SCR in biomass and waste fuelled plants. Benchmarking of Swedish and European plants; SCR i biobraensle- och avfallseldade anlaeggningar. Erfarenheter fraan svenska och europeiska anlaeggningar

Energy Technology Data Exchange (ETDEWEB)

Goldschmidt, Barbara; Olsson, Henrik; Lindstroem, Erica

2010-11-15

In this report the state-of-art of SCR technology in biomass and waste fired plants is investigated. The aim of the investigation is to answer the question why new Swedish biomass combustion and co-combustion plants often prefer SNCR technology, whilst European waste combustion plants often choose SCR technology. In the report positives and negatives of various types of SCR installations are discussed, high-dust versus tail-end, 'normal' SCR versus low-temperature SCR, etc. Experiences, e g catalyst lifetime, deactivation and maintenance requirement, are discussed. The investigation is based partly on literature, but mainly on interviews with plant owners and with suppliers of SCR installations. The interviewed suppliers are mentioned in the reference list and the interviewed plant owners are mentioned in appendix A and B. The experiences from the Swedish and European plants are quite similar. Tail-end SCR is often operated without serious problems in both biomass and waste fuelled plants. The catalyst lifetimes are as long or even longer than for coal fired plants with high-dust SCR. In waste incineration plants high-dust SCR causes big problems and these plants are almost always equipped with tail-end SCR. In co-combustion boilers, where coal and biomass is co-combusted, high-dust SCR is more common, especially if the boilers were originally coal fired. In plants with both SNCR and high-dust SCR, i.e. slip-SCR, the SCR installation is considered to be much less of a problem. Although the activity loss of the catalyst is as quick as in conventional high-dust SCR, the catalyst can be changed less often. This is due to the fact that installed slip-SCR catalysts often are as large as conventional SCR catalysts, although less NO{sub x} reduction is required after the initial SNCR step. Thus, the catalyst lifetime is prolonged.

Emissions from decentralised CHP plants 2007 - Energinet.dk Environmental project no. 07/1882

DEFF Research Database (Denmark)

Nielsen, Malene; Nielsen, Ole-Kenneth; Thomsen, Marianne

Updated emission factors for decentralised combined heat and power (CHP) plants with a capacity project emission measurements as well as emission measurements performed in recent years that were collected. The emission factors valid for 2006/2007 have been...... estimated for the plant technologies: Municipal solid waste (MSW) incineration plants, plants combusting straw or wood, natural gas fuelled reciprocating engines, biogas fuelled engines, natural gas fuelled gas turbines, gas oil fuelled reciprocating engines, gas oil fuelled gas turbines, steam turbines...

Review of European regulatory and tariff experience with the sale of heat and electricity from combined heat and power plants

International Nuclear Information System (INIS)

Dyrelund, A.

1991-12-01

The Prince Edward Island Energy Corporation, Edmonton Power, Energy, Mines and Resources Canada and the Canadian Electrical Association commissioned a study to understand how electrical power and district heat from combined heat and power (CHP) plants is priced in Europe. Four northern European countries were investigated, Denmark, Germany, Sweden and Finland. These countries produce 45.8 TWh of power from combined heat and power plants, 7.1% of their annual consumption. In the case of Denmark, CHP accounts for 37.5% of its total power production. The energy situation in each country is reviewed using published statistics, and in particular the rapidly changing situation with regard to environmental and fuel taxes is examined. In order to obtain practical insights with regard to tariffs used by the various utilities, a series of generic examples were examined, supported by specific case studies. Technologies reviewed included: CHP from coal-fuelled extraction plant, CHP from coal-fuelled back pressure plant, waste heat from a municipal waste plant, and gas turbine with waste heat recovery. The benefits and risks associated with different tariff designs are discussed in detail including tariff formulae. This should enable interested parties to develop appropriate tariffs for combined heat and power plants in the context of current electrical utility policies. As a complement to the tariffs for combined heat and power plants, the design of district heating tariffs is also addressed. The typical concepts used in different countries are presented and discussed. 23 tabs

Solid Waste from the Operation and Decommissioning of Power Plants

Energy Technology Data Exchange (ETDEWEB)

Brown, Marilyn Ann [Georgia Inst. of Technology, Atlanta, GA (United States); D' Arcy, Daniel [Georgia Inst. of Technology, Atlanta, GA (United States); Lapsa, Melissa Voss [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sharma, Isha [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Li, Yufei [Georgia Inst. of Technology, Atlanta, GA (United States)

2017-01-05

This baseline report examines the solid waste generated by the U.S. electric power industry, including both waste streams resulting from electricity generation and wastes resulting from the decommissioning of power plants. Coal and nuclear plants produce large volumes of waste during electricity generation, and this report describes the policies and procedures for handling these materials. Natural gas and oil-fired power plants face similar waste challenges. Renewables considered in this baseline report include hydropower, wind and solar.

Power from waste. [Power plant at landfill site

Energy Technology Data Exchange (ETDEWEB)

Anon,

1991-01-01

Base Load Systems Ltd, a company in the United Kingdom, has just commissioned a power plant in Leicestershire which uses waste gases from a landfill site. The gases power two specially modified turbo charged engine and generator packages. The plant will use approximately 100 cu meters of landfill gas per hour and is expected to feed 1.5MW of electrical power into the supply network of East Midlands Electricity. Once the landfill site has been completely filled and capped with clay, it is estimated that the electrical power output will be 4 MW. At present, since their are no customers for heat in the vicinity, 100 KW of the electricity produced are used to run fans to dissipate the 2.5 MW of waste heat. Base load is also involved elsewhere in combined heat and power projects. (UK).

Disposal of radioactive wastes from Czechoslovak nuclear power plants

International Nuclear Information System (INIS)

Neumann, L.

In gaseous radioactive waste disposal, aerosol particles are filtered and gaseous wastes are discharged in the environment. The filters and filter materials used are stored on solid radioactive waste storage sites in the individual power plants. Liquid radioactive wastes are concentrated and the concentrates are stored. Distillates and low-level radioactive waste water are discharged into the hydrosphere. Solid radioactive wastes are stored without treatment in power plant bunkers. Bituminization and cementation of liquid radioactive wastes are discussed. (H.S.)

Advanced Oxyfuel power plant process with CO{sub 2} separation for power generation from brown coal and competitionable for future; Innovativer Oxyfuel-Kraftwerksprozess mit CO{sub 2}-Abscheidung fuer eine auch in Zukunft wettbewerbsfaehige Stromerzeugung aus Braunkohle

Energy Technology Data Exchange (ETDEWEB)

Gilli, P.G.; Hellfritsch, S. [Technische Universitaet Dresden (Germany); Jentsch, N. [Vattenfall Europe Generation, Cottbus (Germany)

2004-07-01

The Oxyfuel process for lignite combustion with CO{sub 2} separation is illustrated by the example of a industrial-scale power plant process. Consequent optimisation of the process with integrated waste air utilisation and further efficiency-increasing measures will make the power plant as efficient as modern conventional lignite-fuelled power stations. (orig.)

Wood-waste fuelled indirectly-fired gas turbine cogeneration plant for sawmill applications. Phase 2. Site-specific preliminary engineering and financial analysis

Energy Technology Data Exchange (ETDEWEB)

1988-03-01

The use of conventional steam/electricity cogeneration systems is not generally economical at the sawmill scale of operation. This paper describes an evaluation of a wood-waste fueled and, indirectly, gas fired turbine cogeneration plant aimed at developing a cost-effective wood-waste fired power generation and dry kiln heating system for sawmill applications. A preliminary engineering design and financial analysis of the system was prepared for a demonstration site in British Columbia. A number of alternative system configurations were identified and preliminary engineering designs prepared for each. In the first option , wood wastes combusted in a wet cell hot gas generator powered a 600 kW turbine, and produced 7,000 kW for the drying kilns. The second option provided the same electrical and heat output but used a down-fired suspension burner unit fuelled by clean, dried sawdust, together with an integral air heater heat exchanger. The third option represented a commercial-scale configuration with an electrical output of 1,800 kW, and sufficient heat output for the dry kilns. A financial analyis based on a computerized feasibility model was carried out on the last two options. Low electricity rates in British Columbia combined with the small scale of a demonstration project provide an inadequate rate of return at the site without substantial outside support. At a commercial scale of operation and with the higher electricity prices that exist outside of British Columbia the financial analysis indicates that the incremental investment in the electric generation portion of the system provides very attractive rates of return for the 3 options. 11 figs., 10 tabs.

Thermodynamic Performance Analysis of a Biogas-Fuelled Micro-Gas Turbine with a Bottoming Organic Rankine Cycle for Sewage Sludge and Food Waste Treatment Plants

Directory of Open Access Journals (Sweden)

Sunhee Kim

2017-02-01

Full Text Available In the Republic of Korea, efficient biogas-fuelled power systems are needed to use the excess biogas that is currently burned due to a lack of suitable power technology. We examined the performance of a biogas-fuelled micro-gas turbine (MGT system and a bottoming organic Rankine cycle (ORC. The MGT provides robust operation with low-grade biogas, and the exhaust can be used for heating the biodigester. Similarly, the bottoming ORC generates additional power output with the exhaust gas. We selected a 1000-kW MGT for four co-digestion plants with 28,000-m3 capacity. A 150-kW ORC system was selected for the MGT exhaust gas. We analysed the effects of the system size, methane concentration, and ORC operating conditions. Based on the system performance, we analysed the annual performance of the MGT with a combined heat and power (CHP system, bottoming ORC, or both a bottoming ORC and CHP system. The annual net power outputs for each system were 7.4, 8.5, and 9.0 MWh per year, respectively.

Experience with a biomass-fuelled power plant in Peru. Peru kokunai no biomass nenryoka no hatsuden plant no keiken

Energy Technology Data Exchange (ETDEWEB)

1992-11-01

This paper describes the result of operating a 25-kW biomass-fuelled power plant for 500 hours installed for people in a small village in jungle along the Amazon basin in Peru. The gasifier plant consists of two invert type gas combustors combined with series cyclone dryer filters. Filtration used activated carbons and cotton cloths. The fuel for the plant is wood chips containing water at 5.5% to 11% with calorific power of 20 mJ/kg, consumed at 2.0 kg of lumber per kWh (25 kWh). A gas analysis showed values of CO2 at 13%, CO at 14%, H2 at 18%, CH4 at 3%, and N2 at 52%. Because the fuel of wood chips may cause problems if the size is too large, a size of about 10[times]20[times]30 mm was selected finally. Pressure drop in the gas purifying system was measured using a manometer, which verified that a textile filtering material can be used. The gasoline engine rotation was fixed at 2700 rpm upon discussions. The gasoline engine had no need of modification except at a pipe to the carburetor. This system can be installed at any small village. 1 ref., 1 fig.

Component design considerations for gas turbine HTGR waste-heat power plant

International Nuclear Information System (INIS)

McDonald, C.F.; Vrable, D.L.

1976-01-01

Component design considerations are described for the ammonia waste-heat power conversion system of a large helium gas-turbine nuclear power plant under development by General Atomic Company. Initial component design work was done for a reference plant with a 3000-MW(t) High-Temperature Gas-Cooled Reactor (HTGR), and this is discussed. Advanced designs now being evaluated include higher core outlet temperature, higher peak system pressures, improved loop configurations, and twin 4000-MW(t) reactor units. Presented are the design considerations of the major components (turbine, condenser, heat input exchanger, and pump) for a supercritical ammonia Rankine waste heat power plant. The combined cycle (nuclear gas turbine and waste-heated plant) has a projected net plant efficiency of over 50 percent. While specifically directed towards a nuclear closed-cycle helium gas-turbine power plant (GT-HTGR), it is postulated that the bottoming waste-heat cycle component design considerations presented could apply to other low-grade-temperature power conversion systems such as geothermal plants

Management of radioactive wastes at nuclear power plants

International Nuclear Information System (INIS)

2008-03-01

This Regulation refers to the requirements of the Regulation CNEN-NE.1.26, 'Safety Operation of Nuclear Power Plants', as expressed in the section 13, specifically in the subsection 13.4, relatives to the management of radioactive wastes at nuclear power plants

Radioactive waste processing method for a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, Y; Kuriyama, O

1976-06-04

Object is to subject radioactive liquid waste in a nuclear power plant to reverse permeation process after which it is vaporized and concentrated thereby decreasing the quantity of foam to be used to achieve effective concentration of the liquid waste. Liquid waste containing a radioactive material produced from a nuclear power plant is first applied with pressure in excess of osmotic pressure by a reverse permeation device and is separated into clean water and concentrated liquid by semi-permeable membrane. Next, the thus reverse-permeated and concentrated waste is fed to an evaporator which control foaming by the foam and then further reconcentrated for purification of the liquid waste.

Managing nuclear waste from power plants

International Nuclear Information System (INIS)

Keeney, R.L.; Winterfeldt, D. von

1994-01-01

National strategies to manage nuclear waste from commercial nuclear power plants are analyzed and compared. The current strategy is to try to operate a repository at Yucca Mountain, Nevada, to dispose storage at a centralized facility or next to nuclear power plants. If either of these is pursued now, the analysis assumes that a repository will be built in 2100 for waste not subsequently put to use. The analysis treats various uncertainties: whether a repository at Yucca Mountain would be licensed, possible theft and misuse of the waste, innovations in repository design and waste management, the potential availability of a cancer cure by 2100, and possible future uses of nuclear waste. The objectives used to compare alternatives include concerns for health and safety, environmental and socioeconomic impacts, and direct economic costs, as well as equity concerns (geographical, intergenerational, and procedural), indirect economic costs, as well as equity concerns (geographical, intergenerational, and procedural), indirect economic costs to electricity ratepayers, federal government responsibility to manage nuclear waste, and implications of theft and misuse of nuclear waste. The analysis shows that currently building an underground repository at Yucca Mountain is inferior to other available strategies by the equivalent of $10,000 million to $50,000 million. This strongly suggests that this policy should be reconsidered. A more detailed analysis using the framework presented would help to define a new national policy to manage nuclear waste. 36 refs., 3 figs., 17 tabs

A technical and financial analysis of two recuperated, reciprocating engine driven power plants. Part 1: Thermodynamic analysis

International Nuclear Information System (INIS)

Orbaiz, Pedro Jose; Brear, Michael J.

2014-01-01

Highlights: • A thermodynamic analysis of two recuperated ICE plants is undertaken. • The overall plant efficiency and CO 2 emissions are analysed. • Chemical recuperation without a secondary heat source is unlikely. • Using a renewable secondary heat source reduces the CO 2 emission of the plant. - Abstract: This paper is the first of a two part study that analyses the technical and financial performance of particular, recuperated engine systems. This first paper presents a thermodynamic study of two systems. The first system involves the chemical recuperation of a reciprocating, spark ignited, internal combustion engine using only the waste heat of the engine to power a steam–methane reformer. The performance of this system is evaluated for different coolant loads and steam–methane ratios. The second system is a so-called ’hybrid’ in which not only the waste heat of the engine is used, but also a secondary heat source – the combustion of biomass. The effects of the reformer’s temperature and the steam–methane ratio on the system performance are analysed. These analyses show that the potential efficiency improvement obtained when using only the engine waste heat to power the recuperation is marginal. However, results for the hybrid show that although the overall efficiency of the plant, defined in terms of the energy from both the methane and biomass, is similar to that of the conventional, methane fuelled engine, the efficiency of the conversion of the biomass fuel energy to work output appears to be higher than for other biomass fuelled technologies currently in use. Further, in the ideal limit of a fully renewable biomass fuel, the burning of biomass does not contribute to the net CO 2 emissions, and the CO 2 emission reduction for this second plant can be considerable. Indeed, its implementation on larger internal combustion engine power plants, which have efficiencies of around 45–50%, could result in CO 2 emissions that are as much as

Availability of thermal power plants 1981-1990

International Nuclear Information System (INIS)

Nitsch, D.; Schmitz, H.

1991-01-01

The present volume covers the period of 1981 to 1990 and contains availability data of power plants in Germany and abroad. Data are presented on fossil-fuelled units, units with a combined gas/steam cycle, nuclear power plants and gas turbines. The fossil-fuelled units are broken down by unit size, years of operation, fuel, type of combustion (dry, melt) and type (mono, duo units, subcritical and supercritical systems). Nuclear power stations are arranged by type of reactor (PWR, BWR), unit size and years of operation. Combined cycle power plants are listed separately due to their different technical concepts. Apart from availability and utilisation values of gas turbines there are data on reliability and the number of successful and unsuccessful starts. In general the data are first given for all plants and then for the German plants in particular. Performance values are gross values measured at generator terminals and, as the number of plants, they are end-of-the-year figures [de

Management of radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

1985-01-01

This Code of Practice defines the minimum requirements for the design and operation of structures, systems and components important for the management of radioactive wastes from thermal neutron nuclear power plants. The topics covered include design and operation of gaseous, liquid and solid waste systems, waste transport, storage and disposal, decommissioning wastes and wastes from unplanned events

Waste generation comparison: Coal-fired versus nuclear power plants

International Nuclear Information System (INIS)

LaGuardia, T.S.

1998-01-01

Low-level radioactive waste generation and disposal attract a great deal of attention whenever the nuclear industry is scrutinized by concerned parties, be it the media, the public, or political interests. It is therefore important to the nuclear industry that this issue be put into perspective relative to other current forms of energy production. Most of the country's fossil-fueled power comes from coal-fired plants, with oil and gas as other fuel sources. Most of the generated waste also comes from coal plants. This paper, therefore, compares waste quantities generated by a typical (1150-MW(electric)) pressurized water reactor (PWR) to that of a comparably sized coal-fired power plant

Radioactive waste treatment technology at Czech nuclear power plants

International Nuclear Information System (INIS)

Kulovany, J.

2001-01-01

This presentation describes the main technologies for the treatment and conditioning of radioactive wastes at Czech nuclear power plants. The main technologies are bituminisation for liquid radioactive wastes and supercompaction for solid radioactive wastes. (author)

Improvements of radioactive waste management at WWER nuclear power plants

International Nuclear Information System (INIS)

2006-04-01

This report is part of a systematic IAEA effort to improve waste management practices at WWER plants and to make them consistent with the current requirements and standards for safe and reliable operation of nuclear power plants. The report reviews the wet and dry solid waste management practices at the various types of WWER nuclear power plants (NPP) and describes approaches and recent achievements in waste minimization. Waste minimization practices in use at western PWRs are reviewed and compared, and their applicability at WWER plants is evaluated. Radioactive waste volume reduction issues and waste management practices are reflected in many IAEA publications. However, aspects of waste minimization specific to individual WWER nuclear power plant designs and WWER waste management policies are not addressed extensively in those publications. This report covers the important aspects applicable to the improvement of waste management at WWER NPP, including both plant-level and country-level considerations. It is recognized that most WWER plants are already implementing many of these concepts and recommendations with varying degrees of success; others will benefit from the included considerations. The major issues addressed are: - Review of current waste management policies and practices related to WWERs and western PWRs, including the influence of the original design concepts and significant modifications, liquid waste discharge limits and dry solid waste clearance levels applied in individual countries, national policies and laws, and other relevant aspects affecting the nature and quantities of waste arisings; - Identification of strategies and methods for improving the radioactive waste management generated in normal operation and maintenance at WWERs. This report is a composite (combination) of the two separate initiatives mentioned above. The first draft report was prepared at the meeting 26-30 May 1997 by five consultants. The draft was improved during an

Disposal of slightly contaminated radioactive wastes from nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

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

1995-02-01

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

Combined heat and power plants with parallel tandem steam turbines; Smaaskalig kraftvaerme med parallellkopplade tandemturbiner

Energy Technology Data Exchange (ETDEWEB)

Steinwall, Pontus; Norstroem, Urban; Pettersson, Camilla; Oesterlin, Erik

2004-12-01

We investigate the technical and economical conditions for a concept with parallel coupled tandem turbines in small scale combined heat and power plants fired with bio-fuel and waste. Performance and heat production costs at varying electricity prices for the concept with two smaller tandem coupled steam turbines has been compared to the traditional concept with one single multi-staged turbine. Three different types of plants have been investigated: - Bio fuelled CHP plant with thermal capacity of 15 MW{sub th}; - Waste fired CHP plant with thermal capacity of 20 MW{sub th}; - Bio fuelled CHP plant with thermal capacity of 25 MW{sub th}. The simple steam turbines (Curtis turbines) used in the tandem arrangement has an isentropic efficiency of about 49 to 53% compared to the multi-staged steam turbines with isentropic efficiency in the range of 59% to 81%. The lower isentropic efficiency for the single staged turbines is to some extent compensated at partial load when one of the two turbines can be shut down leading to better operational conditions for the one still in operation. For concepts with saturated steam at partial load below 50% the tandem arrangements presents higher electricity efficiency than the conventional single turbine alternative. The difference in annual production of electricity is therefore less than the difference in isentropic efficiency for the two concepts. Production of electricity is between 2% and 42% lower for the tandem arrangements in this study. Investment costs for the turbine island has been calculated for the two turbine concepts and when the costs for turbines, generator, power transmission, condensing system, piping system, buildings, assembling, commissioning and engineering has been added the sum is about the same for the two concepts. For the bio-fuelled plant with thermal capacity of 15 MW{sub th} the turbine island amount to about 10-12 MSEK and about 13-15 MSEK for the waste fired plant with a thermal capacity of 20 MW

Design of Radioactive Waste Management Systems at Nuclear Power Plants

International Nuclear Information System (INIS)

1986-01-01

This Safety Guide is addressed to the administrative and technical authorities and specialists dealing with the design, construction and operation of nuclear power plants, and in particular waste management facilities at nuclear power plants. This Guide has been prepared as part of the IAEA Waste Handling, Treatment and Storage programme. It is a follow-up document to the Code of Practice on Management of Radioactive Wastes from Nuclear Power Plants published in 1985 in the IAEA Safety Standards, Safety Series No. 69, in which basic principles for management of radioactive wastes at nuclear power plants are set out. The IAEA has established wide ranging programmes to provide Member States with guidance on different aspects of safety and technology related to thermal neutron power reactors and associated nuclear fuel cycle operations, including those for management of radioactive wastes. There are many IAEA publications related to various technical and safety aspects of different nuclear energy applications. All these publications are issued by the Agency for the use of Member States in connection with their own nuclear technological safety requirements. They are based on national experience contributed by experts from different countries and relate to common features in approaches to the problems discussed. However, the final decision and legal responsibility in any regulatory procedure always rest with the Member State. This particular Guide aims to provide general and detailed principles for the design of waste management facilities at nuclear power plants. It emphasizes what and how specific safety requirements for the management of radioactive wastes from nuclear power plants can be met in the design and construction stage. The safety requirements for operation of such facilities will be considered in the Agency's next Safety Series publication, Safety Guide 50-SG-011, Operational Management for Radioactive Effluents and Wastes Arising in Nuclear Power Plants

Management of abnormal radioactive wastes at nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

As with any other industrial activity, a certain level of risk is associated with the operation of nuclear power plants and other nuclear facilities. That is, on occasions nuclear power plants or nuclear facilities may operate under conditions which were not specifically anticipated during the design and construction of the plant. These abnormal conditions and situations may cause the production of abnormal waste, which can differ in character or quantity from waste produced during normal routine operation of nuclear facilities. Abnormal waste can also occur during decontamination programmes, replacement of a reactor component, de-sludging of storage ponds, etc. The management of such kinds of waste involves the need to evaluate existing waste management systems in order to determine how abnormal wastes should best be handled and processed. There are no known publications on this subject, and the IAEA believes that the development and exchange of such information among its Member States would be useful for specialists working in the waste management area. The main objective of this report is to review existing waste management practices which can be applied to abnormal waste and provide assistance in the selection of appropriate technologies and processes that can be used when abnormal situations occur. Naturally, the subject of abnormal waste is complex and this report can only be considered as a guide for the management of abnormal waste. Refs, figs and tabs.

A comparison of circulating fluidised bed combustion and gasification power plant technologies for processing mixtures of coal, biomass and plastic waste

International Nuclear Information System (INIS)

McIlveen-Wright, D.R.; Huang, Y.; McMullan, J.T.; Pinto, F.; Franco, C.; Gulyurtlu, I.; Armesto, L.; Cabanillas, A.; Caballero, M.A.; Aznar, M.P.

2006-01-01

Environmental regulations concerning emission limitations from the use of fossil fuels in large combustion plants have stimulated interest in biomass for electricity generation. The main objective of the present study was to examine the technical and economic viability of using combustion and gasification of coal mixed with biomass and plastic wastes, with the aim of developing an environmentally acceptable process to decrease their amounts in the waste stream through energy recovery. Mixtures of a high ash coal with biomass and/or plastic using fluidised bed technologies (combustion and gasification) were considered. Experiments were carried out in laboratory and pilot plant fluidised bed systems on the combustion and air/catalyst and air/steam gasification of these feedstocks and the data obtained were used in the techno-economic analyses. The experimental results were used in simulations of medium to large-scale circulating fluidised bed (CFB) power generation plants. Techno-economic analysis of the modelled CFB combustion systems showed efficiencies of around 40.5% (and around 46.5% for the modelled CFB gasification systems) when fuelled solely by coal, which were only minimally affected by co-firing with up to 20% biomass and/or wastes. Specific investments were found to be around $2150/kWe to $2400/kWe ($1350/kWe to $1450/kWe) and break-even electricity selling prices to be around $68/MWh to $78/MWh ($49/MWh to $54/MWh). Their emissions were found to be within the emission limit values of the large combustion plant directive. Fluidised bed technologies were found to be very suitable for co-firing coal and biomass and/or plastic waste and to offer good options for the replacement of obsolete or polluting power plants. (author)

Deposition and effects on some aquatic organisms of particulate matter emitted from some peat fuelled power plants in Finland. Deposition och effekter paa naagra vattenlevande organismer av emitterat stoft fraan naagra torveldade kraftverk i Finland

Energy Technology Data Exchange (ETDEWEB)

Bengtsson, C; Fischer, S; Hellstroem, T; Notini, M; Steen, B; Waltersson, E; Landner, L

1982-01-01

At three different peat fuelled plants in Finland, environmental studies have been carried out with the aim of obtaining part of the background data necessary for the formulation of environmental guidelines in relation to the future use of peat for energy and heat production in Sweden. The present project was comprised of (a) field studies of the composition pattern of polyaromatic hydrocarbons (PAH) and of heavy metals in the surroundings of some existing peat fuelled power plants, and (b) laboratory tests with a few aquatic organisms to check the possible biological effects induced by emitted particles. The results of these studies indicate that the deposition of (PAH) in the surroundings of three power plants (measured by snow sampling and by analysis of kale grown in the area) did not exceed the background level, whereas the deposition of heavy metals emitted from one power plant resulted in increased concentrations of Fe, Mn, Pb, Zn and possibly of Hg, compared to the assumed background level. Biological tests with particles originating from two different peat fuelled power plants showed that only weak, but obvious, effects could be detected at concentrations corresponding to realistic deposition levels. These effects are supposed to be due to the metal content of the particles rather than to the PAH content. When evaluating the lab results, it should be considered that a certain fixation of metals dissolved in the snow melting water may take place in the soil surface. Therefore, the biological effect studies, carried out so far, do not indicate that peat combustion at the investigated power plants, using efficient flue gas cleaning systems, cause any considerable biological effects in the surroundings of the plants. However, it is evident that the present set of data does not allow a general evaluation of the over-all environmental impact of peat combustion.

Radioactive waste management at nuclear power plant Cernavoda

International Nuclear Information System (INIS)

Raducea, D.

2002-01-01

Many human activities generate waste, but people are worried about wastes produced in nuclear power plants (NPPs). Their concern is an unjustified fear toward the hazards from radioactive waste, probably because in any country generating electric power by NPPs a lot of attention is paid to relevant parties involved in radioactive waste management. Significant attention is also given to the management of radioactive waste at the Cemavoda NPP. The general approach required for the collection, handling, conditioning and storage of radioactive wastes, while maintaining acceptable levels of safety for workers, members of the public and the environment, is conceptually established. The overall programme provides the necessary facilities to adequately manage solid radioactive waste from Cemavoda NPP Unit 1 and will be capable of expansion when other units are brought into service. (author)

From the idea to the construction of a biomass fuelled plant. The marketing potential

International Nuclear Information System (INIS)

Beyer, Ranveig Vaa

2000-12-01

The report deals with the case handling in connection with the planning of a biomass fuelled plant as well as the market potential for a biomass fuelled Stirling engines and direct combustion of biomass with a steam circuit

Waste heat recovery options in a large gas-turbine combined power plant

Science.gov (United States)

Upathumchard, Ularee

This study focuses on power plant heat loss and how to utilize the waste heat in energy recovery systems in order to increase the overall power plant efficiency. The case study of this research is a 700-MW natural gas combined cycle power plant, located in a suburban area of Thailand. An analysis of the heat loss of the combustion process, power generation process, lubrication system, and cooling system has been conducted to evaluate waste heat recovery options. The design of the waste heat recovery options depends to the amount of heat loss from each system and its temperature. Feasible waste heat sources are combustion turbine (CT) room ventilation air and lubrication oil return from the power plant. The following options are being considered in this research: absorption chillers for cooling with working fluids Ammonia-Water and Water-Lithium Bromide (in comparison) and Organic Rankine Cycle (ORC) with working fluids R134a and R245fa. The absorption cycles are modeled in three different stages; single-effect, double-effect and half-effect. ORC models used are simple ORC as a baseline, ORC with internal regenerator, ORC two-phase flash expansion ORC and ORC with multiple heat sources. Thermodynamic models are generated and each system is simulated using Engineering Equation Solver (EES) to define the most suitable waste heat recovery options for the power plant. The result will be synthesized and evaluated with respect to exergy utilization efficiency referred as the Second Law effectiveness and net output capacity. Results of the models give recommendation to install a baseline ORC of R134a and a double-effect water-lithium bromide absorption chiller, driven by ventilation air from combustion turbine compartment. The two technologies yield reasonable economic payback periods of 4.6 years and 0.7 years, respectively. The fact that this selected power plant is in its early stage of operation allows both models to economically and effectively perform waste heat

Management of nontritium radioactive wastes from fusion power plants

International Nuclear Information System (INIS)

Kaser, J.D.; Postma, A.K.; Bradley, D.J.

1976-09-01

This report identifies nontritium radioactive waste sources for current conceptual fusion reactor designs. Quantities and compositions of the radwaste are estimated for the tokamaks of the University of Wisconsin (UWMAK-I), the Princeton Plasma Physics Laboratory (PPPL), and the Oak Ridge National Laboratory (ORNL); the Reference Theta Pinch Reactor of the Los Alamos Scientific Laboratory (LASL); and the Minimum Activation Blanket of the Brookhaven National Laboratory (BNL). Disposal of large amounts of radioactive waste appears necessary for fusion reactors. Although the curie (Ci) level of the wastes is comparable to that of fission products in fission reactors, the isotopes are less hazardous, and have shorter half-lives. Therefore radioactivity from fusion power production should pose a smaller risk than radioactivity from fission reactors. Radioactive waste sources identified for the five reference plants are summarized. Specific radwaste treatments or systems had to be assumed to estimate these waste quantities. Future fusion power plant conceptual designs should include radwaste treatment system designs so that assumed designs do not have to be used to assess the environmental effects of the radioactive waste

Considerations on the DEMO pellet fuelling system

Energy Technology Data Exchange (ETDEWEB)

Lang, P.T., E-mail: peter.lang@ipp.mpg.de [Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany); Day, Ch. [Karlsruhe Institute of Technology, 76021 Karlsruhe (Germany); Fable, E. [Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany); Igitkhanov, Y. [Karlsruhe Institute of Technology, 76021 Karlsruhe (Germany); Köchl, F. [Association EURATOM-Ö AW/ATI, Atominstitut, TU Wien, 1020 Vienna (Austria); Mooney, R. [Culham Centre for Fusion Energy, Culham Science Centre, Oxfordshire OX14 3DB (United Kingdom); Pegourie, B. [CEA, IRFM, 13108 Saint-Paul-lez-Durance (France); Ploeckl, B. [Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany); Wenninger, R. [Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany); EFDA, Garching (Germany); Zohm, H. [Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany)

2015-10-15

Graphical abstract: - Highlights: • Considerations are made for a core particle fuelling system covering all DEMO requirements. • Particle deposition beyond the pedestal top is needed to achieve efficient fuelling. • Conventional pellet technology enabling launching from the torus inboard side can be used. • Efforts have been taken for integrating a suitable pellet guiding system into the EU DEMO model. • In addition, further techniques bearing potential for advanced fuelling performance are considered. - Abstract: The Demonstration Fusion Power Reactor DEMO is the step foreseen to bridge the gap between ITER and the first commercial fusion power plant. One key element in the European work plan for DEMO is the elaboration of a conceptual design for a suitable core particle fuelling system. First considerations for such a system are presented in this contribution. Following the well-considered ITER solution, most analysis performed in this study assumes conventional pellet technology will be used for the fuelling system. However, taking advantage of the less compressed time frame for the DEMO project, several other techniques thought to bear potential for advanced fuelling performance are considered as well. In a first, basic analysis all actuation parameters at hand and their implications on the fuelling performance were considered. Tentative transport modeling of a reference scenario strongly indicates only particles deposited inside the plasma pedestal allow for efficient fuelling. Shallow edge fuelling results in an unbearable burden on the fuel cycle. Sufficiently deep particle deposition seems technically achievable, provided pellets are launched from the torus inboard at sufficient speed. All components required for a DEMO pellet system capable for high speed inboard pellet launch are already available or can be developed in due time with reasonable efforts. Furthermore, steps to integrate this solution into the EU DEMO model are taken.

Considerations on the DEMO pellet fuelling system

International Nuclear Information System (INIS)

Lang, P.T.; Day, Ch.; Fable, E.; Igitkhanov, Y.; Köchl, F.; Mooney, R.; Pegourie, B.; Ploeckl, B.; Wenninger, R.; Zohm, H.

2015-01-01

Graphical abstract: - Highlights: • Considerations are made for a core particle fuelling system covering all DEMO requirements. • Particle deposition beyond the pedestal top is needed to achieve efficient fuelling. • Conventional pellet technology enabling launching from the torus inboard side can be used. • Efforts have been taken for integrating a suitable pellet guiding system into the EU DEMO model. • In addition, further techniques bearing potential for advanced fuelling performance are considered. - Abstract: The Demonstration Fusion Power Reactor DEMO is the step foreseen to bridge the gap between ITER and the first commercial fusion power plant. One key element in the European work plan for DEMO is the elaboration of a conceptual design for a suitable core particle fuelling system. First considerations for such a system are presented in this contribution. Following the well-considered ITER solution, most analysis performed in this study assumes conventional pellet technology will be used for the fuelling system. However, taking advantage of the less compressed time frame for the DEMO project, several other techniques thought to bear potential for advanced fuelling performance are considered as well. In a first, basic analysis all actuation parameters at hand and their implications on the fuelling performance were considered. Tentative transport modeling of a reference scenario strongly indicates only particles deposited inside the plasma pedestal allow for efficient fuelling. Shallow edge fuelling results in an unbearable burden on the fuel cycle. Sufficiently deep particle deposition seems technically achievable, provided pellets are launched from the torus inboard at sufficient speed. All components required for a DEMO pellet system capable for high speed inboard pellet launch are already available or can be developed in due time with reasonable efforts. Furthermore, steps to integrate this solution into the EU DEMO model are taken.

The risk of storing radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

Gruemm, H.

1976-09-01

Serious bottle-necks exist in the nuclear fuel cycle and will continue for the next decade. A total of 800 nuclear reactors are now in operation. 153 nuclear power plants represent an installed capacity of 70 GVe. Until 1985 five hundred nuclear power plants will be in operation from which up to this date 53.000 t uranium will have been discharged. Part of this will have to be reprocessed. Associated with the above mentioned amount are 500 t plutonium and 1.500 t highly radioactive wastes. Two risks for the population have to be considered: firstly, the effect of small amounts of radioactive substances released during normal operation of nuclear power plants (the annual dose is about 1 mrem per person). Secondly, the possibility of the release of great amounts of radioactivity during heavy accidents (the probability for which is extremely small). A series of feasible possibilities for conditioning are shown. Firstly, the wastes are packed in substances which are insoluble in water. Secondly, for low and medium wastes these can be mixed with concrete or bitumen and filled into stable containers. Thirdly, the wastes could also be solidified. Fourthly, the wastes could be enclosed in small glass spheres which are embedded in a metal matrix. (H.G.)

Bio-oil fuelled diesel power plant; Biooeljyllae toimiva dieselvoimala

Energy Technology Data Exchange (ETDEWEB)

Vuorinen, A [Modigen Oy, Helsinki (Finland)

1997-12-01

The project mission is to develop a diesel power plant which is capable of using liquid bio-oils as the main fuel of the power plant. The applicable bio-oils are rape seed oils and pyrolysis oils. The project was started in 1994 by installing a 1.5 MW Vasa 4L32 engine in VTT Energy laboratory in Otaniemi. During 1995 the first tests with the rape seed oils were made. The tests show that the rape seed oil can be used in Vasa 32 engines without difficulties. In the second phase of the project during 1996 pyrolysis oil made of wood was tested. Finally a diesel power plant concept with integrated pyrolysis oil, electricity and heat production will be developed

Vitrification of liquid waste from nuclear power plants

International Nuclear Information System (INIS)

Sheng Jiawei; Choi, Kwansik; Song, Myung-Jae

2001-01-01

Glass is an acceptable waste form to solidify the low-level waste from nuclear power plants (NPPs) because of the simplicity of processing and its unique ability to accept a wide variety of waste streams. Vitrification is being considered to solidify the high-boron-containing liquid waste generated from Korean NPPs. This study dealt with the development of a glass formulation to solidify the liquid waste. Studies were conducted in a borosilicate glass system. Crucible studies have been performed with surrogate waste. Several developed glass frits were evaluated to determine their suitability for vitrifying the liquid waste. The results indicated that the 20 wt% waste oxides loading required could not be obtained using these glass frits. Flyash produced from coal-burning electric power stations, whose major components are SiO 2 and Al 2 O 3 , is a desirable glass network former. Detailed product evaluations including waste loading, homogeneity, chemical durability and viscosity, etc., were carried out on selected formulations using flyash. Up to 30 wt% of the waste oxides was successfully solidified into the flyash after the addition of 5-10 wt% Na 2 O at 1200 deg. C

On-power fuelling machine of Dhruva research reactor: An indigenous effort (Paper No. 043)

International Nuclear Information System (INIS)

Rao, T.K.; Andhansare, M.G.

1987-02-01

On-power fuelling machine of Dhruva Research Reactor has been indigenously designed, manufactured, installed and commissioned. This is being used for fuelling of Dhruva Research reactor regularly since June 1985. This paper deals with the developmental efforts made during design and manufacture for meeting the functional requirements of the fuelling machine. This paper also highlights the special features of the components like servo valves, hydraulic motors, S.S. bellows, bearings, roller chains, solenoid valves etc. needed for reliable operation and maintenance of the fuelling machine whose down time should be minimum to achieve maximum reactor availability. (author). 17 figs

Availability of thermal power plants 1980-1989

International Nuclear Information System (INIS)

Nitsch, D.; Schmitz, H.

1990-01-01

The evaluation submitted here is the 19th annual evaluation since 1970. It covers the period from 1980 to 1989 and contains availability data of 324 power stations (domestic and international) with roundabout 94000 MW and 3800 plant years. Data relate to fossil-fuelled cogeneration plants, combined cycle plants (gas-steam combined process), nuclear power stations and gas turbines. The fossil-fuelled blocks are broken down by size, time of operation, fuel, type of combustion (dry, melt) and type mono-, duoblocks, subcritical and supercritical systems, nuclear power stations are organised by type of reactor heavy-water/pressurized water reactor and type of operation. Combined cycle power plants are listed separately due to their different technical concept. Gas turbines are sub-divided by type of operation (time). Apart from availability and utilisation values of gas turbines there are data on reliability and the number of successful and unsuccessful starts. In general the values are first given for all plants of one particular type and then for the German plants in particular. Performance values are gross values measured at generator and like the number of plants they are end-of-the-year figures. In order to increase the usefulness of the VGB-availability studies various items in the recording and evaluation were improved and extended as of 1987. (orig./HS) [de

Liquid waste management at nuclear power plant with WWER

International Nuclear Information System (INIS)

Sabouni, Zahra.

