options to mitigate the effects of subsidence at low-level radioactive waste disposal sites on the Nevada Test Site was conducted using an informal method of expert judgment. Mitigation options for existing waste cells and future waste cells were identified by a committee composed of knowledgeable personnel from the DOE and DOE-contractors. Eight ranking factors were developed to assess the mitigation options and these factors were scored through elicitation of consensus views from the committee. Different subsets of the factors were applied respectively, to existing waste cells and future waste cells, and the resulting scores were ranked using weighted and unweighted scores. These scores show that there is a large number of viable mitigation options and considerable flexibility in assessing the subsidence issue with a greater range of options for future waste cells compared to existing waste cells. A highly ranked option for both existing and future waste cells is covering the waste cells with a thick closure cap of native alluvium

  10. Hanford Site Waste Management Plan

    International Nuclear Information System (INIS)

    1988-12-01

    The Hanford Site Waste Management Plan (HWMP) was prepared in accordance with the outline and format described in the US Department of Energy Orders. The HWMP presents the actions, schedules, and projected costs associated with the management and disposal of Hanford defense wastes, both radioactive and hazardous. The HWMP addresses the Waste Management Program. It does not include the Environmental Restoration Program, itself divided into the Environmental Restoration Remedial Action Program and the Decontamination and Decommissioning Program. The executive summary provides the basis for the plans, schedules, and costs within the scope of the Waste Management Program at Hanford. It summarizes fiscal year (FY) 1988 including the principal issues and the degree to which planned activities were accomplished. It further provides a forecast of FY 1989 including significant milestones. Section 1 provides general information for the Hanford Site including the organization and administration associated with the Waste Management Program and a description of the Site focusing on waste management operations. Section 2 and Section 3 describe radioactive and mixed waste management operations and hazardous waste management, respectively. Each section includes descriptions of the waste management systems and facilities, the characteristics of the wastes managed, and a discussion of the future direction of operations

  11. Proceedings of the eighth annual DOE low-level waste management forum: Technical Session 8, Future DOE low-level waste management

    International Nuclear Information System (INIS)

    1987-02-01

    This volume contains the following papers: (1) DOE Systems Approach and Integration; (2) Impacts of Hazardous Waste Regulation on Low-Level Waste Management; (3) Site Operator Needs and Resolution Status; and (4) Establishment of New Disposal Capacity for the Savannah River Plant. All papers have been processed for inclusion in the Energy Data Base. (AT)

  12. Radioactive waste management in the United Kingdom

    International Nuclear Information System (INIS)

    Hill, J.

    1976-01-01

    The principles to be followed in the processing and disposal of radioactive wastes are summarized and the procedures practiced in the United Kingdom for different types of wastes are reviewed to illustrate how these principles are being observed. The objectives for the future in modification of current practices are discussed

  13. Waste package reliability analysis

    International Nuclear Information System (INIS)

    Pescatore, C.; Sastre, C.

    1983-01-01

    Proof of future performance of a complex system such as a high-level nuclear waste package over a period of hundreds to thousands of years cannot be had in the ordinary sense of the word. The general method of probabilistic reliability analysis could provide an acceptable framework to identify, organize, and convey the information necessary to satisfy the criterion of reasonable assurance of waste package performance according to the regulatory requirements set forth in 10 CFR 60. General principles which may be used to evaluate the qualitative and quantitative reliability of a waste package design are indicated and illustrated with a sample calculation of a repository concept in basalt. 8 references, 1 table

  14. The Future of Hazardous Waste Tracking: Radio Frequency Identification (RFID)

    Science.gov (United States)

    The capability and performance of various RFID technologies to track hazardous wastes and materials (HAZMAT) across international borders will be verified in the El Paso, Texas-Ciudad Juarez, Mexico area under EPA's Environmental Technology Verification (ETV)/Environmental and S...

  15. Managing America's solid waste

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, J. A.

    1998-09-15

    This report presents an historical overview of the federal role in municipal solid waste management from 1965 to approximately 1995. Attention is focuses on the federal role in safeguarding public health, protecting the environment, and wisely using material and energy resources. It is hoped that this report will provide important background for future municipal solid waste research and development initiatives.

  16. Environmental impact of the management of wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Sousselier, Y.

    1980-01-01

    The subject is discussed under the headings; introduction; present and future management of radioactive wastes (origin and characteristics of radioactive wastes; present and possible future processes for management); production of waste following present management methods (quantities produced by one reactor, and estimate of global production; estimate of cumulative global production to the year 2000); alternative management processes; environmental impacts of present management methods (pollution; land use; natural resources; socio-economic constraints); impacts of effluent release (radiation doses due to various isotopes, at different distances and over various periods); global impacts; impacts of radioactive waste processing, storing and disposal (various methods discussed); detailed consideration of underground disposal (migration of radionuclides through geologic formations); disposal of wastes from decommissioning of nuclear installations (reactors and reprocessing plants); mining wastes; alternative processes; conclusions. (U.K.)

  17. Deep geological radioactive waste disposal in Germany: Lessons learned and future perspectives

    International Nuclear Information System (INIS)

    Lempert, J.P.; Biurrun, E.

    2001-01-01

    As far back as in the seventies a fully developed, integrated concept for closing the nuclear fuel cycle was agreed upon in Germany between the Federal Government of that time and the electricity utilities. In the twenty years elapsed since then it was further developed as necessary to permanently fit the state of the art of science and technology. For management of spent fuel, the concept currently considers two equivalent alternatives: direct disposal of the spent fuel or reprocessing the fuel and recycling in thermal reactors. Interim storage of spent fuel and vitrified high level waste (HLW) to allow for decay heat generation to decrease to a convenient level is carried out in centralized installations. Radioactive waste disposal in pursuant to German regulations for all kinds of waste is to be carried out exclusively in deep geologic repositories. At present in the country, there are three centralized interim storage facilities for spent fuel, one of them can also accept vitrified HLW. Several facilities are in use for low level waste (LLW) and intermediate level waste (ILW) storage at power plants and other locations. A pilot conditioning facility for encapsulating spent fuel and/or HLW for final disposal is now ready to be commissioned. Substantial progress has been achieved in realization of HLW disposal, including demonstration of all the needed technology and fabrication of a significant part of the equipment. With regard to deep geologic disposal of LLW and ILW, Germany has worldwide unique experience. The Asse salt mine was used as an experimental repository for some 10 years in the late sixties and seventies. After serving since then as an underground research facility, it is now being backfilled and sealed. The Morsleben deep geologic repository was in operation for more than 25 years until September 1998. (author)

  18. Repurposing Waste Streams: Lessons on Integrating Hospital Food Waste into a Community Garden.

    Science.gov (United States)

    Galvan, Adri M; Hanson, Ryan; George, Daniel R

    2018-04-06

    There have been increasing efforts in recent decades to divert institutional food waste into composting programs. As major producers of food waste who must increasingly demonstrate community benefit, hospitals have an incentive to develop such programs. In this article, we explain the emerging opportunity to link hospitals' food services to local community gardens in order to implement robust composting programs. We describe a partnership model at our hospital in central Pennsylvania, share preliminary outcomes establishing feasibility, and offer guidance for future efforts. We also demonstrate that the integration of medical students in such efforts can foster systems thinking in the development of programs to manage hospital waste streams in more ecologically-friendly ways.

  19. 2009 National inventory of radioactive material and wastes. In short

    International Nuclear Information System (INIS)

    2009-01-01

    This booklet gives a summary of the national inventory report on radioactive wastes that are present on the French territory (as recorded until december, 2007). Intended for public information, the booklet explains the basics of radioactive materials and wastes and waste management, and gives some data on present and future waste volumes, information about radioactive waste classification, the geographical distribution of waste sites in France, etc. The various types of radioactive wastes are described (classified by their lifetime and activity level) as well as historical storage sites, polluted areas where wastes are stored, radioactive objects, etc. and their respective management approaches are presented

  20. Nuclear wastes: status and perspectives; Les Dechets nucleaires: etat des lieux et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Barre, B.; Bazile, F.; Bonin, B.; Marvy, A.; Ouzounian, G.; Wizsenfeld, B.

    2011-07-01

    Radioactive wastes are considered by the large public as a problem which mortgages the future of nuclear industry. Today, the main principles of radioactive wastes management are defined: separation, conditioning, storage and disposal are the main elements of a strategy allowing to protect the man and the environment from the impacts of the inevitable ultimate wastes. In a period of debate concerning the future of these wastes, this book aims at supplying to the public the elements which will allow him to build his own opinion about this hot topic. (J.S.)

  1. America's nuclear waste backlog

    International Nuclear Information System (INIS)

    Benenson, R.

    1981-01-01

    This report discusses three topics: concern and controversy relating to nuclear waste; high-level waste storage and politics of waste disposal. The most pressing waste disposal problem concerns spent fuel assemblies from commercial nuclear power plants. It was expected that commercial spent fuel would be sent to commercial reprocessing plants. The feasibility of commercial reprocessing in the United States is contingent on the expansion of the nuclear power industry. The current high-level liquid waste inventory is about 77 million gallons. These are stored at Richland, Washington; Aiken, South Carolina; and Idaho Falls, Idaho. The only commercial high-level wastes ever produced are stored at the defunct reprocessing facility at West Valley, New York. A high-level waste repository must be capable of isolating wastes that will remain dangerous for thousands of years. Salt has long been considered the most suitable medium for high-level and transuranic waste disposal. The timetable for opening a deep geological repository is one of the issues that will have to be dealt with by Congress. The 97th Congress appears ready to act on high-level nuclear waste legislation. Even opponents of nuclear expansion admit the necessity of legislation. Even if Congress gets its act together, it does not mean that the nuclear waste issue is gone. There are still unknowns - future of reprocessing, the needs and demands of the military; the health of the nuclear power industry; the objections of residents in potential site areas; the possibility of a state veto, and the unsolved technological problems in geologic site selection

  2. Nuclear waste

    International Nuclear Information System (INIS)

    1990-06-01

    DOE estimates that disposing of radioactive waste from civilian nuclear power plants and its defense-related nuclear facilities could eventually end up costing $32 billion. To pay for this, DOE collects fees from utilities on electricity generated by nuclear power plants and makes payments from its defense appropriation. This report states that unless careful attention is given to its financial condition, the nuclear waste program is susceptible to future shortfalls. Without a fee increase, the civilian-waste part of the program may already be underfunded by at least $2.4 billion (in discounted 1988 dollars). Also, DOE has not paid its share of cost-about $480 million-nor has it disclosed this liability in its financial records. Indexing the civilian fee to the inflation rate would address one major cost uncertainty. However, while DOE intends to do this at an appropriate time, it does not use a realistic rate of inflation as its most probable scenario in assessing whether that time has arrived

  3. Radioactive waste management policy for nuclear power

    International Nuclear Information System (INIS)

    Andrei, V.; Glodeanu, F.; Simionov, V.

    1998-01-01

    Nuclear power is part of energy future as a clean and environmental friendly source of energy. For the case of nuclear power, two specific aspects come more often in front of public attention: how much does it cost and what happens with radioactive waste. The competitiveness of nuclear power vs other sources of energy is already proved in many developed and developing countries. As concerns the radioactive wastes treatment and disposal, industrial technologies are available. Even final solutions for disposal of high level radioactive waste, including spent fuel, are now fully developed and ready for large scale implementation. Policies and waste management strategies are established by all countries having nuclear programs. Once, the first nuclear power reactor was commissioned in Romania, and based on the national legal provisions, our company prepared the first issue of a general strategy for radioactive waste management. The general objective of the strategy is to dispose the waste according to adequate safety standards protecting the man and the environment, without undue burden on future generations. Two target objectives were established for long term: an interim spent fuel dry storage facility and a low and intermediate level waste repository. A solution for spent fuel disposal will be implemented in the next decade, based on international experience. Principles for radioactive waste management, recommended by IAEA are closely followed in the activities of our company. The continuity of responsibilities is considered to be very important. The radioactive waste management cost will be supported by the company. A tax on unit price of electricity will be applied. The implementation of radioactive waste management strategy includes as a major component the public information. A special attention will be paid by the company to an information program addressed to different categories of public in order to have a better acceptance of our nuclear power projects

  4. Amount of radioactive wastes in the Federal Republic of Germany - waste inquiry for the year 1985

    International Nuclear Information System (INIS)

    Brennecke, P.; Schumacher, J.

    1986-09-01

    On December 31, 1985, about 61 400 waste packages were stored in intermediate storage facilities. The unconditioned radioactive wastes amounted to about 6 300 m 3 . The volume of the conditioned radioactive wastes amounted to about 29 600 m 3 . Thereof the waste from nuclear research establishments made up about 11 200 m 3 , the waste from the operation of nuclear power plants about 9 900 m 3 and the waste from reprocessing of spent fuel elements about 5 800 m 3 . In addition the future amount of conditioned radioactive wastes with negligible heat generation was prognosticated. Due to this forecast an amount of about 227 600 m 3 of these wastes is expected in the year 2000. In 1985 a capacity of about 88 700 m 3 for the intermediate storage of radioactive wastes was available in the Federal Republic of Germany. On December 31, 1985, this capacity was utilized by unconditioned and conditioned radioactive wastes at an average of about 40%. It may be concluded from the data on the expected amount of radioactive wastes with negligible heat generation and on the utilization factor of the intermediate storage facilities that no bottlenecks are to be assumed up to the planned operation of the Konrad repository. (orig./HP) [de

  5. Yield of radioactive wastes in the Federal Republic of Germany - waste survey for the year 1986

    International Nuclear Information System (INIS)

    Brennecke, P.; Schumacher, J.

    1987-05-01

    On December 31, about 67600 waste packages were stored in interim storage facilities. The unconditioned radioactive wastes amounted to about 6600 m 3 . The volume of the conditioned radioactive wastes amounted to about 33900 m 3 . Thereof the waste from nuclear research establishments made up about 13300 m 3 , the waste from the operation of nuclear power plants about 10700 m 3 and the waste from reprocessing of spent fuel elements about 6700 m 3 . In addition the future amount of conditioned radioactive wastes with negligible heat generation was prognosticated. According to this forecast, the waste package volume will be approximately in the order of 218200 m 3 up to the year 2000. In 1986 a capacity of about 97500 m 3 for the interim storage of radioactive wastes was available in the Federal Republic of Germany. On December 31, 1986, this capacity was utilized by unconditioned and conditioned radioactive wastes at an average of about 38%. It may be concluded from the data on the expected amount of radioactive wastes with negligible heat generation and on the utilization factor of the interim storage facilities that no bottlenecks are to be assumed up to the planned operation of the Konrad repository. (orig./RB) [de

  6. Preliminary assessment of blending Hanford tank wastes

    International Nuclear Information System (INIS)

    Geeting, J.G.H.; Kurath, D.E.

    1993-03-01

    A parametric study of blending Hanford tank wastes identified possible benefits from blending wastes prior to immobilization as a high level or low level waste form. Track Radioactive Components data were used as the basis for the single-shell tank (SST) waste composition, while analytical data were used for the double-shell tank (DST) composition. Limiting components were determined using the existing feed criteria for the Hanford Waste Vitrification Plant (HWVP) and the Grout Treatment Facility (GTF). Results have shown that blending can significantly increase waste loading and that the baseline quantities of immobilized waste projected for the sludge-wash pretreatment case may have been drastically underestimated, because critical components were not considered. Alternatively, the results suggest further review of the grout feed specifications and the solubility of minor components in HWVP borosilicate glass. Future immobilized waste estimates might be decreased substantially upon a thorough review of the appropriate feed specifications

  7. Preliminary assessment of blending Hanford tank wastes

    Energy Technology Data Exchange (ETDEWEB)

    Geeting, J.G.H.; Kurath, D.E.

    1993-03-01

    A parametric study of blending Hanford tank wastes identified possible benefits from blending wastes prior to immobilization as a high level or low level waste form. Track Radioactive Components data were used as the basis for the single-shell tank (SST) waste composition, while analytical data were used for the double-shell tank (DST) composition. Limiting components were determined using the existing feed criteria for the Hanford Waste Vitrification Plant (HWVP) and the Grout Treatment Facility (GTF). Results have shown that blending can significantly increase waste loading and that the baseline quantities of immobilized waste projected for the sludge-wash pretreatment case may have been drastically underestimated, because critical components were not considered. Alternatively, the results suggest further review of the grout feed specifications and the solubility of minor components in HWVP borosilicate glass. Future immobilized waste estimates might be decreased substantially upon a thorough review of the appropriate feed specifications.

  8. Process Waste Assessment for the Plotting and Digitizing Support Laboratory

    International Nuclear Information System (INIS)

    Phillips, N.M.

