WorldWideScience

Sample records for waste derived fuels

  1. Designing the microturbine engine for waste-derived fuels.

    Science.gov (United States)

    Seljak, Tine; Katrašnik, Tomaž

    2016-01-01

    Presented paper deals with adaptation procedure of a microturbine (MGT) for exploitation of refuse derived fuels (RDF). RDF often possess significantly different properties than conventional fuels and usually require at least some adaptations of internal combustion systems to obtain full functionality. With the methodology, developed in the paper it is possible to evaluate the extent of required adaptations by performing a thorough analysis of fuel combustion properties in a dedicated experimental rig suitable for testing of wide-variety of waste and biomass derived fuels. In the first part key turbine components are analyzed followed by cause and effect analysis of interaction between different fuel properties and design parameters of the components. The data are then used to build a dedicated test system where two fuels with diametric physical and chemical properties are tested - liquefied biomass waste (LW) and waste tire pyrolysis oil (TPO). The analysis suggests that exploitation of LW requires higher complexity of target MGT system as stable combustion can be achieved only with regenerative thermodynamic cycle, high fuel preheat temperatures and optimized fuel injection nozzle. Contrary, TPO requires less complex MGT design and sufficient operational stability is achieved already with simple cycle MGT and conventional fuel system. The presented approach of testing can significantly reduce the extent and cost of required adaptations of commercial system as pre-selection procedure of suitable MGT is done in developed test system. The obtained data can at the same time serve as an input for fine-tuning the processes for RDF production. Copyright © 2015. Published by Elsevier Ltd.

  2. Diesel engine performance and emissions with fuels derived from waste tyres.

    Science.gov (United States)

    Verma, Puneet; Zare, Ali; Jafari, Mohammad; Bodisco, Timothy A; Rainey, Thomas; Ristovski, Zoran D; Brown, Richard J

    2018-02-06

    The disposal of waste rubber and scrap tyres is a significant issue globally; disposal into stockpiles and landfill poses a serious threat to the environment, in addition to creating ecological problems. Fuel production from tyre waste could form part of the solution to this global issue. Therefore, this paper studies the potential of fuels derived from waste tyres as alternatives to diesel. Production methods and the influence of reactor operating parameters (such as reactor temperature and catalyst type) on oil yield are outlined. These have a major effect on the performance and emission characteristics of diesel engines when using tyre derived fuels. In general, tyre derived fuels increase the brake specific fuel consumption and decrease the brake thermal efficiency. The majority of studies indicate that NOx emissions increase with waste tyre derived fuels; however, a few studies have reported the opposite trend. A similar increasing trend has been observed for CO and CO 2 emissions. Although most studies reported an increase in HC emission owing to lower cetane number and higher density, some studies have reported reduced HC emissions. It has been found that the higher aromatic content in such fuels can lead to increased particulate matter emissions.

  3. Energy recovery from municipal solid waste by refuse derived fuel production in Malaysia

    International Nuclear Information System (INIS)

    Sanaz Saheri; Noorezlin Ahmad Baseri; Masoud Aghajani Mir; Malmasi Saeed

    2010-01-01

    Energy recovery from municipal solid waste (MSW) is so beneficial both for the energy and for the positive environmental implications. Mainly related to the saving of primary energy derived from fossil fuel. Malaysia as a fast growing population country has the average amount of municipal solid waste (MSW) generated around 0.5-0.8 kg/person/day and it has been increased to 1.7 kg/person/day in major cities. Regarding characterization exercise, the main parts of the Malaysian MSW were found to be food, paper and plastic, which made up almost 80 % of the waste by weight. Furthermore, the average moisture content of the MSW was about 55 %, making incineration a challenging mission. In addition waste sectors in Malaysia contributes to 1.3 million ton of CH 4 compare to total CH 4 emission which is 2.2 MT. In order to overcome waste problem considering other technical, environmental and economical methods seems to be necessarily. Resource recovery centers recovers the maximum proportion of recyclable and recoverable resources from the mixed municipal solid waste .The resource recovery process itself is one of the step-by-step segregation and elimination of all non-combustibles , and separation of the combustibles in the desired form of fuel for good combustion. Then, a further mechanical separation process converts combustible materials to refuse derived fuel (RDF) with moisture content between 20 and 30 % and an average calorific fuel value of about 3450 kcal/kg. So, the aim of this paper is taking into account resource recovery from waste using refuse derived fuel as a secondary resource with regarding advantages and disadvantages of this kind of energy production in Malaysia as a developing country. (author)

  4. Steam gasification of tyre waste, poplar, and refuse-derived fuel: A comparative analysis

    International Nuclear Information System (INIS)

    Galvagno, S.; Casciaro, G.; Casu, S.; Martino, M.; Mingazzini, C.; Russo, A.; Portofino, S.

    2009-01-01

    In the field of waste management, thermal disposal is a treatment option able to recover resources from 'end of life' products. Pyrolysis and gasification are emerging thermal treatments that work under less drastic conditions in comparison with classic direct combustion, providing for reduced gaseous emissions of heavy metals. Moreover, they allow better recovery efficiency since the process by-products can be used as fuels (gas, oils), for both conventional (classic engines and heaters) and high efficiency apparatus (gas turbines and fuel cells), or alternatively as chemical sources or as raw materials for other processes. This paper presents a comparative study of a steam gasification process applied to three different waste types (refuse-derived fuel, poplar wood and scrap tyres), with the aim of comparing the corresponding yields and product compositions and exploring the most valuable uses of the by-products

  5. Experimental investigations on a diesel engine operated with fuel blends derived from a mixture of Pakistani waste tyre oil and waste soybean oil biodiesel.

    Science.gov (United States)

    Qasim, Muhammad; Ansari, Tariq Mahmood; Hussain, Mazhar

    2017-10-18

    The waste tyre and waste cooking oils have a great potential to be used as alternative fuels for diesel engines. The aim of this study was to convert light fractions of pyrolysis oil derived from Pakistani waste vehicle tyres and waste soybean oil methyl esters into valuable fuel and to reduce waste disposal-associated environmental problems. In this study, the waste tyre pyrolysis liquid (light fraction) was collected from commercial tyre pyrolysis plant and biodiesel was prepared from waste soybean oil. The fuel blends (FMWO10, FMWO20, FMWO30, FMWO40 and FMWO50) were prepared from a 30:70 mixture of waste tyre pyrolysis liquid and waste soybean oil methyl esters with different proportions of mineral diesel. The mixture was named as the fuel mixture of waste oils (FMWO). FT-IR analysis of the fuel mixture was carried out using ALPHA FT-IR spectrometer. Experimental investigations on a diesel engine were carried out with various FMWO blends. It was observed that the engine fuel consumption was marginally increased and brake thermal efficiency was marginally decreased with FMWO fuel blends. FMWO10 has shown lowest NOx emissions among all the fuel blends tested. In addition, HC, CO and smoke emissions were noticeably decreased by 3.1-15.6%, 16.5-33.2%, and 1.8-4.5%, respectively, in comparison to diesel fuel, thereby qualifying the blends to be used as alternative fuel for diesel engines.

  6. Predicting the calorific value of refuse derived fuel from the characteristics of municipal solid waste

    International Nuclear Information System (INIS)

    Sivapalan Kathiravale; Muhd Noor Muhd Yunus; Mohamad Puad Abu; Mohamad Azman Che Mat Isa; Mohd Fairus Abdul Farid; Norasalwa Zakaria; Khaironie Mohd Takip; Rohyiza Ba'an

    2006-01-01

    The Imposing need to manage the municipal solid waste generated by society in a proper manner has urged municipalities to look into new management methods, which are not only environmentally friendly but also economically profitable. One such way is by converting this waste material into fuel. Currently, Kajang in the State of Selangor, Malaysia, generates about 700 tons of Municipal Solid Waste (MSW) a day. Due to rapid development, lack of land area for new landfill and the environmental impact of raw landfills, the local municipal council has collaborated with a local company in the management of this waste. The company has proposed to convert the MSW to Refuse Derived Fuel (RDF). In view of this, a pilot plant to convert MSW to RDF was erected by the company and begun operation in January 2002. This pilot plant has the capability of converting 15 tons of MSW to 5 tons of RDF. At the same time studies, have been carried out to assess the plant performance, the flue gas analysis, and also the MSW and RDF characteristic. This paper will highlight the findings of the MSW and RDF characterization work carried out over the past year. Sampling and analysis was carried in accordance with ASTM standards. Results of the waste analysis showed that the calorific value of the resulting RDF could be predicted from the physical characteristics as well as the moisture content. Regression analysis on the available data has been used to create equations relating the proximate composition and moisture content of the incoming municipal solid waste to the calorific value of the RDF

  7. Nitrogen oxides from combustion of nitrogen-containing polymers in waste-derived fuels

    International Nuclear Information System (INIS)

    Zevenhoven, R.; Kilpinen, P.; Hupa, M.; Elomaa, M.

    2000-01-01

    Usually, waste-derived fuels present nitrogen-containing fractions, which produce nitrogen oxides (NO) during combustion. This study was mainly concerned with poly amides (PA) (nylon), poly urethanes (PU), urea formaldehyde (UF) glue, sewage sludge and refuse-derived fuels (RDF). For control purposes, the authors chose a Polish sub-bituminous coal and a Finnish pine wood sample. An almost inverse trend between fuel nitrogen content and NO emissions was revealed through analysis of NO emissions at 850 Celsius, 1 bar, 7 per cent O 2 in N 2 . It was not possible to derive a clear correlation to the amount of ash generated by the samples. PU foam decomposed through a two-step process, as suggested by thermochromatography, and PA6-containing samples yielded epsilon-caprolactam as a major decomposition product. Important decomposition products from PU, PA6, PA6/PE, sewage sludge and UF glue samples were greenhouse gases as demonstrated by pyrolysis-gas chromatography/mass spectroscopy. The work was carried out at Abo Akademi University and University of Helsinki, Finland. 5 refs., 2 tabs., 3 figs

  8. The combustion characteristics of refuse derived fuels using coke/waste tire

    Energy Technology Data Exchange (ETDEWEB)

    Park, M.H. [Dep. of Mechanical Eng., Samcheok Nat' l Univ., Samcheok (Korea); Shin, D.Y. [Research Center for Advanced Mineral Aggregate Composite Products, Kangwon Nat' l Univ., Chuncheon (Korea)

    2005-07-01

    Today every nation faces serious problems of energy supply. Reasonable technologies to make use of coal (including coke) can not only help the mining-related economy which is showing a downward trend but also may fit in with the governmental energy policy. In this research, we aim to supply heating systems in factories, homes, and farms with a substitute fuel by developing coke/waste tire compound fuel with high efficiency for rational use of energy and for recycling of industrial products. A coke/waste boiler was used for this experiment, and different kinds of fuel were experimented including coke, waste tire, coke/waste A and coke/waste B. Four kinds of exhaust gas were also sampled by a gas analyzer, including CO, CO{sub 2}, NO and NO{sub 2} at different temperatures. (orig.)

  9. Characterization of char derived from various types of solid wastes from the standpoint of fuel recovery and pretreatment before landfilling

    International Nuclear Information System (INIS)

    Hwang, I.H.; Matsuto, T.; Tanaka, N.; Sasaki, Y.; Tanaami, K.

    2007-01-01

    Carbonization is a kind of pyrolysis process to produce char from organic materials under an inert atmosphere. In this work, chars derived from various solid wastes were characterized from the standpoint of fuel recovery and pretreatment of waste before landfilling. Sixteen kinds of municipal and industrial solid wastes such as residential combustible wastes, non-combustible wastes, bulky wastes, construction and demolition wastes, auto shredder residue, and sludges were carbonized at 500 deg. C for 1 h under nitrogen atmosphere. In order to evaluate the quality of char as fuel, proximate analysis and heating value were examined. The composition of raw waste had a significant influence on the quality of produced char. The higher the ratio of woody biomass in waste, the higher heating value of char produced. Moreover, an equation to estimate heating value of char was developed by using the weight fraction of fixed carbon and volatile matter in char. De-ashing and chlorine removal were performed to improve the quality of char. The pulverization and sieving method seems to be effective for separation of incombustibles such as metal rather than ash. Most char met a 0.5 wt% chlorine criterion for utilization as fuel in a shaft blast furnace after it was subjected to repeated water-washing. Carbonization could remove a considerable amount of organic matter from raw waste. In addition, the leaching of heavy metals such as chrome, cadmium, and lead appears to be significantly suppressed by carbonization regardless of the type of raw waste. From these results, carbonization could be considered as a pretreatment method for waste before landfilling, as well as for fuel recovery

  10. An integrated appraisal of energy recovery options in the United Kingdom using solid recovered fuel derived from municipal solid waste.

    Science.gov (United States)

    Garg, A; Smith, R; Hill, D; Longhurst, P J; Pollard, S J T; Simms, N J

    2009-08-01

    This paper reports an integrated appraisal of options for utilising solid recovered fuels (SRF) (derived from municipal solid waste, MSW) in energy intensive industries within the United Kingdom (UK). Four potential co-combustion scenarios have been identified following discussions with industry stakeholders. These scenarios have been evaluated using (a) an existing energy and mass flow framework model, (b) a semi-quantitative risk analysis, (c) an environmental assessment and (d) a financial assessment. A summary of results from these evaluations for the four different scenarios is presented. For the given ranges of assumptions; SRF co-combustion with coal in cement kilns was found to be the optimal scenario followed by co-combustion of SRF in coal-fired power plants. The biogenic fraction in SRF (ca. 70%) reduces greenhouse gas (GHG) emissions significantly ( approximately 2500 g CO(2) eqvt./kg DS SRF in co-fired cement kilns and approximately 1500 g CO(2) eqvt./kg DS SRF in co-fired power plants). Potential reductions in electricity or heat production occurred through using a lower calorific value (CV) fuel. This could be compensated for by savings in fuel costs (from SRF having a gate fee) and grants aimed at reducing GHG emission to encourage the use of fuels with high biomass fractions. Total revenues generated from coal-fired power plants appear to be the highest ( 95 pounds/t SRF) from the four scenarios. However overall, cement kilns appear to be the best option due to the low technological risks, environmental emissions and fuel cost. Additionally, cement kiln operators have good experience of handling waste derived fuels. The scenarios involving co-combustion of SRF with MSW and biomass were less favourable due to higher environmental risks and technical issues.

  11. An integrated appraisal of energy recovery options in the United Kingdom using solid recovered fuel derived from municipal solid waste

    International Nuclear Information System (INIS)

    Garg, A.; Smith, R.; Hill, D.; Longhurst, P.J.; Pollard, S.J.T.; Simms, N.J.

    2009-01-01

    This paper reports an integrated appraisal of options for utilising solid recovered fuels (SRF) (derived from municipal solid waste, MSW) in energy intensive industries within the United Kingdom (UK). Four potential co-combustion scenarios have been identified following discussions with industry stakeholders. These scenarios have been evaluated using (a) an existing energy and mass flow framework model, (b) a semi-quantitative risk analysis, (c) an environmental assessment and (d) a financial assessment. A summary of results from these evaluations for the four different scenarios is presented. For the given ranges of assumptions; SRF co-combustion with coal in cement kilns was found to be the optimal scenario followed by co-combustion of SRF in coal-fired power plants. The biogenic fraction in SRF (ca. 70%) reduces greenhouse gas (GHG) emissions significantly (∼2500 g CO 2 eqvt./kg DS SRF in co-fired cement kilns and ∼1500 g CO 2 eqvt./kg DS SRF in co-fired power plants). Potential reductions in electricity or heat production occurred through using a lower calorific value (CV) fuel. This could be compensated for by savings in fuel costs (from SRF having a gate fee) and grants aimed at reducing GHG emission to encourage the use of fuels with high biomass fractions. Total revenues generated from coal-fired power plants appear to be the highest ( Pounds 95/t SRF) from the four scenarios. However overall, cement kilns appear to be the best option due to the low technological risks, environmental emissions and fuel cost. Additionally, cement kiln operators have good experience of handling waste derived fuels. The scenarios involving co-combustion of SRF with MSW and biomass were less favourable due to higher environmental risks and technical issues.

  12. Characteristics of fuel cycle waste

    International Nuclear Information System (INIS)

    Aquilina, C.A.; Everette, S.E.

    1982-01-01

    The Low-Level Waste Management System started in 1979 to describe and model the existing commercial low-level waste management system. The system description produced is based on the identification of the different elements making up both the fuel and non-fuel cycle and their relationships to each other. A systems model based on the system description can accurately reflect the flow of low-level waste from generator to disposal site and is only limited by the reliability of the information it uses. For both the fuel cycle and non-fuel cycle large quantities of information is required in order to allow the system to operate at its full potential. Work is ongoing to collect this information. Significant progress is being made in the fuel cycle area primarily because the majority of fuel cycle low-level radioactive waste is produced by commercial power reactor plant operations. The Low-Level Waste Management system is only beginning to derive the benefits to be obtained from an accurate low-level waste management information system. As data is verified and analyzed, results on a national as well as individual organization level will be gained. Comparisons to previous studies will be made. Accurate projections of waste volumes and activities to be produced, projected impacts of waste streams of treatment or management changes are only examples of information to be produced. 1 figure, 1 table

  13. Production and characterization refuse derived fuel (RDF) from high organic and moisture contents of municipal solid waste (MSW)

    Science.gov (United States)

    Dianda, P.; Mahidin; Munawar, E.

    2018-03-01

    Many cities in developing countries is facing a serious problems to dealing with huge municipal solid waste (MSW) generated. The main approach to manage MSW is causes environmental impact associated with the leachate and landfill gas emissions. On the other hand, the energy available also limited by rapid growth of population and economic development due to shortage of the natural resource. In this study, the potential utilized of MSW to produce refuse derived fuel (RDF) was investigate. The RDF was produced with various organic waste content. Then, the RDF was subjected to laboratory analysis to determine its characteristic including the calorific value. The results shows the moisture content was increased by increasing organic waste content, while the calorific value was found 17-36 MJ/kg. The highest calorific value was about 36 MJ/kg obtained at RDF with 40% organic waste content. This results indicated that the RDF can be use to substitute coal in main burning process and calcinations of cement industry.

  14. Waste as a fuel

    Energy Technology Data Exchange (ETDEWEB)

    Lowes, T. M.; Lorimer, A. D.

    1979-07-01

    The methods of using the energy available in wastes to reduce the energy costs in processes are discussed. Special reference is made to the need for careful evaluation of the potential of the waste to reduce energy costs, before significant investment is made. Problems generally arise due to the effective balancing of the cost of the waste pretreatment with the disposal fee and prime fuel saving. Special reference is made to use of waste as a fuel in the cement industry. Municipal refuse is discussed as a typical successful application.

  15. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    1982-01-01

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

  16. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

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

    1983-07-01

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

  17. Wastes from fuel reprocessing

    International Nuclear Information System (INIS)

    Eschrich, H.

    1976-01-01

    Handling, treatment, and interim storage of radioactive waste, problems confronted with during the reprocessing of spent fuel elements from LWR's according to the Purex-type process, are dealt with in detail. (HR/LN) [de

  18. Investigation - Derived Waste Program

    International Nuclear Information System (INIS)

    Beardsley, C.; Anderson, R.

    1998-06-01

    The Investigation-Derived Waste Program is a software application that was developed to identify the groundwater monitoring wells at the Savannah River Site that require containerization and treatment for purge water generated during sampling

  19. Particulate emissions from a stationary engine fueled with ultra-low-sulfur diesel and waste-cooking-oil-derived biodiesel.

    Science.gov (United States)

    Betha, Raghu; Balasubramanian, Rajasekhar

    2011-10-01

    Stationary diesel engines, especially diesel generators, are increasingly being used in both developing countries and developed countries because of increased power demand. Emissions from such engines can have adverse effects on the environment and public health. In this study, particulate emissions from a domestic stationary diesel generator running on ultra-low-sulfur diesel (ULSD) and biodiesel derived from waste cooking oil were characterized for different load conditions. Results indicated a reduction in particulate matter (PM) mass and number emissions while switching diesel to biodiesel. With increase in engine load, it was observed that particle mass increased, although total particle counts decreased for all the fuels. The reduction in total number concentration at higher loads was, however, dependent on percentage of biodiesel in the diesel-biodiesel blend. For pure biodiesel (B100), the reduction in PM emissions for full load compared to idle mode was around 9%, whereas for ULSD the reduction was 26%. A large fraction of ultrafine particles (UFPs) was found in the emissions from biodiesel compared to ULSD. Nearly 90% of total particle concentration in biodiesel emissions comprised ultrafine particles. Particle peak diameter shifted from a smaller to a lower diameter with increase in biodiesel percentage in the fuel mixture.

  20. Fuel processing. Wastes processing

    International Nuclear Information System (INIS)

    Bourgeois, M.

    2000-01-01

    The gaseous, liquid and solid radioactive effluents generated by the fuel reprocessing, can't be release in the environment. They have to be treated in order to respect the limits of the pollution regulations. These processing are detailed and discussed in this technical paper. A second part is devoted to the SPIN research program relative to the separation of the long life radionuclides in order to reduce the radioactive wastes storage volume. (A.L.B.)

  1. The analysis of quantitative methods for renewable fuel processes and lubricant of materials derived from plastic waste

    Science.gov (United States)

    Rajagukguk, J. R.

    2018-01-01

    Plastic has become an important component in modern life today. Its role has replaced wood and metal, given its advantages such as light and strong, corrosion resistant, transparent and easy to color and good insulation properties. The research method is used with quantitative and engineering research methods. Research objective is to convert plastic waste into something more economical and to preserve the environment surrounding. Renewable fuel and lubricant variables are simultaneously influenced significantly to the sustainable environment. This is based on Fh> Ft of 62.101> 4.737) and its significance is 0.000 sustainable, the value of correlation coefficient 0.941 or 94.1% which means there is a very strong relationship between renewable fuel variables and lubricants to the sustainable environment. And utilizing plastic waste after being processed by pyrolysis method produces liquid hydrocarbons having elements of compounds such as crude oil and renewable fuels obtained from calculations are CO2 + H2O + C1-C4 + Residual substances. Then the plastic waste can be processed by isomerization process + catalyst to lubricating oil and the result of chemical calculation obtained is CO2, H2O, C18H21 and the rest.

  2. Combustion, Performance, and Emission Evaluation of a Diesel Engine with Biodiesel Like Fuel Blends Derived From a Mixture of Pakistani Waste Canola and Waste Transformer Oils

    Directory of Open Access Journals (Sweden)

    Muhammad Qasim

    2017-07-01

    Full Text Available The aim of this work was to study the combustion, performance, and emission characteristics of a 5.5 kW four-stroke single-cylinder water-cooled direct-injection diesel engine operated with blends of biodiesel-like fuel (BLF15, BLF20 & BLF25 obtained from a 50:50 mixture of transesterified waste transformer oil (TWTO and waste canola oil methyl esters (WCOME with petroleum diesel. The mixture of the waste oils was named as biodiesel-like fuel (BLF.The engine fuelled with BLF blends was evaluated in terms of combustion, performance, and emission characteristics. FTIR analysis was carried out to know the functional groups in the BLF fuel. The experimental results revealed the shorter ignition delay and marginally higher brake specific fuel consumption (BSFC, brake thermal efficiency (BTE and exhaust gas temperature (EGT values for BLF blends as compared to diesel. The hydrocarbon (HC and carbon monoxide (CO emissions were decreased by 10.92–31.17% and 3.80–6.32%, respectively, as compared to those of diesel fuel. Smoke opacity was significantly reduced. FTIR analysis has confirmed the presence of saturated alkanes and halide groups in BLF fuel. In comparison to BLF20 and BLF25, the blend BLF15 has shown higher brake thermal efficiency and lower fuel consumption values. The HC, CO, and smoke emissions of BLF15 were found lower than those of petroleum diesel. The fuel blend BLF15 is suggested to be used as an alternative fuel for diesel engines without any engine modification.

  3. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Allan, C.J.

    1993-01-01

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

  4. Study of combustion and emission characteristics of fuel derived from waste plastics by various waste to energy (W-t-E) conversion processes

    Science.gov (United States)

    Hazrat, M. A.; Rasul, M. G.; Khan, M. M. K.

    2016-07-01

    Reduction of plastic wastes by means of producing energy can be treated as a good investment in the waste management and recycling sectors. In this article, conversion of plastics into liquid fuel by two thermo-chemical processes, pyrolysis and gasification, are reviewed. The study showed that the catalytic pyrolysis of homogenous waste plastics produces better quality and higher quantity of liquefied fuel than that of non-catalytic pyrolysis process at a lower operating temperature. The syngas produced from gasification process, which occurs at higher temperature than the pyrolysis process, can be converted into diesel by the Fischer-Tropsch (FT) reaction process. Conducive bed material like Olivine in the gasification conversion process can remarkably reduce the production of tar. The waste plastics pyrolysis oil showed brake thermal efficiency (BTE) of about 27.75%, brake specific fuel consumption (BSFC) of 0.292 kg/kWh, unburned hydrocarbon emission (uHC) of 91 ppm and NOx emission of 904 ppm in comparison with the diesel for BTE of 28%, BSFC of 0.276 kg/kWh, uHC of 57 ppm and NOx of 855 ppm. Dissolution of Polystyrene (PS) into biodiesel also showed the potential of producing alternative transport fuel. It has been found from the literature that at higher engine speed, increased EPS (Expanded Polystyrene) quantity based biodiesel blends reduces CO, CO2, NOx and smoke emission. EPS-biodiesel fuel blend increases the brake thermal efficiency by 7.8%, specific fuel consumption (SFC) by 7.2% and reduces brake power (Pb) by 3.2%. More study using PS and EPS with other thermoplastics is needed to produce liquid fuel by dissolving them into biodiesel and to assess their suitability as a transport fuel. Furthermore, investigation to find out most suitable W-t-E process for effective recycling of the waste plastics as fuel for internal combustion engines is necessary to reduce environmental pollution and generate revenue which will be addressed in this article.

  5. Burning characteristics and gaseous/solid emissions of blends of pulverized coal with waste tire-derived fuel

    Energy Technology Data Exchange (ETDEWEB)

    Levendis, Y.A.; Atal, A.; Courtemanche, B.; Carlson, J.B. [Northeastern University, Boston, MA (United States). Dept. of Mechanical, Industrial and Manufacturing Engineering

    1998-10-01

    The combustion behaviour and the emissions from blends of a pulverized bituminous coal and ground waste automobile tires were investigated. Combustion took place under steady flow conditions, in an electrically-heated drop-tube furnace in air at a gas temperature of 1150{degree}C and a particle heating rate of approximate to 10{sup 5}{degree}C/s. Combustion observations were conducted with simultaneous pyrometry and cinematography. Interparticle flame interactions were visually observed in the near-stoichiometric and fuel-rich regions. Volatile flame interactions were apparent at a lower phi for tire crumb particles than for coal particles and became progressively more intense with increasing phi until at sufficiently high phi`s large group flames formed for tire particles. As particle flame interactions increased, average maximum temperatures in the flame decreased. Coal particles resisted the formation of group flames, even at high phi`s. Such observations correlated with the trends observed for the PAH emissions of the two fuels, those of tire crumb being much higher than those of coal Some stratification in the combustion of blends of particles of the two fuels was observed. This kept the PAH emissions lower levels than expected. NO{sub x} emissions from tires were much lower than those of coal, while those of the blends were close to the weighted average emissions. SO{sub 2} emissions from the blends were close to the weighted average emissions of the two fuels. Blending coal with tire reduced the CO{sub 2} emissions of coal but increased the CO emissions. Particulate emissions (soot and ash), measured in the range of 0.4 to 8{mu}m, increased with phi. Generally, tire produced more mass of submicron particulates than coal. Particulate emissions of blends of the two fuels were close to those expected based on weighted average of the two fuels.

  6. Toxicity of water-soluble fractions of biodiesel fuels derived from castor oil, palm oil, and waste cooking oil.

    Science.gov (United States)

    Leite, Maria Bernadete Neiva Lemos; de Araújo, Milena Maria Sampaio; Nascimento, Iracema Andrade; da Cruz, Andrea Cristina Santos; Pereira, Solange Andrade; do Nascimento, Núbia Costa

    2011-04-01

    Concerns over the sustained availability of fossil fuels and their impact on global warming and pollution have led to the search for fuels from renewable sources to address worldwide rising energy demands. Biodiesel is emerging as one of the possible solutions for the transport sector. It shows comparable engine performance to that of conventional diesel fuel, while reducing greenhouse gas emissions. However, the toxicity of products and effluents from the biodiesel industry has not yet been sufficiently investigated. Brazil has a very high potential as a biodiesel producer, in view of its climatic conditions and vast areas for cropland, with consequent environmental risks because of possible accidental biodiesel spillages into water bodies and runoff to coastal areas. This research determined the toxicity to two marine organisms of the water-soluble fractions (WSF) of three different biodiesel fuels obtained by methanol transesterification of castor oil (CO), palm oil (PO), and waste cooking oil (WCO). Microalgae and sea urchins were used as the test organisms, respectively, for culture-growth-inhibition and early-life-stage-toxicity tests. The toxicity levels of the analyzed biodiesel WSF showed the highest toxicity for the CO, followed by WCO and the PO. Methanol was the most prominent contaminant; concentrations increased over time in WSF samples stored up to 120 d. Copyright © 2010 SETAC.

  7. Refuse derived fuel incineration: Fuel gas monitoring and analysis

    International Nuclear Information System (INIS)

    Ranaldi, E.; Coronidi, M.; De Stefanis, P.; Di Palo, C.; Zagaroli, M.

    1993-11-01

    Experience and results on refuse derived fuel (selected from municipal solid wastes) incineration are reported. The study involved the investigation of inorganic compounds (heavy metals, acids and toxic gases) emissions, and included feeding materials and incineration residues characterization and mass balance

  8. Waste Plastic Converting into Hydrocarbon Fuel Materials

    Energy Technology Data Exchange (ETDEWEB)

    Sarker, Moinuddin; Mamunor Rashid, Mohammad; Molla, Mohammad

    2010-09-15

    The increased demand and high prices for energy sources are driving efforts to convert organic compounds into useful hydrocarbon fuels. Although much of this work has focused on biomass, there are strong benefits to deriving fuels from waste plastic material. Natural State Research Inc. (NSR) has invented a simple and economically viable process to decompose the hydrocarbon polymers of waste plastic into the shorter chain hydrocarbon of liquid fuel (patent pending). The method and principle of the production / process will be discussed. Initial tests with several widely used polymers indicate a high potential for commercialization.

  9. Portland clinker production with carbonatite waste and tire-derived fuel: crystallochemistry of minor and trace elements

    Directory of Open Access Journals (Sweden)

    F. R. D. Andrade

    2014-12-01

    Full Text Available This paper presents results on the composition of Portland clinkers produced with non-conventional raw-materials and fuels, focusing on the distribution of selected trace elements. Clinkers produced with three different fuel compositions were sampled in an industrial plant, where all other parameters were kept unchanged. The fuels have chemical fingerprints, which are sulfur for petroleum coke and zinc for TDF (tire-derived fuel. Presence of carbonatite in the raw materials is indicated by high amounts of strontium and phosphorous. Electron microprobe data was used to determine occupation of structural site of both C3S and C2S, and the distribution of trace elements among clinker phases. Phosphorous occurs in similar proportions in C3S and C2S; while considering its modal abundance, C3S is its main reservoir in the clinker. Sulfur is preferentially partitioned toward C2S compared to C3S. Strontium substitutes for Ca2+ mainly in C2S and in non-silicatic phases, compared to C3S.

  10. The development of municipal solid waste treatment technology based on refuse derived fuel and bio-gasification integration

    International Nuclear Information System (INIS)

    Muhd Noor Muhd Yunus

    2006-01-01

    The amount of MSW generated in big cities in Malaysia is very alarming. In Kuala Lumpur, the total waste generated is about 2,500 t/day. The existing landfills are being overused and should have been closed by now. However, till today, the solution is not really in place. The Government is planning to build a 1200 t/day Gasification and Ash Melting (GAMF) plant to partially resolve the above problem in Kuala Lumpur. However, even though environmentally rated as one of the best, technology is not cheap, thus failed to meet the BATNEEC concept. Currently, the Government, through the Strategic Master Plan, encourages the development of local technologies that are cheap and yet comply to international standards. As such, a private company, Recycle Energy Sdn Bhd (RESB), took the initiative to develop the RDF from Malaysian MSW. MINT Incineration and Renewable Energy Center (MIREC) has been commissioned to collaborate in the development of this technology, together with Universiti Putra Malaysia (UPM). A 15 t/day pilot scale RDF plant was established in 2001 in Kajang, to refine the concept as well as to establish more data. One year later, the company was given permission by the Government to set up a 700 t/day commercial facility in Semenyih, based on early success of the pilot testing done in Kajang. The integration of RDF, Anaerobic Digester and Fuel Cell Technology is adopted to generate in house power and export to the national grid, besides recycling a portion of the waste materials. This integration seems to be the best environmental as well as economic option that complies to BATNEEC concept. This paper highlights and discusses the issues and challenges in the process of developing RDF technology, both at the pilot scale R and D as well as the commercial scale plant planning

  11. Fuel reprocessing and waste management

    International Nuclear Information System (INIS)

    Philippone, R.L.; Kaiser, R.A.

    1989-01-01

    Because of different economic, social and political factors, there has been a tendency to compartmentalize the commercial nuclear power industry into separate power and fuel cycle operations to a greater degree in some countries compared to other countries. The purpose of this paper is to describe how actions in one part of the industry can affect the other parts and recommend an overall systems engineering approach which incorporates more cooperation and coordination between individual parts of the fuel cycle. Descriptions are given of the fuel cycle segments and examples are presented of how a systems engineering approach has benefitted the fuel cycle. Descriptions of fuel reprocessing methods and the waste forms generated are given. Illustrations are presented describing how reprocessing options affect waste management operations and how waste management decisions affect reprocessing

  12. Co-combustion of Fossil Fuels and Waste

    DEFF Research Database (Denmark)

    Wu, Hao

    The Ph.D. thesis deals with the alternative and high efficiency methods of using waste-derived fuels in heat and power production. The focus is on the following subjects: 1) co-combustion of coal and solid recovered fuel (SRF) under pulverized fuel combustion conditions; 2) dust-firing of straw...

  13. Power generation from refuse derived fuel

    International Nuclear Information System (INIS)

    Surroop, Dinesh; Mohee, Romeela

    2010-01-01

    Full text: The beginning of the third millennium has been characterized by a progressive increase in the demand for fossil fuels, which has caused a steep rise in oil price. At the same time, several environmental disasters have increased the sensitivity of world-wide public opinion towards the effect that environmental pollution has on human health and climate change. These conditions have fostered a renewed interest in renewable energy like solar energy, wind energy, biomass and solid wastes. In addition, the disposal of municipal solid waste (MSW) has become a critical and costly problem. The traditional landfill method requires large amounts of land and contaminates air, water and soil. The increase in socio-economic condition during the past ten years has also significantly increased the amount of solid waste generated. There are around 1200 tons of municipal solid waste (MSW) generated daily, of which the combustibles namely plastics, paper and textile waste represent 28%, and with the present generation rate, the landfill will be filled by 2012. The study was, therefore, initiated to assess the potential of power generation from refused derived fuels (RDF) from municipal solid waste (MSW) in order to reduce the dependency on fossil fuels. There are 336 tons which is equivalent to 12 tons/ h of RDF that can be generated daily from the MSW and this would generate 19.2 MW power. There will be 312 kg/ h of ash that would be generated and the NO x and SO 2 concentration were found to be 395.5 and 43.3 mg/ Nm 3 respectively. It was also found that the amount of non-biogenic CO 2 produced was 471 g/ kWhe. (author)

  14. Refuse derived fuel potential in DKI Jakarta

    Science.gov (United States)

    Widyatmoko, H.

    2018-01-01

    Combustible waste fractions of municipal solid waste (MSW) which can not be easily separated or sorted, reused or recycled, may have a high calorifiv value (CV) that can be used in a fuel for energy recovery. The objective of this study was to explore the Refuse Derived Fuel (RDF) potential of municipal solid waste from DKI Jakarta to produce electricity and to promote it to be socially and politically acceptable. For this purpose, 24 sampels of RDF were taken from Bantargebang, cabonized, molded and pressed to be briquette. All samples were analized for moisture, ash, and calorific value in the physical and chemistry Laboratory of ITB Bandung. The analysis of calorific value (CV) shows the CV difference of 1815.8 cal/g between the briquettes (8051.25 cal/g) and the RDF (9867.12 cal/g. The total waste DKI which can be used as briquettes 5253 ton / day or equivalent with 49154115 kWh / day. If the efficiency of electricity production from RDF was 25%, then Jakarta is able to generate electricity from RDF of 12288529 kWh / day or as much as energy needed by 573,480 middle-class households with energy needs of 642.84 kWh/month.

  15. Potential of solid waste utilization as source of refuse derived fuel (RDF) energy (case study at temporary solid waste disposal site in West Jakarta)

    Science.gov (United States)

    Indrawati, D.; Lindu, M.; Denita, P.

    2018-01-01

    This study aims to measure the volume of solid waste generated as well asits density, composition, and characteristics, to analyze the potential of waste in TPS to become RDF materials and to analyze the best composition mixture of RDF materials. The results show that the average of solid waste generation in TPS reaches 40.80 m3/day, with the largest percentage of its share is the organic waste component of 77.9%, while the smallest amount of its share is metal and rubber of 0.1%. The average water content and ash content of solid waste at the TPS is 27.7% and 6.4% respectively, while the average calorific potential value is 728.71 kcal/kg. The results of solid waste characteristics comparison at three TPS indicate thatTPS Tanjung Duren has the greatest waste potential to be processed into RDF materials with a calorific value of 893.73 kcal/kg, water content level of 24.6%, andlow ash content of 6.11%. This research has also shown that the best composition for RDF composite materials is rubber, wood, and textile mixtureexposed to outdoor drying conditions because it produced low water content and low ash content of 10.8% and 9.6%, thus optimizedthe calorific value of 4,372.896 kcal/kg.

  16. New techniques for the characterization of refuse-derived fuels and solid recovered fuels.

    Science.gov (United States)

    Rotter, Vera Susanne; Lehmann, Annekatrin; Marzi, Thomas; Möhle, Edda; Schingnitz, Daniel; Hoffmann, Gaston

    2011-02-01

    Solid recovered fuel (SRF) today refers to a waste-derived fuel meeting defined quality specifications, in terms of both origin (produced from non-hazardous waste) and levels of certain fuel properties. Refuse-derived fuel (RDF) nowadays is more used for unspecified waste after a basic processing to increase the calorific value and therefore this term usually refers to the segregated, high calorific fraction of municipal solid waste (MSW), commercial or industrial wastes. In comparison with conventional fuels, both types of secondary fuel show waste of inherently varying quality and an increased level of waste-specific contaminants.The transition from RDF to SRF in the emerging national and European market requires a quality assurance system with defined quality parameters and analytical methods to ensure reliable fuel characterization. However, due to the quality requirements for RDF and SRF, the current standardized analysis methods often do not meet these practical demands. Fast test methods, which minimize personnel, financial and time efforts and which are applicable for producers as well as users can be an important supporting tool for RDF- and SRF-characterization. Currently, a fast test system based on incineration and correlation analyses which enable the determination of relevant fuel parameters is under development. Fast test methods are not aimed at replacing current standardized test methods, but have to be considered as practical supporting tools for the characterization of RDF and SRF.

  17. The Canadian fuel waste management program

    International Nuclear Information System (INIS)

    McConnell, D.B.

    1986-04-01

    This report is the sixth in the series of annual reports on the research and development program for the safe management and disposal of Canada's nuclear fuel waste. The report summarizes progress in 1984 for the following activities: storage and transportation of used fuel, immobilization of nuclear fuel waste, geotechnical research, environmental research, and environmental and safety assessment. 186 refs

  18. Generation of transportation fuel from solid municipal waste plastics

    Energy Technology Data Exchange (ETDEWEB)

    Sarker, Moinuddin

    2010-09-15

    Transportation fuels derived from fossil fuels are subjected to the price fluctuations of the global marketplace, and constitute a major expense in the operation of a vehicle. Emissions from the evaporation and combustion of these fuels contribute to a range of environmental problems, causing poor air quality and emitting greenhouse gases that contribute to global warming. Alternative fuels created from domestic sources have been proposed as a solution to these problems, and many fuels are being developed based on biomass and other renewable sources. Natural State Research, Inc. developed different alternative hydrocarbon fuel which is produced from waste plastic materials.

  19. Waste management in MOX fuel fabrication plants

    International Nuclear Information System (INIS)

    Schneider, V.

    1982-01-01

    After a short description of a MOX fuel fabrication plant's activities the waste arisings in such a plant are discussed according to nature, composition, Pu-content. Experience has shown that proper recording leads to a reduction of waste arisings by waste awareness. Aspects of the treatment of α-waste are given and a number of treatment processes are reviewed. Finally, the current waste management practice and the α-waste treatment facility under construction at ALKEM are outlined. (orig./RW)

  20. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.

    1984-12-01

    The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1983 are described in this report

  1. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.; Rosinger, E.L.J.