1995-07-01

Management of radioactive wastes have become an area of ever increasing important in nuclear power plants. This is due to the fact that national and international regulations will only allow activity release to the environment based on ALARA principles. Radioactive liquids in the nuclear power plant originate as leakage from equipment, as drains from reactor and auxiliary systems, from decontamination and cleaning operations, from active laundry and from personnel showers. They will collected through the controlled zone of the plant in sumps and automatically pumped to large tanks and then to treatment system. The radioactive wastes are separated and categorized according to their main physical and chemical properties. Methods most frequently applied for low and intermediate level; liquid wastes are: chemical treatment (precipitation), ion exchange, and evaporation, and the decontamination ors are a few hundred, 10 2 -10 4 and 10 3 -10 6 , respectively. As a result of the treatment of radioactive liquids by mentioned methods a concentration of activity takes place in filter media, ion exchange resins, and evaporator concentrates. Before the semi-solid wastes shipped for storage, it has to be solidified in order to handle and transport in easier way. The solidification of wastes can take place by different methods. The general methods are: cementation, and bituminization processes. The selection of each process will depend on many factors which should be considered during the design phase. (author)

Comparison of environmental impact of waste disposal from fusion, fission and coal-fired power plants

Energy Technology Data Exchange (ETDEWEB)

Frey, Bruno [Fichtner GmbH und Co. KG, Stuttgart (Germany)

2011-08-15

The radiotoxic hazard of waste from fusion power plants has been compared with that of fission power and radioactive trace elements in coal ash within some research programs such as SEAFP and SEIF. Within another program, in 2005 a Power Plant Conceptual Study (PPCS) has been finalized investigating 4 fusion power plant models A to D. In this paper, the radiotoxicity of model B is compared with a fission power plant, concentrating on the production of wastes. The hazard of the respective masses of enriched uranium before use in a fission power plant and coal ash of a power plant generating the same amount of electricity are used as benchmarks. It is evident that the development of ingestion and inhalation hazard of the PPCS model B is different from the results of earlier studies because of different assumptions on material impurities and other constraints. An important aspect is the presence of actinides in fusion power plant waste. (orig.)

Supply, operation and radioactive waste disposal of nuclear power plants

International Nuclear Information System (INIS)

Mohrhauer, H.; Krey, M.; Haag, G.; Wolters, J.; Merz, E.; Sauermann, P.F.

1981-07-01

The subject of 'Nuclear Fuel Cycle' is treated in 5 reports: 1. Uranium supply; 2. Fabrication and characteristics of fuel elements; 3. Design, operation and safety of nuclear power plants after Harrisburg; 4. Radioactive waste disposal of nuclear power plants - changed political scenery after 1979; 5. Shutdown and dismantling of LWR-KKW - state of knowledge and feasibility. (HP) [de

Sampling and transport of paraffin waste form from CWDS of nuclear power plant

International Nuclear Information System (INIS)

Lee, J. M.; Hwang, J. H.; Kim, C. R.; Park, J. W.

2000-01-01

Sampling and transport of paraffin waste form from concentrated waste drying system (CWDS) of domestic nuclear power plant were performed to collect the leaching characteristic data for the disposal of radioactive waste. Transport was performed according to the national regulations and the internal rules of the nuclear power plant. The sample of paraffin waste form was classified as L type package according to the regulation and radiation exposure of operator was measured in the range of 6 to 12 mrem that was less than the estimated amount

DENINT power plant cost benefit analysis code: Analysis of methane fuelled power plant/district heating system

International Nuclear Information System (INIS)

Cincotti, V.; D'Andrea, A.

1989-07-01

The DENINT power plant cost benefit analysis code takes into consideration, not only power production costs at the generator terminals, but also, in the case of cogeneration, the costs of the fuel supply and heat and power distribution systems which depend greatly on the location of the plant. The code is able to allow comparisons of alternatives with varying annual operation hours, fuel cost increases, and different types of fossil fuels and production systems. For illustrative purposes, this paper examines two methane fired cogeneration plant/district heating alternatives

Co-combustion of gasified contaminated waste wood in a coal fired power plant

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This project demonstrates the technical and economical feasibility of the producing and cofiring of product gas from demolition waste wood. For this purpose LCV product gas is generated in an atmospheric circulating fluidized bed (CFB) gasification plant, cooled and cleaned and transported to the boiler of a 600 MWe pulverized coal fired power plant. Gas cooling and cleaning takes place in a waste heat boiler and a multi stage wet gas cleaning train. Steam raised in the waste heat boiler is exported to the power plant. On an annual basis 70,000 tons of steam coal are substituted by 150,000 tons of contaminated demolition waste wood (50,000 tons oil equivalent), resulting in a net CO2 emission reduction of 170,000 tons per year, while concurrently generating 205 GWh of electrical power. The wood gasification plant was built by NV EPZ (now incorporated in Essent Energi BV) for Amergas BV, now a 100% subsidiary of Essent Energie BV. The gasification plant is located at the Amer Power Station of NV EPZ Production (now Essent Generation) at Geertruidenberg, The Netherlands. Demonstrating several important design features in wood gasification, the plant started hot service in the Spring of 2000, with first gasification accomplished in the Summer of 2000 and is currently being optimized. (au)

Optimal placement of biomass fuelled gas turbines for reduced losses

International Nuclear Information System (INIS)

Jurado, Francisco; Cano, Antonio

2006-01-01

This paper presents a method for the optimal location and sizing of biomass fuelled gas turbine power plants. Both profitability in using biomass and power loss are considered in the cost function. The first step is to assess the plant size that maximizes the profitability of the project. The second step is to determine the optimal location of the gas turbines in the electric system to minimize the power loss of the system

Selected problems of minimization and management of radioactive wastes from nuclear power plant decommissioning. Part 2

International Nuclear Information System (INIS)

Kyrs, M.; Moravec, A.

1988-06-01

The processing prior to storage of radioactive wastes produced in nuclear power plant decommissioning is described as are the types of containers employed for waste transport and/or disposal. Data are summarized on exposure of personnel to radioactivity resulting from nuclear power plant decommissioning activities, and accessible data are collected on the costs of nuclear power plant decommissioning and of waste management. Potential directions of research in this field under Czechoslovak conditions are specified. (author)

Some contributions to the examination of composites from power plant wastes

Directory of Open Access Journals (Sweden)

Trifunović Prvoslav

2015-01-01

Full Text Available This paper describes an investigation into the possibilities of the use of all three types of solid power plant wastes: fly ash (FA, flue gas desulphurization gypsum (FGD gypsum and bottom ash (BA as components of composites for road construction. Two mixtures were made: 1. power plant wastes - Portland cement (PC and 2. power plant wastes - sand (S - Portland cement (PC. The mass ratio of components in these mixtures was: 1. FA - FGD gypsum - BA - PC = 2 : 1.5 : 5 : 1.5 and 2. FA- FGD gypsum-BA - S - PC= 2 : 1.5 : 4 : 1 : 1.5. For both mixtures, the compressive strength, the mineralogical composition, the water absorption and the resistance to freeze-thaw treatment were determined 7 and 28 days after preparation of samples (mixing with water. The obtained results showed that both mixtures could have potential to be used for sub-base layers in road construction and the second mixture (with natural aggregate-sand has advantage over the first mixture in terms of compressive strength, mineralogical composition, and resistance to freeze-thaw treatment.

An intelligent tutoring system for a power plant simulator

Energy Technology Data Exchange (ETDEWEB)

Seifi, H.; Seifi, A.R. [Tarbiat Modarres University, Tehran (Iran). Faculty of Engineering, Dept. of Electrical Engineers

2002-07-28

An intelligent tutoring system (ITS) is proposed for a power plant simulator. With a well designed ITS, the need for an instructor is minimized and the operator may readily and efficiently take, in real-time, the control of simulator with appropriate messages he(she) gets from the tutoring system. Using SIMULINK and based on object oriented programming (OOP) and C programming language, a fossil-fuelled power plant simulator with an ITS is proposed. Promising results are demonstrated for a typical power plant.

IAEA provisional code of practice on management of radioactive waste from nuclear power plants

International Nuclear Information System (INIS)

1982-10-01

This Code of Practice defines the minimum requirements for operations and design of structures, systems and components important for management of wastes from thermal nuclear power plants. It emphasizes what safety requirements shall be met rather than specifies how these requirements can be met; the latter aspect is covered in Safety Guides. The Code defines the need for a Government to assume responsibility for regulating waste management practices in conjunction with the regulation of a nuclear power plant. The Code does not prejudge the organization of the regulatory authority, which may differ from one Member State to another, and may involve more than one body. Similarly, the Code does not deal specifically with the functions of a regulatory authority responsible for such matters, although it may be of value to Member States in providing a basis for consideration of such functions. The Code deals with the entire management system for all wastes from nuclear power plants embodying thermal reactors including PWR, BWR, HWR and HTGR technologies. Topics included are: design, normal and abnormal operation, and regulation of management systems for gaseous, liquid and solid wastes, including decommissioning wastes. The Code includes measures to be taken with regard to the wastes arising from spent fuel management at nuclear power plants. However, the options for further management of spent fuel are only outlined since it is the subject of decisions by individual Member States. The Code does not require that an option(s) be decided upon prior to construction or operation of a nuclear power plant

Waste-to-energy advanced cycles and new design concepts for efficient power plants

CERN Document Server

Branchini, Lisa

2015-01-01

This book provides an overview of state-of-the-art technologies for energy conversion from waste, as well as a much-needed guide to new and advanced strategies to increase Waste-to-Energy (WTE) plant efficiency. Beginning with an overview of municipal solid waste production and disposal, basic concepts related to Waste-To-Energy conversion processes are described, highlighting the most relevant aspects impacting the thermodynamic efficiency of WTE power plants. The pervasive influences of main steam cycle parameters and plant configurations on WTE efficiency are detailed and quantified. Advanc

The role of the operator of nuclear power plants in disposal of nuclear waste

International Nuclear Information System (INIS)

Chaussade, J.P.

1995-01-01

Public opinion polls show that the French have largely understood the importance of our nuclear programme in maintaining French independence with regard to power supply and its security and that they have confidence in the technicians for the proper construction and operation of these power plants, but that they retain many questions concerning the disposal of nuclear waste. They have the impression that solutions remain to be found, and especially that the Electricite de France (EDF) devised the nuclear power programme without concern for the disposal of waste. This lack of information is fortunately far from reality, EDF, under the supervision of the security authorities, manages the waste produced in the nuclear power plants. Final stocking of waste is handled by a body that is independent of the waste producer, the ''Agence nationale pour la gestion des dechets radioactifs'' (Andra) (National Agency for the Management of Radioactive Waste). (author). 7 refs., 1 tab

Development of recycling techniques for nuclear power plant decommissioning waste

International Nuclear Information System (INIS)

Ishikura, Takeshi; Oguri, Daiichiro; Abe, Seiji; Ohnishi, Kazuhiko

2003-01-01

Recycling of concrete and metal waste will provide solution to reduce waste volume, contributing to save the natural resources and to protect the environment. Nuclear Power Engineering Corporation has developed techniques of concrete and metal recycling for decommissioning waste of commercial nuclear power plants. A process of radioactive concrete usage for mortar solidification was seen to reduce concrete waste volume by 2/3. A concrete reclamation process for high quality aggregate was confirmed that the reclaimed aggregate concrete is equivalent to ordinary concrete. Its byproduct powder was seen to be utilized various usage. A process of waste metal casting to use radioactive metal as filler could substantially decrease the waste metal volume when thinner containers are applied. A pyro-metallurgical separation process was seen to decrease cobalt concentration by 1/100. Some of these techniques are finished of demonstration tests for future decommissioning activity. (author)

Management of radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

Krause, H.

1984-01-01

The importance of radioactive wastes from nuclear power plants (NPPs) results primarily from their large amounts. In NPPs more radioactive wastes arise than in all other plants of the nuclear fuel cycle, with the exception of uranium mills. Although the volume is great, NPP wastes are relatively low in activity and radiotoxicity and short in half-life. Several methods for treatment of NPP wastes are available that meet all the relevant requirements and they have attained high technical standards and are highly reliable. Consequently, the discharge of radionuclides with liquid and gaseous effluents and the resulting dose commitment to the general public are far below established limits. The quality of the conditioned wastes conforms to the requirements for ultimate disposal. The final disposal of NPP wastes has already been demonstrated successfully in several places and the feasibility of NPP decommissioning and management of the wastes arising in this process have been proved. The problems associated with the management of radioactive wastes from NPPs have been solved both scientifically and technically; there is no urgent need for improvement. This is why for new developments cost-benefit aspects must be considered, including the dose commitment to the operating staff and general aspects such as public acceptance and socio-ethical questions. Spectacular new developments are not to be expected in the near future. However, by continuous improvement of details and optimization of the whole system useful contributions can still be made to develop nuclear technology further. (author)

Waste from nuclear power plants

International Nuclear Information System (INIS)

1980-01-01

The report presents proposals for organizing and financing of the treatment and deposition of spent fuel and radioactive waste. Decommissioning of plants is taken into consideration. The proposals refer to a program of twelve reactors. A relatively complete model for the handling of radioactive waste in Sweden is at hand. The cost for the years 1980 to 2000 is estimated at approx 1040 million SKr. Also the expense to dispose of the rest of the waste is calculated up to the year 2060, when the waste is planned to be put into final deposit. The state must have substantial influence over the organization which should be closely connected to the nuclear industry. Three different types of organization are discussed, namely (i) a company along with a newly created authority, (ii) a company along with the existing Nuclear Power Inspectorate or (iii) a company along with a board of experts. The proposals for financing the cost of handling nuclear waste are given in chief outlines. The nuclear industry should reserve means to special funds. The allocations are calculated to 1.4 oere per delivered kWh up to and including the year 1980. The accumulated allocations for 1979 should thus amount to 1310 million SKr. The charge for supervision and for certain research and development is recommended to be 0.1 oere per kWh which corresponds to approx 23 million SKr for 1980. The funds should be assured by binding agreements which must be approved by the state. The amounts are given in the monetary value of the year 1979. (G.B.)

Innovative waste treatment and conditioning technologies at nuclear power plants

International Nuclear Information System (INIS)

2006-05-01

The objective of this publication is to provide Member States with information on the most innovative technologies and strategies used in waste treatment and conditioning. At present, some of those technologies and strategies might not be widely implemented at nuclear power plants (NPP), but they have an important potential for their use as part of the long range NPP, utility, or national strategy. Thus, the target audience is those decision makers at the national and organizational level responsible for selecting waste processing technologies and strategies over a period of three to ten years. Countries and individual nuclear plants have limited financial resources which can be applied toward radioactive waste processing (treatment and conditioning). They are challenged to determine which of the many available technologies and strategies are best suited to meet national or local needs. This publication reduces the selection of processes for wastes generated by nuclear power plants to those technologies and strategies which are considered innovative. The report further identifies the key benefits which may derive from the adoption of those technologies, the different waste streams to which each technology is relevant, and the limitations of the technologies. The technologies and strategies identified have been evaluated to differentiate between (1) predominant technologies (those that are widely practiced in multiple countries or a large number of nuclear plants), and (2) innovative technologies (those which are not so widely used but are considered to offer benefits which make them suitable for broader application across the industry). Those which fall into the second category are the primary focus of this report. Many IAEA publications address the technical aspects of treatment and conditioning for radioactive wastes, covering research, technological advances, and safety issues. These studies and reports primarily target the research and technical staff of a

New solutions for waste management centers of new Russian-type nuclear power plant designs

International Nuclear Information System (INIS)

Buettner, Klaus

2010-01-01

There has been a change of mind with respect to waste management among power plant operators in Russia and planners of the new VVER reactor line. Solid waste no longer is to be stored on the site of the power plant; instead, a functioning direct method of treatment of the different categories of waste arising in operation is favored. Waste conditioning and reduced storage volumes are indispensable arguments in selling reactor technology to markets outside Russia. Reference often is made to the internationally discussed volume of 50 m 3 of waste per reactor unit and year, which is then defined as a target. NUKEM Technologies verified existing technical concepts and worked out proposals of improved waste management. One project proposal accepted by ASE (Atomstroyexport) was elaborated to the Technical Project (corresponding to Basic Design) status. Specific management of materials flows, the use of processes tailored to the waste stream, and adaptation of the throughputs of these plants to the waste arisings actually expected are able to reduce clearly both the volume of conditioned waste to be stored and the capital costs. (orig.)

Safety analysis of disposal of decommissioning waste from the Olkiluoto nuclear power plant - PURKU-93

International Nuclear Information System (INIS)

Vieno, T.; Meszaros, F.; Nordman, H.; Taivassalo, V.

1993-12-01

Decommissioning waste from the Olkiluoto nuclear power plant will be disposed of at the depth between 60 and 100 meters in the bedrock at the power plant site. The existing VLJ repository for low and medium level operating waste will be extended with three new silos for the decommissioning waste of the TVO I and II reactors and the spent fuel interim store at the Olkiluoto site. Besides dismantling waste also used fuel boxes, control rods and other activated metal components accumulated during the operation of the reactors will be disposed of in the repository. The safety analysis is based on the detailed decommissioning plan of the Olkiluoto power plants and the comprehensive safety analysis carried out for the Final Safety Analysis Report of the VLJ repository. (58 refs., 31 figs., 38 tabs.)

Use of fixation techniques in processing radioactive wastes from nuclear power plants in Czechoslovakia

International Nuclear Information System (INIS)

Seliga, M.

1977-01-01

The current state of radioactive waste disposal from the Bohunice nuclear power plant is described. The method of vacuum cementation was chosen for solidifying liquid radioactive wastes. This method makes it possible to obtain a product whose properties, namely strength, leachability, and radiation stability allow for the production of blocks without packing material. Also solved was the fixation of liquid radioactive waste using bituminization based on mixing liquid radioactive waste with aqueous bitumen emulsion in a film evaporator in which the mixture of liquid radioactive wastes and bitumen emulsion evaporate producing solid bitumen. The parameters are given of the cementation and bituminization lines which are designed for use in nuclear power plants with WWER type reactors. (J.B.)

Nuclear power plants waste management practices in France

International Nuclear Information System (INIS)

Matsuda, Fumio

1998-01-01

This survey offers a complete review concerning the nuclear power plants waste management in France from generation to disposal, as well as future evolutions. Fundamental Safety Rule specified by the government defines safety objectives, design bases for surface disposals and preliminary terms for acceptance of waste packages on the surface disposal site. A governmental decree authorizes the creation of CSA (Centre de Stockage de l'Aude; French surface repository), and defines the limits of radiological inventory of the disposal facility. The national waste agency ANDRA was established in 1979 by government (turned into public in 1991), and ANDRA defines the technical specifications involving acceptance criteria of the waste packages. The main feature of the French management includes; Comprehensive quality assurance program that encompasses all area of the management. Centralized installation for the melting of contaminated scrap metals and incineration of low level technological wastes. Mobile unit for common treatment of ion exchange resin. Concrete package assuring the long term containment. Complete tracking system of wastes from generation to disposal. This survey would be useful in the consideration of Japanese waste management including miscellaneous wastes, high βγ wastes, large metallic wastes, etc. (author)

Management of radioactive waste from nuclear power plants: An overview

International Nuclear Information System (INIS)

Devgun, J.S.

1994-01-01

The nuclear power industry, which accounts for about 20% of the total electricity supply, is a vital part of the nation's energy resource. While it generates approximately one-third of the commercial low-level radioactive waste produced in the country, it has achieved one of the most successful examples in waste minimization. On the other hand, progress on development of new disposal facilities by the state compacts is currently stalled. The milestones have been repeatedly postponed, and the various Acts passed by Congress on nuclear waste disposal have not accomplished what they were intended to do. With dwindling access to waste disposal sites and with escalating disposal costs, the power plant utilities are forced to store wastes onsite as an interim measure. However, such temporary measures are not a permanent solution. A national will is sorely needed to break out of the current impasse

Sewage sludge drying process integration with a waste-to-energy power plant.

Science.gov (United States)

Bianchini, A; Bonfiglioli, L; Pellegrini, M; Saccani, C

2015-08-01

Dewatered sewage sludge from Waste Water Treatment Plants (WWTPs) is encountering increasing problems associated with its disposal. Several solutions have been proposed in the last years regarding energy and materials recovery from sewage sludge. Current technological solutions have relevant limits as dewatered sewage sludge is characterized by a high water content (70-75% by weight), even if mechanically treated. A Refuse Derived Fuel (RDF) with good thermal characteristics in terms of Lower Heating Value (LHV) can be obtained if dewatered sludge is further processed, for example by a thermal drying stage. Sewage sludge thermal drying is not sustainable if the power is fed by primary energy sources, but can be appealing if waste heat, recovered from other processes, is used. A suitable integration can be realized between a WWTP and a waste-to-energy (WTE) power plant through the recovery of WTE waste heat as energy source for sewage sludge drying. In this paper, the properties of sewage sludge from three different WWTPs are studied. On the basis of the results obtained, a facility for the integration of sewage sludge drying within a WTE power plant is developed. Furthermore, energy and mass balances are set up in order to evaluate the benefits brought by the described integration. Copyright © 2015 Elsevier Ltd. All rights reserved.

Management of effluents and radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

2005-01-01

Management of effluents and radioactive waste from nuclear power plants, from the viewpoint of radiological protection, basically consists of three main themes: 1) developing and implementing actions that minimize, or where possible, eliminate generation. These actions ranging from simple awareness of people involved with the work on project modifications; 2) maintain a system of accounting and control that allows to know the characteristics of effluents and wastes, charting indicators that reveal the performance and trends of plant, and supplying data proving the compliance of national regulatory body standards; 3) Storing the solid waste generated in a safe manner, ensuring that the physical integrity of the packaged is maintained and that there is no impact to the population and the environment

Waste incineration on its way to the power plants; Muellverbrennung auf dem Weg zum Kraftwerk

Energy Technology Data Exchange (ETDEWEB)

Reich, J. [STEAG encotec GmbH, Essen (Germany); Neukirchen, B. [STEAG AG, Essen (Germany)

2004-07-01

Looking at the year 2005 and the end of disposal of untreated domestic waste the politic hopes that the prognosticated lack of waste treatment capacity is remedied by coal-fired power plants. The classical municipal waste incinerators by contrast want to get recognition as energetic recycler in comparison with power stations. The decision of the European Court of Justice concerning recycling and disposal of domestic waste by incineration has started the discussion and competition on fuel-rich commercial waste. Are municipal waste incineration plants power stations or must power plants be regarded as incinerators? These questions are still open. (orig.) [German] Mit Blick auf das Jahr 2005 und das Ende der Ablagerung von unbehandeltem Siedlungsabfall hofft die Politik, dass der prognostizierte Mangel an Vorbehandlungskapazitaeten von den Kohlekraftwerken behoben wird. Die klassischen Muellverbrennungsanlagen wollen dagegen mit dem Kraftwerksvergleich die Anerkennung als energetische Verwerter erreichen. Das EuGH-Urteil zur Verwertung oder Beseitigung von Siedlungsabfall durch Verbrennen hat in diesem Jahr die Diskussion und den Kampf um den heizwertreichen Gewerbeabfall angeheizt. Die Frage, wie weit in Zukunft die Muellverbrennungsanlagen als Kraftwerke, aber auch die Kraftwerke als Muellverbrennungsanlagen angesehen werden muessen, ist noch offen. (orig.)

Performance of on-power fuelling equipment at Rajasthan Atomic Power Station

International Nuclear Information System (INIS)

Jayabarathan, S.; Gopalakrishnan, S.

1977-01-01

Natural uranium reactors on account of their intrinsically low reactivity need frequent refuelling. The Rajasthan Atomic Power Station based on natural uranium reactors has, therefore, been provided with on-power fuel handling system which was installed in 1972. Its performance has met the design intent and operational objectives which are enumerated. However, continuous fuelling 7 to 10 days has not been possible because frequent maintenance of refuelling system is needed on account of certain deficiencies major of which is the heavy water leakage. For better performance, installation of a programmable logic controller is suggested. Mention has also been made of inadequate number of skilled man-power required for maintenance which leads to quick depletion of man-rem of all the available personnel trained for maintenance work. (M.G.B.)

Liquid and solid rad waste treatment in advanced nuclear power plants. Application to the SBWR design

International Nuclear Information System (INIS)

Tielas Reina, M.; Asuar Alonso, O.

1994-01-01

Rad waste treatment requirements for the new generation of American advanced passive and evolutionary power plants are listed in the URD (Utility Requirements Document) of the EPRI (Electrical Power Research Institute). These requirements focus on: - Minimization of shipped solid wastes - Minimization of liquid effluents - Simplification of design and operation, with emphasis not only on waste treatment system design but also on general plant design and operation These objectives are aimed at: - Reducing and segregating wastes at source - Minimizing chemical contamination of these wastes System design simplification is completed by providing free space in the building for the use of mobile plants, either for special services not considered in the basic design or to accommodate future technical advances. (Author)

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.

Solid Waste from Four-stroke Medium Speed Engine Power Plant Operation

OpenAIRE

Smart, Heidi

2016-01-01

This thesis is a study of the solid-state waste generated in power plants based on internal combustion engine (ICE) technology, supplied by the Wärtsilä Energy Solutions division. This thesis, which characterizes and quantifies the waste, was done to enhance the ability of supporting customers in issues related to social and environmental impact assessment, environmental permits, waste management planning, etc. The Performance Standards on Environmental and Social Sustainability and the E...

Utilization of waste heat from nuclear power plants in agriculture

International Nuclear Information System (INIS)

Horacek, P.

1981-01-01

The development of nuclear power will result in the relative and absolute increase in the amount of waste heat which can be used in agriculture for heating greenhouses, open spaces, for fish breeding in heated water, for growing edible mushrooms, growing algae, for frost protection of orchards, air conditioning of buildings for breeding livestock and poultry, and for other purposes. In addition of the positive effect of waste heat, the danger increases of disease, weeds and pests. Pilot plant installations should be build in Czechoslovakia for testing the development of waste heat utilization. (Ha)

Fuelling with flow at Bruce A

Energy Technology Data Exchange (ETDEWEB)

Gray, M G [Canadian General Electric Co. Ltd., Peterborough, ON (Canada)

1997-12-31

Fuelling with flow is the solution chosen by Bruce A to overcome the potential power pulse caused by a major inlet header failure. Fuelling with flow solves the problem by rearranging the core to place new fuel at the channel inlet and irradiated fuel at the channel outlet. The change has a significant impact on the Bruce A fuel handling system which was designed primarily to do on power fuelling in the against flow direction. Mechanical changes to the fuelling machine include a modification to the existing ram head and the replacement of standard fuel carriers with new fuelling with flow fuel carriers having the capability of opening the channel latch. Changes to the control system are more involved. A new set of operational sequences are required for both the upstream and downstream fuelling machines to achieve the fuel change. Steps based on sensitive ram push are added to reduce the risk of failing to close the latch at the correct position to properly support the fuel string. Changes are also required to the protective interlocks to allow fuelling with flow and reduce risk. A new fuel string supporting shield plug was designed and tested to reduce the risk of endplate cracking that could occur on the irradiated bundle that would have been supported directly by the channel latch. Some operational changes have been incorporated to accommodate this new shield plug. Considerable testing has been carried out on all aspects of fuel handling where fuelling with flow differs from the reference fuelling against flow. (author). 3 figs.

Advanced construction methods for new nuclear power plants

International Nuclear Information System (INIS)

Bilbao y Leon, Sama; Cleveland, John; Moon, Seong-Gyun; Tyobeka, Bismark

2009-01-01

The length of the construction and commissioning phases of nuclear power plants have historically been longer than for conventional fossil fuelled plants, often having a record of delays and cost overruns as a result from several factors including legal interventions and revisions of safety regulations. Recent nuclear construction projects however, have shown that long construction periods for nuclear power plants are no longer the norm. While there are several inter-related factors that influence the construction time, the use of advanced construction techniques has contributed significantly to reducing the construction length of recent nuclear projects. (author)

Design of on-power fuelling machines

International Nuclear Information System (INIS)

Jackson, W.H.

2004-01-01

In May 1957, CGE was asked to design a fuelling machine for NPD2 Reactor. Two fuelling machines were required, one at each end of the reactor, that could either push the fuel bundles through the reactor or accept the bundles being pushed out. The machines had to connect on to the end fittings of the same tube, seal, fill with heavy water and pressure up to 1000 psi without external leaks. Each machine had to remove the tube seal plug from its end fitting and store it in an indexing magazine, which also had to hold up to six fuel bundles, or retrieve that many, if the magazine was empty. There was also the provision to store a spare plug. When finished moving fuel bundles, the tube plugs were to be replaced and tested for leaks, before the fuelling machines would be detached from the end fittings. This was all to be done by remote control. By late September 1957, sufficient design features were on paper and CGE management made a presentation to AECL at Chalk River Laboratories and this proposal was later accepted

Waste Minimization Policy at the Romanian Nuclear Power Plant

International Nuclear Information System (INIS)

Andrei, V.; Daian, I.

2002-01-01

The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) in Romania was designed to maintain acceptable levels of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation. In accordance with terminology of the International Atomic Energy Agency (IAEA), this system consists of the ''pretreatment'' of solid and organic liquid radioactive waste, which may include part or all of the following activities: collection, handling, volume reduction (by an in-drum compactor, if appropriate), and storage. Gaseous and aqueous liquid wastes are managed according to the ''dilute and discharge'' strategy. Taking into account the fact that treatment/conditioning and disposal technologies are still not established, waste minimization at the source is a priority environmental management objective, while waste minimization at the disposal stage is presently just a theoretical requirement for future adopted technologies . The necessary operational and maintenance procedures are in place at Cernavoda to minimize the production and contamination of waste. Administrative and technical measures are established to minimize waste volumes. Thus, an annual environmental target of a maximum 30 m3 of radioactive waste volume arising from operation and maintenance has been established. Within the first five years of operations at Cernavoda NPP, this target has been met. The successful implementation of the waste minimization policy has been accompanied by a cost reduction while the occupational doses for plant workers have been maintained at as low as reasonably practicable levels. This paper will describe key features of the waste management system along with the actual experience that has been realized with respect to minimizing the waste volumes at the Cernavoda NPP

Device for district heating with utilization of waste heat from power plants

International Nuclear Information System (INIS)

Korek, J.

1976-01-01

In order to utilize the waste heat developing in power plants - especially in nuclear power plants - the author suggests to lead the waste heat of the coolers for oil (which the bearings are lubricated with), hydrogen (which serves for the stator rotor-cooling), and the stator cooling water to the circulating district heating water and to arrange these heat exchangers one behind another or parallel to each other in the water circuit of the district heating system. The oil cooler of the engine transformer is also connected with the circulation of the district heating water. The runback water of the district heating network could thus be heated from approx. 40 0 C up to 65 0 C. (UA) [de

Power plant waste disposals in open-cast mines

Energy Technology Data Exchange (ETDEWEB)

Herstus, J.; Stastny, J. [AGE s.r.o. - Aplikovana Geotechnika a Ekologie, Thamova (Czechoslovakia)

1995-12-01

High population density in Czech Republic has led, as well as in other countries, to strong NIMBY syndrome influencing the waste disposal location. The largest thermal power plants are situated in neighborhood of extensive open-cast brown coal mines with huge area covered by tipped clayey spoil. Such spoil areas, technically almost useless, are potential space for power giant waste disposal position. There are several limitations, based on specific structural features of tipped clayey spoil, influencing decision to use such area as site for waste disposal. Low shear strength and extremely high compressibility belong to the geotechnical limitations. High permeability of upper ten or more meters of tipped spoil and its changes with applied stress level belongs to transitional features between geotechnical and environmental limitations. The problems of ash and FGD products stabilized interaction with such subgrade represent environmental limitation. The paper reports about the testing procedure developed for thickness and permeability estimation of upper soil layer and gives brief review of laboratory and site investigation results on potential sites from point of view of above mentioned limitations. Also gives an outline how to eliminate the influence of unfavorable conditions.

Leachability of radionuclides from cement solidified waste forms produced at operating nuclear power plants

International Nuclear Information System (INIS)

Croney, S.T.

1985-03-01

This study determined the leachability indexes of radionuclides contained in solidified liquid wastes from operating nuclear power plants. Different sizes of samples of cement-solidified liquid wastes were collected from two nuclear power plants - a pressurized water reactor and a boiling water reactor - to correlate radionuclide leaching from small- and full-sized (55-gallon) waste forms. Diffusion-based model analysis (ANS 16.1) of measured radionuclide leach data from both small- and full-sized samples was performed and indicate that leach data from small samples can be used to determine leachability indexes for full-sizes waste forms. The leachability indexes for cesium, strontium, and cobalt isotopes were determined for waste samples from both plants according to the models used for ANS 16.1. The leachability indexes for the pressurized water reactor samples were 6.4 for cesium, 7.1 for strontium, and 10.4 for cobalt. Leachability indexes for the boiling water reactor samples were 6.5 for cesium, 8.6 for strontium, and 11.1 for cobalt

ORC power plant for electricity production from forest and agriculture biomass

International Nuclear Information System (INIS)

Borsukiewicz-Gozdur, A.; Wiśniewski, S.; Mocarski, S.; Bańkowski, M.

2014-01-01

Highlights: • Results for three variants of CHP plant fuelled by sawmill biomass are presented. • Octamethyltrisiloxane, MDM, methanol and H 2 O working fluids was conducted in CHP. • CHP with internal regeneration and “dry” working fluid has the highest electric power. • Power output, drying heat and drying temperature depend on CHP variant and ORC fluid. - Abstract: The paper presents the calculation results for three variants of CHP plant fuelled by sawmill biomass. The plant shall produce electricity and heat for a drying chamber. An analysis of the system efficiency for four different working fluids was conducted: octamethyltrisiloxane, methylcyclohexane, methanol and water. The highest electric power was obtained for the system with internal regeneration and methylcyclohexane applied as the “dry” working fluid, the highest temperature to supply the drying chamber was obtained for the system with external regeneration and octamethyltrisiloxane applied as the working fluid. The results of the analysis indicate that, by proper choice of the working fluid and of the regeneration variant (internal or external), it is possible to “adjust” the work of the system to the needs and expectations of the plant investor (user)

Availability of thermal power plants 1977-1986

International Nuclear Information System (INIS)

Nitsch, D.; Schmitz, H.

1987-01-01

To get a picture of power plant availability and its influencing factors, availability data have been acquired and evaluated by VGB according to different design and operation parameters since 1970. The present volume is the 16th annual statistics since 1970. It covers the decade of 1977 to 1986 and contains availability data of 384 power plants in Germany and abroad, with a total of 94.896 MW and 3.768 plant years. Data are presented on fossil-fuelled units, units with a combined gas/steam cycle, nuclear power plants and gas turbine systems, with further sub-categories according to unit size, fuel, type, years of operation, and operating regime. German plants are reviewed separately. All power data are gross data measured at the generator terminals. For a comparative evaluation, the data of 1986 are supplemented by yearly averages since 1977 and averages for the decade from 1977 to 1986. Since 1978, nonavailability data are categorized as 'unscheduled' and 'scheduled' nonavailabilities. For availability data of 1970 to 1976, see the VGB publication 'Availability of thermal power plants, 1970 to 1981'. (orig./UA) [de

Integration of torrefaction with steam power plant

Energy Technology Data Exchange (ETDEWEB)

Zakri, B.; Saari, J.; Sermyagina, E.; Vakkilainen, E.

2013-09-01

Torrefaction is one of the pretreatment technologies to enhance the fuel characteristics of biomass. The efficient and continuous operation of a torrefaction reactor, in the commercial scale, demands a secure biomass supply, in addition to adequate source of heat. Biorefinery plants or biomass-fuelled steam power plants have the potential to integrate with the torrefaction reactor to exchange heat and mass, using available infrastructure and energy sources. The technical feasibility of this integration is examined in this study. A new model for the torrefaction process is introduced and verified by the available experimental data. The torrefaction model is then integrated in different steam power plants to simulate possible mass and energy exchange between the reactor and the plants. The performance of the integrated plant is investigated for different configurations and the results are compared. (orig.)

Low-level radioactive waste management in EDF nuclear power plants (FRANCE)

International Nuclear Information System (INIS)

Boussard, C.

1991-01-01

This paper shows some recent examples of Low-level radioactive waste management in EDF nuclear power plants: - Radioactive liquid wastes proceeding from steam generators leaching (NOGENT SUR SEINE-1 REACTOR) - Thermal insulation proceeding from heat exchanger and blower (CHINON-2 REACTOR) - Old iron from reactor dismantling (CHINON-3 REACTOR, MARCOULE G1 REACTOR, MARCOULE G2-G3 REACTORS) - fresh air filter and fire detector - CHINON-2 REACTOR breaker chambers

Design methods for high temperature power plant structures

International Nuclear Information System (INIS)

Townley, C.H.A.

1984-01-01

The subject is discussed under the headings: introduction (scope of paper - reviews of design methods and design criteria currently in use for both nuclear and fossil fuelled power plant; examples chosen are (a) BS 1113, representative of design codes employed for power station boiler plant; (b) ASME Code Case N47, which is being developed for high temperature nuclear reactors, especially the liquid metal fast breeder reactor); design codes for power station boilers; Code Case N47 (design in the absence of thermal shock and thermal fatigue; design against cyclic loading at high temperature; further research in support of high temperature design methods and criteria for LMFBRs); concluding remarks. (U.K.)

Financing the management of wastes generated by the Swiss nuclear power plants

International Nuclear Information System (INIS)

Baumgartner, K.; Enderli, P.

1996-01-01

Since the beginning of nuclear power production in Switzerland, expenditure on managing operational waste and spent fuel has represented a fixed component of the kilowatt hour production costs which is calculated on the basis of careful estimates of waste management costs. For making these estimates, the operators of the nuclear power plants at Beznau, Muehleberg, Goesgen and Leibstadt rely on calculations performed by recognised nuclear fuel specialists and on data and empirical values from domestic and foreign waste management organisations. The calculations are subject to periodic review and, where necessary, take into account new information. The last review was concluded at the beginning of 1996. (author) 1 fig

Fuel cycle modelling of open cycle thorium-fuelled nuclear energy systems

International Nuclear Information System (INIS)

Ashley, S.F.; Lindley, B.A.; Parks, G.T.; Nuttall, W.J.; Gregg, R.; Hesketh, K.W.; Kannan, U.; Krishnani, P.D.; Singh, B.; Thakur, A.; Cowper, M.; Talamo, A.

2014-01-01

Highlights: • We study three open cycle Th–U-fuelled nuclear energy systems. • Comparison of these systems is made to a reference U-fuelled EPR. • Fuel cycle modelling is performed with UK NNL code “ORION”. • U-fuelled system is economically favourable and needs least separative work per kWh. • Th–U-fuelled systems offer negligible waste and proliferation resistance advantages. - Abstract: In this study, we have sought to determine the advantages, disadvantages, and viability of open cycle thorium–uranium-fuelled (Th–U-fuelled) nuclear energy systems. This has been done by assessing three such systems, each of which requires uranium enriched to ∼20% 235 U, in comparison to a reference uranium-fuelled (U-fuelled) system over various performance indicators, spanning material flows, waste composition, economics, and proliferation resistance. The values of these indicators were determined using the UK National Nuclear Laboratory’s fuel cycle modelling code ORION. This code required the results of lattice-physics calculations to model the neutronics of each nuclear energy system, and these were obtained using various nuclear reactor physics codes and burn-up routines. In summary, all three Th–U-fuelled nuclear energy systems required more separative work capacity than the equivalent benchmark U-fuelled system, with larger levelised fuel cycle costs and larger levelised cost of electricity. Although a reduction of ∼6% in the required uranium ore per kWh was seen for one of the Th–U-fuelled systems compared to the reference U-fuelled system, the other two Th–U-fuelled systems required more uranium ore per kWh than the reference. Negligible advantages and disadvantages were observed for the amount and the properties of the spent nuclear fuel (SNF) generated by the systems considered. Two of the Th–U-fuelled systems showed some benefit in terms of proliferation resistance of the SNF generated. Overall, it appears that there is little

State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants

International Nuclear Information System (INIS)

1980-04-01

A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report

Waste management at the Ardennes power plant

International Nuclear Information System (INIS)

Abraham, J.P.