    1994-04-01

    This Process Waste Assessment was conducted to evaluate the Plotting and Digitizing Support Laboratory, located in Building 913, Room 157. It documents the processes, identifies the hazardous chemical waste streams generated by these processes, recommends possible ways to minimize waste, and serves as a reference for future assessments of this facility

  9. Criticality safety of high-level tank waste

    International Nuclear Information System (INIS)

    Rogers, C.A.

    1995-01-01

    Radioactive waste containing low concentrations of fissile isotopes is stored in underground storage tanks on the Hanford Site in Washington State. The goal of criticality safety is to ensure that this waste remains subcritical into the indefinite future without supervision. A large ratio of solids to plutonium provides an effective way of ensuring a low plutonium concentration. Since the first waste discharge, a program of audits and appraisals has ensured that operations are conducted according to limits and controls applied to them. In addition, a program of surveillance and characterization maintains watch over waste after discharge

  10. Waste Immobilisation Plant (WIP), Trombay

    International Nuclear Information System (INIS)

    Kaushik, C.P.; Agarwal, K.

    2017-01-01

    Waste Immobilization Plant (WIP), Trombay is designed and constructed for the management of radioactive liquid wastes generated during reprocessing of spent nuclear fuel from research reactors at Bhabha Atomic Research Centre. In common with such facilities elsewhere, the objective here is to manage the wastes in such a way as to protect human health and the environment and to limit any burden on future generations. The plant has several facilities for the handling and treatment of the three classes of waste, viz., high, intermediate and low level, a classification based on their radioactivity content. In keeping with the general objective of radioactive waste management, the focus is on concentration and confinement of radioactivity. Strict adherence to the universal principles of radiation protection during operation of the plant ensures that radiation exposure is always kept as low as reasonably achievable (ALARA) under the prescribed limits

  11. Hospital Waste Management - Case Study

    Directory of Open Access Journals (Sweden)

    Beatriz Edra

    2017-07-01

    Full Text Available The importance of waste management in hospitals is indisputable in preserving the environment and protecting public health, but management models are rarely discussed. This study presents the legal and conceptual frameworks of good waste management practices applicable to hospitals and associated indicators. As a case study, the overall performance of Hospital Centre of São João, in Porto, was analysed based on published reports. Data on the production of waste in their different typologies were collected from 2010 to 2016, enabling a correlation of the waste production with the kg/bed/day indicator. The aim of this study was to gather data and discuss trends in a real scenario of evolution over a six-year period in order to contribute to a future research proposal on indicators that can be used as reference for benchmarking the construction of methodological guides for hospital waste management.

  12. Food waste and the food-energy-water nexus: A review of food waste management alternatives.

    Science.gov (United States)

    Kibler, Kelly M; Reinhart, Debra; Hawkins, Christopher; Motlagh, Amir Mohaghegh; Wright, James

    2018-04-01

    Throughout the world, much food produced is wasted. The resource impact of producing wasted food is substantial; however, little is known about the energy and water consumed in managing food waste after it has been disposed. Herein, we characterize food waste within the Food-Energy-Water (FEW) nexus and parse the differential FEW effects of producing uneaten food and managing food loss and waste. We find that various food waste management options, such as waste prevention, landfilling, composting, anaerobic digestion, and incineration, present variable pathways for FEW impacts and opportunities. Furthermore, comprehensive sustainable management of food waste will involve varied mechanisms and actors at multiple levels of governance and at the level of individual consumers. To address the complex food waste problem, we therefore propose a "food-waste-systems" approach to optimize resources within the FEW nexus. Such a framework may be applied to devise strategies that, for instance, minimize the amount of edible food that is wasted, foster efficient use of energy and water in the food production process, and simultaneously reduce pollution externalities and create opportunities from recycled energy and nutrients. Characterization of FEW nexus impacts of wasted food, including descriptions of dynamic feedback behaviors, presents a significant research gap and a priority for future work. Large-scale decision making requires more complete understanding of food waste and its management within the FEW nexus, particularly regarding post-disposal impacts related to water. Copyright © 2018 Elsevier Ltd. All rights reserved.

  13. Disaster waste management: A review article

    International Nuclear Information System (INIS)

    Brown, Charlotte; Milke, Mark; Seville, Erica

    2011-01-01

    Depending on their nature and severity, disasters can create large volumes of debris and waste. The waste can overwhelm existing solid waste management facilities and impact on other emergency response and recovery activities. If poorly managed, the waste can have significant environmental and public health impacts and can affect the overall recovery process. This paper presents a system overview of disaster waste management based on existing literature. The main literature available to date comprises disaster waste management plans or guidelines and isolated case studies. There is ample discussion on technical management options such as temporary storage sites, recycling, disposal, etc.; however, there is little or no guidance on how these various management options are selected post-disaster. The literature does not specifically address the impact or appropriateness of existing legislation, organisational structures and funding mechanisms on disaster waste management programmes, nor does it satisfactorily cover the social impact of disaster waste management programmes. It is envisaged that the discussion presented in this paper, and the literature gaps identified, will form a basis for future comprehensive and cohesive research on disaster waste management. In turn, research will lead to better preparedness and response to disaster waste management problems.

  14. The waste disposal facility in the Aube District

    International Nuclear Information System (INIS)

    Torres, Patrice

    2013-06-01

    The waste disposal facility in the Aube district is the second surface waste disposal facility built in France. It is located in the Aube district, and has been operated by Andra since 1992. With a footprint of 95 hectares, it is licensed for the disposal of 1 million cubic meters of low- and intermediate-level, short-lived waste packages. The CSA is located a few kilometers away another Andra facility, currently in operation for very-low-level waste, and collection and storage of non-nuclear power waste (the Cires). Contents: Andra in the Aube district, an exemplary industrial operator - The waste disposal facility in the Aube district (CSA); Low- and intermediate-level, short-lived radioactive waste (LILW-SL); The LILW-SL circuit; Protecting present and future generations

  15. Considerations in reviewing the waste volume reduction program in a large utility

    International Nuclear Information System (INIS)

    Kohout, R.; Calzolari, L.M.

    1987-01-01

    A program is underway at Ontario Hydro to establish a desirable future scheme for central processing/volume reduction of solid radioactive Low-Level Wastes (LLW) prior to their placement into the centralized storage, and in the future into a disposal facility. The approach being investigated is to furnish the current Waste Volume Reduction Facility (WVRF) with state-of-art processes, reclassify the waste categories and segregate the wastes such that each volume reduction (VR) process is then applied where it would be most effective. The ''optimized'' approach is then compared with other, specific schemes, which basically differ in that each scheme omits one of the major VR processes, thus allowing the next most effective process to take over its role. Each scheme is assessed quantitatively from the viewpoint of cost and VR effectiveness, and qualitatively from the viewpoint of resultant waste form. The economic assessments take into consideration the long term (20 year) impact of selected VR schemes on the overall waste management cost, including construction and operation of the storage facility. This paper highlights the overall study, includes the major results, and identifies aspects that need to be addressed in the selection of a desirable combination of VR processes in absence of knowledge of future waste disposal costs

  16. Reevaluation Of Vitrified High-Level Waste Form Criteria For Potential Cost Savings At The Defense Waste Processing Facility

    International Nuclear Information System (INIS)

    Ray, J. W.; Marra, S. L.; Herman, C. C.

    2013-01-01

    At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form

  17. Nuclear waste disposal: Can there be a resolution? Past problems and future solutions

    Energy Technology Data Exchange (ETDEWEB)

    Ahearne, J [Scientific Research Society, Sigma Xi, Research Triangle Park, NC (United States)

    1990-07-01

    Why does the high level waste problem have to be solved now? There are perhaps three answers to that question. First, to have a recovery of nuclear power. But a lack of resolution of the high level waste problem is not the principal reason that nuclear power has foundered and, consequently, solving it will not automatically revive nuclear power. However, if the nuclear industry is adamantly convinced that this is the key to reviving nuclear power, then the nuclear industry should demonstrate its conviction by putting much greater effort into resolving the high level waste problem technically, not through public relations. For example, a substantial effort on the actinide burning approach might demonstrate, in the old American phrase, 'putting your money where your mouth is'. Second, the high level waste problem must be solved now because it is a devil's brew. However, chemical wastes last longer, as we all know, than do the radioactive wastes. As one expert has noted: 'There is real risk in nuclear power, just as there is real risk in coal power.... For some of [these risks], like the greenhouse effect, the potential damage is devastating. While for others, like nuclear accidents, the risk is limited, but imaginations are not. For still others, like the risk posed by a high-level waste repository, there is essentially nothing outside the imagination of the gullible.' Furthermore, any technical solution or any solution to a risky problem requires one to think carefully. It is often better to do it right than quickly. A third reason for requiring it to be solved right now is that HLW disposal is a major technical problem blocking a potentially valuable energy source. But we need a new solution. The current solutions are not working. I believe that we ought to recognize the failure of the geologic repository approach. I believe the federal government should identify, with industry's assistance, the best techniques for surface storage. Some federal locations should be

  18. Nuclear waste disposal: Can there be a resolution? Past problems and future solutions

    International Nuclear Information System (INIS)

    Ahearne, J.

    1990-01-01

    Why does the high level waste problem have to be solved now? There are perhaps three answers to that question. First, to have a recovery of nuclear power. But a lack of resolution of the high level waste problem is not the principal reason that nuclear power has foundered and, consequently, solving it will not automatically revive nuclear power. However, if the nuclear industry is adamantly convinced that this is the key to reviving nuclear power, then the nuclear industry should demonstrate its conviction by putting much greater effort into resolving the high level waste problem technically, not through public relations. For example, a substantial effort on the actinide burning approach might demonstrate, in the old American phrase, 'putting your money where your mouth is'. Second, the high level waste problem must be solved now because it is a devil's brew. However, chemical wastes last longer, as we all know, than do the radioactive wastes. As one expert has noted: 'There is real risk in nuclear power, just as there is real risk in coal power.... For some of [these risks], like the greenhouse effect, the potential damage is devastating. While for others, like nuclear accidents, the risk is limited, but imaginations are not. For still others, like the risk posed by a high-level waste repository, there is essentially nothing outside the imagination of the gullible.' Furthermore, any technical solution or any solution to a risky problem requires one to think carefully. It is often better to do it right than quickly. A third reason for requiring it to be solved right now is that HLW disposal is a major technical problem blocking a potentially valuable energy source. But we need a new solution. The current solutions are not working. I believe that we ought to recognize the failure of the geologic repository approach. I believe the federal government should identify, with industry's assistance, the best techniques for surface storage. Some federal locations should be

  19. Directions in low-level radioactive-waste management. Planning state policy on low-level radioactive waste

    International Nuclear Information System (INIS)

    1982-10-01

    The majority of states face a growing problem in the management of low-level radioactive waste generated within their borders. The current uncertainty regarding the availability of disposal sites for these waste products exacerbates their increasing generation rate. The purpose of this publication is to assist state governments in planning effective policy to address these problems. Background information is presented on the current situation, the responsibilities of state government, and the assistance available to states from federal agencies and national groups. The document then focuses on state policy planning, including: (a) methodology for assessing a state's current waste management status and for projecting future needs, (b) consideration of waste management options for a state, and (c) insight into the possible effects and implications of planned policies. This information is intended primarily for state officials - executive, legislative, and agency - and does not include detailed technical information on waste characteristics or handling techniques

  20. Prospects for vitrification of mixed wastes at ANL-E

    International Nuclear Information System (INIS)

    Mazer, J.; No, Hyo.

    1993-01-01

    This report summarizes a study evaluating the prospects for vitrification of some of the mixed wastes at ANL-E. This project can be justified on the following basis: Some of ANL-E's mixed waste streams will be stabilized such that they can be treated as a low-level radioactive waste. The expected volume reduction that results during vitrification will significantly reduce the overall waste volume requiring disposal. Mixed-waste disposal options currently used by ANL-E may not be permissible in the near future without treatment technologies such as vitrification

  1. Monitoring of radioactive wastes

    International Nuclear Information System (INIS)

    Houriet, J.Ph.

    1982-08-01

    The estimation of risks presented by final disposal of radioactive wastes depends, among other things, on what is known of their radioisotope content. The first aim of this report is to present the current state of possibilities for measuring (monitoring) radionuclides in wastes. The definition of a global monitoring system in the framework of radioactive waste disposal has to be realized, based on the information presented here, in accordance with the results of work to come and on the inventory of wastes to be stored. Designed for direct measurement of unpackaged wastes and for control of wastes ready to be stored, the system would ultimately make it possible to obtain all adaquate information about their radioisotope content with regard to the required disposal safety. The second aim of this report is to outline the definition of such a global system of monitoring. Designed as a workbase and reference source for future work by the National Cooperative for the Storage of Radioactive Waste on the topic of radioactive waste monitoring, this report describes the current situation in this field. It also makes it possible to draw some preliminary conclusions and to make several recommendations. Centered on the possibilities of current and developing techniques, it makes evident that a global monitoring system should be developed. However, it shows that the monitoring of packaged wastes will be difficult, and should be avoided as far as possible, except for control measurements

  2. Radioactive waste management centers: an approach

    International Nuclear Information System (INIS)

    Lotts, A.L.

    1980-01-01

    Radioactive waste management centers would satisfy the need for a cost-effective, sound management system for nuclear wastes by the industry and would provide a well integrated solution which could be understood by the public. The future demands for nuclear waste processing and disposal by industry and institutions outside the United States Government are such that a number of such facilities are required between now and the year 2000. Waste management centers can be organized around two general needs in the commercial sector: (1) the need for management of low-level waste generated by nuclear power plants, the once-through nuclear fuel cycle production facilities, from hospitals, and other institutions; and (2) more comprehensive centers handling all categories of nuclear wastes that would be generated by a nuclear fuel recycle industry. The basic technology for radioactive waste management will be available by the time such facilities can be deployed. This paper discusses the technical, economic, and social aspects of organizing radioactive waste managment centers and presents a strategy for stimulating their development

  3. TMI abnormal wastes disposal options

    International Nuclear Information System (INIS)

    Ayers, A.L. Jr.

    1984-03-01

    A substantial quantity of high beta-gamma/high-TRU contaminated wastes are expected from cleanup activities of Unit 2 of the Three Mile Island Nuclear Power Station. Those wastes are not disposable because of present regulatory constraints. Therefore, they must be stored temporarily. This paper discusses three options for storage of those wastes at the Idaho National Engineering Laboratory: (1) storage in temporary storage casks; (2) underground storage in vaults; and (3) storage in silos at a hot shop. Each option is analyzed and evaluated. Also included is a discussion of future disposal strategies, which might be pursued when a suitable federal or commercial repository is built

  4. Solid low-level waste forecasting guide

    International Nuclear Information System (INIS)

    Templeton, K.J.; Dirks, L.L.

    1995-03-01

    Guidance for forecasting solid low-level waste (LLW) on a site-wide basis is described in this document. Forecasting is defined as an approach for collecting information about future waste receipts. The forecasting approach discussed in this document is based solely on hanford's experience within the last six years. Hanford's forecasting technique is not a statistical forecast based upon past receipts. Due to waste generator mission changes, startup of new facilities, and waste generator uncertainties, statistical methods have proven to be inadequate for the site. It is recommended that an approach similar to Hanford's annual forecasting strategy be implemented at each US Department of Energy (DOE) installation to ensure that forecast data are collected in a consistent manner across the DOE complex. Hanford's forecasting strategy consists of a forecast cycle that can take 12 to 30 months to complete. The duration of the cycle depends on the number of LLW generators and staff experience; however, the duration has been reduced with each new cycle. Several uncertainties are associated with collecting data about future waste receipts. Volume, shipping schedule, and characterization data are often reported as estimates with some level of uncertainty. At Hanford, several methods have been implemented to capture the level of uncertainty. Collection of a maximum and minimum volume range has been implemented as well as questionnaires to assess the relative certainty in the requested data

  5. An example of toxic effluents treatment: nuclear waste vitrification

    International Nuclear Information System (INIS)

    Moncouyoux, J.P.; Teulon, F.