    1984-04-01

    This report, the fifth of a series of annual reports, reviews the progress that has been made in the research and development program for the safe management and disposal of Canada's nuclear fuel waste. The report summarizes activities over the past year in the following areas: public interaction; used fuel storage and transportation; immobilization of used fuel and fuel recycle waste; geoscience research related to deep underground disposal; environmental research; and environmental and safety assessment

  2. Fuel Cell Power Plants Renewable and Waste Fuels

    Science.gov (United States)

    2011-01-13

    logo, Direct FuelCell and “DFC” are all registered trademarks (®) of FuelCell Energy, Inc. Applications •On-site self generation of combined heat... of FuelCell Energy, Inc. Fuels Resources for DFC • Natural Gas and LNG • Propane • Biogas (by Anaerobicnaerobic Digestion) - Municipal Waste...FUEL RESOURCES z NATURAL GAS z PROPANE z DFC H2 (50-60%) z ETHANOL zWASTE METHANE z BIOGAS z COAL GAS Diversity of Fuels plus High Efficiency

  3. The chemistry of nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Wiles, D.R.

    2002-01-01

    About one-fifth of the world's supply of energy is derived from nuclear fission. While this important source of power avoids the environmental and resource problems of most other fuels, and although nuclear accident statistics are much less alarming, no other peacetime technology has evoked such public disquiet and impassioned feeling. Central to dealing with these fears is the management and disposal of radioactive waste. An expert Canadian panel in 1977 recommended permanent disposal of wastes in deep geological formations, providing a basis for subsequent policies and research. In 1988, the Federal Environmental Assessment Review Office (FEARO) appointed a panel to assess the proposed disposal concepts and to recommend government policy. The panel in turn appointed a Scientific Review Group to examine the underlying science. Behind all these issues lay one central question: How well is the chemistry understood? This became the principal concern of Professor Donald Wiles, the senior nuclear chemist of the Scientific Review Group. In this book, Dr. Wiles carefully describes the nature of radioactivity and of nuclear power and discusses in detail the management of radioactive waste by the multi-barrier system, but also takes an unusual approach to assessing the risks. Using knowledge of the chemical properties of the various radionuclides in spent fuel, this book follows each of the important radionuclides as it travels through the many barriers placed in its path. It turns out that only two radionuclides are able to reach the biosphere, and they arrive at the earth's surface only after many thousands of years. A careful analysis of the critical points of the disposal plan emphasizes site rejection criteria and other stages at which particular care must be taken, demonstrating how dangers can be anticipated and putting to rest the fear of nuclear fuel waste and its geological burial

  4. Use of combustible wastes as fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kotler, V.R.; Salamov, A.A.

    1983-01-01

    Achievements of science and technology in creating and using units for combustion of wastes with recovery of heat of the escaping gases has been systematized and generalized. Scales and outlooks are examined for the use of general, industrial and agricultural waste as fuel, composition of the waste, questions of planning and operating units for combustion of solid refuse, settling of waste water and industrial and agricultural waste. Questions are covered for preparing them for combustion use in special units with recovery of heat and at ES, aspects of environmental protection during combustion of waste, cost indicators of the employed methods of recovering the combustible waste.

  5. Waste management, final waste disposal, fuel cycle

    International Nuclear Information System (INIS)

    Rengeling, H.W.

    1991-01-01

    Out of the legal poblems that are currently at issue, individual questions from four areas are dealt with: privatization of ultimate waste disposal; distribution of responsibilities for tasks in the field of waste disposal; harmonization and systematization of regulations; waste disposal - principles for making provisions for waste disposal - proof of having made provisions for waste disposal; financing and fees. A distinction has to be made between that which is legally and in particular constitutionally imperative or, as the case may be, permissible, and issues where there is room for political decision-making. Ultimately, the deliberations on the amendment are completely confined to the sphere of politics. (orig./HSCH) [de

  6. Status quo of energy recovery from waste in special industrial facilities and evaluation of the environmental impacts of using refuse derived fuel (RDF) in cement kilns in Germany; Untersuchung der Umweltauswirkungen des Einsatzes von Abfaellen ausserhalb thermischer Abfallbehandlungsanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Alwast, H.; Marton, C.; Koepp, M.

    2001-10-01

    Within the study presented here the use of energy recovery from waste was analysed for several industrial facilities, focussing on cement plants, kilns in the lime and gypsum industry, steel works and plants for the production of non ferrous metals. 44 German cement plants dispose of an own clinker production. Presently 31 plants have a permit for recovering energy from waste. The total permitted capacity for energy recovery in German cement kilns amounts to nearly 2,6 Mio. t/a. Mainly waste oil, old tyres, fuel derived from processed production-specific and municipal waste, plastics, scrap wood and waste paper are co-incinerated. In 1998/99 a total amount of roughly 945.000 t refuse was processed in 30 units of the studied facilities. In five furnaces at three steel works waste can be used for energy or material recovery. The approved total capacity of high calorific waste for energy recovery comes to nearly 350,000 t/a. Especially industrial plastics and packaging waste from DSD, plastics processed in scrap mills and shreddered waste and granulated paint sludge are used. In 1998 the facilities processed only old plastic, representing a total amount of nearly 109.000 t. At present seven facilities in the non ferrous metal industry have a permit for energy recovery from waste. The maximum capacity amounts on national level to nearly 140.000 t/a. Especially waste oil, packaging waste, plastics and scrap wood can be processed. The analysis of respective applications of the 17th BImSchV shows an inconsistency within the amending permitting procedures. For the time to come a conformity between the respective regional permitting authorities would be recommendable. Moreover, the effects on air emission caused by using waste for energy recovery were analysed for cement kilns with own clinker production. Due to the amendment of the 17th BImSchV more stringent requirements regarding waste composition must be established. This is especially valid for the highly volatile

  7. Municipal solid waste combustion: Fuel testing and characterization

    Energy Technology Data Exchange (ETDEWEB)

    Bushnell, D.J.; Canova, J.H.; Dadkhah-Nikoo, A.

    1990-10-01

    The objective of this study is to screen and characterize potential biomass fuels from waste streams. This will be accomplished by determining the types of pollutants produced while burning selected municipal waste, i.e., commercial mixed waste paper residential (curbside) mixed waste paper, and refuse derived fuel. These materials will be fired alone and in combination with wood, equal parts by weight. The data from these experiments could be utilized to size pollution control equipment required to meet emission standards. This document provides detailed descriptions of the testing methods and evaluation procedures used in the combustion testing and characterization project. The fuel samples will be examined thoroughly from the raw form to the exhaust emissions produced during the combustion test of a densified sample.

  8. New developments in tire derived fuels (TDF)

    Energy Technology Data Exchange (ETDEWEB)

    Hawkins, G. [Portland Cement Association, Skokie, IL (United States)

    2006-07-01

    Portland cement is a mixture of finely ground raw materials that are processed in a rotary kiln heated to 1500 degrees C by various fuels. Cooled clinker from the kiln is ground into portland cement. This presentation provided an overview of the role that tire-derived fuels is now playing in cement manufacturing. Data on the extent of TDF use in cement manufacturing processes were presented, as well as the results of air emissions monitoring programs conducted to assess the environmental impacts of TDF. During the cement manufacturing process, shredded and chipped tires are blown into the kiln to provide fuel, while whole tires are placed in the midpoint of long dry or wet kilns. For preheater and precalciner kilns, whole tires are added to raw material entering the kiln. The kiln's controlled combustion environment ensures the complete destruction of scrap tires. Approximately 130 million scrap tires were recycled in Portland cement plants in 2003. Forty-four portland cement plants are currently using TDF in North America. The United States Department of Energy has estimated that TDF produces less carbon dioxide (CO{sub 2}) per unit of energy than coal. Monitoring programs at Portland cement plants have indicated that the use of TDF in place of coal has resulted in moderate reductions of nitrogen oxide (NO{sub x}) emissions, slightly lower sulfuric oxide (SO{sub 2}) emissions and moderate reductions in carbon monoxide (CO). Some plants have reported slight reductions in particulate matter (PM) emissions. It was concluded that the use of scrap tires as a fuel reduces a waste stream and contributes to energy and raw material requirements. Moreover, plant air emissions are either reduced or are not impacted by TDF use. refs., tabs., figs.

  9. Waste management and the holistic fuel cycle

    International Nuclear Information System (INIS)

    Holmes, R.G.G.; Robbins, R.A.; Eilbeck, A.

    1996-01-01

    This paper outlines a holistic approach to the nuclear fuel cycle and the impact that waste management can have on the holistic approach. The philosophy includes regarding irradiated fuel as a resource rather than a waste that can be used as a source of fissile material to be recycled, either Uranium returned to fuel or Plutonium in mixed oxide fuels (MOX) for fast and impact of those compounds that leave the cycle (solid waste, liquid effluent and gaseous effluent) are minimized. This can only be achieved by applying a full life cycle analysis of process benefits. The paper describes some of the work in waste management but notes that waste and its generation must be seen as an integral part of any developed strategy. (authors)

  10. Fusion fuel cycle solid radioactive wastes

    International Nuclear Information System (INIS)

    Gore, B.F.; Kaser, J.D.; Kabele, T.J.

    1978-06-01

    Eight conceptual deuterium-tritium fueled fusion power plant designs have been analyzed to identify waste sources, materials and quantities. All plant designs include the entire D-T fuel cycle within each plant. Wastes identified include radiation-damaged structural, moderating, and fertile materials; getter materials for removing corrosion products and other impurities from coolants; absorbents for removing tritium from ventilation air; getter materials for tritium recovery from fertile materials; vacuum pump oil and mercury sludge; failed equipment; decontamination wastes; and laundry waste. Radioactivity in these materials results primarily from neutron activation and from tritium contamination. For the designs analyzed annual radwaste volume was estimated to be 150 to 600 m 3 /GWe. This may be compared to 500 to 1300 m 3 /GWe estimated for the LMFBR fuel cycle. Major waste sources are replaced reactor structures and decontamination waste

  11. Closed Fuel Cycle Waste Treatment Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Vienna, J. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Collins, E. D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Crum, J. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ebert, W. L. [Argonne National Lab. (ANL), Argonne, IL (United States); Frank, S. M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Garn, T. G. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gombert, D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jubin, R. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Maio, V. C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Marra, J. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Matyas, J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nenoff, T. M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Riley, B. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sevigny, G. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Soelberg, N. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Strachan, D. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Thallapally, P. K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, J. H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-02-01

    This study is aimed at evaluating the existing waste management approaches for nuclear fuel cycle facilities in comparison to the objectives of implementing an advanced fuel cycle in the U.S. under current legal, regulatory, and logistical constructs. The study begins with the Global Nuclear Energy Partnership (GNEP) Integrated Waste Management Strategy (IWMS) (Gombert et al. 2008) as a general strategy and associated Waste Treatment Baseline Study (WTBS) (Gombert et al. 2007). The tenets of the IWMS are equally valid to the current waste management study. However, the flowsheet details have changed significantly from those considered under GNEP. In addition, significant additional waste management technology development has occurred since the GNEP waste management studies were performed. This study updates the information found in the WTBS, summarizes the results of more recent technology development efforts, and describes waste management approaches as they apply to a representative full recycle reprocessing flowsheet. Many of the waste management technologies discussed also apply to other potential flowsheets that involve reprocessing. These applications are occasionally discussed where the data are more readily available. The report summarizes the waste arising from aqueous reprocessing of a typical light-water reactor (LWR) fuel to separate actinides for use in fabricating metal sodium fast reactor (SFR) fuel and from electrochemical reprocessing of the metal SFR fuel to separate actinides for recycle back into the SFR in the form of metal fuel. The primary streams considered and the recommended waste forms include; Tritium in low-water cement in high integrity containers (HICs); Iodine-129: As a reference case, a glass composite material (GCM) formed by the encapsulation of the silver Mordenite (AgZ) getter material in a low-temperature glass is assumed. A number of alternatives with distinct advantages are also considered including a fused silica waste form

  12. Residue Derived Fuels as an Alternative Fuel for the Hellenic Power Generation Sector and their Potential for Emissions ReductionConstantinos S. Psomopoulos

    Directory of Open Access Journals (Sweden)

    Constantinos S. Psomopoulos

    2014-09-01

    Full Text Available The European Union Landfill Directive (1999/31 EC promotes more environmental friendly waste management options, by reducing the amount of wastes and more specific of biodegradable wastes, disposed of in landfills. The EU member states are adopting the mechanical-biological treatment process for municipal solid waste and non-hazardous industrial wastes to comply with the abovementioned Directive's targets on landfill diversion, and produce waste derived fuels such as refuse derived fuel and solid recovered fuel. Waste derived fuels present high calorific values depending on their synthesis and are being used both in dedicated waste-to-energy plants and as fuel substitutes in industrial processes. In this paper the refuse derived fuel and solid recovered fuel production and utilisation options in European Union are presented, and the possibilities in Greece based on the waste production and National Plan for Waste Management of the Ministry of Environment is attempted. The existing and ongoing studies on co-combustion and co-gasification with brown coal support the use of refuse derived fuel and solid recovered fuel as fuel on Hellenic Power Sector, adopting in the existing lignite power plants adequate Air Pollution Control systems. If the co-combustion or co-gasification of these alternative fuels is adopted from the Hellenic Power Sector a reduction on emissions is expected that cannot be neglected.

  13. Combustion Of Poultry-Derived Fuel in a CFBC

    Science.gov (United States)

    Jia, Lufei; Anthony, Edward J.

    Poultry farming generates large quantities of waste. Current disposal practice is to spread the poultry wastes onto farmland as fertilizer. However, as the factory farms for poultry grow both in numbers and size, the amount of poultry wastes generated has increased significandy in recent years. In consequence, excessive application of poultry wastes on farmland is resulting in more and more contaminants entering the surface water. One of the options being considered is the use of poultry waste as power plant fuel. Since poultry-derived fuel (PDF) is biomass, its co-firing will have the added advantage of reducing greenhouse gas emissions from power generation. To evaluate the combustion characteristics of co-firing PDF with coal, combustion tests of mixtures of coal and PDF were conducted in CanmetENERGY's pilot-scale CFBC. The goal of the tests was to verify that PDF can be co-fired with coal and, more importantly, that emissions from the combustion process are not adversely affected by the presence of PDF in the fuel feed. The test results were very promising and support the view that co-firing in an existing coal-fired CFBC is an effective method of utilizing this potential fuel, both resolving a potential waste disposal problem and reducing the amount of CO2 released by the boiler.

  14. Nuclear fuel waste policy in Canada

    International Nuclear Information System (INIS)

    Brown, P.A.; Letourneau, C.

    1999-01-01

    The 1996 Policy Framework for Radioactive Waste established the approach in Canada for dealing with all radioactive waste, and defined the respective roles of Government and waste producers and owners. The Policy Framework sets the stage for the development of institutional and financial arrangements to implement long-term waste management solutions in a safe, environmentally sound, comprehensive, cost-effective and integrated manner. For nuclear fuel waste, a 10-year environmental review of the concept to bury nuclear fuel waste bundles at a depth of 500 m to 1000 m in stable rock of the Canadian Shield was completed in March 1998. The Review Panel found that while the concept was technically safe, it did not have the required level of public acceptability to be adopted at this time as Canada's approach for managing its nuclear fuel waste. The Panel recommended that a Waste Management Organization be established at arm's length from the nuclear industry, entirely funded by the waste producers and owners, and that it be subject to oversight by the Government. In its December 1998 Response to the Review Panel, the Government of Canada provided policy direction for the next steps towards developing Canada's approach for the long-term management of nuclear fuel waste. The Government chose to maintain the responsibility for long-term management of nuclear fuel waste close with the producers and owners of the waste. This is consistent with its 1996 Policy Framework for Radioactive Waste. This approach is also consistent with experience in many countries. In addition, the federal government identified the need for credible federal oversight. Cabinet directed the Minister of NRCan to consult with stakeholders, including the public, and return to ministers within 12 months with recommendations on means to implement federal oversight. (author)

  15. Production, quality and quality assurance of Refuse Derived Fuels (RDFs).

    Science.gov (United States)

    Sarc, R; Lorber, K E

    2013-09-01

    This contribution describes characterization, classification, production, application and quality assurance of Refuse Derived Fuels (RDFs) that are increasingly used in a wide range of co-incineration plants. It is shown in this paper, that the fuel-parameter, i.e. net calorific value [MJ/kg(OS)], particle size d(90) or d(95) [mm], impurities [w%], chlorine content [w%], sulfur content [w%], fluorine content [w%], ash content [w%], moisture [w%] and heavy metals content [mg/kg(DM)], can be preferentially used for the classification of different types of RDF applied for co-incineration and substitution of fossil-fuel in different industial sectors. Describing the external production of RDF by processing and confectioning of wastes as well as internal processing of waste at the incineration plant, a case study is reported on the application of RDF made out of different household waste fractions in a 120,000t/yr Waste to Energy (WtE) circulating fluidized bed (CFB) incinerator. For that purpose, delivered wastes, as well as incinerator feedstock material (i.e. after internal waste processing) are extensively investigated. Starting with elaboration of sampling plan in accordance with the relevant guidelines and standards, waste from different suppliers was sampled. Moreover, manual sorting analyses and chemical analyses were carried out. Finally, results of investigations are presented and discussed in the paper. Copyright © 2013 Elsevier Ltd. All rights reserved.

  16. Spent fuel and waste inventories and projections

    International Nuclear Information System (INIS)

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

    1980-08-01

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

  17. Waste management and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Molinari, J.

    1982-01-01

    The present lecture deals with energy needs and nuclear power, the importance of waste and its relative place in the fuel cycle, the games of controversies over nuclear waste in the strategies of energy and finally with missions and functions of the IAEA for privileging the rational approach and facilitating the transfer of technology. (RW)

  18. Radioactive waste management decommissioning spent fuel storage. V. 3. Waste transport, handling and disposal spent fuel storage

    International Nuclear Information System (INIS)

    1985-01-01

    As part of the book entitled Radioactive waste management decommissioning spent fuel storage, vol. 3 dealts with waste transport, handling and disposal, spent fuel storage. Twelve articles are presented concerning the industrial aspects of nuclear waste management in France [fr

  19. Advanced waste forms from spent nuclear fuel

    International Nuclear Information System (INIS)

    Ackerman, J.P.; McPheeters, C.C.

    1995-01-01

    More than one hundred spent nuclear fuel types, having an aggregate mass of more than 5000 metric tons (2700 metric tons of heavy metal), are stored by the United States Department of Energy. This paper proposes a method for converting this wide variety of fuel types into two waste forms for geologic disposal. The method is based on a molten salt electrorefining technique that was developed for conditioning the sodium-bonded, metallic fuel from the Experimental Breeder Reactor-II (EBR-II) for geologic disposal. The electrorefining method produces two stable, optionally actinide-free, high-level waste forms: an alloy formed from stainless steel, zirconium, and noble metal fission products, and a ceramic waste form containing the reactive metal fission products. Electrorefining and its accompanying head-end process are briefly described, and methods for isolating fission products and fabricating waste forms are discussed

  20. 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)

  1. Radioactive wastes in nuclear fuel cycle

    International Nuclear Information System (INIS)

    Sakata, Sadahiro; Nagaike, Tadakatsu; Emura, Satoru; Matsumoto, Akira; Morisawa, Shinsuke.

    1978-01-01

    Recent topics concerning radioactive water management and disposal are widely reviewed. As the introduction, various sources of radioactivity including uranium mining, fuel fabrication, reactor operation and fuel reprocessing and their amount of wastes accumulated per 1000 MWe year operation of a LWR are presented together with the typical methods of disposal. The second section discusses the problems associated with uranium fuel fabrication and with nuclear power plants. Typical radioactive nuclides and their sources in PWRs and BWRs are discussed. The third section deals with the problems associated with reprocessing facilities and with mixed oxide fuel fabrication. Solidification of high-level wastes and the methods of the disposal of transuranic nuclides are the main topics in this section. The fourth section discusses the methods and the problems of final disposal. Various methods being proposed or studied for the final disposal of low- and high-level wastes and transuranic wastes are reviewed. The fifth section concerns with the risk analysis of waste disposal. Both deterministic and probabilistic methods are treated. As the example, the assessment of the risk due to floods is explained. The associated event tree and fault three are presented together with the estimated probability of the occurrence of each constituent failure. In the final section, the environmental problems of radioactive wastes are widely reviewed. (Aoki, K.)

  2. Personnel exposure estimates associated with nuclear fuel reprocessing waste

    International Nuclear Information System (INIS)

    Boone, F.W.; Rogers, B.W.

    1983-08-01

    The operation design of the Barnwell Nuclear Fuel Plant (BNFP) calls for shipment of its wastes to either a low-level waste disposal site or to a Federal repository. This study analyzes the probable radiation dose accrued to the personnel involved in handling waste packages from all identified waste streams of the BNFP from generation to reception at destination and including transportation. The shielding characteristics of the transport packages were derived by assuming packaging in existing or prototyped casks. Possible combinations of waste forms and packages for which the projected dose exceeded DOT or NRC regulations for transport of radioactive materials were rejected. Legal weight truck and legal weight rail transport modes were assumed. Potential ways for reducing overall personnel exposure are considered, concentrating on the particular streams with the largest dose contributions. The personnel exposure estimates were determined using a computer program specifically designed for this purpose. This program is described in Appendix A. 9 references, 3 figures, 19 tables

  3. Transportation of radioactive wastes from nuclear fuel cycles

    International Nuclear Information System (INIS)

    1979-09-01

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

  4. Mixed waste paper to ethanol fuel

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    The objectives of this study were to evaluate the use of mixed waste paper for the production of ethanol fuels and to review the available conversion technologies, and assess developmental status, current and future cost of production and economics, and the market potential. This report is based on the results of literature reviews, telephone conversations, and interviews. Mixed waste paper samples from residential and commercial recycling programs and pulp mill sludge provided by Weyerhauser were analyzed to determine the potential ethanol yields. The markets for ethanol fuel and the economics of converting paper into ethanol were investigated.

  5. Nuclear fuel waste disposal in Canada

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Gillespie, P.A.

    1990-05-01

    Atomic Energy of Canada Limited (AECL) has developed a concept for disposing of Canada's nuclear fuel waste and is submitting it for review under Federal Environmental Assessment and Review Process. During this review, AECL intends to show that careful, controlled burial 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield is a safe and feasible way to dispose of Canada's nuclear fuel waste. The concept has been assessed without identifying or evaluating any particular site for disposal. AECL is now preparing a comprehensive report based on more than 10 years of research and development

  6. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Rummery, T.E.; Rosinger, E.L.J.

    1983-05-01

    The Canadian Nuclear Fuel Waste Management Program is now well established. This report outlines the generic research and technological development underway in this program to assess the concept of immobilization and subsequent disposal of nuclear fuel waste deep in a stable plutonic rock in the Canadian Shield. The program participants, funding, schedule and associated external review processes are briefly outlined. The major scientific and engineering components of the program, namely, immobilization studies, geoscience research and environmental and safety assessment, are described in more detail

  7. Nuclear fuel waste disposal in Canada

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Gillespie, P.A.

    1990-05-01

    Atomic Energy of Canada Limited (AECL) has developed a concept for disposing of Canada's nuclear fuel waste and is submitting it for review under the Federal Environmental Assessment and Review Process. During this review, AECL intends to show that careful, controlled burial 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield is a safe and feasible way to dispose of Canada's nuclear fuel waste. The concept has been assessed without identifying or evaluating any particular site for disposal. AECL is now preparing a comprehensive report based on more than 10 years of research and development

  8. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Rummery, T.E.; Rosinger, E.L.J.

    1984-12-01

    The Canadian Nuclear Fuel Waste Management Program is in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are described. Program funding, scheduling and associated external review processes are briefly outlined

  9. Waste derived bioeconomy in India: A perspective.

    Science.gov (United States)

    S, Venkata Mohan; P, Chiranjeevi; Dahiya, Shikha; A, Naresh Kumar

    2018-01-25

    Environmental and climatic change issues, population explosion, rapid urbanisation, depletion of fossil reserves, need for energy security, huge waste generation, etc. are some of the inherent issues associated with the fossil based linear economy which need greater attention. In this context, the world is gradually transforming from fossil-based economy to a sustainable circular bio-economy. The biogenic waste which is generated in enormous quanties in India can be considered as potential feedstock for structuring the bio-based economy. This communication depicts the need for developing waste derived bioeconomy in the Indian perspective. Waste is now being perceived as a resource with value and believed to supplement petroleum feedstock to a great extent if properly utilized. The necessity to introduce waste as the core element for the future economic models which also allows sustainable development is discussed. The review also establishes drivers for the bioeconomy and structures the waste derived bioeconomy in a sustainable format to address the futuristic needs, scope and opportunities envisaged in the business and economic realm. The enabling technologies/processes that can be applied for biogenic wastes valorisation are elaborated. Circularizing the economy in a waste biorefinery model for the production of biobased products including bioenergy is discussed. Copyright © 2017 Elsevier B.V. All rights reserved.

  10. 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

  11. Characteristics of radioactive waste streams generated in HTGR fuel reprocessing

    International Nuclear Information System (INIS)

    Lin, K.H.

    1976-01-01

    Results are presented of a study concerned with identification and characterization of radioactive waste streams from an HTGR fuel reprocessing plant. Approximate quantities of individual waste streams as well as pertinent characteristics of selected streams have been estimated. Most of the waste streams are unique to HTGR fuel reprocessing. However, waste streams from the solvent extraction system and from the plant facilities do not differ greatly from the corresponding LWR fuel reprocessing wastes

  12. Disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Nuttall, K.

    1994-01-01

    In 1978, the governments of Canada and Ontario established the Nuclear Fuel Waste Management program. As of the time of the conference, the research performed by AECL was jointly funded by AECL and Ontario Hydro through the CANDU owners' group. Ontario Hydro have also done some of the research on disposal containers and vault seals. From 1978 to 1992, AECL's research and development on disposal cost about C$413 million, of which C$305 was from funds provided to AECL by the federal government, and C$77 million was from Ontario Hydro. The concept involves the construction of a waste vault 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield. Used fuel (or possibly solidified reprocessing waste) would be sealed into containers (of copper, titanium or special steel) and emplaced (probably in boreholes) in the vault floor, surrounded by sealing material (buffer). Disposal rooms might be excavated on more than one level. Eventually all excavated openings in the rock would be backfilled and sealed. Research is organized under the following headings: disposal container, waste form, vault seals, geosphere, surface environment, total system, assessment of environmental effects. A federal Environmental Assessment Panel is assessing the concept (holding public hearings for the purpose) and will eventually make recommendations to assist the governments of Canada and Ontario in deciding whether to accept the concept, and how to manage nuclear fuel waste. 16 refs., 1 tab., 3 figs

  13. From waste to traffic fuel (W-fuel)

    Energy Technology Data Exchange (ETDEWEB)

    Kask, Ue.; Andrijevskaja, J.; Kask, L. [and others

    2012-11-01

    The EU directive on the promotion of the use of energy from renewable sources (Directive 2009/28/EC) sets a mandatory minimum target for the use of fuels produced using renewable energy sources of 10% of total petrol and diesel consumption in the transport sector by the year 2020. In addition, it states that production of renewable fuels should be consistent with sustainable development and must not endanger biodiversity. In the INTERREG IVA Southern Finland - Estonia Sub-programme, efforts towards finding solutions to the tasks set by the EU were undertaken in co-operation with Finnish and Estonian researchers. The purpose of the 'From Waste to Traffic Fuel' (W-Fuel) project was to promote the sustainable production and use of biogas using locally-sourced biodegradable waste materials from the food and beverage industry and the agricultural and municipal sectors. The ultimate aim of the project was to upgrade the biogas (produced based on anaerobic digestion of biodegradable wastes, sludge, manure, slurry and energy crops) to biomethane with a methane content similar to natural gas, to be further used as transport fuel with the aim of reducing traffic-borne emissions, in particular CO{sub 2}. The project combined waste, energy and traffic solutions in order to decrease emissions, costs and the use of materials. Six case areas in southern Finland and northern Estonia were selected. The two case areas in Estonia were the counties of Harju and Laeaene-Viru in northern Estonia. The project aimed to promote waste and sludge prevention and to commence biogas production and its subsequent upgrading to biomethane for use as a renewable fuel. The project promoted regional businesses and employment in waste treatment and 'green energy' production. On basis of the gathered data, the biogas potentials and prerequisites of each case county were analysed. Furthermore, the environmental, economic and other regional effects of the different options were

  14. Nuclear fuel cycle and waste management in France

    International Nuclear Information System (INIS)

    Sousselier, Yves.

    1981-05-01

    After a short description of the nuclear fuel cycle mining, milling, enrichment and reprocessing, radioactive waste management in France is exposed. The different types of radioactive wastes are examined. Storage, solidification and safe disposal of these wastes are described

  15. Cleaner emissions from a DI diesel engine fueled with waste plastic oil derived from municipal solid waste under the influence of n-pentanol addition, cold EGR, and injection timing.

    Science.gov (United States)

    Damodharan, Dillikannan; Sathiyagnanam, Amudhavalli Paramasivam; Rajesh Kumar, Babu; Ganesh, Kuttalam Chidambaradhanu

    2018-05-01

    Urban planning and development is a decisive factor that increases the automobile numbers which leads to increased energy demand across the globe. In order to meet the escalating requirements of energy, it is necessary to find viable alternatives. Waste plastic oil (WPO) is one such alternative which has dual benefits as it reduces the environmental pollution caused by plastic waste and it could possibly meet the energy requirement along with fossil fuels. The study attempted to reduce emissions from a DI diesel engine fueled with WPO using 30% by volume of n-pentanol with fossil diesel (WPO70P30). EGR (10, 20, and 30%) and injection timing modifications were made with the intention to find optimum engine operating conditions. The experimental results indicated that addition of renewable component like n-pentanol had improved the combustion characteristics by igniting WPO more homogeneously producing a higher premixed combustion phase. Smoke density for WPO70P30 was found to be twice lower than that of neat WPO at standard injection timing of 23°CA bTDC at any given EGR rate, NOx emissions were slightly on the higher side about 12% for WPO70P30 blend against WPO at same operating conditions. WPO70P30 showed lowest smoke and carbon monoxide emissions than diesel and WPO while delivering BTE's higher than WPO and closer to diesel at all EGR and injection timings. However NOx and HC emissions increased with n-pentanol addition. The use of EGR reduced NOx emissions but was found to aggravate other emissions. It was concluded WPO70P30 can be favorably used in a DI diesel engine at the engines advanced injection timing for better performance than diesel with a slight penalty in NOx emissions.

  16. Fuel cycle and waste management: A perspective from British nuclear fuels plc

    International Nuclear Information System (INIS)

    Holmes, R.G.G.; Fairhall, G.A.; Robbins, R.A.

    1996-01-01

    The phrase fuel cycle and waste management implies two separate and distinct activities. British Nuclear Fuels plc (BNFL) has adopted a holistic approach to the fuel cycle that integrates the traditional fuel cycle activities of conversion to uranium hexafluoride, fuel fabrication, power generation, and reprocessing with waste arisings, its subsequent treatment, and disposal

  17. Waste-wood-derived fillers for plastics

    Science.gov (United States)

    Brent English; Craig M. Clemons; Nicole Stark; James P. Schneider

    1996-01-01

    Filled thermoplastic composites are stiffer, stronger, and more dimensionally stable than their unfilled counterparts. Such thermoplastics are usually provided to the end-user as a precompounded, pelletized feedstock. Typical reinforcing fillers are inorganic materials like talc or fiberglass, but materials derived from waste wood, such as wood flour and recycled paper...

  18. Material streams in the fuel supply to and disposal of waste from nuclear power stations

    International Nuclear Information System (INIS)

    Merz, E.

    1990-01-01

    The nuclear fuel cycle is characterized by specifically small, but complex material streams. The fresh fuel derived from natural uranium is fed into the cycle at the stage of fuel element fabrication, while at the end stage, waste from spent fuel element reprocessing, or non-reprocessible fuel elements, are taken out of the cycle and prepared for ultimate disposal. The alternative methods of waste management, reprocessing or direct ultimate disposal, are an issue of controversial debate with regard to their differences in terms of supply policy, economic and ecological aspects. (orig.) [de

  19. Fuel Pellets Production from Biodiesel Waste

    Directory of Open Access Journals (Sweden)

    Kawalin Chaiyaomporn

    2010-01-01

    Full Text Available This research palm fiber and palm shell were used as raw materials to produce pelletised fuel, and waste glycerol were used as adhesive to reduce biodiesel production waste. The aim of this research is to find optimum ratio of raw material (ratio of palm fiber and palm shell, raw material size distribution, adhesive temperature, and ratio of ingredients (ratio of raw material, waste glycerol, and water. The optimum ratio of pelletized fuel made only by palm fiber was 50:10:40; palm fiber, water, and waste glycerol respectively. In the best practice condition; particle size was smaller than 2 mm, adhesive glycerol was heated. From the explained optimum ratio and ingredient, pelletizing ratio was 62.6%, specific density was 982.2 kg/m3, heating value was 22.5 MJ/kg, moisture content was 5.9194%, volatile matter was 88.2573%, fix carbon content was 1.5894%, and ash content was 4.2339% which was higher than the standard. Mixing palm shell into palm fiber raw material reduced ash content of the pellets. The optimum raw material ratio, which minimizes ash content, was 80 to 20 palm fiber and palm shell respectively. Adding palm shell reduced ash content to be 2.5247% which was higher than pelletized fuel standard but followed cubed fuel standard. At this raw material ratio, pelletizing ratio was 70.5%, specific density was 774.8 kg/m3, heating value was 19.71 MJ/kg, moisture content was 9.8137%, volatile matter was 86.2259%, fix carbon content was 1.4356%, and compressive force was 4.83 N. Pelletized fuel cost at optimum condition was 1.14 baht/kg.

  20. The management of nuclear fuel waste

    International Nuclear Information System (INIS)

    1980-06-01

    A Select Committee of the Legislature of Ontario was established to examine the affairs of Ontario Hydro, the provincial electrical utility. The Committee's terms of reference included examination of the waste management program being carried out jointly by the Ontario provincial government and the Canadian federal government. Public hearings were held which included private citizens as well as officials of organizations in the nuclear field and independent experts. Recommendations were made concerning the future direction of the Canadian fuel waste management program. (O.T.)

  1. Use of the fuel obtained from waste plastics as a mixture with diesel and biofuel

    Energy Technology Data Exchange (ETDEWEB)

    Kiernicki, Z.; Zelazo, P. [Lublin Univ. of Technology (Poland)

    2013-06-01

    The researches concerning the use of fuel derived from waste plastics and biodiesel have been presented in the paper. The biodiesel and the fuel obtained from waste plastics were both used as fuel components. The bio-admixture in the fuel was FAME, STING and rape oil. The catalytic cracking of polyolefin's was the source of second fuel admixture. The physical properties of analyzed components of the fuel have been presented. The operational parameters of direct injection diesel engine fuelled with tested fuel blends have been set out. The principles of fuel mixture preparation has been also described. The concept of the diesel fuel which is made from the components of opposite physical properties could have a positive practical effect and could improve the use of biofuels. (orig.)

  2. Estimates of relative areas for the disposal in bedded salt of LWR wastes from alternative fuel cycles

    International Nuclear Information System (INIS)

    Lincoln, R.C.; Larson, D.W.; Sisson, C.E.

    1978-01-01

    The relative mine-level areas (land use requirements) which would be required for the disposal of light-water reactor (LWR) radioactive wastes in a hypothetical bedded-salt formation have been estimated. Five waste types from alternative fuel cycles have been considered. The relative thermal response of each of five different site conditions to each waste type has been determined. The fuel cycles considered are the once-through (no recycle), the uranium-only recycle, and the uranium and plutonium recycle. The waste types which were considered include (1) unreprocessed spent reactor fuel, (2) solidified waste derived from reprocessing uranium oxide fuel, (3) plutonium recovered from reprocessing spent reactor fuel and doped with 1.5% of the accompanying waste from reprocessing uranium oxide fuel, (4) waste derived from reprocessing mixed uranium/plutonium oxide fuel in the third recycle, and (5) unreprocessed spent fuel after three recycles of mixed uranium/plutonium oxide fuels. The relative waste-disposal areas were determined from a calculated value of maximum thermal energy (MTE) content of the geologic formations. Results are presented for each geologic site condition in terms of area ratios. Disposal area requirements for each waste type are expressed as ratios relative to the smallest area requirement (for waste type No. 2 above). For the reference geologic site condition, the estimated mine-level disposal area ratios are 4.9 for waste type No. 1, 4.3 for No. 3, 2.6 for No. 4, and 11 for No. 5

  3. Fuels and chemicals from equine-waste-derived tail gas reactive pyrolysis oil: technoeconomic analysis, environmental and exergetic life cycle assessment

    Science.gov (United States)

    Horse manure, whose improper disposal imposes considerable environmental costs, constitutes an apt feedstock for conversion to renewable fuels and chemicals when tail gas reactive pyrolysis (TGRP) is employed. TGRP is a modification of fast pyrolysis that recycles its non-condensable gases and produ...

  4. Mixed waste paper as a fuel

    International Nuclear Information System (INIS)

    Kersletter, J.D.; Lyons, J.K.

    1991-01-01

    A successful recycling program requires several components: education and promotion, convenient collection service, and most importantly, a market for collected materials. In Washington state, domestic markets currently have, or are building, the capacity to use most of the glass, newsprint, aluminum, tin cans, and corrugated materials that are collected. Unfortunately, markets for mixed waste paper (MWP), a major component of the state's solid waste stream, have been slow to develop and are unable to absorb the tremendous volumes of material generated. The American Paper Stock Institute classifies MWP as low grade paper such as magazines, books, scrap paper, non-corrugated cardboard (boxboard/chipboard), and construction paper. When viewed as part of a curbside collection program MWP consists primarily of catalogs, binder paper, magazines, brochures, junk mail, cereal boxes, and other household packaging items. A comprehensive analysis of Washington State's solid waste stream showed that during 1988, Washington citizens generated approximately 460,000 tons of mixed waste paper. No small amount, this is equivalent to more than 10% of the total solid waste generated in the state, and is expected to increase. Current projections of MWP generation rates indicated that Washington citizens could discard as much as 960,000 tons of MWP by the year 2010 making it one of the single largest components of the state's solid waste stream. This paper reports on the use of MWP as fuel source

  5. Obtaining fuel briquets from the solid municipal waste

    International Nuclear Information System (INIS)

    Armenski, Slave; Kachurkov, Gjorgji; Vasilevski, Goce

    1998-01-01

    Recycling systems for solid waste materials are designed to reduce the amount of solid waste materials going to land fields. Through the Trash Separation Systems, clean municipal waste are reused in production of fuel pellets. Other waste streams such as coal fines, sawdust, wood chips, coke breeze and agricultural waste can be blended with these pellets along with a high thermal value binder and/or used motor oil to form a quality clean burning alternative fuel. (Author)

  6. Preliminary evaluation of fuel oil produced from pyrolysis of waste ...

    African Journals Online (AJOL)

    It could be refined further to produce domestic kerosene and gasoline. The physical and structural properties of the fuel oil produced compared favorably with that of Aviation fuel JP-4 (a wide-cut US Air force fuel). Presently African countries are importing aviation fuels. The fuel oil produced from the pyrolysis of waste water ...

  7. Special actinide nuclides: Fuel or waste?

    International Nuclear Information System (INIS)

    Srinivasan, M.; Rao, K.S.; Dingankar, M.V.

    1989-01-01

    The special actinide nuclides such as Np, Cm, etc. which are produced as byproducts during the operation of fission reactors are presently looked upon as 'nuclear waste' and are proposed to be disposed of as part of high level waste in deep geological repositories. The potential hazard posed to future generations over periods of thousands of years by these long lived nuclides has been a persistent source of concern to critics of nuclear power. However, the authors have recently shown that each and every one of the special actinide nuclides is a better nuclear fuel than the isotopes of plutonium. This finding suggests that one does not have to resort to exotic neutron sources for transmuting/incinerating them as proposed by some researchers. Recovery of the special actinide elements from the waste stream and recycling them back into conventional fission reactors would eliminate one of the stigmas attached to nuclear energy

  8. Effect of advanced fuel cycles on waste management policies

    International Nuclear Information System (INIS)

    Cavedon, J.M.; Haapalehto, T.

    2005-01-01

    The study aims at analysing a range of future fuel cycle options from the perspective of their impact on waste repository demand and specification. The study would focus on: Assessment of the characteristics of radioactive wastes arising from advanced nuclear fuel cycle options, repository performance analysis studies using source terms for waste arising from such advanced nuclear fuel cycles, identification of new options for waste management and disposal. Three families of fuel cycles having increasing recycling capabilities are assessed. Each cycle is composed of waste generating and management processes. Examples of waste generating processes are fuel factories (7 types) and reprocessing plants (7 types). Packaging and conditioning plants (7) and disposal facilities are examples of waste management processes. The characteristic of all these processes have been described and then total waste flows are summarised. In order to simplify the situation, three waste categories have been defined based on the IAEA definitions in order to emphasize the major effects of different types of waste. These categories are: short-life waste for surface or sub-surface disposal, long-life low heat producing waste for geological disposal, high-level waste for geological disposal. The feasibilities of the fuel cycles are compared in terms of economics, primary resource consumption and amount of waste generated. The effect of high-level waste composition for the repository performance is one of the tools in these comparisons. The results of this will be published as an NEA publication before the end of 2005. (authors)

  9. Advanced nuclear fuel cycles and radioactive waste management

    International Nuclear Information System (INIS)

    2006-01-01

    This study analyses a range of advanced nuclear fuel cycle options from the perspective of their effect on radioactive waste management policies. It presents various fuel cycle options which illustrate differences between alternative technologies, but does not purport to cover all foreseeable future fuel cycles. The analysis extends the work carried out in previous studies, assesses the fuel cycles as a whole, including all radioactive waste generated at each step of the cycles, and covers high-level waste repository performance for the different fuel cycles considered. The estimates of quantities and types of waste arising from advanced fuel cycles are based on best available data and experts' judgement. The effects of various advanced fuel cycles on the management of radioactive waste are assessed relative to current technologies and options, using tools such as repository performance analysis and cost studies. (author)

  10. Energy Supply- Production of Fuel from Agricultural and Animal Waste

    Energy Technology Data Exchange (ETDEWEB)

    Gabriel Miller

    2009-03-25

    The Society for Energy and Environmental Research (SEER) was funded in March 2004 by the Department of Energy, under grant DE-FG-36-04GO14268, to produce a study, and oversee construction and implementation, for the thermo-chemical production of fuel from agricultural and animal waste. The grant focuses on the Changing World Technologies (CWT) of West Hempstead, NY, thermal conversion process (TCP), which converts animal residues and industrial food processing biproducts into fuels, and as an additional product, fertilizers. A commercial plant was designed and built by CWT, partially using grant funds, in Carthage, Missouri, to process animal residues from a nearby turkey processing plant. The DOE sponsored program consisted of four tasks. These were: Task 1 Optimization of the CWT Plant in Carthage - This task focused on advancing and optimizing the process plant operated by CWT that converts organic waste to fuel and energy. Task 2 Characterize and Validate Fuels Produced by CWT - This task focused on testing of bio-derived hydrocarbon fuels from the Carthage plant in power generating equipment to determine the regulatory compliance of emissions and overall performance of the fuel. Task 3 Characterize Mixed Waste Streams - This task focused on studies performed at Princeton University to better characterize mixed waste incoming streams from animal and vegetable residues. Task 4 Fundamental Research in Waste Processing Technologies - This task focused on studies performed at the Massachusetts Institute of Technology (MIT) on the chemical reformation reaction of agricultural biomass compounds in a hydrothermal medium. Many of the challenges to optimize, improve and perfect the technology, equipment and processes in order to provide an economically viable means of creating sustainable energy were identified in the DOE Stage Gate Review, whose summary report was issued on July 30, 2004. This summary report appears herein as Appendix 1, and the findings of the report

  11. Wastes and waste management in the uranium fuel cycle for light water reactors

    International Nuclear Information System (INIS)

    Costello, J.M.