1979-01-01

In 1976, the SENA (with the participation of EDF, CEA and CEC in the framework of a research program on the management and storage of radioactive wastes) has developed an industrial pilot plant for the encapsulation of wastes in thermosetting polyester resins. The industrial putting in operation of the plant will enable most of the wastes from the nuclear station to be processed. The quality of products will be improved and the volume and processing cost reduced

Defense waste processing facility at Savannah River Plant. Instrument and power jumpers

International Nuclear Information System (INIS)

Heckendorm, F.M. II.

1983-06-01

The Defense Waste Processing Facility (DWPF) for waste vitrification at the Savannah River Plant is in the final design stage. Development of equipment interconnecting devices or jumpers for use within the remotely operated processing canyon is now complete. These devices provide for the specialized instrument and electrical requirements of the DWPF process for low-voltage, high-frequency, and high-power interconnections

Using thermal power plants waste for building materials

Science.gov (United States)

Feduik, R. S.; Smoliakov, A. K.; Timokhin, R. A.; Batarshin, V. O.; Yevdokimova, Yu G.

2017-10-01

The recycled use of thermal power plants (TPPs) wastes in the building materials production is formulated. The possibility of using of TPPs fly ash as part of the cement composite binder for concrete is assessed. The results of X-ray diffraction and differential thermal analysis as well as and materials photomicrographs are presented. It was revealed that the fly ash of TPPs of Russian Primorsky Krai is suitable for use as a filler in cement binding based on its chemical composition.

Advanced fuelling system for ITER

Energy Technology Data Exchange (ETDEWEB)

Raman, Roger [University of Washington, Seattle, WA (United States)], E-mail: raman@aa.washington.edu

2008-12-15

Steady-state high-performance discharges in reactors, such as the Advanced Tokamak (AT) scenarios would rely on optimized density and pressure profiles that must be maintained. This maximizes the bootstrap current fraction, reduces reactor recycling power and reduces thermal stresses. Other than a system for the balance of current drive not provided by bootstrap current drive, no other sources of input power, such as from neutral beams, are allowed. For these systems, a precision fuelling system would be the ideal way to control the fusion burn by controlling and maintaining the required pressure profile. This requires a fuelling system that is capable of depositing fuel at any radial location within the plasma while at the same time not altering the density profile to a level that degrades the required pressure profile. Present fuelling systems are incapable of meeting these requirements. An advanced fuelling system based on Compact Toroid injection has the potential to meet these needs while simultaneously providing a source of toroidal momentum input. Description of a conceptual Compact Toroid fueller for ITER is presented in conjunction with a plan for developing this much needed technology.

Nuclear power. Volume 1. Nuclear power plant design

International Nuclear Information System (INIS)

Pedersen, E.S.

1978-01-01

NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 1 contains the following chapters; (1) nuclear reactor theory; (2) nuclear reactor design; (3) types of nuclear power plants; (4) licensing requirements; (5) shielding and personnel exposure; (6) containment and structural design; (7) main steam and turbine cycles; (8) plant electrical system; (9) plant instrumentation and control systems; (10) radioactive waste disposal (waste management) and (11) conclusion

Calculations on heavy-water moderated and cooled natural uranium fuelled power reactors

International Nuclear Information System (INIS)

Pinedo V, J.L.

1979-01-01

One of the codes that the Instituto Nacional de Investigaciones Nucleares (Mexico) has for the nuclear reactors design calculations is the LEOPARD code. This work studies the reliability of this code in reactors design calculations which component materials are the same of the heavy water moderated and cooled, natural uranium fuelled power reactors. (author)

Availability of thermal power plants

International Nuclear Information System (INIS)

Nitsch, D.; Schmitz, H.

1981-01-01

Availability data based on unique uniform, and clearly defined concepts and methods of acquisition have been compiled by the VGB since 1970. The data are published in anual reports. These reports contain availability data of fossil-fuelled units, combined gas/steam units, nuclear power plants, and gas turbine plants in Germany and abroad, listed by unit size fuel type, time of operation, and application. For the purpose of comparison, the data for the years since 1970 are presented as well as data averaged for the whole period under report. The main results for the year 1980 are presented now that the greater part of the plants has been evaluated. The complete evaluation will be published towards the end of 1981. (orig.) [de

The use of thermal wastes from nuclear power plants

International Nuclear Information System (INIS)

Balligand, P.

1976-01-01

A glance at the diagrams which summarize national primary energy consumption expressed in tons of oil equivalent for various needs shows that 50% and sometimes more of the energy imput is lost during use. It is only logical that an attempt is being made to use this lost energy. However the solution is not an easy one, as it generally involves energy which is widely distributed in low temperature wastes, at any event in the case of present-day electrical power plants, and the economics of the project must be carefully examined. In the case of agriculture, it may be asserted that many solutions for recovery are available depending on the type of waste. These uses are likely to reduce the fuel consumption of agricultural farms and the areas which can be heated are considerable. However, this means concentrating agricultural installations likely to benefit from hot water economic problems. As for urban heating with a heat pump, in order for the system to be economical, we feel that water must be available at least at the temperature of the water from cooling towers, a minimum of 30 0 C, together with a high user density in the immediate vicinity of the power plant. (orig./RW) [de

A comprehensive economic evaluation of integrated desalination systems using fossil fuelled and nuclear energies and including their environmental costs

International Nuclear Information System (INIS)

Nisan, S.; Benzarti, N.

2008-01-01

Seawater desalination is now widely accepted as an attractive alternative source of freshwater for domestic and industrial uses. Despite the considerable progress made in the relevant technologies desalination, however, remains an energy intensive process in which the energy cost is the paramount factor. This Study is a first of a kind in that we have integrated the environmental costs into the power and desalination costs. The study has focused on the seawater desalination cost evaluation of the following systems. It is supposed that they will be operating in the co-generation mode (Simultaneous production of electrical power and desalted water) in 2015: Fossil fuelled based systems such as the coal and oil fired plants and the gas turbine combined cycle plant, coupled to MED, and RO; Pressurised water reactors such as the PWR-900 and the AP-600, coupled to MED, and RO; High temperature reactors such as the GT-MHR, the PBMR, coupled to MED, with the utilisation of virtually free waste-heat provided by these reactors. The study is made in real site-specific conditions of a site In Southern Europe. Sensitivity studies for different parameters such as the fossil fuel prices, interest and discount rates, power costs etc., have also been undertaken. The results obtained are then used to evaluate the financial interest of selected integrated desalination systems in terms of a detailed cash flow analysis, providing the net present values, pay back periods and the internal rate of returns. Analysis of the results shows that among the fossil fuelled systems the power and desalination costs by circulating fluidized bed coal fired plant would be the lowest with current coal prices. Those by oil fired plants would be highest. In all cases, integrated nuclear energy systems would lead to considerably lower power and water costs than the corresponding coal based systems. When external costs for different energies are internalized in power and water costs, the relative cost

Physico-chemical characterization of slag waste coming from GICC thermal power plant

Energy Technology Data Exchange (ETDEWEB)

Acosta, A.; Aineto, M.; Iglesias, I. [Laboratory of Applied Mineralogy, Universidad de Castilla-La Mancha, Ciudad Real Madrid (Spain); Romero, M.; Rincon, J.Ma. [The Glass-Ceramics Laboratory, Insituto Eduardo Torroja de Ciencias de la Construccion, CSIC, c/Serrano Galvache s/n, 28033, Madrid (Spain)

2001-09-01

The new gas installations of combined cycle (GICC) thermal power plants for production of electricity are more efficient than conventional thermal power plants, but they produce a high quantity of wastes in the form of slags and fly ashes. Nowadays, these by-products are stored within the production plants with, until now, no applications of recycling in other industrial processes. In order to evaluate the capability of these products for recycling in glass and ceramics inductory, an investigation for the full characterization has been made by usual physico-chemical methods such as: chemical analysis, mineralogical analysis by XRD, granulometry, BET, DTA/TG, heating microscopy and SEM/EDX.

A urine-fuelled soil-based bioregenerative life support system for long-term and long-distance manned space missions

Science.gov (United States)

Maggi, Federico; Tang, Fiona H. M.; Pallud, Céline; Gu, Chuanhui

2018-05-01

A soil-based cropping unit fuelled with human urine for long-term manned space missions was investigated with the aim to analyze whether a closed-loop nutrient cycle from human liquid wastes was achievable. Its ecohydrology and biogeochemistry were analysed in microgravity with the use of an advanced computational tool. Urine from the crew was used to supply primary (N, P, and K) and secondary (S, Ca and Mg) nutrients to wheat and soybean plants in the controlled cropping unit. Breakdown of urine compounds into primary and secondary nutrients as well as byproduct gases, adsorbed, and uptake fractions were tracked over a period of 20 years. Results suggested that human urine could satisfy the demand of at least 3 to 4 out of 6 nutrients with an offset in pH and salinity tolerable by plants. It was therefore inferred that a urine-fuelled life support system can introduce a number of advantages including: (1) recycling of liquids wastes and production of food; (2) forgiveness of neglect as compared to engineered electro-mechanical systems that may fail under unexpected or unplanned conditions; and (3) reduction of supply and waste loads during space missions.

Efficiency evaluation of gas fuelled and electric driven buses in the public transport sector

Energy Technology Data Exchange (ETDEWEB)

Aigner, Tobias Alexander

2013-07-01

The following report evaluates the efficiency of gas fuelled and electric driven buses in the public transport sector on a theoretical basis. The results indicate that the combination of CHP power plants and electric driven buses reach an overall efficiency of about 51% throughout the production chain (Well-to-Wheel), including heat distribution losses. The overall Well-to-Wheel efficiency for conventional gas turbines without heat recovery decreases to around 28%. For gas fuelled buses the Well-to-Wheel efficiency is about 30%. The Co2-emissions are evaluated based on the example of a #Left Double Quotation Mark#Volvo B10L CNG#Right Double Quotation Mark# gas bus and the electric driven #Left Double Quotation Mark#Eurabus 600#Right Double Quotation Mark#. The low energy consumption of the electric driven bus results in Co2-emissions of only 181.4 g Co2/km (Grid-to-Wheel). Depending on the utilised power plant technology the overall Co2-emissions (Well-to-Wheel) amount to 307.5 g Co2/km for a CHP power plant and 553.5 g Co2/km for a conventional gas turbine. On the other hand, gas fuelled buses emit about 1.25 kg Co2/km (Tank-to-Wheel), which is eightfold the emissions of an electrical bus. The Well-to-Tank emissions further increase to about 1.32 kg Co2/km. The emission calculation is based on real gas consumption data from a Norwegian public transport utility. The results indicate that the combination of CHP plants and electrical buses provide a much higher efficiency while reducing Co2-emissions. (author)

CANDU 9 fuelling machine carriage

Energy Technology Data Exchange (ETDEWEB)

Ullrich, D J; Slavik, J F [Atomic Energy of Canada Ltd., Saskatoon, SK (Canada)

1997-12-31

Continuous, on-power refuelling is a key feature of all CANDU reactor designs and is essential to maintaining high station capacity factors. The concept of a fuelling machine carriage can be traced to the early CANDU designs, such as the Douglas Point Nuclear Generating Station. In the CANDU 9 480NU unit, the combination of a mobile carriage and a proven fuelling machine head design comprises an effective means of transporting fuel between the reactor and the fuel transfer ports. It is a suitable alternative to the fuelling machine bridge system that has been utilized in the CANDU 6 reactor units. The CANDU 9 480NU fuel handling system successfully combines features that meet the project requirements with respect to fuelling performance, functionality, seismic qualification and the use of proven components. The design incorporates improvements based on experience and applicable current technologies. (author). 4 figs.

CANDU 9 fuelling machine carriage

International Nuclear Information System (INIS)

Ullrich, D.J.; Slavik, J.F.

1996-01-01

Continuous, on-power refuelling is a key feature of all CANDU reactor designs and is essential to maintaining high station capacity factors. The concept of a fuelling machine carriage can be traced to the early CANDU designs, such as the Douglas Point Nuclear Generating Station. In the CANDU 9 480NU unit, the combination of a mobile carriage and a proven fuelling machine head design comprises an effective means of transporting fuel between the reactor and the fuel transfer ports. It is a suitable alternative to the fuelling machine bridge system that has been utilized in the CANDU 6 reactor units. The CANDU 9 480NU fuel handling system successfully combines features that meet the project requirements with respect to fuelling performance, functionality, seismic qualification and the use of proven components. The design incorporates improvements based on experience and applicable current technologies. (author). 4 figs

Hydrogen Fuelling Stations

DEFF Research Database (Denmark)

Rothuizen, Erasmus Damgaard

. A system consisting of one high pressure storage tank is used to investigate the thermodynamics of fuelling a hydrogen vehicle. The results show that the decisive parameter for how the fuelling proceeds is the pressure loss in the vehicle. The single tank fuelling system is compared to a cascade fuelling......This thesis concerns hydrogen fuelling stations from an overall system perspective. The study investigates thermodynamics and energy consumption of hydrogen fuelling stations for fuelling vehicles for personal transportation. For the study a library concerning the components in a hydrogen fuelling...... station has been developed in Dymola. The models include the fuelling protocol (J2601) for hydrogen vehicles made by Society of Automotive Engineers (SAE) and the thermodynamic property library CoolProp is used for retrieving state point. The components in the hydrogen fuelling library are building up...

Method of processing concentrated liquid waste in nuclear power plant

International Nuclear Information System (INIS)

Hasegawa, Kazuyuki; Kitsukawa, Ryozo; Ohashi, Satoru.

1988-01-01

Purpose: To reduce the oxidizable material in the concentrated liquid wastes discharged from nuclear power plants. Constitution: Nitrate bacteria are added to liquid wastes in a storage tank for temporarily storing concentrated liquid wastes or relevant facilities thereof. That is, nitrites as the oxidizable material contained in the concentrated liquid wastes are converted into nitrate non-deleterious to solidification by utilizing biological reaction of nitrate bacteria. For making the conversion more effectively, required time for the biological reaction of the nitrate bacteria is maintained from the injection of nitrate bacteria to solidification, thereby providing advantageous conditions for the propagation of the nitrate bacteria. In this way, there is no problem for the increase of the volume of the powdery wastes formed by the addition of inhibitor for the effect of oxidizable material. Further, heating upon solidification which is indispensable so far is no more necessary to simplify the facility and the operation. Furthermore, the solidification inhibiting material can be reduced stably and reliably under the same operation conditions even if the composition of the liquid wastes is charged or varied. (Kamimura, M.)

Power generation from waste wood

Energy Technology Data Exchange (ETDEWEB)

Nitsche, H

1980-04-18

Since the energy crisis, power generation from waste wood has become increasingly important. The most profitable way to use waste wood in woodworking plants with an annual production of 100 to 150,000 m/sup 3/ solid measure of wood chips and bark is by combustion and thermal energy recovery. In plants with an annual production of 10,000 m/sup 3/ solid measure of wood chips and bark, electric power generation is a suitable application.

The state of radioactive waste management and personnel radiation exposure in commercial nuclear power plants in fiscal 1981

International Nuclear Information System (INIS)

1982-01-01

Radioactive waste management: The owners of commercial nuclear power plants are obligated to control the release of gaseous and liquid radioactive wastes below the objective release levels, and to store solid wastes in containers on the site. As for the former, the released (radioactive) quantity in fiscal 1981 (from April, 1981, to March, 1982,) together with the objective levels are given for respective nuclear power stations; and as for the latter, the stored quantity and also the cumulative quantity up to the year are given. Radiation exposure: The owners of commercial nuclear power plants are obligated to control the personnel exposure below the permissible level. The personnel exposure dose in fiscal 1981 is given for respective nuclear power station. (Mori, K.)

Volume reduction of dry active waste by use of a waste sorting table at the Brunswick nuclear power plant

International Nuclear Information System (INIS)

Snead, P.B.

1988-01-01

Carolina Power and Light Company's Brunswick nuclear power plant has been using a National Nuclear Corporation Model WST-18 Waste Sorting Table to monitor and sort dry active waste for segregating uncontaminated material as a means of low-level waste volume reduction. The WST-18 features 18 large-area, solid scintillation detectors arranged in a 3 x 6 array underneath a sorting/monitoring surface that is shielded from background radiation. An 11-week study at Brunswick showed that the use of the waste sorting table resulted in dramatic improvements in both productivity (man-hours expended per cubic foot of waste processed) and monitoring quality over the previous hand-probe frisking method. Use of the sorting table since the study has confirmed its effectiveness in volume reduction. The waste sorting table paid for its operation in volume reduction savings alone, without accounting for the additional savings from recovering reusable items

Safeguarding on-power fuelled reactors - instrumentation and techniques

International Nuclear Information System (INIS)

Waligura, A.; Konnov, Y.; Smith, R.M.; Head, D.A.

1977-05-01

Instrumentation and techniques applicable to safeguarding reactors that are fuelled on-power, particularly the CANDU type, have been developed. A demonstration is being carried out at the Douglas Point Nuclear Generating Station in Canada. Irradiated nuclear materials in certain areas - the reactor and spent fuel storage bays - are monitored using photographic and television cameras, and seals. Item accounting is applied by counting spent-fuel bundles during transfer from the reactor to the storage bay and by placing these spent-fuel bundles in a sealed enclosure. Provision is made for inspection and verification of the bundles before sealing. The reactor's power history is recorded by a Track-Etch power monitor. Redundancy is provided so that the failure of any single piece of equipment does not invalidate the entire safeguards system. Several safeguards instruments and devices have been developed and evaluated. These include a super-8-mm surveillance camera system, a television surveillance system, a spent-fuel bundle counter, a device to detect dummy fuel bundles, a cover for enclosing a stack of spent-fuel bundles, and a seal suitable for underwater installation and ultrasonic interrogation. (author)

Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

International Nuclear Information System (INIS)

Horvath, J.; Dugovic, L.

1999-01-01

Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

Polyolephine waste recycling as source of power energy

Directory of Open Access Journals (Sweden)

Tisovski Štefan

2008-01-01

Full Text Available Polyolephine waste (polyetilene, polypropilene is the main source of environmental pollution. Depolymerization of waste in reactor under atmospheric pressure yields hydrocarbon mixture C1-C34. In turn, combustion of C1-C7 fraction provides reactor temperature regime. The plant is automated and energetically highly efficient. Small electric power is required for operating the plant. The waste originating from depolymerazation does not pollute the environment. Fraction C7-C34 not only serves for commercial purposes but also as a power energy provider within the waste deploymerization plant.

Nant-De-Chatillon: electric power generation by ORC (organic Rankine cycle) using waste heat from the Chatillon biogas plant; Nant-de-Chatillon: Production d'electricite par ORC a partir des rejets de chaleur du site de methanisation de Chatillon. Resume

Energy Technology Data Exchange (ETDEWEB)

Kane, M.; Gay, B.

2005-07-01

This report prepared for the Swiss Federal Office of Energy (SFOE) describes the practical realisation and testing of a heat recovery system based on a one-stage organic Rankine cycle with R134a as the working fluid. The waste heat has a temperature of 95 {sup o}C and originates from a gas engine that powers a small co-generation plant fuelled with biogas produced on-site. Two similar cycles have been built, ORC1 with one and ORC2 with two turbines. Only ORC1 has been tested so far. The maximum efficiency measured in these tests was 6.64% (theoretical Carnot-efficiency: 17 %) and the electric power output was 5.0 kW. The problems encountered during commissioning are described and recommendations for further improvements are given.

The Swedish concept for disposal of waste arising from the operation of nuclear power plants

International Nuclear Information System (INIS)

Carlsson, J.

1996-01-01

The Swedish nuclear power programme consists of 12 reactors producing 50% of the electricity in Sweden. It is stated by law that a waste producer has to make sure a safe handling and disposal of his radioactive waste. SKB is performing necessary activities on behalf of the waste producers. A system is in operation today that will manage all the radioactive waste produced in the country. The system consists of a transportation system, a final repository for operational waste and an interim storage facility for spent fuel. What remains to be built is an encapsulation plant for the spent fuel and a deep repository for final disposal of spent fuel and other long lived waste. All costs for managing and disposal of radioactive waste is paid by the owners of the nuclear power utilities. (author) 9 figs

Nuclear power plant decommissioning

International Nuclear Information System (INIS)

Yaziz Yunus

1986-01-01

A number of issues have to be taken into account before the introduction of any nuclear power plant in any country. These issues include reactor safety (site and operational), waste disposal and, lastly, the decommissioning of the reactor inself. Because of the radioactive nature of the components, nuclear power plants require a different approach to decommission compared to other plants. Until recently, issues on reactor safety and waste disposal were the main topics discussed. As for reactor decommissioning, the debates have been academic until now. Although reactors have operated for 25 years, decommissioning of retired reactors has simply not been fully planned. But the Shippingport Atomic Power Plant in Pennysylvania, the first large scale power reactor to be retired, is now being decommissioned. The work has rekindled the debate in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. (author)

Optimizing Waste Heat Recovery for Class A Biosolids Production from a Combined Cycle Power Plant

Energy Technology Data Exchange (ETDEWEB)

Soroushian, Fred

2003-07-01

The City of Corona serves a rapidly growing area of Southern California, The City operates three wastewater treatment plants (WWTPs) that produce reclaimed water for unrestricted reuse. The sludge from the three WWTPs is transported to a central sludge treatment facility located at WWTP No. 1. The sludge treatment facility consists of sludge receiving, thickening, anaerobic digestion, and dewatering. In the year 2000, the City was faced with two crises. First, the California power shortage and escalating cost of power severely impacted the industry and businesses. Second, bans on Class B biosolids land application and the shutdown of a local privatized composting facility where the bulk of the City's biosolids were processed or reused forced the City to transport bulk waste a much greater distance. To cost-effectively respond to these crises, the City decided to start generating and supplying power to its constituents by constructing a nominal 30-megawatt (MW) power plant. The feasibility study proved that locating the power plant at the City's largest WWTP produced significant synergies. The reclaimed water from the WWTP could be used for power plant cooling, the waste heat from the power plant could be recovered and used in Class A biosolids processes, the digester gas could be used for supplementing the fuel needs of the sludge dryer, and the combined facilities operation was more efficient than physically separate facilities. This paper presents the results of this analysis as well as the construction and operational aspects of the project. (author)

Treatment of fuel oil contaminated waste water from liquid fuel processing plants associated to thermal power plants or heat and power cogeneration plants

International Nuclear Information System (INIS)

Petrescu, S.

1996-01-01

According to the statistical data presented in the most important European and world meetings on environmental protection, the oil product amounts which pollute the surface water is estimated to be of about 6 mill. tones yearly out of which 35 %, 10 %, and 1 % come from oil tanks, natural sources, and offshore drilling, respectively, while 54 % reach seas and oceans trough rivers, rains a.o. Among the water consumers and users of Romania, the thermal power plants, belonging to RENEL (Romanian Electricity Authority), are the greatest. A part of the water with modified chemical-physical parameters, used for different technological processes, have to be discharged from the user precinct directly towards natural agents or indirectly through public sewage networks as domestic and industrial waste water. These waste waters need an adequate treatment before discharging as to meet the requirements imposed by the norms and regulations related to environment protection. For this purpose, before discharging, after using, the water must be circulated through the treatment plants designed and operated as to ensure the correction of the inadequate values of the residual water parameters. The paper presents the activities developed in the Institute for Power Studies and Design concerning the environmental protection against pollution produced by the entire power generation circuit, from the design phase up to product supplying. (author). 1 tab., 2 refs

Fuel cells fuelled by Saccharides

International Nuclear Information System (INIS)

Schechner, P.; Mor, L.; Sabag, N.; Rubin, Z.; Bubis, E.

2005-01-01

Full Text:Saccharides, like glucose, fructose and lactose, are ideal renewable fuels. They have high energy content, are safe, transportable, easy to store, non-flammable, non poisonous, non-volatile, odorless, easy to produce anywhere and abundant. Fuel Cells are electro-chemical devices capable to convert chemical energy into electrical energy from fuels, with theoretical efficiencies higher than 0.8 at room temperatures and with low pollutant emissions. Fuel Cells that can produce electricity form saccharides will be able to replace batteries, power electrical plants from biomass wastes, and serve as engines for transportation. In spite of these advantages, saccharide fuelled fuel cells are no available yet. Two obstacles hinder the feasibility of this potentially revolutionary device. The first is the high stability of the saccharides, which requires a good catalyst to extract the electrons from the saccharide fuel. The second is related to the nature of the Fuel Cells: the physical process takes place at the interface surface between the fuel and the electrode. In order to obtain high densities, materials with high surface to volume ratio are needed. Efforts to overcome these obstacles will be described. The use of saccharides as a fuel was treated from the thermodynamic point of view and compared with other common fuels currently used in fuel cells. We summarize measurements performed in a membrane less Alkaline Fuel Cell, using glucose as a fuel and KOH as electrolyte. The anode has incorporated platinum particles and operated at room temperature. Measurements were done, at different concentrations of glucose, of the Open Circuit Voltage, Polarization Curves and Power Density as function of the Current Density. The maximum Power Density reached was 0.61 mW/cm 2 when the Current density was 2.13 mA/cm 2 and the measured Open Circuit Voltage was 0.771 V

Thermodynamic evaluation of CHP (combined heat and power) plants integrated with installations of coal gasification

International Nuclear Information System (INIS)

Ziębik, Andrzej; Malik, Tomasz; Liszka, Marcin

2015-01-01

Integration of a CHP steam plant with an installation of coal gasification and gas turbine leads to an IGCC-CHP (integrated gasification combined cycle-combined heat and power). Two installations of coal gasification have been analyzed, i.e. pressurized entrained flow gasifier – case 1 and pressurized fluidized bed gasifier with CO_2 recirculation – case 2. Basing on the results of mathematical modelling of an IGCC-CHP plant, the algorithms of calculating typical energy indices have been derived. The following energy indices are considered, i.e. coefficient of heat performance and relative savings of chemical energy of fuels. The results of coefficients of heat performance are contained between 1.87 and 2.37. Values exceeding 1 are thermodynamically justified because the idea of cogeneration of heat and electricity based on combining cycles of the heat engine and heat pump the efficiency of which exceeds 1. Higher values concerning waste heat replace more thermodynamically effective sources of heat in CHP plants. Relative savings of the chemical energy of fuels are similar in both cases of IGCC-CHP plants and are contained between the lower value of the CHP (combined heat and power) plants fuelled with coal and higher value of CHP plants fired with natural gas. - Highlights: • Energy savings of fuel is an adequate measure of cogeneration. • Relative energy savings of IGCC-CHP is near the result of a gas and steam CHP. • COHP (coefficient of heat performance) can help to divide fuel between heat fluxes. • Higher values of COHP in the case of waste heat recovery result from the lower thermal parameters.

Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plants. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

The purpose of this Safety Guide is to provide recommendations to the regulatory body, focused on the operational aspects of radiation protection and radioactive waste management in nuclear power plants, and on how to ensure the fulfilment of the requirements established in the relevant Safety Requirements publications. It will also be useful for senior managers in licensee or contractor organizations who are responsible for establishing and managing programmes for radiation protection and for the management of radioactive waste. This Safety Guide gives general recommendations for the development of radiation protection programmes at nuclear power plants. The issues are then elaborated by defining the main elements of a radiation protection programme. Particular attention is paid to area classification, workplace monitoring and supervision, application of the principle of optimization of protection (also termed the 'as low as reasonably achievable' (ALARA) principle), and facilities and equipment. This Safety Guide covers all the safety related aspects of a programme for the management of radioactive waste at a nuclear power plant. Emphasis is placed on the minimization of waste in terms of both activity and volume. The various steps in predisposal waste management are covered, namely processing (pretreatment, treatment and conditioning), storage and transport. Releases of effluents, the application of authorized limits and reference levels are discussed, together with the main elements of an environmental monitoring programme

Quantitative analysis of the radioactive wastes to be generated in the Brazilian nuclear power plants

International Nuclear Information System (INIS)

Santos, Jose Mauro Esteves dos

1979-01-01

In the nuclear fuel cycle radioactive waste requiring special treatment (processing, transportation and disposal) is produced. For the implementation of a waste management program, parameters such as volume, specific activity, thermal power, gamma power, (alpha,η) and spontaneous fission neutron production rates are required. In this work, we have calculated: a) The specific activity, thermal power, gamma power and neutron production rate for the irradiated fuel of Angra II; b) The volumes of radioactive waste that will be produced in the nuclear fuel cycle in Brazil; c) The specific activity, thermal power, gamma power and neutron production rate for the high-level waste that will be produced during fuel reprocessing. In the short-term it is concluded that the major problems that will require solution will be the disposal of the low-level waste (volume V L ) and the interim storage of the irradiated fuel elements (volume V F ) generated in the nuclear power plants. For the years 1990 and 2010 these volumes are: (1990) V L = 16149 m 3 ; V F = 1287 m 3 and (2010) V L = 690506 m 3 , V F = 55051 m 3 . In the medium-term the problem of the interim storage of the high-level waste (volume V H ) must be solved. The volumes of this waste we have calculated for the years 2000 and 2010 are: (2000) V H = 50 m 3 and (2010) V H = 1265 m 3 . Long term evaluation of high-level waste disposal must be analysed to aid in initial studies of this problem. Several parameters of this waste have been calculated as a function of time after reprocessing. (author)

Classification of low-level radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

Stanford, R.E.L.

1984-01-01

The NRC regulation, 10 CFR Part 61, establishes three classes of wastes designated A, B, and C based on listed concentrations of specific nuclides. The NRC Branch Technical Position (BTP) relative to the required compliance program focused on extensive waste stream sampling and analysis as a means of compliance. To meet the above regulatory requirements, an engineering analysis approach for quantifying the concentrations and amounts of radionuclides of classification concern was developed as an alternative to an extensive and difficult waste sampling and analysis program. Essentially this methodology involves a material balance of radionuclides which for the most part originate in the reactor core and are transported to the waste streams by reactor coolants and whose concentration in the coolant is primarily a function of fuel performance. The use of scaling factors between readily measured key radionuclides and others required for classification have been published in Report AIF/NESP-027 entitled, Methodologies for Classification of Low-Level Radioactive Wastes from Nuclear Power Plants. Since then data from about 1000 samples on nuclide concentrations in various reactor waste streams from 65 units at 40 sites was collated, analyzed and evaluated to confirm the calculational methodology in AIF/NESP-027. In summary, the approach and results of the engineering analysis methodology were validated

'Capture ready' regulation of fossil fuel power plants - Betting the UK's carbon emissions on promises of future technology

International Nuclear Information System (INIS)

Markusson, Nils; Haszeldine, Stuart

2010-01-01

Climate change legislation requires emissions reductions, but the market shows interest in investing in new fossil fuelled power plants. The question is whether capture ready policy can reconcile these interests. The term 'capture ready' has been used a few years by the UK Government when granting licences for fossil fuelled power plants, but only recently has the meaning of the term been defined. The policy has been promoted as a step towards CCS and as an insurance against carbon lock-in. This paper draws on literature on technology lock-in and on regulation of technology undergoing development. Further, versions of the capture readiness concept proposed to date are compared. Capture readiness requirements beyond the minimum criterion of space on the site for capture operations are explored. This includes integration of capture and power plant, downstream operations, overall system integration and regulation of future retrofitting. Capture readiness comes with serious uncertainties and is no guarantee that new-built fossil plants will be abatable or abated in the future. As a regulatory strategy, it has been over-promised in the UK.

Process of liquid radioactive waste treatment in nuclear power plant and development trend

International Nuclear Information System (INIS)

Liu Jiean; Wang Xin; Liu Dan; Zhu Laiye; Chen Bin

2014-01-01

The popular liquid radioactive waste treatment methods in nuclear power plants (NPP) are Chemical precipitation, evaporation, ion exchange, membrane treatment, chemical coagulation and activated carbon absorption and so on. 'Filter + activated carbon absorption (Chemical coagulation) + ion exchange' has a good prospect for development, as its simple process, high decontamination factor, low energy consumption and smaller secondary wastes. Also the process is used in Sanmen and Haiyang Projects. The severe incident in NPP set an even higher demand on liquid radioactive waste treatment. The new type treatment materials, optimization of the existed treatment, combination of treatment and the mobile treatment facility is the development trend in liquid radioactive waste treatment in NPP. (authors)

Application of ion exchange in liquid radioactive waste management of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Pal, Puskar; Chopra, S K; Sharma, P D [Nuclear Power Corporation, Bhabha Atomic Research Centre, Mumbai (India)

1994-06-01

The operation of nuclear power plants would necessarily result in generation of gaseous, liquid and solid radioactive wastes. The wastes are treated/conditioned to ensure that the permissible discharge limits laid down by Atomic Energy Regulatory Board of India are complied with. The wastes are segregated on activity levels, types of radioisotopes present and chemical nature of liquid streams. The basic philosophy of various treatment techniques is to concentrate and contain as much activity as possible. It is of utmost importance that the wastes are effectively treated by proven methods/processes. The radiochemical nature of waste generated is one of the parameters to select a treatment/conditioning method. The paper presents an outline of various processes adopted for treatment of liquid waste and ion exchange processes, their application in liquid waste management in detail. Projected quantities of liquid wastes for the current designs are included. (author). 2 tabs.

Enhancement of LNG plant propane cycle through waste heat powered absorption cooling

International Nuclear Information System (INIS)

Rodgers, P.; Mortazavi, A.; Eveloy, V.; Al-Hashimi, S.; Hwang, Y.; Radermacher, R.

2012-01-01

In liquefied natural gas (LNG) plants utilizing sea water for process cooling, both the efficiency and production capacity of the propane cycle decrease with increasing sea water temperature. To address this issue, several propane cycle enhancement approaches are investigated in this study, which require minimal modification of the existing plant configuration. These approaches rely on the use of gas turbine waste heat powered water/lithium bromide absorption cooling to either (i) subcool propane after the propane cycle condenser, or (ii) reduce propane cycle condensing pressure through pre-cooling of condenser cooling water. In the second approach, two alternative methods of pre-cooling condenser cooling water are considered, which consist of an open sea water loop, and a closed fresh water loop. In addition for all cases, three candidate absorption chiller configurations are evaluated, namely single-effect, double-effect, and cascaded double- and single-effect chillers. The thermodynamic performance of each propane cycle enhancement scheme, integrated in an actual LNG plant in the Persian Gulf, is evaluated using actual plant operating data. Subcooling propane after the propane cycle condenser is found to improve propane cycle total coefficient of performance (COP T ) and cooling capacity by 13% and 23%, respectively. The necessary cooling load could be provided by either a single-effect, double-effect or cascaded and single- and double-effect absorption refrigeration cycle recovering waste heat from a single gas turbine operated at full load. Reducing propane condensing pressure using a closed fresh water condenser cooling loop is found result in propane cycle COP T and cooling capacity enhancements of 63% and 22%, respectively, but would require substantially higher capital investment than for propane subcooling, due to higher cooling load and thus higher waste heat requirements. Considering the present trend of short process enhancement payback periods in the

Safeguarding on-power fuelled reactors - instrumentation and techniques

International Nuclear Information System (INIS)

Waligura, A.; Konnov, Y.; Smith, R.M.; Head, D.A.

1977-01-01

Instrumentation and techniques applicable to safeguarding reactors that are fuelled on-power, particularly the CANDU type, have been developed. A demonstration is being carried out at the Douglas Point Nuclear Generating Station in Canada. Irradiated nuclear materials in certain areas - the reactor and spent fuel storage bays - are monitored using photographic and television cameras, and seals. Item accounting is applied by counting spent-fuel bundles during transfer from the reactor to the storage bay and by placing these spent-fuel bundles in a sealed enclosure. Provision is made for inspection and verification of the bundles before sealing. The reactor's power history is recorded by a track-etch power monitor. Redundancy is provided so that the failure of any single piece of equipment does not invalidate the entire safeguards system. Several safeguards instruments and devices have beeen developed and evaluated. These include a super-8 mm surveillance camera system, a television surveillance system, a spent-fuel bundle counter, a device to detect dummy fuel bundles, a cover for enclosing a stack of spent-fuel bundles, and a seal suitable for underwater installation and ultrasonic interrogation. The information provided by these different instruments should increase the effectiveness of Agency safeguards and, when used in combination with other measures, will facilitate inspection at reactor sites

The IPRP (Integrated Pyrolysis Regenerated Plant) technology: From concept to demonstration

International Nuclear Information System (INIS)

D’Alessandro, Bruno; D’Amico, Michele; Desideri, Umberto; Fantozzi, Francesco

2013-01-01

Highlights: ► IPRP technology development for distributed conversion of biomass and wastes. ► IPRP demonstrative unit combines a rotary kiln pyrolyzer to a 80 kWe microturbine. ► Main performances and critical issues are pointed out for different residual fuels. -- Abstract: The concept of integrated pyrolysis regenerated plant (IPRP) is based on a Gas Turbine (GT) fuelled by pyrogas produced in a rotary kiln slow pyrolysis reactor, where waste heat from GT is used to sustain the pyrolysis process. The IPRP plant provides a unique solution for microscale (below 250 kW) power plants, opening a new and competitive possibility for distributed biomass or wastes to energy conversion systems. The paper summarizes the state of art of the IPRP technology, from preliminary numerical simulation to pilot plant facility, including some new available data on pyrolysis gas from laboratory and pilot plants.

Evaluation of nuclear power plant siting by probabilistic assessment of environmental impacts

International Nuclear Information System (INIS)

Vuori, S.

1978-01-01

The work consists of the description of a probabilistic consequence assessment model ARANO, and the individual calculation schemes therein included. This assessment model has been applied to the risk/benefit and cost/benefit analyses of the siting of nuclear power plants. In addition, there have been made some comparisons with the alternative fossil fuelled energy production scenarios. (author)

Renewable energy in Switzerland - Potential of waste-water treatment plants, waste-incineration plants and drinking water supply systems - Strategical decisions in politics

International Nuclear Information System (INIS)

Kernen, M.

2006-01-01

This article discusses how waste-water treatment plants, waste-incineration plants and drinking water supply systems make an important contribution to the production of renewable energy in Switzerland. Financing by the 'Climate-Cent' programme, which finances projects involving the use of renewable energy, is discussed. Figures are quoted on the electrical energy produced in waste-water treatment plants, waste-incineration plants and combined heat and power generation plant. Eco-balances of the various systems are discussed. Political efforts being made in Switzerland, including the 'Climate Cent', are looked at and promotion provided by new energy legislation is discussed. Eco-power and the processing of sewage gas to meet natural gas quality standards are discussed, as are energy analysis, co-operation between various research institutions and external costs

Radioactive waste management in nuclear power plants with WWER-type reactors

Energy Technology Data Exchange (ETDEWEB)

Dlouhy, Z; Napravnik, J; Safar, O

1975-05-01

The possibilities of radioactive waste solidification in nuclear power plants with LWR reactors (of the WWER type) and the problems of their safe storage in Czechoslovakia are discussed. The most suitable method for the treatment of emitted sorbents and concentrates seems to be their incorporation in bitumen or concrete. In the disposal of solidified blocks all requirements should be met including the selection of suitable sites and of convenient methods of transportation. A preliminary economic estimate shows that the storage of bitumen-incorporated wastes in trenches seems to be less expensive from the point of view of exploitation of the storage facility as well as from the point of view of investment.

Management of radioactive waste nuclear power plants

International Nuclear Information System (INIS)

Dlouhy, Z.; Marek, J.

1976-01-01

The authors give a survey of the sources, types and amounts of radioactive waste in LWR nuclear power stations (1,300 MWe). The amount of solid waste produced by a Novovorenezh-type PWR reactor (2 x 400 resp. 1 x 1,000 MWe) is given in a table. Treatment, solidification and final storage of radioactive waste are shortly discussed with special reference to the problems of final storage in the CSR. (HR) [de

Core fuelling to produce peaked density profiles in large tokamaks

International Nuclear Information System (INIS)

Mikkelsen, D.R.; McGuire, K.M.; Schmidt, G.L.; Zweben, S.J.