    1993-01-01

    The management of radioactive waste has to aim to avoid to bring nuisances to future generations whom industrial people, public authorities would be responsible. The French way of doing in radioactive waste storage is called multi-barriers, to forbid or limit radionuclides migration to the biosphere. This containment system is composed of three barriers: the waste packaging, the storage and the site or geological barrier. This way of doing can also be used for toxic industrial waste. 4 refs

  6. Initial experience with a new articulating energy device for laparoscopic liver resection.

    Science.gov (United States)

    Berber, Eren; Akyuz, Muhammet; Aucejo, Federico; Aliyev, Shamil; Aksoy, Erol; Birsen, Onur; Taskin, Eren

    2014-03-01

    Although significant advances have been made in laparoscopic liver resection (LLR), most techniques still rely on multiple energy devices and staplers, which increase operative costs. The aim of this study was to report the initial results of a new multifunctional energy device for hepatic parenchymal transection. Fourteen patients who underwent LLR using this new device were compared to 20 patients who had LLR using current laparoscopic techniques (CL). Data were collected prospectively. The groups were similar demographics and tumor type and size. Although the type of resection was similar between the groups, the parenchymal transection time was less in the Caiman group (32 ± 5 vs. 63 ± 4 min, respectively, p = 0.0001). The operative time was similar (194 ± 21 vs. 233 ± 16 min, respectively, p = 0.158). There was reduction of the number of advanced instrumentation used in the Caiman group, including the staplers. Estimated blood loss, size of surgical margin, and hospital stay were similar. There was no mortality, and morbidity was 7 % in the Caiman and 20 % in the CL group. This initial study shows that the new device is safe and efficient for LLR. Its main advantage is shortening of hepatic parenchymal transection time. This has implications for increasing efficiency and cost saving in LLR.

  7. The Civilisation Biorefinery - A Future Approach for Material and Energy Recovery from Regional Organic Waste

    International Nuclear Information System (INIS)

    Koerner, I.

    2010-01-01

    The future shortage of energy and raw materials as well as the problems on climate protection are challenges for which a solution is imperative. For efficient utilizing organic liquid and solid wastes which are generated in a city, a city itself could become a civilisation biorefinery. The output will be various energetic and material products, which can be used in the city or in the surrounding of the city. Depending on the nature of the various urban input materials, they need to be fed in to biorefineries adapted to the substrate type. The separate substrate-specific biorefineries may be at central or decentralised locations within the city. Moreover, since the residues from one system can be used in others as input, mutual networking is of importance. To facilitate efficient valorification, bioresources and the type of biorefinery need to be optimally matched. That also means that at the collection stage already, the material properties of the bioresource must be taken into account and where appropriate, new collection systems introduced, or consideration should be given to technical processes for separation of mixtures of materials. Extremely differing cascades will be appropriate for the various regional situations. For this reason, the evaluation of alternative schemes will be seen as very significant. Additional important points are the suitability of new measures or processes for integration into existing regional structures, as well as the logistics aspects, including the question of whether bioconversion processes should be conducted centrally or in decentralised locations. In Germany, considerable amounts of biowaste are available today and in the future which, until now, were almost entirely composted. The possibilities of anaerobic fermentation are gaining more and more in importance. Aerobic and anaerobic treatments of biowaste are more and more combined within the scope of a win-win situation. These technologies will be important parts of a

  8. Radioactive Waste Generation in Pyro-SFR Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Gao, Fanxing; Park, Byung Heung; Ko, Won Il

    2011-01-01

    Which nuclear fuel cycle option to deploy is of great importance in the sustainability of nuclear power. SFR fuel cycle employing pyroprocessing (named as Pyro- SFR Cycle) is one promising fuel cycle option in the near future. Radioactive waste generation is a key criterion in nuclear fuel cycle system analysis, which considerably affects the future development of nuclear power. High population with small territory is one special characteristic of ROK, which makes the waste management pretty important. In this study, particularly the amount of waste generation with regard to the promising advanced fuel cycle option was evaluated, because the difficulty of deploying an underground repository for HLW disposal requires a longer time especially in ROK

  9. Assessment for the management of NORM wastes in conventional hazardous and nonhazardous waste landfills

    Energy Technology Data Exchange (ETDEWEB)

    Mora, Juan C., E-mail: jc.mora@ciemat.es [Unit for Radiation Protection of the Public and the Environment (PRPYMA), CIEMAT, Avda. Complutense, 40, 28040 Madrid (Spain); Energy Engineering Department, Power Engineering, Nuclear Area, ETSII, UNED (Spain); Baeza, Antonio [LARUEX, Dpt. Applied Physics, Faculty of Veterinary Science, University of Extremadura, Avda. Universidad, s/n, 10071 Cáceres (Spain); Robles, Beatriz [Unit for Radiation Protection of the Public and the Environment (PRPYMA), CIEMAT, Avda. Complutense, 40, 28040 Madrid (Spain); Sanz, Javier [Energy Engineering Department, Power Engineering, Nuclear Area, ETSII, UNED (Spain)

    2016-06-05

    Highlights: • Before 2010 NORM waste is managed as non-radioactive, disposed in landfills. • After 2010 radiological impact of the management of NORM wastes must be assessed. • Quantities that can be disposed in hazardous or non-hazardous landfills are given. • Uncertainty analysis is included to provide consistency to the calculations. - Abstract: Naturally Occurring Radioactive Materials (NORM) wastes are generated in huge quantities in several industries and their management has been carried out under considerations of industrial non-radioactive wastes, before the concern on the radioactivity content was included in the legislation. Therefore these wastes were conditioned using conventional methods and the waste disposals were designed to isolate toxic elements from the environment for long periods of time. Spanish regulation for these conventional toxic waste disposals includes conditions that assure adequate isolation to minimize the impact of the wastes to the environment in present and future conditions. After 1996 the radiological impact of the management of NORM wastes is considered and all the aspects related with natural radiations and the radiological control regarding the management of residues from NORM industries were developed in the new regulation. One option to be assessed is the disposal of NORM wastes in hazardous and non-hazardous waste disposals, as was done before this new regulation. This work analyses the management of NORM wastes in these landfills to derive the masses that can be disposed without considerable radiological impact. Generic dose assessments were carried out under highly conservative hypothesis and a discussion on the uncertainty and variability sources was included to provide consistency to the calculations.

  10. Assessment for the management of NORM wastes in conventional hazardous and nonhazardous waste landfills

    International Nuclear Information System (INIS)

    Mora, Juan C.; Baeza, Antonio; Robles, Beatriz; Sanz, Javier

    2016-01-01

    Highlights: • Before 2010 NORM waste is managed as non-radioactive, disposed in landfills. • After 2010 radiological impact of the management of NORM wastes must be assessed. • Quantities that can be disposed in hazardous or non-hazardous landfills are given. • Uncertainty analysis is included to provide consistency to the calculations. - Abstract: Naturally Occurring Radioactive Materials (NORM) wastes are generated in huge quantities in several industries and their management has been carried out under considerations of industrial non-radioactive wastes, before the concern on the radioactivity content was included in the legislation. Therefore these wastes were conditioned using conventional methods and the waste disposals were designed to isolate toxic elements from the environment for long periods of time. Spanish regulation for these conventional toxic waste disposals includes conditions that assure adequate isolation to minimize the impact of the wastes to the environment in present and future conditions. After 1996 the radiological impact of the management of NORM wastes is considered and all the aspects related with natural radiations and the radiological control regarding the management of residues from NORM industries were developed in the new regulation. One option to be assessed is the disposal of NORM wastes in hazardous and non-hazardous waste disposals, as was done before this new regulation. This work analyses the management of NORM wastes in these landfills to derive the masses that can be disposed without considerable radiological impact. Generic dose assessments were carried out under highly conservative hypothesis and a discussion on the uncertainty and variability sources was included to provide consistency to the calculations.

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

    International Nuclear Information System (INIS)

    1994-10-01

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

  12. Future Climate Analysis

    International Nuclear Information System (INIS)

    James Houseworth

    2001-01-01

    This Analysis/Model Report (AMR) documents an analysis that was performed to estimate climatic variables for the next 10,000 years by forecasting the timing and nature of climate change at Yucca Mountain (YM), Nevada (Figure 1), the site of a potential repository for high-level radioactive waste. The future-climate estimates are based on an analysis of past-climate data from analog meteorological stations, and this AMR provides the rationale for the selection of these analog stations. The stations selected provide an upper and a lower climate bound for each future climate, and the data from those sites will provide input to the infiltration model (USGS 2000) and for the total system performance assessment for the Site Recommendation (TSPA-SR) at YM. Forecasting long-term future climates, especially for the next 10,000 years, is highly speculative and rarely attempted. A very limited literature exists concerning the subject, largely from the British radioactive waste disposal effort. The discussion presented here is one method, among many, of establishing upper and lower bounds for future climate estimates. The method used here involves selecting a particular past climate from many past climates, as an analog for future climate. Other studies might develop a different rationale or select other past climates resulting in a different future climate analog. Revision 00 of this AMR was prepared in accordance with the ''Work Direction and Planning Document for Future Climate Analysis'' (Peterman 1999) under Interagency Agreement DE-AI08-97NV12033 with the U.S. Department of Energy (DOE). The planning document for the technical scope, content, and management of ICN 01 of this AMR is the ''Technical Work Plan for Unsaturated Zone (UZ) Flow and Transport Process Model Report'' (BSC 2001a). The scope for the TBV resolution actions in this ICN is described in the ''Technical Work Plan for: Integrated Management of Technical Product Input Department''. (BSC 2001b, Addendum B

  13. Future Climate Analysis

    Energy Technology Data Exchange (ETDEWEB)

    James Houseworth

    2001-10-12

    This Analysis/Model Report (AMR) documents an analysis that was performed to estimate climatic variables for the next 10,000 years by forecasting the timing and nature of climate change at Yucca Mountain (YM), Nevada (Figure 1), the site of a potential repository for high-level radioactive waste. The future-climate estimates are based on an analysis of past-climate data from analog meteorological stations, and this AMR provides the rationale for the selection of these analog stations. The stations selected provide an upper and a lower climate bound for each future climate, and the data from those sites will provide input to the infiltration model (USGS 2000) and for the total system performance assessment for the Site Recommendation (TSPA-SR) at YM. Forecasting long-term future climates, especially for the next 10,000 years, is highly speculative and rarely attempted. A very limited literature exists concerning the subject, largely from the British radioactive waste disposal effort. The discussion presented here is one method, among many, of establishing upper and lower bounds for future climate estimates. The method used here involves selecting a particular past climate from many past climates, as an analog for future climate. Other studies might develop a different rationale or select other past climates resulting in a different future climate analog. Revision 00 of this AMR was prepared in accordance with the ''Work Direction and Planning Document for Future Climate Analysis'' (Peterman 1999) under Interagency Agreement DE-AI08-97NV12033 with the U.S. Department of Energy (DOE). The planning document for the technical scope, content, and management of ICN 01 of this AMR is the ''Technical Work Plan for Unsaturated Zone (UZ) Flow and Transport Process Model Report'' (BSC 2001a). The scope for the TBV resolution actions in this ICN is described in the ''Technical Work Plan for: Integrated Management of Technical

  14. Mixed and low-level waste treatment facility project. Volume 3, Waste treatment technologies (Draft)

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  15. Integrated solid waste management in megacities

    Directory of Open Access Journals (Sweden)

    M.A. Abdoli

    2016-05-01

    Full Text Available Rapid urbanization and industrialization, population growth and economic growth in developing countries make management of municipal solid waste more complex comparing with developed countries. Furthermore, the conventional municipal solid waste management approach often is reductionists, not tailored to handle complexity. Therefore, the need to a comprehensive and multi-disciplinary approach regarding the municipal solid waste management problems is increasing. The concept of integrated solid waste management is accepted for this aim all over the world. This paper analyzes the current situation as well as opportunities and challenges regarding municipal solid waste management in Isfahan according to the integrated solid waste management framework in six aspects: environmental, political/legal, institutional, socio-cultural, financial/economic, technical and performance aspects. Based on the results obtained in this analysis, the main suggestions for future integrated solid waste management of Isfahan are as i promoting financial sustainability by taking the solid waste fee and reducing the expenses through the promoting source collection of recyclable materials, ii improving compost quality and also marketing the compost products simultaneously, iii promoting the private sector involvements throughout the municipal solid waste management system.

  16. CO{sub 2}-emissions from future waste incineration - Sub-Project 5; CO{sub 2}-utslaepp fraan framtida avfallsfoerbraanning - Delprojekt 5 inom projektet Perspektiv paa framtida avfallsbehandling

    Energy Technology Data Exchange (ETDEWEB)

    Bisaillon, Mattias; Detterfelt, Lia; Edner, Stig; Maartenssson, Paal

    2013-09-01

    The use of fossil fuels in Swedish district heating systems has fallen sharply. With continued pressure from society to reduce emissions of greenhouse gases, it is likely that the use of these fuels will decrease further. The major remaining source of emissions of fossil carbon dioxide (CO{sub 2}) from district heating systems 2020 is waste incineration with energy recovery in the form of electricity and heat. The aim of this project was, from two perspectives (stack perspective and system perspective), to analyze future emissions of fossil CO{sub 2} from Swedish waste incineration in the Swedish district heating systems. By studying both perspectives at the same time, the results answer whether changes in emissions in one perspective give similar or opposite effects seen from the other perspective. The purpose was also to make cost estimates for emission reduction measures affecting waste, energy and material production system. These costs were related to the price of allowances in the EU ETS and to the Swedish carbon tax. The project was performed in 2012 as a part of the research project 'Perspectives on sustainable waste treatment'.

  17. Current status of radioactive waste management (RWM) in Thailand

    International Nuclear Information System (INIS)

    Chantaraprachoom, N.

    2003-01-01

    Radioactive wastes in Thailand are mainly from the nuclear application in medicine, industry, agriculture, education and research reactor operation. The quantities of radioactive waste each year are relatively small. About 90 m 3 of processed waste and 7 m 3 unprocessed wastes are now stored at the waste storage facilities in the OAP. Recently the regulation on radioactive waste management was drafted and proposed to the cabinet for approval and to be promulgated as a ministerial regulation. A new nuclear research center, r which comprises 10 MW Research Reactor, Radioisotope Production and Centralized Waste Processing and Storage Facilities, is to be established at Ongkarak district in Nakornnayok province in the future. (author)

  18. Sixth General Radioactive Waste Plan. Planning to the future of ENRESA

    International Nuclear Information System (INIS)

    Espejo Hernandez, J. M.

    2006-01-01

    The Government approved last June 23''rd the Sixth General Radioactive Waste Plan that presents the activities to be carried out by ENRESA in all its field of responsibility to the year 2070. The document considers as one of the principal changes that ENRESA will be restructured to corporate public entity assigned to the Ministry of Industry, Tourism and Trade as well as the need of a Centralised Temporary Storage for the spent fuel and the high level radioactive wastes generated in Spain. Nevertheless, information is provided on the plans for the full decommissioning of the nuclear power plants to complete their operational life and also the economic and financial aspects related to the activities contemplated in the Plan. (Author) 13 refs

  19. Solid Waste Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, D.R.

    1990-08-01

    The objective of the Solid Waste Management Program Plan (SWMPP) is to provide a summary level comprehensive approach for the storage, treatment, and disposal of current and future solid waste received at the Hanford Site (from onsite and offsite generators) in a manner compliant with current and evolving regulations and orders (federal, state, and Westinghouse Hanford Company (Westinghouse Hanford)). The Plan also presents activities required for disposal of selected wastes currently in retrievable storage. The SWMPP provides a central focus for the description and control of cost, scope, and schedule of Hanford Site solid waste activities, and provides a vehicle for ready communication of the scope of those activities to onsite and offsite organizations. This Plan represents the most complete description available of Hanford Site Solid Waste Management (SWM) activities and the interfaces between those activities. It will be updated annually to reflect changes in plans due to evolving regulatory requirements and/or the SWM mission. 8 refs., 9 figs., 4 tabs.

  20. Development of agency guidance for nuclear industry submissions for conditioning intermediate level waste

    International Nuclear Information System (INIS)

    2001-01-01

    The project was carried out by RM Consultants with the overall intention of providing the Environment Agency with a sound basis on which to develop guidance on the conditioning of intermediate level waste (ILW). Waste producers are currently in the process of retrieving and conditioning many of its ILW waste streams. This is at a time where the nature and timing of any future disposal route for these wastes is uncertain. The Agency is concerned that decisions taken on how ILW should be conditioned take into account matters of interest to the Agency, such as the future disposability of wastes, the production of secondary wastes and releases to the environment. This study provides information on the arrangements by which waste producers' proposals for the conditioning of intermediate level waste are assessed, and on the Agency's role in liaising with the Nuclear Installations Inspectorate, waste producers and Nirex. The report makes recommendations on the content and handling of waste producers' proposals in order that the Agency can satisfy itself that the environmental impact of waste conditioning and the disposability of the resultant waste packages is addressed in a timely and consistent manner

  1. Radiological impact of radioactive waste management

    International Nuclear Information System (INIS)

    Beninson, D.J.; Migliori de Beninson, Ambreta.