    1975-08-01

    The manufacturing processes in the uranium fuel cycle for light water reactors have been described with particular reference to the chemical and radiological wastes produced and the waste management procedures employed. The problems and possible solutions of ultimate disposal of high activity fission products and transuranium elements from reprocessing of irradiated fuel have been reviewed. Quantities of wastes arising in each stage of the fuel cycle have been summarised. Wastes arising from reactor operation have been described briefly. (author)

  12. Remote waste handling at the Hot Fuel Examination Facility

    International Nuclear Information System (INIS)

    Vaughn, M.E.

    1982-01-01

    Radioactive solid wastes, some of which are combustible, are generated during disassembly and examination of irradiated fast-reactor fuel and material experiments at the Hot Fuel Examination Facility (HFEF). These wastes are remotely segregated and packaged in doubly contained, high-integrity, clean, retrievable waste packages for shipment to the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). This paper describes the equipment and techniques used to perform these operations

  13. Waste disposal from the light water reactor fuel cycle

    International Nuclear Information System (INIS)

    Costello, J.M.; Hardy, C.J.

    1981-05-01

    Alternative nuclear fuel cycles for support of light water reactors are described and wastes containing naturally occurring or artificially produced radioactivity reviewed. General principles and objectives in radioactive waste management are outlined, and methods for their practical application to fuel cycle wastes discussed. The paper concentrates upon management of wastes from upgrading processes of uranium hexafluoride manufacture and uranium enrichment, and, to a lesser extent, nuclear power reactor wastes. Some estimates of radiological dose commitments and health effects from nuclear power and fuel cycle wastes have been made for US conditions. These indicate that the major part of the radiological dose arises from uranium mining and milling, operation of nuclear reactors, and spent fuel reprocessing. However, the total dose from the fuel cycle is estimated to be only a small fraction of that from natural background radiation

  14. National briefing summaries: Nuclear fuel cycle and waste management

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Lakey, L.T.; Silviera, D.J.

    1988-12-01

    The National Briefing Summaries is a compilation of publicly available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 21 nations, including the United States and three international agencies that have publicized their activities in this field. It presents available highlight information with references that may be used by the reader for additional information. The information in this document is compiled primarily for use by the US Department of Energy and other US federal agencies and their contractors to provide summary information on radioactive waste management activities in other countries. This document provides an awareness to managers and technical staff of what is occurring in other countries with regard to strategies, activities, and facilities. The information may be useful in program planning to improve and benefit United States' programs through foreign information exchange. Benefits to foreign exchange may be derived through a number of exchange activities.

  15. National briefing summaries: Nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    Schneider, K.J.; Lakey, L.T.; Silviera, D.J.

    1988-12-01

    The National Briefing Summaries is a compilation of publicly available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 21 nations, including the United States and three international agencies that have publicized their activities in this field. It presents available highlight information with references that may be used by the reader for additional information. The information in this document is compiled primarily for use by the US Department of Energy and other US federal agencies and their contractors to provide summary information on radioactive waste management activities in other countries. This document provides an awareness to managers and technical staff of what is occurring in other countries with regard to strategies, activities, and facilities. The information may be useful in program planning to improve and benefit United States' programs through foreign information exchange. Benefits to foreign exchange may be derived through a number of exchange activities

  16. Emulsification of waste cooking oils and fatty acid distillates as diesel engine fuels: An attractive alternative

    Directory of Open Access Journals (Sweden)

    Eliezer Ahmed Melo Espinosa

    2016-06-01

    Full Text Available The scope of this paper is to analyze the possibility and feasibility of the use of emulsification method applied to waste cooking oils and fatty acid distillates as diesel engine fuels, compared with other commonly used methods. These waste products are obtained from the refining oil industry, food industry and service sector, mainly. They are rarely used as feedstock to produce biofuels and other things, in spite of constitute a potential source of environmental contamination. From the review of the state of arts, significant decreases in exhaust emissions of nitrogen oxides, cylinder pressure as well as increases of the ignition delay, brake specific fuel consumption, hydrocarbon, smoke opacity, carbon monoxide, particulate matters to emulsified waste cooking oils and fatty acid distillates compared with diesel fuel are reported. In some experiments the emulsified waste cooking oils achieved better performance than neat fatty acid distillates, neat waste cooking oils and their derivatives methyl esters.

  17. EoW criteria for waste-derived aggregates

    NARCIS (Netherlands)

    Hjelmar, O.; Sloot, van der H.A.; Comans, R.N.J.; Wahlstrom, H.

    2013-01-01

    Waste-derived aggregates are being considered as possible candidates for development of End-of-Waste (EoW) criteria at European Union (EU) level in accordance with Article 6 (1) of the EU Waste Framework Directive (2008/98/EC) as a means of increasing the recovery of resources from waste. If a

  18. Spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1984-09-01

    Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy (DOE) radioactive wastes were compiled through December 31, 1983, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 37 years and characteristics of these materials are also presented, consistent with the latest DOE/Energy Information Administration (EIA) or projection of US commercial nuclear power growth and expected defense-related and private industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, airborne waste, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated, based on reported or calculated isotopic compositions. 48 figures, 107 tables

  19. Waste management in IFR [Integral Fast Reactor] fuel cycle

    International Nuclear Information System (INIS)

    Johnson, T.R.; Battles, J.E.

    1991-01-01

    The fuel cycle of the Integral Fast Reactor (IFR) has important potential advantage for the management of high-level wastes. This sodium-cooled, fast reactor will use metal fuels that are reprocessed by pyrochemical methods to recover uranium, plutonium, and the minor actinides from spent core and blanket fuel. More than 99% of all transuranic (TRU) elements will be recovered and returned to the reactor, where they are efficiently burned. The pyrochemical processes being developed to treat the high-level process wastes are capable of producing waste forms with low TRU contents, which should be easier to dispose of. However, the IFR waste forms present new licensing issues because they will contain chloride salts and metal alloys rather than glass or ceramic. These fuel processing and waste treatment methods can also handle TRU-rich materials recovered from light-water reactors and offer the possibility of efficiently and productively consuming these fuel materials in future power reactors

  20. Wastes from the light water reactor fuel cycle

    International Nuclear Information System (INIS)

    Steindler, M.J.; Trevorrow, L.E.

    1976-01-01

    The LWR fuel cycle is represented, in the minimum detail necessary to indicate the origin of the wastes, as a system of operations that is typical of those proposed for various commercial fuel cycle ventures. The primary wastes (before any treatment) are described in terms of form, volume, radioactivity, chemical composition, weight, and combustibility (in anticipation of volume reduction treatments). Properties of the wastes expected from the operation of reactors, fuel reprocessing plants, and mixed oxide fuel fabrication plants are expressed in terms of their amounts per unit of nuclear energy produced

  1. Military Solid Waste Reformer: A Pilot Study to Convert Military Waste to Logistics Fuel in the Field

    National Research Council Canada - National Science Library

    Myers, Duane

    2004-01-01

    .... Our approach to solve the military waste disposal and fuel supply problems was to convert the waste to a liquid fuel that can be used in place of or blended with conventional logistic fuels, particularly JP-8...

  2. Report on the disposal of radioactive wastes and spent fuel elements from Baden-Wuerttemberg

    International Nuclear Information System (INIS)

    2017-04-01

    The report on the disposal of radioactive wastes and spent fuel elements from Baden- Wuerttemberg covers the following issues: legal framework for the nuclear disposal; producer of spent fuels and radioactive wastes in Baden- Report on the disposal of radioactive wastes and spent fuel elements from Baden- Wuerttemberg; low- and medium-level radioactive wastes (non heat generating radioactive wastes); spent fuels and radioactive wastes from waste processing (heat generating radioactive wastes); final disposal.

  3. Commercial Spent Nuclear Fuel Waste Package Misload Analysis

    International Nuclear Information System (INIS)

    J.K. Knudson

    2003-01-01

    The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M and O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis

  4. Characteristics of used CANDU fuel relevant to the Canadian nuclear fuel waste management program

    Energy Technology Data Exchange (ETDEWEB)

    Wasywich, K M

    1993-05-01

    Literature data on the characteristics of used CANDU power reactor fuel that are relevant to its performance as a waste form have been compiled in a convenient handbook. Information about the quantities of used fuel generated, burnup, radionuclide inventories, fission gas release, void volume and surface area, fuel microstructure, fuel cladding properties, changes in fuel bundle properties due to immobilization processes, radiation fields, decay heat and future trends is presented for various CANDU fuel designs. (author). 199 refs., 39 tabs., 100 figs.

  5. Characteristics of used CANDU fuel relevant to the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Wasywich, K.M.

    1993-05-01

    Literature data on the characteristics of used CANDU power reactor fuel that are relevant to its performance as a waste form have been compiled in a convenient handbook. Information about the quantities of used fuel generated, burnup, radionuclide inventories, fission gas release, void volume and surface area, fuel microstructure, fuel cladding properties, changes in fuel bundle properties due to immobilization processes, radiation fields, decay heat and future trends is presented for various CANDU fuel designs. (author). 199 refs., 39 tabs., 100 figs

  6. Comparison of coal/solid recovered fuel (SRF) with coal/refuse derived fuel (RDF) in a fluidised bed reactor

    International Nuclear Information System (INIS)

    Wagland, S.T.; Kilgallon, P.; Coveney, R.; Garg, A.; Smith, R.; Longhurst, P.J.; Pollard, S.J.T.; Simms, N.

    2011-01-01

    An experimental study was undertaken to compare the differences between municipal solid waste (MSW) derived solid recovered fuel (SRF) (complying with CEN standards) and refuse derived fuel (RDF). Both fuels were co-combusted with coal in a 50 kW fluidised bed combustor and the metal emissions were compared. Synthetic SRF was prepared in the laboratory by grinding major constituents of MSW such as paper, plastic, textile and wood. RDF was obtained from a local mechanical treatment plant. Heavy metal emissions in flue gas and ash samples from the (coal + 10% SRF) fuel mixture were found to be within the acceptable range and were generally lower than that obtained for coal + 10% RDF fuel mixture. The relative distribution of heavy metals in ash components and the flue gas stream shows the presence of a large fraction (up to 98%) of most of the metals in the ash (except Hg and As). Thermo-gravimetric (TG) analysis of SRF constituents was performed to understand the behaviour of fuel mixtures in the absence and presence of air. The results obtained from the experimental study will enhance the confidence of fuel users towards using MSW-derived SRF as an alternative fuel.

  7. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Nuttall, K.

    1987-01-01

    Canada has established an extensive research program to develop and demonstrate the technology for safely disposing of nuclear fuel waste from Canadian nuclear electric generating stations. The program focuses on the concept of disposal deep in plutonic rock, which is abundant in the province of Ontario, Canada's major producer of nuclear electricity. Research is carried out at field research areas in the Canadian Precambrian Shield, and in government and university laboratories. The schedule calls for a document assessing the disposal concept to be submitted to regulatory and environmental agencies in late 1988. This document will form the basis for a review of the concept by these agencies and by the public. No site selection will be carried out before this review is completed. 10 refs.; 2 figs

  8. Potential health hazard of nuclear fuel waste and uranium ore

    International Nuclear Information System (INIS)

    Mehta, K.; Sherman, G.R.; King, S.G.

    1991-06-01

    The variation of the radioactivity of nuclear fuel waste (used fuel and fuel reprocessing waste) with time, and the potential health hazard (or inherent radiotoxicity) resulting from its ingestion are estimated for CANDU (Canada Deuterium Uranium) natural-uranium reactors. Four groups of radionuclides in the nuclear fuel waste are considered: actinides, fission products, activation products of zircaloy, and activation products of fuel impurities. Contributions from each of these groups to the radioactivity and to the potential health hazard are compared and discussed. The potential health hazard resulting from used fuel is then compared with that of uranium ore, mine tailings and refined uranium (fresh fuel) on the basis of equivalent amounts of uranium. The computer code HAZARD, specifically developed for these computations, is described

  9. Radioactive waste management of experimental DUPIC fuel fabrication process

    International Nuclear Information System (INIS)

    Lee, H. H.; Park, J. J.; Shin, J. M.; Yang, M. S.; Hong, K. P.

    2001-01-01

    The concept of DUPIC(Direct Use of Spent PWR Fuel in CANDU Reactors) is a dry processing technology to manufacture CANDU compatible DUPIC fuel from spent PWR fuel material. Real spent PWR fuel was used in IMEF M6 hot cell to carry out DUPIC experiment. Afterwards, about 200 kg-U of spent PWR fuel is supposed to be used till 2006. This study has been conducted in some hot cells of PIEF and M6 cell of IMEF. There are various forms of nuclear material such as rod cut, powder, green pellet, sintered pellet, fabrication debris, fuel rod, fuel bundle, sample, and process waste produced from various manufacturing experiment of DUPIC fuel. After completing test, the above nuclear wastes and test equipment etc. will be classified as radioactive waste, transferred to storage facility and managed rigorously according to domestic and international laws until the final management policy is determined. It is desirable to review management options in advance for radioactive waste generated from manufacturing experiment of DUPIC nuclear fuel as well as residual nuclear material and dismantled equipment. This paper includes basic plan for DUPIC radwaste, arising source and estimated amount of radioactive waste, waste classification and packing, transport cask, transport procedures

  10. Providing flexibility in spent fuel and vitrified waste management

    International Nuclear Information System (INIS)

    Bradley, N.; O'Tallamhain, C.; Brown, G.A.

    1986-01-01

    The UK Central Electricity Generating Board is pondering a decision to build a dry vault store as a buffer in its overall AGR spent fuel management programme. The application of the dry vault is not limited to fuel from gas cooled reactors, it can be used for spent LWR fuel and vitrified waste. A cutaway diagram of such a vault is presented. (UK)

  11. Alternative Fuels

    Science.gov (United States)

    Alternative fuels include gaseous fuels such as hydrogen, natural gas, and propane; alcohols such as ethanol, methanol, and butanol; vegetable and waste-derived oils; and electricity. Overview of alternative fuels is here.

  12. L. Transportation of fuel and wastes

    International Nuclear Information System (INIS)

    1976-01-01

    The principles applied to the transport of nuclear fuels and wastes have been founded on the more general provisions governing the transport of radioactive materials. Safe shipment of radioactive materials has historically been sought by specifying required characteristics in the shipping packages and establishing minimum acceptable levels of package integrity. The reason for this is that in the course of transport by road, rail, sea, or air, consignments of radioactive material are in close proximity to members of the public, and in many cases they are loaded or unloaded by transport workers who have had no special training or experience in the handling of such substances. The procedures adopted to ensure transport safety have worked satisfactorily. Both in the USA and the UK, the industry and regulatory authorities have established outstanding safety records in shipping radioactive materials over a period of thirty years. It is claimed that there have been no injuries due to the radioactive nature of the shipments, nor has there been a release of nuclear materials serious enough to be a threat of death or injury. Admittedly, about 95% of the 800,000 shipments estimated in the USA each year involve small quantities for use in industry, medicine, agriculture and education. However the principals underlying the safe packaging of these and reactor fuels are the same, and there is little reason to doubt that a similar safety record can be maintained

  13. Comparative techniques for nuclear fuel cycle waste management systems

    International Nuclear Information System (INIS)

    Pelto, P.J.; Voss, J.W.

    1979-09-01

    A safety assessment approach for the evaluation of predisposal waste management systems is described and applied to selected facilities in the light water reactor (LWR) once-through fuel cycle and a potential coprocessed UO 2 -PuO 2 fuel cycle. This approach includes a scoping analysis on pretreatment waste streams and a more detailed analysis on proposed waste management processes. The primary evaluation parameters used in this study include radiation exposures to the public from radionuclide releases from normal operations and potential accidents, occupational radiation exposure from normal operations, and capital and operating costs. On an overall basis, the waste management aspects of the two fuel cycles examined are quite similar. On an individual facility basis, the fuel coprocessing plant has the largest waste management impact

  14. National briefing summaries: Nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    Schneider, K.J.; Harmon, K.M.; Lakey, L.T.; Silviera, D.J.; Leigh, I.W.

    1987-09-01

    This report is a compilation of publicly-available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 20 nations and three international agencies that have publicized their activities in this field. The information in this document is compiled to provide summary information on radioactive waste management activities in other countries. This document indicates what is occurring in other countries with regard to strategies, activities, and facilities. This document first presents a short overview of the activities and trends for managing low- to high-level radioactive waste and spent fuel by the entities covered in this review. This is followed by information for each country for nuclear power; fuel cycle and waste management strategy/policy; highlights and major milestones; institutional considerations/organizations; nuclear fuel production; fuel recycle; spent fuel storage and transport; waste conditioning, storage and transport; surface and near-surface waste disposal; geologic waste disposal; management of uranium mine and mill wastes; decommissioning; international; and references. 406 refs

  15. Fuel handling, reprocessing, and waste and related nuclear data aspects

    International Nuclear Information System (INIS)

    Kuesters, H.; Lalovic, M.; Wiese, H.W.

    1979-06-01

    The essential processes in the out-of-pile nuclear fuel cycle are described, i.e. mining and milling of uranium ores, enrichment, fuel fabrication, storage, transportation, reprocessing of irradiated fuel, waste treatment and waste disposal. The aspects of radiation (mainly gammas and neutrons) and of heat production, as well as special safety considerations are outlined with respect to their potential operational impacts and long-term hazards. In this context the importance of nuclear data for the out-of-pile fuel cycle is discussed. Special weight is given to the LWR fuel cycle including recycling; the differences of LMFBR high burn-up fuel with large PuO 2 content are described. The HTR fuel cycle is discussed briefly as well as some alternative fuel cycle concepts. (orig.) [de

  16. Solid waste generation in reprocessing nuclear fuel

    International Nuclear Information System (INIS)

    North, E.D.

    1975-01-01

    Estimates are made of the solid wastes generated annually from a 750-ton/year plant (such as the NFS West Valley plant): high-level waste, hulls, intermediate level waste, failed equipment, HEPA filters, spent solvent, alpha contaminated combustible waste, and low specific activity waste. The annual volume of each category is plotted versus the activity level

  17. Production of metal waste forms from spent fuel treatment

    International Nuclear Information System (INIS)

    Westphal, B.R.; Keiser, D.D.; Rigg, R.H.; Laug, D.V.

    1995-01-01

    Treatment of spent nuclear fuel at Argonne National Laboratory consists of a pyroprocessing scheme in which the development of suitable waste forms is being advanced. Of the two waste forms being proposed, metal and mineral, the production of the metal waste form utilizes induction melting to stabilize the waste product. Alloying of metallic nuclear materials by induction melting has long been an Argonne strength and thus, the transition to metallic waste processing seems compatible. A test program is being initiated to coalesce the production of the metal waste forms with current induction melting capabilities

  18. Fuel reprocessing and waste management in the UK

    International Nuclear Information System (INIS)

    Heafield, W.; Griffin, N.L.

    1994-01-01

    The currently preferred route for the management of irradiated fuel in the UK is reprocessing. This paper, therefore, concentrates on outlining the policies, practices and achievement of British Nuclear Fuels plc (BNFL) associated with the management of its irradiated fuel facilities at Sellafield. The paper covers reprocessing and how the safe management of each of the major waste categories is achieved. BNFL's overall waste management policy is to develop, in close consultation with the regulatory authorities, a strategy to minimize effluent discharges and provide a safe, cost effective method of treating and preparing for disposal all wastes arising on the site

  19. Bioconversion of organic wastes for fuel and manure

    International Nuclear Information System (INIS)

    Jain, M.C.

    1993-01-01

    Major source of fuel in rural areas is still fire wood, cowdung and crop residues. Cowdung and crop residues can be effectively used as manure too. Bioconversion of organic wastes for fuel and manure can solve the twin problems. The paper deals with various kinds of organic wastes used as fuel, manure and for both, other organic wastes as alternate and supplemental feedstocks, impact of their bioconversion on rural energy and environment, dry fermentation technology, manurial value of the biogas slurry, etc. Important constraints in popularizing the biogas programme have been mentioned and their remedial measures have also been suggested. (author). 32 refs., 4 tabs., 3 figs

  20. Spent fuel and radioactive-waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1982-10-01

    Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 40 years, and characteristics of these materials are also presented, based on a present DOE/EIA projection of US commercial nuclear power growth and expected defense-related and industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, remedial action waste, active uranium mill tailings, airborne waste, and decommissioning. For each category, current and projected inventories are given through the year 2020. The land usage requirements are given for storage/disposal of low-level and transuranic wastes, and for the present inventories of inactive uranium mill tailings. For each waste category the radioactivity and thermal power are calculated. Isotopic compositions and cost data are given for each waste type and for spent fuel

  1. PRODUCTION OF NEW BIOMASS/WASTE-CONTAINING SOLID FUELS

    Energy Technology Data Exchange (ETDEWEB)

    David J. Akers; Glenn A. Shirey; Zalman Zitron; Charles Q. Maney

    2001-04-20

    CQ Inc. and its team members (ALSTOM Power Inc., Bliss Industries, McFadden Machine Company, and industry advisors from coal-burning utilities, equipment manufacturers, and the pellet fuels industry) addressed the objectives of the Department of Energy and industry to produce economical, new solid fuels from coal, biomass, and waste materials that reduce emissions from coal-fired boilers. This project builds on the team's commercial experience in composite fuels for energy production. The electric utility industry is interested in the use of biomass and wastes as fuel to reduce both emissions and fuel costs. In addition to these benefits, utilities also recognize the business advantage of consuming the waste byproducts of customers both to retain customers and to improve the public image of the industry. Unfortunately, biomass and waste byproducts can be troublesome fuels because of low bulk density, high moisture content, variable composition, handling and feeding problems, and inadequate information about combustion and emissions characteristics. Current methods of co-firing biomass and wastes either use a separate fuel receiving, storage, and boiler feed system, or mass burn the biomass by simply mixing it with coal on the storage pile. For biomass or biomass-containing composite fuels to be extensively used in the U.S., especially in the steam market, a lower cost method of producing these fuels must be developed that includes both moisture reduction and pelletization or agglomeration for necessary fuel density and ease of handling. Further, this method of fuel production must be applicable to a variety of combinations of biomass, wastes, and coal; economically competitive with current fuels; and provide environmental benefits compared with coal. Notable accomplishments from the work performed in Phase I of this project include the development of three standard fuel formulations from mixtures of coal fines, biomass, and waste materials that can be used in

  2. Minimization of waste from uranium purification, enrichment and fuel fabrication

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-10-01

    As any industry, nuclear industry generates a diverse range of waste which has to be managed in a safe manner to be acceptable to the public and the environment. The cost of waste management, the risks to the public and employees, and the detriment to the environment are dependent on the quantity and radioactive content of the waste generated. Waste minimization is a necessary activity needed to reduce the impact from nuclear fuel cycle operations and it is included in the national policy of some countries. In recognition of the importance of the subject, the IAEA has decided to review the current status of the work aimed at waste minimization in the nuclear fuel cycle. The waste minimization issues related to the back end of the nuclear fuel cycle are covered in Technical Reports Series No. 377 'Minimization of Radioactive Waste from Nuclear Power Plants and the Back End of the Nuclear Fuel Cycle' published in 1995. The present report deals with the front end of the nuclear fuel cycle, including existing options, approaches, developments and some specific considerations to be taken into account in decision making on waste minimization. It has been recognized that, in comparison with the back end of the nuclear fuel cycle, much less information is available, and this report should be considered as a first attempt to analyse waste minimization practices and opportunities in uranium purification, conversion, enrichment and fuel fabrication. Although mining and milling is an important part of the front end of the nuclear fuel cycle, these activities are excluded from consideration since relevant activities are covered in other IAEA publications.

  3. Minimization of waste from uranium purification, enrichment and fuel fabrication

    International Nuclear Information System (INIS)

    1999-10-01

    As any industry, nuclear industry generates a diverse range of waste which has to be managed in a safe manner to be acceptable to the public and the environment. The cost of waste management, the risks to the public and employees, and the detriment to the environment are dependent on the quantity and radioactive content of the waste generated. Waste minimization is a necessary activity needed to reduce the impact from nuclear fuel cycle operations and it is included in the national policy of some countries. In recognition of the importance of the subject, the IAEA has decided to review the current status of the work aimed at waste minimization in the nuclear fuel cycle. The waste minimization issues related to the back end of the nuclear fuel cycle are covered in Technical Reports Series No. 377 'Minimization of Radioactive Waste from Nuclear Power Plants and the Back End of the Nuclear Fuel Cycle' published in 1995. The present report deals with the front end of the nuclear fuel cycle, including existing options, approaches, developments and some specific considerations to be taken into account in decision making on waste minimization. It has been recognized that, in comparison with the back end of the nuclear fuel cycle, much less information is available, and this report should be considered as a first attempt to analyse waste minimization practices and opportunities in uranium purification, conversion, enrichment and fuel fabrication. Although mining and milling is an important part of the front end of the nuclear fuel cycle, these activities are excluded from consideration since relevant activities are covered in other IAEA publications

  4. The Derivation of Evaluation Criteria of Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Kim, S. K.; Ko, W. I.

    2013-01-01

    This study suggests the evaluation criteria and evaluation indicators derived using a factor analysis. As a result of a factor analysis, 5 evaluation criteria (safety (technological feature), environmental impact, economic feasibility, sociality, institution) and 24 evaluation indicators were selected. Particularly, the level of legislation for the management of radioactive waste, the level of establishment of safety standards of the country, and the level of application of international safety standards were analyzed to be qualitative evaluation indicators that should be considered in the aspect of the institution. The purpose of an analysis on diverse nuclear fuel cycles is to select the optimum nuclear fuel cycle suitable for the environment of one's own country. Accordingly, diverse evaluation criteria and evaluation indicators are necessary. In addition, individual evaluation criteria can be explained with various evaluation indicators. For example, the evaluation criteria for economic feasibility can be explained with evaluation indicators such as the unit cost or total cost. However, if too many evaluation indicators are included in one evaluation criterion, the evaluation is not easy, and if too few evaluation indicators are established, the evaluation criteria cannot be explained sufficiently, and thus the evaluation can be distorted. Accordingly, not only should the evaluation indicators be composed of an appropriate number of units, but they should also not be overlapped, and ambiguous evaluation indicators should be dropped out and necessary evaluation indicators must be included

  5. Spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1983-09-01

    Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled through December 31, 1982, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 40 years and characteristics of these materials are also presented, based on the latest DOE/EIA projection of US commercial nuclear power growth and expected defense-related and industrial and institutional activities. Materials considered, on a chapter-by-chapter bases, are: spent fuel, high-level waste, transuranic waste, low-level waste, active uranium mill tailings, airborne waste, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated, based on reported or calculated isotopic compositions. One chapter gives broad, summary data on the costs of spent fuel and radioactive waste management and disposal to provide an economic perspective. This chapter is not intended as a definitive guide, but it is a source of reasonable, order-of-magnitude costs and also provides references to more-detailed and scenario-specific studies. An appendix on generic flowsheets and source terms used for the projections is also included

  6. Radioactive waste management and advanced nuclear fuel cycle technologies

    International Nuclear Information System (INIS)

    2007-01-01

    In 2007 ENEA's Department of Nuclear Fusion and Fission, and Related Technologies acted according to national policy and the role assigned to ENEA FPN by Law 257/2003 regarding radioactive waste management and advanced nuclear fuel cycle technologies

  7. Legislative and Regulatory Timeline for Fossil Fuel Combustion Wastes

    Science.gov (United States)

    This timeline walks through the history of fossil fuel combustion waste regulation since 1976 and includes information such as regulations, proposals, notices, amendments, reports and meetings and site visits conducted.

  8. Microgasification cookstoves and pellet fuels from waste biomass: A ...

    African Journals Online (AJOL)

    Microgasification cookstoves and pellet fuels from waste biomass: A cost and performance comparison with charcoal and natural gas in Tanzania. ... produce too much smoke and 40% stating that controlling the air vent is too much trouble.

  9. The use of modified tyre derived fuel for compression ignition engines.

    Science.gov (United States)

    Pilusa, T J

    2017-02-01

    This study investigated physical and chemical modification of tyre-derived fuel oil (TDFO) obtained from pyrolysis of waste tyres and rubber products for application as an alternative fuel for compression ignition engines (CIE's). TDFO collected from a local waste tyre treatment facility was refined via a novel "oxidative gas-phase fractional distillation over 13× molecular sieves" to recover the light to medium fractions of the TDFO while oxidising and capturing some sulphur compounds in a gas phase. This was followed by desulphurization and chemical modification to improve cetane number, kinematic viscosity and fuel stability. The resulting fuel was tested in an ADE407T truck engine to compare its performance with petroleum diesel fuel. It was discovered that gas phase oxidative fractional distillation reduces the low boiling point sulphur compounds in TDFO such as mercaptans. Using petroleum diesel fuel as a reference, it was observed that the produced fuel has a lower cetane number, flash point and viscosity. On storage the fuel tends to form fibrous microstructures as a result of auto-oxidation of asphaltenes present in the fuel. Mixtures of alkyl nitrate, vinyl acetate, methacrylic anhydride, methyl-tert butyl ether, n-hexane and n-heptane were used to chemically modify the fuel in accordance with the minimum fuel specifications as per SANS 342. The engine performance tests results did not show any sign of engine ceasing or knocking effect. The power-torque trend was very consistent and compared well with petroleum diesel fuelled engine. The levels of total sulphur are still considerably high compared to other cleaner fuel alternatives derived from zero sulphur sources. Copyright © 2016. Published by Elsevier Ltd.

  10. Status of the Canadian Nuclear Fuel Waste Management Program

    International Nuclear Information System (INIS)

    Lyon, R.B.

    1985-10-01

    The Canadian Nuclear Fuel Waste Management Program is in the fifth year of a ten-year generic research and development phase. The major objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are well established

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  12. Anticipating Potential Waste Acceptance Criteria for Defense Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Rechard, R.P.; Lord, M.E.; Stockman, C.T.; McCurley, R.D.

    1997-01-01

    The Office of Environmental Management of the U.S. Department of Energy is responsible for the safe management and disposal of DOE owned defense spent nuclear fuel and high level waste (DSNF/DHLW). A desirable option, direct disposal of the waste in the potential repository at Yucca Mountain, depends on the final waste acceptance criteria, which will be set by DOE's Office of Civilian Radioactive Waste Management (OCRWM). However, evolving regulations make it difficult to determine what the final acceptance criteria will be. A method of anticipating waste acceptance criteria is to gain an understanding of the DOE owned waste types and their behavior in a disposal system through a performance assessment and contrast such behavior with characteristics of commercial spent fuel. Preliminary results from such an analysis indicate that releases of 99Tc and 237Np from commercial spent fuel exceed those of the DSNF/DHLW; thus, if commercial spent fuel can meet the waste acceptance criteria, then DSNF can also meet the criteria. In large part, these results are caused by the small percentage of total activity of the DSNF in the repository (1.5%) and regulatory mass (4%), and also because commercial fuel cladding was assumed to provide no protection

  13. Influence of fuel composition on the non-oxidizing heating of steel in a waste gas atmosphere

    Energy Technology Data Exchange (ETDEWEB)

    Minkler, W [LOI Industrieofenanlagen G.m.b.H., Essen (Germany, F.R.)

    1979-04-01

    On the basis of a number of graphs and data on theoretical combustion temperatures and the difference between the heating value of the fuel and the waste gas in respect of 1 m/sup 3/ of waste gas, the author demonstrates the influence of fuel composition on the non-oxidizing heating of steel in a waste gas atmosphere derived from five different fuels. A rotary-hearth furnace is described for the non-oxidizing heating of pressings from plain carbon and alloy steel.

  14. Overview of biomass and waste fuel resources for power production

    International Nuclear Information System (INIS)

    Easterly, J.L.; Burnham, M.

    1993-01-01

    This paper provides an overview of issues and opportunities associated with the use of biomass for electric power generation. Important physical characteristics of biomass and waste fuels are summarized, including comparisons with conventional fossil fuels, primarily coal. The paper also provides an overview of the current use of biomass and waste fuels for electric power generation. Biomass and waste fuels are currently used for approximately 9,800 megawatts (MW) of electric generating capacity, including about 6,100 MW of capacity fueled by wood/wood waste and about 2,200 MW of capacity fueled with municipal solid waste. Perspectives on the future availability of biomass fuels (including energy crops) are addressed, as well as projected levels of market penetration for biomass power. By the year 2010, there is a potential for 22,000 MW, to as much as 70,000 MW of biomass-powered electric generating capacity in the U.S. Given the range of benefits offered by biomass, including reduced sulfur emissions, reduced greenhouse gas emissions, job creation, rural revitalization impacts, and new incentives under the Energy Policy Act of 1992, the potential use of biomass for power production could significantly expand in the future

  15. Underlying chemistry research for the nuclear fuel waste management program

    International Nuclear Information System (INIS)

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

    1984-04-01

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

  16. Upgrading of waste oils into transportation fuels using hydrotreating technologies

    OpenAIRE

    Sudipta De; Rafael Luque

    2014-01-01

    The generation of organic waste continues to increase, causing severe environmental pollution. Waste valorization is currently an emerging technology that can address this problem with an extra benefit of producing a range of valued products. In this contribution, we report the current developments in hydrotreating technologies for upgrading waste oil fractions into usable transportation fuels. Particular focus is given on the catalysts selection for a general hydroprocessing technique as wel...

  17. Characterization of pyrolytic oil obtained from pyrolysis of TDF (Tire Derived Fuel)

    International Nuclear Information System (INIS)

    Banar, Müfide; Akyıldız, Vildan; Özkan, Aysun; Çokaygil, Zerrin; Onay, Özlem

    2012-01-01

    Highlights: ► We pyrolyzed Tire Derived Fuel (TDF) at different heating rates and temperatures. ► We determine convenient pyrolysis temperature for pyrolytic oil. ► The product can be used as fuel for combustion system in industry. ► TDF pyrolysis is advisable recycling system because of low hazardous constituents. - Abstract: In recent years, waste utilization before disposing to the land is the most important point about waste management. Due to the increasing emphasis on recycling, related to the two European Commission Directives (EC End of Life Vehicle Directive, EC Waste Landfill Directive) affecting the management of waste tires, there is interest in the development of alternative technologies for recycling waste tires. One of them is pyrolysis. For this purpose, a fixed bed reactor was used to pyrolysis of Tire Derived Fuel (TDF) at the temperatures of 350, 400, 450, 500, 550 and 600 °C with the heating rates of 5 and 35 °C/min. The maximum pyrolytic oil yield (38.8 wt.%) was obtained at 400 °C with 5 °C/min heating rate. The yield of pyrolytic oil decreased with increasing pyrolysis temperatures whereas the yield of gases increased. The fuel properties of the pyrolytic oil including higher heating value (HHV), elemental composition, flash point, viscosity, distillation and density were determined. Pyrolytic oil was characterized by fourier transform infrared spectroscopy (FT-IR), hydrogen nuclear magnetic resonance spectroscopy ( 1 H NMR) and gas chromatography–mass spectroscopy (GC–MS) techniques and also, the amount of polychlorinated dibenzodioxins/polychlorinated dibenzofurans (PCDDs/PCDFs) and congener distribution characteristics were studied for determination of environmental effects. It was seen that the pyrolytic oils have similar fuel properties with the diesel. It was also found that pyrolytic oil contained 0.00118 I-TEQs/g at very low level. Finally, the pyrolytic oil can be evaluated for energy recovery according to Regulation

  18. Commercial waste and spent fuel packaging program. Annual report

    International Nuclear Information System (INIS)

    Hakl, A.R.

    1981-10-01

    This document is a report of activities performed by Westinghouse Advanced Energy Systems Division - Nevada Operations in meeting subtask objectives described in the Nevada Nuclear Waste Storage Investigations (NNWSI) Project Plan and revised planning documentation for Fiscal Year (FY) 1981. Major activities included: completion of the first fuel exchange in the Spent Fuel Test - Climax program; plasma arc welder development; modification and qualification of a canister cutter; installation, and activation of a remote area monitor, constant air monitor and an alpha/beta/gamma counting system; qualification of grapples required to handle pressurized water reactor or boiling water reactor fuel and high level waste (HLW) logs; data acquisition from the 3 kilowatt soil temperature test, 2 kw fuel temperature test, and 2 kw drywell test; calorimetry of the fuel assembly used in the fuel temperature test; evaluation of moisture accumulation in the drywells and recommendations for proposed changes; revision of safety assessment document to include HLW log operations; preparation of quality assurance plan and procedures; development and qualification of all equipment and procedures to receive, handle and encapsulate both the HLW log and spent fuel for the basalt waste isolation program/near surface test facility program; preliminary studies of both the requirements to perform waste packaging for the test and evaluation facility and a cask storage program for the DOE Interim Spent Fuel Management program; and remote handling operations on radioactive source calibration in support of other contractors

  19. Safety aspects in fuel reprocessing and radioactive waste management

    International Nuclear Information System (INIS)

    Agarwal, K.

    2018-01-01

    Nuclear energy is used for generation of electricity and for production of a wide range of radionuclides for use in research and development, healthcare and industry. Nuclear industry uses nuclear fission as source of energy so a large amount of energy is available from very small amount of fuel. As India has adopted c losed fuel cycle , spent nuclear fuel from nuclear reactor is considered as a material of resource and reprocessed to recovery valuable fuel elements. Main incentive of reprocessing is to use the uranium resources effectively by recovering/recycling Pu and U present in the spent fuel. This finally leads to a very small percentage of residual material present in spent nuclear fuel requiring their management as radioactive waste. Another special feature of the Indian Atomic Energy Program is the attention paid from the very beginning to the safe management of radioactive waste

  20. Plan for spent fuel waste form testing for NNWSI [Nevada Nuclear Waste Storage Investigations

    International Nuclear Information System (INIS)

    Shaw, H.F.

    1987-11-01

    The purpose of spent fuel waste form testing is to determine the rate of release of radionuclides from failed disposal containers holding spent fuel, under conditions appropriate to the Nevada Nuclear Waste Storage Investigations (NNWSI) Project tuff repository. The information gathered in the activities discussed in this document will be used: to assess the performance of the waste package and engineered barrier system (EBS) with respect to the containment and release rate requirements of the Nuclear Regulatory Commission, as the basis for the spent fuel waste form source term in repository-scale performance assessment modeling to calculate the cumulative releases to the accessible environment over 10,000 years to determine compliance with the Environmental Protection Agency, and as the basis for the spent fuel waste form source term in repository-scale performance assessment modeling to calculate cumulative releases over 100,000 years as required by the site evaluation process specified in the DOE siting guidelines. 34 refs

  1. Description of different techniques and their potentials of development for the reduction of nitrous oxides in the exhaust gases of waste incinerators and refuse-derived fuel-fired power plants in terms of performance, cost and power consumption; Beschreibung unterschiedlicher Techniken und deren Entwicklungspotentiale zur Minderung von Stickstoffoxiden im Abgas von Abfallverbrennungsanlagen und Ersatzbrennstoff-Kraftwerken hinsichtlich Leistungsfaehigkeit, Kosten und Energieverbrauch

    Energy Technology Data Exchange (ETDEWEB)

    Beckmann, Michael [Technische Univ. Dresden (Germany)

    2011-11-15

    On 22nd July, 2002 the European Parliament passes the sixth Environmental Action Programme of the European Community. According to this Programme, the environmental pollution can be reduced to a level at which adverse effects on human health have to be reduced. Under this aspect, the author of the contribution under consideration describes various techniques and their development potential for the reduction of nitrogen oxides in the exhaust of waste incinerators and refuse-derived fuel-fired power plants in terms of performance, cost and power consumption. Primary measures (air staging, flue gas recirculation) and secondary measures (SNCR, SCR process, combined procedure) were used as techniques.

  2. Management of wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Heafield, W.; Barlow, P.

    1988-01-01

    The management of wastes from the nuclear fuel cycle is a key activity which affects all stages of the cycle and in which there is intense public interest, particularly at the culmination of waste management activities where dispersal and disposal are practised or are proposed. The different categories of waste are considered - high, intermediate and low level. A description is given of how and where in the fuel cycle they are produced, giving indications of volumes and activities. The fundamental objectives of waste management are reviewed and the application of these objectives to select practicable waste management processes, covering process systems product and safety considerations is discussed. Current technology can deal with the wastes now in storage, those which will be generated from oxide fuel reprocessing and future decommissioning activities; examples of these technologies, ranging from compaction and incineration for low level waste, encapsulation for intermediate level waste through to vitrification for high level waste, are described. The specific objectives relating to disposal are considered in the context of international co-operation on development and national strategies aimed at providing safe, deep repositories over the next 20 years. (author)

  3. Waste removal in pyrochemical fuel processing for the Integral Fast Reactor

    International Nuclear Information System (INIS)

    Ackerman, J.P.; Johnson, T.R.; Laidler, J.J.