1995-01-01

Peaking the density profile increases the usable bootstrap current and the average fusion power density; this could reduce the current drive power and increase the net output of power producing tokamaks. The use of neutral beams and pellet injection to produce peaked density profiles is assessed. It is shown that with radially 'hollow' diffusivity profiles (and no particle pinch) moderately peaked density profiles can be produced by particle source profiles that are peaked off-axis. The fuelling penetration requirements can therefore be relaxed and this greatly improves the feasibility of generating peaked density profiles in large tokamaks. In particular, neutral beam fuelling does not require Megavolt particle energies. Even with beam voltages of ∼ 200 keV, however, exceptionally good particle confinement is needed to achieve net electrical power generation. The required ratio of particle to thermal diffusivities is an order of magnitude outside the range reported for tokamaks. In a system with no power production requirement (e.g., neutron sources) neutral beam fuelling should be capable of producing peaked density profiles in devices as large as ITER. Fuelling systems with low energy cost per particle - such as cryogenic pellet injection - must be used in power producing tokamaks when τ P ∼ τ E . Simulations with pellet injection speeds of 7 km/s show that the peaking factor, n e0 / e >, approaches 2. (author). 65 refs, 8 figs

Structural radioactive waste from 'retubing/refurbishment' of Embalse nuclear power plant. Regulatory perspective

International Nuclear Information System (INIS)

Alvarez, Daniela E.; Lee Gonzales, Horacio M.; Medici, Marcela A.; Piumetti, Elsa H.

2009-01-01

Unlike the building of a new nuclear reactor, the 'retubing / refurbishment' of nuclear reactors that have been in operation for many years, involves the replacement of components in a radioactive environment. This requires a carefully planned radiation protection program to ensure protection of workers, the public and the environment as well as a radioactive waste management program for those radioactive waste generated during the process, which go beyond those generated during the normal operation and maintenance of the plant. Nucleoelectrica Argentina Sociedad Anonima (NA-SA) is scheduled to conduct the Life Extension Process of Embalse Nuclear Power Plant (CNE) which essentially consist of 'retubing / refurbishment' of the installation. The Nuclear Regulatory Authority (ARN) will then have an important activity related to the above process. In particular, this paper will describe some points of interest related to the generation and management of radioactive waste during the 'retubing / refurbishment' of the CNE, from the regulatory point of view. (author)

Nuclear power for developing countries

International Nuclear Information System (INIS)

Hirschmann, H.; Vennemann, J.

1980-01-01

The paper describes the energy policy quandary of developing countries and explains why nuclear power plants of a suitable size - the KKW 200 MW BWR nuclear power plant for electric power and/or process steam generation is briefly presented here - have an economic advantage over fossil-fuelled power plants. (HP) [de

Nuclear Power, its Waste in the World and in Turkey

OpenAIRE

Temiz, Fatih

2017-01-01

Nuclear power plants were born in 1950s. Taking only 30 grams of used fuel annually for a person’s energy consumption many countries built their own nuclear power plants. In this story, there is the fuel on one hand and the waste on the other. In general sense, used up fuel rods from nuclear reactors and the waste from reprocessing plants are referred to as nuclear waste. These wastes can be stored for decades in the cooling pools of nuclear reacto...

Treatment of waste water containing solid particles (coal-ash-water suspensions) from 500 MW blocks of brown coal power plants

Energy Technology Data Exchange (ETDEWEB)

Morgenstern, H

1981-01-01

This paper presents a technological scheme and details on efficiency of the waste water cleaning installation in the 4 x 500 MW Boxberg III brown coal power plant. The power plant waste water contains between 0.1 and 100 kg of solids per m/sup 3/ of waste water; it requires cleaning to the environmental standard of up to 30 mg/l. The water cleaning installation consists of a coarse grain settling tank 30.7 m long, four one chamber thickeners with a 22 m diameter each, using aluminium sulfate as flocculent, and a water purification basin. The coarse grain settling tank is furnished with a continuously working chain scraper for removal of up to 100 m/sup 3//d of sludge from the bottom of the tank. Technological parameters of the settling tank are provided. Details of the tank's water cleaning performance are compared to the coarse grain settling tank at the Hagenwerder power plant. A list of the percentage of grain sizes removed from waste waters at both power plants is given. It is concluded that 85% of solids are removed from the Boxberg III waste water at the first water purification stage with a coarse grain settling tank and that use of continuously working chain scrapers is successful for removal of sludge with high water content and with a high content of fines in the grain size below 0.1 mm.

Waste-heat disposal from US geothermal power plants: An update

Science.gov (United States)

Robertson, R. C.

1982-05-01

Some of the more interesting and significant methods that are currently being studied in the US for reducing waste heat dissipation system costs and water consumption are: (1) allowing plant power output to vary with ambient conditions; (2) use of ammonia to transport waste heat from the turbine condenser to air-cooled coils; (3) development of a plastic-membrane type wet/dry tower; (4) marketing of steam turbines that can tolerate a wider range of back pressure; (5) use of circulating water storage to delay heat dissipation until more favorable conditions exist; (6) development of tubes with enhanced heat transfer surfaces to reduce condenser capital costs; and (7) use of evaporative condensers to reduce costs in binary cycles. Many of these projects involve large scale tests that are now fully installed and producing some preliminary data.

Management of radioactive wastes from the operation of nuclear power plants

International Nuclear Information System (INIS)

Hawickhorst, W.

1997-01-01

A prerequisite for the acceptance of the nuclear energy system is the effective management of the rad-wastes. Among the wastes to be considered, there are the wastes from the operation and decommissioning of nuclear power plants, as well as those from the nuclear fuel cycle. For the management of operating wastes, processes and facilities optimized in the course of several decades, are available, with which the raw solid and liquid wastes can be reduced in volume and turned into products which are physically and chemically stable and thus suitable for final disposal. The management of spent fuel can be done either by direct final disposal or reprocessing. The required interim storage facilities are ready for operation. The methods and a facility for packaging spent fuel for direct final disposal are in an advanced stage of development and construction. If fuel assemblies are to be reprocessed abroad, the wastes generated from the process must be taken back. Decommissioning wastes have technical properties which correspond essentially to the various groups of operating wastes and can thus be processed with similar methods; however since large quantities of them are generated in relatively short times, they present particular logistic problems. All waste types end up in final disposal sites to be built under the responsibility of the federal government. A final disposal site for low level wastes is in operation. In addition, two final disposal projects for accommodating higher level wastes including spent fuel for direct disposal and vitrified wastes from reprocessing, are being pursued. (orig.)

Climate effects of electricity production fuelled by coal, forest slash and municipal solid waste with and without carbon capture

International Nuclear Information System (INIS)

Sathre, Roger; Gustavsson, Leif; Truong, Nguyen Le

2017-01-01

We analyse the climate implications of producing electricity in large-scale conversion plants using coal, forest slash and municipal solid waste with and without carbon capture and storage (CCS). We calculate the primary energy, carbon dioxide (CO_2) and methane (CH_4) emission profiles, and the cumulative radiative forcing (CRF) of different systems that produce the same amount of electricity. We find that using slash or waste for electricity production instead of coal somewhat increases the instantaneous CO_2 emission from the power plant, but avoids significant subsequent emissions from decaying slash in forests or waste in landfills. For slash used instead of coal, we find robust near- and long-term reductions in total emissions and CRF. Climate effects of using waste instead of coal are more ambiguous: CRF is reduced when CCS is used, but without CCS there is little or no climate benefits of using waste directly for energy, assuming that landfill gas is recovered and used for electricity production. The application of CCS requires more fuel, but strongly reduces the CO_2 emissions. The use of slash or waste together with CCS results in negative net emissions and CRF, i.e. global cooling. - Highlights: • Using slash or waste for energy emits CO_2 from power plants, but avoids CO_2 and CH_4 emissions from forests or landfills. • Using forest slash for energy instead of coal gives robust short- and long-term climate benefits. • Using waste instead of coal gives questionable climate benefits, if the waste would otherwise be landfilled properly.

Emissions from decentralised CHP plants 2007 - Energinet.dk Environmental project no. 07/1882. Project report 5 - Emission factors and emission inventory for decentralised CHP production

Energy Technology Data Exchange (ETDEWEB)

Nielsen, Malene; Nielsen, Ole-Kenneth; Thomsen, M.

2010-06-15

Updated emission factors for decentralised combined heat and power (CHP) plants with a capacity < 25MWe have been estimated based on project emission measurements as well as emission measurements performed in recent years that were collected. The emission factors valid for 2006/2007 have been estimated for the plant technologies: Municipal solid waste (MSW) incineration plants, plants combusting straw or wood, natural gas fuelled reciprocating engines, biogas fuelled engines, natural gas fuelled gas turbines, gas oil fuelled reciprocating engines, gas oil fuelled gas turbines, steam turbines combusting residual oil and reciprocating engines combusting biomass producer gas based on wood. The emission factors for MSW incineration plants are much lower than the emission factors that were estimated for year 2000. The considerable reduction in the emission factors is a result of lower emission limit values in Danish legislation since 2006 that has lead to installation of new and improved flue gas cleaning systems in most MSW incineration plants. For CHP plants combusting wood or straw no major technical improvements have been implemented. The emission factors for natural gas fuelled reciprocating engines have been reduced since year 2000 as a result of technical improvements that have been carried out due to lower emission limit values in Danish legislation. The NO{sub x} emission factor for natural gas fuelled gas turbines has decreased 62 % since year 2000. This is a result of installation of low-NO{sub x} burners in almost all gas turbines that has been necessary to meet new emission limits in Danish legislation. The emission measurements programme included screening of the emissions of HCB, PCB, PCDD/-F and PBDD/-F. Compared to the Danish national emission decentralized CHP plants are major emission sources for CH{sub 4}, NO{sub x}, SO{sub 2}, heavy metals and HCB. (author)

Calculation of Efficiencies of a Ship Power Plant Operating with Waste Heat Recovery through Combined Heat and Power Production

Directory of Open Access Journals (Sweden)

Mirko Grljušić

2015-05-01

Full Text Available The aim of this research was to investigate the possibility of a combined heat & power (CHP plant, using the waste heat from a Suezmax-size oil tanker’s main engine, to meet all heating and electricity requirements during navigation. After considering various configurations, a standard propulsion engine operating at maximum efficiency, combined with a supercritical Organic Rankine cycle (ORC system, was selected to supply the auxiliary power, using R245fa or R123 as the working fluid. The system analysis showed that such a plant can meet all heat and electrical power requirements at full load, with the need to burn only a small amount of supplementary fuel in a heat recovery steam generator (HRSG when the main engine operates at part load. Therefore, it is possible to increase the overall thermal efficiency of the ship’s power plant by more than 5% when the main engine operates at 65% or more of its specified maximum continuous rating (SMCR.

Radioactive waste management in the Chernobyl exclusion zone: 25 years since the Chernobyl nuclear power plant accident.

Science.gov (United States)

Oskolkov, Boris Y; Bondarkov, Mikhail D; Zinkevich, Lubov I; Proskura, Nikolai I; Farfán, Eduardo B; Jannik, G Timothy

2011-10-01

Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities in the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste-related problems in Ukraine and the Chernobyl Exclusion Zone and, in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program.

Decontamination process applied to radioactive solid wastes from nuclear power plants

International Nuclear Information System (INIS)

Franco, Milton B.; Kastner, Geraldo F.; Monteiro, Roberto Pellacani G.

2009-01-01

The process of decontamination is an important step in the economic operation of nuclear facilities. A large number of protective clothing, metallic parts and equipment get contaminated during the handling of radioactive materials in laboratory, plants and reactors. Safe and economic operation of these nuclear facilities will have a bearing on the extent to which these materials are reclaimed by the process of decontamination. The most common radioactive contaminants are fission products, corrosion products, uranium and thorium. The principles involved in decontamination are the same as those for an industrial cleaning process. However, the main difference is in the degree of cleaning required and at times special techniques have to be employed for removing even trace quantities of radioactive materials. This paper relate decontaminations experiences using acids and acids mixtures (HCl, HF, HNO 3 , KMnO 4 , C 2 H 2 O 4 , HBF 4 ) in several kinds of radioactive solid wastes from nuclear power plants. The result solutions were monitored by nuclear analytical techniques, in order to contribute for radiochemical characterization of these wastes. (author)

Effect of power-plant waste on farming in the surrounding regions

Energy Technology Data Exchange (ETDEWEB)

Kozel, J; Maly, V

1972-01-01

The results of research undertaken concerning the waste of two power plants in Czechoslovakia are presented. Increased dust was observed in the proximity of the waste as compared with distant sites. Some dirt was observed in the crops around the waste - this demonstrates the dust infestation of the crops. The content of ash in the organic dry matter in farm crops in the proximity of waste were also higher than in the same crops in unaffected regions. Sulfur compounds were found in the ash of organic matter and in its dry matter that exceed the normal values. Dust blocked the pores of the assimilation organs of crops, although the value was lower than in forest wood species, particularly conifers. In most cases the analyses of soil samples collected around the waste demonstrated an increase in lime content. The soils around the wastes were found to contain sulfates, in some cases in fairly high amounts. Spectral analysis revealed trace amounts of some microelements which might have a toxic effect if their contents were increased (As, Pb, Zn, Cr, Be, Ni, Co). The fly ash had a negative influence on the physical properties of soil in the surrounding fields. In the vicinity of the waste severe dampness of the fields was observed in some cases. The dampness of soil decreased with the distance from the waste although moisture values characteristic of soil dampness were found 400 meters from the waste.

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.)

Radioactive waste disposal by nuclear power plants in the light of operational economy

International Nuclear Information System (INIS)

Reinhard, H.; Schmidt, D.

1984-01-01

The expansion of power generation on the basis of nuclear energy in the Federal Republic of Germany calls for answers also to the questions arising at the level of operating efficiency from the radioactive waste disposal requirements necessarily associated with the operation of nuclear power plants. As these are measures of very long-term consequences and which are, for the greater part, only-coming up in future, not only the effects to be expected on the balance of trade and taxbalance, but also the influence on price calculation will be of paramount importance for public utilities. Moreover, because of the continually increasing financial reserves for radioactive waste disposal the financing aspects are gaining added weight; reliance on foreign capital, anyhow specific to that sector of industry, is much aggravated. (orig.) [de

Strategy for optimal operation of a biomass-fired cogeneration power plant

International Nuclear Information System (INIS)

Prasertsan, S.; Krukanont, P.; Nigamsritragul, P.; Kirirat, P.

2001-01-01

Biomass-fired cogeneration not only is an environmentally friendly energy production, but also possesses high energy conversion efficiency. Generally, the wood product industry requires both heat and electricity. Combined heat and power generation (cogeneration) using wood residue has a three-fold benefit: waste minimization, reduction of an energy-related production cost and additional income from selling the excess electricity to the utility. In reality, the process heat demand fluctuates according to the production activities in the factory. The fluctuation of process heat demand affects the cogeneration efficiency and the electricity output and, consequently, the financial return, since the prices of heat and electricity are different. A study by computer simulation to establish a guideline for optimum operation of a process heat fluctuating cogeneration power plant is presented. The power plant was designed for a sawmill and an adjacent plywood factory using wood wastes from these two processes. The maximum boiler thermal load is 81.9 MW while the electricity output is in the range 19-24 MW and the process heat 10-30 MW. Two modes of operation were studied, namely the full (boiler) load and the partial (boiler) load. In the full load operation, the power plant is operated at a maximum boiler thermal load, while the extracted steam is varied to meet the steam demand of the wood-drying kilns and the plywood production. The partial load operation was designed for the partially fuelled boiler to provide sufficient steam for the process and to generate electricity at a desired capacity ranging from the firmed contract of 19 MW to the turbine maximum capacity of 24 MW. It was found that the steam for process heat has an allowable extracting range, which is limited by the low pressure feed water heater. The optimum operation for both full and partial load occurs at the lower limit of the extracting steam. A guideline for optimum operation at various combinations of

Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

Energy Technology Data Exchange (ETDEWEB)

Larsson, Arne; Lidar, Per [Studsvik Nuclear AB, SE-611 82 Nykoeping (Sweden); Bergh, Niklas; Hedin, Gunnar [Westinghouse Electric Sweden AB, Fredholmsgatan 2, SE-721 63, Vaesteraas (Sweden)

2013-07-01

Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid

Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

International Nuclear Information System (INIS)

Larsson, Arne; Lidar, Per; Bergh, Niklas; Hedin, Gunnar

2013-01-01

Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

Nuclear power plant siting

International Nuclear Information System (INIS)

Sulkiewicz, M.; Navratil, J.

The construction of a nuclear power plant is conditioned on territorial requirements and is accompanied by the disturbance of the environment, land occupation, population migration, the emission of radioactive wastes, thermal pollution, etc. On the other hand, a nuclear power plant makes possible the introduction of district heating and increases the economic and civilization activity of the population. Due to the construction of a nuclear power plant the set limits of negative impacts must not be exceeded. The locality should be selected such as to reduce the unfavourable effects of the plant and to fully use its benefits. The decision on the siting of the nuclear power plant is preceded by the processing of a number of surveys and a wide range of documentation to which the given criteria are strictly applied. (B.H.)

Fuelling tomorrow's transport

International Nuclear Information System (INIS)

Cadwallader, S.; Donovan, N.

1995-11-01

Fuelling Tomorrow's Transport provides a thorough analysis of key industry trends; developments in technology, fuel use and efficiency; environmental and legislative constraints; and company and governmental policy. It discusses in detail the changes facing the transport industry and analyses how the various technological, political and economic developments will affect the industry into the next century. Key issues addressed include: current and future fuel use in road, marine and aviation transport; growth in the transport sector and the impact on the oil market; likely scenarios for future transport fuelling; the latest developments in alternative fuels and engines, including electricity, natural gas, nuclear power and liquid hydrogen, and the commercial feasibility of these technologies; government policy and current and proposed legislative and fiscal incentives for the development and take-up of alternative fuels and engines; the driving force of the environmental debate; the current research and development programmes of individual companies; and the commercial openings offered by these developments. (author)

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

The long term plan for the integration of nuclear power plants into the Turkish Electrical Power System

International Nuclear Information System (INIS)

Kutukcuoglu, A.

1974-03-01

The report covers in detail the study of the expansion of the Turkish Electric Power System for the period 1980-1987. Load forecast is done by sectors and regions and inter-regions power balances gave the basis for the high voltage network configurations. Expansion alternatives are defined giving priority to hydroelectric projects, to local resources and nuclear power plants concurrently with conventional plants (lignite and oil). Several reactor strategies are analysed with LWR, HWR, FBR and HTGR power plants. Present worth value method is used for comparison of alternatives and sensitivity analysis is done for those ranked in the first places. Load flow, transient stability and frequency deviation studies of the power system are studied carefully by means of A.C. calculator and digital computer codes in order to see the influence of the introduction of large-sized power plants (600-750MW(e)) and their location in the power system. A 600MW(e) nuclear plant in 1983 and a second one of 750MW(e) in 1987 should, it is found, be commissioned into the system. The economic optimization was done with two computer programmes developed by KFA (Juelich): IACO for fuelling nuclear plant and RESTRAPO for power system with high hydroelectric component. The report is bound in three volumes: Volume I: Summary and Conclusions; Volume II: System Planning; Volume III: Electrical Survey

Safety assurance in radioactive waste management at nuclear power plants of the Northwest region of Russia

Energy Technology Data Exchange (ETDEWEB)

Safonov, Igor

1999-07-01

This presentation describes the two large operating nuclear power plants (NPP) in Northwest Russia, the Kola NPP and the Leningrad NPP. The four units at Kola are tank-type pressurised water reactors of 440 MW (electric) while the four Leningrad reactors are 1000 MW (electric) of RBMK type. Gosatomnadzor of Russia regularly conducts so-called target inspections on safety assurance for radioactive waste management at NNP. Among the many items checked during such inspections are the existence and realisation of an action plan for waste reduction, the technical state of equipment and the compliance with previous directions. The management of liquid, solid and gaseous radioactive wastes is described in some detail, and so are the violations revealed at both sites. There is also some discussion of modernisation plans for waste management. It is stated that the ecological impact of the plants is negligible and there is no hazard to people or environment. The presentation concludes with some suggestions for improving the licensing requirements for waste management.

Safety assurance in radioactive waste management at nuclear power plants of the Northwest region of Russia

International Nuclear Information System (INIS)

Safonov, Igor

1999-01-01

This presentation describes the two large operating nuclear power plants (NPP) in Northwest Russia, the Kola NPP and the Leningrad NPP. The four units at Kola are tank-type pressurised water reactors of 440 MW (electric) while the four Leningrad reactors are 1000 MW (electric) of RBMK type. Gosatomnadzor of Russia regularly conducts so-called target inspections on safety assurance for radioactive waste management at NNP. Among the many items checked during such inspections are the existence and realisation of an action plan for waste reduction, the technical state of equipment and the compliance with previous directions. The management of liquid, solid and gaseous radioactive wastes is described in some detail, and so are the violations revealed at both sites. There is also some discussion of modernisation plans for waste management. It is stated that the ecological impact of the plants is negligible and there is no hazard to people or environment. The presentation concludes with some suggestions for improving the licensing requirements for waste management

Utilization of red mud for the purification of waste waters from nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Luka, Mikelic; Visnja, Orescanin; Stipe, Lulic [Rudjer Boskovic Institute, Lab. for radioecology, Zagreb (Croatia)

2006-07-01

Sorption of the radionuclides and heavy metals from low level liquid radioactive waste on the coagulant produced from bauxite waste (red mud and waste base) was presented. Research was conducted on composite annual samples of waste water collected in the Waste Monitor Tank (W.M.T.) from Kro Nuclear Power Plant during each month. Activities of radionuclide in W.M.T. were measured before and after purification using high purity germanium detector. Also, elemental concentrations in W.M.T. before and after purification were measured by source excited energy dispersive X-ray fluorescence (E.D.X.R.F.). It has been showed that activated red mud is excellent purification agent for the removal of radionuclides present in low level liquid radioactive waste. Removal efficiency was 100% for the radionuclides {sup 58}Co and {sup 60}Co 100%, and over 60% for {sup 134}Cs and {sup 137}Cs. (authors)

Utilization of red mud for the purification of waste waters from nuclear power plants

International Nuclear Information System (INIS)

Luka, Mikelic; Visnja, Orescanin; Stipe, Lulic

2006-01-01

Sorption of the radionuclides and heavy metals from low level liquid radioactive waste on the coagulant produced from bauxite waste (red mud and waste base) was presented. Research was conducted on composite annual samples of waste water collected in the Waste Monitor Tank (W.M.T.) from Kro Nuclear Power Plant during each month. Activities of radionuclide in W.M.T. were measured before and after purification using high purity germanium detector. Also, elemental concentrations in W.M.T. before and after purification were measured by source excited energy dispersive X-ray fluorescence (E.D.X.R.F.). It has been showed that activated red mud is excellent purification agent for the removal of radionuclides present in low level liquid radioactive waste. Removal efficiency was 100% for the radionuclides 58 Co and 60 Co 100%, and over 60% for 134 Cs and 137 Cs. (authors)

Integrated systems for power plant cooling and wastewater management

International Nuclear Information System (INIS)

Haith, D.A.

1975-01-01

The concept of integrated management of energy and water resources, demonstrated in hydropower development, may be applicable to steam-generated power, also. For steam plants water is a means of disposing of a waste product, which is unutilized energy in the form of heat. One framework for the evolution of integrated systems is the consideration of possible technical linkages between power plant cooling and municipal wastewater management. Such linkages include the use of waste heat as a mechanism for enhancing wastewater treatment, the use of treated wastewater as make-up for evaporative cooling structures, and the use of a pond or reservoir for both cooling and waste stabilization. This chapter reports the results of a systematic evaluation of possible integrated systems for power plant cooling and waste water management. Alternatives were analyzed for each of three components of the system--power plant cooling (condenser heat rejection), thermally enhanced waste water treatment, and waste water disposal. Four cooling options considered were evaporative tower, open cycle, spray pond, and cooling pond. Three treatment alternatives considered were barometric condenser-activated sludge, sectionalized condenser-activated sludge, and cooling/stabilization pond. Three disposal alternatives considered were ocean discharge, land application (spray irrigation), and make-up (for evaporative cooling). To facilitate system comparisons, an 1100-MW nuclear power plant was selected. 31 references

Pre design processing of waste of ex-resin without materials matrix from nuclear power plant type PWR 1000 MW

International Nuclear Information System (INIS)

Cerdas Tarigan

2010-01-01

Have been done pre design processing of waste ex-resin without capacities matrix materials from nuclear power plant type PWR 1000 MW During the time radioactive waste of ex-resin processed to use process of immobilization use matrix materials like mixture cement and epoxy resin and then conditioning. This process is not effective and efficient because end result volume of end product bigger than volume early operation system and maintenance of its installation more difficult. To overcome this created a design of technology processing of waste of ex- resin without matrix materials through process of strainer, drying and conditioning represent technological innovation newly processing of radioactive waste of ex-resin. Besides this process more effective and efficient, volume of end product waste much more small from volume early and operation system and maintenance of its easier installation. Pre design is expected to be used as a basis to make conceptual of pre design installation of strainer, drying and conditioning for the processing of waste of ex-resin from nuclear power plant type PWR 1000 MW. (author)

Natural radionuclides in coal and waste material originating from coal fired power plant

International Nuclear Information System (INIS)

Marovic, Gordana; Franic, Zdenko; Sencar, Jasminka; Petrinec, Branko; Bituh, Tomislav; Kovac, Jadranka

2008-01-01

This paper presents long-term investigations of natural radioactivity in coal, used for power production in the coal-fired power plant (CFPP) situated on the Adriatic coast, and resulting slag and ash. Activity concentrations of 40 K, 232 Th, 226 Ra and 238 U in used coal and resulting waste material have been measured for 25 years. As expected, it was demonstrated that the content of radionuclides in deposited bottom and filter ash material are closely related with radionuclide activity concentrations and mineral matter fraction in used coals. The external hazard index has been calculated and discussed for the slag and ash depository. During the first decade of operation of the CFPP has been used domestic coal produced in nearby area characterized by higher background radiation compared with the rest of Croatia. Therefore, the coal itself had relatively high 226 Ra and 238 U activity concentrations while potassium and thorium content was very low, 40 K activity concentrations being 2-9% and those of 232 Th 1-3% of total activity. As, in addition, the sulphur concentrations in coal were very high use of domestic coal was gradually abandoned till it was completely substituted by imported coal originated from various sources and of low natural radioactivity. Upon this, activity concentrations of uranium series radionuclides in deposited waste materials decreased significantly. Consequently, waste material i.e., slag and ash, generated in the last several years of coal fired power plant operation could be readily used in cement industry and as additive to other building materials, without any special restrictions according to the Croatian regulations dealing with building materials and European directives. (author)

Combining plasma gasification and solid oxide cell technologies in advanced power plants for waste to energy and electric energy storage applications.

Science.gov (United States)

Perna, Alessandra; Minutillo, Mariagiovanna; Lubrano Lavadera, Antonio; Jannelli, Elio

2018-03-01

The waste to energy (WtE) facilities and the renewable energy storage systems have a strategic role in the promotion of the "eco-innovation", an emerging priority in the European Union. This paper aims to propose advanced plant configurations in which waste to energy plants and electric energy storage systems from intermittent renewable sources are combined for obtaining more efficient and clean energy solutions in accordance with the "eco-innovation" approach. The advanced plant configurations consist of an electric energy storage (EES) section based on a solid oxide electrolyzer (SOEC), a waste gasification section based on the plasma technology and a power generation section based on a solid oxide fuel cell (SOFC). The plant configurations differ for the utilization of electrolytic hydrogen and oxygen in the plasma gasification section and in the power generation section. In the first plant configuration IAPGFC (Integrated Air Plasma Gasification Fuel Cell), the renewable oxygen enriches the air stream, that is used as plasma gas in the gasification section, and the renewable hydrogen is used to enrich the anodic stream of the SOFC in the power generation section. In the second plant configuration IHPGFC (Integrated Hydrogen Plasma Gasification Fuel Cell) the renewable hydrogen is used as plasma gas in the plasma gasification section, and the renewable oxygen is used to enrich the cathodic stream of the SOFC in the power generation section. The analysis has been carried out by using numerical models for predicting and comparing the systems performances in terms of electric efficiency and capability in realizing the waste to energy and the electric energy storage of renewable sources. Results have highlighted that the electric efficiency is very high for all configurations (35-45%) and, thanks to the combination with the waste to energy technology, the storage efficiencies are very attractive (in the range 72-92%). Copyright © 2017 Elsevier Ltd. All rights

Power plant wastes capitalization as geopolymeric building materials

Science.gov (United States)

Ciobanu, Gabriela; Litu, Loredana; Harja, Maria

2017-11-01

In this innovative study, we are present an investigation over the properties of geopolymeric materials prepared using ash supplied by power plant Iasi, Romania and sodium hydroxide solutions/pellets. Having as objective a minimum consumption of energy and materials was developed a class of advanced eco-materials. New synthesized materials can be used as a binder for cement replacement or for the removal/immobilization of pollutants from waste waters or soils. It offers an advanced and low cost-effective solution too many problems, where waste must be capitalized. The geopolymer formation, by hydrothermal method, is influenced by: temperature (20-600°C), alkali concentration (2M-6M), solid /liquid ratio (1-2), ash composition, time of heating (2-48 h), etc. The behaviour of the FTIR peak of 6M sample indicated upper quantity of geopolymer formation at the first stage of the reaction. XRD spectra indicated phases like sodalite, faujasite, Na-Y, which are known phases of geopolymer/zeolite. Advanced destroyed of ash particles due to geopolymerisation reaction were observed when the temperature was higher. At the constant temperature the percentage of geopolymer increases with increasing of curing time, from 4-48 h. Geopolymer materials are environmentally friendly, for its obtaining energy consumption, and CO2 emission is reduced compared to cement binder.

Decommissioning project of commercial nuclear power plant

International Nuclear Information System (INIS)

Karigome, S.

2008-01-01

Decommissioning project of commercial nuclear power plant in Japan was outlined. It is expected that the land, after the decommissioning of commercial nuclear power plants, will serve as sites for new plants. Steps will be taken to reduce the amount of wastes generated and to recycle/reuse them. Wastes with a radioactivity concentration below the 'clearance level' need not be dealt with as radioactive material, and may be handled in the same way as conventional wastes. The Tokai-1 power station, a 166 MWe carbon dioxide cooled reactor which closed down in 1998, is being decommissioned and the first ten years as 'safe storage' to allow radioactivity to decay. Non-reactor grade components such as turbines were already removed, heat exchanger dismantling started and the reactor will be dismantled, the buildings demolished and the site left ready for reuse. All radioactive wastes will be classified as low-level wastes in three categories and will be buried under the ground. The total cost will be 88.5 billion yen -34.7 billion for dismantling and 53.8 billion for waste treatment including the graphite moderator. (T. Tanaka)

The management of the radioactive waste generated by the EDF nuclear power plants in service

International Nuclear Information System (INIS)

Lantes, B.; Beguin, St.

2011-01-01

From the very beginning of France's nuclear power programme, EDF has developed industrial-scale management of the waste it produces, which has constantly progressed in line with changes in the regulations and the available technology. This management process, improved thanks to feedback and experience, ensures that any risk of exposure, at every stage, from production to final disposal, is controlled. The guidelines adopted by EDF for sustainable management of its waste are as follows: -) reduce the quantity of waste, from the production stage and then through recycling and reprocessing; -) sort waste according to its nature and activity level, so that it can be processed and packaged appropriately and the appropriate long-term management solution implemented; -) package waste as soon as it is produced to prevent any risk of dispersion; -) store waste, pending decay or the availability of an appropriate disposal solution; -) transport and place waste in repositories, keeping it away from Man and the environment by means of engineered or natural barriers for as long as required for the radioactivity to decay to an acceptable level. Regarding short-lived waste produced during operating and maintenance activities at power plants in service, EDF currently implements fully-integrated industrial management solutions which are constantly being optimised in conjunction with its industrial partners. (authors)

Thermodynamic Analysis of a Ship Power Plant Operating with Waste Heat Recovery through Combined Heat and Power Production

Directory of Open Access Journals (Sweden)

Mirko Grljušić

2014-11-01

Full Text Available The goal of this research is to study a cogeneration plant for combined heat & power (CHP production that utilises the low-temperature waste energy in the power plant of a Suezmax-size oil tanker for all heating and electricity requirements during navigation. After considering various configurations, a standard propulsion engine operating at maximum efficiency and a CHP Plant with R245fa fluid using a supercritical organic Rankine cycle (ORC is selected. All the ship heat requirements can be covered by energy of organic fluid after expansion in the turbine, except feeder-booster heating. Hence, an additional quantity of working fluid may be heated using an after Heat Recovery Steam Generator (HRSG directed to the feeder-booster module. An analysis of the obtained results shows that the steam turbine plant does not yield significant fuel savings. However, a CHP plant with R245fa fluid using supercritical ORC meets all of the demands for electrical energy and heat while burning only a small amount of additional fuel in HRSG at the main engine off-design operation.

Solid municipal waste processing plants: Cost benefit analysis

International Nuclear Information System (INIS)

Gerardi, V.

1992-01-01

This paper performs cost benefit analyses on three solid municipal waste processing alternatives with plants of diverse daily outputs. The different processing schemes include: selected wastes incineration with the production of refuse derived fuels; selected wastes incineration with the production of refuse derived fuels and compost; pyrolysis with energy recovery in the form of electric power. The plant daily outputs range from 100 to 300 tonnes for the refuse derived fuel alternatives, and from 200 to 800 tonnes for the pyrolysis/power generation scheme. The cost analyses consider investment periods of fifteen years in duration and interest rates of 5%

Management of radioactive waste from a major core damage in a BWR power plant

International Nuclear Information System (INIS)

Elkert, J.; Christensen, H.; Torstenfelt, B.

1990-01-01

Large amounts of fission products would be released in case of a major core damage in a nuclear power reactor. In this theoretical study the core damage is caused by a loss of coolant accident followed by a complete loss of all electric power for about 30 minutes resulting in the release of 10% of the core inventory of noble gases. A second case has also been briefly studied, in which the corresponding core damage is supposed to be created merely by the complete loss of electric power during a limited time period. It appears from the study that the radioactive waste generated as a consequence of an accident of the extent can be managed in the reference reactor with only minor modifications required in the waste plant. The detailed results of the study are reactor specific, but many of the findings and recommendations are generally applicable. (author) 28 refs

Proceedings of the symposium on the on-site management of power reactor wastes

International Nuclear Information System (INIS)

Anon.

1979-01-01

This symposium represents a synthesis of some current practices and research and development work in the field of radioactive waste management at nuclear power plants. It includes the following sessions: radioactive waste management practices at nuclear power plants; waste production and operating experiences; coolant and liquid waste processing; solidification methods; volume reduction methods; solid waste containment

Perspectives of new fossil-fuelled power plants with CO2 capture in the liberalised European electricity market

International Nuclear Information System (INIS)

Kober, Tom

2014-01-01

Against the background of an increasing importance of climate change mitigation and the liberalization of the European energy supply this study assesses the perspectives of power plants with Carbon dioxide Capture and Storage (CCS). CCS power plants represent one option to reduce CO 2 emissions of fossil energy based electricity production significantly. In this study the deployment of CCS power plants is investigated for the European electricity market until 2050 taking different energy and climate policy framework conditions into consideration. By applying an integrated model-based approach, structural changes of the whole energy system are incorporated, including their implications on costs and emissions. The study addresses uncertainties concerning future CCS power plant invest costs and efficiencies explicitly, and analyses the effects of changes of these parameters with respect to the perspectives of CCS power plants in Europe. Thereby, interdependencies on horizontal level related to competition of different technologies within the electricity sector are examined, but also vertical interdependencies resulting from effects between the upstream and energy demand sectors. In order to reflect the heterogeneity among the national energy systems in Europe, country specific particularities on technical aspects and energy policy are taken into account, such as potentials and costs of CO 2 storage, and national regulations on the use of nuclear power and renewable energy. The results of the analysis reveal a strong influence of the stringency of the EU greenhouse gas reduction target and the policy on the use of nuclear energy on the perspectives of CCS power plants in the European electricity market. Comparing the influence of different policy frameworks analysed in this study with the influences of the variation of the technical and economic CCS power plant parameters shows, that uncertainties concerning energy policy measures can have a stronger influence on the

Clearance of very low level radioactive waste in spanish nuclear power plants

International Nuclear Information System (INIS)

Alvarez Mir, F.

2001-01-01

According to present Spanish legislation a radioactive waste is defined as any material or waste product, without any possible planned use, that contains or is contaminated with radionuclides in concentrations or activity levels higher than those established by the Regulatory Authorities. Legally, this situation allows to develop a conventional management of very low level radioactive waste, by checking the negligibility of their radiological impact, and thus obtaining the corresponding Authorization to treat them as conventional waste. This presentation describes the clearance project of contaminated oils from spanish nuclear power plants. The on-site management includes: -) preliminary settling, centrifugation and filtration; -) oil purification; and -) radiological characterization. The off-site management includes the following operations: -) transportation to the facility where treatment is developed (dilution); -) temporary storage (decay); -) transportation to the place where final management is carried out; -) oil burning (dilution); and management of ashes and other combustion products. An annual amount of 70 m 3 /year (63 MBq) of very low contaminated oil with a specific concentration of 1 Bq/g could be disposed off. (A.C.)

Determination and use of scaling factors for waste characterization in nuclear power plants

International Nuclear Information System (INIS)

2009-01-01

of nuclear power plants, the SF technique is also applicable to other situations where it is desirable to infer the activity of DTM nuclides from easy to make measurements, such as for research reactors, nuclear fuel manufacturing plants, nuclear fuel reprocessing plants, decommissioning waste, historical waste, contaminated land, etc. In each case, the technique employed is similar, but consideration must be given to the unique aspects of the situation, such as the radionuclides of concern. Development of SFs in Member States has been based on analysis of representative waste streams and/or on theoretical calculations and modelling of radionuclide production and transport mechanisms. There is general consensus among Member States that the results derived from the application of SFs must be reasonable without being overly conservative. For example, if the estimate of a DTM nuclide is overly conservative (i.e. too high), it may prematurely result in the radionuclide capacity or authorized limit of a repository being 'expended' before the repository is physically full. The acceptable degree of conservatism will vary depending on the application. Many Member States use the same set of key nuclides and apply similar sampling and analysis strategies. There is also an indication that Member States operating similar nuclear facilities (e.g. the same design of nuclear power plant) may be able to pool their data to develop common SFs for certain radionuclides and waste streams. This is especially useful for Member States with smaller nuclear programmes that may not be able on their own to support a large sampling and analysis programme to develop their own SFs or who lack the technical infrastructure to perform the complex measurements required. The experience compiled from Member States indicates that the development and use of SFs is a widely accepted practice by waste generators, facility operators and regulators in many countries. While the details and scope of SF

Natural radionuclides in waste water discharged from coal-fired power plants in Serbia.

Science.gov (United States)

Janković, Marija M; Todorović, Dragana J; Sarap, Nataša B; Krneta Nikolić, Jelena D; Rajačić, Milica M; Pantelić, Gordana K

2016-12-01

Investigation of the natural radioactivity levels in water around power plants, as well as in plants, coal, ash, slag and soil, and to assess the associated radiation hazard is becoming an emerging and interesting topic. This paper is focused on the results of the radioactivity analysis in waste water samples from five coal-fired power plants in Serbia (Nikola Tesla A, Nikola Tesla B, Kolubara, Morava and Kostolac), which were analyzed in the period 2003-2015. River water samples taken upstream and downstream from the power plants, drain water and overflow water were analyzed. In the water samples gamma spectrometry analysis was performed as well as determination of gross alpha and beta activity. Natural radionuclide 40 K was detected by gamma spectrometry, while the concentrations of other radionuclides, 226 Ra, 235 U and 238 U, usually were below the minimum detection activity (MDA). 232 Th and artificial radionuclide 137 Cs were not detected in these samples. Gross alpha and beta activities were determined by the α/β low level proportional counter Thermo Eberline FHT 770 T. In the analyzed samples, gross alpha activity ranged from MDA to 0.47 Bq L - 1 , while the gross beta activity ranged from MDA to 1.55 Bq L - 1 .