    1985-01-01

    The radiological impacts from management of wastes from the nuclear fuel cycle have been estimated for several alternative fuel cycle strategies. The impacts are expressed as collective effective dose equivalent commitments. Mill tailings make an important contribution, which depends on the uranium requirements for each reference fuel cycle, being the largest for once-through cycles. Disposal of high level waste or spent fuel is also an important contribution, usually larger for once-through cycle where the entire actinide inventory is disposed off. Although at present conversion and enrichment tailing are not considered wastes, they have assumed to be wastes in the reference cycle. In this case, their relative contribution is significant for fuel cycles using enriched uranium. The totals for waste management and disposal are of the same order of magnitude as the collective dose commitments from occupational and public exposures arising from the operation of the nuclear fuel cycle installations. The incomplete collective dose commitments from waste management and disposal assessed by integrating the collective dose rate over a fixed period of time (usually selected as 500 years), at time when the integral is maximum, are also comparable with the corresponding quantity arising from the operation of the fuel cycle installations. The maximum per caput doses predicted for the far future are small, usually a small fraction of the relevant dose limits. The maximun future doses in the critical groups in the vicinity of the repositories will be very low, of about a few percents of that experienced from the exposure to natural radiation sources. (M.E.L.) [es

  2. The role of weapons production and military waste in the repository selection process

    International Nuclear Information System (INIS)

    Nelson, D.; Hope, J.; Power, W.; Hunter, T.

    1987-01-01

    The decision to commingle defense waste with commercial waste in the nuclear waste repository program has many impacts on that program. There will be more waste to place in the two repositories authorized under the Nuclear Waste Policy Act, more transport miles to get the waste to a repository, and more costs associated with environmental and socio-economic impact mitigation. This paper explores the links between weapons production and military waste, and the repository selection process. The paper first describes the importance of state, tribe and public participation to the acceptance of a repository site selection. The paper then examines the various estimates of amounts of existing and future military nuclear wastes, and how these estimates affect repository siting decisions. The final section addresses the public policy questions which surround this issue. Repository siting may be jeopardized unless there is open public discussion about existing radioactive contamination at military production sites and about future nuclear weapons production. Cost-sharing is considered within this context

  3. Radioactive and mixed waste - risk as a basis for waste classification. Symposium proceedings No. 2

    International Nuclear Information System (INIS)

    1995-01-01

    The management of risks from radioactive and chemical materials has been a major environmental concern in the United states for the past two or three decades. Risk management of these materials encompasses the remediation of past disposal practices as well as development of appropriate strategies and controls for current and future operations. This symposium is concerned primarily with low-level radioactive wastes and mixed wastes. Individual reports were processed separately for the Department of Energy databases

  4. Radioactive and mixed waste - risk as a basis for waste classification. Symposium proceedings No. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-21

    The management of risks from radioactive and chemical materials has been a major environmental concern in the United states for the past two or three decades. Risk management of these materials encompasses the remediation of past disposal practices as well as development of appropriate strategies and controls for current and future operations. This symposium is concerned primarily with low-level radioactive wastes and mixed wastes. Individual reports were processed separately for the Department of Energy databases.

  5. Commercial low-level radioactive waste disposal in the US

    Energy Technology Data Exchange (ETDEWEB)

    Smith, P.

    1995-10-01

    Why are 11 states attempting to develop new low-level radioactive waste disposal facilities? Why is only on disposal facility accepting waste nationally? What is the future of waste disposal? These questions are representative of those being asked throughout the country. This paper attempts to answer these questions in terms of where we are, how we got there, and where we might be going.

  6. Commercial low-level radioactive waste disposal in the US

    International Nuclear Information System (INIS)

    Smith, P.

    1995-01-01

    Why are 11 states attempting to develop new low-level radioactive waste disposal facilities? Why is only on disposal facility accepting waste nationally? What is the future of waste disposal? These questions are representative of those being asked throughout the country. This paper attempts to answer these questions in terms of where we are, how we got there, and where we might be going

  7. Long-lived legacy: Managing high-level and transuranic waste at the DOE Nuclear Weapons Complex. Background paper

    International Nuclear Information System (INIS)

    1991-05-01

    The document focuses on high-level and transuranic waste at the DOE nuclear weapons complex. Reviews some of the critical areas and aspects of the DOE waste problem in order to provide data and further analysis of important issues. Partial contents, High-Level Waste Management at the DOE Weapons Complex, are as follows: High-Level Waste Management: Present and Planned; Amount and Distribution; Current and Potential Problems; Vitrification; Calcination; Alternative Waste Forms for the Idaho National Engineering Laboratory; Technologies for Pretreatment of High-Level Waste; Waste Minimization; Regulatory Framework; Definition of High-Level Waste; Repository Delays and Contingency Planning; Urgency of High-Level Tank Waste Treatment; Technologies for High-Level Waste Treatment; Rethinking the Waste Form and Package; Waste Form for the Idaho National Engineering Laboratory; Releases to the Atmosphere; Future of the PUREX Plant at Hanford; Waste Minimization; Tritium Production; International Cooperation; Scenarios for Future HLW Production. Partial contents of Chapter 2, Managing Transuranic Waste at the DOE Nuclear Weapons Complex, are as follows: Transuranic Waste at Department of Energy Sites; Amount and Distribution; Waste Management: Present and Planned; Current and Potential Problems; Three Technologies for Treating Retrievably Stored Transuranic Waste; In Situ Vitrification; The Applied Research, Development, Demonstration, Testing, and Evaluation Plan (RDDT ampersand E); Actinide Conversion (Transmutation); Waste Minimization; The Regulatory Framework; Definition of, and Standards for, Disposal of Transuranic Waste; Repository Delays; Alternative Storage and Disposal Strategies; Remediation of Buried Waste; The Waste Isolation Pilot Plant; Waste Minimization; Scenarios for Future Transuranic Waste Production; Conditions of No-Migration Determination

  8. Evaluation of solidified high-level waste forms

    International Nuclear Information System (INIS)

    1981-01-01

    One of the objectives of the IAEA waste management programme is to coordinate and promote development of improved technology for the safe management of radioactive wastes. The Agency accomplished this objective specifically through sponsoring Coordinated Research Programmes on the ''Evaluation of Solidified High Level Waste Products'' in 1977. The primary objectives of this programme are to review and disseminate information on the properties of solidified high-level waste forms, to provide a mechanism for analysis and comparison of results from different institutes, and to help coordinate future plans and actions. This report is a summary compilation of the key information disseminated at the second meeting of this programme

  9. Transuranic waste management at Sandia National Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Humphrey, Betty [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bland, Jesse John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2018-01-01

    This paper documents the history of the TRU program at Sandia, previous and current activities associated with TRU material and waste, interfaces with other TRU waste generator sites and the Waste Isolation Pilot Plan (WIPP), and paths forward for TRU material and waste. This document is a snapshot in time of the TRU program and should be updated as necessary, or when significant changes have occurred in the Sandia TRU program or in the TRU regulatory environment. This paper should serve as a roadmap to capture past TRU work so that efforts are not repeated and ground is not lost due to future inactivity and personnel changes.

  10. Feed Materials Production Center Waste Management Plan

    International Nuclear Information System (INIS)

    Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

    1986-01-01

    In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the waste generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF 2 , slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program

  11. ICRP policy for radioactive waste disposal

    International Nuclear Information System (INIS)

    Nenot, Jean-Claude

    2002-01-01

    Jean-Claude Nenot (IPSN, France) gave an overview of recommendations from ICRP during the past 25 years that are relevant to the safety of waste disposal. These recommendations were primarily concerned with public exposure, and suggested that the necessary system of protection should be controlled through the principles of constrained optimisation and prescriptive limits. The principles of justification, optimisation and dose and risk limitation were applicable to waste management. Justification should however be applied to the practice resulting in the generation of waste rather than to waste management per se. As regards optimisation, this should be interpreted in a subtler manner than the simple application of cost-benefit analysis, as an aggregation of very small doses over future world populations would be essentially meaningless. The primary criterion should therefore be the dose to an individual from a relevant critical group, and optimisation should also take account of social and economic factors. The application of dose limits had intrinsic difficulties because of multiple sources, through restrictions determined as a result of monitoring could be envisaged. The approach to dealing with potential future intrusion presented a particular difficulty (as compared to natural processes) because the probability of occurrence could not realistically be determined and therefore a risk-based approach was not recommended. Instead, prospective doses should be assessed against criteria for intervention situations, as proposed in ICRP 82, i.e. action (in terms of a preventative design change, for example) was unlikely to be justifiable at hypothetical and uncertain future dose levels below about 10 mSv/year

  12. Current and future trends in global landfill gas generation and emissions

    International Nuclear Information System (INIS)

    Meadows, M.; Franklin, C.; Campbell, D.

    1996-01-01

    This paper assesses the magnitude and distribution of current and future methane generation and emissions from landfill on a world-wide basis. It also estimates the current and future global potential for energy recovery from landfill methane. The mass of methane emitted from land disposal of wastes in any country depends on the waste management strategy of that country. In turn, the waste management strategy of a country depends on its population size, relative proportion living in rural or urban regions and the economic development of the country. We estimate by 2010 there will be a large increase in global methane emissions from solid wastes disposed on land. This increase will be largely from developing regions of the world. The main factor driving this increase is a population shift from rural to urban areas, particularly in regions of highest population, i.e. China and India. This will lead to a greater concentration of waste generation, in turn leading to increased disposal of wastes in deeper sites. In addition increased industrialisation and improved standard of living in regions of high population, will increase the mass of waste disposed of per person and the degradable carbon content of the waste, i.e. the waste will become more like waste from developed countries. In contrast, methane emissions from waste disposed on land in developed countries is likely to decrease by 2010, mainly as result of increased collection and combustion of landfill methane. (Author)

  13. Radioactive waste disposal - policy and perspectives

    International Nuclear Information System (INIS)

    Roberts, L.E.J.

    1979-01-01

    Methods are discussed that have been developed and could be used for management and disposal of highly active wastes. The characteristics of such waste are, described and the concept of toxic potential is explained. General principles of waste disposal and the various options which have been considered are discussed. Studies on the incorporation of waste into glass, and on container materials are described. Consideration is also given to the requirements of stores and repositories from the aspect of heat dissipation, design, siting, etc. The advantages and disadvantages of the various types of geological formation ie salt, argillaceous deposits, hardrocks, suitable for containment of highly active wastes are examined. Studies carried out on the safety of repositories and an ocean disposal of the waste are summarised. The review ends with a brief account of the status of the vitrification process in the UK and abroad and of future programmes involving geological and related studies. (UK)

  14. 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)

  15. Radioactive waste disposal - policy and perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, L E.J. [UKAEA, Harwell. Atomic Energy Research Establishment

    1979-04-01

    Methods are discussed that have been developed and could be used for management and disposal of highly active wastes. The characteristics of such waste are, described and the concept of toxic potential is explained. General principles of waste disposal and the various options which have been considered are discussed. Studies on the incorporation of waste into glass, and on container materials are described. Consideration is also given to the requirements of stores and repositories from the aspect of heat dissipation, design, siting, etc. The advantages and disadvantages of the various types of geological formation ie salt, argillaceous deposits, hardrocks, suitable for containment of highly active wastes are examined. Studies carried out on the safety of repositories and an ocean disposal of the waste are summarised. The review ends with a brief account of the status of the vitrification process in the UK and abroad and of future programmes involving geological and related studies.

  16. Historical perspective, economic analysis, and regulatory analysis of the impacts of waste partitioning-transmutation on the disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Forsberg, C.W.; Croff, A.G.; Kocher, D.C.

    1990-10-01

    Partitioning-transmutation, sometimes called actinide burning, is an alternative approach to high-level radioactive waste management. It consists of removing long-lived radionuclides from wastes and destroying those radionuclides, thus reducing the long-term hazards of radioactive waste. It was studied in detail in the 1970's. New developments in technology and other factors are resulting in a reexamination of this waste management option. This report consists of three papers which summarize the historical work, update the analysis of the costs of waste disposal, and describe current regulatory requirements which might be impacted by P-T. The papers provide a starting point for future research on P-T. 152 refs., 2 figs., 19 tabs

  17. Basis for criteria for exemption of decommissioning waste

    International Nuclear Information System (INIS)

    Elert, M.; Wiborgh, M.; Bengtsson, A.

    1992-02-01

    The purpose of this study was to provide the Swedish Radiation Protection Institute (SSI) with technical background material to be used as a basis for future decisions concerning exemption levels for decommissioning waste. Simple models have been developed for evaluating the individual doses that may arise from steel waste, concrete waste and non-burnable waste exempted from regulatory control. Two alternatives were studied for the exempted wastes: recycling and disposal in different types of near-surface repositories. The example calculations for the recycling scenarios show that the individual dose obtained is strongly dependent on the exposure time. Thus, the storage of the waste at a scrap yard will give rise to a higher dose than the melting, due to the longer storage time. (28 refs.)

  18. Disaster waste management: a review article.

    Science.gov (United States)

    Brown, Charlotte; Milke, Mark; Seville, Erica

    2011-06-01

    Depending on their nature and severity, disasters can create large volumes of debris and waste. The waste can overwhelm existing solid waste management facilities and impact on other emergency response and recovery activities. If poorly managed, the waste can have significant environmental and public health impacts and can affect the overall recovery process. This paper presents a system overview of disaster waste management based on existing literature. The main literature available to date comprises disaster waste management plans or guidelines and isolated case studies. There is ample discussion on technical management options such as temporary storage sites, recycling, disposal, etc.; however, there is little or no guidance on how these various management options are selected post-disaster. The literature does not specifically address the impact or appropriateness of existing legislation, organisational structures and funding mechanisms on disaster waste management programmes, nor does it satisfactorily cover the social impact of disaster waste management programmes. It is envisaged that the discussion presented in this paper, and the literature gaps identified, will form a basis for future comprehensive and cohesive research on disaster waste management. In turn, research will lead to better preparedness and response to disaster waste management problems. Copyright © 2011 Elsevier Ltd. All rights reserved.

  19. 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

  20. The stakes in managing radioactive wastes

    International Nuclear Information System (INIS)

    Boissier, F.

    2012-01-01

    Like any human activity, the nuclear industry produces wastes. The wastes containing radioactive substances have to be managed as a function of the related risks. Nowadays, 1.300.000 tons of radioactive wastes have accumulated in France. More than 90% of them have short half-lives and are stored on the ground by ANDRA (national agency for the management of radioactive wastes) on 2 sites in the Aube district. ANDRA also designs solutions for stocking the other wastes. Those with long half-lives and very high activity will be stored deep underground (500 meter deep) at Cigeo in the Meuse and Haute-Marne districts. The wastes with long half-lives but low activity (less than 10 5 decays/s for graphite and less than a few thousands decays/s for radium contaminated wastes) will be disposed in a specific way. Implementing a storage solution for each type of waste is necessary for the nuclear industry's sustainability, but it does not dispense the latter from pursuing its efforts to reduce the quantity and danger of the wastes produced. This holds in particular for the so-called 'fourth generation' of future installations. It is important to take stock of all the issues related to managing nuclear wastes

  1. Waste package/repository impact study: Final report

    Energy Technology Data Exchange (ETDEWEB)

    1985-09-01

    The Waste Package/Repository Impact Study was conducted to evaluate the feasibility of using the current reference salt waste package in the salt repository conceptual design. All elements of the repository that may impact waste package parameters, i.e., (size, weight, heat load) were evaluated. The repository elements considered included waste hoist feasibility, transporter and emplacement machine feasibility, subsurface entry dimensions, feasibility of emplacement configuration, and temperature limits. The evaluations are discussed in detail with supplemental technical data included in Appendices to this report, as appropriate. Results and conclusions of the evaluations are discussed in light of the acceptability of the current reference waste package as the basis for salt conceptual design. Finally, recommendations are made relative to the salt project position on the application of the reference waste package as a basis for future design activities. 31 refs., 11 figs., 11 tabs.

  2. Waste package/repository impact study: Final report

    International Nuclear Information System (INIS)

    1985-09-01

    The Waste Package/Repository Impact Study was conducted to evaluate the feasibility of using the current reference salt waste package in the salt repository conceptual design. All elements of the repository that may impact waste package parameters, i.e., (size, weight, heat load) were evaluated. The repository elements considered included waste hoist feasibility, transporter and emplacement machine feasibility, subsurface entry dimensions, feasibility of emplacement configuration, and temperature limits. The evaluations are discussed in detail with supplemental technical data included in Appendices to this report, as appropriate. Results and conclusions of the evaluations are discussed in light of the acceptability of the current reference waste package as the basis for salt conceptual design. Finally, recommendations are made relative to the salt project position on the application of the reference waste package as a basis for future design activities. 31 refs., 11 figs., 11 tabs

  3. Performance assessment for continuing and future operations at solid waste storage area 6

    International Nuclear Information System (INIS)

    1997-09-01

    This revised performance assessment (PA) for the continued disposal operations at Solid Waste Storage Area (SWSA) 6 on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the performance objectives for low-level radioactive waste (LLW) disposal contained in the US Department of Energy (DOE) Order 5820.2A. This revised PA considers disposal operations conducted from September 26, 1988, through the projects lifetime of the disposal facility

  4. Performance assessment for continuing and future operations at solid waste storage area 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This revised performance assessment (PA) for the continued disposal operations at Solid Waste Storage Area (SWSA) 6 on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the performance objectives for low-level radioactive waste (LLW) disposal contained in the US Department of Energy (DOE) Order 5820.2A. This revised PA considers disposal operations conducted from September 26, 1988, through the projects lifetime of the disposal facility.