    1994-01-01

    Electrorefining in a molten salt electrolyte is used in the Integral Fast Reactor fuel cycle to recover actinides from spent fuel. Processes that are being developed for removing the waste constituents from the electrorefiner and incorporating them into the waste forms are described in this paper. During processing, halogen, chalcogen, alkali, alkaline earth, and rare earth fission products build up in the molten salt as metal halides and anions, and fuel cladding hulls and noble metal fission products remain as metals of various particle sizes. Essentially all transuranic actinides are collected as metals on cathodes, and are converted to new metal fuel. After processing, fission products and other waste are removed to a metal and a mineral waste form. The metal waste form contains the cladding hulls, noble metal fission products, and (optionally) most rare earths in a copper or stainless steel matrix. The mineral waste form contains fission products that have been removed from the salt into a zeolite or zeolite-derived matrix

  4. Program summary. Nuclear waste management and fuel cycle programs

    International Nuclear Information System (INIS)

    1982-07-01

    This Program Summary Document describes the US Department of Energy (DOE) Nuclear Waste Management and Fuel Cycle Programs. Particular emphasis is given to near-term, specifically Fiscal Year (FY) 1982, activities. The overall objective of these programs will be achieved by the demonstration of: (1) safe radioactive waste management practices for storage and disposal of high-level waste and (2) advanced technologies necessary to close the nuclear fuel cycle on a schedule which would assure a healthy future for the development of nuclear power in this country

  5. Radiological protection and transuranic wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Morley, F.; Kelly, G.N.

    1976-01-01

    The significant higher actinides in the nuclear fuel cycle are identified and current knowledge of their radiotoxicity is reviewed with particular emphasis on plutonium. Experience of plutonium in the environment is briefly summarised. The origins of fuel cycle wastes contaminated by actinides are described and available data examined to estimate the amounts of radioactivity involved now and in the future. The radiological importance of individual isotopes of the various actinide elements in wastes is compared and attention drawn to changes with time. Some possible alternative waste management policies are reviewed against the requirements of radiological safety. (author)

  6. Review of the nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Hatcher, S.R.

    1980-06-01

    Progress over the previous year in the nuclear fuel waste management program is reviewed. Universities, industry and consultants have become increasingly involved, and the work is being overseen by a Technical Advisory Committee. The program has also been investigated by Ontario's Porter Commission and Select Committe on Ontario Hydro Affairs. A public information program has been extended to cover most of the Canadian Shield region of Ontario. Ontario Hydro is studying spent fuel storage and transportation, while AECL is covering immobilization of spent fuel or processing wastes, geotechnical and geochemical research in the laboratory and in the field, design of disposal facilities, and environmental and safety assessments. (L.L.)

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

    International Nuclear Information System (INIS)

    Soerlie, A.A.

    2002-01-01

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

  8. Evaluation of Waste Arising from Future Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  9. Environmental economics of lignin derived transport fuels

    OpenAIRE

    Obydenkova, SV; Kouris, P Panagiotis; Hensen, EJM Emiel; Heeres, Hero J; Boot, MD Michael

    2017-01-01

    This paper explores the environmental and economic aspects of fast pyrolytic conversion of lignin, obtained from 2G ethanol plants, to transport fuels for both the marine and automotive markets. Various scenarios are explored, pertaining to aggregation of lignin from several sites, alternative energy carries to replace lignin, transport modalities, and allocation methodology. The results highlight two critical factors that ultimately determine the economic and/or environmental fuel viability....

  10. Fuel corrosion processes under waste disposal conditions

    International Nuclear Information System (INIS)

    Shoesmith, D.W.

    2000-01-01

    The release of the majority of radionuclides from spent nuclear fuel under permanent disposal conditions will be controlled by the rate of dissolution of the UO 2 fuel matrix. In this manuscript the mechanism of the coupled anodic (fuel dissolution) and cathodic (oxidant reduction) reactions which constitute the overall fuel corrosion process is reviewed, and the many published observations on fuel corrosion under disposal conditions discussed. The primary emphasis is on summarizing the overall mechanistic behaviour and establishing the primary factors likely to control fuel corrosion. Included are discussions on the influence of various oxidants including radiolytic ones, pH, temperature, groundwater composition, and the formation of corrosion product deposits. The relevance of the data recorded on unirradiated UO 2 to the interpretation of spent fuel behaviour is included. Based on the review, the data used to develop fuel corrosion models under the conditions anticipated in Yucca Mountain (NV, USA) are evaluated

  11. Rotary kiln and batch pyrolysis of waste tire to produce gasoline and diesel like fuels

    International Nuclear Information System (INIS)

    Ayanoğlu, Abdulkadir; Yumrutaş, Recep

    2016-01-01

    Highlights: • Waste Tire Oil (WTO) is produced from waste tire at rotary kiln reactor. • Physical and chemical properties of WTO and fuel samples are analyzed. • Gasoline like fuel (GLF) and diesel like fuel (DLF) are produced from the WTO-10 wt% CaO mixture at fixed bed reactor. • Physical and chemical properties of the GLF and DLF are compared with the standard fuels. - Abstract: In this study, waste tire is pyrolyzed in a rotary kiln reactor to obtain more gas, light liquid, heavy liquid, wax products, and less carbon black at their maximum yields as, 20%, 12%, 25%, 8% and 35% of the total weight (4 tones), respectively. Then, the heavy and light oils are reacted with additives such as natural zeolite (NZ) and lime (CaO) at different mass ratio as 2, 6, and 10 wt%, respectively, in the batch reactor to produce liquids similar to standard petroleum fuels. The heavy and light oils mixture samples are distillated to observe their optimum graphics which are similar to gasoline and diesel like fuel. Consequently, the best results are obtained from the CaO sample with 10 wt% in comparison to the ones from the gasoline and diesel fuels. The 10 wt% CaO light liquid mixture resembles to gasoline named as gasoline like fuel (GLF) and the 10 wt% CaO heavy liquid mixture is similar to diesel called as diesel like fuel (DLF). The chemical and physical features of the waste tire, light oil, heavy oil, GLF, and DLF are analyzed by TG (thermogravimetric)/dTG (derivative thermogravimetric), proximate, ultimate, higher heating value (HHV), fourier transform-infrared spectroscopy (FT-IR), Brunauer–Emmett–Teller (BET), sulfur, density, viscosity, gas chromatography–mass spectroscopy (GC–MS), flash point, moisture, and distillation tests. The test results are turned out to be very close to the standard petroleum fuel.

  12. Monitoring methods for nuclear fuel waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, R B; Barnard, J W; Bird, G A [and others

    1997-11-01

    This report examines a variety of monitoring activities that would likely be involved in a nuclear fuel waste disposal project, during the various stages of its implementation. These activities would include geosphere, environmental, vault performance, radiological, safeguards, security and community socioeconomic and health monitoring. Geosphere monitoring would begin in the siting stage and would continue at least until the closure stage. It would include monitoring of regional and local seismic activity, and monitoring of physical, chemical and microbiological properties of groundwater in rock and overburden around and in the vault. Environmental monitoring would also begin in the siting stage, focusing initially on baseline studies of plants, animals, soil and meteorology, and later concentrating on monitoring for changes from these benchmarks in subsequent stages. Sampling designs would be developed to detect changes in levels of contaminants in biota, water and air, soil and sediments at and around the disposal facility. Vault performance monitoring would include monitoring of stress and deformation in the rock hosting the disposal vault, with particular emphasis on fracture propagation and dilation in the zone of damaged rock surrounding excavations. A vault component test area would allow long-term observation of containers in an environment similar to the working vault, providing information on container corrosion mechanisms and rates, and the physical, chemical and thermal performance of the surrounding sealing materials and rock. During the operation stage, radiological monitoring would focus on protecting workers from radiation fields and loose contamination, which could be inhaled or ingested. Operational zones would be established to delineate specific hazards to workers, and movement of personnel and materials between zones would be monitored with radiation detectors. External exposures to radiation fields would be monitored with dosimeters worn by

  13. The presence of zinc in Swedish waste fuels.

    Science.gov (United States)

    Jones, Frida; Bisaillon, Mattias; Lindberg, Daniel; Hupa, Mikko

    2013-12-01

    Zinc (Zn) is a chemical element that has gained more attention lately owing to its possibility to form corrosive deposits in large boilers, such as Waste-to-Energy plants. Zn enters the boilers in many different forms and particularly in waste, the amount of Zn is hard to determine due to both the heterogeneity of waste in general but also due to the fact that little is yet published specifically about the Zn levels in waste. This study aimed to determine the Zn in Swedish waste fuels by taking regular samples from seven different and geographically separate waste combustion plants over a 12-month period. The analysis shows that there is a relation between the municipal solid waste (MSW) content and the Zn-content; high MSW-content gives lower Zn-content. This means that waste combustion plants with a higher share of industrial and commercial waste and/or building and demolition waste would have a higher share of Zn in the fuel. The study also shows that in Sweden, the geographic location of the plant does not have any effect on the Zn-content. Furthermore, it is concluded that different seasons appear not to affect the Zn concentrations significantly. In some plants there was a clear correlation between the Zn-content and the content of other trace metals. Copyright © 2013 Elsevier Ltd. All rights reserved.

  14. Soybean-derived biofuels and home heating fuels.

    Science.gov (United States)

    Mushrush, George W; Wynne, James H; Willauer, Heather D; Lloyd, Christopher L

    2006-01-01

    It is environmentally enticing to consider replacing or blending petroleum derived heating fuels with biofuels for many reasons. Major considerations include the soaring worldwide price of petroleum products, especially home heating oil, the toxicity of the petroleum-derived fuels and the environmental damage that leaking petroleum tanks afford. For these reasons, it has been suggested that domestic renewable energy sources be considered as replacements, or at the least, as blending stocks for home heating fuels. If recycled soy restaurant cooking oils could be employed for this purpose, this would represent an environmental advantage. Renewable plant sources of energy tend to be less toxic than their petroleum counterparts. This is an important consideration when tank leakage occurs. Home fuel oil storage tanks practically always contain some bottom water. This water environment has a pH value that factors into heating fuel stability. Therefore, the question is: would the biofuel help or exacerbate fuel stability and furnace maintenance issues?

  15. NEW SOLID FUELS FROM COAL AND BIOMASS WASTE; FINAL

    International Nuclear Information System (INIS)

    Hamid Farzan

    2001-01-01

    Under DOE sponsorship, McDermott Technology, Inc. (MTI), Babcock and Wilcox Company (B and W), and Minergy Corporation developed and evaluated a sludge derived fuel (SDF) made from sewage sludge. Our approach is to dry and agglomerate the sludge, combine it with a fluxing agent, if necessary, and co-fire the resulting fuel with coal in a cyclone boiler to recover the energy and to vitrify mineral matter into a non-leachable product. This product can then be used in the construction industry. A literature search showed that there is significant variability of the sludge fuel properties from a given wastewater plant (seasonal and/or day-to-day changes) or from different wastewater plants. A large sewage sludge sample (30 tons) from a municipal wastewater treatment facility was collected, dried, pelletized and successfully co-fired with coal in a cyclone-equipped pilot. Several sludge particle size distributions were tested. Finer sludge particle size distributions, similar to the standard B and W size distribution for sub-bituminous coal, showed the best combustion and slagging performance. Up to 74.6% and 78.9% sludge was successfully co-fired with pulverized coal and with natural gas, respectively. An economic evaluation on a 25-MW power plant showed the viability of co-firing the optimum SDF in a power generation application. The return on equity was 22 to 31%, adequate to attract investors and allow a full-scale project to proceed. Additional market research and engineering will be required to verify the economic assumptions. Areas to focus on are: plant detail design and detail capital cost estimates, market research into possible project locations, sludge availability at the proposed project locations, market research into electric energy sales and renewable energy sales opportunities at the proposed project location. As a result of this program, wastes that are currently not being used and considered an environmental problem will be processed into a renewable

  16. Solid recovered fuel: influence of waste stream composition and processing on chlorine content and fuel quality.

    Science.gov (United States)

    Velis, Costas; Wagland, Stuart; Longhurst, Phil; Robson, Bryce; Sinfield, Keith; Wise, Stephen; Pollard, Simon

    2012-02-07

    Solid recovered fuel (SRF) produced by mechanical-biological treatment (MBT) of municipal waste can replace fossil fuels, being a CO(2)-neutral, affordable, and alternative energy source. SRF application is limited by low confidence in quality. We present results for key SRF properties centered on the issue of chlorine content. A detailed investigation involved sampling, statistical analysis, reconstruction of composition, and modeling of SRF properties. The total chlorine median for a typical plant during summer operation was 0.69% w/w(d), with lower/upper 95% confidence intervals of 0.60% w/w(d) and 0.74% w/w(d) (class 3 of CEN Cl indicator). The average total chlorine can be simulated, using a reconciled SRF composition before shredding to limit for ash content marginally below the 20% w/w(d) deemed suitable for certain power plants; and a lower 95% confidence limit of net calorific value (NCV) at 14.5 MJ kg(ar)(-1). The data provide, for the first time, a high level of confidence on the effects of SRF composition on its chlorine content, illustrating interrelationships with other fuel properties. The findings presented here allow rational debate on achievable vs desirable MBT-derived SRF quality, informing the development of realistic SRF quality specifications, through modeling exercises, needed for effective thermal recovery.

  17. Generic waste management concepts for six LWR fuel cycles

    International Nuclear Information System (INIS)

    DePue, J.D.

    1979-04-01

    This report supplements the treatment of waste management issues provided in the Generic Environmental Statement on the use of recycle plutonium in mixed oxide fuel in light water cooled reactors (GESMO, NUREG-0002). Three recycle and three no-recycle options are described in this document. Management of the radioactive wastes that would result from implementation of either type of fuel cycle alternative is discussed. For five of the six options, wastes would be placed in deep geologic salt repositories for which thermal criteria are considered. Radiation doses to the workers at the repositories and to the general population are discussed. The report also covers the waste management schedule, the land and salt commitments, and the economic costs for the management of wastes generated

  18. Refuse-derived fuel from municipal solid waste residuals : a feasibility study[Manure, biosolids, and organic industrial/commercial residuals in land applications programs : improving beneficial reuse and protection of water quality

    Energy Technology Data Exchange (ETDEWEB)

    Sturgess, C.; Johnson, R. [Alberta Research Council, Vegreville, AB (Canada). Environmental Technologies; Schubert, J. [EWMC Operations, Edmonton, AB (Canada)

    2007-07-01

    Edmonton's Waste Management Centre (EWMC) consists of a composting plant and a materials recovery facility, which accepts over 230,000 tonnes of residential waste per year. It removes 74,000 tonnes of residuals from these two facilities through a series of processing and refining stages and landfilling. Alternative waste management strategies are being considered to handle these residuals as the city's landfill site is approaching its maximum capacity. One option that takes advantage of the high calorific value of these residues is gasification. To ensure consistent and uniform gasification, the residuals have to be processed to a homogenous feedstock. This paper outlined the steps that were taken to characterize the four distinct residual streams, process them to a refuse-derived fluff and pelletize mixtures of these four streams with specific additives. The paper discussed pellet criteria; feedstock preparation; the physical and chemical properties of the fluff and pelletized mixture; pelletization; and, cost estimates of the processing stages involved. Last, a summary of the project was provided. The first phase of the project has been completed. The second phase of the project involves the development of the optimum business case, which includes further cost assessment of the feedstock preparation stage; leasing commercial scale equipment to establish efficiency and robustness of the process; assessing an alternative feeding system for the gasification system; and evaluating methanol production using a catalyst to convert the syngas to methanol. 5 tabs., 4 figs.

  19. Annex 34 : task 1 : analysis of biodiesel options : biomass-derived diesel fuels : final report

    Energy Technology Data Exchange (ETDEWEB)

    McGill, R [Oak Ridge National Laboratory, TN (United States); Aakko-Saksa, P; Nylund, N O [TransEnergy Consulting Ltd., Helsinki (Finland)

    2009-06-15

    Biofuels are derived from woody biomass, non-woody biomass, and organic wastes. The properties of vegetable oil feedstocks can have profound effects on the properties of the finished biodiesel product. However, all biodiesel fuels have beneficial effects on engine emissions. This report discussed the use of biodiesel fuels as replacements for part of the diesel fuel consumed throughout the world. Biodiesel fuels currently being produced from fatty acid esters today were reviewed, as well as some of the more advanced diesel replacement fuels. The report was produced as part of the International Energy Agency (IEA) Advanced Motor Fuels (AMF) Implementing Agreement Annex 34, and was divided into 14 sections: (1) an introduction, (2) biodiesel and biomass, (3) an explanation of biodiesel, (4) properties of finished biodiesel fuels, (5) exhaust emissions of finished biodiesel fuels and blends, (6) life-cycle emissions and energy, (7) international biodiesel (FAME) technical standards and specifications, (8) growth in production and use of biodiesel fuels, (9) biofuel refineries, (10) process technology, (11) development and status of biorefineries, (12) comparison of options to produce biobased diesel fuels, (13) barriers and gaps in knowledge, and (14) references. 113 refs., 37 tabs., 74 figs.

  20. Distributed renewable power from biomass and other waste fuels

    Science.gov (United States)

    Lyons, Chris

    2012-03-01

    The world population is continually growing and putting a burden on our fossil fuels. These fossil fuels such as coal, oil and natural gas are used for a variety of critical needs such as power production and transportation. While significant environmental improvements have been made, the uses of these fuels are still causing significant ecological impacts. Coal power production efficiency has not improved over the past thirty years and with relatively cheap petroleum cost, transportation mileage has not improved significantly either. With the demand for these fossil fuels increasing, ultimately price will also have to increase. This presentation will evaluate alternative power production methods using localized distributed generation from biomass, municipal solid waste and other waste sources of organic materials. The presentation will review various gasification processes that produce a synthetic gas that can be utilized as a fuel source in combustion turbines for clean and efficient combined heat and power. This fuel source can produce base load renewable power. In addition tail gases from the production of bio-diesel and methanol fuels can be used to produce renewable power. Being localized can reduce the need for long and costly transmission lines making the production of fuels and power from waste a viable alternative energy source for the future.

  1. Immobilization of radioactive waste sludge from spent fuel storage pool

    International Nuclear Information System (INIS)

    Pavlovic, R.; Plecas, I.

    1998-01-01

    In the last forty years, in FR Yugoslavia, as result of the research reactors' operation and radionuclides application in medicine, industry and agriculture, radioactive waste materials of the different categories and various levels of specific activities were generated. As a temporary solution, these radioactive waste materials are stored in the two hanger type interim storages for solid waste and some type of liquid waste packed in plastic barrels, and one of three stainless steal underground containers for other types of liquid waste. Spent fuel elements from nuclear reactors in the Vinca Institute have been temporary stored in water filled storage pool. Due to the fact that the water in the spent fuel elements storage pool have not been purified for a long time, all metallic components submerged in the water have been hardly corroded and significant amount of the sludge has been settled on the bottom of the pool. As a first step in improving spent fuel elements storage conditions and slowing down corrosion in the storage spent fuel elements pool we have decided to remove the sludge from the bottom of the pool. Although not high, but slightly radioactive, this sludge had to be treated as radioactive waste material. Some aspects of immobilisation, conditioning and storage of this sludge are presented in this paper. (author

  2. Addressing ethical considerations about nuclear fuel waste management

    International Nuclear Information System (INIS)

    Greber, M.A.

    1996-01-01

    Ethical considerations will be important in making decisions about the long-term management of nuclear fuel waste. Public discussions of nuclear fuel waste management are dominated by questions related to values, fairness, rights and responsibilities. To address public concerns, it is important to demonstrate that ethical responsibilities associated with the current management of the waste are being fulfilled. It is also important to show that our responsibilities to future generations can be met, and that ethical principles will be applied to the implementation of disposal. Canada's nuclear fuel waste disposal concept, as put forward in an Environmental Impact Statement by Atomic Energy of Canada Limited (AECL), is currently under public review by a Federal Environmental Assessment Panel. Following this review, recommendations will be made about the direction that Canada should take for the long-term management of this waste. This paper discusses the ethical principles that are seen to apply to geological disposal and illustrates how the Canadian approach to nuclear fuel waste management can meet the challenge of fulfilling these responsibilities. The author suggests that our ethical responsibilities require that adaptable technologies to site, design, construct, operate decommission and close disposal facilities should de developed. We cannot, and should not, present future generations from exercising control over what they inherit, nor control whether they modify or even reverse today's decisions if that is what they deem to be the right thing to do. (author)

  3. Environmental economics of lignin derived transport fuels

    NARCIS (Netherlands)

    Obydenkova, Svetlana V.; Kouris, Panos D.; Hensen, Emiel J. M.; Heeres, Hero J.; Boot, Michael D.

    2017-01-01

    This paper explores the environmental and economic aspects of fast pyrolytic conversion of lignin, obtained from 2G ethanol plants, to transport fuels for both the marine and automotive markets. Various scenarios are explored, pertaining to aggregation of lignin from several sites, alternative

  4. Fuel corrosion processes under waste disposal conditions

    International Nuclear Information System (INIS)

    Shoesmith, D.W.

    1999-09-01

    Under the oxidizing conditions likely to be encountered in the Yucca Mountain Repository, fuel dissolution is a corrosion process involving the coupling of the anodic dissolution of the fuel with the cathodic reduction of oxidants available within the repository. The oxidants potentially available to drive fuel corrosion are environmental oxygen, supplied by the transport through the permeable rock of the mountain and molecular and radical species produced by the radiolysis of available aerated water. The mechanism of these coupled anodic and cathodic reactions is reviewed in detail. While gaps in understanding remain, many kinetic features of these reactions have been studied in considerable detail, and a reasonably justified mechanism for fuel corrosion is available. The corrosion rate is determined primarily by environmental factors rather than the properties of the fuel. Thus, with the exception of increase in rate due to an increase in surface area, pre-oxidation of the fuel has little effect on the corrosion rate

  5. Fuel corrosion processes under waste disposal conditions

    Energy Technology Data Exchange (ETDEWEB)

    Shoesmith, D.W. [Univ. of Western Ontario, Dept. of Chemistry, London, Ontario (Canada)

    1999-09-01

    Under the oxidizing conditions likely to be encountered in the Yucca Mountain Repository, fuel dissolution is a corrosion process involving the coupling of the anodic dissolution of the fuel with the cathodic reduction of oxidants available within the repository. The oxidants potentially available to drive fuel corrosion are environmental oxygen, supplied by the transport through the permeable rock of the mountain and molecular and radical species produced by the radiolysis of available aerated water. The mechanism of these coupled anodic and cathodic reactions is reviewed in detail. While gaps in understanding remain, many kinetic features of these reactions have been studied in considerable detail, and a reasonably justified mechanism for fuel corrosion is available. The corrosion rate is determined primarily by environmental factors rather than the properties of the fuel. Thus, with the exception of increase in rate due to an increase in surface area, pre-oxidation of the fuel has little effect on the corrosion rate.

  6. Palm oil and derivatives: fuels or potential fuels?

    Directory of Open Access Journals (Sweden)

    Pioch Daniel

    2005-03-01

    Full Text Available Scientific and technical information including field trials about uses of palm oil as fuel has been available for more than half a century now. Several ways were investigated, from the simple mixture with petroleum Diesel fuel, to more sophisticated solutions. The quality of vegetable oils in natura as fuel is difficult to assess because of interferences between properties of the triacylglycerols – the main components – and those of the many minor components, their content varying significantly from sample to sample. A methodology set up at Cirad allowed to investigate separately natural triacylglycerols alone and the effect of minor components. In addition to these laboratory experiments, engine test at bench and field trials performed in palm oil producing countries, show that this oil is among the best oils as fuel; palm kernel oil whose chemical and physical properties are very close to those of the best of the series investigated, namely copra oil, should display also very interesting properties as Diesel biofuel. Both oils do require external adaptation of the engine when using an indirect injection type engine but even heavier adaptations for a direct injection model. Thus for use as Diesel fuel palm and palm kernel oils are suitable for captive fleets or for engine gensets, to balance the adaptation cost by a scale-up effect either on the number of identical engines or on the nominal vegetable oil consumption per set. Direct use of palm et palm kernel oils fits very well with technical and economical conditions encountered in remote areas. It is also possible to mix palm oil to Diesel fuel either as simple blend or as micro-emulsion. Out of the direct use, palm oil methyl or ethyl ester, often referred to as biodiesel, displays properties similar to those of petroleum Diesel fuel. This technical solution which is suitable to feed all kinds of standard compression ignited engines requires a chemical plant for carrying out the

  7. A preliminary evaluation of a combined tire- and refuse-derived fuel (TDF-RDF)

    Energy Technology Data Exchange (ETDEWEB)

    Stessel, R.I.; Amari, T.; Themelis, N.J.; Wearnick, I.K.

    1999-07-01

    In dense urban areas of the US, it is now becoming clear that waste management is far from economically-optimum. Even with the popularity of inexpensive land disposal, hauling and recycling costs are driving up the average waste bill. An historic option has been refuse-derived fuel, or RDF. Difficulties included low energy content and difficulty obtaining uniformity. Today, many resource-recovery technologies used in RDF are finding their way into materials recovery facilities (MRFs), some of which are reviving the automated processing of waste. Any MRF, automated or not, will have residue streams. Currently, one of the most significant problems is waste tires. Local options are difficult to locate in dense urban areas. As fuels, tires typically have energy contents considerably above those for which most solid-fuel combustors are designed, leading to thermal imbalances and various forms of failure. This paper suggests a new fuel that can be either co-fired with coal, or used in its own right in a combustor primarily designed for coal: TDF-RDF. A preliminary examination is undertaken of thermal and emissions characteristics, and possible costs for a few applications of the fuel. Immediately, TDF is already cleaner-burning than many coals, even in sulfur emissions. RDF has been widely-regarded as being similarly cleanly. Posited MRF residue streams should be still cleaner, and more consistent, than RDF. Overall, there is quite a potential for developing a fuel that would allow old coal powerplants in historic urban centers to be better neighbors, while helping with a few problems in municipal waste management.

  8. Radioactive wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Tomlinson, R.E.

    1975-01-01

    This symposium of 29 papers covers the following topics: overview; management and regulatory aspects; processing and solidification of low-level liquids; treatment of low-level solids; concentration and storage of high-level liquid wastes; and, solidification and storage of high level wastes. Selected papers are indexed separately

  9. A study on production of biodiesel using a novel solid oxide catalyst derived from waste.

    Science.gov (United States)

    Majhi, Samrat; Ray, Srimanta

    2016-05-01

    The issues of energy security, dwindling supply and inflating price of fossil fuel have shifted the global focus towards fuel of renewable origin. Biodiesel, having renewable origin, has exhibited great potential as substitute for fossil fuels. The most common route of biodiesel production is through transesterification of vegetable oil in presence of homogeneous acid or base or solid oxide catalyst. But, the economics of biodiesel is not competitive with respect to fossil fuel due to high cost of production. The vegetable oil waste is a potential alternative for biodiesel production, particularly when disposal of used vegetable oil has been restricted in several countries. The present study evaluates the efficacy of a low-cost solid oxide catalyst derived from eggshell (a food waste) in transesterification of vegetable oil and simulated waste vegetable oil (SWVO). The impact of thermal treatment of vegetable oil (to simulate frying operation) on transesterification using eggshell-derived solid oxide catalyst (ESSO catalyst) was also evaluated along with the effect of varying reaction parameters. The study reported that around 90 % biodiesel yield was obtained with vegetable oil at methanol/oil molar ratio of 18:1 in 3 h reaction time using 10 % ESSO catalyst. The biodiesel produced with ESSO catalyst from SWVO, thermally treated at 150 °C for 24 h, was found to conform with the biodiesel standard, but the yield was 5 % lower compared to that of the untreated oil. The utilization of waste vegetable oil along with waste eggshell as catalyst is significant for improving the overall economics of the biodiesel in the current market. The utilization of waste for societal benefit with the essence of sustainable development is the novelty of this work.

  10. Alpha-contaminated waste from reprocessing of nuclear fuel

    International Nuclear Information System (INIS)

    Sumner, W.

    1982-01-01

    The anticipated alpha-waste production rates from the Barnwell Nuclear Fuel Reprocessing plant is discussed. The estimated alpha-waste production rate from the 1500 metric ton/year plant is about 85,000 ft 3 /year at the 10 nCi/g limit. Most of this waste is estimated to come from the separation facility, and the major waste sources were cladding, which was 27%, and low-level contact-handled general process trash, which was estimated at 32% of the total. It was estimated that 45% of the waste was combustible and 72% of the waste was compactible. These characteristics could have a significant impact on the final volumes as disposed. Changing the alpha-waste limit from 10 nCi/g to 100 nCi/g was estimated to reduce the amount of alpha waste produced by about 20%. Again, the uncertainty in this value obviously has to be substantial. One has to recognize that these estimates were just that; they were not based on any operating experience. The total plutonium losses to waste, including the high-level waste, was estimated to be 1.5%. The cladding waste was estimated to be contaminated with alpha emitters to the extent of 10 4 to 10 5 nCi/g

  11. Impact of advanced fuel cycle options on waste management policies

    International Nuclear Information System (INIS)

    Gordelier, Stan; Cavedon, Jean-Marc

    2006-01-01

    OECD/NEA has performed a study on the impact of advanced fuel cycle options on waste management policies with 33 experts from 12 member countries, 1 non-member country and 2 international organizations. The study extends a series of previous ones on partitioning and transmutation (P and T) issues, focusing on the performance assessments for repositories of high-level waste (HLW) arising from advanced fuel cycles. This study covers a broader spectrum than previous studies, from present industrial practice to fully closed cycles via partially closed cycles (in terms of transuranic elements); 9 fuel cycle schemes and 4 variants. Elements of fuel cycles are considered primarily as sources of waste, the internal mass flows of each scheme being kept for the sake of mass conservation. The compositions, activities and heat loads of all waste flows are also tracked. Their impact is finally assessed on the waste repository concepts. The study result confirms the findings from the previous NEA studies on P and T on maximal reduction of the waste source term and maximal use of uranium resources. In advanced fuel cycle schemes the activity of the waste is reduced by burning first plutonium and then minor actinides and also the uranium consumption is reduced, as the fraction of fast reactors in the park is increased to 100%. The result of the repository performance assessments, analysing the effect of different HLW isotopic composition on repository performance and on repository capacity, shows that the maximum dose released to biosphere at any time in normal conditions remains, for all schemes and for all the repository concepts examined, well below accepted radiation protection thresholds. The major impact is on the detailed concept of the repositories, through heat load and waste volume. Advanced fuel cycles could allow a repository to cover waste produced from 5 to 20 times more electricity generation than PWR once-through cycle. Given the flexibility of the advanced fuel

  12. Estimate of the Sources of Plutonium-Containing Wastes Generated from MOX Fuel Production in Russia

    Energy Technology Data Exchange (ETDEWEB)

    Kudinov, K. G.; Tretyakov, A. A.; Sorokin, Yu. P.; Bondin, V. V.; Manakova, L. F.; Jardine, L. J.

    2002-02-26

    In Russia, mixed oxide (MOX) fuel is produced in a pilot facility ''Paket'' at ''MAYAK'' Production Association. The Mining-Chemical Combine (MCC) has developed plans to design and build a dedicated industrial-scale plant to produce MOX fuel and fuel assemblies (FA) for VVER-1000 water reactors and the BN-600 fast-breeder reactor, which is pending an official Russian Federation (RF) site-selection decision. The design output of the plant is based on a production capacity of 2.75 tons of weapons plutonium per year to produce the resulting fuel assemblies: 1.25 tons for the BN-600 reactor FAs and the remaining 1.5 tons for VVER-1000 FAs. It is likely the quantity of BN-600 FAs will be reduced in actual practice. The process of nuclear disarmament frees a significant amount of weapons plutonium for other uses, which, if unutilized, represents a constant general threat. In France, Great Britain, Belgium, Russia, and Japan, reactor-grade plutonium is used in MOX-fuel production. Making MOX-fuel for CANDU (Canada) and pressurized water reactors (PWR) (Europe) is under consideration in Russia. If this latter production is added, as many as 5 tons of Pu per year might be processed into new FAs in Russia. Many years of work and experience are represented in the estimates of MOX fuel production wastes derived in this report. Prior engineering studies and sludge treatment investigations and comparisons have determined how best to treat Pu sludges and MOX fuel wastes. Based upon analyses of the production processes established by these efforts, we can estimate that there will be approximately 1200 kg of residual wastes subject to immobilization per MT of plutonium processed, of which approximately 6 to 7 kg is Pu in the residuals per MT of Pu processed. The wastes are various and complicated in composition. Because organic wastes constitute both the major portion of total waste and of the Pu to be immobilized, the recommended treatment

  13. Estimate of the Sources of Plutonium-Containing Wastes Generated from MOX Fuel Production in Russia

    International Nuclear Information System (INIS)

    Kudinov, K. G.; Tretyakov, A. A.; Sorokin, Yu. P.; Bondin, V. V.; Manakova, L. F.; Jardine, L. J.

    2002-01-01

    In Russia, mixed oxide (MOX) fuel is produced in a pilot facility ''Paket'' at ''MAYAK'' Production Association. The Mining-Chemical Combine (MCC) has developed plans to design and build a dedicated industrial-scale plant to produce MOX fuel and fuel assemblies (FA) for VVER-1000 water reactors and the BN-600 fast-breeder reactor, which is pending an official Russian Federation (RF) site-selection decision. The design output of the plant is based on a production capacity of 2.75 tons of weapons plutonium per year to produce the resulting fuel assemblies: 1.25 tons for the BN-600 reactor FAs and the remaining 1.5 tons for VVER-1000 FAs. It is likely the quantity of BN-600 FAs will be reduced in actual practice. The process of nuclear disarmament frees a significant amount of weapons plutonium for other uses, which, if unutilized, represents a constant general threat. In France, Great Britain, Belgium, Russia, and Japan, reactor-grade plutonium is used in MOX-fuel production. Making MOX-fuel for CANDU (Canada) and pressurized water reactors (PWR) (Europe) is under consideration in Russia. If this latter production is added, as many as 5 tons of Pu per year might be processed into new FAs in Russia. Many years of work and experience are represented in the estimates of MOX fuel production wastes derived in this report. Prior engineering studies and sludge treatment investigations and comparisons have determined how best to treat Pu sludges and MOX fuel wastes. Based upon analyses of the production processes established by these efforts, we can estimate that there will be approximately 1200 kg of residual wastes subject to immobilization per MT of plutonium processed, of which approximately 6 to 7 kg is Pu in the residuals per MT of Pu processed. The wastes are various and complicated in composition. Because organic wastes constitute both the major portion of total waste and of the Pu to be immobilized, the recommended treatment of MOX-fuel production waste is

  14. Spent fuel and high-level radioactive waste storage

    International Nuclear Information System (INIS)

    Trigerman, S.

    1988-06-01

    The subject of spent fuel and high-level radioactive waste storage, is bibliographically reviewed. The review shows that in the majority of the countries, spent fuels and high-level radioactive wastes are planned to be stored for tens of years. Sites for final disposal of high-level radioactive wastes have not yet been found. A first final disposal facility is expected to come into operation in the United States of America by the year 2010. Other final disposal facilities are expected to come into operation in Germany, Sweden, Switzerland and Japan by the year 2020. Meanwhile , stress is placed upon the 'dry storage' method which is carried out successfully in a number of countries (Britain and France). In the United States of America spent fuels are stored in water pools while the 'dry storage' method is still being investigated. (Author)

  15. Environmental economics of lignin derived transport fuels.

    Science.gov (United States)

    Obydenkova, Svetlana V; Kouris, Panos D; Hensen, Emiel J M; Heeres, Hero J; Boot, Michael D

    2017-11-01

    This paper explores the environmental and economic aspects of fast pyrolytic conversion of lignin, obtained from 2G ethanol plants, to transport fuels for both the marine and automotive markets. Various scenarios are explored, pertaining to aggregation of lignin from several sites, alternative energy carries to replace lignin, transport modalities, and allocation methodology. The results highlight two critical factors that ultimately determine the economic and/or environmental fuel viability. The first factor, the logistics scheme, exhibited the disadvantage of the centralized approach, owing to prohibitively expensive transportation costs of the low energy-dense lignin. Life cycle analysis (LCA) displayed the second critical factor related to alternative energy carrier selection. Natural gas (NG) chosen over additional biomass boosts well-to-wheel greenhouse gas emissions (WTW GHG) to a level incompatible with the reduction targets set by the U.S. renewable fuel standard (RFS). Adversely, the process' economics revealed higher profits vs. fossil energy carrier. Copyright © 2017 The Author(s). Published by Elsevier Ltd.. All rights reserved.

  16. Preliminary waste acceptance criteria for the ICPP spent fuel and waste management technology development program

    International Nuclear Information System (INIS)

    Taylor, L.L.; Shikashio, R.

    1993-09-01

    The purpose of this document is to identify requirements to be met by the Producer/Shipper of Spent Nuclear Fuel/High-LeveL Waste SNF/HLW in order for DOE to be able to accept the packaged materials. This includes defining both standard and nonstandard waste forms

  17. Concerning enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material

    International Nuclear Information System (INIS)

    1988-01-01

    The Atomic Safety Commission of Japan, after examining a report submitted by the Science and Technology Agency concerning the enactment of regulations on burying of waste of nuclear fuel material or waste contaminated with nuclear fuel material, has approved the plan given in the report. Thus, laws and regulations concerning procedures for application for waste burying business, technical standards for implementation of waste burying operation, and measures to be taken for security should be established to ensure the following. Matters to be described in the application for the approval of such business and materials to be attached to the application should be stipulated. Technical standards concerning inspection of waste burying operation should be stipulated. Measures to be taken for the security of waste burying facilities and security concerning the transportation and disposal of nuclear fuel material should be stipulated. Matters to be specified in the security rules should be stipulated. Matters to be recorded by waste burying business operators, measures to be taken to overcome dangers and matters to be reported to the Science and Technology Agency should be stipulated. (Nogami, K.)

  18. Transport of nuclear used fuel and waste materials

    Energy Technology Data Exchange (ETDEWEB)

    Neau, H.J. [World Nuclear Transport Institute, London (United Kingdom)

    2015-07-01

    20 millions consignments of radioactive materials are routinely transported annually on public roads, railways and ships. 5% of these are nuclear fuel cycle related. International Atomic Energy Agency Regulations have been in force since 1961. The sector has an excellent safety record spanning over 50 years. Back end transport covers the operations concerned with spent fuel that leaves reactors and wastes. Since 1971, there have been 70,000 shipments of used fuel (i.e. over 80,000 tonnes) with no damage to property or person. The excellent safety record spanning over 50 years praised every year by the General Conference of the International Atomic Energy Agency. More than 200 sea voyages over a distance of more than 8 million kilometres of transport of used fuel or high-level wastes.

  19. Fuel cycle and waste management demonstration in the IFR Program

    International Nuclear Information System (INIS)

    Lineberry, M.J.; Phipps, R.D.; Benedict, R.W.; Laidler, J.J.; Battles, J.E.; Miller, W.E.

    1992-01-01

    Argonne's National Laboratory's Integral Fast Reactor (IFR) is the main element in the US advanced reactor development program. A unique fuel cycle and waste process technology is being developed for the IFR. Demonstration of this technology at engineering scale will begin within the next year at the EBR-II test facility complex in Idaho. This paper describes the facility being readied for this demonstration, the process to be employed, the equipment being built, and the waste management approach

  20. Management of radioactive fuel wastes: the Canadian disposal program

    International Nuclear Information System (INIS)

    Boulton, J.

    1978-10-01

    This report describes the research and development program to verify and demonstrate the concepts for the safe, permanent disposal of radioactive fuel wastes from Canadian nuclear reactors. The program is concentrating on deep underground disposal in hard-rock formations. The nature of the radioactive wastes is described, and the options for storing, processing, packaging and disposing of them are outlined. The program to verify the proposed concept, select a suitable site and to build and operate a demonstration facility is described. (author)

  1. Species redistribution during solidification of nuclear fuel waste metal castings

    Energy Technology Data Exchange (ETDEWEB)

    Naterer, G F; Schneider, G E [Waterloo Univ., ON (Canada)

    1994-12-31

    An enthalpy-based finite element model and a binary system species redistribution model are developed and applied to problems associated with solidification of nuclear fuel waste metal castings. Minimal casting defects such as inhomogeneous solute segregation and cracks are required to prevent container corrosion and radionuclide release. The control-volume-based model accounts for equilibrium solidification for low cooling rates and negligible solid state diffusion for high cooling rates as well as intermediate conditions. Test problems involving nuclear fuel waste castings are investigated and correct limiting cases of species redistribution are observed. (author). 11 refs., 1 tab., 13 figs.

  2. Spent fuel characterization for the commercial waste and spent fuel packaging program

    International Nuclear Information System (INIS)

    Fish, R.L.; Davis, R.B.; Pasupathi, V.; Klingensmith, R.W.

    1980-03-01

    This document presents the rationale for spent fuel characterization and provides a detailed description of the characterization examinations. Pretest characterization examinations provide quantitative and qualitative descriptions of spent fuel assemblies and rods in their irradiated conditions prior to disposal testing. This information is essential in evaluating any subsequent changes that occur during disposal demonstration and laboratory tests. Interim examinations and post-test characterization will be used to identify fuel rod degradation mechanisms and quantify degradation kinetics. The nature and behavior of the spent fuel degradation will be defined in terms of mathematical rate equations from these and laboratory tests and incorporated into a spent fuel performance prediction model. Thus, spent fuel characterization is an essential activity in the development of a performance model to be used in evaluating the ability of spent fuel to meet specific waste acceptance criteria and in evaluating incentives for modification of the spent fuel assemblies for long-term disposal purposes

  3. Waste cooking oil as source for renewable fuel in Romania

    Science.gov (United States)

    Allah, F. Um Min; Alexandru, G.

    2016-08-01

    Biodiesel is non-toxic renewable fuel which has the potential to replace diesel fuel with little or no modifications in diesel engine. Waste cooking oil can be used as source to produce biodiesel. It has environmental and economic advantages over other alternative fuels. Biodiesel production from transesterification is affected by water content, type f alcohol, catalyst type and concentration, alcohol to oil ratio, temperature, reaction rate, pH, free fatty acid (FFA) and stirrer speed. These parameters and their effect on transesterification are discussed in this paper. Properties of biodiesel obtained from waste cooking oil are measured according to local standards by distributor and their comparison with European biodiesel standard is also given in this paper. Comparison has shown that these properties lie within the limits of the EN 14214 standard. Furthermore emission performance of diesel engine for biodiesel-diesel blends has resulted in reduction of greenhouse gas emissions. Romanian fuel market can ensure energy security by mixing fuel share with biodiesel produced from waste cooking oil. Life cycle assessment of biodiesel produced from waste cooking oil has shown its viability economically and environmentally.

  4. Strategy for management of investigation-derived waste

    International Nuclear Information System (INIS)

    Russell, Laura E.; Hopkins, Gregory G.; Smith, Edward H.; Innis, Pamela S.; Stewart, Robert K.