Nuclear power and other thermal power

International Nuclear Information System (INIS)

Bakke, J.

1978-01-01

Some philosophical aspects of mortality statistics are first briefly mentioued, then the environmental problems of, first, nuclear power plants, then fossil fuelled power plants are summarised. The effects of releases of carbon dioxide, sulphur dioxide and nitrogen oxides are briefly discussed. The possible health effects of radiation from nuclear power plants and those of gaseous and particulate effluents from fossil fuel plants are also discussed. It is pointed out that in choosing between alternative evils the worst course is to make no choice at all, that is, failure to install thermal power plants will lead to isolated domestic burning of fossil fuels which is clearly the worst situation regarding pollution. (JIW)

Energy analysis of a combined solid oxide fuel cell with a steam turbine power plant for marine applications

Science.gov (United States)

Welaya, Yousri M. A.; Mosleh, M.; Ammar, Nader R.

2013-12-01

Strong restrictions on emissions from marine power plants (particularly SO x , NO x ) will probably be adopted in the near future. In this paper, a combined solid oxide fuel cell (SOFC) and steam turbine fuelled by natural gas is proposed as an attractive option to limit the environmental impact of the marine sector. The analyzed variant of the combined cycle includes a SOFC operated with natural gas fuel and a steam turbine with a single-pressure waste heat boiler. The calculations were performed for two types of tubular and planar SOFCs, each with an output power of 18 MW. This paper includes a detailed energy analysis of the combined system. Mass and energy balances are performed not only for the whole plant but also for each component in order to evaluate the thermal efficiency of the combined cycle. In addition, the effects of using natural gas as a fuel on the fuel cell voltage and performance are investigated. It has been found that a high overall efficiency approaching 60% may be achieved with an optimum configuration using the SOFC system. The hybrid system would also reduce emissions, fuel consumption, and improve the total system efficiency.

Transmutation of radioactive wastes from nuclear power plants. A contribution to the reduction of the final repository problem; Transmutation radioaktiver Reststoffe aus Kernkraftwerken. Ein Beitrag zur Verringerung der Endlagerproblematik

Energy Technology Data Exchange (ETDEWEB)

Mach, Manfred [Technische Univ. Berlin (Germany). Inst. fuer Technologie und Management

2015-07-01

The brochure on transmutation of radioactive wastes from nuclear power plants - a contribution to the reduction of the final repository problem covers the following issues: What is transmutation? Nuclear power in Germany; energy density of fuels; time span of energy resources; CO{sub 2} emissions from different energy sources; types of nuclear power plants in Germany; cost of German electricity generation plants; nuclear power plants worldwide; wastes from nuclear electricity production; radiation from fission products; radiation effects on humans, the nuclear fuel cycle, direct final disposal of radioactive wastes; risk assessment of the direct final disposal; partitioning of actinides; transmutation of actinides.

Application of fluidized bed combustor for use of low grade and waste fuels in power plants

International Nuclear Information System (INIS)

Wert, D.A.

1993-01-01

In a span of less that 15 years, CFB combustion technology has progressed from a concept to a demonstrated capability of providing clean, reliable energy from low-cost, low-grade fuels. In fact, one of the major advantages of CFB technology is its ability to burn fuels with high moisture, high ash and high sulfur levels, allowing the users the option of using inexpensive open-quotes opportunityclose quotes fuels. CFB technology has demonstrated reliable operation while burning low-grade, easily available fuels which other combustion technologies, preclude or cannot easily accommodate (such as peat, waste coals, sludges, municipal wastes and lignite). The CFB units can be designed to burn a wide range of different fuels, alone or in combination. This capability allows the user to take advantage of various fuel supplies to lower operating costs while still complying with ever increasing environmental regulations. This paper will review the evolution and experience of CFB technology and discuss the operating history of the first culm-fired (anthracite mine tailings) power plant. The development of opportunity-fueled power plants has been associated with the establishment of the Independent Power Industry in the United States. Traditional utilities have relied on premium fuels (oil, natural gas, coal and nuclear) due to availability and the ability to pass fuel costs through to consumers. With the development of privatized power plants, more emphasis has been placed on fixing fuel costs over the life of the plant to minimize investor risk. An analogy can be drawn between the growth of the Independent Power Industry in the United States over the last ten years with the need for capacity in many Developing Countries today

Recycling of concrete waste generated from nuclear power plant dismantling

International Nuclear Information System (INIS)

Ogawa, Hideo; Nagase, Takahiro; Tanaka, Hiroaki; Nawa, Toyoharu

2012-01-01

Non-radioactive concrete waste generated from dismantling of a standard large nuclear power plant is estimated to be about 500,000 tons in weight. Using such waste as recycled aggregate within the enclosure of the plant requires a new manufacturing technology that generates a minimal amount of by-product powder. Recycled aggregate has brittle parts with defects such as cracks, pores, and voids in residual paste from original concrete. This study presents a method of selectively removing the defective parts during manufacture to improve the quality of the recycled fine aggregate. With this selective removal method used, the amount of by-product powder can be reduced by half as compared to that by a conventional method. The influences of the characteristics of the recycled fine aggregate on the flowability and strength of the mortar using recycled fine aggregate were evaluated by multiple linear regression analysis. The results clearly showed that the flowability was primarily affected by the filling fraction of recycled fine aggregate, while the compressive strength of mortar was primarily affected by the fraction of defects in the aggregate. It was also found that grains produced by a granulator have more irregularities in the surfaces than those produced by a ball mill, providing an increased mortar strength. Using these findings from this study, efforts are also being made to develop a mechanical technology that enables simultaneous processing of decontamination and recycling. The granulator under consideration is capable of grinding the surfaces of irregularly shaped particles and may be used successfully, under optimal conditions, for the surface decontamination of concrete waste contaminated with radioactive materials. (author)

Power and Torque Characteristics of Diesel Engine Fuelled by Palm-Kernel Oil Biodiesel

Directory of Open Access Journals (Sweden)

Oguntola J. ALAMU

2009-07-01

Full Text Available Short-term engine performance tests were carried out on test diesel engine fuelled with Palm kernel oil (PKO biodiesel. The biodiesel fuel was produced through transesterification process using 100g PKO, 20.0% ethanol (wt%, 1.0% potassium hydroxide catalyst at 60°C reaction temperature and 90min. reaction time. The diesel engine was attached to a general electric dynamometer. Torque and power delivered by the engine were monitored throughout the 24-hour test duration at 1300, 1500, 1700, 2000, 2250 and 2500rpm. At all engine speeds tested, results showed that torque and power outputs for PKO biodiesel were generally lower than those for petroleum diesel. Also, Peak torque for PKO biodiesel occurred at a lower engine speed compared to diesel.

Fuel switching in power-plants: Modelling and impact on the analysis of energy projects

International Nuclear Information System (INIS)

Varympopiotis, G.; Tolis, A.; Rentizelas, A.

2014-01-01

Highlights: • The impact of fuel-switching in electricity generation is researched. • 15 Scenarios of fuel-technology combinations are compared using a computational model. • Fuel-switching results to higher yields compared to single-fuelled plants. • Plants with natural gas combined cycle and solid fuel supercritical boilers are optimal. • Fuel-switching, offers higher flexibility and security of fuel supply. - Abstract: In electricity markets, where conditions are uncertain, the choice of the best technology and the optimisation of production processes may not anymore be enough to ensure optimal investment yield of energy business plans. Providing some aspects of flexibility might enhance their financial performance; fuel switching may prove to be an alternative option, offering operational flexibility over time, as well as significant financial benefits. Traditional investment analysis methods are considered marginally useful to analyse this case. Instead, the recent tools of time-dependent investment analysis are more appropriate, since they are not inherently restricted to immediate, irreversible decisions. In the present work, a time-dependent computational model is presented and applied in the case study of the Greek Power Sector, in order to estimate the potential advantages of the fuel switching concept. Moreover, the optimal timing of switching is derived, to ensure increasing yields of an average-capacity power-plant. The results of the research indicate significant financial benefits anticipated in most scenarios from applying fuel switching, compared to single-fuelled electricity generation units. Security of fuel supply and enhanced flexibility may also be offered to the power plant since more than one technology and fuels may be engaged

Radioactive emission from thermal power plants

Energy Technology Data Exchange (ETDEWEB)

Okamoto, K [New South Wales Univ., Kensington (Australia). Dept. of Applied Mathematics

1981-07-01

Radioactive hazards of the emissions and wastes of thermal power plants arising from fuel impurities of uranium and thorium are discussed. The hazard due to radioactive emission is calculated for an average Australian bituminous coal which contains 2 ppm of U and 2.7 ppm of Th. When the dust removal efficiency of a coal-fired power plant is 99%, the radioactive hazard is greater than that of a nuclear reactor of the same electrical output. After 500 years the radioactive toxicity of the coal waste will be higher than that of fission products of a nuclear reactor and after 2,000 years it will exceed the toxicity of all the nuclear wastes including actinides. The results of a recent calculation are shown, according to which the radioactive hazard of a coal-fired power plant to the public is from several hundred to several tens of thousands of times higher than that of a total fuel cycle of plutonium. It is found that in some regions, such as Japan, the hazard due to /sup 210/Po through seafood could be considerable.

Managing radioactive wastes of nuclear power plants in operation and site decommissioning phases

International Nuclear Information System (INIS)

Ardalani, E.; Khadivi, S.

2008-01-01

A large nuclear reactor annually produces about 25-50 tons consumed Uranium. These consumed materials consist of Uranium and also Plutonium and Curium. In total, about three percent of these materials are remained from fission. Existing actinides (Uranium, Plutonium, and Curium) cause long-term and short-term radiation that could have harmful effects on the environment. In order to reduce the diverse effects of radioactive wastes in Nuclear Power Plants, different procedures are employed such as compaction, chemical treatment, vitrification, canning and sealing with concrete and safe storage. In this paper, the harmful effects of nuclear wastes on the environment are introduced and a management procedure is presented to minimize its diverse effects

Fiscal 1997 report of the development of high efficiency waste power generation technology. No.2 volume. Pilot plant verification test; Kokoritsu haikibutsu hatsuden gijutsu kaihatsu (pilot plant jissho shiken). 1997 nendo hokokusho (daini bunsatsu)

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

As to a high efficiency waste power generation system using general waste as fuel, the details of the following were described: design/construction management and operational study of pilot plant, design/manufacture/construction of pilot plant, and study of an optimal total system. Concerning the construction management and operational study, the paper described the application for governmental/official inspection procedures and taking inspection, process management of pilot plant, site patrol, safety management, management of trial run of pilot plant, drawing-up of a verification test plan and test run, etc. Relating to the design/manufacture/construction of pilot plant, an outline of the pilot plant was described. The paper also stated points to be considered in design of furnace structure and boiler structure, points to be considered of the verification test, etc. As to the study of an optimal total system, the following were described: survey of waste gasification/slagging power generation technology, basic study on RDF production process, survey of trends of waste power generation technology in the U.S., etc. 52 refs., 149 figs., 121 tabs.

Strategic analysis of biomass and waste fuels for electric power generation

International Nuclear Information System (INIS)

Wiltsee, G.A. Jr.; Easterly, J.; Vence, T.

1993-12-01

In this report, the Electric Power Research Institute (EPRI) intends to help utility companies evaluate biomass and wastes for power generation. These fuels may be alternatives or supplements to fossil fuels in three applications: (1) utility boiler coining; (2) dedicated combustion/energy recovery plants; and 3) dedicated gasification/combined cycle plants. The report summarizes data on biomass and waste properties, and evaluates the cost and performance of fuel preparation and power generation technologies. The primary biomass and waste resources evaluated are: (1) wood wastes (from forests, mills, construction/demolition, and orchards) and short rotation woody crops; (2) agricultural wastes (from fields, animals, and processing) and herbaceous energy crops; and (3) consumer or industrial wastes (e.g., municipal solid waste, scrap tires, sewage sludge, auto shredder waste). The major fuel types studied in detail are wood, municipal solid waste, and scrap tires. The key products of the project include the BIOPOWER model of biomass/waste-fired power plant performance and cost. Key conclusions of the evaluation are: (1) significant biomass and waste fuel resources are available; (2) biomass power technology cannot currently compete with natural gas-fired combined cycle technology; (3) coining biomass and waste fuels with coal in utility and industrial boilers is the most efficient, lowest cost, and lowest risk method of energy recovery from residual materials; (4) better biomass and waste fuel production and conversion technology must be developed, with the help of coordinated government energy and environmental policies and incentives; and (5) community partnerships can enhance the chances for success of a project

Radioactive commitment due to use of coal in power plants

International Nuclear Information System (INIS)

Fenger, J. and H. Flyger.

1980-11-01

A short review of the literature on release of radioactivity due to use of coal in power plants with the emphasis on the stack effluent and waste products. It is concluded that during normal operation coal fired power plants give a larger dose commitment than nuclear power plants, but both types have insignificant effects. The problem of waste management has never been studied in detail; ash deposit should probably be monitored. (Auth)

A thermodynamic analysis of waste heat recovery from reciprocating engine power plants by means of Organic Rankine Cycles

International Nuclear Information System (INIS)

Uusitalo, Antti; Honkatukia, Juha; Turunen-Saaresti, Teemu; Larjola, Jaakko

2014-01-01

Organic Rankine Cycle (ORC) is a Rankine cycle using organic fluid as the working fluid instead of water and steam. The ORC process is a feasible choice in waste heat recovery applications producing electricity from relatively low-temperature waste heat sources or in applications having a rather low power output. Utilizing waste heat from a large high-efficiency reciprocating engine power plant with ORC processes is studied by means of computations. In addition to exhaust gas heat recovery, this study represents and discusses an idea of directly replacing the charge air cooler (CAC) of a large turbocharged engine with an ORC evaporator to utilize the charge air heat in additional power production. A thermodynamic analysis for ORCs was carried out with working fluids toluene, n-pentane, R245fa and cyclohexane. The effect of different ORC process parameters on the process performance are presented and analyzed in order to investigate the heat recovery potential from the exhaust gas and charge air. A simplified feasibility consideration is included by comparing the ratio of the theoretical heat transfer areas needed and the obtained power output from ORC processes. The greatest potential is related to the exhaust gas heat recovery, but in addition also the lower temperature waste heat streams could be utilized to boost the electrical power of the engine power plant. A case study for a large-scale gas-fired engine was carried out showing that the maximum power increase of 11.4% was obtained from the exhaust gas and 2.4% from the charge air heat. - Highlights: • Waste heat recovery potential of reciprocating engines was studied. • Thermodynamic optimization for ORCs was carried out with different fluids. • The utilization of exhaust gas and charge air heat is presented and discussed. • Simplified economic feasibility study was included in the analysis. • Power increase of 11.4% was obtained from exhaust gas and 2.4% from charge air

Radioactive Waste Management In The Chernobyl Exclusion Zone - 25 Years Since The Chernobyl Nuclear Power Plant Accident

International Nuclear Information System (INIS)

Farfan, E.; Jannik, T.

2011-01-01

Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities of the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste related problems in Ukraine and the Chernobyl Exclusion Zone, and in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program. The brief overview of the radioactive waste issues in the ChEZ presented in this article demonstrates that management of radioactive waste resulting from a beyond-designbasis accident at a nuclear power plant becomes the most challenging and the costliest effort during the mitigation and remediation activities. The costs of these activities are so high that the provision of radioactive waste final disposal facilities compliant with existing radiation safety requirements becomes an intolerable burden for the current generation of a single country, Ukraine. The nuclear accident at the Fukushima-1 NPP strongly indicates that accidents at nuclear sites may occur in any, even in a most technologically advanced country, and the Chernobyl experience shows that the scope of the radioactive waste management activities associated with the mitigation of such accidents may exceed the capabilities of a single country. Development of a special international program for broad international cooperation in accident related radioactive waste management activities is required to handle these issues. It would also be reasonable to consider establishment of a dedicated international fund for mitigation of accidents at nuclear sites, specifically, for handling radioactive waste problems in the ChEZ. The experience of handling Chernobyl radioactive waste management issues, including large volumes of radioactive soils and complex structures

Nuclear power plant decommissioning and radioactive waste management in the U.K.. A regulatory perspective

International Nuclear Information System (INIS)

Ross, W.M.

1993-01-01

Effective control of the decommissioning and radioactive waste management of nuclear power plant in United Kingdom are introduced. The Government established the legislative framework and national strategy, operators provided the necessary skills and equipment for implementation, and the regulators used the legislative controls to ensure a safe system of work is achieved and maintained

Development of database for spent fuel and special waste from the Spanish nuclear power plants

International Nuclear Information System (INIS)

Gonzalez Gandal, R.; Rodriguez Gomez, M. A.; Serrano, G.; Lopez Alvarez, G.

2013-01-01

GNF Engineering is developing together with ENRESA and with the UNESA participation, the spent fuel and high activity radioactive waste data base of Spanish nuclear power plants. In the article is detailed how this strategic project essential to carry out the CTS (centralized temporary storage) future management and other project which could be emerged is being dealing with, This data base will serve as mechanics of relationship between ENRESA and Spanish NPPS, covering the expected necessary information to deal with mentioned future management of spent fuel and high activity radioactive waste. (Author)

GreenVMAS: Virtual Organization Based Platform for Heating Greenhouses Using Waste Energy from Power Plants.

Science.gov (United States)

González-Briones, Alfonso; Chamoso, Pablo; Yoe, Hyun; Corchado, Juan M

2018-03-14

The gradual depletion of energy resources makes it necessary to optimize their use and to reuse them. Although great advances have already been made in optimizing energy generation processes, many of these processes generate energy that inevitably gets wasted. A clear example of this are nuclear, thermal and carbon power plants, which lose a large amount of energy that could otherwise be used for different purposes, such as heating greenhouses. The role of GreenVMAS is to maintain the required temperature level in greenhouses by using the waste energy generated by power plants. It incorporates a case-based reasoning system, virtual organizations and algorithms for data analysis and for efficient interaction with sensors and actuators. The system is context aware and scalable as it incorporates an artificial neural network, this means that it can operate correctly even if the number and characteristics of the greenhouses participating in the case study change. The architecture was evaluated empirically and the results show that the user's energy bill is greatly reduced with the implemented system.

GreenVMAS: Virtual Organization Based Platform for Heating Greenhouses Using Waste Energy from Power Plants

Directory of Open Access Journals (Sweden)

Alfonso González-Briones

2018-03-01

Full Text Available The gradual depletion of energy resources makes it necessary to optimize their use and to reuse them. Although great advances have already been made in optimizing energy generation processes, many of these processes generate energy that inevitably gets wasted. A clear example of this are nuclear, thermal and carbon power plants, which lose a large amount of energy that could otherwise be used for different purposes, such as heating greenhouses. The role of GreenVMAS is to maintain the required temperature level in greenhouses by using the waste energy generated by power plants. It incorporates a case-based reasoning system, virtual organizations and algorithms for data analysis and for efficient interaction with sensors and actuators. The system is context aware and scalable as it incorporates an artificial neural network, this means that it can operate correctly even if the number and characteristics of the greenhouses participating in the case study change. The architecture was evaluated empirically and the results show that the user’s energy bill is greatly reduced with the implemented system.

Study of waste-heat recovery and utilization at the Farmington Municipal Power Plant. Final report, December 1, 1980-June 30, 1981

Energy Technology Data Exchange (ETDEWEB)

Leigh, G.G.; Edgel, W.R.; Feldman, K.T. Jr.; Moss, E.J.

1982-03-01

An examination was made of the technical and economc feasibility of utilizing waste heat from the Farmington Municipal Power Plant. First, the production cycles of the natural-gas-fired plant were assessed to determine the quantity and quality of recoverable waste heat created by the plant during its operation. Possibilities for utilizing waste heat from the exhaust gases and the cooling water were then reviewed. Hot water systems that can be used to retrieve heat from hot flue gases were investigated; the heated water can then be used for space heating of nearby buildings. The potential use of waste heat to operate a refrigeration plant was also analyzed. The use of discharged cooling water for hydroelectric generation was studied, as well as its application for commercial agricultural and aquaculture enterprises.

Power generation by nuclear power plants

International Nuclear Information System (INIS)

Bacher, P.

2004-01-01

Nuclear power plays an important role in the world, European (33%) and French (75%) power generation. This article aims at presenting in a synthetic way the main reactor types with their respective advantages with respect to the objectives foreseen (power generation, resources valorization, waste management). It makes a fast review of 50 years of nuclear development, thanks to which the nuclear industry has become one of the safest and less environmentally harmful industry which allows to produce low cost electricity: 1 - simplified description of a nuclear power generation plant: nuclear reactor, heat transfer system, power generation system, interface with the power distribution grid; 2 - first historical developments of nuclear power; 3 - industrial development and experience feedback (1965-1995): water reactors (PWR, BWR, Candu), RBMK, fast neutron reactors, high temperature demonstration reactors, costs of industrial reactors; 4 - service life of nuclear power plants and replacement: technical, regulatory and economical lifetime, problems linked with the replacement; 5 - conclusion. (J.S.)

Input of biomass in power plants or the power generation. Calculation of the financial gap

International Nuclear Information System (INIS)

De Vries, H.J.; Van Tilburg, X.; Pfeiffer, A.E.; Cleijne, H.

2005-09-01

The project on the title subject concerns two questions: (1) Are projects in which wood-pellets are co-fired in a coalfired power plant representative for bio-oil fueled co-firing projects in a gas-fired plant?; and (2) are new projects representative for existing projects? To answer those questions the financial gaps have been calculated for five different situations: Co-firing bio-oil in a gas-fired power plant; Co-firing bio-oil in a coal-fired power plant; Co-firing wood pellets in a coal-fired power plant; Co-firing agro-residues in a coal-fired power plant; and Co-firing waste-wood (A- and B-grade) in a coal-fired power plant. The ranges and reference cases in this report show that co-firing bio-oil on average has a smaller financial gap than the solid biomass reference case. On average it can also be concluded that by using waste wood or agro-residues, the financial gaps can decrease [nl

Experience gained in the management of radioactive waste from maintenance, decontamination and partial decommissioning of a reprocessing plant and conclusions resulting for the management of radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

Hild, W.

1983-01-01

After a short description of the historical background of Eurochemic, its main tasks and the various operational phases, a detailed description of the waste management principles applied is presented. The practical experience in the waste treatment is reported for both the operational phase of the reprocessing plant and its decontamination and partial decommissioning after shutdown. Based on this experience and the presented data, an assessment of the practical operations is made and conclusions are drawn. Finally, recommendations are formulated both for the general waste management policy and the practical waste treatment processes in nuclear power reactors. (author)

Models for the dilution of thermal wastes from power plants on the Channel French shore

International Nuclear Information System (INIS)

Boulot, F.

1980-11-01

This report presents the mathematical models developed and employed at EDF estimating the dilution of waste from the power plants along the Channel. The following points are discussed: the model building hypotheses, the difficulties of a numerical kind encountered and the manner in which they were solved, the results obtained and the comparison with the experimental results [fr

Safety in nuclear power plants

International Nuclear Information System (INIS)

Koeberlein, K.

1987-01-01

In nuclear power plants large amounts of radioactive fission products ensue from the fission of uranium. In order to protect the environment, the radioactive material is confined in multiple 'activity barriers' (crystal matrix of the fuel, fuel cladding, coolant boundary, safety containment, reactor building). These barriers are protected by applying a defense-in-depth concept (high quality requirements, protection systems which recognize and terminate operational incidents, safety systems to cope with accidents). In spite of a favorable safety record of German nuclear power plants it is obvious - and became most evident by the Chernobyl accident - that absolute safety is not achievable. At Chernobyl, however, design disadvantages of that reactor type (like positive reactivity feedback of coolant voiding, missing safety containment) played an important role in accident initiation and progression. Such features of the Russian 'graphite-moderated pressure tube boiling water reactor' are different from those of light water reactors operating in western countries. The essential steps of the waste management of the nuclear fuel cycle ('Entsorgung') are the interim storage, the shipment, and the reprocessing of the spent fuel and the final repository of radioactive waste. Reprocessing means the separation of fossil material (uranium, plutonium) from radioactive waste. Legal requirements for radiological protection of the environment, which are identical for nuclear power plants and reprocessing plant, are complied with by means of comprehensive filter systems. Safety problems of a reprocessing plant are eased considerably by the fact that system pressures, process temperatures and energy densities are low. In order to confine the radioactive waste from the biosphere for a very long period of time, it is to be discarded after appropriate treatment into the deep geological underground of salt domes. (orig./HP) [de

Low activation material design methodology for reduction of radio-active wastes of nuclear power plant

International Nuclear Information System (INIS)

Hasegawa, A.; Satou, M.; Nogami, S.; Kakinuma, N.; Kinno, M.; Hayashi, K.

2007-01-01

Most of the concrete shielding walls and pipes around a reactor pressure vessel of a light water reactor become low level radioactive waste at decommission phase because they contain radioactive nuclides by thermal-neutron irradiation during its operation. The radioactivity of some low level radioactive wastes is close to the clearance level. It is very desirable in terms of life cycle cost reduction that the radioactivity of those low level radioactive wastes is decreased below clearance level. In case of light water reactors, however, methodology of low activation design of a nuclear plant has not been established yet because the reactor is a large-scale facility and has various structural materials. The Objectives of this work are to develop low activation material design methodology and material fabrication for reduction of radio-active wastes of nuclear power plant such as reinforced concrete. To realize fabrication of reduced radioactive concrete, it is necessary to develop (1) the database of the chemical composition of raw materials to select low activation materials, (2) the tool for calculation of the neutron flux and the spectrum distribution of nuclear plants to evaluate radioactivity of reactor components, (3) optimization of material process conditions to produce the low activation cement and the low activation steels. Results of the data base development, calculation tools and trial production of low activation cements will be presented. (authors)

Technical Feasibility Study of Thermal Energy Storage Integration into the Conventional Power Plant Cycle

Directory of Open Access Journals (Sweden)

Jacek D. Wojcik

2017-02-01

Full Text Available The current load balance in the grid is managed mainly through peaking fossil-fuelled power plants that respond passively to the load changes. Intermittency, which comes from renewable energy sources, imposes additional requirements for even more flexible and faster responses from conventional power plants. A major challenge is to keep conventional generation running closest to the design condition with higher load factors and to avoid switching off periods if possible. Thermal energy storage (TES integration into the power plant process cycle is considered as a possible solution for this issue. In this article, a technical feasibility study of TES integration into a 375-MW subcritical oil-fired conventional power plant is presented. Retrofitting is considered in order to avoid major changes in the power plant process cycle. The concept is tested based on the complete power plant model implemented in the ProTRAX software environment. Steam and water parameters are assessed for different TES integration scenarios as a function of the plant load level. The best candidate points for heat extraction in the TES charging and discharging processes are evaluated. The results demonstrate that the integration of TES with power plant cycle is feasible and provide a provisional guidance for the design of the TES system that will result in the minimal influence on the power plant cycle.

Environmental assessment of the atlas bio-energy waste wood fluidized bed gasification power plant. Final report

Energy Technology Data Exchange (ETDEWEB)

Holzman, M.I.

1995-08-01

The Atlas Bio-Energy Corporation is proposing to develop and operate a 3 MW power plant in Brooklyn, New York that will produce electricity by gasification of waste wood and combustion of the produced low-Btu gas in a conventional package steam boiler coupled to a steam-electric generator. The objectives of this project were to assist Atlas in addressing the environmental permit requirements for the proposed power plant and to evaluate the environmental and economic impacts of the project compared to more conventional small power plants. The project`s goal was to help promote the commercialization of biomass gasification as an environmentally acceptable and economically attractive alternative to conventional wood combustion. The specific components of this research included: (1) Development of a permitting strategy plan; (2) Characterization of New York City waste wood; (3) Characterization of fluidized bed gasifier/boiler emissions; (4) Performance of an environmental impact analysis; (5) Preparation of an economic evaluation; and (6) Discussion of operational and maintenance concerns. The project is being performed in two phases. Phase I, which is the subject of this report, involves the environmental permitting and environmental/economic assessment of the project. Pending NYSERDA participation, Phase II will include development and implementation of a demonstration program to evaluate the environmental and economic impacts of the full-scale gasification project.

Nuclear power for energy production and hazardous waste regulations in India

International Nuclear Information System (INIS)

Sharma, Prabhakar; Goel, Gaurav

2010-01-01

Before installing any nuclear power- generation plants in India, it is important to implement stringent regulations for the health and safety of the people and for protection of the environment, soil and water from the nuclear and hazardous waste produced in the power plants. Although some initiatives have been taken for radioactive waste disposal in India, the current hazardous and nuclear waste storage/disposal regulations are still too soft and are not being implemented properly in the country

The role of wastes from nuclear power plants in the overall management of radioactive wastes

International Nuclear Information System (INIS)

Krause, H.

1983-01-01

The wastes arising from nuclear power plants (NPP) are rather low in activity and the radionuclides contained therein have a low radiotoxicity and short half-life as a rule. However, NPPs are the largest in number among all nuclear facilities and produce the greatest amount of radioactive wastes. All NPPs have been able to keep the radiation doses in the environment below the permissible values, in most cases at 1 mrem/a or even lower. The methods applied for the treatment of liquid radioactive effluents have reached a high degree of effectivity and reliability. For the solidification of the residues several appropriate methods are available. However, some improvements are still desirable. Although methods exist for incineration, cutting and baling of solid wastes, only the last method is employed at NPPs as a rule. Central treatment facilities could improve this situation. The exhaust air treatment has reached a state that satisfies high standards during normal operation and in design base accidents. Improvements seem indicated regarding the in situ-inspection of HEPA-filters and the protection of filters against excess humidity and droplets. The partial and total decommissioning of NPPs has already been demonstrated. The problems caused by the wastes arising from such actions are in the same range as those from routine operation and maintenance of NPPs. Large amounts of radioactive wastes have already been disposed of by shallow land burial, disposal into deep geological formations or dumping into the deep sea. Specific standards could probably facilitate the disposal of wastes from NPPs. The present management of radioactive wastes from NPPs satisfies all actual needs. Therefore, spectacular new developments are neither required nor to be expected. However, by the continuous improvement of details and by optimization of the whole system progress can still be achieved and useful contributions to the further development of nuclear energy be made. (author)

Low-level radioactive waste associated with plant life extension

International Nuclear Information System (INIS)

Sciacca, F.; Zigler, G.; Walsh, R.

1992-01-01

Many utilities operating nuclear power plants are expected to seek to extend the useful life of their plants through license renewal. These US Nuclear Regulatory Commission (NRC) licensees are expected to implement enhanced inspection, surveillance, testing, and monitoring (ISTM) as needed to detect and mitigate age-related degradation of important structures, systems, and components (SSCs). In addition, utilities may undertake various refurbishment and upgrade activities at these plants to better assure economic and reliable power generation. These activities performed for safety and/or economic reasons can result in radioactive waste generation, which is incremental to that generated in the original licensing term. Work was performed for the NRC to help define and characterize potential environmental impacts associated with nuclear plant license renewal and plant life extension. As part of this work, projections were made of the types and quantities of low-level radioactive waste (LLRW) likely to be generated by licensee programs. These projections were needed to estimate environmental impacts related to the disposal of such wastes

Environmental codes of practice for steam electric power generation

International Nuclear Information System (INIS)

1985-03-01

The Design Phase Code is one of a series of documents being developed for the steam electric power generation industry. This industry includes fossil-fuelled stations (gas, oil and coal-fired boilers), and nuclear-powered stations (CANDU heavy water reactors). In this document, environmental concerns associated with water-related and solid waste activities of steam electric plants are discussed. Design recommendations are presented that will minimize the detrimental environmental effects of once-through cooling water systems, of wastewaters discharged to surface waters and groundwaters, and of solid waste disposal sites. Recommendations are also presented for the design of water-related monitoring systems and programs. Cost estimates associated with the implementation of these recommendations are included. These technical guides for new or modified steam electric stations are the result to consultation with a federal-provincial-industry task force

Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

International Nuclear Information System (INIS)

Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B.

2017-01-01

The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, 3 H, 14 C, 55 Fe, 59 Ni, 63 Ni, 90 Sr, 93 Zr, 94 Nb, 99 Tc, 129 I, 235 U, 238 U, 238 Pu, 239 + 240 Pu, 241 Pu, 242 Pu, 241 Am, 242 Cm e 243 + 244 Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

Managing radioactive waste issues and misunderstandings (radiation realities, energy comparison, waste strategies)

International Nuclear Information System (INIS)

Rosen, M.

2001-01-01

The technical specialist is confident that radioactive waste can be safely managed, but many in the public remain totally unconvinced. There are issues and deep-seated misunderstandings that drive public doubts. Currently, a growing concern with pollution from other industrial waste is enabling radioactive waste issues to be debated in a wider context that allows comparisons with other potentially hazardous waste, particularly from energy generation sources. Health effects and time period issues are not unique to radioactive waste. This paper concentrates on 3 topics. The first concerns radiation health effects where the real realities of radiation are covered. The large misunderstandings that exist about radiation and its health effects have led to an almost zero health impact regulatory policy. A policy which must be more fully understood and dealt with. The second topic deals with a few revealing comparisons about the various energy generation systems. Nuclear power's 10 thousand fold lower fuel requirements, compared with a comparable fossil fuelled plant, is a dominating factor decisively minimising environmental impacts. The third topic examines waste disposal strategies. Extraordinarily small radioactive waste quantities permit a confinement strategy for disposal as opposed to the more common dispersion strategy for most toxic waste. The small quantities coupled with radioactive decay, contrary to the public perception, make any potential hazard from both low and high level radioactive waste exceedingly small. (author)

Feasibility Assessment of Using Power Plant Waste Heat in Large Scale Horticulture Facility Energy Supply Systems

Directory of Open Access Journals (Sweden)

Min Gyung Yu

2016-02-01

Full Text Available Recently, the Korean government has been carrying out projects to construct several large scale horticulture facilities. However, it is difficult for an energy supply to operate stably and economically with only a conventional fossil fuel boiler system. For this reason, several unused energy sources have become attractive and it was found that power plant waste heat has the greatest potential for application in this scenario. In this study, we performed a feasibility assessment of power plant waste heat as an energy source for horticulture facilities. As a result, it was confirmed that there was a sufficient amount of energy potential for the use of waste heat to supply energy to the assumed area. In Dangjin, an horticultural area of 500 ha could be constructed by utilizing 20% of the energy reserves. In Hadong, a horticulture facility can be set up to be 260 ha with 7.4% of the energy reserves. In Youngdong, an assumed area of 65 ha could be built utilizing about 19% of the energy reserves. Furthermore, the payback period was calculated in order to evaluate the economic feasibility compared with a conventional system. The initial investment costs can be recovered by the approximately 83% reduction in the annual operating costs.

Water management of the Dukovany nuclear power plant

International Nuclear Information System (INIS)

Rabusic, P.

1990-01-01

Industrial water for the Dukovany nuclear power plant is taken from a reservoir built on the Jihlava river. The volume of the reservoir is 17.1 million m 3 . The water taken serves mainly as the make-up water for the cooling circuit and is treated by clearing; it is also used for the preparation of demineralized water for making up the condensate circuit and for the preparation of soft water for making up the heat piping. The consumption of industrial water is 1 to 2 m 3 /s. Waste waters are released into rainwater drainage, sewage drainage and industrial water drainage. Waste waters are segregated according to the place of their origin and are purified, mainly on ion exchangers and on an evaporator. In normal conditions, they are returned to the operation. Concentrated liquid residues and solid wastes will be stored by using the multiple containment system. The most important radioisotopes that may be present in nuclear power plant waste waters, the water and radionuclide balance of the Dukovany nuclear power plant, and chemical and radiological data on the Dukovany waste waters (1989) are tabulated. (P.A.). 6 refs

Assessment of Environmental External Effects in Power Generation

DEFF Research Database (Denmark)

Meyer, Henrik Jacob; Morthorst, Poul Erik; Ibsen, Liselotte Schleisner

1996-01-01

to the production of electricity based on a coal fired conventional plant. In the second case heat/power generation by means of a combined heat and power plant based on biomass-generated gas is compared to that of a combined heat and power plant fuelled by natural gas.In the report the individual externalities from...

The main methods of solving the problem of radioactive waste management from nuclear power stations and spent fuel reprocessing plants in the USSR

International Nuclear Information System (INIS)

1978-09-01

The main directions of solving the problem of radioactive waste management from nuclear power stations and radiochemical plants, the aspects of gaseous waste management, liquid HLW storage in vessels and the problems of heat removal during storage of vitrified HLW in surface storages are considered. The main problems arising during fine decontamination of gaseous discharges from nuclear power stations and reprocessing plants are discussed. The migration of fission products in the environment and technical aspects of their capture from gaseous discharges are also considered

An radiotoxicity evaluation of high level wastes for a scenery of Brazilian Nuclear Power Plants in accordance with the Energy Expansion Brazilian Plan 2030

International Nuclear Information System (INIS)

Guilhem, Andres C.; Maiorino, Jose R.

2011-01-01

This paper is a part of the author scientific initiation, and makes an evaluation of the radiotoxicity which would be produced by the Brazilian nuclear power plants in a scenery of 7 power plants operating in 2030, in according to the official expansion plans which point out the additional introduction of 4000 MW(e), or 4 ne power plant additionally to the Angra I, II and III. Considering that all reactors would be a PWR reactors. The calculated parameter was the relative toxicity of the low and intermediate level nuclear wastes (LLPP - long lived fission products and HLW - high level waste related to the radiotoxicity of natural uranium versus time. All the calculation used the ORIGEN-S code. (author)

Management of radioactive wastes at nuclear power plants

International Nuclear Information System (INIS)

1968-01-01

Design data and operating experience with waste management systems at nuclear power stations in Canada, France, the United Kingdom and the United States of America are described. Although the specific designs and operating practices vary between nations, the underlying philosophies are essentially identical, being based on the protection principles of ICRP. The operating experience with different waste management systems has been excellent in maintaining the radiation exposures in the environment well below the accepted dose standards.

Nuclear power plant decommissioning. The nature of problems

Energy Technology Data Exchange (ETDEWEB)

Yunus, Yaziz

1986-04-01

A number of issues have to be taken into account before the introduction of any nuclear power plant in any country. These issues include reactor safety (site and operational), waste disposal and, lastly, the decommissioning of the reactor inself. Because of the radioactive nature of the components, nuclear power plants require a different approach to decommission compared to other plants. Until recently, issues on reactor safety and waste disposal were the main topics discussed. As for reactor decommissioning, the debates have been academic until now. Although reactors have operated for 25 years, decommissioning of retired reactors has simply not been fully planned. But the Shippingport Atomic Power Plant in Pennysylvania, the first large-scale power reactor to be retired, is now being decommissioned. The work has rekindled the debate in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane.

Current fusion power plant design concepts

International Nuclear Information System (INIS)

Gore, B.F.; Murphy, E.S.

1976-09-01

Nine current U.S. designs for fusion power plants are described in this document. Summary tabulations include a tenth concept, for which the design document was unavailable during preparation of the descriptions. The information contained in the descriptions was used to define an envelope of fusion power plant characteristics which formed the basis for definition of reference first commercial fusion power plant design. A brief prose summary of primary plant features introduces each of the descriptions contained in the body of this document. In addition, summary tables are presented. These tables summarize in side-by-side fashion, plant parameters, processes, combinations of materials used, requirements for construction materials, requirements for replacement materials during operation, and production of wastes

Determination of 93Zr in medium and low level radioactive wastes from Brazilian nuclear power plants

International Nuclear Information System (INIS)

Oliveira, Thiago C.; Oliveira, Arno H.

2015-01-01

The majority of long-lived radionuclides produced in the nuclear power plants can be regarded as difficult-to-measure radionuclides (RDM), hence chemical separation is necessary before the nuclear measurement of them. The zirconium isotope 93 Zr is a long-lived pure β-particle-emitting radionuclide produced from 235 U fission and from neutron activation of the stable isotope 92 Zr and thus occurring as one of the radionuclides found in nuclear reactors. Due to its long half-life, 93 Zr is one of the radionuclides of interest for the performance of assessment studies of waste storage or disposal. Two different methodologies based on extractive resins and LSC and ICP-MS techniques that enables the 93 Zr determination in medium (ILW) and low level (LLW) radioactive wastes samples from Brazilian nuclear power plants has been developed in our laboratory. Analyzing real samples 65% and 75% chemical yields for 93 Zr recovery were achieved for ICP-MS and LSC techniques, respectively. The detection limits were 0.045 μg.L -1 for ICP-MS and 0.05 Bq.L -1 for LSC techniques. (author)

Nuclear and thermal power plants and the environment

International Nuclear Information System (INIS)

Mejstrik, V.