  5. Industrial aspects of radioactive waste management in Western Europe

    International Nuclear Information System (INIS)

    Marcus, F.R.

    1976-01-01

    Various aspects of waste management are discussed from the viewpoint of the nuclear industry. Future amounts of waste generated in the 15 Foratom countries in Western Europe are estimated. Industrial waste questions--as seen by electricity producers, reprocessors, and waste operators--are discussed; questions concerning decommissioning are also dealt with. A number of recommendations for further action, primarily on the part of national authorities and international organizations, are put forward. One conclusion of the study is that there is no reason for waste-management problems to impede the timely development of nuclear energy as a large-scale industrial activity in Western Europe

  6. Responsibility, fairness and credibility - ethical dilemmas concerning nuclear waste

    International Nuclear Information System (INIS)

    Nilsson, Annika

    1999-01-01

    This book is written with the aim to stimulate discussion and studies on ethical aspects of nuclear waste management. It does not penetrate the technical details of the different stages of waste handling, but concentrates on questions such as our responsibility towards future generations etc

  7. Ceramic and glass radioactive waste forms

    Energy Technology Data Exchange (ETDEWEB)

    Readey, D.W.; Cooley, C.R. (comps.)

    1977-01-01

    This report contains 14 individual presentations and 6 group reports on the subject of glass and polycrystalline ceramic radioactive waste forms. It was the general consensus that the information available on glass as a waste form provided a good basis for planning on the use of glass as an initial waste form, that crystalline ceramic forms could also be good waste forms if much more development work were completed, and that prediction of the chemical and physical stability of the waste form far into the future would be much improved if the basic synergistic effects of low temperature, radiation and long times were better understood. Continuing development of the polycrystalline ceramic forms was recommended. It was concluded that the leach rate of radioactive species from the waste form is an important criterion for evaluating its suitability, particularly for the time period before solidified waste is permanently placed in the geologic isolation of a Federal repository. Separate abstracts were prepared for 12 of the individual papers; the remaining two were previously abstracted.

  8. Thermal treatment for TRU waste sorting

    International Nuclear Information System (INIS)

    Sasaki, Toshiki; Aoyama, Yoshio; Yamashita, Toshiyuki

    2009-03-01

    A thermal treatment that can automatically unpack TRU waste and remove hazardous materials has been developed to reduce the risk of radiation exposure and save operation cost. The thermal treatment is a process of removing plastic wrapping and hazardous material from TRU waste by heating waste at 500 to 700degC. Plastic wrappings of simulated wastes were removed using a laboratory scale thermal treatment system. Celluloses and isoprene rubbers that must be removed from waste for disposal were pyrolyzed by the treatment. Although the thermal treatment can separate lead and aluminum from the waste, a further technical development is needed to separate lead and aluminum. A demonstration scale thermal treatment system that comprises a rotary kiln with a jacket water cooler and a rotating inner cage for lead and aluminum separation is discussed. A clogging prevention system against zinc chloride, a lead and aluminum accumulation system, and a detection system for spray cans that possibly cause explosion and fire are also discussed. Future technology development subjects for the TRU waste thermal treatment system are summarized. (author)

  9. Identification and characterization of radioactive wastes

    International Nuclear Information System (INIS)

    RANDRIAMORA, T.H.

    2007-01-01

    As the goal of the radioactive waste management is to protect human health and the environment, without imposing excessive constraints to the future generations, this work consists with of the identification of the radioactive waste existing in Madagascar, theirs characterizations for their later conditioning and their final storage. In this work, we used a dosimeter GRAETZ X5 C and a portable spectrometer EXPLORANIUM GR 135. These apparatuses have a great advantage at the user level because of their capacity to measure the equivalent dose rate, to identify, search and locate radiocative elements. The establishment of national center for radioactive waste management for the conditioning and the storage of spent sealed sources is the best solution for radioactive waste management in Madagascar. [fr

  10. Ventilation and air conditioning system in waste treatment and storage facilities

    International Nuclear Information System (INIS)

    Kinoshita, Hirotsugu; Sugawara, Kazushige.

    1987-01-01

    So far, the measures concerning the facilities for treating and storing radioactive wastes in nuclear fuel cycle in Japan were in the state which cannot be said to be sufficient. In order to cope with this situation, electric power companies constructed and operated radioactive waste concentration and volume reduction facilities, solid waste storing facilities for drums, high level solid waste storing facilities, spent fuel cask preserving facilities and so on successively in the premises of nuclear power stations, and for the wastes expected in future, the research and the construction plan of the facilities for treating and storing low, medium and high level wastes have been advanced. The ventilation and air conditioning system for these facilities is the important auxiliary system which has the mission of maintaining safe and pleasant environment in the facilities and lowering as far as possible the release of radioactive substances to outside. The outline of waste treatment and storage facilities is explained. The design condition, ventilation and air conditioning method, the features of respective waste treatment and storage facilities, and the problems for the future are described. Hereafter, mechanical ventilation system continues to be the main system, and filters become waste, while the exchange of filters is accompanied by the radiation exposure of workers. (Kako, I.)

  11. Environmental impact assessment of solid waste management in Beijing City, China

    International Nuclear Information System (INIS)

    Zhao Yan; Christensen, Thomas H.; Lu Wenjing; Wu Huayong; Wang Hongtao

    2011-01-01

    The environmental impacts of municipal solid waste management in Beijing City were evaluated using a life-cycle-based model, EASEWASTE, to take into account waste generation, collection, transportation, treatment/disposal technologies, and savings obtained by energy and material recovery. The current system, mainly involving the use of landfills, has manifested significant adverse environmental impacts caused by methane emissions from landfills and many other emissions from transfer stations. A short-term future scenario, where some of the landfills (which soon will reach their capacity because of rising amount of waste in Beijing City) are substituted by incinerators with energy recovery, would not result in significant environmental improvement. This is primarily because of the low calorific value of mixed waste, and it is likely that the incinerators would require significant amounts of auxiliary fuels to support combustion of wet waste. As for the long-term future scenario, efficient source separation of food waste could result in significant environmental improvements, primarily because of increase in calorific value of remaining waste incinerated with energy recovery. Sensitivity analysis emphasized the importance of efficient source separation of food waste, as well as the electricity recovery in incinerators, in order to obtain an environmentally friendly waste management system in Beijing City.

  12. Synroc - progress and future prospects

    International Nuclear Information System (INIS)

    Jostsons, A.

    2001-01-01

    Most of the early development of SYNROC focused on the SYNROC-C formulation for immobilising liquid HLW from the reprocessing of commercial LWR spent fuel. Subsequently, ANSTO has responded to developments in R and D on partitioning and transmutation, excess plutonium disposition and the needs of global remediation programs by developing a variety of titanate ceramic waste forms for specific applications. This paper reviews the progress in the development of titanate ceramics and ceramic/glass composites and addresses the relevance of this work in future radioactive waste management strategies

  13. Waste management in space: a NASA symposium. Special issue

    Science.gov (United States)

    Wydeven, T. (Principal Investigator)

    1991-01-01

    This special issue contains papers from the NASA Symposium on Waste Processing for Advanced Life Support, which was held at NASA Ames Research Center on September 11-13, 1990. Specialists in waste management from academia, government, and industry convened to exchange ideas and advise NASA in developing effective methods for waste management in a Controlled Ecological Life Support System (CELSS). Innovative and well-established methods were presented to assist in developing and managing wastes in closed systems for future long-duration space missions, especially missions to Mars.

  14. Current status and future considerations for a transportation system for spent fuel and radioactive waste

    International Nuclear Information System (INIS)

    Anderson, R.T.; Darr, D.G.; Godfrey, W.L.; Keely, R.B.; Lusk, E.C.; Peterson, R.W.; Ridihalgh, J.L.; Shallo, F.A.; Young, M.

    1978-02-01

    This report is part of the OWI Transportation/Logistics systems analysis of problems associated with shipping these wastes to waste terminal storage facilities. It covers governmental regulations and functional responsibilities, highway and rail transportation status and economic considerations, assessment of present industry capabilities and business-related considerations, important receiving facility considerations, necessary engineering and licensing-related aspects of packaging systems, and essential elements of reprocessing plant waste activities including packaging and transportation

  15. U. K. rad waste management-present status and future plans

    International Nuclear Information System (INIS)

    Eyre, Brian Leonard

    1991-01-01

    It is essential that we demonstrate that the nuclear industry world-wide has the technology to carry out the necessary operations to the highest standards. Management of radioactive wastes requires a range of technical skills, together with a sensitive appreciation of planning issues and of the need for two-way communication with public representatives and politicians. In the UK there is today a well-founded technology in this subject, based upon an overall strategy which has been carefully developed by the nuclear industry. Government and Regulatory Agencies. Large-scale operations of waste processing, packaging, storage and disposal are now taking shape in many countries, so that real experience of plant design, costs and public relations issues is available. In the UK this experience resides with UKAEA, BNFL, Neurox, Nuclear Electric plc, Government Departments and increasingly with private suppliers of process plant and services. This is a subject area in which there is no need for secrecy, so for many years there have been valuable international exchanges. The IAEA, Nea and CAC have all been very active in encouraging and facilitating collaboration.

  16. In situ vitrification on buried waste

    International Nuclear Information System (INIS)

    Bates, S.O.

    1992-01-01

    In situ vitrification (ISV) is being evaluated as a remedial treatment technology for buried mixed and transuranic (TRU) wastes at the Subsurface Disposal Area (SDA) at Idaho National Engineering Laboratory (INEL) and can be related to buried wastes at other Department of Energy (DOE) sites. There are numerous locations around the DOE Complex where wastes were buried in the ground or stored for future burial. The Buried Waste Program (BWP) is conducting a comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) remedial investigation/feasibility study (RI/FS) for the Department of Energy - Field Office Idaho (DOE-ID). As part of the RI/FS, an ISV scoping study on the treatability of the SDA mixed low-level and mixed TRU waste is being performed for applicability to remediation of the waste at the Radioactive Waste Management Complex (RWMC). The ISV project being conducted at the INEL by EG ampersand G Idaho, Inc. consists of a treatability investigation to collect data to satisfy nine CERCLA criteria with regards to the SDA. This treatability investigation involves a series of experiments and related efforts to study the feasibility of ISV for remediation of mixed and TRU waste disposed of at the SDA

  17. Development of polymer concrete radioactive waste management containers

    Energy Technology Data Exchange (ETDEWEB)

    Chung, H.; Lee, M. S.; Ahn, D. H.; Won, H. J.; Kang, H. S.; Lee, H. S.; Lim, S.P.; Kim, Y. E.; Lee, B. O.; Lee, K. P.; Min, B. Y.; Lee, J.K.; Jang, W. S.; Sim, W. B.; Lee, J. C.; Park, M. J.; Choi, Y. J.; Shin, H. E.; Park, H. Y.; Kim, C. Y

    1999-11-01

    A high-integrity radioactive waste container has been developed to immobilize the spent resin wastes from nuclear power plants, protect possible future, inadvertent intruders from damaging radiation. The polymer concrete container is designed to ensure safe and reliable disposal of the radioactive waste for a minimum period of 300 years. A built-in vent system for each container will permit the release of gas. An experimental evaluation of the mechanical, chemical, and biological tests of the container was carried out. The tests showed that the polymer concrete container is adequate for safe disposal of the radioactive wastes. (author)

  18. Public perceptions of aspects of radioactive waste management

    International Nuclear Information System (INIS)

    1985-04-01

    The paper concerns a study of peoples' attitude towards the siting of radioactive waste repositories, carried out by the University of Surrey, United Kingdom. The work has been commissioned by the Department of the Environment as part of its radioactive waste management research programme. The people taking part were asked to mark on a map of Great Britain places they felt radioactive waste repositories would be least objectionable. The degree to which people worried about the technology and the management of radioactive waste disposal was monitored. Questions were asked about storage, disposal and transportation aspects, and about present and future worries. (UK)

  19. National waste terminal storage program bibliography

    International Nuclear Information System (INIS)

    Asher, J.M.

    1977-01-01

    In February 1976, the Energy Research and Development Administration (ERDA) announced a greatly expanded waste management program for defense and commercial radioactive waste. In that announcement, ERDA indicated that the Oak Ridge Operations Office (ORO) of ERDA would have lead responsibility for overall coordination of the expanded commercial geologic disposal program and that an Office of Waste Isolation (OWI) would be created within Union Carbide Corporation-Nuclear Division (UCC-ND) with the responsibility for program management of that activity. This bibliography lists many of the documents authored since 1958 by UCC-ND's technical personnel, consultants, and subcontractors as part of the geologic waste disposal programs at Oak Ridge National Laboratory and the current National Waste Terminal Storage (NWTS) Program. Future editions will contain new documents as well as other prior-year documents which, because of our schedule, we were unable to identify, locate, and include in this first edition. Longer-range plans include broadening the scope of coverage to include documents authored by other NWTS Program participants. This edition, as well as future editions, will list only those documents that have been processed through ERDA's Technical Information Center for public availability from the National Technical Information Service, Springfield, Virginia. Full reference and citation information appears only once, with various indexes provided for the convenience of the user. Report references are arranged by issuing organization with sequencing according to document numbers; references to journal articles and conference proceedings are arranged by issue date

  20. Solid waste management in Macao: Practices and challenges

    International Nuclear Information System (INIS)

    Jin Jianjun; Wang Zhishi; Ran Shenghong

    2006-01-01

    The rapid economic development and population growth in Macao have resulted in a large increase in refuse generated over the past decade. In 2003, the quantity of solid waste generated reached 249,255 tons, corresponding to 1.52 kg/day per capita. This figure has been gradually increasing. Domestic solid waste is the primary source of solid waste generation. The data showed that a considerable amount of the solid waste generated can be recycled and reutilized. Due to Macao's small geographic area and high cost of land, landfilling has the lowest priority for waste disposal. Solid waste incineration has been given a top priority over other waste disposal methods although it is much more expensive. In the last decade, more than 80% of the total waste in Macao was incinerated. However, the incineration capacity of the Macao Incineration Plant is going to reach its saturation earlier than expected. Waste minimization, the establishment of an effective waste collection and disposal fee system, and alternate ways dealing with the limited capacity of waste treatment facilities are regarded to be major challenges in the future

  1. Waste to wealth

    International Nuclear Information System (INIS)

    Sivapalan Kathiravale; Muhd Noor Muhd Yunus

    2010-01-01

    We currently live in a world where depletion of resources is beyond control. The call for sustainable development both environmentally and economically is spelt out loud and clear. Hence, the current and future generations must ensure that all resources shall be preserved, fully utilized and well managed. Waste generation has been part and parcel of man kinds pursuit for development, be it in social or economic activities. Municipal Solid Waste (MSW) is an example of socio-economic activities that entails with waste generation. Generation rates of MSW vary according to the economic and social standing of a country. This in return will also affect the management style of the MSW generated. Generally, the higher income countries generated more waste, recycle more and have the money to employ new technology to treat their waste. As for the lower income countries, the waste generated is more organic in nature, which calls for lesser recycling, whereas disposal is by open dumping. The effects of this naturally would mean that in the lower income countries pollution to the water and air is huge as compare to the more developed countries. However on the other hand, does waste alone generate harmful gasses that pollute the world or does manufacturing, transportation and power production, which is rampant in the more industrialized countries contributing more towards pollution? This subject is argumentative and could be discussed at length. However, the environment cannot wait for the population to debate on the above matter. Action needs to be taken in a world where economic power determines the treatment method. Hence, the idea of recovering all 'wealth' in the waste is essential to ensure that even the poorest countries could benefit from all waste management technologies. For this to work, recycling, reuse and recovery of energy is essential in an integrated approach towards waste management. This would also mean that many environmental disasters could be avoided

  2. Quantity assessment of waste in the dismantlement of liquid waste treatment plant and its actual state

    International Nuclear Information System (INIS)

    Uchiyama, Takafumi; Mitsuhashi, Ishi; Matsumoto, Tetsuo; Morishima, Kayoko; Tanzawa, Tomio

    2016-01-01

    From the progress of decommissioning project work of Tokyo City University Atomic Energy Research Institute, this paper reports the comparison between the actual amount of the waste generated during dismantlement work at liquid waste treatment facilities and the assessment quantity before starting the dismantlement. The quantity assessment was made on the basis of the installation license application, design specifications, drawings, records, history of use, site investigation results, etc. Since this quantity assessment did not take into account the dismantling contents of reservoir concrete, the assessed quantity of non-radioactive waste (NR waste) did not match the sum of actual NR waste. However, if an actually generated quantity of concrete of radioactive waste was added to the quantity assessment as NR waste, the quantity of actually generated NR waste and that of assessed NR waste were nearly consistent, which verified the validity of this assessment. This method is considered to be able to be utilized in the future quantity assessment of decommissioning work and the like. On the other hand, it was found that the number of drums that were actually stored tended to increase more than the estimated number of drum conversion. In old buildings, it is necessary to take into account the generation of waste other than radioactive materials in the quantity assessment stage and dismantlement stage. (A.O.)