    1992-01-01

    Large quantities of wastes containing hazardous and/or radiological constituents are being generated as part of the field investigations at the U.S. Department of Energy's Hanford Site in Richland, Washington. A problem exists with the integration of regulations under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980, the Resource Conservation and Recovery Act of 1976, the Washington Hazardous Waste Management Act of 1976, and the Washington Administrative Code Waste management criteria under these regulations need to be consolidated into a single, acceptable management approach that can reasonably be applied to the Hanford Site cleanup effort. In response to this need, a Technical Task Team of representatives from the Washington Department of Ecology, U.S. Environmental Protection Agency, U.S. Department of Energy, and Westinghouse Hanford Company was organized. As a result of nearly two years of negotiations the Technical Task Team produced a specific waste management plan which is presented in the paper as the Strategy for Management of Investigation-Derived Waste. The paper outlines the strategy for handling and storing investigation-derived waste within a given operable unit until a waste unit-specific Record of Decision can be issued. To date, the Strategy for Management of Investigation-Derived Waste has not been finalized. However, formal approval by the U.S. Environmental Protection Agency is expected soon and will result in implementation of the management strategy at waste sites in which they have been identified as the lead regulatory agency. Negotiations with the Washington State Department of Ecology are ongoing. At the time of this writing, it is uncertain what the Washington State Department of Ecology's position will be regarding investigation-derived waste. Both the U.S. Environmental Protection Agency and the U.S. Department of Energy believe the Strategy for Management of Investigation-Derived Waste to be

  5. Management of radioactive wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1976-01-01

    The increased emphasis in many countries on the development and utilization of nuclear power is leading to an expansion of all sectors of the nuclear fuel cycle, giving rise to important policy issues and radioactive-waste management requirements. Consequently, the IAEA and the Nuclear Energy Agency of OECD felt that it would be timely to review latest technology for the management of the radioactive wastes arising from nuclear fuel cycle facilities, to identify where important advances have been made, and to indicate those areas where further technological development is needed. Beginning in 1959, the IAEA, either by itself or jointly with OECD/NEA has held seven international symposia on the management of radioactive wastes. The last symposium, on the management of radioactive wastes from fuel reprocessing, was held jointly by the IAEA and OECD/NEA in Paris in November 1972. An objective of the 1976 symposium was to update the information presented at the previous symposia with the latest technological developments and thinking regarding the management and disposal of all categories of radioactive wastes. Consequently, although the scope of the symposium was rather broad, attention was focussed on operational experience and progress in unresolved areas of radioactive waste management. The programme dealt primarily with the solidification of liquid radioactive wastes and disposal of the products, especially the high-level fission products and actinide-containing waste from fuel reprocessing. Other topics covered policy and planning, treatment of hulls and solvent, management of plutonium-contaminated waste, and removal of gaseous radionuclides. The major topic of interest was the current state of the technology for the reduction and incorporation of the high-level radioactive liquid from fuel reprocessing into solid forms, such as calcines, glasses or ceramics, for safe interim storage and eventual disposal. The approaches to vitrification ranged from two stage

  6. Estimate of the Sources of Plutonium-Containing Wastes Generated from MOX Fuel Production in Russia

    International Nuclear Information System (INIS)

    Kudinov, K.G.; Tretyakov, A.A.; Sorokin, Y.P.; Bondin, V.V.; Manakova, L.F.; Jardine, L.J.

    2001-01-01

    In Russia, mixed oxide (MOX) fuel is produced in a pilot facility ''Paket'' at ''MAYAK'' Production Association. The Mining-Chemical Combine (MCC) has developed plans to design and build a dedicated industrial-scale plant to produce MOX fuel and fuel assemblies (FA) for VVER-1000 water reactors and the BN-600 fast-breeder reactor, which is pending an official Russian Federation (RF) site-selection decision. The design output of the plant is based on production capacity of 2.75 tons of weapons plutonium per year to produce the resulting fuel assemblies: 1.25 tons for the BN-600 reactor FAs and the remaining 1.5 tons for VVER-1000 FAs. It is likely the quantity of BN-600 FAs will be reduced in actual practice. The process of nuclear disarmament frees a significant amount of weapons plutonium for other uses, which, if unutilized, represents a constant general threat. In France, Great Britain, Belgium, Russia, and Japan, reactor-grade plutonium is used in MOX-fuel production. Making MOX-fuel for CANDU (Canada) and pressurized water reactors (PWR) (Europe) is under consideration Russia. If this latter production is added, as many as 5 tons of Pu per year might be processed into new FAs in Russia. Many years of work and experience are represented in the estimates of MOX fuel production wastes derived in this report. Prior engineering studies and sludge treatment investigations and comparisons have determined how best to treat Pu sludges and MOX fuel wastes. Based upon analyses of the production processes established by these efforts, we can estimate that there will be approximately 1200 kg of residual wastes subject to immobilization per MT of plutonium processed, of which approximately 6 to 7 kg is Pu in the residuals per MT of Pu processed. The wastes are various and complicated in composition. Because organic wastes constitute both the major portion of total waste and of the Pu to be immobilized, the recommended treatment of MOX-fuel production waste is incineration

  7. Upgrading of waste oils into transportation fuels using hydrotreating technologies

    Directory of Open Access Journals (Sweden)

    Sudipta De

    2014-12-01

    Full Text Available The generation of organic waste continues to increase, causing severe environmental pollution. Waste valorization is currently an emerging technology that can address this problem with an extra benefit of producing a range of valued products. In this contribution, we report the current developments in hydrotreating technologies for upgrading waste oil fractions into usable transportation fuels. Particular focus is given on the catalysts selection for a general hydroprocessing technique as well as the competitive role of those catalysts in hydrotreating and hydrocracking processes.

  8. Ceramic waste forms for fuel-containing masses at Chernobyl

    International Nuclear Information System (INIS)

    Oversby, V.M.

    1994-05-01

    The fuel materials originally in the core of the Chernobyl Unit 4 reactor are now present within the Ukrytie in three major forms: (1) very fine particles of fuel dispersed as dust (about 10 tonnes), (2) fragments of the destroyed core, and (3) lavas containing fuel, cladding, and other materials. All of these materials will need to be immobilized into waste forms suitable for final disposal. We propose a ceramic waste form system that could accommodate all three waste types with a single set of processing equipment. The waste form would include the mineral zirconolite for immobilization of actinide materials (including uranium), perovskite, nepheline, spinel, and other phases as dictated by the chemistry of the lava masses. Waste loadings as high as 50% U can be achieved if pyrochlore, a close relative of zirconolite, is used as the U host. The ceramic immobilization could be achieved with low additions of inert chemicals to minimize the final disposal volume while ensuring a durable product. The sequence of processing would be to collect and immobilize the fuel dust first. This material will require minimal preprocessing and will provide experience in the handling of the fuel materials. Core fragments would be processed next, using a cryogenic crushing stage to reduce the size prior to adding ceramic additives. The lavas would be processed last, which is compatible with the likely sequence of availability of materials and with the complexity of the operations. The lavas will require more adjustment of chemical additive composition than the other streams to ensure that the desired phases are produced in the waste form

  9. Comparative life cycle analysis of cement made with coal vs hazardous waste as fuel

    International Nuclear Information System (INIS)

    Kelly, K.E.; Beeh, J.

    1994-01-01

    The purpose of this life cycle analysis (LCA) is to compare the life cycle of cement made with coal, the standard fuel used in a cement kiln, versus cement made with hazardous waste-derived fuels. The intent of the study is to determine whether the use of hazardous waste as a fuel in the production of cement could result in an increase in detrimental effects to either health or environment. Those evaluated for potential adverse effect include cement kiln workers, waste transporters, and consumers using the final product for private use. The LCA stages included all the processes involved with cement, including raw materials acquisition, transportation, manufacturing, packaging, distribution, use, recycling, and disposal. The overall conclusions of the LCA are that use of waste fuels instead of coal to make cement: (1) does not increase, and may reduce, the concentration of contaminants in the cement product due to the reduction or elimination of the use of coal; (2) reduces or eliminates use of non-renewable fossil fuels, such as coal, as well as the environmental damage and impacts associated with coal mining; (3) provides a more environmentally beneficial means of destroying many types of wastes than alternative treatment methods, including incineration, thus decreasing the need for waste treatment facilities and capacity; (4) decreases overall emissions during transportation but may increase the overall consequences of accidents or spills; (5) results in cement product which may be packaged, transported, distributed and used in the same manner as cement product made with coal; (6) lowers the cost of cement production; and (7) overall appears to result in less health and environmental impacts

  10. Liquid waste treatment at plutonium fuels fabrication facility, 2

    International Nuclear Information System (INIS)

    Matsumoto, Ken-ichi; Itoh, Ichiroh; Ohuchi, Jin; Miyo, Hiroaki

    1974-01-01

    The economics in the management of the radioactive liquid waste from Plutonium Fuels Fabrication Facility with sludge-blanket type flocculators has been evaluated. (1) Cost calculation: The cost of chemicals and electricity to treat 1 cubic meter of liquid waste is about 876 yen, while the total operating cost is 250 thousand yen per cubic meter in the case of 140 m 3 /year treatment. These figures are much higher than those for ordinary wastes, due to the particular operation against plutonium. (2) Proposal of the closed system for liquid waste treatment at PFFF: In the case of a closed system using evaporator, ion exchange column and rotary-kiln calciner, the operating cost is estimated at 40 thousand yen per cubic meter of liquid waste. Final radioactivity of treated liquid is below 10 -8 micro curies/ml. (Mori, K.)

  11. International trade and waste and fuel managment issue, 2006

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2006-01-15

    The focus of the January-February issue is on international trade and waste and fuel managment. Major articles/reports in this issue include: HLW management in France, by Michel Debes, EDF, France; Breakthroughs from future reactors, by Jacques Bouchard, CEA, France; 'MOX for peace' a reality, by Jean-Pierre Bariteau, AREVA Group, France; Swedish spent fuel and radwaste, by Per H. Grahn and Marie Skogsberg, SKB, Sweden; ENC2005 concluding remarks, by Larry Foulke, 'Nuclear Technology Matters'; Fuel crud formation and behavior, by Charles Turk, Entergy; and, Plant profile: major vote of confidence for NP, by Martti Katka, TVO, Finland.

  12. Program for responsible and safe disposal of spent fuel elements and radioactive wastes (National disposal program)

    International Nuclear Information System (INIS)

    2015-01-01

    The contribution covers the following topics: fundamentals of the disposal policy; amount of radioactive wastes and prognosis; disposal of radioactive wastes - spent fuel elements and wastes from waste processing, radioactive wastes with low heat production; legal framework of the nuclear waste disposal in Germany; public participation, cost and financing.

  13. International trade and waste and fuel managment issue, 2007

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2007-01-15

    The focus of the January-February issue is on international trade and waste and fuel managment. Major articles/reports in this issue include: New plants with high safety and availability, by Bill Poirier, Westinghouse Electric Company; Increased reliability and competitiveness, by Russell E. Stachowski, GE Energy, Nuclear; Fuel for long-term supply of nuclear power, by Kumiaki Moriya, Hitachi, Ltd., Japan; Super high burnup fuel, By Noboru Itagaki and Tamotsu Murata, Nuclear Fuel Industries LTD., Japan; Zero fuel failures by 2010, by Tom Patten, AREVA NP Inc.; Decommissioning opportunities in the UK, by David Brown and William Thorn, US Department of Commerce; Industry's three challenges, by Dale E. Klein, US Nuclear Regulatory Commission; and, A step ahead of the current ABWR's, compiled by Claire Zurek, GE Energy.

  14. Waste Not, Want Not: Lactate Oxidation Fuels the TCA Cycle.

    Science.gov (United States)

    Martínez-Reyes, Inmaculada; Chandel, Navdeep S

    2017-12-05

    Previous studies have demonstrated that mitochondrial respiration is essential for tumorigenesis. Hui et al. (2017) and Faubert et al. (2017) demonstrate that lactate, traditionally viewed as a waste product of anaerobic and aerobic glycolysis, is a major carbon source to fuel the mitochondrial TCA cycle in normal tissue and in tumors. Copyright © 2017 Elsevier Inc. All rights reserved.

  15. Radioactive wastes and spent fuels management in Argentina

    International Nuclear Information System (INIS)

    Maset, Elvira R.

    2006-01-01

    CNEA was created in 1950 and since then has carried out research and development activities, production of radioisotopes, medical and industrial applications, and those activities related with the nuclear fuel cycle, including the operation of two nuclear power stations. More ever, different public and private institutions use radioactive materials in medical, industrial and research activities. These activities generate different types of radioactive waste, desuse sealed sources and spent fuel. The management of radioactive waste of all types produced in the country, as the spent nuclear fuel of power and research reactors and the used radioactive sources was always and it is at present a CNEA's responsibility. In February 2003, according to the Law No. 25.018, called 'Management of Radioactive Waste Regimen', the 'Radioactive Waste Management National Programme' was created by CNEA to fulfill the institutional functions and responsibilities established in the Law, in order to guarantee the safe management of radioactive waste according to the regulations established by the Argentine Nuclear Regulatory Agency and to the legislation in force. (author) [es

  16. Radioactive Wastes Generated From JAERI Partitioning-Transmutation Fuel Cycle

    International Nuclear Information System (INIS)

    Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

    2003-01-01

    Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI's processes. Long-lived radionuclides such as 14 C and 59 Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (authors)

  17. Geoscience research for the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Whitaker, S.H.

    1987-01-01

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

  18. Save energy: using cellulosic wastes for fuel and food

    Energy Technology Data Exchange (ETDEWEB)

    Gupta, Y.P.

    The development of technology to convert biomass into liquid fuels for transportation uses could reduce dependence on oil imports and make India's economy more stable. The enthusiasm for alcohol fuels, however, competes with food growing. Efforts to find unconventional sources of protein to deal with the malnutrition that accompanies overpopulation also focus on cellulosic wastes and micro-organisms that break down cellulose. India's scientists are looking at microbial proteins from cellulose wastes as a cattle and protein feed. Although micro-organisms are rich and balanced in amino acids, there are some health problems in human consumption of microbial food which need to be resolved before they can provide both economic fuel and food for developing countries.

  19. RTR spent fuel treatment and final waste storage

    International Nuclear Information System (INIS)

    Thomasson, J.

    2000-01-01

    A number of RTR operators have chosen in the past to send their spent fuel to the US in the framework of the US take back program. However, this possibility ends as of May 12th, 2006. 3 different strategies are left for managing RTR spent fuel: extended storage, direct disposal and treatment-conditioning through reprocessing. Whilst former strategies raise a number of uncertainties, the latter already offers a management solution. It features two advantages. It benefits from the long experience of existing flexible industrial facilities from countries like France. Secondly, it offers a dramatic volume reduction of the ultimate waste to be stored under well-characterized, stable and durable forms. RTR spent fuel management through reprocessing-conditioning offers a durable management solution that can be fully integrated in whatever global radioactive waste management policy, including ultimate disposal

  20. Source term for the bounding assessment of the Canadian nuclear fuel waste disposal concept

    International Nuclear Information System (INIS)

    Flavelle, P.

    1996-02-01

    This is the second in a series to derive the bounds of the post-closure hazard of the Canadian nuclear fuel waste disposal concept, based on the premise that it is unnecessary to predict accurately the real hazard if the bounding hazard can be shown to be acceptable. In this report a reference used (Bruce A fuel, 865 GJ/kgU average burnup) is used to derive the source term for contaminant releases from the emplacement canisters. This requires development of a container failure function which defines the age of the fuel when the canister is perforated and flooded. The source term is expressed as the time-dependent fractional release rate from the used fuel or as the time-dependent contaminant concentrations in the canister porewater. It is derived as the superposition of an instant release, comprising the upper bound of the gap and grain boundary inventory in the used fuel, and the long-term dissolution of the used fuel matrix. Several dissolution models (stoichiometric dissolution/preferential leaching) under different conditions (matrix solubility limited/ unlimited; oxidizing/ reducing solubility limits; groundwater flow/ no flow) are evaluated and the one resulting in the highest release rate/ highest porewater concentration is adopted as the bounding case. Comparisons between the models are made on the basis of the potential ingestion hazard of the canister porewater, to account for differences in the hazard of different radionuclides. (author) 20 refs., 4 tabs., 9 figs

  1. The present Swedish nuclear fuel and waste position in perspective

    International Nuclear Information System (INIS)

    Svenke, E.

    1983-01-01

    In Sweden current efforts are focussed on research and development of the management of all types of radioactive residues and on industrial projects for the implementation of a complete programme for the back-end of the fuel cycle, where, in fact, international commercial services scarcely exist. Another reason for this priority is the need to allay public anxiety on the subject. The paper describes the policy, planning, and development of the Swedish nuclear back-end as well as its organization and financing. In Sweden the licensee of a nuclear power facility assumes direct responsibility, technically and financially, for the nuclear waste he generates. To cover future costs with respect to the back-end, the utilities pay to the State a fee related to their production of nuclear electricity. The fee is kept in a fund administered by the State through an authority, the 'National Board for Spent Nuclear Fuel'. The technical implementation programme comprises a sea transportation system to be operational by the end of 1982 and a central facility for intermediate storage of spent reactor fuel to be operational by 1985. The third step in the Swedish waste programme is a central final storage facility for reactor wastes other than spent fuel (planned to be in operation by 1988). Broad research and development work is going on in a deep underground system for the isolation of highly active and long-lived wastes. A rock drilling programme is being carried out at several places and is planned to continue for a period of approximately ten years. Encapsulation of waste and the properties of buffer materials are being studied. The paper stresses the importance of achieving generally and multi-nationally accepted guidelines for waste isolation systems and also of proper demonstration of the performance of the various parts of such systems

  2. Modules for estimating solid waste from fossil-fuel technologies

    International Nuclear Information System (INIS)

    Crowther, M.A.; Thode, H.C. Jr.; Morris, S.C.

    1980-10-01

    Solid waste has become a subject of increasing concern to energy industries for several reasons. Increasingly stringent air and water pollution regulations result in a larger fraction of residuals in the form of solid wastes. Control technologies, particularly flue gas desulfurization, can multiply the amount of waste. With the renewed emphasis on coal utilization and the likelihood of oil shale development, increased amounts of solid waste will be produced. In the past, solid waste residuals used for environmental assessment have tended only to include total quantities generated. To look at environmental impacts, however, data on the composition of the solid wastes are required. Computer modules for calculating the quantities and composition of solid waste from major fossil fuel technologies were therefore developed and are described in this report. Six modules have been produced covering physical coal cleaning, conventional coal combustion with flue gas desulfurization, atmospheric fluidized-bed combustion, coal gasification using the Lurgi process, coal liquefaction using the SRC-II process, and oil shale retorting. Total quantities of each solid waste stream are computed together with the major components and a number of trace elements and radionuclides

  3. Long-term α-hazard of high activity waste from nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Girardi, F.; Bertozzi, G.

    1974-01-01

    The concentration and decay of α-emitters in high activity waste arising from spent nuclear fuel reprocessing was calculated under specified reference conditions. An attempt to evaluate the long-term hazard of such waste is being made by applying the ''barrier'' approach derived from reactor safety studies. Four barriers were identified, which could be evaluated in a probabilistic way by taking into account the great uncertainties present in each of them. The barriers are: 1) quality of the segregation afforded by deep geological formations, 2) stability of conditioned waste (chemical and physical), 3) retention by immediate surrounding, 4) distribution pattern of actinides in the environment. The analysis of a fictional accident showed that the uncertainties connected with the evaluation of the barriers' value are rather large. Additional studies particularly on the stability of conditioned waste and ecological properties of the environment towards actinides, would considerably improve our knowledge of the value of the barrier system. Chemical separation of actinides from high activity waste would be an additional option of undoubted value for the disposal of high activity waste. Its value for the overall safety of the entire waste inventory depends on many factors which need better evaluation, such as safety of the disposal of the separated actinides and the amount and quality of the additional waste generated by the separation process. An analysis of various levels of possible separations suggests that a reasonable target might be: Pu, Am and Cm, decontamination factor 10 3 ; Np, coextraction with U and Pu with a 90% yield

  4. Fuel Cells in the Waste-to-Energy Chain Distributed Generation Through Non-Conventional Fuels and Fuel Cells

    CERN Document Server

    McPhail, Stephen J; Moreno, Angelo

    2012-01-01

    As the availability of fossils fuels becomes more limited, the negative impact of their consumption becomes an increasingly relevant factor in our choices with regards to primary energy sources. The exponentially increasing demand for energy is reflected in the mass generation of by-products and waste flows which characterize current society’s development and use of fossil sources. The potential for recoverable material and energy in these ever-increasing refuse flows is huge, even after the separation of hazardous constituent elements, allowing safe and sustainable further exploitation of an otherwise 'wasted' resource.  Fuel Cells in the Waste-to-Energy Chain explores the concept of waste-to-energy through a 5 step process which reflects the stages during the transformation of  refuse flows to a valuable commodity such as clean energy. By providing selected, integrated alternatives to the current centralized, wasteful, fossil-fuel based infrastructure, Fuel Cells in the Waste-to-Energy Chain explores ho...

  5. Municipal Solid Waste Combustion : Fuel Testing and Characterization : Task 1 Report, May 30, 1990-October 1, 1990.

    Energy Technology Data Exchange (ETDEWEB)

    Bushnell, Dwight J.; Canova, Joseph H.; Dadkhah-Nikoo, Abbas.

    1990-10-01

    The objective of this study is to screen and characterize potential biomass fuels from waste streams. This will be accomplished by determining the types of pollutants produced while burning selected municipal waste, i.e., commercial mixed waste paper residential (curbside) mixed waste paper, and refuse derived fuel. These materials will be fired alone and in combination with wood, equal parts by weight. The data from these experiments could be utilized to size pollution control equipment required to meet emission standards. This document provides detailed descriptions of the testing methods and evaluation procedures used in the combustion testing and characterization project. The fuel samples will be examined thoroughly from the raw form to the exhaust emissions produced during the combustion test of a densified sample.

  6. Sampling, characterisation and processing of solid recovered fuel production from municipal solid waste: An Italian plant case study.

    Science.gov (United States)

    Ranieri, Ezio; Ionescu, Gabriela; Fedele, Arcangela; Palmieri, Eleonora; Ranieri, Ada Cristina; Campanaro, Vincenzo

    2017-08-01

    This article presents the classification of solid recovered fuel from the Massafra municipal solid waste treatment plant in Southern Italy in compliancy with the EN 15359 standard. In order to ensure the reproducibility of this study, the characterisation methods of waste input and output flow, the mechanical biological treatment line scheme and its main parameters for each stage of the processing chain are presented in details, together with the research results in terms of mass balance and derived fuel properties. Under this study, only 31% of refused municipal solid waste input stream from mechanical biological line was recovered as solid recovered fuel with a net heating value (NC=HV) average of 15.77 MJ kg -1 ; chlorine content average of 0.06% on a dry basis; median of mercury solid recovered fuel produced meets the European Union standard requirements and can be classified with the class code: Net heating value (3); chlorine (1); mercury (1).

  7. Labeling of the spent fuel waste package

    International Nuclear Information System (INIS)

    Culbreth, W.G.; Chagari, A.K.

    1992-01-01

    This paper reports that the containers used to store spent fuel in an underground repository must meet federal guidelines that call for unique labels that identify the contents and processing history. Existing standards in the nuclear power industry and relevant ASME/ANSI codes have been reviewed for possible application to the spent-fuel container labeling. An Array of labeling techniques were found that include recommendations for: fonts, word spacing, color combinations, label materials and mounting methods, placement, and content. The use of bar code, optical character recognition, and RF labels were also studied to meet the requirement that the container labels be consistent with the methods used to maintain the repository records

  8. Support of the radioactive waste treatment nuclear fuel fabrication facility

    International Nuclear Information System (INIS)

    Park, H.H.; Han, K.W.; Lee, B.J.; Shim, G.S.; Chung, M.S.

    1982-01-01

    Technical service of radioactive waste treatment in Daeduck Engineering Center includes; 1) Treatment of radioactive wastes from the nuclear fuel fabrication facility and from laboratories. 2) Establishing a process for intermediate treatment necessary till the time when RWTF is in completion. 3) Technical evaluation of unit processes and equipments concerning RWTF. About 35 drums (8 m 3 ) of solid wastes were treated and stored while more than 130 m 3 of liquid wastes were disposed or stored. A process with evaporators of 10 1/hr in capacity, a four-stage solvent washer, storage tanks and disposal system was designed and some of the equipments were manufactured. Concerning RWTF, its process was reviewed technically and emphasis were made on stability of the bituminization process against explosion, function of PAAC pump, decontamination, and finally on problems to be solved in the comming years. (Author)

  9. Fuel isolation research for the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    1982-06-01

    This document is intended to give a broad outline of the Fuel Isolatikn program and to indicate how this program fits into the overall framework of the Canadian Nuclear Fuel Waste Management Program. Similar activities in other countries are described, and the differences in philosophy behind these and the Canadian program are highlighted. A program plan is presented that outlines the development of research programs that contribute to the safety assessment of the disposal concept and the development of technology required for selection and optimization of a feasible fuel isolation system. Some indication of the work that might take place beyond concept assessment, at the end of the decade, is also given. The current program is described in some detail, with emphasis on what the prkgram has achieved to date and hopes to achieve in the future for the concept assessment phase of the waste management program. Finally, some major capital facilities associated with the fuel isolation program are described

  10. USA: energy policy and spent fuel and waste management

    International Nuclear Information System (INIS)

    Petroll, M.R.

    2001-01-01

    The new US administration under President Bush has shifted political weights in the country's energy policy. The policy pursued by the Clinton administration, which had been focused strongly on energy efficiency and environmental protection, will be revoked in a number of points, and the focus instead will now be on economics and continuity of supply, also against the backdrop of the current power supply crisis in California. However, it is more likely that fossil-fired generating capacity will be expanded or added than new nuclear generating capacity. As far as the policy of managing radioactive waste is concerned, no fast and fundamental changes are expected. Low-level waste arising in medicine, research, industry, and nuclear power plants will be stored in a number of shallow ground burial facilities also involving more than one federal state. The Yucca Mountain repository project will be advanced with a higher budget, and WIPP (Waste Isolation Plant) in the state of New Mexico has been in operation since 1998. Plans for the management of spent fuel elements include interim stores called ISFSIs (Independent Spent Fuel Storage Installations) both near and independent of nuclear power sites. Nineteen sites have been licensed, another eighteen are ready to be licensed. In addition, also international spent fuel and nuclear waste management approaches are being discussed in the United States which, inter alia, are meant to offer comprehensive solutions to countries running only a small number of nuclear power plants. (orig.) [de

  11. Evaluation of thorium based nuclear fuel. Actinide waste

    International Nuclear Information System (INIS)

    Wichers, V.A.

    1995-06-01

    Use of thorium based fuel has recently been proposed as a possible way to reduce the amount of actinide waste from nuclear power. To examine this possibility, burnup calculations were done of five once-through Thorium Heavy Water Reactor (THWR) systems, and three THWR systems with uranium recycle. The natural uranium once-through system was adopted as reference. The studied THWR fuel systems differed in the choice of fissile makeup fuel and exit burnup. The HWR was chosen because of its good neutron economy. Actinide waste production (in mass per GW e a) and radiotoxicity (in ALI per GW e a) for storage times up to 10 6 a were calculated for each system. The study shows that the THWR system with uranium recycle and High Enriched Uranium (U-235) makeup fuel performed best, producing both the lowest amount of plutonium and actinide waste with the lowest radiotoxicity. Relative to the natural uranium in HWR once-through system, radiotoxicity is reduced by a factor varying between 2 and 50 for the full range of storage times up to 10 6 a. (orig.)

  12. Category 3 investigation-derived waste Readiness Evaluation Plan

    International Nuclear Information System (INIS)

    Ludowise, J.D.

    1996-08-01

    This Readiness Evaluation Plan presents the methodology used to assess the readiness for loading investigation-derived waste (IDW) drums on trucks for transport to the Environmental Restoration Disposal Facility (ERDF). The scope of this Readiness Evaluation Plan includes an assessment of the organizations, procedures, and regulatory approvals necessary for the handling of IDW containers and the subsequent transportation of materials to ERDF

  13. APEX nuclear fuel cycle for production of LWR fuel and elimination of radioactive waste

    International Nuclear Information System (INIS)

    Steinberg, M.; Powell, J.R.

    1981-08-01

    The development of a nuclear fission fuel cycle is proposed which eliminates all the radioactive fission product waste effluent and the need for geological-age high level waste storage and provides a long term supply of fissile fuel for an LWR power reactor economy. The fuel cycle consists of reprocessing LWR spent fuel (1 to 2 years old) to remove the stable nonradioactive (NRFP, e.g. lanthanides, etc.) and short-lived fission products SLFP e.g. half-lives of (1 to 2 years) and returning, in dilute form, the long-lived fission products, ((LLFPs, e.g. 30 y half-life Cs, Sr, and 10 y Kr, and 16 x 10 6 y I) and the transuranics (TUs, e.g. Pu, Am, Cm, and Np) to be refabricated into fresh fuel elements. Makeup fertile and fissile fuel are to be supplied through the use of a Spallator (linear accelerator spallation-target fuel-producer). The reprocessing of LWR fuel elements is to be performed by means of the Chelox process which consists of Airox treatment (air oxidation and hydrogen reduction) followed by chelation with an organic reagent (β-diketonate) and vapor distillation of the organometallic compounds for separation and partitioning of the fission products

  14. CO-COMBUSTION OF REFUSE DERIVED FUEL WITH COAL IN A FLUIDISED BED COMBUSTOR

    Directory of Open Access Journals (Sweden)

    W. A. WAN AB KARIM GHANI

    2009-03-01

    Full Text Available Power generation from biomass is an attractive technology which utilizes municipal solid waste-based refused derived fuel. In order to explain the behavior of biomass-fired fluidized bed incinerator, biomass sources from refuse derived fuel was co-fired with coal in a 0.15 m diameter and 2.3 m high fluidized bed combustor. The combustion efficiency and carbon monoxide emissions were studied and compared with those from pure coal combustion. This study proved that the blending effect had increased the carbon combustion efficiency up to 12% as compared to single MSW-based RDF. Carbon monoxide levels fluctuated between 200-1600 ppm were observed when coal is added. It is evident from this research that efficient co-firing of biomass with coal can be achieved with minimum modification of existing coal-fired boilers.

  15. Recovery of technetium from nuclear fuel wastes

    International Nuclear Information System (INIS)

    Carlin, W.W.

    1975-01-01

    Technetium is removed from aqueous, acidic waste solutions. The acidic waste solution is mixed with a flocculant, e.g., an alkaline earth metal hydroxide or oxide, to precipitate certain fission products. Technetium remains in solution and in the resulting supernatant alkaline aqueous phase. The supernatant alkaline aqueous phase is made acidic and electrolyzed in an electrolytic cell under controlled cathodic potential conditions to deposit technetium on the cathode. Elemental technetium is removed from the cathode. Technetium is separated from other plated fission product metals by extraction from an alkaline solution with an organic extractant, such as pyridine, having affinity for technetium. Technetium is separated from the organic extractant by steam distillation and the resulting aqueous phase treated with ammoniacal reagent to precipitate technetium as ammonium pertechnetate. The precipitate may be acidified to form an aqueous acidic solution of fission product metal values and the solution electrolyzed in an electrolytic cell under controlled cathodic potential conditions and at a potential sufficiently negative to plate out from the solution those fission product metals desired. The metal deposit is stripped from the cathode and stored until its radioactivity has diminished. (U.S.)

  16. Transmutation of radioactive waste: Effect on the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Rasmussen, N.C.; Pigford, T.H.

    1997-01-01

    A committee of the National Research Council reviewed three concepts for transmuting radionuclides recovered from the chemical reprocessing of commercial light-water-reactor (LWR) fuel: LWR transmutation reactors fueled with recycled actinides, advanced liquid-metal reactors (ALMRs), and accelerator-driven subcritical reactors for transmutation of waste (ATW). The concepts were evaluated in terms of: (1) the extent to which waste disposal would benefit from transmutation, (2) time required to reduce the total inventory of radionuclides in the waste and fuel cycle, (3) the complexity of the overall transmutation system, (4) the extent of new development required, and (5) institutional and economic problems of operating such systems. Transmutation could affect geologic disposal of waste by reducing the inventory of transuranics (TRUs), fission products, and other radionuclides in the waste. Reducing the inventory of transuranics does not necessarily affect radiation doses to people who use contaminated ground water if the dissolution rate of transuranics in waste is controlled by elemental solubilities. However, reducing inventories of Am and Pu would decrease potential hazards from human intrusion. The likelihood for underground nuclear criticality would also be reduced. The long-lived fission products Tc-99, I-129, Cs-135 and others typically contribute most to the long-term radiation doses to future populations who use contaminated water from the repository. Their transmutation requires thermal or epithermal neutrons, readily available in LWR and ATW transmutors. ALMR and LWR transmutors would require several hundred years to reduce the total transuranic inventory by even a factor of 10 at constant electric power, and thousands of years for a hundred-fold reduction. For the same electrical power, the ATW could reduce total transuranic inventory about tenfold more rapidly, because of its very high thermal-neutron flux. However, extremely low process losses would be

  17. Spent Fuel and High-Level Radioactive Waste Transportation Report

    International Nuclear Information System (INIS)

    1992-03-01

    This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by SSEB in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ''comprehensive overview of the issues.'' This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste Issues. In addition. this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list

  18. Spent fuel and high-level radioactive waste transportation report

    Energy Technology Data Exchange (ETDEWEB)

    1989-11-01

    This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages sew be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

  19. Spent fuel and high-level radioactive waste transportation report

    International Nuclear Information System (INIS)

    1989-11-01

    This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ''comprehensive overview of the issues.'' This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages sew be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list

  20. Spent fuel and high-level radioactive waste transportation report

    International Nuclear Information System (INIS)

    1990-11-01

    This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ''comprehensive overview of the issues.'' This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list

  1. From waste to traffic fuel -projects. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Rasi, S; Lehtonen, E; Aro-Heinilae, E [and others

    2012-11-01

    The main objective of the project was to promote biogas production and its use as traffic fuel. The aims in the four Finnish and two Estonian case regions were to reduce the amount and improve the sustainable use of waste and sludge, to promote biogas production, to start biogas use as traffic fuel and to provide tools for implementing the aims. The results of this study show that achieving the food waste prevention target will decrease greenhouse gas emissions by 415 000 CO{sub 2}-eq tons and result in monetary savings for the waste generators amounting to almost 300 euro/ capita on average in all case regions in 2020. The results show that waste prevention should be the first priority in waste management and the use of waste materials as feedstock for energy production the second priority. In total 3 TWh energy could be produced from available biomass in the studied case regions. This corresponds to the fuel consumption of about 300 000 passenger cars. When a Geographical Information System (GIS) was used to identify suitable biogas plant site locations with particular respect to the spatial distribution of available biomass, it was found that a total of 50 biogas plants with capacity varying from 2.1 to 14.5 MW could be built in the case regions. This corresponds to 2.2 TWh energy and covers from 5 to 40% of the passenger car fuel consumption in these regions. Using all produced biogas (2.2 TWh energy) for vehicle fuel GHG emissions would lead to a 450 000 t CO{sub 2}-eq reduction. The same effect on emissions would be gained if more than 100 000 passenger cars were to be taken off the roads. On average, the energy consumed by biogas plants represents approximately 20% of the produced energy. The results also show that biomethane production from waste materials is profitable. In some cases the biomethane production costs can be covered with the gained gate fees. The cost of biomethane production from agricultural materials is less than 96 euro/MWh{sub th

  2. Multiple criteria decision making of alternative fuels for waste collection vehicles in southeast region of Serbia

    Directory of Open Access Journals (Sweden)

    Petrović Goran S.

    2016-01-01

    Full Text Available In this paper multiple criteria decision making approach of alternative fuels for waste collection vehicles in southeast region of Serbia was presented. Eight alternative fuels and advanced vehicle technologies were ranked according to thirteen criteria, including financial, socio-technical, and environmental. Assessment of alternatives was performed by using the weighted aggregated sum product assessment method and results were verified using multi-objective optimization on the basis of ratio analysis method. Considered criteria were obtained from previous researches and by assessment of professional experts from manufacturing industries, public utility companies, and academics institutions. The analysis showed that both biodiesel fuels - derived from used cooking oil or from vegetable oils are the best alternative fuels for Serbian waste collection vehicles in this point of time. Compressed natural gas-powered vehicles were also ranked high in this analysis, but due to the lack of financial capability for their purchase (especially in southeast region of Serbia, their gradual introduction into the waste collection fleet was proposed.

  3. Influence of injection timing on DI diesel engine characteristics fueled with waste transformer oil

    Directory of Open Access Journals (Sweden)

    S. Prasanna Raj Yadav

    2015-12-01

    Full Text Available This research work targets on the effective utilization of WTO (waste transformer oil in a diesel engine, which would rather reduce environmental problems caused by disposing of it in the open land. The waste transformer oil was compared with the conventional diesel fuel and found that it can also be used as fuel in compression ignition engines since the WTO is also a derivative of crude oil. In this present work, the WTO has been subjected to traditional base-catalyzed trans-esterification process in order to reduce the high viscosity of the WTO which helps to effectively utilize WTO as a fuel in DI diesel engine. The objective of the work is to study the influence of injection timing on the performance, emission and combustion characteristics of a single cylinder, four stroke, direct injection diesel engine using TWTO (trans-esterified waste transformer oil as a fuel. Experiments were performed at four injection timings (23°, 22°, 21°, and 20° bTDC. The results indicate that the retarded injection timing of 20° bTDC resulted in decreased oxides of nitrogen, carbon monoxide and unburned hydrocarbon by 11.57%, 17.24%, and 10% respectively while the brake thermal efficiency and smoke increased under all the load conditions when compared to that of standard injection timing.

  4. Waste form development and characterization in pyrometallurgical treatment of spent nuclear fuel

    International Nuclear Information System (INIS)

    Ackerman, J.

    1998-01-01

    Electrometallurgical treatment is a compact, inexpensive method that is being developed at Argonne National Laboratory to deal with spent nuclear fuel, primarily metallic and oxide fuels. In this method, metallic nuclear fuel constituents are electrorefined in a molten salt to separate uranium from the rest of the spent fuel. Oxide and other fuels are subjected to appropriate head end steps to convert them to metallic form prior to electrorefining. The treatment process generates two kinds of high-level waste--a metallic and a ceramic waste. Isolation of these wastes has been developed as an integral part of the process. The wastes arise directly from the electrorefiner, and waste streams do not contain large quantities of solvent or other process fluids. Consequently, waste volumes are small and waste isolation processes can be compact and rapid. This paper briefly summarizes waste isolation processes then describes development and characterization of the two waste forms in more detail

  5. Fuel cycle and waste newsletter Vol. 1, No. 1

    International Nuclear Information System (INIS)

    2005-08-01

    The purpose of the NEFW Newsletter is to inform a wider audience about the activities performed in the Division, as well as to provide topical articles in the field. The News letter informs about the Symposium on Uranium Production and Raw Materials for the Nuclear Fuel Cycle - Supply and Demand, Economics, the Environment and Energy Security, held in Vienna, June 2005. In this first issue the activities in the Nuclear Fuel Cycle and Materials Section (NFCMS) and Waste Technology Section (WTS) are presented. The article 'The Promise of underground geological repositories' is presented

  6. Waste management analysis for the nuclear fuel cycle. I. Actinide recovery from aqueous salt wastes

    International Nuclear Information System (INIS)

    Martella, L.L.; Navratil, J.D.

    1979-01-01

    A preliminary feasibility study of solvent extraction methods has been completed for removing actinides from selected salt wastes likely to be produced during reactor fuel fabrication and reprocessing. The use of a two-step solvent extraction system, tributyl phosphate (TBP) followed by a bidentate organophosphorus extractant (DHDECMP), appears most efficient for removing actinides from salt waste. The TBP step would remove most of the plutonium and >99.99% of the uranium. The second step, using DHDECMP, would remove >99.91% of the americium, the remaining plutonium (>99.98%), and other actinides from the acidified salt waste

  7. Nuclear fuel waste disposal. Canada's consultative approach

    Energy Technology Data Exchange (ETDEWEB)

    Hillier, J A.R.; Dixon, R S [AECL (Canada)

    1993-07-01

    Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

  8. Nuclear fuel waste disposal. Canada's consultative approach

    International Nuclear Information System (INIS)

    Hillier, J.A.R.; Dixon, R.S.

    1993-01-01

    Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

  9. Waste transmutation with minimal fuel cycle long-term risk

    Energy Technology Data Exchange (ETDEWEB)

    Slessarev, I.; Salvatores, M.; Uematsu, M. [Direction des Reacteurs Nucleaires, Cadarache (France)

    1995-10-01

    Hybrid systems (source-driven subcritical reactors), are investigated at CEA, mainly from a conceptual point of view, in order to assess their potential to transmute radioactive wastes (mainly long-lived fission products, LLFP) and their potential to insure a minimal long-term radiological risk related both to the fuel inventory inside the system and to the full fuel cycle (mass flows, reprocessing transport, waste disposal). The physics of these systems has been explored and work is in progress both in the field of basic data and INC code validation, in the frame of international collaborations and in the field of conceptual design studies. The most interesting feature of subcritical source-driven system is related to the possibility to obtain an {open_quotes}excess{close_quotes} of neutrons per fission, which can be used to reduce the long-term radiological risk. A specific example will be discussed here.