1978-01-01

The growth is briefly outlined of world daily power consumption and the possibilities are discussed of meeting this demand. Coal and nuclear power are of primary importance as energy resources for the present and the near future. Production costs per 1 kWh of electric power in nuclear power plants are already lower in fossil fuel power plants and both types of power plants have an environmental impact. Activities are presented of radioisotopes resulting from nuclear reactor operation and their release and environmental impact are discussed. An analysis is made of emissions from combustion processes and of wastes from fossil-fuel power plant operation. The environmental impacts of nuclear and fossil fuel power plants are compared. (Z.M.)

Nuclear and thermal power plants and the environment

Energy Technology Data Exchange (ETDEWEB)

Mejstrik, V [Ceskoslovenska Akademie Ved, Pruhonice. Ustav Krajinne Ekologie

1978-01-01

The growth is briefly outlined of world daily power consumption and the possibilities are discussed of meeting this demand. Coal and nuclear power are of primary importance as energy resources for the present and the near future. Production costs per 1 kWh of electric power in nuclear power plants are already lower than in fossil fuel power plants and both types of power plants have an environmental impact. Activities are presented of radioisotopes resulting from nuclear reactor operation and their release and environmental impact are discussed. An analysis is made of emissions from combustion processes and of wastes from fossil-fuel power plant operation. The environmental impacts of nuclear and fossil fuel power plants are compared.

Pilot incineration plant for solid, combustible, and low-level wastes

International Nuclear Information System (INIS)

Francioni, W.M.

Radioactively contaminated wastes are formed in the handling of radioactive materials at the Federal Institute for Reactor Research (FIRR) and in other facilities, hospitals, sanitoria, industry, and nuclear power plants. A large part of the wastes are combustible and only very slightly radioactive. Incineration of these wastes is obvious. A pilot incineration plant, henceforth called the PIP, for radioactive combustible wastes of the FIRR is surveyed. The plant and its individual components are described. The production costs of the plant and experience gained in operation available at present are reviewed. Solid combustible radioactive waste can be incinerated in the PIP. The maximum possible reduction in volume of these wastes is achieved by incineration. Subsequently the chemically sterile ashes can be consolidated in a stable block suitable for long-term storage mixing with cement

Affective imagery and acceptance of replacing nuclear power plants.

Science.gov (United States)

Keller, Carmen; Visschers, Vivianne; Siegrist, Michael

2012-03-01

This study examined the relationship between the content of spontaneous associations with nuclear power plants and the acceptance of using new-generation nuclear power plants to replace old ones. The study also considered gender as a variable. A representative sample of the German- and French-speaking population of Switzerland (N= 1,221) was used. Log-linear models revealed significant two-way interactions between the association content and acceptance, association content and gender, and gender and acceptance. Correspondence analysis revealed that participants who were opposed to nuclear power plants mainly associated nuclear power plants with risk, negative feelings, accidents, radioactivity, waste disposal, military use, and negative consequences for health and environment; whereas participants favoring nuclear power plants mainly associated them with energy, appearance descriptions of nuclear power plants, and necessity. Thus, individuals opposing nuclear power plants had both more concrete and more diverse associations with them than people who were in favor of nuclear power plants. In addition, participants who were undecided often mentioned similar associations to those participants who were in favor. Males more often expressed associations with energy, waste disposal, and negative health effects. Females more often made associations with appearance descriptions, negative feelings, and negative environmental effects. The results further suggest that acceptance of replacing nuclear power plants was higher in the German-speaking part of the country, where all of the Swiss nuclear power plants are physically located. Practical implications for risk communication are discussed. © 2011 Society for Risk Analysis.

Decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Vollradt, J.

1977-01-01

A survey of the main questions of decommissioning of nuclear power plants will be given in the sight of German utilities (VDEW-Working group 'Stillegung'). The main topics are: 1) Definitions of decommissioning, entombment, removal and combinations of such alternatives; 2) Radioactive inventory (build up and decay); 3) Experience up to now; 4) Possibilities to dismantle are given by possibility to repair nuclear power plants; 5) Estimated costs, waste, occupational radiation dose; 6) German concept of decommissioning. (orig./HK) [de

Radioactivity of coals and ash and slag wastes at coal-fired thermal power plants

Science.gov (United States)

Krylov, D. A.; Sidorova, G. P.

2013-04-01

This paper presents an analysis of published data on the content of radioactive nuclides in coals originating from various coal deposits, and in ash and slag wastes produced at coal-fired thermal power plants, as well as in fly ash emitted from thermal power plants into the atmosphere. Problems related to the use of coals with an elevated content of natural radionuclides (NRNs) and methods of their solution implemented at the Urtuyskoe coalfield are dealt with. Data on the analysis of Transbaikal coals for the NRN content, as well as weighted mean content of uranium and thorium in coals from the Siberian Region, are given. In order to reduce irradiation of plant personnel and the population of the areas where coal producers and coal-fired thermal power plants are located, it is necessary to organize very careful control of the NRN content in both coals and products of their combustion that are released into the environment. To solve the problem related to the control of radioactivity, the centralized approach and creation of a proper normative base are needed. Experience gained in developing the Urtuyskoe coalfield shows that it is possible to create an efficient system of coal quality control with respect to the radiation hygiene factor and provide protection of the environment and health of the population.

Safety aspects of nuclear power plant automation and robotics

International Nuclear Information System (INIS)

1992-10-01

The question being considered in this report is the extent to which the following aims are promoted through the use of robotics and automatic plant systems: nuclear power is safe (nuclear power plants and related facilities will not be constructed or allowed to continue operating if they are not perceived as being safe); nuclear power is economic (in comparison to other forms of electricity production once the environmental costs have been fully considered and as part of a unified energy policy); nuclear power is conservative (using nuclear fuel does not waste natural resources, damage the atmosphere, or produce unmanageable waste). Refs, figs, tabs

Safety analysis of disposal of decommissioning wastes from Loviisa nuclear power plant

International Nuclear Information System (INIS)

Vieno, T.; Nordman, H.; Rasilainen, K.; Suolanen, V.

1987-12-01

The repository for decommissioning wastes from the Loviisa nuclear power plant consisting of two 445 MWe PWR units is planned to be excavated at the depth of 90-130 meters in the bedrock of the power plant site. The reactor vessels weighing each about 215 tons will be transferred each in one piece into the repository. They are emplaced in an upright position in big holes excavated in the bottom of repository caverns. The reactor vessel internals are then emplaced inside the vessels. Finally, the vessels will be filled with concrete and the lids will be emplaced and sealed. Steam generators and pressurizers will also be disposed of uncutted. Other decommissioning wastes will be cut into smaller pieces and emplaced in concrete or wooden containers. The repository will be situated on the small island on which the power plant is located. The groundwater on the island contains two zones of different salinity: an upper zone of fresh, flowing groundwater and a lower zone of saline, stagnant groundwater where the repository will be situated. Three groundwater scenarios have been considered in the safety analysis: a scenario based on the present site conditions, an altered scenario where the repository is assumed to be situated in a zone of fresh, flowing groundwater and a distruptive event scenario with an intensive groundwater flow through the repository. The obtained results of the analysis show clear safety margins. In the basic scenario the maximum annul dose rate is 6x10 -14 Sv/a via the local sea pathways, 6x10 -11 Sv/a via the lake pathways and 4x10 -8 Sv/a via a well bored in the vicinity of the repository. In the altered groundwater scenario the maximum annual dose rate is 4x10 -10 Sv/a via the sea pathways, 3x10 -7 Sv/a via the lake pathways and 1x10 -5 Sv/a via the well pathway. In the unlikely disruptive event scenario the corresponding dose rates are 8x10 -10 Sv/a (sea), 7x10 -7 Sv/a (lake) and 2x10 -4 Sv/a (well)

Waste heat of HTR power stations for district heating

International Nuclear Information System (INIS)

Bonnenberg, H.; Schlenker, H.V.

1975-01-01

The market situation, the applied techniques, and the transport, for district heating in combination with HTR plants are considered. Analysis of the heat market indicates a high demand for heat at temperatures between 100 and 150 0 C in household and industry. This market for district heating can be supplied by heat generated in HTR plants using two methods: (1) the combined heat and power generation in steam cycle plants by extracting steam from the turbine, and (2) the use of waste heat of a closed gas turbine cycle. The heat generation costs of (2) are negligible. The cost for transportation of heat over the average distance between existing plant sites and consumer regions (25 km) are between 10 and 20% of the total heat price, considering the high heat output of nuclear power stations. Comparing the price of heat gained by use of waste heat in HTR plants with that of conventional methods, considerable advantages are indicated for the combined heat and power generation in HTR plants. (author)

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

Treatment and processing of the effluents and wastes (other than fuel) produced by a 900 MWe nuclear power plant

International Nuclear Information System (INIS)

Giraud

1983-01-01

Effluents produced by a 900 MWe power plant, are of three sorts: gaseous, liquid and solid. According to their nature, effluents are either released or stored for decaying before being released to the atmosphere. The non-contaminated reactor coolant effluents are purified (filtration, gas stripping) and treated by evaporation for reuse. Depending upon their radioactive level, liquid waste is either treated by evaporation or discharged after filtration. Solid waste issuing from previous treatments (concentrates, resins, filters) is processed in concrete drums using an encapsulation process. The concrete drum provides biological self-protection consistent with the national and international regulations pertaining to the transport of radioactive substance. Finally, the various low-level radioactive solid waste collected throughout the plant, is compacted into metal drums. Annual estimates of the quantity of effluents (gaseous, liquid) released in the environment and the number of drums (concrete, metal) produced by the plant figure in the conclusion

STUDY ON WASTE WATER TREATMENT PLANTS

Directory of Open Access Journals (Sweden)

Mariana DUMITRU

2015-04-01

Full Text Available Biogas is more and more used as an alternative source of energy, considering the fact that it is obtained from waste materials and it can be easily used in cities and rural communities for many uses, between which, as a fuel for households. Biogas has many energy utilisations, depending on the nature of the biogas source and the local demand. Generally, biogas can be used for heat production by direct combustion, electricity production by fuel cells or micro-turbines, Combined Hest and Power generation or as vehicle fuel. In this paper we search for another uses of biogas and Anaerobe Digestion substrate, such as: waste water treatment plants and agricultural wastewater treatment, which are very important in urban and rural communities, solid waste treatment plants, industrial biogas plants, landfill gas recovery plants. These uses of biogas are very important, because the gas emissions and leaching to ground water from landfill sites are serious threats for the environment, which increase more and more bigger during the constant growth of some human communities. That is why, in the developed European countries, the sewage sludge is treated by anaerobe digestion, depending on national laws. In Romania, in the last years more efforts were destined to use anaerobe digestion for treating waste waters and management of waste in general. This paper can be placed in this trend of searching new ways of using with maximum efficiency the waste resulted in big communities.

Investigation about the ecotown-enterprise for establishing recycling system of non-radioactive waste arising from power plant decommissioning

International Nuclear Information System (INIS)

Hironaga, Michihiko; Nishiuchi, Tatsuo; Ozaki, Yukio; Yamamoto, Kimio

2004-01-01

About 95% of demolition wastes generated by decommissioning nuclear power plants are below the clearance level, i.e., the wastes can be dealt with as industrial wastes. On that case, rational processing, disposal, and reuse are expectable. However, even if the demolition waste is below a clearance level, it seems to be difficult to be immediately accepted in general society with the demolition wastes. Therefore, it is important to establish the technology for an effective recycle system of demolition wastes, and to reuse demolition wastes as much as possible, resulting in recognition of the value by the society. On the other hand, as for recycling of industrial waste, the recycling enterprise is promoted in the domestic self-governing body in response to the 'eco-town enterprise' which is recommended by the government. This report investigates the system and subjects of a 'eco-town enterprise' for recycling demolition wastes. (author)

Survey of minipower plant for municipal solid waste firing

International Nuclear Information System (INIS)

Merkkiniemi, R.; Hyoety, P.; Saiha, E.

1999-01-01

Dumping of municipal waste to disposal areas has caused environmental problems, and this has led to more sophisticated disposal systems and high prices. That and a general demand to reduce the quantity of waste require new solutions, and a question has been arisen whether combustion could be used to treat waste. This project is concentrating to bum waste in a small-scale power plant. The background is one 10-MW pilot in Tampere city based on smelting furnace and a 0.3-MW pyrolyse furnace. The results of these from the viewpoint of operation and effluent were satisfactory and the burning process used is in line with the latest regulations. The second aspect is the economy of waste handling. The minipower plant is designed for reasonable small municipalities, abt 20 000 inhabitants or 1 - 20 MW heat input. According to several feasibility studies this method is the cheapest way to handle waste. A local heat demand is used to support the economy. The prices of products, heat and power, and cost are of the same level as the market prices. Thus, we expect a economical and environmentally safe operation with the minipower plant and it will also give a hint to solve a higher capacity demand of one unit. (orig.)

Topic of nuclear power plant wastes at fifth CMEA symposium on research of fuel and radioactive solution reprocessing

International Nuclear Information System (INIS)

Kyrs, M.; Napravnik, J.

1982-01-01

A survey is presented of the results of the work of Session 3 of the Symposium held in Marianske Lazne from April 7 to 10, 1981. The participants heard 44 papers mainly related to the following problem areas: existing methods and methods being developed of handling radioactive wastes from nuclear power plants; improvements in the technology of the concentration of liquid wastes by evaporation and other methods; solidification of concentrated liquid wastes into suitable form; methods of the treatment of solid (combustible, non-combustible and compactable) wastes; improvements in methods of the treatment of gaseous effluents. A survey was organized on criteria applied to methods used for radioactive waste processing. The inquiry showed that the principal criteria are the product Quality, costs for waste processing and the release of harmful substances into the environment. (Ha)

Treatment of some power plant waters

International Nuclear Information System (INIS)

Konecny, C.; Vanura, P.; Franta, P.; Marhol, M.; Tejnecky, M.; Fidler, J.

1987-01-01

Major results are summed up obtained in 1986 in the development of techniques for the treatment of coolant in the fuel transport and storage tank, of reserve coolant in the primary circuit and of waste water from the special nuclear power plant laundries, containing new washing agent Alfa-DES. A service test of the filter filled with Czechoslovak-made cation exchanger Ostion KSN in the boric acid concentrate filter station showed that the filter can be used in some technological circuits of nuclear power plants. New decontamination agents are also listed introduced in production in Czechoslovakia for meeting the needs of nuclear power plants. (author). 6 refs

Life-cycle impacts from novel thorium–uranium-fuelled nuclear energy systems

International Nuclear Information System (INIS)

Ashley, S.F.; Fenner, R.A.; Nuttall, W.J.; Parks, G.T.

2015-01-01

Highlights: • LCA performed for three open cycle Th–U-fuelled nuclear energy systems. • LCA for open cycle U-fuelled nuclear energy system (Areva’s EPR) used as benchmark. • U-fuelled EPR had lowest emissions per kWh over all systems studied in this work. • LCA model developed for thorium recovered from monazitic beach sands. • LCA model developed for the production of heavy water. - Abstract: Electricity generated from nuclear power plants is generally associated with low emissions per kWh generated, an aspect that feeds into the wider debate surrounding nuclear power. This paper seeks to investigate how life-cycle emissions would be affected by including thorium in the nuclear fuel cycle, and in particular its inclusion in technologies that could prospectively operate open Th–U-based nuclear fuel cycles. Three potential Th–U-based systems operating with open nuclear fuel cycles are considered: AREVA’s European Pressurised Reactor; India’s Advanced Heavy Water Reactor; and General Atomics’ Gas-Turbine Modular Helium Reactor. These technologies are compared to a reference U-fuelled European Pressurised Reactor. A life-cycle analysis is performed that considers the construction, operation, and decommissioning of each of the reactor technologies and all of the other associated facilities in the open nuclear fuel cycle. This includes the development of life-cycle analysis models to describe the extraction of thorium from monazitic beach sands and for the production of heavy water. The results of the life-cycle impact analysis highlight that the reference U-fuelled system has the lowest overall emissions per kWh generated, predominantly due to having the second-lowest uranium ore requirement per kWh generated. The results highlight that the requirement for mined or recovered uranium (and thorium) ore is the greatest overall contributor to emissions, with the possible exception of nuclear energy systems that require heavy water. In terms of like

Greater-than-Class C low-level radioactive waste characterization. Appendix A-2: Timing of greater-than-Class C low-level radioactive waste from nuclear power plants

International Nuclear Information System (INIS)

Steinke, W.F.

1994-09-01

Planning for the storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste. Timing, or the date the waste will require storage or disposal, is an integral aspect of that planning. The majority of GTCC LLW is generated by nuclear power plants, and the length of time a reactor remains operational directly affects the amount of GTCC waste expected from that reactor. This report uses data from existing literature to develop high, base, and low case estimates for the number of plants expected to experience (a) early shutdown, (b) 40-year operation, or (c) life extension to 60-year operation. The discussion includes possible effects of advanced light water reactor technology on future GTCC LLW generation. However, the main focus of this study is timing for shutdown of current technology reactors that are under construction or operating

Permitting a biomass-fired power plant in California -- A case study

International Nuclear Information System (INIS)

Reisman, J.I.; Needham, G.A.

1995-01-01

This paper describes the process of preparing an air permit application for a proposed biomass-fired power plant. The plant is designed to produce a net electric power output of 16 megawatts (MW) for sale to Pacific Gas and Electric Company. The biomass fuel will consist of urban wood waste, construction wood waste, and waste from agricultural products, such as tree prunings and fruit pits. The site is located in an industrial park in Soledad, California

The practical zoning at the Blayais nuclear power plant

International Nuclear Information System (INIS)

Marcucci, P.

2001-01-01

The nuclear facilities have the obligation to create a zoning of their installation. The different parts must allow to identify the waste in nuclear waste or conventional waste. The nuclear power plant of the Blayais is taken as example. (N.C.)

Decommissioning and back working of Greifswald nuclear power plant

International Nuclear Information System (INIS)

Rittscher, D.; Leushacke, D.F.; Meyer, R.

1998-01-01

At Nuclear Power Plant Greifswald, the Energiewerke Nord are carrying out the presently world's largest decommissioning project. This requires the gathering up of experience from the operation of the nuclear power plants at Greifswald, the decommissioning of other nuclear power plants, waste management, project management and licensing procedures for the decommissioning of nuclear power plants. That confirmed that the back working of nuclear plants is not a technical problem but a challenge for project management and logistics. It shows that the dismantling and disposal of nuclear plants is an ordinary process in our economic life. (orig.) [de

Economic competitiveness of nuclear power in China

International Nuclear Information System (INIS)

Hu Chuanwen

2005-01-01

Development of nuclear power in China has made a good progress. Currently, economic competitiveness of nuclear power compared to fossil-fuelled power plants is one of the major problems which hamper its development. This article presents the economic competitiveness of nuclear power in China with two-level analyses. First, levelized lifetime cost method is adopted for electricity generation cost comparisons. Important factors influencing economic competitiveness of nuclear power are described. Furthermore, a broad economic evaluation of the full fuel chain of nuclear power and fossil-fuelled plants is discussed concerning macro social-economic issues, environmental and health impacts. The comprehensive comparative assessment would be carried out for decision making to implement nuclear power programme. In consideration of external costs and carbon value, the economic competitiveness of nuclear power would be further improved. Facing swift economic growth, huge energy demand and heavy environmental burden, nuclear power could play a significant role in sustainable development in China. (authors)

Research of waste heat energy efficiency for absorption heat pump recycling thermal power plant circulating water

Science.gov (United States)

Zhang, Li; Zhang, Yu; Zhou, Liansheng; E, Zhijun; Wang, Kun; Wang, Ziyue; Li, Guohao; Qu, Bin

2018-02-01

The waste heat energy efficiency for absorption heat pump recycling thermal power plant circulating water has been analyzed. After the operation of heat pump, the influences on power generation and heat generation of unit were taken into account. In the light of the characteristics of heat pump in different operation stages, the energy efficiency of heat pump was evaluated comprehensively on both sides of benefits belonging to electricity and benefits belonging to heat, which adopted the method of contrast test. Thus, the reference of energy efficiency for same type projects was provided.

Chemistry in power plants 2011

International Nuclear Information System (INIS)

2011-01-01

Within the VGB Powertech conference from 25th to 27th October, 2011, in Munich (Federal Republic of Germany), the following lectures and poster contributions were presented: (1) The revised VGB standard for water-steam-cycle Chemistry; (2) Switchover from neutral operation to oxygen treatment at the power station Stuttgart-Muenster of EnBW Kraftwerke AG; (3) Steam contamination with degradation products of organic matters present in the feedwater of the Lanxess-Rubber cogeneration plant; (4) Laboratory scale on-line noble metal deposition experiments simulating BWR plant conditions; (5) Building a new demin installation for the power plant EPZ in Borssele; (6) Replacement of the cooling tower installations in the nuclear power plant Goesgen-Daenien AG; (7) Aging of IEX resins in demin plants - Cost optimisation by adaptation of regenerants; (8) The largest DOW trademark EDI System at a combined cycled plant in Europe; (9) Upgrading river Main water to boiler feed water - Experiences with ultrafiltration; (10) Experiences with treatment of the water-steam-cycle in the RDF power plant Nehlsen Stavenhagen with film-forming amines; (11) Comparative modelling of the bubbles thermal collapse and cavitations for estimation of bubbles collapse influence; (12) Overcoming the steam quality - issues from an HRSG for the production of process steam; (13) Legionella - new requirements for power plant operation; (14) How the right chemistry in the FGD helps to improve the removal in the waste water treatment plant; (15) High efficiency filtration in dry/semi-dry FGD plants; (16) Expanding the variety of renewable fuels in the biomass power plant Timelkam using the chemical input control; (17) Corrosion, operating experiences and process improvements to increase the availability and operating time of the biomass power plant Timelkam; (18) The influence of temperature on the measurement of the conductivity of highly diluted solutions; (19) A multiparameter instrumentation approach

Floating nuclear power plant safety assurance principles

International Nuclear Information System (INIS)

Zvonarev, B.M.; Kuchin, N.L.; Sergeev, I.V.

1993-01-01

In the north regions of the Russian federation and low density population areas, there is a real necessity for ecological clean energy small power sources. For this purpose, floating nuclear power plants, designed on the basis of atomic ship building engineering, are being conceptualized. It is possible to use the ship building plants for the reactor purposes. Issues such as radioactive waste management are described

An overview of U.S. plant performance improvement through effective radioactive waste management

International Nuclear Information System (INIS)

Sieberling, R.; Lyons, P.W.

1986-01-01

Radioactive waste volumes in the United States commercial nuclear power industry have declined over the last five years after increasing steadily in the late 1970's. This decline is considered to be especially significant because major backfits/modifications and major component repair/replacement at U.S. nuclear power stations have been accomplished during this period. This paper analyzes the key reasons for this performance and outlines the positive effects that this trend has upon overall nuclear plant performance. In reviewing plant performance data, there appears to be a direct correlation between overall plant performance and radioactive waste performance. For example, plants with high capacity factors, strong industrial safety programs, low collective man-rem, and good contamination controls, generally have a history of low radioactive waste volumes. The reasons for this excellent performance is the result of direct management and supervisory involvement in plant operations, implementation of high standards of performance, and monitoring performance against these standards. Using the techniques outlined in this paper, the U.S. nuclear power industry can continue to reduce the volume of low-level solid radioactive waste being generated

Effect of thermal and radioactive waste waters from nuclear power plant on recipient biocenosis

Energy Technology Data Exchange (ETDEWEB)

Veresikova, M; Csupka, S; Tomanova, E [Krajska Hygienicka Stanica, Bratislava (Czechoslovakia)

1979-01-01

During the years 1974 to 1976 the effect was studied of thermal and radioactive effluents from the A-1 nuclear power plant on aquatic microorganisms. The values obtained from the waste water canal and the river Dudvah after the canal discharged into the river were compared with the values found in the Dudvah before the discharge. The correlation between aquatic microorganisms and water temperature was found to be closest in the waste water canal and between microorganisms and /sup 137/Cs content in the Dudvah after sewer emptying. With increasing water temperature the populations of aquatic microorganisms decrease, with the exception of producers whose numbers will increase with rising water temperature. The content of /sup 137/Cs in water had an effect similar to that of water temperature.

Exhaust of plant oil fuelled cogeneration unit drives a two-stage refrigerating absorber; Abgas aus Pflanzenoel-BHKW treibt zweistufige Absorptionskaeltemaschine an

Energy Technology Data Exchange (ETDEWEB)

Schmid, W.

2008-05-15

Skating rinks are expensive to operate. In view of exploding energy prices, energetic optimisation is economically favourable even in more recent buildings. In the Hacker-Pschorr-Arena building at Bad Toelz, which was commissioned in 2004, the space HVAC system was modernized. A plant oil fuelled cogeneration unit and an exhaust-driven two-stage refrigerating absorber were installed. (orig.)

Acceptance and tracking of waste packages from nuclear power plants at the Centre de l'Aube

International Nuclear Information System (INIS)

Errera, J.; Tison, J.L.

2001-01-01

For 30 years, the French National Agency for Radioactive Waste Management (ANDRA) is in charge of the radioactive waste management and acquired a good knowledge relating to the control of low and intermediate level waste produced by nuclear power plants (NPP), the waste characteristics and the waste conditioning. The integrated waste management system for low-level radioactive waste in France implemented by ANDRA covers all stages from waste generation to final disposal at the Centre de I'Aube near surface facility. ANDRA defined a quality assurance program for waste management that specifies the level of quality to be achieved by solidification and packaging processes, defines quality control requirements and defines waste tracking requirements, from waste generation through final disposal. Verification of quality of waste packages is implemented at three levels of the waste management system. The first one consists of inspections of waste packages at the generator's premises and audits of the quality assurance organization of the waste generator. The second level of verification consists of the waste tracking system. It allows identifying and tracking each waste package from the step it is fabricated to its final disposal at the ANDRA site. The third level of verification is obtained by mean of non-destructive and destructive assays of waste packages. These assays allow to verify generator compliance with ANDRA's technical specifications and to investigate the accuracy of physical and radioactive characteristics reported to ANDRA by the generator. (author)

Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B., E-mail: rpgm@cdtn.br, E-mail: reisas@cdtn.br, E-mail: gfk@cdtn.br, E-mail: esct@cdtn.br, E-mail: tco@cdtn.br, E-mail: ama@cdtn.br, E-mail: francom@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, {sup 3}H, {sup 14}C, {sup 55}Fe, {sup 59}Ni, {sup 63}Ni, {sup 90}Sr, {sup 93}Zr, {sup 94}Nb, {sup 99}Tc, {sup 129}I, {sup 235}U, {sup 238}U, {sup 238}Pu, {sup 239}+{sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 242}Cm e {sup 243}+{sup 244}Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

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)

A process for separating aggregate from concrete waste during the dismantlement of nuclear power plants

International Nuclear Information System (INIS)

Koga, Yasuo; Inoue, Toshikatsu; Tateyashiki, Hisashi; Sukekiyo, Mitsuaki; Okamoto, Masamichi; Asano, Touichi.

1997-01-01

The decommissioning and dismantling of nuclear power plants will produce a large quantity of non-active waste concrete. From the viewpoint of recycling of this waste concrete the recovery of aggregate contained in concrete at 80% and reuse of it into a new plant construction are envisioned. For these purposes we have studied the recovery process of aggregate from concrete composed of a heating step followed by a milling step onto waste concrete blocks. We have found that higher operation temperature brings a better effect for the separation of aggregate from a concrete body, however too high temperature may reversely degrade a quality of recovered aggregate itself. The most effective heating temperature which is considered not to give the damage to a quality of aggregate stays between 200-500degC. The effect of a duration at such temperature zone is relatively small. As a conclusion we have found that 300degC of heating temperature and 30-120 minutes of a duration in a rod mill with high efficiency of rubbing work for getting coarse aggregate and an agitate mill for fine aggregate might be proper operating conditions under which we can recover both coarse and fine aggregate with the quality within JASS 5N standard. (author)

Nuclear power and other energy

International Nuclear Information System (INIS)

Doederlein, J.M.

1975-01-01

A comparison is made between nuclear power plants, gas-fuelled thermal power plants and oil-fired thermal power plants with respect to health factors, economy, environment and resource exploitation, with special reference to the choice of power source to supplement Norwegian hydroelectric power. Resource considerations point clearly to nuclear power, but, while nuclear power has an overall economic advantage, the present economic situation makes its heavy capital investment a disadvantage. It is maintained that nuclear power represents a smaller environmental threat than oil or gas power. Finally, statistics are given showing that nuclear power involves smaller fatality risks for the population than many other hazards accepted without question. (JIW)

CNG Fuelling Stations Design Philosophy

International Nuclear Information System (INIS)

Radwan, H.

2004-01-01

I. Overview (a) Compressed Natural Gas - CNG:- Natural Gas, as an alternative fuel for vehicles, is supplied from the Natural Gas Distribution Network to the CNG fuelling stations to be compressed to 250 bars. It is then dispensed, to be stored on board of the vehicle at about 200 bars in a cylinder installed in the rear, under carriage, or on top of the vehicle. When the Natural Gas is required by the engine, it leaves the cylinder traveling through a high pressure pipe to a high pressure regulator, where the pressure is reduced close to atmospheric pressure, through a specially designed mixer, where it is properly mixed with air. The mixture then flows into the engine's combustion chamber, and is ignited to create the power required to drive the vehicle. (b) CNG Fuelling Stations General Description: as Supply and Metering The incoming gas supply and metering installation primarily depend on the pressure and flow demands of the gas compressor. Natural Gas Compressor In general, gas compressors for natural gas filling stations have relatively low flow rates

Decommissioning of building part of nuclear power plant

International Nuclear Information System (INIS)

Sochor, R.

1988-01-01

The characteristics are discussed using literature data of building work during decommissioning or reconstruction of nuclear power plants. The scope of jobs associated with power plant decommissioning is mainly given by the size of contaminated parts, intensity of radioactivity, the volume of radioactive wastes and the possible building processes. Attention is devoted to the cost of such jobs and the effect of the plant design on cost reduction. (Z.M.). 6 refs

Physicochemical characterization of solidification agents used and products formed with radioactive wastes at LWR nuclear power plants

International Nuclear Information System (INIS)

Kibbey, A.H.; Godbee, H.W.

1978-01-01

Solidification of evaporator concentrates, filter sludges, and spent ion exchange resins used in LWR streams is discussed. The introduction of solidification agents to immobilize these sludges and resins can increase the volume of these wastes by a factor of slightly over 1 to greater than 2, depending on the binder chosen. The agents and methods used or proposed for use in solidification of LWR power plant wastes are generally suitable for treating most of the other-than-high-level wastes generated throughout the entire fuel cycle. Among the solidification agents most commonly used or suggested for use are the inorganic cements and organic plastics, which are listed and compared. A summary of considerations important in choosing a solidification agent is presented tabularly

Meteorological safeguarding of nuclear power plant operation in Czechoslovakia

International Nuclear Information System (INIS)

Rak, J.; Skulec, S.

1976-01-01

A meteorological tower 200 m high has to be built for meteorological control of the operation of the A-1 nuclear power plant at Jaslovske Bohunice. This meteorological station will measure the physical properties of the lower layers of the atmosphere, carry out experimental verifications of the models of air pollution, investigate the effects of waste heat and waste water from the nuclear power plant on the microclimate, provide the theoretical processing of measured data with the aim of selecting the most favourable model for conditions prevailing in the Czechoslovak Socialist Republic, perform basic research of the physical properties of the ground and boundary layers of the atmosphere and the coordination of state-wide plans in the field of securing the operation of nuclear power plants with regard to meteorology. (Z.M.)

Docommissioning of nuclear power plants

International Nuclear Information System (INIS)

Essmann, J.

1981-01-01

The German utilities operating nuclear power plants have long concerned themselves with aspects of decommissioning and for this purpose an engineering company was given a contract to study the entire spectrum of decommissioning. The results of this study have been available in autumn 1980 and it is possible to discuss all the aspects of decommissioning on a new basis. Following these results no change in the design concept of LWR nuclear power plants in operation or under construction is necessary because the techniques, necessary for decommissioning, are fully available today. The technical feasibility of decommissioning for power plants of Biblis A and KRB type has been shown in detail. The calculations of the quantity of waste produced during removal of a nuclear power plant could be confirmed and it could be determined with high procedure. The radiation dose to the decommissioning personnel is in the range of the radiation protection regulations and is in the same range as the radiation dose to the personnel within a yearly inservice inspection. (AF)

The future of nuclear power

International Nuclear Information System (INIS)

Corak, Z.

2004-01-01

Energy production and use will contribute to global warming through greenhouse gas emissions in the next 50 years. Although nuclear power is faced with a lot of problems to be accepted by the public, it is still a significant option for the world to meet future needs without emitting carbon dioxide (CO 2 ) and other atmospheric pollutants. In 2002, nuclear power provided approximately 17% of world energy consumption. There is belief that worldwide electricity consumption will increase in the next few years, especially in the developing countries followed by economic growth and social progress. Official forecasts shows that there will be a mere increase of 5% in nuclear electricity worldwide by 2020. There are also predictions that electricity use may increase at 75%. These predictions require a necessity for construction of new nuclear power plants. There are only a few realistic options for reducing carbon dioxide emissions from electricity generation: Increase efficiency in electricity generation and use; Expand use of renewable energy sources such as wind, solar, biomass and geothermal; Capture carbon dioxide emissions at fossil-fuelled electric generating plants and permanently sequester the carbon; Increase use of nuclear power. In spite of the advantages that nuclear power has, it is faced with stagnation and decline today. Nuclear power is faced with four critical problems that must be successfully defeat for the large expansion of nuclear power to succeed. Those problems are cost, safety, waste and proliferation. Disapproval of nuclear power is strengthened by accidents that occurred at Three Mile Island in 1979, at Chernobyl in 1986 and by accidents at fuel cycle facilities in Japan, Russia and in the United States of America. There is also great concern about the safety and security of transportation of nuclear materials and the security of nuclear facilities from terrorist attack. The paper will provide summarized review regarding cost, safety, waste and

Super compacting of drums with dry solid radioactive waste in the nuclear power plant of Laguna Verde;Super compactacion de bidones con desecho radiactivo solido seco en la central nucleo electrica Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Ramirez G, R.; Lara H, M. A.; Cabrera Ll, M.; Verdalet de la Torre, O., E-mail: marco.lara@cfe.gob.m [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Nautla-Cardel Km. 42.5, Alto Lucero, Veracruz (Mexico)

2009-10-15

The nuclear power plant of Laguna Verde located in the Gulf of Mexico, completes in this 2009, nineteen years to produce by nuclear means 4.78% of the electric power that Mexico requires daily. During this time, the Unit 1 has generated more of 88.85 million mega watt-hour and the Unit 2 more of 69.48 million mega watt-hour with an availability average of 83.55%. Derived of their operation cycles, the nuclear power plant has generated (as any other installation of its type) radioactive wastes of low activity that at the moment are temporarily stored in the site. Due to the life cycle of the nuclear power plant, actually has become necessary to begin a project series focused to continue guaranteeing the storage of these wastes, guarantee that is a license requirement for the operation of this nuclear installation before the National Commission of Nuclear Security and Safeguards. The Federal Commission of Electricity beginning a project that allows continue guaranteeing space of sufficient storage for the wastes that the nuclear power plant of Laguna Verde could generate for the rest of its useful life, this project consisted on a process of physical volume reduction of dry solid radioactive wastes denominated super compacting, it has made possible to reduce the volume that these wastes occupy in the temporary storage noted Dry Solid Radioactive Wastes Deposit located inside the site that occupies the nuclear power plant of Laguna Verde. This work presents the super compacting results, as well as a description of the realization of this task until concluding with the super compacting of 5,854 drums with dry solid radioactive waste of low activity. We will enunciate which were the radiological controls that the Department of Radiological Protection of the nuclear power plant of Laguna Verde applied to this work that was realized for first time in Mexico and the nuclear power plant. (Author)

Inertial Fusion Power Plant Concept of Operations and Maintenance

Energy Technology Data Exchange (ETDEWEB)

Anklam, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Knutson, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dunne, A. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kasper, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sheehan, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lang, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Roberts, V. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mau, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2015-01-15

Parsons and LLNL scientists and engineers performed design and engineering work for power plant pre-conceptual designs based on the anticipated laser fusion demonstrations at the National Ignition Facility (NIF). Work included identifying concepts of operations and maintenance (O&M) and associated requirements relevant to fusion power plant systems analysis. A laser fusion power plant would incorporate a large process and power conversion facility with a laser system and fusion engine serving as the heat source, based in part on some of the systems and technologies advanced at NIF. Process operations would be similar in scope to those used in chemical, oil refinery, and nuclear waste processing facilities, while power conversion operations would be similar to those used in commercial thermal power plants. While some aspects of the tritium fuel cycle can be based on existing technologies, many aspects of a laser fusion power plant presents several important and unique O&M requirements that demand new solutions. For example, onsite recovery of tritium; unique remote material handling systems for use in areas with high radiation, radioactive materials, or high temperatures; a five-year fusion engine target chamber replacement cycle with other annual and multi-year cycles anticipated for major maintenance of other systems, structures, and components (SSC); and unique SSC for fusion target waste recycling streams. This paper describes fusion power plant O&M concepts and requirements, how O&M requirements could be met in design, and how basic organizational and planning issues can be addressed for a safe, reliable, economic, and feasible fusion power plant.

Nuclear electric power plants. [Journal, in Russian]. Atomnye elektricheskie stantsii

Energy Technology Data Exchange (ETDEWEB)

Voronin, L M [ed.

1980-01-01

Separate articles are concerned with experience gained in the planning, exploitation, and adjustment of nuclear power plants with channel reactors. An examination is made of measures to be taken for assuring equipment reliability for nuclear power plants during the planning stage. Also examined is the experience gained in the operation of the pilot plants of the Kursk and Chernobyl' nuclear power plants, and the Bilibin nuclear thermal electric power plant. Considerable attention is given to the reprocessing and disposal of radioactive waste, the quality control of metal ducts in nuclear power plants, and the development of methods and means of controlling technological processes and equipment. The journal is intended for engineering-technical personnel of power plants, power supply administrations, adjustment, repair, and planning organizations.

Strategic analysis of biomass and waste fuels for electric power generation

International Nuclear Information System (INIS)

McGowin, C.R.; Wiltsee, G.A.

1993-01-01

Although the environmental and other benefits of using biomass and waste fuel energy to displace fossil fuels are well known, the economic realities are such that these fuels can not compete effectively in the current market without tax credits, subsidies, and other artificial measures. In 1992, EPRI initiated a strategic analysis of biomass and waste fuels and power technologies, both to develop consistent performance and cost data for the leading fuels and technologies and to identify the conditions that favor and create market pull for biomass and waste fuel energy. Using the interim results of the EPRI project, this paper compares the relative performance and cost of power generation from coal, natural gas, and biomass and waste fuels. The range of fuels includes wood, agricultural wastes, municipal solid waste, refuse-derived fuel, scrap tires, and tire-derived fuel, scrap tires, and tire-derived fuel. The power technologies include pulverized coal and natural gas/combined cycle power plants, cofiring with coal in coal-fired utility boilers, and wood gasification/combined cycle power plants. The analysis suggests that, in the near term, the highest-efficiency, lowest-cost, lowest-risk technology is cofiring with coal in industrial and utility boilers. However, this relative to fossil fuel, or the fuel user receives a tipping fee, subsidy, or emissions credit. In order to increase future use of biomass and waste fuels, a joint initiative, involving government, industry, and fuel suppliers, transporters, and users, is needed to develop low-cost and efficient energy crop production and power technology

Environmental hazards from nuclear power plants

International Nuclear Information System (INIS)

Bockelmann, D.