  3. Radioactive waste from nuclear power stations and other nuclear facilities

    International Nuclear Information System (INIS)

    Jelinek-Fink, P.

    1976-01-01

    After estimating the amounts of liquid and solid radioactive wastes that will be produced in nuclear power plants, reprocessing plants, by the fuel cycle industry, and in the nuclear research centers in the FRG until 1990, it is reported on the state of technology and on the tendencies in the development of processing radioactive waste. The paper also describes, how waste disposal is managed by those producing radioactive waste (see above), and discusses the future development of the complex of waste disposal from the industry's point of view. (HR/LN) [de

  4. Review of radioactive waste management programs in the United Kingdom

    International Nuclear Information System (INIS)

    Keen, N.J.; Duncan, A.G.

    1982-01-01

    The paper reports progress by the Department of Environment and the nuclear industry in developing and implementing a strategy for the management of radioactive waste in the UK. It outlines the range of possible disposal facilities required to deal with all classes of waste arising from nuclear power generation. The present practices for waste management and the main lines of development by the main waste producers of the plant needed in future are outlined, together with a summary of some of the more generic R and D devoted to treatment, packaging and transport of wastes

  5. Incineration of low level and mixed wastes: 1986

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    The University of California at Irvine, in cooperation with the Department of Energy, American Society of Mechanical Engineers, and chapters of the Health Physics Society, coordinated this conference on the Incineration of Low-Level Radioactive and Mixed Wastes, with the guidance of professionals active in the waste management community. The conference was held in April 22-25, 1986 at Sheraton airport hotel Charlotte, North Carolina. Some of the papers' titles were: Protection and safety of different off-gas treatment systems in radioactive waste incineration; performance assessment of refractory samples in the Los Alamos controlled-Air incinerator; incineration systems for low-level and mixed wastes; incineration of low-level radioactive waste in Switzerland-operational experience and future activities

  6. Knowledge for the future - Time eats information

    International Nuclear Information System (INIS)

    Kornwachs, Klaus

    2015-01-01

    The need to pass knowledge on to future generations is not unique to radioactive waste management. Think, for instance, of chemical waste, space debris, the location of land mines, or the genetic code of manipulated organisms, etc.. In all these cases we have to handle the impacts and effects of technologies over the long term. The time frame of these effects surmounts the lifetime of one generation and more. In order to enable future generations to handle this precarious legacy we need to hand on suitable information. However, this is not enough; we have to facilitate the understanding of the very meaning of this information, too. This can be referred to as a 'wicked problem', since the legacy of the nuclear age is distributed all over the world and huge amounts of wastes have been accumulated. There is not yet any solution available which could reduce the half-life of nuclear waste on a large industrial scale. Information is constantly decaying, e.g. due to copy processes and the limited lifetime of information carriers such as paper, chemical, electronic and nano-storage technologies. For time frames greater than 1 000 years none of the present technologies seems to be long lasting enough or effective by itself. It can be shown that no presently known information and communication technology (ICT) can preserve written or electronically stored information over 4 000 years, say. The preservation effort would have to include the reception, deciphering, and the semantically correct understanding. The decay of information entails the decay of knowledge. This leads to a decrease of possibilities to act. However, we and future generations need this knowledge (including the basics of physics and relevant technology) in order to be able to take action in the future. This task is still unresolved, both for nuclear waste management and for other issues. One can only try to pass knowledge on to future generations via institutions. However, an organisational

  7. 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.

  8. 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.

  9. A generic hazardous waste management training program

    International Nuclear Information System (INIS)

    Carter, R.J.; Karnofsky, B.

    1988-01-01

    The main purpose of this training program element is to familiarize personnel involved in hazardous waste management with the goals of RCRA and how they are to be achieved. These goals include: to protect health and the environment; to conserve valuable material and energy resources; to prohibit future open dumping on the land; to assure that hazardous waste management practices are conducted in a manner which protects human health and the environment; to insure that hazardous waste is properly managed thereby reducing the need for corrective actions in the future; to establish a national policy to reduce or eliminate the generation of hazardous waste, wherever feasible. Another objective of this progam element is to present a brief overview of the RCRA regulations and how they are implemented/enforced by the Environmental Protection Agency (EPA) and each of the fifty states. This element also discusses where the RCRA regulations are published and how they are updated. In addition it details who is responsible for compliance with the regulations. Finally, this part of the training program provides an overview of the activities and materials that are regulated. 1 ref

  10. Optimising waste treatment and energy systems - focusing on spatial and temporal issues

    DEFF Research Database (Denmark)

    Pizarro Alonso, Amalia Rosa; Münster, Marie; Ravn, H.

    The aim of the TOPWASTE project is to evaluate current and future optimal treatment of waste fractions in terms of economy and the environment, with a focus on recycling versus Waste-to-Energy technologies. After optimization of the waste management system, results must be analysed so...

  11. Environmental risks of HBCDD from construction and demolition waste: a contemporary and future issue.

    Science.gov (United States)

    Nie, Zhiqiang; Yang, Ziliang; Fang, Yanyan; Yang, Yufei; Tang, Zhenwu; Wang, Xingrun; Die, Qingqi; Gao, Xingbao; Zhang, Fengsong; Wang, Qi; Huang, Qifei

    2015-11-01

    Hexabromocyclododecane (HBCDD), as one of the most widely used brominated flame retardants (BFRs), is of great concern globally because of its persistence in the environment and negative impacts on humans and animals. HBCDD has been mainly used in flame-retarded expanded (EPS) and extruded (XPS) polystyrene foams for insulation in the construction industry. Most of these products will become a part of the construction and demolition (C&D) waste at the end of their life cycle (30-50 years) which is typically disposed of into landfills or incineration. However, the recycling of this material takes quite a low share compared with landfill and incineration. Consequently, high environmental risks will exist in these disposal approaches due to the HBCDD in C&D waste. Currently, XPS or EPS products containing HBCDD in the construction industry have not reached the end of their life cycle in most countries. Relatively little attention has been paid to this emergency issue by either the government or public. Furthermore, C&D waste is most likely disposed of by direct dumping, simple stacking, or open burning in developing countries. Therefore, this paper highlights the global environmental risks of HBCDD from C&D waste. Areas of research for key problems of HBCDD contained in C&D waste are suggested to help control and finally eliminate the impact.

  12. Design and construction of the defense waste processing facility project at the Savannah River Plant

    International Nuclear Information System (INIS)

    Baxter, R.G.

    1986-01-01

    The Du Pont Company is building for the Department of Energy a facility to vitrify high-level radioactive waste at the Savannah River Plant (SRP) near Aiken, South Carolina. The Defense Waste Processing Facility (DWPF) will solidify existing and future radioactive wastes by immobilizing the waste in Processing Facility (DWPF) will solidify existing and future radioactives wastes by immobilizing the waste in borosilicate glass contained in stainless steel canisters. The canisters will be sealed, decontaminated and stored, prior to emplacement in a federal repository. At the present time, engineering and design is 90% complete, construction is 25% complete, and radioactive processing in the $870 million facility is expected to begin by late 1989. This paper describes the SRP waste characteristics, the DWPF processing, building and equipment features, and construction progress of the facility

  13. Radioactive waste in Federal Germany

    International Nuclear Information System (INIS)

    Brennecke, P.; Schumacher, J.; Warnecke, E.

    1988-01-01

    The Physikalisch-Technische Bundesanstalt (PTB) is responsible for the long-term storage and disposal of radioactive waste according to the Federal Atomic Energy Act. On behalf of the Federal Minister of the Environment, Nature Conservation and Nuclear Safety, since 1985, the PTB has been carrying out annual inquiries into the amounts of radioactive waste produced in the Federal Republic of Germany. Within the scope of this inquiry performed for the preceding year, the amounts of unconditioned and conditioned waste are compiled on a producer- and plant-specific basis. On the basis of the inquiry for 1986 and of data presented to the PTB by the waste producers, future amounts of radioactive waste have been estimated up to the year 2000. The result of this forecast is presented. In the Federal Republic of Germany two sites are under consideration for disposal of radioactive waste. In the abandoned Konrad iron mine in Salzgitter-Bleckenstedt it is intended to dispose of such radioactive waste which has a negligible thermal influence upon the host rock. The Gorleben salt dome is being investigated for its suitability for the disposal of all kinds of solid and solidified radioactive wastes, especially of heat-generating waste. Comparing the estimated amount of radioactive wastes with the capacity of both repositories it may be concluded that the Konrad and Gorleben repositories will provide sufficient capacity to ensure the disposal of all kinds of radioactive waste on a long-term basis in the Federal Republic of Germany. 1 fig., 2 tabs

  14. Reevaluation of Vitrified High-Level Waste Form Criteria for Potential Cost Savings at the Defense Waste Processing Facility - 13598

    Energy Technology Data Exchange (ETDEWEB)

    Ray, J.W. [Savannah River Remediation (United States); Marra, S.L.; Herman, C.C. [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)

    2013-07-01

    At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form. (authors)

  15. New paradigms on how to achieve zero food waste in future cities : Optimizing food use by waste prevention and valorization

    OpenAIRE

    Redlingshofer, Barbara; Guilbert, Stéphane; Fuentes, Claire; Gracieux, Mélanie

    2015-01-01

    Cities currently manage uneaten food and other food system based biowaste quite inefficiently. The organic compound, despite its high nutriment value, is only to a small extent recycled and returned to farm soil and therefore, does not contribute to closing ecological nutrient cycles and to supporting sustainable food production [1]. In the US, over 97% of food waste is estimated to be buried in landfills [2]. Forkes has shown for Toronto that only 4.7% at most of food waste nitrogen (includi...

  16. Interim waste storage for the Integral Fast Reactor

    International Nuclear Information System (INIS)

    Benedict, R.W.; Phipps, R.D.; Condiff, D.W.

    1991-01-01

    The Integral Fast Reactor (IFR), which Argonne National Laboratory is developing, is an innovative liquid metal breeder reactor that uses metallic fuel and has a close coupled fuel recovery process. A pyrochemical process is used to separate the fission products from the actinide elements. These actinides are used to make new fuel for the reactor. As part of the overall IFR development program, Argonne has refurbished an existing Fuel Cycle Facility at ANL-West and is installing new equipment to demonstrate the remote reprocessing and fabrication of fuel for the Experimental Breeder Reactor II (EBR-II). During this demonstration the wastes that are produced will be treated and packaged to produce waste forms that would be typical of future commercial operations. These future waste forms would, assuming Argonne development goals are fulfilled, be essentially free of long half-life transuranic isotopes. Promising early results indicate that actinide extraction processes can be developed to strip these isotopes from waste stream and return them to the IFR type reactors for fissioning. 1 fig

  17. Waste management, decommissioning and environmental restoration for Canada's nuclear activities: 'Current practices and future needs'

    International Nuclear Information System (INIS)

    2006-01-01

    The Canadian Nuclear Society conference on Waste Management, Decommissioning and Environmental Restoration for Canada's Nuclear Activities was held on May 8-11, 2005 in Ottawa, Ontario, Canada. The objective of this Conference was to provide a forum for discussion and exchange of views on the technical, regulatory and social challenges and opportunities in radioactive waste management, nuclear facility decommissioning and environmental restoration activities in Canada. The Conference was organized into several plenary sessions and eight technical tracks: Low- and intermediate-level wastes; Uranium mining and milling wastes; Used nuclear fuel; Decommissioning; Environmental restoration; Policy, economics and social issues; Licensing and regulatory issues; and, Radioactive materials transportation. The three-day Conference involved waste management, decommissioning and environmental technology practitioners; delegates from industry, academia, and government agencies and regulators; consulting engineers; financial and legal experts; and other specialists working in the field. While the Conference had a primarily Canadian focus, about 10 per cent of the submissions received came from foreign and international organizations, which provided insights into how other countries are dealing with similar issues

  18. Los Alamos Plutonium Facility Waste Management System

    International Nuclear Information System (INIS)

    Smith, K.; Montoya, A.; Wieneke, R.; Wulff, D.; Smith, C.; Gruetzmacher, K.

    1997-01-01

    This paper describes the new computer-based transuranic (TRU) Waste Management System (WMS) being implemented at the Plutonium Facility at Los Alamos National Laboratory (LANL). The Waste Management System is a distributed computer processing system stored in a Sybase database and accessed by a graphical user interface (GUI) written in Omnis7. It resides on the local area network at the Plutonium Facility and is accessible by authorized TRU waste originators, count room personnel, radiation protection technicians (RPTs), quality assurance personnel, and waste management personnel for data input and verification. Future goals include bringing outside groups like the LANL Waste Management Facility on-line to participate in this streamlined system. The WMS is changing the TRU paper trail into a computer trail, saving time and eliminating errors and inconsistencies in the process

  19. WASTE MANAGEMENT AT SRS - MAKING IT HAPPEN

    International Nuclear Information System (INIS)

    Heenan, T. F.; Kelly, S.

    2002-01-01

    The past five years have witnessed a remarkable transition in the pace and scope of waste management activities at SRS. At the start of the new M and O contract in 1996, little was being done with the waste generated at the site apart from storing it in readiness for future treatment and disposal. Large volumes of legacy waste, particularly TRU and Low Level Waste, had accumulated over many years of operation of the site's nuclear facilities, and the backlog was increasing. WSRC proposed the use of the talents of the ''best in class'' partners for the new contract which, together with a more commercial approach, was expected to deliver more results without a concomitant increase in cost. This paper charts the successes in the Solid Waste arena and analyzes the basis for success

  20. Past, present and future

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    The development of nuclear power over the past 40 years is outlined, with reactor and fuel cycle choice, opposition, non-proliferation, cost escalation and industrial development all being considered briefly. The current (1986) situation is summarized and future prospects for nuclear power considered in the light of energy demand, public acceptability (especially following accidents), and the nuclear technology now available, including radioactive waste management. The alternatives for producing electricity are discussed. These include buying from other producers, or generating oneself, using nuclear power plants or non-nuclear plants. If nuclear power is chosen then the type of plant to be used is considered. Waste disposal is mentioned briefly. (U.K.)

  1. Radioactive waste from non-power applications in Sweden

    International Nuclear Information System (INIS)

    Haegg, Ann-Christin; Lindbom, Gunilla; Persson, Monica

    2001-01-01

    regulations enable the free release of small amounts of radioactive waste either to the municipal sewage system or for delivering to a municipal dumpsite. Identified issues. It is not possible for the SSI to conduct more than a limited number of inspections. SSI relies on the licensee to inform the SSI when the source is no longer in use. An incitement for this is the annual fee mentioned above. Sources with activity below 500 megaBq from facilities with a summary licence are not accounted for separately and can therefore be difficult to control. The only radioactive waste facility (recognised waste facility) with the capacity and the authorisation for taking care of disused radioactive sources and other forms of radioactive waste from Non-Power applications is Studsvik AB. The future costs for final disposal of this waste is unclear because of the lack of final repository. Studsvik has to make sure that future costs are covered by the fee they charges for taking care of radioactive waste. As the only recognised waste facility Studsvik can freely set the fee for taking care of radioactive waste. If the fee is set too high there's a risk that waste from some unserious license-holder will be lost' or kept in storage. Studsvik has no formal responsibility for taking care of used radioactive sources. It's not unrealistic that Studsvik in the future decides not to accept a specific waste-form. Commercial products: Approximately there are 10 millions fireguards containing about 40 kBq Am-241 in Sweden. The average lifetime of the fireguards is 10 years and implicates that about one million fireguards are disposed of each year. SSI has issued regulations stating that private persons are allowed to occasionally throw a fireguard on municipal dump-sites. Companies are allowed to throw up to five fireguards each month. Identified issues: An assumption for the regulations was that the fireguards were not disposed at the same time nor at the same place. A dilution was anticipated

  2. International Conference on the Safety of Radioactive Waste Management. Book of Papers

    International Nuclear Information System (INIS)

    2016-01-01

    The purpose of the conference was to highlight the importance of an integrated long term approach to the management of radioactive waste and spent fuel. The objectives of the conference were: • To foster information exchange between Member States, • To provide inputs that will promote further harmonization of safety in the fields of predisposal management and disposal of radioactive waste, • To highlight progress made in the safety of all types of radioactive waste. The conference served as a forum for discussing past experiences and future challenges. Furthermore, it seeked to identify Member States’ needs in order to assist them — through specific activities under future IAEA programmes in this area — to develop and implement safe solutions for the management of their entire radioactive waste inventory. The conference addressed all aspects of predisposal management and disposal of radioactive waste and spent fuel, including waste arising from accidental situations. The management of radioactive waste and residues from mining activities, as well as the control of discharges from nuclear facilities and activities, were, however, outside of its scope.