  10. Combustion of Refuse Derived Fuels; Foerbraenning av utsorterade avfallsfraktioner

    Energy Technology Data Exchange (ETDEWEB)

    Berg, Magnus; Wikman, Karin [AaF-Energi och Miljoe, Stockholm (Sweden); Andersson, Christer; Myringer, Aase; Helgesson, Anna [Vattenfall Utveckling AB, Aelvkarleby (Sweden); Eskilsson, David; Ekvall, Annika [SP Swedish National Testing and Research Inst., Boraas (Sweden); Oehman, Marcus; Geyter, Sigrid de [Umeaa Univ. (Sweden). Energy Technology and Thermal Process Chemistry

    2005-03-01

    The aim of this project was to increase the understanding of opportunities and problems connected with combustion of sorted waste fractions containing paper, wood and plastics (PWP-fuel) in fluidized bed boilers. An evaluation of the effect of sulphur containing additives in a PWP-fuel fired boiler was also performed within the project since this is not previously reported in open literature. The experience from two boilers at different plants, Johannes (BFB) and Hoegdalen P6 (CFB) during the firing season 2003/2004 was documented. In the Johannes boiler the main fuel is bark while Hoegdalen P6 combusts 100 % PWP-fuel. Analysis of the fuels shows that there are large differences between the two boilers. At Johannes the PWP-fuel contained low amounts of elements (chlorine, alkali and other metals) that are expected to result in increased operational problems or emissions. A large proportion of these unwanted elements came from the wood and paper fractions. The plastic fraction in Johannes had very low levels of unwanted elements. The fuel at Hoegdalen contained large amounts of elements such as chlorine, alkali and other metals that can cause operational problems. First of all the plastic fraction contained large amounts of chlorine, most likely from PVC, which results in a more corrosive atmosphere in the boiler. The fraction of fines in the Hoegdalen fuel contained larger concentrations of potassium and sodium compared with the other fuel fractions, substances that also are related to the formation of deposits. The fraction of fines in the fuel probably also results in combustion taking place high up in the boiler and to some extent continuing in the cyclones. The characterisation of the combustion behaviour performed in Johannes identified a maldistribution in O{sub 2}, CO and gas temperature over a cross-section of the furnace. This was not depending on the fuel mixture but is more likely depending on uneven fuel feeding or air distribution. A comparison between

  11. Municipal solid waste generation in municipalities: quantifying impacts of household structure, commercial waste and domestic fuel.

    Science.gov (United States)

    Lebersorger, S; Beigl, P

    2011-01-01

    Waste management planning requires reliable data concerning waste generation, influencing factors on waste generation and forecasts of waste quantities based on facts. This paper aims at identifying and quantifying differences between different municipalities' municipal solid waste (MSW) collection quantities based on data from waste management and on socio-economic indicators. A large set of 116 indicators from 542 municipalities in the Province of Styria was investigated. The resulting regression model included municipal tax revenue per capita, household size and the percentage of buildings with solid fuel heating systems. The model explains 74.3% of the MSW variation and the model assumptions are met. Other factors such as tourism, home composting or age distribution of the population did not significantly improve the model. According to the model, 21% of MSW collected in Styria was commercial waste and 18% of the generated MSW was burned in domestic heating systems. While the percentage of commercial waste is consistent with literature data, practically no literature data are available for the quantity of MSW burned, which seems to be overestimated by the model. The resulting regression model was used as basis for a waste prognosis model (Beigl and Lebersorger, in preparation). Copyright © 2011 Elsevier Ltd. All rights reserved.

  12. Municipal solid waste generation in municipalities: Quantifying impacts of household structure, commercial waste and domestic fuel

    International Nuclear Information System (INIS)

    Lebersorger, S.; Beigl, P.

    2011-01-01

    Waste management planning requires reliable data concerning waste generation, influencing factors on waste generation and forecasts of waste quantities based on facts. This paper aims at identifying and quantifying differences between different municipalities' municipal solid waste (MSW) collection quantities based on data from waste management and on socio-economic indicators. A large set of 116 indicators from 542 municipalities in the Province of Styria was investigated. The resulting regression model included municipal tax revenue per capita, household size and the percentage of buildings with solid fuel heating systems. The model explains 74.3% of the MSW variation and the model assumptions are met. Other factors such as tourism, home composting or age distribution of the population did not significantly improve the model. According to the model, 21% of MSW collected in Styria was commercial waste and 18% of the generated MSW was burned in domestic heating systems. While the percentage of commercial waste is consistent with literature data, practically no literature data are available for the quantity of MSW burned, which seems to be overestimated by the model. The resulting regression model was used as basis for a waste prognosis model (Beigl and Lebersorger, in preparation).

  13. The disposal of Canada's nuclear fuel waste: engineered barriers alternatives

    International Nuclear Information System (INIS)

    Johnson, L.H.; Tait, J.C.; Shoesmith, D.W.; Crosthwaite, J.L.; Gray, M.N.

    1994-01-01

    The concept for disposal of Canada's nuclear fuel waste involves emplacing the waste in a vault excavated at a depth of 500 to 1000 m in plutonic rock of the Canadian Shield. The solid waste would be isolated from the biosphere by a multibarrier system consisting of engineered barriers, including long-lived containers and clay and cement-based sealing materials, and the natural barrier provided by the massive geological formation. The technical feasibility of this concept and its impact on the environment and human health are being documented in an Environmental Impact Statement (EIS), which will be submitted for review under the federal Environmental Assessment and Review Process. This report, one of nine EIS primary references, describes the various alternative designs and materials for engineered barriers that have been considered during the development of the Canadian disposal concept and summarizes engineered barrier concepts being evaluated in other countries. The basis for the selection of a reference engineered barrier system for the EIS is presented. This reference system involves placing used CANDU (Canada Deuterium Uranium) fuel bundles in titanium containers, which would then be emplaced in boreholes drilled in the floor of disposal rooms. Clay-based sealing materials would be used to fill both the space between the containers and the rock and the remaining excavations. In the section on waste forms, the properties of both used-fuel bundles and solidified high-level wastes, which would be produced by treating wastes resulting from the reprocessing of used fuel, are discussed. Methods of solidifying the wastes and the chemical durability of the solidified waste under disposal conditions are reviewed. Various alternative container designs are reviewed, ranging from preliminary conceptual designs to designs that have received extensive prototype testing. Results of structural performance, welding and inspection studies are also summarized. The corrosion of

  14. Production, characterization and fuel properties of alternative diesel fuel from pyrolysis of waste plastic grocery bags

    Science.gov (United States)

    Pyrolysis of HDPE waste grocery bags followed by distillation resulted in a liquid hydrocarbon mixture that consisted of saturated aliphatic paraffins (96.8%), aliphatic olefins (2.6%), and aromatics (0.6%) that corresponded to the boiling range of conventional petroleum diesel fuel (#1 diesel 182–2...

  15. Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography

    OpenAIRE

    Jonkmans, G.; Anghel, V. N. P.; Jewett, C.; Thompson, M.

    2012-01-01

    This paper explores the use of cosmic ray muons to image the contents of shielded containers and detect high-Z special nuclear materials inside them. Cosmic ray muons are a naturally occurring form of radiation, are highly penetrating and exhibit large scattering angles on high Z materials. Specifically, we investigated how radiographic and tomographic techniques can be effective for non-invasive nuclear waste characterization and for nuclear material accountancy of spent fuel inside dry stor...

  16. Final disposal of high levels waste and spent nuclear fuel

    International Nuclear Information System (INIS)

    Gelin, R.

    1984-05-01

    Foreign and international activities on the final disposal of high-level waste and spent nuclear fuel have been reviewed. A considerable research effort is devoted to development of acceptable disposal options. The different technical concepts presently under study are described in the report. Numerous studies have been made in many countries of the potential risks to future generations from radioactive wastes in underground disposal repositories. In the report the safety assessment studies and existing performance criteria for geological disposal are briefly discussed. The studies that are being made in Canada, the United States, France and Switzerland are the most interesting for Sweden as these countries also are considering disposal into crystalline rocks. The overall time-tables in different countries for realisation of the final disposal are rather similar. Normally actual large-scale disposal operations for high-level wastes are not foreseen until after year 2000. In the United States the Congress recently passed the important Nuclear Waste Policy Act. It gives a rather firm timetable for site-selection and construction of nuclear waste disposal facilities. According to this act the first repository for disposal of commercial high-level waste must be in operation not later than in January 1998. (Author)

  17. Wastes from fossil and nuclear fuels

    International Nuclear Information System (INIS)

    Kornberg, H.A.

    1976-01-01

    The purpose of this paper is to develop a perspective of what the United States reasonably can expect in terms of wastes from coal- and nuclear-fired power plants. Only power plant operations are compared to the end of the century. To do so, it is assumed that no major technological breakthrough will significantly affect the way mass quantities of electricity are to be generated to the end of this century. This is considered a reasonable assumption since society's inertia and momenta are not likely to change in 24 short years. Unlike the debate on the health risks of nuclear energy, where agreement cannot be reached because estimates of things that have not happened must be used, this examines things that can be weighed, seen, and otherwise perceived. Although numbers used and projections made are based on historical data and attempts to be accurate were made, figures developed could be off by an order of magnitude and more, without affecting the general conclusions

  18. Oxidative stability of biodiesel blends derived from waste frying oils

    Directory of Open Access Journals (Sweden)

    Michael Feroldi

    2017-07-01

    Full Text Available The high cost of biodiesel production is mainly linked to the price of raw material.This factor has favored the use of alternative fats and oils such as those used in frying. Since biodiesel can be obtained from several vegetable and animal raw materials, the physicochemical characteristics of the fuel may vary considerably. One of these characteristics is the fatty acid composition. It directly affects the oxidative stability of biodiesel, which can be impaired when the fuel undergoes exposure to sunlight, metals, oxygen and high temperatures. In order to improve the oxidative stability of biodiesels produced from waste frying oil some studies involving blends of different raw materials have been carried out. In this sense, this work aimed to assess the characteristics resulting from the blending of soybean waste frying oil with other waste biodiesels in what concerns to oxidation. The blends of fatty materials were obtained by means of a 2² factorial design. The induction periods of biodiesel blends were enough to meet the ASTM D6751 standard. Swine fat was responsible for the increase in the induction period values.

  19. Radiological aspects of postfission waste management for light-water reactor fuel cycle options

    Energy Technology Data Exchange (ETDEWEB)

    Shipler, D B; Nelson, I C [Battelle Pacific Northwest Laboratories, Richland, WA (United States)

    1978-12-01

    A generic environmental impact statement on the management of radioactive postfission wastes from various light-water reactor fuel cycles in the United States has been prepared. The environmental analysis for post-fission waste management includes an examination of radiological impacts related to different waste treatment, storage, transportation, and disposal options at the process level. Effects addressed include effluents from plants, and radiological impacts from facility operation (routine and accidents), and decommissioning. Environmental effects are combined for fuel reprocessing plants, mixed-oxide fuel fabrication plants, and waste repositories. Radiological effects are also aggregated for several fuel cycle options over the period 1980 and 2050. Fuel cycles analyzed are (1) once-through cycle in which spent reactor fuel is cooled in water basins for at least 6-1/2 years and then disposed of in deep geologic repositories; (2) spent fuel reprocessing in which uranium only and uranium and plutonium is recycled and solidified high level waste, fuel residues, and non-high-level transuranic wastes are disposed of in deep geologic repositories; and (3) deferred cycle that calls for storage of spent fuel at Federal spent fuel storage facilities until the year 2000 at which time a decision is made whether to dispose of spent fuel as a waste or to reprocess the fuel to recover uranium and plutonium. Key environmental issues for decision-making related to waste management alternatives and fuel cycle options are highlighted. (author)

  20. Review of best available techniques for the control of pollution from the combustion of fuels manufactured from or including waste

    International Nuclear Information System (INIS)

    1995-01-01

    This report is a technical review of the techniques available for controlling pollution from combustion processes burning fuels (over 3 MW thermal input) manufactured from or including the following: Waste and recovered oil; Refuse derived fuel; Rubber tyres and other rubber waste; Poultry litter; Wood and straw. This review forms the basis for the revision of the Chief Inspector's Guidance Notes referring to the prescribed processes listed with special emphasis on recommending achievable releases to all environmental media. In formulating achievable releases account is taken of technologies in operation in the UK and overseas. (UK)

  1. National briefing summaries: Nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

    1991-04-01

    Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy

  2. National briefing summaries: Nuclear fuel cycle and waste management

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

    1991-04-01

    Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy.

  3. Chemistry research for the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  4. Performance Analysis of Cofiring Densified Refuse Derived Fuel in a Military Boiler.

    Science.gov (United States)

    1981-12-01

    Use of Waste Oils to Improve Densified Refuse-Derived Fuel 79 Study of the State of the Art of Dioxin from Corbustion Sour ,-es 81 Numerical...very large hammermills for shredu-,nt ii -et re C strean . Tne suitability of this technique has beer . : , 1:d aeauie of its undesirable proper- ,V.>- ir...oe iut- fraction while reducing the hrsepower requiie:: ,. ht uuty shredders have -c-en used as a pfre -. . :-r,der-s have not beer perfected wnich

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

    International Nuclear Information System (INIS)

    2003-12-01

    criteria for disposal of radioactive wastes to near surface facilities. These criteria are qualitative in nature and, for example, they do not address limitations on radionuclide content of waste, waste packages or the facility as a whole. This publication is to present an approach for establishing radiological waste acceptance criteria using a safety assessment methodology and to illustrate its application in establishing limits on the total activity and the activity concentrations of radioactive waste to be disposed in near surface disposal facilities. The approach makes use of accepted methods and computational schemes currently used in assessing the safety of near surface disposal facilities both during the operational and post-closure periods. The scope of this publication covers the use of safety assessment methodology to calculate total and specific activities limits for radioactive waste in near surface disposal facilities. It is used to evaluate the potential operational and post-closure radiological impact of solid and solidified radioactive waste in near surface facilities. The radioactive waste types used to illustrate the approach range from waste containing radionuclides used for medical, industrial and research purposes to waste arising from nuclear fuel cycle activities. They also include waste arising from the decommissioning of nuclear facilities. The focus of the publication is on using of safety assessment methodology in derivation of quantitative radioactivity limits. This report deals with the role of activity limits in disposal system safety (Section 2), the relevant radiation protection criteria (Section 3), the approach to derive activity limits (Section 4), illustrations of the application of this approach (Section 5), and guidance on the use of the approach (Section 6)

  6. Regulations for the safe management of radioactive wastes and spent nuclear fuel

    International Nuclear Information System (INIS)

    Voica, Anca

    2007-01-01

    The paper presents the national, international and European regulations regarding radioactive waste management. ANDRAD is the national authority charged with nation wide coordination of safe management of spent fuel and radioactive waste including their final disposal. ANDRAD's main objectives are the following: - establishing the National Strategy concerning the safety management of radioactive waste and spent nuclear fuel; - establishing the national repositories for the final disposal of the spent nuclear fuel and radioactive waste; - developing the technical procedures and establishing norms for all stages of management of spent nuclear fuel and radioactive waste, including the disposal and the decommissioning of the nuclear and radiologic facilities

  7. Management of severely damaged nuclear fuel and related waste

    International Nuclear Information System (INIS)

    1991-01-01

    This report is concerned primarily with severe fuel damage accidents in large electric power producing reactors such as those in the TMI and Chernobyl plants. It does include, as appropriate, knowledge gained from accidents in other power, research and military reactors. It is believed that the conclusions and recommendations apply to a large extent to severe fuel damage accidents in all types of reactors. The period considered in this publication begins after the initial crisis of an accident has been brought under control. (This initial crisis could be from one day to several weeks after the event, depending on the specific conditions). Accordingly, it is assumed that the plant is shut down, the reactor is under control and decay heat removal is in progress in a stable manner so that attention must be given to cleanup. This report addresses the principles involved in planning, engineering, construction, operation and other activities to characterize, clean up and dispose of the fuel and related waste. The end of the period under consideration is when the fuel and abnormal wastes are packaged either for interim storage or final disposal and activities are started either to restore the plant to service or to establish a safe state from which decommissioning planning can start. 36 refs, 3 figs, 4 tabs.

  8. Multiple Tier Fuel Cycle Studies for Waste Transmutation

    International Nuclear Information System (INIS)

    Hill, R.N.; Taiwo, T.A.; Stillman, J.A.; Graziano, D.J.; Bennett, D.R.; Trellue, H.; Todosow, M.; Halsey, W.G.; Baxter, A.

    2002-01-01

    As part of the U.S. Department of Energy Advanced Accelerator Applications Program, a systems study was conducted to evaluate the transmutation performance of advanced fuel cycle strategies. Three primary fuel cycle strategies were evaluated: dual-tier systems with plutonium separation, dual-tier systems without plutonium separation, and single-tier systems without plutonium separation. For each case, the system mass flow and TRU consumption were evaluated in detail. Furthermore, the loss of materials in fuel processing was tracked including the generation of new waste streams. Based on these results, the system performance was evaluated with respect to several key transmutation parameters including TRU inventory reduction, radiotoxicity, and support ratio. The importance of clean fuel processing (∼0.1% losses) and inclusion of a final tier fast spectrum system are demonstrated. With these two features, all scenarios capably reduce the TRU and plutonium waste content, significantly reducing the radiotoxicity; however, a significant infrastructure (at least 1/10 the total nuclear capacity) is required for the dedicated transmutation system. (authors)

  9. Multiple tier fuel cycle studies for waste transmutation

    International Nuclear Information System (INIS)

    Hill, R.N.; Taiwo, T.A.; Stillman, J.A.; Graziano, D.J.; Bennett, D.R.; Trellue, H.; Todosow, M.; Halsey, W.G.; Baxter, A.

    2002-01-01

    As part of the U.S. Department of Energy Advanced Accelerator Applications Program, a systems study was conducted to evaluate the transmutation performance of advanced fuel cycle strategies. Three primary fuel cycle strategies were evaluated: dual-tier systems with plutonium separation, dual-tier systems without plutonium separation, and single-tier systems without plutonium separation. For each case, the system mass flow and TRU consumption were evaluated in detail. Furthermore, the loss of materials in fuel processing was tracked including the generation of new waste streams. Based on these results, the system performance was evaluated with respect to several key transmutation parameters including TRU inventory reduction, radiotoxicity, and support ratio. The importance of clean fuel processing (∼0.1% losses) and inclusion of a final tier fast spectrum system are demonstrated. With these two features, all scenarios capably reduce the TRU and plutonium waste content, significantly reducing the radiotoxicity; however, a significant infrastructure (at least 1/10 the total nuclear capacity) is required for the dedicated transmutation system

  10. International trade and waste and fuel managment issue, 2008

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2008-01-15

    The focus of the January-February issue is on international trade and waste and fuel managment. Major articles/reports in this issue include: A global solution for clients, by Yves Linz, AREVA NP; A safer, secure and economical plant, by Andy White, GE Hitachi Nuclear; Robust global prospects, by Ken Petrunik, Atomic Energy of Canada Limited; Development of NPPs in China, by Chen Changbing and Li Huiqiang, Huazhong University of Science and Technology; Yucca Mountain update; and, A class of its own, by Tyler Lamberts, Entergy Nuclear. The Industry Innovation articles in this issue are: Fuel assembly inspection program, by Jim Lemons, Tennessee Valley Authority; and, Improved in-core fuel shuffle for reduced refueling duration, by James Tusar, Exelon Nuclear.

  11. Transportation of high-level waste and spent fuel

    International Nuclear Information System (INIS)

    Carlson, J.H.; Lake, W.H.; Thompson, J.H.

    1993-01-01

    The Office of Civilian Radioactive Waste Management (OCRWM) transportation program is a multifaceted undertaking to transport spent nuclear fuel from commercial reactors to temporary and permanent storage facilities commencing in 1998. One of the significant ingredients necessary to achieving this goal is the development and acquisition of shipping casks. Efforts to design and acquire high capacity casks is ongoing, as are efforts to purchase casks that can be made available using current technology. By designing casks that are optimized to the specifications of the older cooler spent fuel that will be shipped, and by designing to current NRC requirements, OCRWM's new generation of spent fuel casks will be more efficient and at least as safe as current cask designs. (J.P.N.)

  12. Investigation-Derived Waste Management Plan. Revision 2

    International Nuclear Information System (INIS)

    Molen, G.

    1995-01-01

    SRS has implemented a comprehensive environmental program to maintain compliance with environmental regulations and mitigate impacts to the environment. One element of the environmental program is the investigation of inactive waste units. Environmental Investigation-Derived Waste (IDW). IDW may include purge water , soil cuttings, drilling fluids, well pumping test and development water, decontamination solutions, contaminated equipment, and personal protection equipment (PPE). In cases where investigations confirm the presence of contamination and the IDW contains waste constituents in concentrations high enough to be of environmental or health concern, special management procedures are warranted. This IDW Management Plan describes specific SRS initiatives for IDW management. The goal is the development of a plan for prudent management of IDW from environmental investigations that is protective of human health and the environment

  13. Environment-friendly type energy and coordinated community development project. Feasibility study for industrialization of high efficiency waste-fired power generation system (industrial refuse derived fuel and gas turbine combined type); Kankyo chowagata energy community keisei sokushin. Kokoritsu haikibutsu hatsuden (sangyo RDF GT fukugogata) jigyoka FS chosa

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    High efficiency power generation, which is useful for promoting the environment-friendly type energy and coordinated community, is investigated by combining a steam turbine power generation system using the PS-RDF (paper sludge-refuse derived fuel) and a gas turbine (GT) combined cycle. Industrialization plan for processing PS in low cost has been made to ensure the profitability by participating the wholesale power supply under the law of electric power industry. This combined system is similar to the so-called super power generation using municipal garbage, but the lower temperature of steam from GT waste heat boilers (WHB) is super-heated by the flue gas from RDF boiler, which is called advanced power generation system (A.S.S.). The total power generation capacity is 149,000 kW, which consists of three 35,000 kW units of GT and one 44,000 kW unit of steam turbine. When comparing the combined system (A.S.S.) and usual one with the independent installation of the RDF steam power generation system and a GT combined cycle, the A.S.S. provides the repowering efficiency of 7,600 kW output with exactly the same quantity of fuel input as usual one. 71 figs., 31 tabs.

  14. 10 CFR 71.97 - Advance notification of shipment of irradiated reactor fuel and nuclear waste.

    Science.gov (United States)

    2010-01-01

    ... fuel and nuclear waste. 71.97 Section 71.97 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING... notification of shipment of irradiated reactor fuel and nuclear waste. (a) As specified in paragraphs (b), (c... advance notification of transportation of nuclear waste was published in the Federal Register on June 30...

  15. Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes

    International Nuclear Information System (INIS)

    Harmon, K.M.; Johnson, A.B. Jr.

    1984-04-01

    The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage

  16. Processing and properties of a solid energy fuel from municipal solid waste (MSW) and recycled plastics.

    Science.gov (United States)

    Gug, JeongIn; Cacciola, David; Sobkowicz, Margaret J

    2015-01-01

    sample composition was similar to biomass fuels but had significant advantages due to addition of waste plastics that have high energy content compared to other waste types. Addition of PP and HDPE presented better benefits than addition of PET due to lower softening temperature and lower oxygen content. It should be noted that while harmful emissions such as dioxins, furans and mercury can result from burning plastics, WTE facilities have been able to control these emissions to meet US EPA standards. This research provides a drop-in coal replacement that reduces demand on landfill space and replaces a significant fraction of fossil-derived fuel with a renewable alternative. Copyright © 2014 Elsevier Ltd. All rights reserved.

  17. Emissions of toxic pollutants from co-combustion of demolition and construction wood and household waste fuel blends.

    Science.gov (United States)

    Edo, Mar; Ortuño, Núria; Persson, Per-Erik; Conesa, Juan A; Jansson, Stina

    2018-07-01

    Four different types of fuel blends containing demolition and construction wood and household waste were combusted in a small-scale experimental set-up to study the effect of fuel composition on the emissions of polychlorinated dibenzo-p-dioxins (PCDDs), dibenzofurans (PCDFs), biphenyls (PCBs), chlorobenzenes (PCBzs), chlorophenols (PCPhs) and polycyclic aromatic hydrocarbons (PAHs). Two woody materials, commercial stemwood (ST) and demolition and construction wood (DC) were selected because of the differences in their persistent organic pollutants (POPs), ash and metals content. For household waste, we used a municipal solid waste (MSW) and a refuse-derived fuel (RDF) from MSW with 5-20 wt% and up to 5 wt% food waste content respectively. No clear effect on the formation of pollutants was observed with different food waste content in the fuel blends tested. Combustion of ST-based fuels was very inefficient which led to high PAH emissions (32 ± 3.8 mg/kg fuel ). The use of DC clearly increased the total PCDD and PCDF emissions (71 ± 26 μg/kg fuel ) and had a clear effect on the formation of toxic congeners (210 ± 87 ng WHO 2005 -TEQ/kg fuel ). The high PCDD and PCDF emissions from DC-based fuels can be attributed to the presence of material contaminants such as small pieces of metals or plastics as well as timber treated with chromated copper arsenate preservatives and pentachlorophenol in the DC source. Copyright © 2018 Elsevier Ltd. All rights reserved.

  18. Fuel cycle and waste newsletter, Vol. 4, No. 1, April 2008

    International Nuclear Information System (INIS)

    2008-04-01

    This issue of the Fuel Cycle and Waste Newsletter presents the International Decommissioning Network, the cooperation between INPRO (the International Project on Innovative Nuclear Reactors and Fuel Cycles) and NEFW (IAEA's Division of Nuclear Fuel Cycle and Waste Technology), the policies and strategies for spent fuel and radioactive waste management, recent developments of decommissioning waste, integrated approach to decommissioning and environmental remediation, CEG Workshop, repatriation of sealed sources in Latin America, the technical working Group on research reactors (TWGRR), an update on research reactor networks, Atominstitut Vienna, modernization and refurbishment of research reactors, a new CRP on innovative methods in research reactor analysis, management of damaged spent nuclear fuel, influence of high-burnup UOX and MOX water reactor fuel on spent fuel management, a new CRP on improvement in the computer code modelling of high burnup nuclear fuel (FUMEX-3), reuse options for reprocessed uranium (RepU), a basic fact-book on coated particle fuel, recent publications and upcoming meetings

  19. 10 CFR 72.108 - Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Spent fuel, high-level radioactive waste, or reactor... RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Siting Evaluation Factors § 72.108 Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation. The...

  20. Biodegradation of radioactive organic liquid waste from spent fuel reprocessing

    International Nuclear Information System (INIS)

    Ferreira, Rafael Vicente de Padua

    2008-01-01

    The research and development program in reprocessing of low burn-up spent fuel elements began in Brazil in 70's, originating the lab-scale hot cell, known as Celeste located at Nuclear and Energy Research Institute, IPEN - CNEN/SP. The program was ended at the beginning of 90's, and the laboratory was closed down. Part of the radioactive waste generated mainly from the analytical laboratories is stored waiting for treatment at the Waste Management Laboratory, and it is constituted by mixture of aqueous and organic phases. The most widely used technique for the treatment of radioactive liquid wastes is the solidification in cement matrix, due to the low processing costs and compatibility with a wide variety of wastes. However, organics are generally incompatible with cement, interfering with the hydration and setting processes, and requiring pre -treatment with special additives to stabilize or destroy them. The objective of this work can be divided in three parts: organic compounds characterization in the radioactive liquid waste; the occurrence of bacterial consortia from Pocos de Caldas uranium mine soil and Sao Sebastiao estuary sediments that are able to degrade organic compounds; and the development of a methodology to biodegrade organic compounds from the radioactive liquid waste aiming the cementation. From the characterization analysis, TBP and ethyl acetate were chosen to be degraded. The results showed that selected bacterial consortia were efficient for the organic liquid wastes degradation. At the end of the experiments the biodegradation level were 66% for ethyl acetate and 70% for the TBP. (author)

  1. A comparison study on radioactive waste management effectiveness in various nuclear fuel cycles

    International Nuclear Information System (INIS)

    Ko, Won Il; Kim, Ho Dong

    2001-07-01

    This study examines whether the DUPIC (Direct Use of Spent PWR Fuel In CANDU) fuel cycle make radioactive waste management more effective, by comparing it with other fuel cycles such as the PWR (Pressurized Water Reactor) once-through cycle, the HWR (Pressurized Heavy Water Reactor) once-through cycle and the thermal recycling option to use an existing PWR with MOX (Mixed Oxide) fuel. This study first focuses on the radioactive waste volume generated in all fuel cycle steps, which could be one of the measures of effectiveness of the waste management. Then the total radioactive waste disposition cost is estimated based on two units measuring; m3/GWe-yr and US$/GWe-yr. We find from the radioactive waste volume estimation that the DUPIC fuel cycle could have lower volumes for milling tailings, low level waste and spent fuel than those of other fuel cycle options. From the results of the disposition cost analysis, we find that the DUPIC waste disposition cost is the lowest among fuel cycle options. If the total waste disposition cost is used as a proxy for quantifying the easiness or difficulty in managing wastes, then the DUPIC option actually make waste management easier

  2. The situation of radioactive waste management in the fuel reprocessing facility (for fiscal 1979)

    International Nuclear Information System (INIS)

    1981-01-01

    In the fuel reprocessing facility of Power Reactor and Nuclear Fuel Development Corporation (PNC), the release of radioactive gaseous and liquid wastes was so controlled as not to exceed the set standards. Of the radioactive liquid wastes, concentrated wastes and sludge are stored in tanks. Radioactive solid wastes are suitably stored in containers. The situation of radioactive waste management in the fuel reprocessing facility in fiscal 1979 (from April, 1979, to March, 1980) is presented on the basis of the radiation control report made by PNC. The release of radioactive gaseous and liquid wastes was below the set standards. The following data are given in tables: the released quantity of radioactive gaseous and liquid wastes, the cumulative stored amount of radioactive liquid wastes, the produced quantity and cumulative stored amount of radioactive solid wastes; (for reference) the released quantity of radioactive gaseous and liquid wastes in fiscal 1977, 1978 and 1979. (J.P.N.)

  3. Baseline concentrations of nuclear fuel waste nuclides in the environment

    International Nuclear Information System (INIS)

    Amiro, B.D.

    1992-04-01

    Protection of the environment is a key issue in the disposal of long-lived radioactive wastes. To assess the implications of undergound disposal, transport models are commonly used to predict radionuclide concentrations in soil and water. However, an appropriate framework needs to be established to ensure that the predicted concentrations do not impose unacceptable environmental impacts. Here, we suggest baseline environmental concentrations of the most important radionuclides in nuclear fuel waste. We summarize background concentrations of the nuclides in soil and surface water, and suggest Environmental Increments (EI) that could be added to soil and water without causing detectable effects. The EI values are based mostly on natural variability, but some alternative methods are used for radionuclides that are very rare in nature. The background concentrations and EI values are most useful as a screening tool to help identify potentially unacceptable concentrations arising from a disposal concept. When available, we also report data on concentrations that have been measured in the environment without causing an observable effect. This review focuses especially on concentrations applicable to the Canadian Precambrian Shield, as part of the Canadian concept of nuclear fuel waste disposal in a deep, stable geological formation

  4. Waste-to-Fuel: A Case Study of Converting Food Waste to Renewable Natural Gas as a Transportation Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Mintz, Marianne [Argonne National Lab. (ANL), Argonne, IL (United States); Tomich, Matthew [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-05-01

    This case study explores the production and use of renewable compressed natural gas (R-CNG)—derived from the anaerobic digestion (AD) of organic waste—to fuel heavy-duty refuse trucks and other natural gas vehicles in Sacramento, California.

  5. Characteristics of and sorption to biochars derived from waste material

    Science.gov (United States)

    Sun, Huichao; Kah, Melanie; Sigmund, Gabriel; Hofmann, Thilo

    2015-04-01

    Biochars can exhibit a high sorption potential towards heavy metals and organic contaminants in various environmental matrices (e.g., water, soil). They have therefore been proposed for environmental remediation purposes to sequester contaminants. To date, most studies have focused on the physicochemical and sorption properties of mineral phases poor biochars, which are typically produced from plant residues. Only little knowledge is available for biochars derived from human and animal waste material, which are typically characterized by high mineral contents (e.g., sewage sludge, manure). Using human and animal waste as source material to produce biochars would support the development of attractive combined strategies for waste management and remediation. The potential impact of mineral phases on the physicochemical and sorption properties of biochars requires further studies so that the potential as sorbent material can be evaluated. With this purpose, different source material biochars were produced at 200°C, 350°C and 500°C, to yield a series of biochars representing a range of mineral content. The derived biochars from wood shavings (sludge (50-70% ash) and pig manure (30-60% ash), as well as a commercial biochar derived from grain husks (40% ash), were extensively characterized (e.g., element composition, surface area, porosity, Fourier transform infrared spectroscopy). The contents of potentially toxic elements (i.e., heavy metals and polycyclic aromatic hydrocarbons) of all materials were within the guidelines values proposed by the International Biochar Initiative, indicating their suitability for environmental application. Single point sorption coefficients for the model sorbate pyrene were measured to investigate the effect of mineral content, feedstock, pyrolysis temperature, particle size fractions and acid demineralization on sorption behavior. Overall, sorption of pyrene was strong for all materials (4 waste material and exhibiting high mineral

  6. Nano-watt fueling from a micro-scale microbial fuel cell using black tea waste

    KAUST Repository

    Rojas, Jhonathan Prieto

    2016-02-03

    In this report, we show the rapid assessment of black tea as potential fuel to power up nanopower systems using a microsized, simplistic and sustainable air-cathode microbial fuel cell. It was found that tea produced more power compared with traditional sodium acetate media due in part to its acidophilic pH and its higher organics content. Although high internal resistance remains a big concern, this simple, curiosity-driven experiment gave us the preliminary results to say that energy could be extracted from the reuse of waste resources such the collection of our afternoon-tea\\'s leftovers.

  7. Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    1994-01-01

    This report describes the many fundamental issues relating to the strategy being proposed by Atomic Energy of Canada Limited for the long-term management of nuclear fuel waste. It discusses the need for a method for disposal of nuclear fuel waste that would permanently protect human health and the natural environment and that would not unfairly burden future generations. It also describes the background and mandate of the Nuclear Fuel Waste Management Program in Canada.

  8. Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-01

    This report describes the many fundamental issues relating to the strategy being proposed by Atomic Energy of Canada Limited for the long-term management of nuclear fuel waste. It discusses the need for a method for disposal of nuclear fuel waste that would permanently protect human health and the natural environment and that would not unfairly burden future generations. It also describes the background and mandate of the Nuclear Fuel Waste Management Program in Canada.

  9. Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-01

    This report describes the many fundamental issues relating to the strategy being proposed by Atomic Energy of Canada Limited for the long-term management of nuclear fuel waste. It discusses the need for a method for disposal of nuclear fuel waste that would permanently protect human health and the natural environment and that would not unfairly burden future generations. It also describes the background and mandate of the Nuclear Fuel Waste Management Program in Canada.

  10. Wastes from selected activities in two light-water reactor fuel cycles

    International Nuclear Information System (INIS)

    Palmer, C.R.; Hill, O.F.

    1980-07-01

    This report presents projected volumes and radioactivities of wastes from the production of electrical energy using light-water reactors (LWR). The projections are based upon data developed for a recent environmental impact statement in which the transuranic wastes (i.e., those wastes containing certain long-lived alpha emitters at concentrations of at least 370 becquerels, or 10 nCi, per gram of waste) from fuel cycle activities were characterized. In addition, since the WG.7 assumed that all fuel cycle wastes except mill tailings are placed in a mined geologic repository, the nontransuranic wastes from several activities are included in the projections reported. The LWR fuel cycles considered are the LWR, once-through fuel cycle (Strategy 1), in which spent fuel is packaged in metal canisters and then isolated in geologic formations; and the LWR U/Pu recycle fuel cycle (Strategy 2), wherein spent fuel is reprocessed for recovery and recycle of uranium and plutonium in LWRs. The wastes projected for the two LWR fuel cycles are summarized. The reactor operations and decommissioning were found to dominate the rate of waste generation in each cycle. These activities account for at least 85% of the fuel cycle waste volume (not including head-end wastes) when normalized to per unit electrical energy generated. At 10 years out of reactor, however, spent fuel elements in Strategy 1 represent 98% of the fuel cycle activity but only 4% of the volume. Similarly, the packaged high-level waste, fuel hulls and hardware in Strategy 2 concentrate greater than 95% of the activity in 2% of the waste volume

  11. Compacting biomass waste materials for use as fuel

    Science.gov (United States)

    Zhang, Ou

    Every year, biomass waste materials are produced in large quantity. The combustibles in biomass waste materials make up over 70% of the total waste. How to utilize these waste materials is important to the nation and the world. The purpose of this study is to test optimum processes and conditions of compacting a number of biomass waste materials to form a densified solid fuel for use at coal-fired power plants or ordinary commercial furnaces. Successful use of such fuel as a substitute for or in cofiring with coal not only solves a solid waste disposal problem but also reduces the release of some gases from burning coal which cause health problem, acid rain and global warming. The unique punch-and-die process developed at the Capsule Pipeline Research Center, University of Missouri-Columbia was used for compacting the solid wastes, including waste paper, plastics (both film and hard products), textiles, leaves, and wood. The compaction was performed to produce strong compacts (biomass logs) under room temperature without binder and without preheating. The compaction conditions important to the commercial production of densified biomass fuel logs, including compaction pressure, pressure holding time, back pressure, moisture content, particle size, binder effects, and mold conditions were studied and optimized. The properties of the biomass logs were evaluated in terms of physical, mechanical, and combustion characteristics. It was found that the compaction pressure and the initial moisture content of the biomass material play critical roles in producing high-quality biomass logs. Under optimized compaction conditions, biomass waste materials can be compacted into high-quality logs with a density of 0.8 to 1.2 g/cm3. The logs made from the combustible wastes have a heating value in the range 6,000 to 8,000 Btu/lb which is only slightly (10 to 30%) less than that of subbituminous coal. To evaluate the feasibility of cofiring biomass logs with coal, burn tests were

  12. Sludge derived fuel technique of sewage sludge by oil vacuum evaporation drying

    International Nuclear Information System (INIS)

    Kim, Seokhwan; Lim, Byungran; Lee, Sookoo

    2010-01-01

    Sewage sludge contains high content of organic materials and its water content is also very high about 80% even after filtration process. Landfill as a sludge treatment methods can cause odor problem and leachate production which can derive the secondary contamination of soil and groundwater. The ocean dumping will be prohibited according to the London Convention and domestic stringent environmental regulation. Based on domestic agenda on organic sewage sludge treatment, the ocean disposal will be prohibited from 2012, thus alternative methods are demanded. Sludge derived fuel (SDF) technology can alleviate the emission of greenhouse gas and recover energy from sludge. For proper treatment and SDF production from sludge, the vacuum evaporation and immersion frying technology was adopted in this research. This technology dries moisture in sludge after mixing with oil such as Bunker C oil, waste oil or waste food oil etc. Mixing sludge and oil secures liquidity of organic sludge to facilitate handling throughout the drying process. The boiling temperature could be maintained low through vacuum condition in whole evaporation process. This study was performed to find the optimum operating temperature and pressure, the mixing ratio of sludge and oil. Finally, we could obtained SDF which moisture content was less than 5%, its heating value was over 4,500 kcal/ kg sludge. This heating value could satisfy the Korean Fuel Standard for the Recycle Products. Assessed from the perspective of energy balance and economic evaluation, this sludge drying system could be widely used for the effective sludge treatment and the production of SDF. (author)

  13. Proceedings - Alternate Fuels II: The disposal and productive use of industrial wastes

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    The proceedings contain 26 papers dealing with the following topics: fuels (biomass, coal, petroleum coke, landfill gas, hazardous and toxic wastes, liquid wastes, and digester gas); combustion systems; plant systems (pollution control, combustion control, and materials handling systems); external factors (public relations, markets, hazardous waste, vitrification for waste management); and case histories of resource recovery facilities, process heating plants, and retrofits to alternative fuels. All papers have been processed separately for inclusion on the data base

  14. Commentary on the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Sheng, G.; Shemilt, L.W.

    1981-01-01

    A summary of the first formal review of the Technical Advisory Committee (TAC) to Atomic Energy of Canada Limited on the Nuclear Fuel Waste Management Program is presented. The Program is described briefly and the composition and role of TAC in relation to the Program is outlined. Salient points and major recommendations are presented from the First Annual Report of TAC in which geoscience aspects of the Program were emphasized. It is the view of the Committee that overall, the whole Waste Management Program is well conceived, that there are many impressive accomplishments of high quality, that detailed research objectives are becoming more clearly delineated, that there is growing clarification as to the most critical areas in which research needs to be accomplished and that the increasing participation by university and industry scientists and engineers is reassuring

  15. Liquid waste processing from TRIGA spent fuel storage pits

    International Nuclear Information System (INIS)

    Buchtela, Karl

    1988-01-01

    At the Atominstitute of the Austrian Universities and also at other facilities running TRIGA reactors, storage pits for spent fuel elements are installed. During the last revision procedure, the reactor group of the Atominstitute decided to refill the storage pits and to get rid of any contaminated storage pit water. The liquid radioactive waste had been pumped to polyethylene vessels for intermediate storage before decontamination and release. The activity concentration of the storage pit water at the Aominstitute after a storage period of several years was about 40 kBq/l, the total amount of liquid in the storage pits was about 0.25 m 3 . It was attempted to find a simple and inexpensive method to remove especially the radioactive Cesium from the waste solution. Different methods for decontamination like distillation, precipitation and ion exchange are discussed

  16. Methods of conditioning waste fuel decladding hulls and dissolver residues

    International Nuclear Information System (INIS)

    De Regge, P.; Loida, A.; Schmidt-Hansberg, T.; Sombret, C.

    1985-01-01

    Several methods for conditioning spent fuel decladding hulls or dissolver residues have been considered in various countries of the European Community. Five of these methods used embedding technique with or without prior compaction: they are based on incorporation in metallic alloys, glass, ceramics, cements and metals or graphite compounds. A sixth one consists in melting the decladding materials. The corresponding research programmes have been pursued to varying states of progress with regard to demonstrating their feasibility on an industrial scale and the use of genuine wastes in bench scale experiments. The properties of the conditioned wastes have been investigated. Special attention has been paid to the corrosion resistance to various aqueous media as tap water, brine or clayey water. Although no categorical conclusion can be drawn from the initial results, the available findings provide a basis for assessing the different processes

  17. Shipments of nuclear fuel and waste: are they really safe

    International Nuclear Information System (INIS)

    1977-10-01

    The safety aspects of shipping nuclear fuels and radioactive wastes are discussed by considering: US regulations on the shipment of hazardous and radioactive materials, types of radioactive wastes; packaging methods, materials, and specifications; design of shipping containers; evaluation of the risk potential under normal shipping conditions and in accident situations. It is concluded that: the risk of public catastrophe has been eliminated by strict standards, engineering design safety, and operational care; the long-term public burden of not transporting nuclear materials is likely to be higher than the risks of carefully controlled transportation, considering the various options available; and the likelihood of death, injury, or serious property damage from the nuclear aspects of nuclear transportation is thousands of times less than the likelihood of death, injury, or serious property damage from more common hazards, such as automobile accidents, boating accidents, accidental poisoning, gunshot wounds, fires, or even falls

  18. Implications of the Croatian Spent Fuel and Radioactive Waste Strategy

    International Nuclear Information System (INIS)

    Lokner, V.; Levanat, I.