1973-04-01

The article discusses the radiation exposure due to nuclear power stations in normal operation and after reactor incidents. Also mentioned is the radiation exposure to the emissions from fuel reprocessing plants and radioactive waste facilities. (RW/AK) [de

Pellet fuelling and ELMy H-mode physics at JET

International Nuclear Information System (INIS)

Horton, L.D.

2001-01-01

As the reference operating regime for ITER, investigations of the ELMy H-mode have received high priority in the JET experimental programme. Recent experiments have concentrated in particular on operation simultaneously at high density and high confinement using high field side (HFS) pellet launch. The enhanced fuelling efficiency of HFS pellet fuelling is found to scale favourably to a large machine such as JET. The achievable density of ELMy H-mode plasmas in JET has been significantly increased using HFS fuelling although at the expense of confinement degradation back to L-mode levels. Initial experiments using control of the pellet injection frequency have shown that density and confinement can simultaneously be increased close to the values necessary for ITER. The boundaries of the available ELMy H-mode operational space have also been extensively explored. The power necessary to maintain the high confinement normally associated with ELMy H-mode operation is found to be substantially higher than the H-mode threshold power. The compatibility of ELMy H-modes with divertor operation acceptable for a fusion device has been studied. Narrow energy scrape-off widths are measured which place stringent limits on divertor power handling. Deuterium and tritium codeposition profiles are measured to be strongly in/out asymmetric. Successful modelling of these profiles requires the inclusion of the (measured) scrape-off layer flows and of the production in the divertor of hydrocarbon molecules with sticking coefficients below unity. Helium exhaust and compression are found to be within the limits sufficient for a reactor. (author)

Power generation from landfill gas, Middleton Broom, UK

International Nuclear Information System (INIS)

Anon.

1994-01-01

A power station is fuelled by gas from a landfill site at Middleton Broom, West Yorkshire in the North of England. The plant was commissioned in January 1993 and has a Declared Net Capacity of about 1.2 MW (enough power for about 700 homes). The electricity produced is exported to the National Grid. After various possible uses of the landfill gas were explored, it was decided that a power station fuelled by the gas was the most commercially viable prospect. Because of the proximity of housing to the landfill site, gas is pumped to the power station, located about 1,500 m from the landfill. (UK)

Nuclear power as a regional energy supply

International Nuclear Information System (INIS)

MacLoon, Frank.

1983-02-01

The author describes the Point Lepreau nuclear power plant and its impact on the electric power grid and the economy of the small province of New Brunswick. The 600 MW CANDU reactor is considered suitable for small operations and has an excellent world record. Although nuclear energy has high capital costs, its fuel costs are low, thus rendering it comparatively inflation free. Its fuel costs of 3 to 4 mills are contrasted with 40 mills for oil-fuelled units. The cost advantage of uranium over coal and oil permits New Brunswick to put aside funds for waste management and decommissioning. Regulatory streamlining is needed to reduce both expense and time of construction. The CANDU system is ideally suited to providing base load, with coal as an intermediate load supply and hydro for peaking. There is room for tidal power as a future part of the mix

Combined heat and power production planning in a waste-to-energy plant on a short-term basis

International Nuclear Information System (INIS)

Touš, Michal; Pavlas, Martin; Putna, Ondřej; Stehlík, Petr; Crha, Lukáš

2015-01-01

In many cases, WtE (waste-to-energy) plants are CHP (combined heat and power) producers. They are often integrated into a central heating system and they also export electricity to the grid. Therefore, they have to plan their operation on a long-term basis (months, years) as well as on a short-term basis (hours, days). Simulation models can effectively support decision making in CHP production planning. In general, CHP production planning on a short-term basis is a challenging task for WtE plants. This article presents a simulation based support. It is demonstrated on an example involving a real WtE plant. Most of the models of relevant WtE sub-systems (boilers, steam turbine) are developed using operational data and applying linear regression and artificial neural network technique. The process randomness given mainly by fluctuating heating value of waste leads to uncertainty in a calculation of CHP production and a stochastic approach is appropriate. The models of the sub-systems are, therefore, extended of a stochastic part and Monte-Carlo simulation is applied. Compared to the current planning strategy in the involved WtE plant, the stochastic simulation based planning provides increased CHP production resulting in better net thermal efficiency and increased revenue. This is demonstrated through a comparison using real operational data. - Highlights: • Introduction of a stochastic model of a CHP production in a waste-to-energy plant. • An application of the model for the next day CHP production planning. • Better net thermal efficiency and therefore increased revenue achieved.

A novel approach for treatment of CO{sub 2} from fossil fired power plants, Part A: The integrated systems ITRPP

Energy Technology Data Exchange (ETDEWEB)

Minutillo, M.; Perna, A. [Department of Industrial Engineering, University of Cassino, Via G. di Biasio, 43, 03043 Cassino, Frosinone (Italy)

2009-05-15

The environmental issues, due to the global warming caused by the rising concentration of greenhouse gases in the atmosphere, require new strategies aimed to increase power plants efficiencies and to reduce CO{sub 2} emissions. This two-paper work focuses on a different approach for capture and reduction of CO{sub 2} from flue gases of fossil fired power plant, with respect to conventional post-combustion technologies. This approach consists of flue gases utilization as co-reactants in a catalytic process, the tri-reforming process, to generate a synthesis gas suitable in chemical and energy industries (methanol, DME, etc.). In fact, the further conversion of syngas to a transportation fuel, such as methanol, is an attractive solution to introduce near zero-emission technologies (i.e. fuel cells) in vehicular applications. In this Part A, integrated systems for co-generation of electrical power and synthesis gas useful for methanol production have been defined and their performance has been investigated considering different flue gases compositions. In Part B, in order to verify the environmental advantages and energy suitability of these systems, their comparison with conventional technology for methanol production is carried out. The integrated systems (ITRPP, Integrated Tri-Reforming Power Plant) consist of a power island, based on a thermal power plant, and a methane tri-reforming island in which the power plants' exhausts react with methane to produce a synthesis gas used for methanol synthesis. As power island, a steam turbine power plant fuelled with coal and a gas turbine combined cycle fuelled with natural gas have been considered. The energy and environmental analysis of ITRPP systems (ITRPP-SC and ITRPP-CC) has been carried out by using thermochemical and thermodynamic models which have allowed to calculate the syngas composition, to define the energy and mass balances and to estimate the CO{sub 2} emissions for each ITRPP configuration. The

Development of bitumization plant of radioactive waste

International Nuclear Information System (INIS)

Lee, S.H.; Chun, K.S.; Song, H.Y.; Park, S.H.; Park, W.J.; Ryoo, R.; Cho, W.J.; Wee, K.S.; Lee, J.D.

1981-01-01

This study is to develop the bitumization techniques of radioactive waste concentrates from nuclear power plants (PWR), Cold-run and hot-run bitumization pilot plant were designed and constructed, and testing was carried out. The results show that the range of pH 7 to 8, in which a soluble product could form, is suitable for feeding in the waste and for its incorporation into asphalt, domestic blown asphalt is suitable up to an exposure of 10 8 rad. The estimated viscosity of the asphalt/waste product is about 14 poises at 175 0 C and the asphalt/wastes products in simulated sea-water for three weeks showed no evidence of swelling. The leaching rate from the spent resin/asphalt products in distilled water less than 1/1000 of that from the cement-products. It is considered that the resin content which is suitable for the incorporation of spent resin into asphalt is less than 50 wt%

Potential environmental effects of fusion reactor power plants

International Nuclear Information System (INIS)

Young, J.R.; Gore, B.F.; Coffman, F.E.

1976-01-01

Construction and operation of fusion power plants is expected to reduce the total environmental effects of 21st century power generation. Fusion power plant impacts due to noise, odors, vibrations, and sanitary wastes are expected to be insignificant. impacts due to land use, chemical releases, and aesthetics are expected to be reduced. Impacts due to heat releases, local socio-economic changes, and non-radioactive liquid and solid disposal are expected to be comparable to those for the alternative fission or coal-fired power systems. Radiation doses to the public due to radioactive wastes are expected to be comparable to, or less than, the trivial low doses due to fission power systems. Research and development will be required, however, to assure adequate containment of tritium, the primary radioisotope of concern. Prevention of accidental tritium releases is within the capability of current engineering practice. Current technology is capable of handling the solid radioactive waste which may be produced, with insignificant environmental impact. Major research efforts are necessary to determine if subtle long-term effects of magnetic fields exist and should be of concern. In view of the large quantities of construction materials required for fusion. Material availability may dictate 21st century power plant design and construction. The accident potential of fusion power plants should be lower than for fission systems. Accidental criticalities and plasma runaways are not considered to be possible. Loss of coolant accidents are not expected to result in damage to the containment. No fission products or actinides are present to be released in an accident, and most activation products are immobilized in structures. The biological hazard of tritium is orders of magnitude smaller than for fission products and actinides. Safeguards against diversion of fissile materials are not expected to be necessary

The Communities' research and development programme on decommissioning of nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

This is the first progress report of the European Community's programme (1979-1983) of research on the decommissioning of nuclear power plants. It shows the status of the programme on 31 December 1980. The programme seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontamination for decommissioning purposes; dismantling techniques; treatment of specific waste materials: steel, concrete and graphite; large transport containers for radioactive was produced in the dismantling of nuclear power plants; estimation of the quantities of radioactive wastes arising from decommissioning of nuclear power plants in the Community; influence of nuclear power plant design features on decommissioning

Waste Heat to Power Market Assessment

Energy Technology Data Exchange (ETDEWEB)

Elson, Amelia [ICF International, Fairfax, VA (United States); Tidball, Rick [ICF International, Fairfax, VA (United States); Hampson, Anne [ICF International, Fairfax, VA (United States)

2015-03-01

Waste heat to power (WHP) is the process of capturing heat discarded by an existing process and using that heat to generate electricity. In the industrial sector, waste heat streams are generated by kilns, furnaces, ovens, turbines, engines, and other equipment. In addition to processes at industrial plants, waste heat streams suitable for WHP are generated at field locations, including landfills, compressor stations, and mining sites. Waste heat streams are also produced in the residential and commercial sectors, but compared to industrial sites these waste heat streams typically have lower temperatures and much lower volumetric flow rates. The economic feasibility for WHP declines as the temperature and flow rate decline, and most WHP technologies are therefore applied in industrial markets where waste heat stream characteristics are more favorable. This report provides an assessment of the potential market for WHP in the industrial sector in the United States.

Simulation analysis of emissions trading impact on a non-utility power plant

International Nuclear Information System (INIS)

Imran, Kashif; Ahmad, Intesar; Hassan, Tehzeebul; Aslam, Muhammad Farooq; Ngan, Hon-Wing

2009-01-01

Non-utility power plants can competitively participate in open electricity market to reduce operational costs but in the absence of pollution charges or emissions trading such generators are tempted to cause greater pollution for profit maximization. This paper presents a solution that incorporates pollution charges for nitrogen oxides and sulphur dioxide emissions in line with existing national environmental quality standards and a new carbon dioxide emissions trading mechanism. A novel approach has been used for allocation of allowable emissions that favors efficiently fuelled and environmentally friendly operation for maximizing profit. Impact of proposed carbon trading on economical utilization of enormous indigenous coal reserves has been analyzed and determined to be acceptable. Software developed in this paper, harnessing Sequential Quadratic Programming capabilities of Matlab, is shown to be adequate simulation tool for various emissions trading schemes and an useful operational decision making tool for constrained non-linear optimization problem of a non-utility power plant. (author)

Simulation analysis of emissions trading impact on a non-utility power plant

Energy Technology Data Exchange (ETDEWEB)

Imran, Kashif; Ahmad, Intesar [Department of Electrical Engineering, COMSATS Institute of IT, Lahore (Pakistan); Hassan, Tehzeebul [Department of Electrical Engineering, University of Engineering and Technology (UET), Lahore (Pakistan); Aslam, Muhammad Farooq [Department of Electrical Engineering, University of Management and Technology (UMT), Lahore (Pakistan); Ngan, Hon-Wing [Department of Electrical Engineering, Hong Kong Polytechnic University (China)

2009-12-15

Non-utility power plants can competitively participate in open electricity market to reduce operational costs but in the absence of pollution charges or emissions trading such generators are tempted to cause greater pollution for profit maximization. This paper presents a solution that incorporates pollution charges for nitrogen oxides and sulphur dioxide emissions in line with existing national environmental quality standards and a new carbon dioxide emissions trading mechanism. A novel approach has been used for allocation of allowable emissions that favors efficiently fuelled and environmentally friendly operation for maximizing profit. Impact of proposed carbon trading on economical utilization of enormous indigenous coal reserves has been analyzed and determined to be acceptable. Software developed in this paper, harnessing Sequential Quadratic Programming capabilities of Matlab, is shown to be adequate simulation tool for various emissions trading schemes and an useful operational decision making tool for constrained non-linear optimization problem of a non-utility power plant. (author)

Simultaneous Waste Heat and Water Recovery from Power Plant Flue Gases for Advanced Energy Systems

Energy Technology Data Exchange (ETDEWEB)

Wang, Dexin [Gas Technology Inst., Des Plaines, IL (United States)

2016-12-31

This final report presents the results of a two-year technology development project carried out by a team of participants sponsored by the Department of Energy (DOE). The objective of this project is to develop a membrane-based technology to recover both water and low grade heat from power plant flue gases. Part of the recovered high-purity water and energy can be used directly to replace plant boiler makeup water as well as improving its efficiency, and the remaining part of the recovered water can be used for Flue Gas Desulfurization (FGD), cooling tower water makeup or other plant uses. This advanced version Transport Membrane Condenser (TMC) with lower capital and operating costs can be applied to existing plants economically and can maximize waste heat and water recovery from future Advanced Energy System flue gases with CO₂ capture in consideration, which will have higher moisture content that favors the TMC to achieve higher efficiency.

Input of biomass in power plants for power generation. Calculation of the financial gap. Final report

International Nuclear Information System (INIS)

Van Tilburg, X.; De Vries, H.J.; Pfeiffer, A.E.; Cleijne, J.W.

2005-09-01

The Ministry of Economic Affairs has requested ECN and KEMA to answer two questions. (1) Are the costs and benefits of projects in which wood-pellets are co-fired in a coal fired power plant representative for those of bio-oil fueled co-firing projects in a gas fired plant?; and (2) Are new projects representative for existing projects? To answer these questions, ECN and KEMA have calculated the financial gaps in six different situations: co-firing bio-oil in a gas fired power plant; co-firing bio-oil in a coal fired power plant; gasification of solid biomass; co-firing wood pellets in a coal fired power plant; co-firing agricultural residues in a coal fired power plant; and co-firing waste wood (A- and B-grade) in a coal fired power plant. The ranges and reference cases show that co-firing bio-oil on average has a smaller financial gap than the solid biomass reference case. On average it can also be concluded that when using waste wood or agro-residues, the financial gaps are smaller. Based on these findings it is concluded that: (1) The reference case of co-firing wood pellets in a coal fired power plant are not representative for bio-fuel options. A new category for bio-oil options seems appropriate; and (2) The financial gap of new projects as calculated in November 2004, is often higher then the ranges for existing projects indicate [nl

Strategic analysis of biomass and waste fuels for electric power generation

International Nuclear Information System (INIS)

McGowin, C.R.; Wiltsee, G.A.

1996-01-01

Although the environmental and other benefits of using biomass and waste fuel energy to displace fossil fuels are well known, the economic realities are such that these fuels cannot compete effectively in the current market without tax credits, subsidies and other artificial measures. In 1992, EPRI initiated a strategic analysis of biomass and waste fuels and power technologies, both to develop consistent performance and cost data for the leading fuels and technologies and to identify the conditions which favor and create market pull for biomass and waste fuel energy. Using the final results of the EPRI project, this paper compares the relative performance and cost of power generation from coal, natural gas, and biomass and waste fuels. The range of fuels includes wood, agricultural wastes, municipal solid waste, refuse-derived fuel, scrap tires and tire-derived fuel. The power technologies include pulverized coal and natural gas/combined cycle power plants, cofiring with coal in coal-fired utility boilers, direct combustion in dedicated mass burn, stoker and fluidized bed boilers, and wood gasification/combined cycle-power plants. The analysis suggests that, in the near term, the highest-efficiency, lowest-cost, lowest-risk technology is cofiring with coal in industrial and utility boilers. However, this approach is economically feasible only when the fuel is delivered at a deep discount relative to fossil fuel, or the fuel user receives a tipping fee, subsidy, or emissions credit. (author)

Comparative study of cogasification and co-combustion of communal sewage sludge in brown coal fuelled plants; Vergleich der Mitvergasung und Mitverbrennung kommunaler Klaerschlaemme in braunkohlegefeuerten Anlagen

Energy Technology Data Exchange (ETDEWEB)

Schiffer, H P; Bierbaum, K; Adlhoch, W; Thomas, G [Rheinbraun AG, Koeln (Germany)

1997-12-31

Co-combustion and cogasification of sewage sludge in brown coal fuelled plants are compared, and an economic assessment is made. (ABI) [Deutsch] Die Mitverbrennung und Mitvergasung von Klaerschlamm in braunkohlegefeuerten Anlagen werden verglichen und auf ihre Wirtschaftlichkeit hin untersucht. (ABI)

Comparative study of cogasification and co-combustion of communal sewage sludge in brown coal fuelled plants; Vergleich der Mitvergasung und Mitverbrennung kommunaler Klaerschlaemme in braunkohlegefeuerten Anlagen

Energy Technology Data Exchange (ETDEWEB)

Schiffer, H.P.; Bierbaum, K.; Adlhoch, W.; Thomas, G. [Rheinbraun AG, Koeln (Germany)

1996-12-31

Co-combustion and cogasification of sewage sludge in brown coal fuelled plants are compared, and an economic assessment is made. (ABI) [Deutsch] Die Mitverbrennung und Mitvergasung von Klaerschlamm in braunkohlegefeuerten Anlagen werden verglichen und auf ihre Wirtschaftlichkeit hin untersucht. (ABI)

THE IMPROVEMENT OF LOW-WASTE TECHNOLOGIES OF WORKING BODY OF WATER PREPARATION AT THERMAL AND NUCLEAR POWER PLANTS

Directory of Open Access Journals (Sweden)

K. D. Rymasheuskaya

2017-01-01

Full Text Available In the present work the main directions of water desalination technologies improving have been analyzed. Possible techniques of high-quality treatment of water that enable the reduction of amounts of environmentally hazardous substances to be discharged into the hydrosphere are indicated. The purpose of the work was to improve the ecological efficiency and the effectiveness of water treatment equipment at heat power plants when designing new and the modernizing existing water treatment schemes. In order to achieve this goal the following problems have been solved: the one of analyzing the main directions of the improvement of technologies of working body of water preparation at thermal and nuclear power plants; of analyzing the main directions of reduction of total volume of highly mineralized power plant wastewaters; of developing the technological scheme of recycling of concentrate of membrane installations and regenerants of ionite filters in acid and alkali; of developing the technological scheme of transformation of the sludge in pre-processing waste into valuable commodity products. The results of research can be applied for the design of new and the modernization of existing water treatment installations of thermal and nuclear power plants. It will enable to reduce considerably the use of natural water and the amount of chemicals added as well as the volume of wastewater and the concentration of dissolved solids in it. As a consequence, the negative impact of thermal and nuclear power plants on the hydrosphere will be reduced. 

Dose reduction at nuclear power plants

International Nuclear Information System (INIS)

Baum, J.W.; Dionne, B.J.

1983-01-01

The collective dose equivalent at nuclear power plants increased from 1250 rem in 1969 to nearly 54,000 rem in 1980. This rise is attributable primarily to an increase in nuclear generated power from 1289 MW-y to 29,155 MW-y; and secondly, to increased average plant age. However, considerable variation in exposure occurs from plant to plant depending on plant type, refueling, maintenance, etc. In order to understand the factors influencing these differences, an investigation was initiated to study dose-reduction techniques and effectiveness of as low as reasonably achievable (ALARA) planning at light water plants. Objectives are to: identify high-dose maintenance tasks and related dose-reduction techniques; investigate utilization of high-reliability, low-maintenance equipment; recommend improved radioactive waste handling equipment and procedures; examine incentives for dose reduction; and compile an ALARA handbook

Software system for fuel management at Embalse nuclear power plant

International Nuclear Information System (INIS)

Grant, C.; Pomerantz, M.E.; Moreno, C.A.

2002-01-01

For accurate tracking of flux and power distribution in a CANDU reactor, the information needed is evaluated from a neutronic code calculation adjusted with experimental values, making use of in-core vanadium detectors at 102 locations together with auxiliary programs.The basic data that feed these programs come from the geometric and neutronic features and the actual instantaneous operating parameters. The system that provides all this information should be designed to meet with software quality assurance requirements. A software system was implemented at Embalse Nuclear Power Plant and it is in operation since 1998 after two year testing. This PC version replaced the former system introducing new concepts in its architecture. The neutronic code runs by procedures implemented in a language of macro instructions, so only new data are loaded for two consecutive instantaneous cases avoiding unnecessary data repetition. After each step, all results of neutronic calculation are stored in master files. Afterwards other auxiliary programs retrieve basic data for further evaluation and files are sorted in different thematic folders using a specific codification, for reevaluating further calculations over any specific case. The whole system can be installed in any PC. The package is provided with its general and particular support documentation and procedures for each program.The main purpose of the system is to track fuel and power distribution calculated after a certain period where fuelling operation were done in between. The main code, PUMA, evaluates in a 3-D, two-group scheme using finite difference diffusion theory. After neutronic calculation is performed, other programs allow to retrieve assorted information valid for fuel strategy and to build the fuelling operation list to be sent to the operation shifts. This program also permits to evaluate the accuracy of PUMA by doing comparisons with experimental values. Along with these features, some other system

Ion temperature anisotropy in high power helium neutral beam fuelling experiments in JET

Energy Technology Data Exchange (ETDEWEB)

Maas, A C; Core, W G.F.; Gerstel, U C; Von Hellermann, M G; Koenig, R W.T.; Marcus, F B [Commission of the European Communities, Abingdon (United Kingdom). JET Joint Undertaking

1994-07-01

During helium beam fuelling experiments in JET, distinctive anisotropic features have been observed in the velocity distribution function describing both fast and thermal alpha particle populations. During the initial fuelling phase the central helium ion temperature observed perpendicular to the magnetic field is higher than the central electron temperature, while the central helium ion temperature observed parallel to the magnetic field is lower than or equal to the central electron temperature. In order to verify temperature measurements of both perpendicular and parallel lines of sight, other independent methods of deducing the ion temperature are investigated: deuterium ion temperature, deuterium density, comparison with neutron rates and profiles (influence of a possible metastable population of helium). 6 refs., 7 figs.

Thermodynamic analysis of a combined gas turbine power plant with a solid oxide fuel cell for marine applications

Directory of Open Access Journals (Sweden)

Yousri M.A. Welaya

2013-12-01

Full Text Available Strong restrictions on emissions from marine power plants (particularly SOx, NOx will probably be adopted in the near future. In this paper, a combined solid oxide fuel cell (SOFC and gas turbine fuelled by natural gas is proposed as an attractive option to limit the environmental impact of the marine sector. It includes a study of a heat-recovery system for 18 MW SOFC fuelled by natural gas, to provide the electric power demand onboard commercial vessels. Feasible heat-recovery systems are investigated, taking into account different operating conditions of the combined system. Two types of SOFC are considered, tubular and planar SOFCs, operated with either natural gas or hydrogen fuels. This paper includes a detailed thermodynamic analysis for the combined system. Mass and energy balances are performed, not only for the whole plant but also for each individual component, in order to evaluate the thermal efficiency of the combined cycle. In addition, the effect of using natural gas as a fuel on the fuel cell voltage and performance is investigated. It is found that a high overall efficiency approaching 70% may be achieved with an optimum configuration using SOFC system under pressure. The hybrid system would also reduce emissions, fuel consumption, and improve the total system efficiency.

Thermodynamic analysis of a combined gas turbine power plant with a solid oxide fuel cell for marine applications

Science.gov (United States)

Welaya, Yousri M. A.; Mosleh, M.; Ammar, Nader R.

2013-12-01

Strong restrictions on emissions from marine power plants (particularly SOx, NOx) will probably be adopted in the near future. In this paper, a combined solid oxide fuel cell (SOFC) and gas turbine fuelled by natural gas is proposed as an attractive option to limit the environmental impact of the marine sector. It includes a study of a heatrecovery system for 18 MW SOFC fuelled by natural gas, to provide the electric power demand onboard commercial vessels. Feasible heat-recovery systems are investigated, taking into account different operating conditions of the combined system. Two types of SOFC are considered, tubular and planar SOFCs, operated with either natural gas or hydrogen fuels. This paper includes a detailed thermodynamic analysis for the combined system. Mass and energy balances are performed, not only for the whole plant but also for each individual component, in order to evaluate the thermal efficiency of the combined cycle. In addition, the effect of using natural gas as a fuel on the fuel cell voltage and performance is investigated. It is found that a high overall efficiency approaching 70% may be achieved with an optimum configuration using SOFC system under pressure. The hybrid system would also reduce emissions, fuel consumption, and improve the total system efficiency.

Fuelling doubts over BNFL

International Nuclear Information System (INIS)

Wyman, V.

1989-01-01

The House of Commons Select Committee on Energy has recently questioned the whole philosophy behind one of Britain's largest process plant operators, British Nuclear Fuels (BNFL). The committee's criticisms and recommendations are of significance to more than just BNFL, whose 1988 turnover of Pound 839 million produced a Pound 100 million pretax profit for its owner, the government. For BNFL's fortunes are linked intimately with those of its customers, the nuclear power station operators. The members of Parliament are especially critical of BNFL's right to pass most of its cost increases on to its customers, which will make the nuclear power stations less attractive to investors when they are privatised. The committee also voices other serious concerns about BNFL's operations. These include worry about the future ownership of plutonium produced by BNFL from its customers' spent nuclear fuel; whether resultant nuclear waste is sent back to overseas customers; and the fate of the vast sums being put aside for future decommissioning of BNFL plant. (author)

Environmental protection in thermal power plants

International Nuclear Information System (INIS)

1987-01-01

This workbook is a compilation of the most important facts and data that are relevant today for environmental protection in thermal power plants. Unlike the other issues the text is not in the form of a random collection of data but in the form of a complete presentation. Possible elaboration projects for pupils can be easily derived from the individual sections. These deal with: the discussion about environmental protection; forest decline; sources of emission; nuisances in the Federal Republic of Germany; environmental protection in fossil-fuel power plants - clean air - cooling water utilization and water protection - noise; environmental protection in nuclear power plants - radioactive material produced in nuclear reactors and the retention of such materials - radioactive waste materials - monitoring of radioactive emissions; accessory materials and hints. (orig./HSCH) [de

A survey of low-level radioactive waste treatment methods and problem areas associated with commercial nuclear power plants

International Nuclear Information System (INIS)

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

1987-01-01

A survey was made (June 1985) of technologies that were currently being used, those that had been discontinued, and those that were under consideration for treatment of low-level radioactive waste from the commercial nuclear power plants in the United States. The survey results included information concerning problems areas, areas needing research and development, and the use of mobile treatment facilities

Small-scale power plant potential in Finland

International Nuclear Information System (INIS)

Helynen, S.

1993-01-01

The presentation discusses the small-scale power plant potential in Finland. The study of the potential is limited to W-scale power plants producing both electric power and heat using solid fuels. The basic power plant dimensioning and electric power load determination is based on traditional boiler and gas turbine technology. The possible sites for power plants are communities using district heating, and industrialized sites needing process steam or heat. In 1990 70 % (17 TWh) of district heat was produced by gas turbines. Ten communities have an own back-pressure power plant, and 40 communities buy heat from industrial plants, owing back-pressure power generation. Additionally about 40 communes buy district heat from companies, owned by power companies and industry. Estimates of small-scale power plant potential has been made plant wise on the basis of district heat loads and industrial heat needs. The scale of the plants has been limited to scale 3 MWe or more. The choosing of the fuel depends on the local conditions. The cheapest indigenous fuels in many communes are industrial wood wastes, and both milled and sod peat. The potential of steam technology based small-scale power plants has been estimated to be about 50 plants in 1992/1993, the total power of which is 220-260 MW. The largest estimate is base situation, in which there would be energy cooperation between the communes and industry. The fuel used by the power plants would be about 5.4-6.6 TWh/a corresponding to 270-330 million FIM/a. The total investment costs of the plants would be about 2.0 billion FIM. The plants would employ about 250 persons, and the fuel supply (wood or peat) about 100 persons

Management of radioactive waste from non-power applications in the Netherlands

International Nuclear Information System (INIS)

Codee, H.D.K.

2002-01-01

Radioactive waste results from the use of radioactive materials in hospitals, research establishments, industry and nuclear power plants. The Netherlands forms a good example of a country with a small and in the near future ending nuclear power programme. The radioactive waste from non-power applications therefore strongly influences the management choices. A dedicated waste management company COVRA, the Central Organisation for Radioactive Waste manages all radioactive waste produced in the Netherlands. For the small volume, but broad spectrum of radioactive waste, a management system was developed based on the principle to isolate, to control and to monitor the waste. Long-term storage is an important element in this management strategy. It is not seen as a 'wait and see' option but as a necessary step in the strategy that will ultimately result in final removal of the waste. Since the waste will remain retrievable for a long time new technologies and new disposal options can be applied when available and feasible. (author)

Hazard caused by radioactive wastes from nuclear power plants in comparison with both natural hazards and those caused by solid wastes from coal-fired plants

International Nuclear Information System (INIS)

Strupczewski, A.

1988-01-01

The risks concerned with radioactive solid wastes deposited deeply underground as well as with low-, intermediate- and high-level radioactive wastes are compared with natural radioactivity and thermal plants solid wastes threats. 17 refs., 5 figs., 4 tabs. (A.S.)

Materials availability for fusion power plant construction

International Nuclear Information System (INIS)

Hartley, J.N.; Erickson, L.E.; Engel, R.L.; Foley, T.J.

1976-09-01

A preliminary assessment was made of the estimated total U.S. material usage with and without fusion power plants as well as the U.S. and foreign reserves and resources, and U.S. production capacity. The potential environmental impacts of fusion power plant material procurement were also reviewed including land alteration and resultant chemical releases. To provide a general measure for the impact of material procurement for fusion reactors, land requirements were estimated for mining and disposing of waste from mining

Management of very low level waste from decommissioning of the A-1 Jaslovske Bohunice nuclear power plant in Slovakia

International Nuclear Information System (INIS)

Burclova, J.; Konecny, L.; Mrskova, A.

2000-01-01

Efforts were made to accelerate decommissioning, particularly of the nuclear power plant A1 of the HWGCR type. Progress made and current developments in this subject area are reviewed. Radioactive waste categories are described along with release criteria. An overview is provided on contaminated scrap and the sorting of contaminated soil and concrete. (author)

Compatibility of the ultraviolet light-ozone system for laundry waste water treatment in nuclear power plants

International Nuclear Information System (INIS)

Matsuo, Toshiaki; Nishi, Takashi; Matsuda, Masami; Izumida, Tatsuo

1997-01-01

As an alternative treatment system for laundry waste water in nuclear power plants, a system was chosen in which such organic compounds as surfactant would be oxidized by ultraviolet (UV) light and ozone. The system compatibility, UV light source, and dissolved ozone concentration were examined through experiments. First, ozone gas was absorbed in the waste water. After the dissolved ozone concentration equilibrated at the desired value, the waste water was irradiated by a mercury lamp. Then, the time dependence of the concentrations of the organic compounds, the dissolved ozone, and the hydrogen peroxide were measured to estimate the treatment rate of the system. The mercury lamp with a 10 5 -Pa vapor pressure achieved large UV radiation and a treatment rate increase, leading to a compatible system without secondary waste generation. The effect of the dissolved ozone concentration on the treatment rate was saturated when concentration was >3.3 x 10 -4 mol/10 -3 m 3 at the time UV radiation was started. Numerical results indicated the saturation was due to hydrogen peroxide generation, which prevents hydroxyl radical generation

Radiological impact of the storage of solid wastes from coal-fored power plants

International Nuclear Information System (INIS)

Hugon, J.; Caries, J.C.; Patellis, A.; Roussel, S.

1983-01-01

Solid wastes from the coal-fired power plant of GARDANNE are stared in piles, outside near the unit. The coal contains a high proportion of sulfur, so the storage pile is a very reducing middle. The radium coming from the ore, which is mostly retained in the bottom ashes, could then be solubilized again, by physicochemical processes, leached by the rain and reach the nearest population through the food-chain pathways. Leaching-tests where made with three sampling series. The measurement datas show that only 15% of the 226 Ra can be solved and that the Ra 226 observed concentrations in vegetal samples come mostly from transportation of dust by the wind [fr

Thermodynamic effects when utilizing waste heat from condensation in cases of a reduced vacuum in steam turbine plants of thermal power stations, to provide heat at low temperatures

Energy Technology Data Exchange (ETDEWEB)

Vasiljevic, N.; Savic, B.; Stojakovic, M.

1986-01-01

There is an interesting variant of cogeneration in the steam turbine system of a thermal power plant, i.e. the utilisation of the waste heat of condensation with a reduced vacuum without reconstruction of the thermal power plant. The thermodynamic effect in cogeneration was calculated in consideration of the dynamics of heat consumption. This cogeneration process has the advantage of saving primary energy without reconstruction of the thermal power plant.

Encapsulation pilot plant of radioactive wastes in thermosetting resins

International Nuclear Information System (INIS)

1982-01-01

The thermosetting resins (polyesters, epoxides) are used to encapsulate the low and intermediate - level radioactive wastes. The testing program concerning the drums produced by the pilot plant of the Chooz nuclear power plant is described. The installation operating is examined while thinking of the industrial application. The production costs are then evaluated

Waste incinerating plant

Energy Technology Data Exchange (ETDEWEB)

1972-12-01

This plant is provided with a NKK-Ferunst type reciprocating stage fire lattice which has a good ventilating effect and a proper stirring and loosening effect, achieving a high combustion rate, and has also a gas flow system by which gas can flow in the reverse direction to adjust its flow for seasonal variations in the quality of waste. Also, a room in which the exhaust gas is mixed is provided in this plant as a help for the complete neutralization and combustion of acid gas such as hydrogen chloride and imperfect combustion gas from plastic waste contained in wastes. In this system, waste can accept a sufficient radiant heat from the combustion gas, the furnace wall, and the ceiling; even on the post combustion fire lattice the ashes are given heat enough to complete the post combustion, so that it can be completely reduced to ashes. For these reasons, this type of incinerator is suitable for the combustion of low-calorie wastes such as city wastes. The harmful gases resulting from the combustion of wastes are treated completely by desulfurization equipment which can remove the oxides of sulfur. This type of plant also can dispose of a wide variety of wastes, and is available in several capacities from 30 tons per 8 hr to 1,200 tons per 24 hr.

Maximization of revenues for power sales from a solid waste resources recovery facility

Energy Technology Data Exchange (ETDEWEB)

1991-12-01

The report discusses the actual implementation of the best alternative in selling electrical power generated by an existing waste-to-energy facility, the Metro-Dade County Resources Recovery Plant. After the plant processes and extracts various products out of the municipal solid waste, it burns it to produce electrical power. The price for buying power to satisfy the internal needs of our Resources Recovery Facility (RRF) is substantially higher than the power price for selling electricity to any other entity. Therefore, without any further analysis, it was decided to first satisfy those internal needs and then export the excess power. Various alternatives were thoroughly explored as to what to do with the excess power. Selling power to the power utilities or utilizing the power in other facilities were the primary options.

Power plants 2009. Lectures

International Nuclear Information System (INIS)

2009-01-01

Within the Annual Conference 2009 of the VGB PowerTech e.V. (Essen, Federal Republic of Germany) from 23rd to 25th May, 2009, in Lyon (France) the following lectures were held: (1) Electricity demand, consequences of the financial and economic crisis - Current overview 2020 for the EU-27 (Hans ten Berge); (2) Status and perspectives of the electricity generation mix in France (Bernard Dupraz); (3) European electricity grid - status and perspective (Dominique Maillard); (4) Technologies and acceptance in the European energy market (Gordon MacKerran); (5) EPR construction in Finland, China, France, (Claude Jaouen); (6) EPR Flamanville 3: A project on the path towards nuclear revival (Jacques Alary); (7) Worldwide nuclear Revival and acceptance (Luc Geraets); (8) An overview on the status of final disposal of radioactive wastes worldwide (Piet Zuidema); (9) Who needs pumped storage plants? PSP are partner to grid stability and renewable energies (Hans-Christoph Funke); (10) Sustainable use of water resources to generate electricity safely and efficiently (Patrick Tourasse); (11) The growth strategy of RWE Innogy - Role of RES in RWE strategy (Fritz Vahrenholt); (12) Solar technologies towards grid parity - key factors and timeframe (G. Gigliucci); (13) Overview on CCS technologies and results of Vattenfalls oxyfuel pilot plant (Philippe Paelinck); (14) Development perspectives of lignite-based IGCC-plants with CCS (Dietmar Keller); (15) Post combustion capture plants - concept and plant integration (Wolfgang Schreier); (16) CCS fossil power generation in a carbon constraint world (Daniel Hofmann); (17) CEZ group strategy in Central and South Eastern Europe (Jan Zizka); (18) Strategy and projects of DONG Energy (Jens Erik Pedersen); (19) E.ON coal-based power generation of the future - The highly efficient power plant and downstream separation of carbon dioxide (Gerhard Seibel); (20) Final sage of first supercritical 460 MW e l. CFB Boiler construction - firs

Radioactive wastes management in fiscal year 1983 in the fuel reprocessing plant

International Nuclear Information System (INIS)

1985-01-01

In the nuclear fuel reprocessing plant of Power Reactor and Nuclear Fuel Development Corporation, the releases of radioactive gaseous and liquid wastes are so managed not to exceed the respective objective release levels. Of the radioactive liquid wastes, the high level concentrated wastes are stored in tanks and the low level wastes are stored in tanks or asphalt solidified. For radioactive solid wastes, high level solid wastes are stored in casks, low level solid wastes and asphalt solids in drums etc. The releases of radioactive gaseous and liquid wastes in the fiscal year 1983 were below the objective release levels. The radioactive wastes management in the fuel reprocessing plant in fiscal year 1983 is given in tables, the released quantities, the stored quantities, etc. (Mori, K.)

Role and position of Nuclear Power Plants Research Institute in nuclear power industry

International Nuclear Information System (INIS)

Metke, E.

1984-01-01

The Nuclear Power Plants Research Institute carries out applied and experimental research of the operating states of nuclear power plants, of new methods of surveillance and diagnosis of technical equipment, it prepares training of personnel, carries out tests, engineering and technical consultancy and the research of automated control systems. The main research programme of the Institute is the rationalization of raising the safety and operating reliability of WWER nuclear power plants. The Institute is also concerned with quality assurance of selected equipment of nuclear power plants and assembly works, with radioactive waste disposal and the decommissioning of nuclear power plants as well as with the preparation and implementation of the nuclear power plant start-up. The Research Institute is developing various types of equipment, such as equipment for the decontamination of the primary part of the steam generator, a continuous analyzer of chloride levels in water, a gas monitoring instrument, etc. The prospects are listed of the Research Institute and its cooperation with other CMEA member countries. (M.D.)