  3. 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

  4. Survey of matrix materials for solidified radioactive high-level waste

    Energy Technology Data Exchange (ETDEWEB)

    Gurwell, W.E.

    1981-09-01

    Pacific Northwest Laboratory (PNL) has been investigating advanced waste forms, including matrix waste forms, that may provide a very high degree of stability under the most severe repository conditions. The purpose of this study was to recommend practical matrix materials for future development that most enhance the stability of the matrix waste forms. The functions of the matrix were reviewed. Desirable matrix material properties were discussed and listed relative to the matrix functions. Potential matrix materials were discussed and recommendations were made for future matrix development. The matrix mechanically contains waste cores, reduces waste form temperatures, and is capable of providing a high-quality barrier to leach waters. High-quality barrier matrices that separate and individually encapsulate the waste cores are fabricated by powder fabrication methods, such as sintering, hot pressing, and hot isostatic pressing. Viable barrier materials are impermeable, extremely corrosion resistant, and mechanically strong. Three material classes potentially satisfy the requirements for a barrier matrix and are recommended for development: titanium, glass, and graphite. Polymers appear to be marginally adequate, and a more thorough engineering assessment of their potential should be made.

  5. Survey of matrix materials for solidified radioactive high-level waste

    International Nuclear Information System (INIS)

    Gurwell, W.E.

    1981-09-01

    Pacific Northwest Laboratory (PNL) has been investigating advanced waste forms, including matrix waste forms, that may provide a very high degree of stability under the most severe repository conditions. The purpose of this study was to recommend practical matrix materials for future development that most enhance the stability of the matrix waste forms. The functions of the matrix were reviewed. Desirable matrix material properties were discussed and listed relative to the matrix functions. Potential matrix materials were discussed and recommendations were made for future matrix development. The matrix mechanically contains waste cores, reduces waste form temperatures, and is capable of providing a high-quality barrier to leach waters. High-quality barrier matrices that separate and individually encapsulate the waste cores are fabricated by powder fabrication methods, such as sintering, hot pressing, and hot isostatic pressing. Viable barrier materials are impermeable, extremely corrosion resistant, and mechanically strong. Three material classes potentially satisfy the requirements for a barrier matrix and are recommended for development: titanium, glass, and graphite. Polymers appear to be marginally adequate, and a more thorough engineering assessment of their potential should be made

  6. 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.

  7. The buried waste integrated demonstration

    International Nuclear Information System (INIS)

    Kostelnik, K.M.

    1991-01-01

    There are numerous locations throughout the Department of Energy (DOE) Complex where wastes have been buried in the ground or stored for future disposal. Much of this buried waste is contaminated with hazardous and radioactive materials. An extensive research program has been initiated at the Idaho National Engineering Laboratory (INEL) to develop and demonstrate advanced remediation techniques for DOE Complex buried waste. The purpose of the Buried Waste Integrated Demonstration (BWID), is to develop a scientifically sound and deployable remediation system consisting of advanced technologies which address the buried waste characteristics of the DOE Complex. This comprehensive remediation system win include technologies for the entire remediation cycle (cradle-to-grave). Technologies developed and demonstrated within the BWID will be transferred to the DOE Complex sites with buried waste, to private industry, and to universities. Multidirectional technology transfer is encouraged by the BWID. Identification and evaluation of plausible technological solutions are an ongoing activity of the BWID. A number of technologies are currently under development throughout the DOE Complex, private industry, and universities. Technology integration mechanisms have been established by BWID to facilitate collaborative research and demonstration of applicable remedial technologies for buried waste. Successful completion of the BWID will result in the development of a proven and deployable system at the INEL and other DOE Complex buried waste sites, thereby supporting the DOE Complex's environmental restoration objectives

  8. Solid waste 30-year volume summary

    International Nuclear Information System (INIS)

    Valero, O.J.; Armacost, L.L.; DeForest, T.J.; Templeton, K.J.; Williams, N.C.

    1994-06-01

    A 30-year forecast of the solid waste volumes to be generated or received at the US Department of Energy Hanford Site is described in this report. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste that will require treatment, storage, and disposal at Hanford's Solid Waste Operations Complex (SWOC) during the 30-year period from FY 1994 through FY 2023. The data used to complete this document were collected from onsite and offsite waste generators who currently, or are planning to, ship solid wastes to the Hanford Site. An analysis of the data suggests that over 300,000 m 3 of LLMW and TRU/TRUM waste will be managed at Hanford's SWOC over the next 30 years. An extensive effort was made this year to collect this information. The 1993 solid waste forecast was used as a starting point, which identified approximately 100,000 m 3 of LLMW and TRU/TRUM waste to be sent to the SWOC. After analyzing the forecast waste volume, it was determined that additional waste was expected from the tank waste remediation system (TWRS), onsite decontamination and decommissioning (D ampersand D) activities, and onsite remedial action (RA) activities. Data presented in this report establish a starting point for solid waste management planning. It is recognized that forecast estimates will vary (typically increasing) as facility planning and missions continue to change and become better defined, but the information presented still provides useful insight into Hanford's future solid waste management requirements

  9. Changes in US commercial radioactive waste management and lessons learned in China

    International Nuclear Information System (INIS)

    Cai Tingsong; Yan Cangsheng

    2014-01-01

    The changes of commercial radioactive waste management in the US and the work done by the LLW generators in seeking new means to cost-effectively dispose these wastes without prejudicing future disposal options are introduced. Then the article concludes the lessons learned on radioactive waste management in China. (authors)

  10. A preliminary evaluation of alternatives for disposal of INEL low-level waste and low-level mixed waste

    International Nuclear Information System (INIS)

    Smith, T.H.; Roesener, W.S.; Jorgenson-Waters, M.J.

    1993-07-01

    The Mixed and Low-Level Waste Disposal Facility (MLLWDF) project was established in 1992 by the US Department of Energy Idaho Operations Office to provide enhanced disposal capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This Preliminary Evaluation of Alternatives for Disposal of INEL Low-Level Waste and Low-Level Mixed Waste identifies and evaluates-on a preliminary, overview basis-the alternatives for disposal of that waste. Five disposal alternatives, ranging from of no-action'' to constructing and operating the MLLWDF, are identified and evaluated. Several subalternatives are formulated within the MLLWDF alternative. The subalternatives involve various disposal technologies as well as various scenarios related to the waste volumes and waste forms to be received for disposal. The evaluations include qualitative comparisons of the projected isolation performance for each alternative, and facility, health and safety, environmental, institutional, schedule, and rough order-of-magnitude life-cycle cost comparisons. The performance of each alternative is evaluated against lists of ''musts'' and ''wants.'' Also included is a discussion of other key considerations for decisionmaking. The analysis of results indicated further study is necessary to obtain the best estimate of long-term future waste volume and characteristics from the INEL Environmental Restoration activities and the expanded INEL Decontamination and Decommissioning Program

  11. Goals for a waste management system: a task force report

    International Nuclear Information System (INIS)

    Bishop, W.

    1976-01-01

    This task force set out in a holistic way to study societal concerns regarding nuclear waste management, and to seek places where the technology interacts with our social system. The procedures involved in the goals for safe waste management are outlined and the organizations needed to carry them out are considered. The task force concluded that the needs for disposing of the present waste should not dictate the nature of the systems to be designed for the future wastes, and that budgetary considerations should not slow down the waste management in the second time frame (wastes no longer being produced). Other desirable goals, such as independence of waste management system regarding the stability of social institutions, are also discussed

  12. 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

  13. Radiation effects in glass and glass-ceramic waste forms for the immobilization of CANDU UO2 fuel reprocessing waste

    International Nuclear Information System (INIS)

    Tait, J.C.

    1993-05-01

    AECL has investigated three waste forms for the immobilization of high-level liquid wastes that would arise if used CANDU fuels were reprocessed at some time in the future to remove fissile materials for the fabrication of new power reactor fuel. These waste forms are borosilicate glasses, aluminosilicate glasses and titanosilicate glass-ceramics. This report discusses the potential effects of alpha, beta and gamma radiation on the releases of radionuclides from these waste forms as a result of aqueous corrosion by groundwaters that would be present in an underground waste disposal vault. The report discusses solid-state damage caused by radiation-induced atomic displacements in the waste forms as well as irradiation of groundwater solutions (radiolysis), and their potential effects on waste-form corrosion and radionuclide release. The current literature on radiation effects on borosilicate glasses and in ceramics is briefly reviewed, as are potential radiation effects on specialized waste forms for the immobilization of 129 I, 85 Kr and 14 C. (author). 104 refs., 9 tabs., 5 figs

  14. Emerging issue of e-waste in Pakistan: A review of status, research needs and data gaps

    International Nuclear Information System (INIS)

    Iqbal, Mehreen; Breivik, Knut; Syed, Jabir Hussain; Malik, Riffat Naseem; Li, Jun; Zhang, Gan; Jones, Kevin C.

    2015-01-01

    This review article focuses on the current situation of e-waste in Pakistan with the emphasis on defining the major e-waste recycling sites, current and future domestic generation of e-waste, hidden flows or import of e-waste and discusses various challenges for e-waste management. Needed policy interventions and possible measures to be taken at governmental level are discussed to avoid the increasing problem of e-waste in the country. Our findings highlight that there is still a general lack of reliable data, inventories and research studies addressing e-waste related issues in the context of environmental and human health in Pakistan. There is therefore a critical need to improve the current knowledge base, which should build upon the research experience from other countries which have experienced similar situations in the past. Further research into these issues in Pakistan is considered vital to help inform future policies/control strategies as already successfully implemented in other countries. - We present a baseline study on e-waste in Pakistan which could guide or facilitate more detailed studies in the future and ultimately lead to improve control strategies.

  15. Waste disposal in Europe - Looking ahead

    International Nuclear Information System (INIS)

    Verkerk, B.

    1985-01-01

    In this introductory paper a short outline is given of the Commission's programme on management and disposal of radioactive waste, followed by a discussion of the programme structure. This leads to the very important aspect of evaluation of results obtained and the communication of the achievements to the outer world. The important role of the media in this respect is stressed. Looking ahead, an important part of the Third Five years programme, the development of demonstration facilities, is projected against the problem of acceptability. Thinking about the consequences of entering the demonstration stage with respect to future research it turns out to be a broad field of work opens up, when the achievements reached in the radioactive waste area, could be transferred to problems of other toxic wastes and fusion wastes

  16. Amount of radioactive wastes in the Federal Republic of Germany - waste survey for the year 1988

    International Nuclear Information System (INIS)

    Brennecke, P.; Schumacher, J.

    1989-06-01

    On December 31, 1988, about 69 800 waste packages - about 40 700 m 3 - were stored in interim storage facilities. The unconditioned radioactive wastes amounted to about 11 700 m 3 . The volume of the conditioned radioactive wastes amounted to about 40 700 m 3 . Of this, the waste from nuclear research centres made up about 16 300 m 3 , the waste from the operation of nuclear power plants about 12 900 m 3 and that from the reprocessing of spent fuel elements about 8 300 m 3 . A prognosis was also made of the future amount of conditioned radioactive wastes. According to this forecast, the cumulated waste package volume of radioactive wastes with negligible heat generation will be approximately in the order of 173 400 m 3 up to the year 2000, whereas for heat-generating radioactive wastes a volume of about 5 800 m 3 is estimated. These figures already express the waste volume reduction according to modern conditioning techniques. In 1988 a capacity of about 123 800 m 3 for the interim storage of radioactive wastes was available in the Federal Republic of Germany. On December 31, 1988, an average of about 37% of this capacity was utilized by unconditioned and conditioned radioactive wastes. From the data on the expected amount of radioactive wastes and on the utilization factor of the interim storage facilities, it may be concluded that, taking an overall view, no bottlenecks in the interim storage of radioactive wastes with negligible heat generation are to be anticipated up to the planned operation of the Konrad repository in 1994. (orig./HP) [de

  17. Waste to Want: Polymer nanocomposites using nanoclays extracted from Oil based drilling mud waste

    International Nuclear Information System (INIS)

    Adegbotolu, Urenna V; Njuguna, James; Pollard, Pat; Yates, Kyari

    2014-01-01

    Due to the European Union (EU) waste frame work directive (WFD), legislations have been endorsed in EU member states such as UK for the Recycling of wastes with a vision to prevent and reduce landfilling of waste. Spent oil based drilling mud (drilling fluid) is a waste from the Oil and Gas industry with great potentials for recycling after appropriate clean-up and treatment processes. This research is the novel application of nanoclays extracted from spent oil based drilling mud (drilling fluid) clean-up as nanofiller in the manufacture of nanocomposite materials. Research and initial experiments have been undertaken which investigate the suitability of Polyamide 6 (PA6) as potential polymer of interest. SEM and EDAX were used to ascertain morphological and elemental characteristics of the nanofiller. ICPOES has been used to ascertain the metal concentration of the untreated nanofiller to be treated (by oil and heavy metal extraction) before the production of nanocomposite materials. The challenges faced and future works are also discussed

  18. CHALLENGES OF MUNICIPAL WASTE MANAGEMENT IN HUNGARY

    Directory of Open Access Journals (Sweden)

    ZOLTÁN OROSZ

    2008-06-01

    Full Text Available Aims, tasks and priorities of medium term development plans of national waste management were defined in the National Waste Management Plan, which was made for the period of 2003–2008 in Hungary. Supporting of the European Union is indispensable for carrying out of plan. The most important areas are related to the developing projects of municipal solid waste treatment (increasingthe capacity of landfills, accomplishment of the infrastructure of selective waste collection, building of new composting plants. The national environmental policy does not focus sufficiently on the prevention of waste production. Due to the high expenses of investment and operation the energetic recovery and the incineration of municipal solid waste do not compete with the deposition. We inclined to think that the waste management of Hungary will be deposition-orientated until 2015. The main problems to the next years will be the lack of reprocessing industry of plastic and glass packaging waste. The high number of to-be-recultivated landfills and the attainability of necessary financial sources are also serious problems. There are many questions. What is the future in national waste management? How can we reduce the quantity of dumped waste? What are challenges of national waste management on the short and long term?

  19. Nuclear waste form risk assessment for US defense waste at Savannah River Plant. Annual report fiscal year 1980

    International Nuclear Information System (INIS)

    Cheung, H.; Jackson, D.D.; Revelli, M.A.

    1981-07-01

    Waste form dissolution studies and preliminary performance analyses were carried out to contribute a part of the data needed for the selection of a waste form for the disposal of Savannah River Plant defense waste in a deep geologic repository. The first portion of this work provides descriptions of the chemical interactions between the waste form and the geologic environment. We reviewed critically the dissolution/leaching data for borosilicate glass and SYNROC. Both chemical kinetic and thermodynamic models were developed to describe the dissolution process of these candidate waste forms so as to establish a fundamental basis for interpretation of experimental data and to provide directions for future experiments. The complementary second portion of this work is an assessment of the impacts of alternate waste forms upon the consequences of disposal in various proposed geological media. Employing systems analysis methodology, we began to evaluate the performance of a generic waste form for the case of a high risk scenario for a bedded salt repository. Results of sensitivity analysis, uncertainty analyses, and sensitivity to uncertainty analysis are presented

  20. Handbook of high-level radioactive waste transportation

    International Nuclear Information System (INIS)

    Sattler, L.R.