    2012-01-01

    Croatian Government approved its national Radioactive waste and Spent Fuel Strategy as a part of the accession process to EU in July 2009 enabling acquisition of adequate administrative capacity by the time of accession to properly implement and enforce the relevant legislation in all areas related to nuclear safety. Strategy was formulated in line with the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. In particular, the strategy was approved to ensure that sufficient qualified staff and adequate financial services are available to support the safety of facilities for spent fuel and radioactive waste management generated by Krsko NPP during their operating lifetime and from decommissioning. Following are statements from the Croatian strategy that are relevant for Croatian position regarding capacity building for storage and disposal of LILW and SF. To be able to fulfill the obligations assumed, Croatia needs to do the following (Strategy Section 3.3): reach an agreement with Slovenia by 2013 at the latest regarding the location of objects for storing LILW; should no such agreement be reached, Croatia is to initiate preparations for assuming its half of operational LILW and for third-country export thereof, or for storing the LILW on Croatian territory, whilst also gradually assuming the part of LILW created from decommissioning; reach an agreement with Slovenia by 2018 at the latest regarding the location of a common SF storage; should no such agreement be reached, initiate preparations for assuming a third-country export of SF, or for storing half of SF on Croatian territory. This paper discusses the Strategy aims in the light of noticeable delay of 2nd revision of the Program of NPP Krsko Decommissioning and SF andLILW Disposal, the status of the planned Slovenian national repository on Vrbina site and the prospects of its use for joint Croatian/Slovenian LILW disposal - all in the context of as yet

  19. A proposed risk acceptance criterion for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Mehta, K.

    1985-06-01

    The need to establish a radiological protection criterion that applies specifically to disposal of high level nuclear fuel wastes arises from the difficulty of applying the present ICRP recommendations. These recommendations apply to situations in which radiological detriment can be actively controlled, while a permanent waste disposal facility is meant to operate without the need for corrective actions. Also, the risks associated with waste disposal depend on events and processes that have various probabilities of occurrence. In these circumstances, it is not suitable to apply standards that are based on a single dose limit as in the present ICRP recommendations, because it will generally be possible to envisage events, perhaps rare, that would lead to doses above any selected limit. To overcome these difficulties, it is proposed to base a criterion for acceptability on a set of dose values and corresponding limiting values of probabilities; this set of values constitutes a risk-limit line. A risk-limit line suitable for waste disposal is proposed that has characteristics consistent with the basic philosophy of the ICRP and UNSCEAR recommendations, and is based on levels on natural background radiation

  20. 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.)

  1. Critical review of real-time methods for solid waste characterisation: Informing material recovery and fuel production.

    Science.gov (United States)

    Vrancken, C; Longhurst, P J; Wagland, S T

    2017-03-01

    Waste management processes generally represent a significant loss of material, energy and economic resources, so legislation and financial incentives are being implemented to improve the recovery of these valuable resources whilst reducing contamination levels. Material recovery and waste derived fuels are potentially valuable options being pursued by industry, using mechanical and biological processes incorporating sensor and sorting technologies developed and optimised for recycling plants. In its current state, waste management presents similarities to other industries that could improve their efficiencies using process analytical technology tools. Existing sensor technologies could be used to measure critical waste characteristics, providing data required by existing legislation, potentially aiding waste treatment processes and assisting stakeholders in decision making. Optical technologies offer the most flexible solution to gather real-time information applicable to each of the waste mechanical and biological treatment processes used by industry. In particular, combinations of optical sensors in the visible and the near-infrared range from 800nm to 2500nm of the spectrum, and different mathematical techniques, are able to provide material information and fuel properties with typical performance levels between 80% and 90%. These sensors not only could be used to aid waste processes, but to provide most waste quality indicators required by existing legislation, whilst offering better tools to the stakeholders. Copyright © 2017 Elsevier Ltd. All rights reserved.

  2. Store for radioactive waste and burnt-up fuel elements

    International Nuclear Information System (INIS)

    Spilker, H.; Rox, R.; Peschl, H.W.

    1985-01-01

    The invention concerns a concrete storage block in which there are several vertical storage and cooling ducts for radioactive waste and burnt-up fuel elements. The storage block is assembled from several square concrete blocks. Several vertical ducts are made in these. The square blocks are placed on a concrete baseplate. The aligned ducts of several square blocks placed above each other form storage and cooling ducts for tubular storage containers. An annular gap is left for cooling air between the outside wall of the storage containers and the inside wall of the storage and cooling ducts. (orig./HP) [de

  3. Program SYVAC, for stochastic assessment of nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Sherman, G.R.; Hoffman, K.J.; Donahue, D.C.

    1985-01-01

    In this paper, the computer program SYVAC, used to assess concepts for the disposal of nuclear fuel waste, is described with regard to the development approach, the basic program structure, and quality assurance. The interrelationships of these aspects are illustrated by detailed descriptions of two concepts of fundamental importance to the program: the method of selecting parameter values from input probability density functions, and the numerical evaluation of the convolution integral. Quality assurance procedures, including different types of comparisons and peer review, are presented

  4. Second annual report of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Boulton, J.

    1980-12-01

    This report, the second of a series of annual reports, reviews in general terms the progress which has been achieved in the research and development program for the safe, permanent disposal of Canada's nuclear fuel wastes. The report summarizes activities over the past year, in the areas of public interaction, used fuel storage and transportation, immobilization of used fuel and fuel reprocessing wastes, research and development associated with deep underground disposal, and environmental and safety assessment. (auth)

  5. Fourth annual report of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Rosinger, E.L.J.; Dixon, R.S.

    1982-12-01

    This report, the fourth of a series of annual reports, reviews the progress that has been made in the research and development program for the safe management and disposal of Canada's nuclear fuel waste. The report summarizes activities over the past year in the following areas: public interaction, used fuel storage and transportation, immobilization of used fuel and fuel recycle waste, geoscience research associated with deep underground disposal, environmental research, environmental and safety assessment

  6. Third annual report of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.; Rosinger, E.L.J.

    1981-12-01

    This report, the third of a series of annual reports, reviews the progress that has been made in the research and development program for the safe management and disposal of Canada's nuclear fuel wastes. The report summarizes activities over the past year, in the areas of public interaction, irradiated fuel storage and transportation, immobilization of irradiated fuel and fuel recycle wastes, research and development associated with deep underground disposal, and environmental and safety assessment

  7. Analysis by simulation of the disposition of nuclear fuel waste

    International Nuclear Information System (INIS)

    Turek, J.L.

    1980-09-01

    A descriptive simulation model is developed which includes all aspects of nuclear waste disposition. The model is comprised of two systems, the second system orchestrated by GASP IV. A spent fuel generation prediction module is interfaced with the AFR Program Management Information System and a repository scheduling information module. The user is permitted a wide range of options with which to tailor the simulation to any desired storage scenario. The model projects storage requirements through the year 2020. The outputs are evaluations of the impact that alternative decision policies and milestone date changes have on the demand for, the availability of, and the utilization of spent fuel storage capacities. Both graphs and detailed listings are available. These outputs give a comprehensive view of the particular scenario under observation, including the tracking, by year, of each discharge from every reactor. Included within the work is a review of the status of spent fuel disposition based on input data accurate as of August 1980. The results indicate that some temporary storage techniques (e.g., transshipment of fuel and/or additional at-reactor storage pools) must be utilized to prevent reactor shutdowns. These techniques will be required until the 1990's when several AFR facilities, and possibly one repository, can become operational

  8. Thermochemical treatment of radioactive waste by using powder metal fuels

    International Nuclear Information System (INIS)

    Dmitriev, S.A.; Ojovan, M.I.; Karlina, O.K.

    2001-01-01

    Full text: A thermochemical approach was suggested for treating and conditioning specific streams of radioactive wastes for example spent ion exchange resins, mixed, organic or chlorine-containing radioactive waste as well as in order to decontaminate heavily contaminated surfaces. Conventional treatment methods of such waste encounters serious problems concerning complete destruction of organic molecules and possible emissions of radionuclides, heavy metals and chemically hazardous species or in case of contaminated materials - complete removal of contamination from surface. The thermochemical treatment of radioactive waste uses powdered metal fuels (PMF) that are specifically formulated for the waste composition and react chemically with the waste components. Thermochemical treatment technologies use the energy of chemical reactions in the mixture of waste with PMF to sustain both decomposition and synthesis processes as well as processes of isomorphic substitutions of hazardous elements into stable mineral forms. The composition of the PMF is designed in such a way as to minimise the release of hazardous components and radionuclides in the off gas and to confine the contaminants in the mineral or glass like final products. The thermochemical procedures allow decomposition of organic matter and capturing hazardous radionuclides and chemical species simultaneously. Thermochemical treatment technologies are very efficient, easy to apply, they have low capital investment and can be used both at large and small facilities. An advantage of thermochemical technologies is their autonomy. Thus these technologies can be successfully applied in order to treat small amount of waste without usage of complex and expensive equipment. They can be used also in emergency situations. Currently the thermochemical treatment technologies were developed and demonstrated to be feasible as follows: 1. Decontamination of surfaces; 2. Processing of organic waste; 3. Vitrification of dusty

  9. Derivation of Waste Acceptance Criteria for Low and Intermediate Level Waste in Surface Disposal Facility

    International Nuclear Information System (INIS)

    Gagner, L.; Voinis, S.

    2000-01-01

    In France, low- and intermediate-level radioactive wastes are disposed in a near-surface facility, at Centre de l'Aube disposal facility. This facility, which was commissioned in 1992, has a disposal capacity of one million cubic meters, and will be operated up to about 2050. It took over the job from Centre de la Manche, which was commissioned in 1969 and shut down in 1994, after having received about 520,000 cubic meters of wastes. The Centre de l'Aube disposal facility is designed to receive a many types of waste produced by nuclear power plants, reprocessing, decommissioning, as well as by the industry, hospitals and armed forces. The limitation of radioactive transfer to man and the limitation of personnel exposure in all situations considered plausible require limiting the total activity of the waste disposed in the facility as well as the activity of each package. The paper presents how ANDRA has derived the activity-related acceptance criteria, based on the safety analysis. In the French methodology, activity is considered as end-point for deriving the concentration limits per package, whereas it is the starting point for deriving the total activity limits. For the concentration limits (called here LMA) the approach consists of five steps: the determination of radionuclides important for safety with regards to operational and long-term safety, the use of relevant safety scenarios as a tool to derive quantitative limits, the setting of dose constraint per situation associated with scenarios, the setting of contribution factor per radionuclide, and the calculation of concentration activity limits. An exhaustive survey has been performed and has shown that the totality of waste packages which should be delivered by waste generators are acceptable in terms of activity limits in the Centre de l'Aube. Examples of concentration activity limits derived from this methodology are presented. Furthermore those limits have been accepted by the French regulatory body and

  10. Removal of actinides from selected nuclear fuel reprocessing wastes

    International Nuclear Information System (INIS)

    Navratil, J.D.; Thompson, G.H.

    1979-01-01

    The US Department of Energy awarded Oak Ridge National Laboratory a program to develop a cost-risk-benefit analysis of partitioning long-lived nuclides from waste and transmuting them to shorter lived or stable nuclides. Two subtasks of this program were investigated at Rocky Flats. In the first subtask, methods for solubilizing actinides in incinerator ash were tested. Two methods appear to be preferable: reaction with ceric ion in nitric acid or carbonate-nitrate fusion. The ceric-nitric acid system solubilizes 95% of the actinides in ash; this can be increased by 2 to 4% by pretreating ash with sodium hydroxide to solubilize silica. The carbonate-nitrate fusion method solubilizes greater than or equal to 98% of the actinides, but requires sodium hydroxide pretreatment. Two additional disadvantages are that it is a high-temperature process, and that it generates a lot of salt waste. The second subtask comprises removing actinides from salt wastes likely to be produced during reactor fuel fabrication and reprocessing. A preliminary feasibility study of solvent extraction methods has been completed. The use of a two-step solvent extraction system - tributyl phosphate (TBP) followed by extraction with a bidentate organophosphorous extractant (DHDECMP) - appears to be the most efficient for removing actinides from salt waste. The TBP step would remove most of the plutonium and > 99.99% of the uranium. The second step using DHDECMP would remove > 99.91% of the americium and the remaining plutonium (> 99.98%) and other actinides from the acidified salt waste. 8 figures, 11 tables

  11. Bioelectrochemical recovery of waste-derived volatile fatty acids and production of hydrogen and alkali.

    Science.gov (United States)

    Zhang, Yifeng; Angelidaki, Irini

    2015-09-15

    Volatile fatty acids (VFA) are organic compounds of great importance for various industries and environmental processes. Fermentation and anaerobic digestion of organic wastes are promising alternative technologies for VFA production. However, one of the major challenges is development of sustainable downstream technologies for VFA recovery. In this study, an innovative microbial bipolar electrodialysis cell (MBEDC) was developed to meet the challenge of waste-derived VFA recovery, produce hydrogen and alkali, and potentially treat wastewater. The MBEDC was operated in fed-batch mode. At an applied voltage of 1.2 V, a VFA recovery efficiency of 98.3%, H2 of 18.4 mL and alkali production presented as pH of 12.64 were obtained using synthetic fermentation broth. The applied voltage, initial VFA concentrations and composition were affecting the VFA recovery. The energy balance revealed that net energy (5.20-6.86 kWh/kg-VFA recovered) was produced at all the applied voltages (0.8-1.4 V). The coexistence of other anionic species had no negative effect on VFA transportation. The VFA concentration was increased 2.96 times after three consecutive batches. Furthermore, the applicability of MBEDC was successfully verified with digestate. These results demonstrate for the first time the possibility of a new method for waste-derived VFA recovery and valuable products production that uses wastewater as fuel and bacteria as catalyst. Copyright © 2015 Elsevier Ltd. All rights reserved.

  12. Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model

    Energy Technology Data Exchange (ETDEWEB)

    Denia Djokic; Steven J. Piet; Layne F. Pincock; Nick R. Soelberg

    2013-02-01

    This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system , and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity.

  13. Update on Canada's nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Allan, C.J.

    1992-09-01

    The Canadian Nuclear Fuel Waste Management Program (CNFWMP) was launched in 1978 as a joint initiative by the governments of Canada and Ontario. Under the program, AECL has been developing and assessing a generic concept to dispose of nuclear fuel waste in plutonic rock of the Canadian Shield. The disposal concept has been referred for review under the Environmental Assessment and Review Process. AECL will submit an Environmental Impact Statement (EIS) to an Environmental Assessment Panel, which was appointed in late 1989. Hearings will be held in areas that have a particular interest in the concept and its application. At the end of the review, the Panel will make recommendations as to the acceptability of the concept and the course of future action. The federal government will decide on the next steps to be taken. In the spring of 1990 public open houses were held to tell prospective participants how to enter the process. Sessions designed to assist the Panel in determining the scope of the EIS took place in the autumn of 1990. In June 1991 the Panel issued for comment a set of draft guidelines for the EIS. More than 30 groups and individuals submitted comments. The final guidelines were issued in March 1992, and AECL expects to submit its EIS to the Panel in 1993. If the concept review is completed by 1995 and if the concept is approved, disposal could begin some time after 2025. (L.L.) (12 refs.)

  14. Muon tomography for imaging nuclear waste and spent fuel verification

    Energy Technology Data Exchange (ETDEWEB)

    Jonkmans, G.; Anghel, V.N.P.; Thompson, M. [Atomic Energy of Canada Limited, Chalk River (Canada)

    2010-07-01

    This paper explores the use of cosmic ray muons to image the content of, and to detect high-Z special nuclear material inside, shielded containers. Cosmic ray muons are a naturally occurring form of radiation, are highly penetrating and exhibit large scattering angles on high Z materials. Specifically, we investigated how radiographic and tomographic techniques can be effective for non-invasive nuclear waste characterization and for nuclear material accountancy of spent fuel inside dry storage containers. We show that the tracking of individual muons, as they enter and exit a structure, can potentially improve the accuracy and availability of data on nuclear waste and the content of Dry Storage Containers (DSC) used for spent fuel storage at CANDU plants. This could be achieved in near real time, with the potential for unattended and remotely monitored operations. We show that the expected sensitivity to perform material accountancy, in the case of the DSC, exceeds the IAEA detection target for nuclear material accountancy. (author)

  15. Processing and properties of a solid energy fuel from municipal solid waste (MSW) and recycled plastics

    International Nuclear Information System (INIS)

    Gug, JeongIn; Cacciola, David; Sobkowicz, Margaret J.

    2015-01-01

    higher heating value. Analysis of the post-processing water uptake and compressive strength showed a correlation between density and stability to both mechanical stress and humid environment. Proximate analysis indicated heating values comparable to coal. The results showed that mechanical and moisture uptake stability were improved when the moisture and air contents were optimized. Moreover, the briquette sample composition was similar to biomass fuels but had significant advantages due to addition of waste plastics that have high energy content compared to other waste types. Addition of PP and HDPE presented better benefits than addition of PET due to lower softening temperature and lower oxygen content. It should be noted that while harmful emissions such as dioxins, furans and mercury can result from burning plastics, WTE facilities have been able to control these emissions to meet US EPA standards. This research provides a drop-in coal replacement that reduces demand on landfill space and replaces a significant fraction of fossil-derived fuel with a renewable alternative

  16. Processing and properties of a solid energy fuel from municipal solid waste (MSW) and recycled plastics

    Energy Technology Data Exchange (ETDEWEB)

    Gug, JeongIn, E-mail: Jeongin_gug@student.uml.edu; Cacciola, David, E-mail: david_cacciola@student.uml.edu; Sobkowicz, Margaret J., E-mail: Margaret_sobkowiczkline@uml.edu

    2015-01-15

    higher heating value. Analysis of the post-processing water uptake and compressive strength showed a correlation between density and stability to both mechanical stress and humid environment. Proximate analysis indicated heating values comparable to coal. The results showed that mechanical and moisture uptake stability were improved when the moisture and air contents were optimized. Moreover, the briquette sample composition was similar to biomass fuels but had significant advantages due to addition of waste plastics that have high energy content compared to other waste types. Addition of PP and HDPE presented better benefits than addition of PET due to lower softening temperature and lower oxygen content. It should be noted that while harmful emissions such as dioxins, furans and mercury can result from burning plastics, WTE facilities have been able to control these emissions to meet US EPA standards. This research provides a drop-in coal replacement that reduces demand on landfill space and replaces a significant fraction of fossil-derived fuel with a renewable alternative.

  17. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment

    International Nuclear Information System (INIS)

    1976-05-01

    Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes

  18. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes. (JGB)

  19. The production of fuels and chemicals from food processing wastes & cellulosics. Final research report

    Energy Technology Data Exchange (ETDEWEB)

    Dale, M.C.; Okos, M.; Burgos, N. [and others

    1997-06-15

    High strength food wastes of about 15-20 billion pounds solids are produced annually by US food producers. Low strength food wastes of 5-10 billion pounds/yr. are produced. Estimates of the various components of these waste streams are shown in Table 1. Waste paper/lignocellulosic crops could produce 2 to 5 billion gallons of ethanol per year or other valuable chemicals. Current oil imports cost the US about $60 billion dollars/yr. in out-going balance of trade costs. Many organic chemicals that are currently derived from petroleum can be produced through fermentation processes. Petroleum based processes have been preferred over biotechnology processes because they were typically cheaper, easier, and more efficient. The technologies developed during the course of this project are designed to allow fermentation based chemicals and fuels to compete favorably with petroleum based chemicals. Our goals in this project have been to: (1) develop continuous fermentation processes as compared to batch operations; (2) combine separation of the product with the fermentation, thus accomplishing the twin goals of achieving a purified product from a fermentation broth and speeding the conversion of substrate to product in the fermentation broth; (3) utilize food or cellulosic waste streams which pose a current cost or disposal problem as compared to high cost grains or sugar substrates; (4) develop low energy recovery methods for fermentation products; and finally (5) demonstrate successful lab scale technologies on a pilot/production scale and try to commercialize the processes. The scale of the wastes force consideration of {open_quotes}bulk commodity{close_quotes} type products if a high fraction of the wastes are to be utilized.

  20. 10 CFR 72.128 - Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste, and other radioactive waste storage and handling. 72.128... STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

  1. Fossil fuel derivatives with reduced carbon. Phase I final report

    Energy Technology Data Exchange (ETDEWEB)

    Kennel, E.B.; Zondlo, J.W.; Cessna, T.J.

    1999-06-30

    This project involves the simultaneous production of clean fossil fuel derivatives with reduced carbon and sulfur, along with value-added carbon nanofibers. This can be accomplished because the nanofiber production process removes carbon via a catalyzed pyrolysis reaction, which also has the effect of removing 99.9% of the sulfur, which is trapped in the nanofibers. The reaction is mildly endothermic, meaning that net energy production with real reductions in greenhouse emissions are possible. In Phase I research, the feasibility of generating clean fossil fuel derivatives with reduced carbon was demonstrated by the successful design, construction and operation of a facility capable of utilizing coal as well as natural gas as an inlet feedstock. In the case of coal, for example, reductions in CO{sub 2} emissions can be as much as 70% (normalized according to kilowatts produced), with the majority of carbon safely sequestered in the form of carbon nanofibers or coke. Both of these products are value-added commodities, indicating that low-emission coal fuel can be done at a profit rather than a loss as is the case with most clean-up schemes. The main results of this project were as follows: (1) It was shown that the nanofiber production process produces hydrogen as a byproduct. (2) The hydrogen, or hydrogen-rich hydrocarbon mixture can be consumed with net release of enthalpy. (3) The greenhouse gas emissions from both coal and natural gas are significantly reduced. Because coal consumption also creates coke, the carbon emission can be reduced by 75% per kilowatt-hour of power produced.

  2. Waste management implications of irradiated nuclear fuel storage

    International Nuclear Information System (INIS)

    Larrick, A.P.; Schneidmiller, D.

    1977-01-01

    Irradiated nuclear fuel is stored underwater in large recirculating basins prior to reprocessing in chemical separations plants. A small number of the fuel rods contain minor defects which allow fission products to seep into the basin water. The predominant radionuclides leached into the water are dependent upon the decay time after removal from the reactor. Freshly discharged fuel releases short half-lived radioiodine which presents exposure and airborne release problems on a short-term basis but does not impose significant long-term waste management problems. After a reasonable decay period, the major radionuclides present are 137 Cs, 144 Ce, 90 Sr, 3 H, and 239 / 240 Pu. Each of the radionuclides imposes specific waste management problems which require individual consideration in their control, packaging and shipment, and permanent disposal. These considerations are reviewed in this paper for general industry practices and specific illustrative examples are presented. Control of radionuclide concentrations and water purity are normally achieved by filtration and ion exchange treatment. Cartridge-type filters are the most common but improved filtration techniques that minimize personnel exposure, particularly during filter replacements, are now being adopted. Mixed bed ion exchange resins are most commonly utilized for soluble radionuclide removal, particularly for basins filled with demineralized water. Cesium-specific exchange media are employed at basins where demineralized water is not employed; these media operate for very long periods of time since they are not depleted by the normal dissolved non-radioactive water impurities. The resins are either buried when depleted or regenerated and the regeneration solutions concentrated for burial. Resin run lengths are usually determined by ionic or radiochemical depletion of the resin or in some cases by limiting radionuclide concentrations specified by shipping regulations or established ion column dose rates

  3. Nuclear fuels

    International Nuclear Information System (INIS)

    Gangwani, Saloni; Chakrabortty, Sumita

    2011-01-01

    Nuclear fuel is a material that can be consumed to derive nuclear energy, by analogy to chemical fuel that is burned for energy. Nuclear fuels are the most dense sources of energy available. Nuclear fuel in a nuclear fuel cycle can refer to the fuel itself, or to physical objects (for example bundles composed of fuel rods) composed of the fuel material, mixed with structural, neutron moderating, or neutron reflecting materials. Long-lived radioactive waste from the back end of the fuel cycle is especially relevant when designing a complete waste management plan for SNF. When looking at long-term radioactive decay, the actinides in the SNF have a significant influence due to their characteristically long half-lives. Depending on what a nuclear reactor is fueled with, the actinide composition in the SNF will be different. The following paper will also include the uses. advancements, advantages, disadvantages, various processes and behavior of nuclear fuels

  4. Key convention on safe management of spent fuel and radioactive waste to enter into force

    International Nuclear Information System (INIS)

    2001-01-01

    At a ceremony at IAEA Headquarters today, Ireland deposited its instrument of ratification to an important convention on the safe management of spent fuel and radioactive waste, thereby ensuring its entry into force. The Convention will be the first international instrument to address the safety of management and storage of radioactive wastes and spent fuels in countries with and without nuclear programmes

  5. The concept of radioactive waste and spent nuclear fuel management in the Czech Republic

    International Nuclear Information System (INIS)

    Suransky, F.; Duda, V.

    2003-01-01

    The article briefly comments on the status of nuclear waste and spent nuclear fuel management in the Czech Republic in the context of the document entitled 'The Concept of Radioactive Waste and Spent Nuclear Fuel Management in the Czech Republic', which was adopted by the Czech Government in May 2002 as a national strategy in this field. (author)

  6. Alternative fuel produced from thermal pyrolysis of waste tires and its use in a DI diesel engine

    International Nuclear Information System (INIS)

    Wang, Wei-Cheng; Bai, Chi-Jeng; Lin, Chi-Tung; Prakash, Samay

    2016-01-01

    Highlights: • The liquid, solid and gas yields from pyrolysis of waste tires were investigated. • For energy and economic consideration, pre-treatments of TPO were avoided. • Various proportions of TPO-diesel mixture were tested in a DI diesel engine. • TPOs derived from various pyrolysis temperatures were also tested in engine. • Fuel consumption, cylinder pressure, engine power, and SO2 emission were discussed. - Abstract: Alternative fuels from waste material have been receiving attentions due to the increasing demand of fossil fuels. Pyrolysis has been a considerable solution for processing waste tires because it gives clean emissions and produces valuable liquid or solid products. Pyrolysis oil from waste tires has become a potential replacement for petroleum diesel due to the similar physical and chemical properties to diesel fuel. In this study, waste tires were pyrolyzed in a lab-scale fixed bed reactor with various reaction temperatures. The liquid, solid and gas product yields from different pyrolysis temperatures were compared, as well as the analyses of property and element for the oil product. Due to the energy and economic consideration, the pre-treatments of TPO before adding into regular diesel were avoided. The TPO derived from various pyrolysis temperatures were mixed with regular diesel at different proportions and subsequently tested in a DI diesel engine. The engine performance, such as fuel consumption, cylinder pressure, engine power, and SO_2 emission, were examined and discussed. The results indicated that increasing the TPO fraction in diesel lead to worse engine performance, but it can be recovered using TPOs produced from higher pyrolysis temperatures.

  7. Site Specific Waste Management Instructions for loading and shipment of category 3 investigation derived waste to ERDF

    International Nuclear Information System (INIS)

    Corriveau, C.E.; Wolf, D.M.

    1996-08-01

    This Site Specific Waste Management Instruction (SSWMI) provides guidance for management of containerized investigation-derived waste being loaded and transported to the Environmental Restoration Disposal Facility. The SSWMI outlines the waste management practices that will be performed in the field to implement federal, state, and US Department of Energy requirements. Additional guidance for waste packaging, marking, labeling and shipping is provided (US DOT rules in 49 CFR have precedence)

  8. Acceptance of failed SNF [spent nuclear fuel] assemblies by the Federal Waste Management System

    International Nuclear Information System (INIS)

    1990-03-01

    This report is one of a series of eight prepared by E. R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high level waste will be accepted in the following categories: failed fuel; consolidated fuel and associated structural parts; non-fuel-assembly hardware; fuel in metal storage casks; fuel in multi-element sealed canisters; inspection and testing requirements for wastes; canister criteria; spent fuel selection for delivery; and defense and commercial high-level waste packages. This document discusses acceptance of failed spent fuel assemblies by the Federal Waste Management System. 18 refs., 7 figs., 25 tabs

  9. Soot and chemiluminescence in diesel combustion of bio-derived, oxygenated and reference fuels

    NARCIS (Netherlands)

    Klein-Douwel, R.J.H.; Donkerbroek, A.J.; Vliet, A.P. van; Boot, M.D.; Somers, L.M.T.; Baert, R.S.G.; Dam, N.J.; Meulen, J.J. ter

    2009-01-01

    High-speed imaging, spectroscopy and thermodynamical characterization are applied to an optically accessible, heavy-duty diesel engine in order to compare sooting and chemiluminescence behaviour of bio-derived, oxygenated fuels and various reference fuels. The fuels concerned include the bio-derived

  10. Characteristics of Waste Plastics Pyrolytic Oil and Its Applications as Alternative Fuel on Four Cylinder Diesel Engines

    Directory of Open Access Journals (Sweden)

    Nosal Nugroho Pratama

    2014-02-01

    Full Text Available Waste plastics recycling using pyrolysis method is not only able to decrease a number of environment pollutant but also able to produce economical and high quality hydrocarbon products. Two experiments were conducted to completely study Waste Plastic Pyrolytic Oil (WPPO characteristics and its applications.  First experiment investigated oil characteristics derived from pyrolysis process in two stages batch reactors: pyrolysis and catalytic reforming reactor, at maximum temperature 500oC and 450oC respectively. Waste Polyethylene (PE, Polypropylene (PP, Polystyrene (PS, Polyethylene Terepthalate (PET and others were used as raw material. Nitrogen flow rate at 0.8 l/minutes was used to increase oil weight percentage. Indonesian natural zeolite was used as catalyst. Then, second experiment was carried out on Diesel Engine Test Bed (DETB used blending of WPPO and Biodiesel fuel with a volume ratio of 1:9. This experiment was specifically conducted to study how much potency of blending of WPPO and biodiesel in diesel engine. The result of first experiment showed that the highest weight percentage of WPPO derived from mixture of PE waste (50%wt, PP waste (40%wt and PS waste (10%wt is 45.13%wt. The more weight percentage of PE in feedstock effected on the less weight percentage of WPPO, the more percentage of C12-C20 content in WPPO and the higher calorific value of WPPO. Characteristics of WPPO such as, Specific Gravity, Flash point, Pour Point, Kinematic Viscosity, Calorific value and percentage of C12-C20 showed interesting result that WPPO could be developed as alternative fuel on diesel fuel blending due to the proximity of their characteristics. Performance of diesel engine using blending of WPPO and biodiesel on second experiment gave good result so the WPPO will have great potency to be valuable alternative liquid fuel in future, especially on stationary diesel engine and transportation engine application.

  11. Waste arisings from a high-temperature reactor with a uranium-thorium fuel cycle

    International Nuclear Information System (INIS)

    1979-09-01

    This paper presents an equilibrium-recycle condition flow sheet for a high-temperature gas-cooled reactor (HTR) fuel cycle which uses thorium and high-enriched uranium (93% U-235) as makeup fuel. INFCE Working Group 7 defined percentage losses to various waste streams are used to adjust the heavy-element mass flows per gigawatt-year of electricity generated. Thorium and bred U-233 are recycled following Thorex reprocessing. Fissile U-235 is recycled one time following Purex reprocessing and then is discarded to waste. Plutonium and other transuranics are discarded to waste. Included are estimates of volume, radioactivity, and heavy-element content of wastes arising from HTR fuel element fabrication; HTR operation, maintenance, and decommissioning; and reprocessing spent fuel where the waste is unique to the HTR fuel cycle

  12. Low carbon fuel and chemical production from waste gases

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, S.; Liew, F.M.; Daniell, J.; Koepke, M. [LanzaTech, Ltd., Auckland (New Zealand)

    2012-07-01

    LanzaTech has developed a gas fermentation platform for the production of alter native transport fuels and commodity chemicals from carbon monoxide, hydrogen and carbon dioxide containing gases. LanzaTech technology uses these gases in place of sugars as the carbon and energy source for fermentation thereby allowing a broad spectrum of resources to be considered as an input for product synthesis. At the core of the Lanzatech process is a proprietary microbe capable of using gases as the only carbon and energy input for product synthesis. To harness this capability for the manufacture of a diverse range of commercially valuable products, the company has developed a robust synthetic biology platform to enable a variety of novel molecules to be synthesised via gas fermentation. LanzaTech initially focused on the fermentation of industrial waste gases for fuel ethanol production. The company has been operating pilot plant that uses direct feeds of steel making off gas for ethanol production for over 24 months. This platform technology has been further successfully demonstrated using a broad range of gas inputs including gasified biomass and reformed natural gas. LanzaTech has developed the fermentation, engineering and control systems necessary to efficiently convert gases to valuable products. A precommercial demonstration scale unit processing steel mill waste gases was commissioned in China during the 2{sup nd} quarter of 2012. Subsequent scale-up of this facility is projected for the 2013 and will represent the first world scale non-food based low carbon ethanol project. More recently LanzaTech has developed proprietary microbial catalysts capable of converting carbon dioxide in the presence of hydrogen directly to value added chemicals, where-in CO{sub 2} is the sole source of carbon for product synthesis. Integrating the LanzaTech technology into a number of industrial facilities, such as steel mills, oil refineries and other industries that emit Carbon bearing

  13. Management of waste from french nuclear fuel cycle: what are the key issues?

    International Nuclear Information System (INIS)

    Londres, V.; Do Quang, R.; Fournier, P.

    2000-01-01

    Like any other industry, the nuclear industry generates waste. This waste arises in the different successive stages of the fuel cycle, including nuclear power plants, and its physical and chemical properties vary greatly. What is special about it is the radioactivity it contains. Management of waste generated by spent fuel conditioning in nuclear reprocessing facilities, and which cannot be stored in surface repositories, according to current French regulations (ILW and HLW), is specifically discussed in this paper. (authors)

  14. Separation of harmful impurities from refuse derived fuels (RDF) by a fluidized bed.

    Science.gov (United States)

    Krüger, B; Mrotzek, A; Wirtz, S

    2014-02-01

    In firing systems of cement production plants and coal-fired power plants, regular fossil fuels are increasingly substituted by alternative fuels. Rising energy prices and ambitious CO2-reduction goals promote the use of alternative fuels as a significant contribution to efficient energy recovery. One possibility to protect energy resources are refuse-derived fuels (RDF), which are produced during the treatment of municipal solid, commercial and industrial waste. The waste fractions suitable for RDF have a high calorific value and are often not suitable for material recycling. With current treatment processes, RDF still contains components which impede the utilization in firing systems or limit the degree of substitution. The content of these undesired components may amount to 4 wt%. These, in most cases incombustible particles which consist of mineral, ceramic and metallic materials can cause damages in the conveying systems (e. g. rotary feeder) or result in contaminations of the products (e. g. cement, chalk). Up-to-date separation processes (sieve machine, magnet separator or air classifier) have individual weaknesses that could hamper a secure separation of these particles. This article describes a new technology for the separation of impurities from refuse derived fuels based on a rotating fluidized bed. In this concept a rotating motion of the particle bed is obtained by the tangential injection of the fluidization gas in a static geometry. The RDF-particles experience a centrifugal force which fluidized the bed radially. The technical principle allows tearing up of particle clusters to single particles. Radially inwards the vertical velocity is much lower thus particles of every description can fall down there. For the subsequent separation of the particles by form and density an additionally cone shaped plate was installed in the centre. Impurities have a higher density and a compact form compared to combustible particles and can be separated with a high

  15. Trends for minimization of radioactive waste arising from spent nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Polyakov, A.S.; Koltunov, V.S.; Marchenko, V.I.; Ilozhev, A.P.; Mukhin, I.V.

    2000-01-01

    Research and development of technologies for radioactive waste (RAW) minimization arising from spent nuclear fuel reprocessing are discussed. Novel reductants of Pu and Np ions, reagents of purification recycled extractant, possibility of the electrochemical methods are studied. The partitioning of high activity level waste are considered. Examples of microbiological methods decomposition of radioactive waste presented. (authors)

  16. Spent Fuel and Waste Management Technology Development Program. Annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Bryant, J.W.

    1994-01-01

    This report provides information on the progress of activities during fiscal year 1993 in the Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) at the Idaho Chemical Processing Plant (ICPP). As a new program, efforts are just getting underway toward addressing major issues related to the fuel and waste stored at the ICPP. The SF&WMTDP has the following principal objectives: Investigate direct dispositioning of spent fuel, striving for one acceptable waste form; determine the best treatment process(es) for liquid and calcine wastes to minimize the volume of high level radioactive waste (HLW) and low level waste (LLW); demonstrate the integrated operability and maintainability of selected treatment and immobilization processes; and assure that implementation of the selected waste treatment process is environmentally acceptable, ensures public and worker safety, and is economically feasible.

  17. Radioactive waste management in a fuel reprocessing facility in fiscal 1982

    International Nuclear Information System (INIS)

    1984-01-01

    In the fuel reprocessing facility of the Power Reactor and Nuclear Fuel Development Corporation, radioactive gaseous and liquid waste are released not exceeding the respective permissible levels. Radioactive concentrated solutions are stored at the site. Radioactive solid waste are stored appropriately at the site. In fiscal 1982, the released quantities of radioactive gaseous and liquid waste were both below the permissible levels. The results of radioactive waste management in the fuel reprocessing facility in fiscal 1982 are given in the tables: the released quantities of radioactive gaseous and liquid waste, the produced quantities of radioactive solid waste, and the stored quantities of radioactive concentrated solutions and of radioactive solid waste as of the end of fiscal 1982. (Mori, K.)

  18. 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

  19. The Canadian program for management of spent fuel and high level wastes

    International Nuclear Information System (INIS)

    Barnes, R.W.; Mayman, S.A.

    A brief history and description of the nuclear power program in Canada is given. Schedules and programs are described for storing spent fuel in station fuel bays, centralized water pool storage facilities, concrete canisters, convection vaults, and rock or salt formations. High-level wastes will be retrievable initially, therefore the focus is on storage in mined cavities. The methods developed for high-level waste storage/disposal will ideally be flexible enough to accommodate spent fuel. (E.C.B.)

  20. Conversion of fuel hulls to zirconate ion exchangers for stabilization of wastes from the thorium fuel cycle

    International Nuclear Information System (INIS)

    Levine, H.S.

    1978-01-01

    A conceptual reprocessing and waste management scheme for Zircaloy clad ThO 2 fuel was formulated to eliminate problems associated with concurrent dissolution of fuel and cladding in the conventional chop-leach headend step. These problems are avoided by use of a modified headend step to form oxide fuel and cladding process streams. A chlorinating agent then converts the cladding hulls and adhering fuel into volatile and nonvolatile chloride fractions. The former product is processed, by use of the Zircaloy conversion process, to form an inorganic ion exchange material and combined with HLLW from subsequent fuel reprocessing to form a stable and refractory waste form. The nonvolatile chloride fraction would be recovered, processed to remove chloride ions, and recombined with the main oxide fuel process stream for further treatment by use of the Thorex process

  1. Integrated data management system for radioactive waste and spent fuel in Korea

    International Nuclear Information System (INIS)

    Shin, Young Ho

    2001-03-01

    An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. So through the system, the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized, and public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information, it can ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management), the system can compensate for the imperfections in safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control and finally re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal. For this objectives, benchmark study was performed on similar data base system worldwide and data specification with major input/output data during the first phase of this project

  2. Towards a regional siting approach for canadian nuclear fuel waste

    International Nuclear Information System (INIS)

    Kuhn, R.G.

    1999-01-01

    The proposal to construct a nuclear fuel waste (NFW) disposal facility in Canada is fraught with difficulties, particularly with respect to gaining public acceptance and consent. Public perceptions of risk associated with a disposal facility are generally negative. Indeed, it was found that over 60% of residents in northern Ontario communities are opposed to the possibility of a disposal facility being constructed within 120 km of their community. Even after being offered the possibility of compensation and incentives, the majority of residents are strongly opposed. Canadian decision makers have generally endorsed a siting framework known as the open siting approach. The major characteristic of this approach is that it allows for substantial public participation in any siting process. It is premised on the notion that only communities where a majority of citizens favour the siting of a facility will be considered as potential hosts. However, given that the majority of residents on the Ontario portion of the Canadian Shield are strongly opposed to a NFW facility, the open approach will not be a panacea for a successful siting process. The major limitation of this approach is the fact that a single community cannot be isolated from its surrounding region and communities. The purpose of this paper is to work towards the development of a regional siting strategy for Canadian nuclear fuel waste management. There are no clear precedents of a regional siting approach to facility location in Canada. However, some analogous planning regimes and initiatives have been attempted. Common to these initiatives is the consideration of a large geographical region and attempts to integrate, at least formally, social, cultural, political and environmental concerns in a coherent and comprehensive manner. Under this type of 'siting strategy' NFW management would be considered within a broad array of resource management initiatives, social and cultural priorities, and institutional

  3. Radionuclide compositions of spent fuel and high level waste for the uranium and plutonium fuelled PWR

    International Nuclear Information System (INIS)

    Fairclough, M.P.; Tymons, B.J.

    1985-06-01

    The activities of a selection of radionuclides are presented for three types of reactor fuel of interest in radioactive waste management. The fuel types are for a uranium 'burning' PWR, a plutonium 'burning' PWR using plutonium recycled from spent uranium fuel and a plutonium 'burning' PWR using plutonium which has undergone multiple recycle. (author)

  4. Safety Aspects of Radioactive Waste Management in Different Nuclear Fuel Cycle Policies, a Comparative Study

    International Nuclear Information System (INIS)

    Gad Allah, A.A.