Options for the ultimate storage of low and medium level radioactive wastes produced at Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Emeterio, Miguel

1991-01-01

The devoted time and still to be expend in prepare, execute and teach permanent and safe solutions to the problem of the evaluation of radioactive wastes reflects the political, economic and environmental importance with respect to public health and safety invested in this task, as well as, its technological challenges. In the case of Laguna Verde nuclear power plant, its low and medium level radioactive wastes are stored in the beginning in a temporal store with a capacity of 2000 m 3 sufficient to four years of normal operation; according to what it is necessary to select one of different ways of waste storage. Different technologies has been evaluated and the preliminary conclusion is that for Mexico the more feasible way to store radioactive wastes is in tumulus (Author)

Theseus, the 50 MW solar thermal power plant; Das solarthermische 50-MW-Kraftwerk Theseus

Energy Technology Data Exchange (ETDEWEB)

Brakmann, G. [Fichtner GmbH und Co. KG, Stuttgart (Germany). Solarenergieprojekte

1998-04-01

The Isle of Crete measures 8331 km{sup 2}, and this island renowned for its historical sites attracts millions of tourists every year. Like any other branch of industry, tourism, which is called a ``white`` industry, has an ever growing demand for electric power. Up to now, electricity generation on the island is based on fossil-fuelled thermal power plants. However, recent developments indicate that this technology might be overtaken soon by the novel Theseus power plant (Thermal Solar European Power Station) currently under construction. It is expected to usher in a new era of power generation on the Isle of Crete. (orig./CB) [Deutsch] Die 8 331 km{sup 2} grosse Insel Kreta wurde vor ueber 3 500 Jahren besiedelt. Der geschichtstraechtige Ort ist ein hochgeschaetztes Reiseziel von Millionen Griechenlandurlaubern. Wie jede Art von Industrie, so benoetigt auch die als `weisse Industrie` bezeichnete Touristikbranche immer mehr elektrische Energie. Diese wird derzeit auf Kreta ausschliesslich mit thermischen Kraftwerken, welche fossile Brennstoffe verbrennen, erzeugt. Aber die Vorherrschaft dieser Technologie kann schon bald mit dem neuen solarthermischen Kraftwerk Theseus (Thermal Solar European Power Station) gebrochen werden. Es soll in wenigen Jahren eine neue Aera der Energieerzeugung auf Kreta einlaeuten. (orig.)

Radioactive Waste Disposal Pilot Plant concept for a New Mexico site

International Nuclear Information System (INIS)

Weart, W.D.

1976-01-01

Twenty years of investigation have shown that disposal of nuclear wastes in deep salt formations is the surest means of isolating these wastes from the biosphere for the extremely long period of time required. A large scale demonstration of this capability will soon be provided by a Radioactive Waste Disposal Pilot Plant (RWDPP) to be developed in southeastern New Mexico. Initially, the pilot plant will accept only ERDA generated waste; high level waste from the commercial power reactor fuel cycle will eventually be accommodated in the pilot plant and the initial RWDPP design will be compatible with this waste form. Selection of a specific site and salt horizon will be completed in June 1976. Conceptual design of the RWDPP and assessment of its environmental impact will be completed by June 1977. Construction is expected to start in 1978 with first waste accepted in 1982. The present concept develops disposal areas for all nuclear waste types in a single salt horizon about 800 meters deep. This single level can accommodate all low level and high level waste generated in the United States through the year 2010. A major constraint on the RWDPP design is the ERDA requirement that all waste be ''readily'' retrievable during the duration of pilot plant operation

Environmental effects of thermal power plants

International Nuclear Information System (INIS)

Gerlitzky, M.; Friedrich, R.; Unger, H.

1986-02-01

Reviewing critically the present literature, the effects of thermal power plants on the environment are studied. At first, the loads of the different power plant types are compiled. With regard to the effects of emission reduction proceedings the pollutant emissions are quantified. The second chapter shows the effects on the ecological factors, which could be caused by the most important emission components of thermal power plants. Where it is possible, relations between immissions respectively depositions and their effects on climate, man, flora, fauna and materials will be given. This shows that many effects depend strongly on the local landscape, climate and use of natural resources. Therefore, it appears efficient to ascertain different load limits. The last chapter gives a suggestion for an ecological compatibility test (ECT) of thermal power plants. In modular form the ECT deals with the emission fields, waste heat, pollution burden of air and water, noise, loss of area and aesthetical aspects. Limits depending on local conditions and use of area will be discussed. (orig.) [de

Liquid radioactive waste processing improvement of PWR nuclear power plants

International Nuclear Information System (INIS)

Nery, Renata Wolter dos Reis; Martinez, Aquilino Senra; Monteiro, Jose Luiz Fontes

2005-01-01

The study evaluate an inorganic ion exchange to process the low level liquid radwaste of PWR nuclear plants, so that the level of the radioactivity in the effluents and the solid waste produced during the treatment of these liquid radwaste can be reduced. The work compares two types of ion exchange materials, a strong acid cation exchange resin, that is the material typically used to remove radionuclides from PWR nuclear plants wastes, and a mordenite zeolite. These exchange material were used to remove cesium from a synthetic effluent containing only this ion and another effluent containing cesium and cobalt. The breakthrough curves of the zeolite and resin using a fix bed reactor were compared. The results demonstrated that the zeolite is more efficient than the resin in removing cesium from a solution containing cesium and cobalt. The results also showed that a bed combining zeolite and resin can process more volume of an effluent containing cesium and cobalt than a bed resin alone. (author)

The case for wood-fuelled heating

International Nuclear Information System (INIS)

Bent, Ewan

2001-01-01

This article looks at the wood heating industry in the UK and examines the heat market and the growth potential in the domestic, public, agricultural and commercial sectors. The current status of wood-fueled heating technology is considered, along with log and chip boilers, and the use of pellet fuel. The economics of wood-fuelled heating, the higher level of utilisation of wood-fuelled heating by utilities in northern European countries compared with the UK, and the barriers to the exploitation of wood fuelled heating are examined

Performance analysis of different organic Rankine cycle configurations on board liquefied natural gas-fuelled vessels

DEFF Research Database (Denmark)

Baldasso, Enrico; Andreasen, Jesper Graa; Meroni, Andrea

2017-01-01

Gas-fuelled shipping is expected to increase significantly in the coming years. Similarly, much effort is devoted to the study of waste heat recovery systems to be implemented on board ships. In this context, the organic Rankine cycle (ORC) technology is considered one of the most promising...

Integrated biomass gasification combined cycle distributed generation plant with reciprocating gas engine and ORC

International Nuclear Information System (INIS)

Kalina, Jacek

2011-01-01

The paper theoretically investigates the performance of a distributed generation plant made up of gasifier, Internal Combustion Engine (ICE) and Organic Rankine Cycle (ORC) machine as a bottoming unit. The system can be used for maximization of electricity production from biomass in the case where there is no heat demand for cogeneration plant. To analyze the performance of the gasifier a model based on the thermodynamic equilibrium approach is used. Performance of the gas engine is estimated on the basis of the analysis of its theoretical thermodynamic cycle. Three different setups of the plant are being examined. In the first one the ORC module is driven only by the heat recovered from engine exhaust gas and cooling water. Waste heat from a gasifier is used for gasification air preheating. In the second configuration a thermal oil circuit is applied. The oil transfers heat from engine and raw gas cooler into the ORC. In the third configuration it is proposed to apply a double cascade arrangement of the ORC unit with a two-stage low temperature evaporation of working fluid. This novel approach allows utilization of the total waste heat from the low temperature engine cooling circuit. Two gas engines of different characteristics are taken into account. The results obtained were compared in terms of electric energy generation efficiency of the system. The lowest obtained value of the efficiency was 23.6% while the highest one was 28.3%. These are very favorable values in comparison with other existing small and medium scale biomass-fuelled power generation plants. - Highlights: →The study presents performance analysis of a biomass-fuelled local power plant. →Downdraft wood gasifier, gas engine and ORC module are modelled theoretically. →Method for estimation of the producer gas fired engine performance is proposed. →Two gas engines of different characteristics are taken into account. →Different arrangements of the bottoming ORC cycle ere examined.

Deployment of Radioactive Waste Disposal Facility with the Introduction of Nuclear Power Plants in Kenya

Energy Technology Data Exchange (ETDEWEB)

Shadrack, Antoony; Kim, Changlak [KEPCO International Nuclear Graduate School, Uljin (Korea, Republic of)

2013-07-01

The nuclear power program will inevitably generate radioactive wastes including low-and intermediate radioactive waste and spent fuel. These wastes are hazardous to human health and the environment and therefore, a reliable radioactive waste disposal facility becomes a necessity. This paper describes Kenya's basic plans for the disposal of radioactive wastes expected from the nuclear program. This plan is important as an initial implementation of a national Low to intermediate level wastes storage facility in Kenya. In Kenya, radioactive waste is generated from the use of radioactive materials in medicine, industry, education and research and development. Future radioactive waste is expected to arise from nuclear reactors, oil exploration, radioisotope and fuel production, and research reactors as shown in table 1. The best strategy is to store the LILW and spent fuel temporarily within reactor sites pending construction of a centralized interim storage facility or final disposal facility. The best philosophy is to introduce both repository and nuclear power programs concurrently. Research and development on volume reduction technology and conceptual design of disposal facility of LILW should be pursued. Safe management of radioactive waste is a national responsibility for sustainable generation of nuclear power. The republic of Kenya is set to become the second African nuclear power generation country after South Africa.

Role of oxides and porosity on high temperature oxidation of liquid fuelled HVOF thermal sprayed Ni50Cr coatings

OpenAIRE

Song, B.; Bai, M.; Voisey, K.T.; Hussain, Tanvir

2017-01-01

High chromium content in Ni50Cr thermally sprayed coatings can generate a dense and protective scale at the surface of coating. Thus, the Ni50Cr coating is widely used in high temperature oxidation and corrosion applications. A commercially available gas atomized Ni50Cr powder was sprayed onto a power plant steel (ASME P92) using a liquid fuelled high velocity oxy-fuel (HVOF) thermal spray with three processing parameters in this study. Microstructure of as-sprayed coatings was examined using...

Experience in industrial operation of the plant for immobilizing radioactive wastes in thermosetting resins at the Ardennes Nuclear Power Station

International Nuclear Information System (INIS)

Haller, P.; Romestain, P.; Bruant, J.P.

1983-01-01

The French Atomic Energy Commission (CEA) has developed, at the Grenoble Centre for Nuclear Studies, a procedure for immobilizing low- and intermediate-level wastes in thermosetting resins of the polyester or epoxy types. To demonstrate feasibility on an industrial scale, a pilot plant has been set up at the effluent treatment station of the Ardennes Franco-Belgium Nuclear Power Station (SENA), which is a 305 MW(e) PWR type. Assembly work began in January 1979. After a period devoted to final adjustments and operation with inactive products, conditioning of active products began in January 1981. In the paper, the methods of conditioning the three types of waste (evaporation concentrates, ion exchange resins and filter cartridges) are described, experience of the start-up and operation of the plant is reported and the principal results of coating characterization tests are given. The results of tests on active and inactive products show that the characteristics of the materials obtained on an industrial scale match those of laboratory products and confirm their high quality with regard to mechanical behaviour, fire resistance, homogeneity and low-leachability. Industrial experience and economic comparisons show that the process of immobilizing waste from nuclear power stations in thermosetting resins offers an extremely interesting alternative to classical methods of conditioning. (author)

Nuclear power plant laundry drain treatment using membrane bio reactor

International Nuclear Information System (INIS)

Tsukamoto, Masaaki; Kohanawa, Osamu; Kinugasa, Atsushi; Ogawa, Naoki; Murogaki, Kenta

2012-01-01

In nuclear power plant, the radioactive effluent generated by washing the clothes worn in controlled area and the hand and shower water used at the controlled area are treated in laundry drain treatment system. Although various systems which treat such liquid waste preexist, the traditional treatment system has disadvantages such as high running cost and a large amount of secondary waste generation. To solve these matters, we have considered application of an activated sludge system, membrane bio reactor, which has been practically used in general industry. For nuclear power plant, the activated sludge system has been developed, tested in its adaptability and the adequacy has been proved. Some preexisting treatment systems have been replaced with this activated sludge system for the first time in a domestic nuclear power plant, and the renewal system is now in operation. The result is reported. (author)

Economic feasibility constraints for renewable energy source power production

International Nuclear Information System (INIS)

Biondi, L.

1992-01-01

Suitable analysis criteria for use in economic feasibility studies of renewable energy source power plants are examined for various plant types, e.g., pumped storage hydroelectric, geothermal, wind, solar, refuse-fuelled, etc. The paper focusses on the impacts, on operating cost and rate structure, of the necessity, depending on demand characteristics, to integrate renewable energy source power production with conventional power production in order to effectively and economically meet peak power demand. The influence of commercialization and marketing trends on renewable energy source power plant economic feasibility are also taken into consideration

Coal-fuelled systems for peaking power with 100% CO2 capture through integration of solid oxide fuel cells with compressed air energy storage

Science.gov (United States)

Nease, Jake; Adams, Thomas A.

2014-04-01

In this study, a coal-fuelled integrated solid oxide fuel cell (SOFC) and compressed air energy storage (CAES) system in a load-following power production scenario is discussed. Sixteen SOFC-based plants with optional carbon capture and sequestration (CCS) and syngas shifting steps are simulated and compared to a state-of-the-art supercritical pulverised coal (SCPC) plant. Simulations are performed using a combination of MATLAB and Aspen Plus v7.3. It was found that adding CAES to a SOFC-based plant can provide load-following capabilities with relatively small effects on efficiencies (1-2% HHV depending on the system configuration) and levelized costs of electricity (∼0.35 ¢ kW-1 h-1). The load-following capabilities, as measured by least-squares metrics, show that this system may utilize coal and achieve excellent load-tracking that is not adversely affected by the inclusion of CCS. Adding CCS to the SOFC/CAES system reduces measurable direct CO2 emission to zero. A seasonal partial plant shutdown schedule is found to reduce fuel consumption by 9.5% while allowing for cleaning and maintenance windows for the SOFC stacks without significantly affecting the performance of the system (∼1% HHV reduction in efficiency). The SOFC-based systems with CCS are found to become economically attractive relative to SCPC above carbon taxes of 22 ton-1.

Modern biofuel-fired power plants in power and heat production

International Nuclear Information System (INIS)

Tuominen, J.

1993-01-01

This article gives a survey of the gasification techniques, power plant technology and boiler solutions for small power plants using biofuels. Also some experiences from commercial projects and targets of development work are presented. At present, fluidized bed combustion is by far the most important combustion technique for biomass fuels in small power plants. Compared with grate combustion, fluidized bed combustion is a distinctly more economical combustion method, and so the thermic dimensioning of a steam boiler is easier. Besides, a wider range of fuels can be used in fluidized bed combustion. Fluidized bed combustion is an excellent combustion technique for biofuels. Plenty of experience has been gained in the combustion of peat and industrial waste wood, as far as both bubbling fluidized bed combustion (BFBC) and circulating fluidized bed combustion (CFBC) are concerned. Both of the fluidized bed techniques are suitable for the combustion of biomasses

Hanford Waste Vitrification Plant Dangerous Waste Permit Application

International Nuclear Information System (INIS)

1991-10-01

The Hanford Facility currently stores mixed waste, resulting from various processing operations, in underground storage tanks. The Hanford Waste Vitrification Plant will be constructed and operated to process the high-activity fraction of mixed waste stored in these underground tanks. The Hanford Waste Vitrification Plant will solidify pretreated tank waste into a glass product that will be packaged for disposal in a national repository. This Vitrification Plant Dangerous Waste Permit Application, Revision 2, consists of both a Part A and a Part B permit application. An explanation of the Part A revisions, including Revision 4 submitted with this application, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987)

Influence of in-plant air pollution control measures on power plant and system operation

International Nuclear Information System (INIS)

Kurten, H.

1990-01-01

The burning of fossil fuels causes the emission of air pollutants which have harmful environmental impact. Consequently many nations have in the last few years established regulations for air pollution control and have initiated the development and deployment of air pollution control systems in power plants. The paper describes the methods used for reducing particulate, SO 2 and NO x emissions, their application as backfit systems and in new plants, the power plant capacity equipped with such systems in the Federal Republic of Germany and abroad and the additional investment and operating costs incurred. It is to be anticipated that advanced power plant designs will produce lower pollutant emissions and less waste at enhanced efficiency levels. A comparison with power generation in nuclear power plants completes the first part of the paper. This paper covers the impact of the above-mentioned air pollution control measures on unit commitment in daily operation

Thermonuclear power plants and the environment

International Nuclear Information System (INIS)

Becka, J.

1978-01-01

Environmental safety and protection from the effects of the thermonuclear power plants are discussed. Factors are assessed which should be considered in the choice of fuel and breeding material of a thermonuclear reactor, the problems of structural material activation and the overall reactor concepts. Main specifications are given of the US thermonuclear power plant projects with D-T reaction based reactors. The overall amounts of tritium in the reactor cycles are shown. The potential biological risk is evaluated for the different materials considered for the UWMAK-1 project. Discussed are possible pathways of activity release in normal plant operation, non-radioactive aspects, such as waste heat, the magnetic field effect on personnel and population, etc., as well as possible environmental impacts in case of accidents. (B.S.)

Wte Power Plant Operation on the Energy Market Under the Influence of Legislation Changes

DEFF Research Database (Denmark)

Tomić, T.; Dominkovic, Dominik Franjo; Pfeifer, A.

2016-01-01

In this paper, the feasibility of combined heat and power waste-to-energy plant is investigated in theconditions of implementation of the new legal framework for waste disposal and management aswell as new power market conditions. As waste management is a core issue of sustainabledevelopment of r...

Method and means for heating buildings in a district heating system with waste heat from a thermal power plant

International Nuclear Information System (INIS)

Margen, P.H.E.

1975-01-01

The waste heat from a thermal power plant is transported through a municipal heating network to a plurality of buildings to be heated. The quantity of heat thus supplied to the buildings is higher than that required for the heating of the buildings. The excess heat is released from the buildings to the atmosphere in the form of hot air

Economic justification of building a power plant on gas from the city dump in Skopje (Macedonia)

International Nuclear Information System (INIS)

Sihamarn, K.; Popovska, Sanja

1995-01-01

Municipal waste treatment is a big problem in almost all urban environments in the world. Its combustion, after previous material sorting and separation for which recycling is possible, is considered the best method. Unfortunately, this method is very expensive and it can be used only in developed countries. Methane production from the municipal waste and its further use in the electric power production is consider a more appropriate method for developing countries. In the Republic of Macedonia the municipal waste problem is foremost in Skopje, where the cumulative quantities of municipal waste enable the production of c-ca 2 million m3 methane annually, sufficing to propel of a thermal power plant capacitating 11 MW. Considering all possible risks of non systematic and incomplete waste retrieval, the estimate is that under the current conditions, the 5,5 MW need of the thermal power plant can completely be covered. According to the data processed from the 5,5 MW Greenmaunt power plant in New Zealand which is being exploited for the last 5 years, the attempt of a evaluating the economic justification of setting up an equivalent power plant in Skopje is currently underway. 2 tabs

Nuclear power plant emergency preparedness

International Nuclear Information System (INIS)

2005-01-01

The guide sets forth detailed requirements on how the licensee of a nuclear power plant shall plan, implement and maintain emergency response arrangements. The guide is also applied to nuclear material and nuclear waste transport in situations referred to in guide YVL 6.5. Requirements on physical protection are presented in a separate guide of Finnish Radiation and Nuclear Safety Authority (STUK)

EPRI waste processing projects

International Nuclear Information System (INIS)

Shaw, R.A.

1987-01-01

The Electric Power Research Institute (EPRI) manages research for its sponsoring electric utilities in the United States. Research in the area of low level radioactive waste (LLRW) from light water reactors focuses primarily on waste processing within the nuclear power plants, monitoring of the waste packages, and assessments of disposal technologies. Accompanying these areas and complimentary to them is the determination and evaluation of the sources of nuclear power plants radioactive waste. This paper focuses on source characterization of nuclear power plant waste, LLRW processing within nuclear power plants, and the monitoring of these wastes. EPRI's work in waste disposal technology is described in another paper in this proceeding by the same author. 1 reference, 5 figures

Radioactive waste management at EDF plants: General overview and perspectives

International Nuclear Information System (INIS)

Debes, M.; Bordier, M.

2001-01-01

During the last fifteen years a significant decrease in solid radioactive waste generated by nuclear power plants of Electricite de France (EDF) has taken place. Technology used by EDF is described, with emphasis on innovative technologies. Experience and lessons learned are described showing how EDF has responded to meet increasingly stringent regulations for radioactive waste management. (author)

Tentative to use wastes from thermal power plants for construction building materials

Science.gov (United States)

Bui, Quoc-Bao; Phan, To-Anh-Vu; Tran, Minh-Tung; Le, Duc-Hien

2018-04-01

Thermal power plants (TPP) generates wastes (bottom and fly ashes) which become a serious environmental problem in Vietnam. Indeed, although in several countries fly ash can be used for cement industry, fly ash from actual TPP in Vietnam does not have enough good quality for cement production, because the fly ash treatment phase has not yet included in the generations of existing Vietnamese TPP. That is why bottom ash and fly ash purely become wastes and their evacuation is an urgent demand of the society. This paper presents an investigation using fly and bottom ashes in the manufacturing of construction materials. The main aims of this study is to reduce environmental impacts of fly and bottom ashes, and to test another non-conventional binder to replace cement in the manufacture of unburnt bricks. Several proportions of fly ash, bottom ash, cement, gravel, sand and water were tested to manufacture concretes. Then, geopolymer was prepared from the fly ash and an activator. Specimens were tested in uniaxial compressions. Results showed that the cement concrete tested had the compressive strengths which could be used for low rise constructions and the material using geopolymer could be used for non-load-bearing materials (unburnt bricks).

EFFICIENCY AND COST MODELLING OF THERMAL POWER PLANTS

Directory of Open Access Journals (Sweden)

Péter Bihari

2010-01-01

Full Text Available The proper characterization of energy suppliers is one of the most important components in the modelling of the supply/demand relations of the electricity market. Power generation capacity i. e. power plants constitute the supply side of the relation in the electricity market. The supply of power stations develops as the power stations attempt to achieve the greatest profit possible with the given prices and other limitations. The cost of operation and the cost of load increment are thus the most important characteristics of their behaviour on the market. In most electricity market models, however, it is not taken into account that the efficiency of a power station also depends on the level of the load, on the type and age of the power plant, and on environmental considerations. The trade in electricity on the free market cannot rely on models where these essential parameters are omitted. Such an incomplete model could lead to a situation where a particular power station would be run either only at its full capacity or else be entirely deactivated depending on the prices prevailing on the free market. The reality is rather that the marginal cost of power generation might also be described by a function using the efficiency function. The derived marginal cost function gives the supply curve of the power station. The load level dependent efficiency function can be used not only for market modelling, but also for determining the pollutant and CO2 emissions of the power station, as well as shedding light on the conditions for successfully entering the market. Based on the measurement data our paper presents mathematical models that might be used for the determination of the load dependent efficiency functions of coal, oil, or gas fuelled power stations (steam turbine, gas turbine, combined cycle and IC engine based combined heat and power stations. These efficiency functions could also contribute to modelling market conditions and determining the

Standard criteria for disposal of liquid radioactive wastes from nuclear power plants into surface waters (river systems)

International Nuclear Information System (INIS)

Pisarev, V.V.; Tsybizov, I.S.

1976-01-01

Radioactive products discharge into natural water streams results in the necessity to regulate nuclear power plant discharges to ensure radiation safety (RS) for population using a river and surrounding river territory. To ensure RS it is necessary to set scientific-founded standards of permissible discharge level of liquid radioactive wastes (LRW) from nuclear power plant assuring observance of hygienic requirements for surface water puring. Volume of permissible LRW discharge into river systems must be set both with provision for concrete physical-geographycal conditions, specficity of utilizing the river and river valley and social-economical peculiarities of crtical population groups. The value of permissible LRW discharge into river systems is determined by three criterion groups: radiological, ecological and hydrological ones. By means of radiological group the internal and external irradiation doses for the whole body and its separate organs are set and RS of population is determined. Ecological criteria include a number of parameters (coefficients of accumulation, distribution and transition) determining quantitative ratios between radioactive element contents in water and separate links of biological chains: soil/water, fish/water, vegetables/water and others. Hydrological criteria determine the degree of waste dilution in rivers, control radioactive contamination of flood-lands areas and in common with ecological criteria determine radionuclide contents in soil and food products. A method of determining average annual values of LRW dilution in river waters is presented [ru

Some issues related to the development of nuclear power plant in Indonesia

International Nuclear Information System (INIS)

Panggabean, L.M.

1987-01-01

Indonesia being a member of ASEAN belongs to the group of developing country. If Indonesia decides to embark on the establishment of nuclear power plan then the country will have no choice but to discuss the following issues: Safe operation of the plant and management of the nuclear waste. Safe operation of the power plant is important not only from the point of view of hazards to human being, or economic loss, or even death, but equally important it is also from the psychological point of view in that not to loose the society's confidence in the overall nuclear power plant programme in the future. The issue of safe operation involves both a safely designed system as well as skilled personnels to execute a well designed operation procedure. The issue of nuclear safety is getting more and more attention lately for various, some due to a deep concern about the quality of the inherent safety of the nuclear power plant to be built, others may just use their emotion to ask question like ''what its''. The issue of nuclear waste is as fundamental as the plant safety. Common people make very little difference between an atomic bomb and waste from a nuclear power plant. Another issue is one of transfer of technology which needs to be tied up with the overall industrialization process, meaning that embarking on nuclear power programme needs to contribute to local industrial activities, at least for some parts or components which can be manufactured locally. (author)

The study on the recycle condition for existence of the decommissioning waste in the nuclear power station

International Nuclear Information System (INIS)

Hironaga, Michihiko; Ozaki, Sachio; Hirai, Mitsuyuki; Sakamoto, Hiroyuki; Usui, Tatsuo; Simizu, Yasuo; Ogane, Daisuke

2000-01-01

To establish the technique of the recycle for concrete waste, this paper describes the recycle condition for existence of the decommissioning concrete waste in the nuclear power plant and considers the durability of cask yard concrete constructed at about twenty years ago. The authors examine the recycle system of concrete in the power plant. (author)

The Community's research and development programme on decommissioning of nuclear power plants

International Nuclear Information System (INIS)

1982-01-01

The programme, adopted by the Council of the European Communities, seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontaminations for decommissioning purposes; dismantling techniques; treatment of specific waste materials (steel, concrete and graphite); large transport containers for radioactive waste arising from decommissioning of nuclear power plants in the Community; and influence of nuclear power plant design features on decommissioning

Incinerators for radioactive wastes in Japanese nuclear power stations

International Nuclear Information System (INIS)

Karita, Yoichi

1983-01-01

As the measures of treatment and disposal of radioactive wastes in nuclear power stations, the development of the techniques to decrease wastes, to reduce the volume of wastes, to treat wastes by solidification and to dispose wastes has been advanced energetically. In particular, efforts have been exerted on the volume reduction treatment from the viewpoint of the improvement of storage efficiency and the reduction of transport and disposal costs. Incineration as one of the volume reduction techniques has been regarded as the most effective method with large reduction ratio, but it was not included in waste treatment system. NGK Insulators Ltd. developed NGK type miscellaneous solid incinerators, and seven incinerators were installed in nuclear power stations. These incinerators have been operated smoothly, and the construction is in progress in six more plants. The necessity of incinerators in nuclear power stations and the problems in their adoption, the circumstance of the development of NGK type miscellaneous solid incinerators, the outline of the incinerator of Karlsruhe nuclear power station and the problems, the contents of the technical development in NGK, the outline of NGK type incinerators and the features, the outline of the pretreatment system, incinerator system, exhaust gas treatment system, ash taking out system and accessory equipment, the operational results and the performance are described. (Kako, I.)

Power from municipal solid waste

International Nuclear Information System (INIS)

Fidalgo dos Reis, A.

1993-01-01

This paper evaluates the energy production potential from urban wastes for several cities in Latin America. Technologies available for transforming wastes into energy are reviewed and the high efficiency and low pollution levels obtained are discussed based on some very successful examples in the developed countries. Several criteria to help plan a plant and choose its location and appropriate size are presented under the framework of environmental and energy constraints. Economic and financial feasibility, barriers to the introduction of new technologies and their transfer to developing countries, and political obstacles created by the lobby that is taking advantage of the present situation are presented. Management of such plants requires that a social communication program be well designed to touch and inform the public about the importance of the plants; it should also emphasize the gains to society. Marketing strategies are presented that will highlight life quality improvement and preservation of the environment to decision makers and the public. A case study for the city of Sao Paulo, Brazil, will be discussed in detail, showing how several levels of decision makers are involved in the preparation of the feasibility study and in raising financial resources both inside and outside the country. The study is for a large plant with a capacity of 1,800 ton/day and the generation of 27 MW of electric power

Waste treatment plant

International Nuclear Information System (INIS)

Adesanmi, C.A

2009-01-01

Waste Treatment Plant (WTP) is designed to provide appropriate systems for processing, immobilization and storage of low and medium radioactive waste arising from the operation of the research facilities of the Nuclear Technology Centre (NTC). It will serve as central collection station processing active waste generated through application of radionuclide in science, medicine and industry in the country. WTP building and structures will house the main waste processing systems and supporting facilities. All facilities will be interconnected. The interim storage building for processed waste drums will be located separately nearby. The separate interim storage building is located near the waste treatment building. Considering the low radiation level of the waste, storage building is large with no solid partitioning walls and with no services or extra facilities other than lighting and smoke alarm sensors. The building will be designed such that drums(200-1)are stacked 3 units high using handling by fork lift truck. To prevent radiation exposure to on-site personnel, the interim storage building will be erected apart from waste treatment plant or other buildings. The interim storage building will also be ready for buffer storage of unconditioned waste waiting for processing or decay and for storage material from the WTP

Decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Friske, A.; Thiele, D.

1988-01-01

The IAEA classification of decommissioning stages is outlined. The international development hitherto observed in decommissioning of nuclear reactors and nuclear power stations is presented. The dismantling, cutting and decontamination methods used in the decommissioning process are mentioned. The radioactive wastes from decommissioning are characterized, the state of the art of their treatment and disposal is given. The radiation burdens and the decommissioning cost in a decommissioning process are estimated. Finally, some evaluation of the trends in the decommissioning process of nuclear power plants is given. 54 refs. (author)

Comparison of balance of tritium activity in waste water from nuclear power plants and at selected monitoring sites in the Vltava River, Elbe River and Jihlava (Dyje) River catchments in the Czech Republic.

Science.gov (United States)

Hanslík, Eduard; Marešová, Diana; Juranová, Eva; Sedlářová, Barbora

2017-12-01

During the routine operation, nuclear power plants discharge waste water containing a certain amount of radioactivity, whose main component is the artificial radionuclide tritium. The amounts of tritium released into the environment are kept within the legal requirements, which minimize the noxious effects of radioactivity, but the activity concentration is well measurable in surface water of the recipient. This study compares amount of tritium activity in waste water from nuclear power plants and the tritium activity detected at selected relevant sites of surface water quality monitoring. The situation is assessed in the catchment of the Vltava and Elbe Rivers, affected by the Temelín Nuclear Power Plant as well as in the Jihlava River catchment (the Danube River catchment respectively), where the waste water of the Dukovany Nuclear Power Plant is discharged. The results show a good agreement of the amount of released tritium stated by the power plant operator and the tritium amount detected in the surface water and highlighted the importance of a robust independent monitoring of tritium discharged from a nuclear power plant which could be carried out by water management authorities. The outputs of independent monitoring allow validating the values reported by a polluter and expand opportunities of using tritium as e.g. tracer. Copyright © 2017 Elsevier Ltd. All rights reserved.

Hydrogen treatment system in the Genkai nuclear power plant No. 2

International Nuclear Information System (INIS)

Nakamura, Masayuki; Kodama, Hideo; Murashima, Masayasu

1977-01-01

The new hydrogen treatment system which injects hydrogen into the volume control tank for purging the mixed waste gas of Kr, Xe, etc. is adopted in the Genkai nuclear power plant No. 2. The system is composed of mainly the waste gas pretreatment equipment, a palladium alloy membrane type hydrogen separator, a hydrogen compressor, and a waste gas decay tank. The outline of the primary cooling system and the chemical volume control system of PWR, the hydrogen treatment system, and the gaseous waste disposal system of original and new types for the Genkai nuclear power plants No. 1 and 2 are explained in this paper. This newly added hydrogen treatment system will be able to reduce the rare gas concentration rate in the primary coolant to about 1/2 and 1/5 for Kr 85 and Xe 133 , respectively. (auth.)

Survey of consolidation for gas turbine re-powering combined WPP (waste power plant) project; Gas turbine repowering haikibutsu fukugo hatsuden system

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

This report describes the survey of gas turbine re-powering combined WPP (or super WPP), which was commercialized by Gunma Prefecture for the first time as an electric power wholesaler in Japan. An outline of the survey is introduced. The system optimization for the commercialization of WPP was studied by considering waste as un-utilized energy. A successful condition and preparation method of the commercialization of a public power plant was also studied, which is a combination of the garbage collection business of a local government and an electric power generation business of a municipal company. For the introduction of the aforementioned system, the problems and supporting methods were studied by making allowance for the profitability of the WPP introduction, because they also need to deliberate it from the economical point of view as electric power companies. Based on the results of foregoing items, commercialization plans, problems encountered from the construction phase through the maintenance and service phase, and the supporting method were arranged. 30 figs., 18 tabs.

Low-level radioactive waste processing at nuclear power plants

International Nuclear Information System (INIS)

1992-12-01

The Solid Radwaste Processing Source Book is presented as a supplement to the Liquid Radwaste Source Book released in 1990 and updated in 1991. The publication is the result of an industry-wide survey, and is intended as a resource for technical and managerial decisions involving of the processing of solid radioactive waste including ''wet'' and ''dry'' active waste as found at both Pressurized and Boiling Water Reactor sites. In addition to information on processes, vendors, volumes, and in-plant management activities, technology under consideration for future use and computer applications are listed. Together with key personnel and contact information contained in the Liquid Source Books, the collected data will be of great use when seeking specific, unbiased experience on which to base decisions related to so processing, disposal policy, or potential economic and regulatory impact

Improved liquid waste processing system of PWR plant

International Nuclear Information System (INIS)

Suehiro, Kazuyasu

1977-01-01

Mitsubishi Heavy Industries, Ltd. has engaged in the improvement and enhancement of waste-processing facilities for PWR power stations, and recently established the improved processing system. With this system, it becomes possible to contain radioactive waste gas semi-permanently within plants and to recycle waste liquid after the treatment, thus to make the release of radioactive wastes practically zero. The improved system has the following features, namely the recycling system is adopted, drain is separated and each separated drain is treated by specialized process, the reboiler type evaporator and the reverse osmosis equipment are used, and the leakless construction is adopted for the equipments. The radioactive liquid wastes in PWR power stations are classified into coolant drain, drain from general equipments, chemical drain and cleaning water. The outline of the improved processing system and the newly developed equipments such as the reboiler type evaporator and the reverse osmosis equipment are explained. With the evaporator, the concentration rate of waste liquid can be raised to about three times, and foaming waste can be treated efficiently. The decontamination performance is excellent. The reverse osmosis treatment is stable and reliable method, and is useful for the treatment of cleaning water. It is also effective for concentrating treatment. The unmanned automatic operation is possible. (Kako, I.)

Current situation regarding the co-combustion of waste materials in power plants; Aktuelle Situation der Mitverbrennung von Abfallstoffen in Kraftwerken

Energy Technology Data Exchange (ETDEWEB)

Schirmer, U.; Krueger, H.; Puch, K.H. [VGB Technische Vereinigung der Grosskraftwerksbetreiber e.V., Essen (Germany)

1998-09-01

In view of the wholly insufficient capacity, relative to current arisings, of waste incineration plants, residue processing plants and plants for the utilisation of other combustible materials we are inevitably faced with the question whether power plant furnaces might not be suited for the thermal treatment and utilisation of wastes and residues. This possibility has been studied by many VGB member companies and seriously investigated for its practicability in several cases. The investigations were premised on the following fundamental positions. The VGB members are prepared to contribute to the solution of the above problems as long as this is possible without detriment to their duties as energy suppliers. They can only assume this responsibility if the requirements of the licensing laws are observed. This concerns the quality and arising quantities of wastes to be taken in, emissions, and the disposal of combustion residues. Power plants typically make more or less complete use of their own process residues, a feature which as far as possible should not be impaired by the co-combustion process. The technical problems posed by the co-combustion of suitable residues and wastes are usually solvable. Co-combustion offers an alternative and a supplement to dedicated waste utilisation plants or plants for the utilisation of suitable residues. Beyond this some companies are interested in profiting from the fees that will be due to them for utilising wastes. From 1990 to 1992 a VGB working group studied the option of co-combustion on the basis of the above premises. The material elaborated by the group now in turn serves as a basis for the following deliberations. [Deutsch] Da die Kapazitaet der Abfallverbrennungsanlagen, der Anlagen zur Reststoffverwertung und der Anlagen zur Nutzung sonstiger brennbaren Stoffe fuer das vorhandene Angebot bei weitem nicht ausreicht, ergibt sich die Frage der Eignung von Kraftwerksfeuerungen zur thermischen Behandlung und Verwertung von

Innovative Nuclear Power Plant Building Arrangement in Consideration of Decommissioning

OpenAIRE

Won-Jun Choi; Myung-Sub Roh; Chang-Lak Kim

2017-01-01

A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA) strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research...

Experiences in the treatment of radioactive wastes in nuclear power plants in the Federal Republic of Germany

International Nuclear Information System (INIS)

Ambros, R.; Rittscher, D.

1983-01-01

The liquid, gaseous and solid radioactive wastes arising from the operation of nuclear power plants (NPP) have - if they cannot be reused - to be disposed of according to rules set up by the competent authorities. In this paper the treatment of wastes from NPP is described as it is carried out today due to the actual lack of a waste repository in the FRG. As most NPP have only an interim storage capacity for 1 year, measures for a further reduction of waste arisings, for volume reduction of the waste and for extension of the storage capacity have become necessary. The reduction of the waste arisings to the possible minimum is being achieved by administrative measures. A volume reduction of the waste is achieved by improvement of already existing methods and by development of new methods. Mixed solid wastes are reduced in volume by baling at high pressure. Burnable wastes can be reduced in volume by incineration. Liquid radioactive concentrates are reduced in volume by water separation, evaporation or drying. The volume reduction factors achieved are large as compared to the formerly applied cementation. The products arising are put into cast-iron containers which following the actual knowledge, should meet the requirements for final disposal with respect to the pressure stability, corrosion resistance and leach resistance. Due to the high density of the container material and the great wall thickness the specific activity of the waste can be increased without exceeding the dose rate limits at the outside of the containers. (author)

Can global warming save nuclear power?

International Nuclear Information System (INIS)

Pearce, D.

1994-01-01

Nuclear powered electricity generation in the United Kingdom has an uncertain future. The relative costs of generating electricity by nuclear fission compared to other means and the need for a desirable mixture or ''portfolio'' of energy sources in the electricity industry are identified as the key to this uncertainty. The author argues that Government commitments to reducing Carbon Monoxide (CO) emissions, and hence global warming, may strengthen arguments in favour of a firm commitment to nuclear power, as even modern fossil-fuelled power plants emit nearly 90 times as much CO as nuclear plants. (UK)

Innovative nuclear power plant building arragement in consideration of decommissioning

International Nuclear Information System (INIS)

Choi, Won Jun; Roh, Myung Sub; Kim, Chang Lak

2017-01-01

A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA) strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research paper, the concept and the implementation method of the INBA strategy will be described. Two primary benefits will be further described: (1) early site restoration; and (2) radioactive waste reduction. Several other potential benefits will also be identified. For the estimation of economic benefit, the INBA strategy, with two primary benefits, will be compared with the immediate dismantling strategy. The effect of a short life cycle nuclear power plant in combination with the INBA strategy will be reviewed. Finally, some of the major impediments to the realization of this strategy will be discussed

Innovative nuclear power plant building arragement in consideration of decommissioning

Energy Technology Data Exchange (ETDEWEB)

Choi, Won Jun; Roh, Myung Sub; Kim, Chang Lak [Dept. of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2017-04-15

A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA) strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research paper, the concept and the implementation method of the INBA strategy will be described. Two primary benefits will be further described: (1) early site restoration; and (2) radioactive waste reduction. Several other potential benefits will also be identified. For the estimation of economic benefit, the INBA strategy, with two primary benefits, will be compared with the immediate dismantling strategy. The effect of a short life cycle nuclear power plant in combination with the INBA strategy will be reviewed. Finally, some of the major impediments to the realization of this strategy will be discussed.

Innovative Nuclear Power Plant Building Arrangement in Consideration of Decommissioning