    1992-10-01

    The High-Level Radioactive Waste Transportation Handbook serves as a reference to which state officials and members of the general public may turn for information on radioactive waste transportation and on the federal government's system for transporting this waste under the Civilian Radioactive Waste Management Program. The Handbook condenses and updates information contained in the Midwestern High-Level Radioactive Waste Transportation Primer. It is intended primarily to assist legislators who, in the future, may be called upon to enact legislation pertaining to the transportation of radioactive waste through their jurisdictions. The Handbook is divided into two sections. The first section places the federal government's program for transporting radioactive waste in context. It provides background information on nuclear waste production in the United States and traces the emergence of federal policy for disposing of radioactive waste. The second section covers the history of radioactive waste transportation; summarizes major pieces of legislation pertaining to the transportation of radioactive waste; and provides an overview of the radioactive waste transportation program developed by the US Department of Energy (DOE). To supplement this information, a summary of pertinent federal and state legislation and a glossary of terms are included as appendices, as is a list of publications produced by the Midwestern Office of The Council of State Governments (CSG-MW) as part of the Midwestern High-Level Radioactive Waste Transportation Project

  1. Waste management, waste resource facilities and waste conversion processes

    International Nuclear Information System (INIS)

    Demirbas, Ayhan

    2011-01-01

    In this study, waste management concept, waste management system, biomass and bio-waste resources, waste classification, and waste management methods have been reviewed. Waste management is the collection, transport, processing, recycling or disposal, and monitoring of waste materials. A typical waste management system comprises collection, transportation, pre-treatment, processing, and final abatement of residues. The waste management system consists of the whole set of activities related to handling, treating, disposing or recycling the waste materials. General classification of wastes is difficult. Some of the most common sources of wastes are as follows: domestic wastes, commercial wastes, ashes, animal wastes, biomedical wastes, construction wastes, industrial solid wastes, sewer, biodegradable wastes, non-biodegradable wastes, and hazardous wastes.

  2. Radioactive waste management; the realities as against the myths

    International Nuclear Information System (INIS)

    Williams, I.

    1980-01-01

    Nuclear power generation is now an essential requirement for the mankind in the current energy difficulties. The problem of radioactive waste management is arousing the opposition, but it must not inhibit the utilization of nuclear energy. Radioactive waste management concerns the whole course from its occurrence to its final disposal. The purpose of the management is then to protect absolutely the human beings of present and future generations from the danger of radioactivity. Radioactive wastes are varied much in their kinds and natures. While the management technology is nearly all established, the amounts of wastes are increasing. The following matters are described. Definition of radioactive waste management, fundamental strategies of the management, kinds of radioactive wastes, the present situation of radioactive waste management, and problems in the management. (J.P.N.)

  3. Issues related to public perception of radioactive waste management options

    International Nuclear Information System (INIS)

    Taylor, D.M.

    2007-01-01

    Public perceptions about radioactive waste are generally rather or even strongly negative. They are also very poorly informed. This is rather unfortunate as it is these perceptions that appear to greatly influence the Public views on nuclear energy in general. This, in turn, has had an influence on political decisions. On the other hand, in a very clear majority of the Member States of the European Union, the Public have already indicated that they would be ready to accept the important role of nuclear in their future energy mix as long as all the radioactive wastes can be safely managed. However perceptions about nuclear energy and radioactive waste should be seen in the context of the Public wider perceptions on energy and, in particular, the role in the future of different sources. It may be wrong for political decisions on nuclear energy in the future to rely to heavily on the Public perceptions. (author)

  4. Building on existing institutions to perpetuate knowledge of waste repositories

    International Nuclear Information System (INIS)

    Weitzberg, A.

    1982-08-01

    Purpose of this report is to examine the function of several existing institutions and to show how they could be effectively used to transmit information about waste repositories for long times into the future. Scope of this report is limited to a discussion of four institutional approaches to the dissemination and retention of information: Widely distributed maps, the marker system of the National Geodetic Survey, the archiving of documents, and one-call systems designed to protect underground utility installations from inadvertent damage by the public. Each of these approaches is discussed in an independent section that describes the background of the institutional approach, discusses methods for applying it to waste repositories, and assesses its potential value. The sole intent of this report is to present supporting data for future decisions about the kinds of communication measures that should be implemented to advise future generations about the locations and hazards of waste repositories

  5. Coal combustion waste management study

    International Nuclear Information System (INIS)

    1993-02-01

    Coal-fired generation accounted for almost 55 percent of the production of electricity in the United States in 1990. Coal combustion generates high volumes of ash and flue gas desulfurization (FGD) wastes, estimated at almost 90 million tons. The amount of ash and flue gas desulfurization wastes generated by coal-fired power plants is expected to increase as a result of future demand growth, and as more plants comply with Title IV of the 1990 Clean Air Act Amendments. Nationwide, on average, over 30 percent of coal combustion wastes is currently recycled for use in various applications; the remaining percentage is ultimately disposed in waste management units. There are a significant number of on-site and off-site waste management units that are utilized by the electric utility industry to store or dispose of coal combustion waste. Table ES-1 summarizes the number of disposal units and estimates of waste contained at these unites by disposal unit operating status (i.e, operating or retired). Further, ICF Resources estimates that up to 120 new or replacement units may need to be constructed to service existing and new coal capacity by the year 2000. The two primary types of waste management units used by the industry are landfills and surface impoundments. Utility wastes have been exempted by Congress from RCRA Subtitle C hazardous waste regulation since 1980. As a result of this exemption, coal combustion wastes are currently being regulated under Subtitle D of RCRA. As provided under Subtitle D, wastes not classified as hazardous under Subtitle C are subject to State regulation. At the same time Congress developed this exemption, also known as the ''Bevill Exclusion,'' it directed EPA to prepare a report on coal combustion wastes and make recommendations on how they should be managed

  6. Vitrification of low level and mixed (radioactive and hazardous) wastes: Lessons learned from high level waste vitrification

    International Nuclear Information System (INIS)

    Jantzen, C.M.

    1994-01-01

    Borosilicate glasses will be used in the USA and in Europe immobilize radioactive high level liquid wastes (HLLW) for ultimate geologic disposal. Simultaneously, tehnologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to immobilize low-level and mixed (radioactive and hazardous) wastes (LLMW) in durable glass formulations for permanent disposal or long-term storage. Vitrification of LLMW achieves large volume reductions (86--97 %) which minimize the associated long-term storage costs. Vitrification of LLMW also ensures that mixed wastes are stabilized to the highest level reasonably possible, e.g. equivalent to HLLW, in order to meet both current and future regulatory waste disposal specifications The tehnologies being developed for vitrification of LLMW rely heavily on the technologies developed for HLLW and the lessons learned about process and product control

  7. Guide to the safe handling of radioactive wastes at nuclear power plants

    International Nuclear Information System (INIS)

    1980-01-01

    This guide discusses the responsibilities of the regulatory authorities, the design considerations of waste management systems and the source and characteristics of waste. Present techniques for treating, conditioning, storing and disposing of gaseous, liquid and solid wastes on and from the site are summarized, and a consensus of good practice in waste management based on current knowledge and experience is given. The guide also contains brief chapters on transport of wastes, monitoring systems, safety analyses and a review of future trends in waste management

  8. Ethical aspects on Nuclear Waste

    International Nuclear Information System (INIS)

    Persson, Lars

    1989-01-01

    In an ethical assessment of how we shall deal with nuclear waste, one of the chief questions that arises is how to initiate action while at the same time taking into consideration uncertainties which are unavoidable seen from a long-term perspective. By means of different formulation and by proceeding from various starting-points, a two edged objective is established vis-a-vis repository facilities: safety in operation combined with reparability, with controls not necessary, but not impossible. Prerequisites for the realization of this objective are the continued advancement of knowledge and refinement of the qualifications required to deal with nuclear waste. The ethical considerations above could be the bases for the future legislation in the field of nuclear energy waste. (author)

  9. Effluent treatment and waste disposal

    International Nuclear Information System (INIS)

    1990-01-01

    In recent years there has been a great increase in the attention given to environmental matters by the public, media and Government. This has been reflected in the increased stature of environmental pressure groups and the introduction of new regulatory bodies and procedures. However, the satisfactory treatment and disposal of waste depends ultimately upon the development and employment of efficient low cost processes, and the enforcement of effective legislation. This Conference organised by the Yorkshire Branch of IChemE in association with the Institution's Environmental Protection Subject Group, will address the areas of waste monitoring, developments in pollution control processes and process economics and will look forward to future trends in waste disposal. It will also consider the impact of recent legislation upon the process industries. (author)

  10. One hundred thousand years back and forth: When archaeology meets radioactive waste

    International Nuclear Information System (INIS)

    Holtorf, Cornelius; Hoegberg, Anders

    2012-01-01

    This presentation discussed the final repository of radioactive waste as an issue at the interface of the sciences and the humanities. Archaeologists have learned that a hundred thousand years ago abstract thought and symbolism by humans began. Since then many communities of human beings have succeeded each other. They often intended to leave a mark for eternity, but they established in fact the truism that nothing ages faster than the future. Archaeologists and historians are promoting remembering, learning and understanding of history for contemporary and future generations. Disposal sites of nuclear waste constitute a special case of heritage. We are creating a very distinctive kind of heritage that in the future may be remembered or forgotten, just like any other heritage we create. The presentation addressed what the realms of heritage and radioactive waste disposal can learn from each other regarding making provisions for the future. Rubbish reflects the conditions from which it originates. The final deposition of radioactive waste is by nature a question of historical consciousness and future uses of the past, of memory and forgetting, and of future didactics of history. Heritage studies as well as history and archaeology are thus inherently relevant. Similarities between archaeology and RWM were thus pointed out, for instance the long time frames, specific sites, dealing with the meaning of rubbish, the fact that we both like to think we are doing something good for future generations,.. But there also are differences, notably that archaeology works with precious objects one wishes to keep. How will the future use our present, which is their past, for their own future? The meaning people give to information is important, and meaning is a continuous process of reinterpreting

  11. The trends of radioactive waste disposal

    International Nuclear Information System (INIS)

    Nomi, Mitsuhiko

    1977-01-01

    The disposal of radioactive wastes instead of their treatment has come to be important problem. The future development of nuclear fuel can not be expected unless the final disposal of nuclear fuel cycle is determined. Research and development have been made on the basis of the development project on the treatment of radioactive wastes published by Japan Atomic Energy Commission in 1976. The high level wastes produced by the reprocessing installations for used nuclear fuel are accompanied by strong radioactivity and heat generation. The most promising method for their disposal is to keep them in holes dug at the sea bottom after they are solidified. Middle or low level wastes are divided into two groups; one contains transuranium elements and the other does not. These wastes are preserved on the ground or in shallow strata, while the safe abandonment into the ground or the sea has been discussed about the latter. The co-operations among nations are necessary not only for peaceful utilization of atomic energy but also for radioactive waste disposal. (Kobatake, H.)

  12. Alternatives to land disposal of solid radioactive mixed wastes on the Hanford Site

    International Nuclear Information System (INIS)

    Jacobsen, P.H.

    1992-03-01

    This report is a detailed description of the generation and management of land disposal restricted mixed waste generated, treated, and stored at the Hanford Site. This report discusses the land disposal restricted waste (mixed waste) managed at the Hanford Site by point of generation and current storage locations. The waste is separated into groups on the future treatment of the waste before disposal. This grouping resulted in the definition of 16 groups or streams of land disposal restricted waste

  13. Methods for removing transuranic elements from waste solutions

    International Nuclear Information System (INIS)

    Slater, S.A.; Chamberlain, D.B.; Connor, C.; Sedlet, J.; Srinivasan, B.; Vandegrift, G.F.

    1994-11-01

    This report outlines a treatment scheme for separating and concentrating the transuranic (TRU) elements present in aqueous waste solutions stored at Argonne National Laboratory (ANL). The treatment method selected is carrier precipitation. Potential carriers will be evaluated in future laboratory work, beginning with ferric hydroxide and magnetite. The process will result in a supernatant with alpha activity low enough that it can be treated in the existing evaporator/concentrator at ANL. The separated TRU waste will be packaged for shipment to the Waste Isolation Pilot Plant

  14. Is there an ethic of radioactive waste management?

    International Nuclear Information System (INIS)

    Chouchan, M.; Montremy, J.M. de; Loisel, J.P.; Arnould, J.; Serre, J.L.; Bucaille, A.; Barre, B.; Duvert, L.; Legrand, P.; Engstorm, S.; Pavlovski, D.

    2004-01-01

    In France today, radioactive wastes are stored in a secure way, waiting for a political decision concerning their disposal. However, their evolution has to be followed and the future generations will need to be informed to eventually modify the present day choices. Thus, the reversibility is one of the ethical dimension of the question. Today, more than 90% of the radioactive wastes produced in France have found a reliable management solution for each category of wastes. This document compares the point of view of several people from nuclear and non-nuclear domains about the deontological and memory dimensions of radioactive waste management. (J.S.)

  15. COMPAS: a European project on the ''comparison of alternative waste management strategies for long-lived radioactive wastes''. Scope, working methods and conclusions

    International Nuclear Information System (INIS)

    Dutton, L.M.C.; Hillis, Z.K.; Roehlig, K.J.

    2004-01-01

    The paper presents the content and major findings of a project on the ''COMParison of Alternative waste management Strategies for long-lived radioactive wastes'' (COMPAS) carried out within the 5 th framework programme of the European commission. Under the leadership of NNC (UK), the project was carried out by individuals representing waste management organisations from 15 European countries. After having compiled information on the nature and amount of long-lived radioactive waste to be managed, issues influencing the selection of waste management strategies and options, presently adopted national strategies as well as options for the future were addressed. Conclusions concerning key issues for the success or otherwise of strategies and management solutions were drawn. (orig.)

  16. Strategy for future seabed investigations

    International Nuclear Information System (INIS)

    Richards, A.F.; Murray, C.N.

    1989-01-01

    The status of seabed disposal studies and possible strategies for future development are reviewed. Background information for strategy development includes presentation of selected recommendations for future studies identified by the NEA/OECD Seabed Working Group, the Engineering Studies Task Group of the Seabed Working Group and the Subseabed Consortium. Inferences from these recommendations, and how sound scientifically based research, significant political perception and technological proof of concept may be related to strategies are considered as a prelude to strategy design. A proposed European strategy, complementary to the 1988 Subseabed Consortium strategy developed in the US, is to proceed to the technological proof of concept by emplacing one or more full-sized waste canisters containing non-radioactive, simulated heat-producing waste by a chosen deployment system. The latter could include the drilled, the penetrator or the pushed-in option. Emplaced canisters would be monitored for an extended period of time, and eventually retrieved for examination. International co-operation and co-ordination of all aspects is recommended. (author)

  17. Transportation of radioactive, hazardous, and mixed wastes: Material identification is the key

    International Nuclear Information System (INIS)

    Stancell, D.F.; Willaford, D.M.

    1992-01-01

    This paper will discuss how material identification and classification will result in an accurate determination of regulatory requirements, and will assure safe and compliant shipment of radioactive, hazardous, and mixed wastes. The primary focus of the paper is a discussion of lessons learned by the Department of Energy in making waste shipments, and how this can be applied to future mixed waste shipments. There will be a brief discussion of the Department's regulatory compliance program, including a presentation of compliance audit results, and how regulatory issues are addressed through effective information exchange, technical assistance, and compliance training. A detailed discussion will follow, which describes cases involving material identification and classification problems. Examples will include both RCRA waste and uranium mill tailings shipments. The paper will conclude with a discussion concerning the application of these lessons to future mixed waste shipments proposed by the Department. (author)

  18. Disposal of Hanford defense waste

    International Nuclear Information System (INIS)

    Holten, R.A.; Burnham, J.B.; Nelson, I.C.

    1986-01-01

    An Environmental Impact Statement (EIS) on the disposal of Hanford Defense Waste is scheduled to be released near the end of March, 1986. This EIS will evaluate the impacts of alternatives for disposal of high-level, tank, and transuranic wastes which are now stored at the Department of Energy's Hanford Site or will be produced there in the future. In addition to releasing the EIS, the Department of Energy is conducting an extensive public participation process aimed at providing information to the public and receiving comments on the EIS

  19. Process waste assessment for the Radiography Laboratory

    International Nuclear Information System (INIS)

    Phillips, N.M.

    1994-07-01

    This Process Waste Assessment was conducted to evaluate the Radiography Laboratory, located in Building 923. It documents the processes, identifies the hazardous chemical waste streams generated by these processes, recommends possible ways to minimize waste, and serves as a reference for future assessments of this facility. The Radiography Laboratory provides film radiography or radioscopy (electronic imaging) of weapon and nonweapon components. The Radiography Laboratory has six x-ray machines and one gamma ray source. It also has several other sealed beta- and gamma-ray isotope sources of low microcurie (μCi) activity. The photochemical processes generate most of the Radiography Laboratory's routinely generated hazardous waste, and most of that is generated by the DuPont film processor. Because the DuPont film processor generates the most photochemical waste, it was selected for an estimated material balance

  20. 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)