    2009-01-01

    With the increasing demand of energy worldwide, and due to the depletion of conventional natural energy resources, energy policies in many countries have been devoted to nuclear energy option. On the other hand, adopting a safe and reliable nuclear fuel cycle concept guarantees future nuclear energy sustain ability is a vital request from environmental and economic point of views. The safety aspects of radioactive waste management in the nuclear fuel cycle is a topic of great importance relevant to public acceptance of nuclear energy and the development of nuclear technology. As a part of nuclear fuel cycle safety evaluation studies in the department of nuclear fuel cycle safety, National Center for Nuclear Safety and Radiation Control (NCNSRC), this study evaluates the radioactive waste management policies and radiological safety aspects of three different nuclear fuel cycle policies. The once-through fuel cycle (OT- fuel cycle) or the direct spent fuel disposal concept for both pressurized light water reactor ( PWR) and pressurized heavy water reactor (PHWR or CANDU) systems and the s elf-generated o r recycling fuel cycle concept in PWR have been considered in the assessment. The environmental radiological safety aspects of different nuclear fuel cycle options have been evaluated and discussed throughout the estimation of radioactive waste generated from spent fuel from these fuel cycle options. The decay heat stored in the spent fuel was estimated and a comparative safety study between the three fuel cycle policies has been implemented

  5. Status of nuclear fuel reprocessing, spent fuel storage, and high-level waste disposal. Nuclear Fuel Cycle Committee, California Energy Resources Conservation and Development Commission. Draft report

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    An analysis of the current status of technologies and issues in the major portions of the back-end of the nuclear fuel cycle is presented. The discussion on nuclear fuel reprocessing covers the reprocessing requirement, reprocessing technology assessment, technology for operation of reprocessing plants, and approval of reprocessing plants. The chapter devoted to spent fuel storage covers the spent fuel storge problem, the legislative response, options for maintaining full core discharge capacity, prospective availability of alterntive storage options, and the outlook for California. The existence of a demonstrated, developed high-level waste disposal technology is reviewed. Recommendations for Federal programs on high-level waste disposal are made

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

    Science.gov (United States)

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

  7. Structure–mechanics property relationship of waste derived biochars

    International Nuclear Information System (INIS)

    Das, Oisik; Sarmah, Ajit K.; Bhattacharyya, Debes

    2015-01-01

    The widespread applications of biochar in agriculture and environmental remediation made the scientific community ignore its mechanical properties. Hence, to examine the scope of biochar's structural applications, its mechanical properties have been investigated in this paper through nanoindentation technique. Seven waste derived biochars, made under different pyrolysis conditions and from diverse feedstocks, were studied via nanoindentation, infrared spectroscopy, X–ray crystallography, thermogravimetry, and electron microscopy. Following this, an attempt was made to correlate the biochars' hardness/modulus with reaction conditions and their chemical properties. The pine wood biochar made at 900 °C and 60 min residence time was found to have the highest hardness and elastic modulus of 4.29 and 25.01 GPa, respectively. It was shown that a combination of higher heat treatment (≥ 500 °C) temperature and longer residence time (~ 60 min) increases the values of hardness and modulus. It was further realized that pyrolysis temperature was a more dominant factor than residence time in determining the final mechanical properties of biochar particles. The degree of aromaticity and crystallinity of the biochar were also correlated with higher values of hardness and modulus. - Highlights: • Characterization was done on waste based biochars which included nanoindentation. • Pine saw dust biochar made at 900 °C for 60 min had highest hardness/modulus. • Combination of temperature/residence time affect biochar's mechanical propertie.s • Aromaticity and crystallinity positively affected biochar's mechanical properties.

  8. Corrosion of copper under Canadian nuclear fuel waste disposal conditions

    International Nuclear Information System (INIS)

    King, F.; Litke, C.D.

    1990-01-01

    The corrosion of copper was studied under Canadian nuclear fuel waste disposal conditions. The groundwater in a Canadian waste vault is expected to be saline, with chloride concentrations from 0.1 to 1.0 mol/l. The container would be packed in a sand/clay buffer, and the maximum temperature on the copper surface would be 100C; tests were performed up to 150C. Radiation fields will initially be around 500 rad/h, and conditions will be oxidizing. Sulfides may be present. The minimum design lifetime for the container is 500 years. Most work has been done on uniform corrosion, although pitting has been considered. It was found that the rate of uniform corrosion in aerated NaCl at room temperature is limited by the rate of the anodic reaction, which is controlled mainly by the rate of transport of dissolved metal species away from the copper surface. The rate of corrosion should become controlled by the transport of oxygen to the copper surface only at very low oxygen concentrations. In the presence of gamma radiation the corrosion rate may never become cathodically transport limited. In compacted buffer material, the corrosion rate appears to be limited by the rate of transport of copper species away from the corroding surface. The authors recommend that long-term predictions of container lifetime should be based on the known rate-determining step for the overall corrosion process. 8 refs

  9. Status of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Allan, C.J.; Stephens, M.E.

    1992-01-01

    The Canadian Concept for the permanent disposal of nuclear fuel waste has been developed extensively over the past several years, and is now well-advanced. The Concept, which involves the construction of a waste vault 500 to 1000 metres deep in plutonic rock located in the Canadian Precambrian Shield, is supported by an R ampersand D program with the following objectives: (1) to develop and demonstrate technology to site, design, build and operate a disposal facility; (2) to develop and demonstrate a methodology to evaluate the performance of the disposal system; and (3) to demonstrate that sites are likely to exist in the Canadian Precambrian Shield that would meet the regulatory requirements. A combination of engineered and natural barriers will be used to ensure that the vault design will meet rigorous safety standards. Experimental work is being carried out to elucidate all the important phenomena associated with the safety of the vault, including the performance of engineered barriers, natural geological barriers, and the biosphere

  10. Environmental Justice, Place and Nuclear Fuel Waste Management in Canada

    International Nuclear Information System (INIS)

    Kuhn, Richard G.

    2006-01-01

    The purpose of this paper is to outline the basis of a Nuclear Fuel Waste management strategy for Canada, taking into account the unique legal tenets (Aboriginal rights; federal - provincial jurisdiction) and the orientation that the Nuclear Waste Management Organization (NWMO) has taken to date. The focus of the paper are grounded in notions of environmental justice. Bullard's definition provides a useful guideline: 'the fair treatment and meaningful involvement of all people regardless of race, colour, national origin or income with respect to the development, implementation and enforcement of environmental laws, regulations and policies'. The overriding concern is to work towards a process that is inclusive and just. Prior to developing a specific strategy to site a NFW disposal facility, we maintain that the NWMO needs to first address three fundamental issues: Expand its mandate to include the future of nuclear energy in Canada; Provide an inclusive role for First Nations (Aboriginal people) in all stages of the process; Adhere to the requirement of specifying an economic region and deal more overtly with the transportation of NF

  11. Environmental Justice, Place and Nuclear Fuel Waste Management in Canada

    Energy Technology Data Exchange (ETDEWEB)

    Kuhn, Richard G. [Univ. of Guelph (Canada). Dept. of Geography; Murphy, Brenda L. [Wilfrid Launer Univ., Brantford (Canada)

    2006-09-15

    The purpose of this paper is to outline the basis of a Nuclear Fuel Waste management strategy for Canada, taking into account the unique legal tenets (Aboriginal rights; federal - provincial jurisdiction) and the orientation that the Nuclear Waste Management Organization (NWMO) has taken to date. The focus of the paper are grounded in notions of environmental justice. Bullard's definition provides a useful guideline: 'the fair treatment and meaningful involvement of all people regardless of race, colour, national origin or income with respect to the development, implementation and enforcement of environmental laws, regulations and policies'. The overriding concern is to work towards a process that is inclusive and just. Prior to developing a specific strategy to site a NFW disposal facility, we maintain that the NWMO needs to first address three fundamental issues: Expand its mandate to include the future of nuclear energy in Canada; Provide an inclusive role for First Nations (Aboriginal people) in all stages of the process; Adhere to the requirement of specifying an economic region and deal more overtly with the transportation of NF.

  12. Refuse-derived fuel as a secondary energy in Taiwan - Using Hotelling space allocation model

    International Nuclear Information System (INIS)

    Kwodong Wey; Sheueching Hong

    2006-01-01

    Most Taiwanese farmers usually blend rice straws into the soil after harvest. However, rice straws possess great thermal energy, which can be used to produce refuse-derived fuel (RDF-5). As Taiwan faces energy shortage, the development benefits of the RDF-5 industry are tempting. This study employs the Hotelling model to design the locations and the optimal numbers of RDF-5 plants. From the technology and material supply point of view, turning waste rice straws into RDF-5 is feasible in Taiwan. Nevertheless, from the business operation perspective, even if the RDF-5 plant is willing to lower its profit rate, its selling price is still hard to compete with imported RDF-5. If the Taiwanese government decides to pursue RDF-5 as an alternative energy, they might need to take a step further to subsidize entrepreneurs or provide appropriate tax benefits. Otherwise, the RDF-5 industry is hard to survive in Taiwan. (Author)

  13. The geochemical environment of nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Gascoyne, M.

    1995-01-01

    The concept for disposal of Canada's nuclear fuel waste in a geologic environment on the Canadian Shield has recently been presented by Atomic Energy of Canada Limited (AECL) to governments, scientists, and the public, for review. An important part of this concept concerns the geochemical environment of a disposal vault and includes consideration of rock and groundwater compositions, geochemical interactions between rocks, groundwaters, and emplaced vault materials, and the influences and significance of anthropogenic and microbiological effects following closure of the vault. This paper summarizes the disposal concept and examines aspects of the geochemical environment. The presence of saline groundwaters and reducing conditions at proposed vault depths (500-1000 m) in the Canadian Shield has an important bearing on the stability of the used nuclear fuel, its container, and buffer and backfill materials. The potential for introduction of anthropogenic contaminants and microbes during site investigations and vault excavation, operation, and sealing is described with examples from AECL's research areas on the Shield and in their underground research laboratory in southeastern Manitoba. (author)

  14. International trade and waste and fuel management issue, 2009

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2009-01-15

    The focus of the January-February issue is on international trade and waste and fuel managment. Major articles/reports in this issue include: Innovative financing and workforce planning, by Donna Jacobs, Entergy Nuclear; Nuclear power - a long-term need, by John C. Devine, Gerald Goldsmith and Michael DeLallo, WorleyParsons; Importance of loan guarantee program, by Donald Hintz; EPC contracts for new plants, by Dave Barry, Shaw Power Group; GNEP and fuel recycling, by Alan Hanson, AREVA NC Inc.; Safe and reliable reactor, by Kiyoshi Yamauchi, Mitsubishi Heavy Industries, Ltd.; Safe, small and simple reactors, by Yoshi Sakashita, Toshiba Corporation; Nuclear power in Thailand, by Tatchai Sumitra, Thailand Institute of Nuclear Technology; and, Nuclear power in Vietnam, by Tran Huu Phat, Vietnam Atomic Energy Commission. The Industry Innovation article this issue is Rectifying axial-offset-anomaly problems, by Don Adams, Tennessee Valley Authority. The Plant Profile article is Star of Stars Excellence, by Tyler Lamberts, Entergy Nuclear Operations, Inc.

  15. Permitting a tire-derived fuel system : a case study : Lafarge's Bath Plant

    Energy Technology Data Exchange (ETDEWEB)

    Cumming, R. [Lafarge North America, Herndon, VA (United States)

    2006-07-01

    Details of a proposed automated tire-derived fuel (TDF) system for an Ontario cement plant using mid-kiln technology were presented. The TDF system will replace approximately 20 per cent of the coal currently used by the cement plant. TDF is a proven technology that is gaining wider acceptance in both North America and Europe. Recent European Union (EU) rulings have placed energy recovery from waste high within the waste management hierarchy. In order to obtain a permit to operate the TDF system in Ontario, owners of the cement plant were obliged to hold preliminary engineering sessions in addition to informal sessions, comment periods and government reviews. The plant is required to meet emission and operational standards and the Industry Emission Reduction Program regardless of the fuel type it uses. Issues complicating the permitting process included the public perception that TDF will result in higher air emissions. However, statistics from other plants using TDF have demonstrated that TDF lowers nitrogen oxide (NO{sub x}) emissions compared to coal NO{sub x} emissions, and using TDF may result in fewer uncontained tire fires that pollute the atmosphere. The cement plant will use an electrostatic precipitator that is currently seen as the best available technology for controlling TDF emissions. Continuous emission monitoring will take place, and stack testing will be required when introducing alternative fuels. In order to engage with the public, the cement plant has promised to have a live, public display of emission levels, and has agreed to be monitored by a citizen's watch committee. A 2 year demonstration period will be established once TDF has been introduced, and annual reporting requirements will be fulfilled. It was concluded that the cement plant's emission standards will be stricter than any other cement plant in Ontario when TDF is introduced. refs., tabs., figs.

  16. Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities. Specific Safety Guide

    International Nuclear Information System (INIS)

    2016-01-01

    This Safety Guide provides guidance on the predisposal management of all types of radioactive waste (including spent nuclear fuel declared as waste and high level waste) generated at nuclear fuel cycle facilities. These waste management facilities may be located within larger facilities or may be separate, dedicated waste management facilities (including centralized waste management facilities). The Safety Guide covers all stages in the lifetime of these facilities, including their siting, design, construction, commissioning, operation, and shutdown and decommissioning. It covers all steps carried out in the management of radioactive waste following its generation up to (but not including) disposal, including its processing (pretreatment, treatment and conditioning). Radioactive waste generated both during normal operation and in accident conditions is considered

  17. Spent fuel and radioactive waste inventories and projections as of December 31, 1980

    International Nuclear Information System (INIS)

    1981-09-01

    Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled, based on the most reliable information available from Government sources and the open literature, technical reports, and direct contacts. Future waste generation rates and characteristics of these materials to be accumulated over the remainder of this century are also presented, based on a present DOE/EIA projection of US commercial nuclear power growth and expected defense-related and industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level wastes, transuranic waste, low-level waste, remedial action waste, active uranium mill tailings, and airborne waste. For each category, current and projected inventories are given through the year 2000. The land usage requirements are given for storage/disposal of low-level and transuranic wastes, and for the present inventories of inactive uranium mill tailings

  18. Evaluation of treatment alternatives for wastes from both spent fuel rod consolidation and miscellaneous commercial activities

    International Nuclear Information System (INIS)

    Ross, W.A.; Schneider, K.J.; Oma, K.H.; Smith, R.I.; Bunnell, L.R.

    1986-07-01

    Alternative treatments were considered for both existing commercial transuranic wastes and future wastes from spent fuel rod consolidation. Waste treatment was assumed to occur at a hypothetical central treatment facility (a Monitored Retrieval Storage [MRS] facility was used as a reference). Disposal of the waste in a geologic repository was also assumed. The waste form charcteristics, process characteristics, and costs were evaluated for each waste treatment alternative. The evaluation indicated that selection of a high volume reduction alternative can save almost $1 billion in life-cycle costs for the management of transuranic and high-activity wastes from 70,000 MTU of spent fuel compared to the reference MRS waste treatment processes. The supercompaction, arc pyrolysis and melting, and maximum volume reduction alternatives are recommended for further consideration; the latter two are recommended for further testing and demonstration

  19. Polystyrene Plastic Waste Conversion into Liquid Fuel with Catalytic Cracking Process Using Al2O3 as Catalyst

    Directory of Open Access Journals (Sweden)

    Nurul Kholidah

    2018-01-01

    Full Text Available The increase in energy consumption and an increase in the plastic waste generation are two major problems that arise along with economic growth and the increase in population. Styrofoam is one type of polystyrene plastic waste that can be processed into liquid fuels by cracking process. In this study, the cracking process of polystyrene plastic waste into liquid fuel carried by the catalytic cracking process using Al2O3 as a catalyst. This study aimed to determine the effect of the catalyst weight, length of cracking time and range of temperature in the catalytic cracking process of polystyrene plastic waste into liquid fuel toward the mass and characteristics of liquid fuels produced and to determine the composition of liquid fuels produced. The catalytic cracking process of polystyrene plastic waste with catalyst was done in the fixed bed type reactor by heating the reactor with a heater, where the process took place at temperature of 150°C, 200°C, 250°C and 300°C and the length of the process was varied into 20, 40, and 60 minutes and the catalyst weight was also varied, which were 4%, 6% and 8%, while the styrofoam weight was 250 grams. From the research, the highest mass of liquid fuel derived from polystyrene catalytic cracking process was in the amount of 48.8 grams and liquid yield percentage of 19.5% at temperature of  250°C, cracking time of 60 minutes and weight of 8% catalyst, while the characteristics of liquid fuel that were approaching the characteristics of gasoline was at temperatures of 250°C, cracking time of 60 minutes and weight of 6% catalyst, in which each value of density of 0.763 g/ml, specific gravity of 0.778 and oAPI gravity of 50.2. While other liquid fuels obtained from the cracking of polystyrene were still within the tolerance range characteristic properties of gasoline. Liquid fuels produced from the catalytic cracking process was analyzed using a GC-MS, in which the analysis results indicated that liquid

  20. Environmental control aspects for fabrication, reprocessing and waste disposal of alternative LWR and LMFBR fuels

    International Nuclear Information System (INIS)

    Nolan, A.M.; Lewallen, M.A.; McNair, G.W.

    1979-11-01

    Environmental control aspects of alternative fuel cycles have been analyzed by evaluating fabrication, reprocessing, and waste disposal operations. Various indices have been used to assess potential environmental control requirements. For the fabrication and reprocessing operations, 50-year dose commitments were used. Waste disposal was evaluated by comparing projected nuclide concentrations in ground water at various time periods with maximum permissible concentrations (MPCs). Three different fabrication plants were analyzed: a fuel fabrication plant (FFP) to produce low-activity uranium and uranium-thorium fuel rods; a plutonium fuel refabrication plant (PFRFP) to produce plutonium-uranium and plutonium-thorium fuel rods; and a uranium fuel refabrication plant (UFRFP) to produce fuel rods containing the high-activity isotopes 232 U and 233 U. Each plant's dose commitments are discussed separately. Source terms for the analysis of effluents from the fuel reprocessing plant (FRP) were calculated using the fuel burnup codes LEOPARD, CINDER and ORIGEN. Effluent quantities are estimated for each fuel type. Bedded salt was chosen for the waste repository analysis. The repository site is modeled on the Waste Isolation Pilot Program site in New Mexico. Wastes assumed to be stored in the repository include high-level vitrified waste from the FRP, packaged fuel residue from the FRP, and transuranic (TRU) contaminated wastes from the FFP, PFRFP, and UFRFP. The potential environmental significance was determined by estimating the ground-water concentrations of the various nuclides over a time span of a million years. The MPC for each nuclide was used along with the estimated ground-water concentration to generate a biohazard index for the comparison among fuel compositions

  1. Treatment of wastes from a central spent-fuel rod consolidation facility

    International Nuclear Information System (INIS)

    Ross, W.A.

    1986-01-01

    The consolidation of commercial spent-fuel rods at a central treatment facility (such as the proposed Monitored Retrievable Storage Facility) will generate several types of waste, which may require treatment and disposal. Eight alternatives for the treatment of the wastes have been evaluated as part of DOE's Nuclear Waste Treatment Program at the Pacific Northwest Laboratory. The evaluation considered the system costs, potential waste form requirements, and processing characteristics

  2. SE-VYZ - Decommissioning of Nuclear Installations, Radioactive Waste and Spent Fuel Management

    International Nuclear Information System (INIS)

    Anon

    2004-01-01

    In this presentations processes of radioactive waste treatment in the Bohunice Radioactive Waste Processing Center (SE-VYZ), Jaslovske Bohunice are presented. Decommissioning of the A-1 NPP is also presented. Disposal of conditioned radioactive waste in fibre concrete containers (FCC) are transported to Mochovce from Jaslovske Bohunice by the transport truck where are reposited in the National radioactive waste repository Mochovce. The Interim spent fuel storage facility (ISFSF) is included into this presentation

  3. Prospects of pyrolysis oil from plastic waste as fuel for diesel engines: A review

    Science.gov (United States)

    Mangesh, V. L.; Padmanabhan, S.; Ganesan, S.; PrabhudevRahul, D.; Reddy, T. Dinesh Kumar

    2017-05-01

    The purpose ofthis study is to review the existing literature about chemical recycling of plastic waste and its potential as fuel for diesel engines. This is a review covering on the field of converting waste plastics into liquid hydrocarbon fuels for diesel engines. Disposal and recycling of waste plastics have become an incremental problem and environmental threat with increasing demand for plastics. One of the effective measures is by converting waste plastic into combustible hydrocarbon liquid as an alternative fuel for running diesel engines. Continued research efforts have been taken by researchers to convert waste plastic in to combustible pyrolysis oil as alternate fuel for diesel engines. An existing literature focuses on the study of chemical structure of the waste plastic pyrolysis compared with diesel oil. Converting waste plastics into fuel oil by different catalysts in catalytic pyrolysis process also reviewed in this paper. The methodology with subsequent hydro treating and hydrocracking of waste plastic pyrolysis oil can reduce unsaturated hydrocarbon bonds which would improve the combustion performance in diesel engines as an alternate fuel.

  4. Acceptance of spent nuclear fuel in multiple element sealed canisters by the Federal Waste Management System

    International Nuclear Information System (INIS)

    1990-03-01

    This report is one of a series of eight prepared by E.R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high level waste will be accepted in the following categories: (1) failed fuel; (2) consolidated fuel and associated structural parts; (3) non-fuel-assembly hardware; (4) fuel in metal storage casks; (5) fuel in multi-element sealed canisters; (6) inspection and testing requirements for wastes; (7) canister criteria; (8) spent fuel selection for delivery; and (9) defense and commercial high-level waste packages. 14 refs., 27 figs

  5. Acceptance of non-fuel assembly hardware by the Federal Waste Management System

    International Nuclear Information System (INIS)

    1990-03-01

    This report is one of a series of eight prepared by E. R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high-priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high-level waste will be accepted in the following categories: failed fuel; consolidated fuel and associated structural parts; non-fuel-assembly hardware; fuel in metal storage casks; fuel in multi-element sealed canisters; inspection and testing requirements for wastes; canister criteria; spent fuel selection for delivery; and defense and commercial high-level waste packages. 14 refs., 12 figs., 43 tabs

  6. Galvanic corrosion of lead coupled with titanium for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Mani Mathew, P.; Krueger, P.A.

    1989-01-01

    In the Canadian Nuclear Fuel Waste Management Program, metals and alloys with low melting points are being evaluated for their potential application as cast matrices within used-fuel immobilization containers. This paper describes studies of galvanic corrosion between lead, candidate matrix metal and ASTM Grade-2 titanium, a candidate container-shell material. The studies were conducted under conditions that simulate a breached disposal container surrounded by a bentonite/sand mixture and emplaced in a granitic rock formation at a depth of 500-1000 m. The fractional factorial statistical design of Box Behnken was used in the tests, which covered a wide range of potential conditions that could occur in a nuclear-waste disposal vault. Test temperatures ranged from 293 to 423 K. Ionic strength and oxygen content of the simulated groundwater varied from 0.0015 to 1.37 mol and 0.02 to 8.0 mg/l, respectively. A mathematical expression was derived for the lead corrosion rates as a function of the independent variables: temperature, ionic strength, and oxygen content. This expression was used to calculate the lifetime of the additional barrier that a 25-mm thick lead layer could provide to a titanium container that eventually perforates by erosion. The results show that at least 860 years of additional barrier life could be provided by the lead matrix

  7. Preliminary analysis of the creep behaviour of nuclear fuel-waste container materials

    International Nuclear Information System (INIS)

    Dutton, R.; Leitch, B.W.; Crosthwaite, J.L.; Kasprick, G.R.

    1996-12-01

    In the Canadian Nuclear Fuel Waste Management Program, it is proposed that nuclear fuel waste be placed in a durable container and disposed of in a deep underground vault. Consideration of various disposal-container designs has identified either titanium or copper as the material suitable for constructing the container shell. As part of the R and D program to examine the structural integrity of the container, creep tests are being conducted on commercially pure titanium and oxygen-free copper. This report presents the preliminary data obtained. It also describes the evaluation of various constitutive equations to represent the creep curves, thus providing the basis for extrapolation of the creep behaviour over the design lifetime of the container. In this regard, a specific focus is placed on equations derived from the 0-Projection Concept. Recognizing that the container lifetime will be determined by the onset of tertiary creep leading to creep rupture, we present the results of the metallographic examination of creep damage. This shows that the tertiary stage in titanium is associated with the formation of transgranular cavities within the region of localized necking of the creep specimens. In contrast, creep damage in copper is in the form of intergranular cavities uniformly distributed throughout the gauge length. These results are analyzed within the context of the extant literature, and their implications for future container design are discussed. (author)

  8. Radiolysis effects on fuel corrosion within a failed nuclear waste container

    International Nuclear Information System (INIS)

    Sunder, S.; Shoeshmith, D.W.; Christensen, H.C.

    2003-01-01

    The concept of geological disposal of used nuclear fuel in corrosion resistant containers is being investigated in several countries. In the Canadian Nuclear Fuel Waste Management Program (CNFWMP), it is assumed that the used fuel will be disposed of in copper containers. Since the predicted lifetimes of these containers are very long (>106 years), only those containers emplaced with an undetected defect will fail within the period for which radionuclide release from the fuel must be considered. Early failure could lead to the entry of water into the container and subsequent release of radionuclides. The release rate of radionuclides from the used fuel will depend upon its dissolution rate. The primary mechanism for release will be the corrosion of the fuel driven by radiolytically-produced oxidants. The studies carried out to determine the effects of water radiolysis on fuel corrosion are reviewed, and some of the procedures used to predict corrosion rates of used fuel in failed nuclear waste containers described. (author)

  9. Deriving a Planting Medium from Solid Waste Compost and Construction, Demolition and Excavation Waste

    Science.gov (United States)

    Farajalla, Nadim; Assaf, Eleni; Bashour, Issam; Talhouk, Salma

    2014-05-01

    Lebanon's very high population density has been increasing since the end of the war in the early 1990s reaching 416.36 people per square kilometer. Furthermore, the influx of refugees from conflicts in the region has increased the resident population significantly. All these are exerting pressure on the country's natural resources, pushing the Lebanese to convert more forest and agricultural land into roads, buildings and houses. This has led to a building boom and rapid urbanization which in turn has created a demand for construction material - mainly rock, gravel, sand, etc. nearly all of which were locally acquired through quarrying to the tune of three million cubic meters annually. This boom has been followed by a war with Israel in 2006 which resulted in thousands of tonnes of debris. The increase in population has also led to an increase in solid waste generation with 1.57 million tonnes of solid waste generated in Lebanon per year. The combination of construction, demolition and excavation (CDE) waste along with the increase in solid waste generation has put a major stress on the country and on the management of its solid waste problem. Compounding this problem are the issues of quarries closure and rehabilitation and a decrease in forest and vegetative cover. The on-going research reported in this paper aims to provide an integrated solution to the stated problem by developing a "soil mix" derived from a mélange of the organic matter of the solid waste (compost), the CDE waste, and soil. In this mix, native and indicator plants are planted (in pots) from which the most productive mix will be selected for further testing at field level in later experiments. The plant species used are Matiolla, a native Lebanese plant and Zea mays, which is commonly known used as an indicator plant due to its sensitivity to environmental conditions. To ensure sustainability and environmental friendliness of the mix, its physical and chemical characteristics are monitored

  10. Status of the Integral Fast Reactor fuel cycle demonstration and waste management practices

    International Nuclear Information System (INIS)

    Benedict, R.W.; Goff, K.M.; McFarlane, H.F.

    1994-01-01

    Over the past few years, Argonne National Laboratory has been preparing for the demonstration of the fuel cycle for the Integral Fast Reactor (IFR), an advanced reactor concept that takes advantage of the properties of metallic fuel and liquid metal cooling to offer significant improvements in reactor safety and operations, fuel-cycle economics, environmental protection, and safeguards. The IFR fuel cycle, which will be demonstrated at Argonne-West in Idaho, employs a pyrometallurgical process using molten salts and liquid metals to recover actinides from spent fuel. The required facility modifications and process equipment for the demonstration are nearing completion. Their status and the results from initial fuel fabrication work, including the waste management aspects, are presented. Additionally, estimated compositions of the various process waste streams have been made, and characterization and treatment methods are being developed. The status of advanced waste processing equipment being designed and fabricated is described

  11. Fuel cycle and waste newsletter, Vol. 4, No. 2, September 2008

    International Nuclear Information System (INIS)

    2008-09-01

    The lead article in this issue of the Fuel Cycle and Waste Newsletter deals with the future of uranium resources. Furthermore this issue presents information about the IAEA's new publications series called the Nuclear Energy Series (NES) and discusses coordinated research projects of the Nuclear Fuel Cycle and Materials Section including 'Fuel Performance Modelling under Extended Burn-up (FUMEX)', 'Fuel Structural Materials and Water Chemistry Management in Nuclear Power Plants (FUWACC)', 'Hydrogen and Hydride Degeneration of Mechanical and Physical Properties of Zr-Alloys - Delayed Hydride Cracking (DHC) of Zirconium Alloy Fuel Cladding', 'Accelerator Simulation and Theoretical Modelling of Radiation Effects (SMoRE)', 'Spent Fuel Performance and Research (SPAR)' and 'Process-losses in Separation Processes in Partitioning and Transmutation (P and T) Systems in View of Minimizing Long-term Environmental Impacts'. This issue also covers information about the estimation of plutonium and minor actinides using NFCSS (Nuclear Fuel Cycle Simulation System), fabrication, properties and irradiation behaviour of stainless steel cladding and fuel assembly materials for liquid metal-cooled fast reactors, fabrication, processing, properties and the creation of a bibliographic database related to minor actinide fuel target, status and development of the IAEA PIE database, the international low level waste disposal network (DISPONET), retrievability in geological disposal and the review of Slovenian national repository for low- and intermediate level radioactive waste programme. A new tool for the reporting of national radioactive waste and spent fuel inventories is presented as well as the Eurobarometer survey on radioactive waste 2008, the radioactive waste assesment methodology and economics of radioactive waste management, recent activities of the International Decommissioning Network (IDN), and D and D Fuel Pools: a huge legacy worldwide. The issue closes with a list of

  12. The present state and future prospects of the radioactive waste and spent fuel management in Lithuania

    International Nuclear Information System (INIS)

    Gylys, J.

    2001-01-01

    The Ignalina nuclear power plant (NPP) is the main source of the spent fuel and the radioactive waste (RW) in Lithuania. Now Lithuania is fully responsible for the management and disposal of its RW and spent fuel. The present scheme of spent fuel, solid, and liquid waste treatment is incomplete. The Department of Thermal and Nuclear Energy at Kaunas University of Technology proposed the new idea - cellular foam apparatus for the concentration of the liquid waste at Ignalina NPP. Some data and main results of the investigation of such apparatus are presented here. (author)

  13. New developments in tire-derived fuels (TDF)

    Energy Technology Data Exchange (ETDEWEB)

    Gilbert, G. [Kentucky Dept. for Environmental Protection, KY (United States)

    2006-07-01

    Public opinion on the use of tire derived fuels (TDF) has been influenced by images of the large, uncontrolled tire fires at landfills that fill the atmosphere with heavy black smoke. This presentation discussed some of the issues and challenges related to the introduction of TDF in communities. The United States Environmental Protection Agency currently supports the responsible use of tires in Portland cement kilns and other industrial facilities if they have a storage and handling plan and have secured a permit for all applicable state and federal environmental programs. The use of TDF falls within the EPA resource conservation challenge (RCC) which has initiated a scrap tire workgroup and a TDF committee. The RCC has asked industry using TDF to assemble and share air, water, and product data to assist new TDF users and permitting agencies. TDF is currently used in cement production, by utility boilers, and pulp and paper manufacturers. A recent comparison of TDF and coal characteristics has shown that TDF releases fewer sulphur emissions than coal and produces more energy. While hydrogen emissions are typically higher, nitrogen emissions are lower. An elemental ash analysis has shown that wire-free TDF contains less aluminum than bitumens, as well as less iron. Particulate matter (PM) emissions and volatile organic carbon (VOC) emissions from various plants using TDF are often lower than, or the same as, coal. It was concluded that in order to challenge preconceived notions about TDF, baseline compliance tests should be conducted before presenting data for a permit. Baseline tests should also be conducted with other fuels such as coal within the same timeframe. refs., tabs., figs.

  14. Fuel cycle and waste newsletter. Vol. 3, No. 2, July 2007

    International Nuclear Information System (INIS)

    2007-07-01

    The top stories in this issue of the Fuel Cycle and Waste Newsletter highlight some important activities of the Division to reduce the nuclear threats worldwide. It involves conditioning and possible repatriation spent sealed radioactive sources, conversion of research reactors from high enriched uranium fuel to low enriched uranium and return of the fuel to the USA and to the Russian Federation. These activities have great technical challenges and are connected with important legal and administrative work. Topics covered are mobile hot cell (SHARS) for conditioning of spent high-activity sealed radioactive sources and support of global efforts to remove highly enriched uranium from international commerce. The activities of the waste technology section (WTS), and of the nuclear fuel cycle and materials section (NFC and MS) are presented as well as the launch of the IAEA's international decommissioning network. Further discussions include the development and implementation of radioactive waste management policies and strategies, the national reporting tool upgrade of the Net -Enabled Waste Management Data Base (NEWMBD), spent fuel assessment and research, spent fuel treatment options, FUMEX (FUel Modelling at EXtende Burnup), FUWAC (Fuel and Water Chemistry), the International Nuclear Fuel Cycle Information System (INFCIS), research reactor availability and reliability, research reactor coalitions and upcoming training course on research reactor water quality management as well as ongoing activities related to Advanced Fuel Cycles (AFC). Recent publications and meetings in 2007 are listed

  15. Structure–mechanics property relationship of waste derived biochars

    Energy Technology Data Exchange (ETDEWEB)

    Das, Oisik, E-mail: odas566@aucklanduni.ac.nz [Department of Civil and Environmental Engineering, University of Auckland, Auckland 1142 (New Zealand); Sarmah, Ajit K., E-mail: a.sarmah@auckland.ac.nz [Department of Civil and Environmental Engineering, University of Auckland, Auckland 1142 (New Zealand); Bhattacharyya, Debes, E-mail: d.bhattacharyya@auckland.ac.nz [Department of Mechanical Engineering, Center for Advanced Composite Materials, University of Auckland, Auckland 1142 (New Zealand)

    2015-12-15

    The widespread applications of biochar in agriculture and environmental remediation made the scientific community ignore its mechanical properties. Hence, to examine the scope of biochar's structural applications, its mechanical properties have been investigated in this paper through nanoindentation technique. Seven waste derived biochars, made under different pyrolysis conditions and from diverse feedstocks, were studied via nanoindentation, infrared spectroscopy, X–ray crystallography, thermogravimetry, and electron microscopy. Following this, an attempt was made to correlate the biochars' hardness/modulus with reaction conditions and their chemical properties. The pine wood biochar made at 900 °C and 60 min residence time was found to have the highest hardness and elastic modulus of 4.29 and 25.01 GPa, respectively. It was shown that a combination of higher heat treatment (≥ 500 °C) temperature and longer residence time (~ 60 min) increases the values of hardness and modulus. It was further realized that pyrolysis temperature was a more dominant factor than residence time in determining the final mechanical properties of biochar particles. The degree of aromaticity and crystallinity of the biochar were also correlated with higher values of hardness and modulus. - Highlights: • Characterization was done on waste based biochars which included nanoindentation. • Pine saw dust biochar made at 900 °C for 60 min had highest hardness/modulus. • Combination of temperature/residence time affect biochar's mechanical propertie.s • Aromaticity and crystallinity positively affected biochar's mechanical properties.

  16. Physical and chemical characterization of waste wood derived biochars.

    Science.gov (United States)

    Yargicoglu, Erin N; Sadasivam, Bala Yamini; Reddy, Krishna R; Spokas, Kurt

    2015-02-01

    Biochar, a solid byproduct generated during waste biomass pyrolysis or gasification in the absence (or near-absence) of oxygen, has recently garnered interest for both agricultural and environmental management purposes owing to its unique physicochemical properties. Favorable properties of biochar include its high surface area and porosity, and ability to adsorb a variety of compounds, including nutrients, organic contaminants, and some gases. Physical and chemical properties of biochars are dictated by the feedstock and production processes (pyrolysis or gasification temperature, conversion technology and pre- and post-treatment processes, if any), which vary widely across commercially produced biochars. In this study, several commercially available biochars derived from waste wood are characterized for physical and chemical properties that can signify their relevant environmental applications. Parameters characterized include: physical properties (particle size distribution, specific gravity, density, porosity, surface area), hydraulic properties (hydraulic conductivity and water holding capacity), and chemical and electrochemical properties (organic matter and organic carbon contents, pH, oxidation-reduction potential and electrical conductivity, zeta potential, carbon, nitrogen and hydrogen (CHN) elemental composition, polycyclic aromatic hydrocarbons (PAHs), heavy metals, and leachable PAHs and heavy metals). A wide range of fixed carbon (0-47.8%), volatile matter (28-74.1%), and ash contents (1.5-65.7%) were observed among tested biochars. A high variability in surface area (0.1-155.1g/m(2)) and PAH and heavy metal contents of the solid phase among commercially available biochars was also observed (0.7-83 mg kg(-1)), underscoring the importance of pre-screening biochars prior to application. Production conditions appear to dictate PAH content--with the highest PAHs observed in biochar produced via fast pyrolysis and lowest among the gasification

  17. First annual report of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Boulton, J.; Gibson, A.R.

    1979-12-01

    The research and development program for the safe, permanent disposal of Canada's nuclear fuel wastes has been established. This report, the first of a series of annual reports, reviews in general terms the progress which has been achieved. After briefly reviewing the rationale and organization of the program, the report summarizes activities in the area of public information, used fuel storage and transportation, immobilization of used fuel and fuel reprocessing wastes, research and development associated with deep underground disposal, and environmental and safety assessment. (auth) [fr

  18. Abundance of 14C in biomass fractions of wastes and solid recovered fuels

    International Nuclear Information System (INIS)

    Fellner, Johann; Rechberger, Helmut

    2009-01-01

    In recent years thermal utilization of mixed wastes and solid recovered fuels has become of increasing importance in European waste management. Since wastes or solid recovered fuels are generally composed of fossil and biogenic materials, only part of the CO 2 emissions is accounted for in greenhouse gas inventories or emission trading schemes. A promising approach for determining this fraction is the so-called radiocarbon method. It is based on different ratios of the carbon isotopes 14 C and 12 C in fossil and biogenic fuels. Fossil fuels have zero radiocarbon, whereas biogenic materials are enriched in 14 C and reflect the 14 CO 2 abundance of the ambient atmosphere. Due to nuclear weapons tests in the past century, the radiocarbon content in the atmosphere has not been constant, which has resulted in a varying 14 C content of biogenic matter, depending on the period of growth. In the present paper 14 C contents of different biogenic waste fractions (e.g., kitchen waste, paper, wood), as well as mixtures of different wastes (household, bulky waste, and commercial waste), and solid recovered fuels are determined. The calculated 14 C content of the materials investigated ranges between 98 and 135 pMC

  19. Physicochemical determinations of petroleum, heavy fuel derivative and combustion nanoparticles

    International Nuclear Information System (INIS)

    Frias Bullain, Jorge; Padron Rodriguez, M.; Perez Barcala, B.; Lopez Guerra, S.

    2016-01-01

    In the investigation, a crude from Cuban Northern Heavy Oil Belt and its fuel oil fraction was characterized by chemical and physical techniques. Subsequent to the characterization of the derivative, MSI gas analyzer was performed, to identify and quantify concentrations of chemical species, in correspondence with EPA (2007) for external sources. Total suspended particles collected in filter holder were identified using the gravimetric method (ISO 9096). With the intention of knowing the magnitude of polycyclic aromatic hydrocarbons reported in literature were chosen the higher and lower molecular mass and measured on the basis of its polar covalent radii. Total aromatic hydrocarbons were identified using activated charcoal with subsequent elution with nhexane for analysis by ultraviolet spectroscopy in a Genesys 10 UV spectrophotometer. Environmental pollution control in the oil sector, is evaluated in three states. The particles in the states mentioned above, whose dimensions are between (1-100) x10-9 meters are called nanoparticles. Nanotechnology currently offers firm steps in the development of different nanoparticles, which are applied directly to the mineralogical industry. Contributions stand out sharply operations: exploration, drilling and refining oil. (Author)

  20. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions

  1. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  2. Co-firing a pressurized fluidized-bed combustion system with coal and refuse derived fuels and/or sludges. Task 16

    Energy Technology Data Exchange (ETDEWEB)

    DeLallo, M.; Zaharchuk, R.

    1994-01-01

    The co-firing of waste materials with coal in utility scale power plants has emerged as an effective approach to produce energy and manage municipal waste. Leading this approach, the atmospheric fluidized-bed combustor (AFBC) has demonstrated its commercial acceptance in the utility market as a reliable source of power burning a variety of waste and alternative fuels. The fluidized bed, with its stability of combustion, reduces the amount of thermochemical transients and provides for easier process control. The application of pressurized fluidized-bed combustor (PFBC) technology, although relatively new, can provide significant enhancements to the efficient production of electricity while maintaining the waste management benefits of AFBC. A study was undertaken to investigate the technical and economic feasibility of co-firing a PFBC with coal and municipal and industrial wastes. Focus was placed on the production of electricity and the efficient disposal of wastes for application in central power station and distributed locations. Wastes considered for co-firing include municipal solid waste (MSW), tire-derived fuel (TDF), sewage sludge, and industrial de-inking sludge. Issues concerning waste material preparation and feed, PFBC operation, plant emissions, and regulations are addressed. This paper describes the results of this investigation, presents conclusions on the key issues, and provides recommendations for further evaluation.

  3. Transporting spent fuel and reactor waste in Sweden experience from 5 years of operation

    International Nuclear Information System (INIS)

    Dybeck, P.; Gustafsson, B.

    1990-01-01

    This paper reports that since the Final Repository for Reactor Waste, SFR, was taken into operation in 1988, the SKB sea transportation system is operating at full capacity by transporting spent fuel and now also reactor waste from the 12 Swedish reactors to CLAB and SFR. Transports from the National Research Center, Studsvik to the repository has recently also been integrated in the system. CLAB, the central intermediate storage for spent fuel, has been in operation since 1985. The SKB Sea Transportation System consists today of the purpose built ship M/s Sigyn, 10 transport casks for spent fuel, 2 casks for spent core components, 27 IP-2 shielded steel containers for reactor waste and 5 terminal vehicles. During an average year about 250 tonnes of spent fuel and 3 -- 4000 m 3 of reactor waste are transported to CLAB and SFR respectively, corresponding to around 30 sea voyages

  4. The disposal of Canada's nuclear fuel waste: public involvement and social aspects

    International Nuclear Information System (INIS)

    Greber, M.A.; Frech, E.R.; Hillier, J.A.R.

    1994-01-01

    This report describes the activities undertaken to provide information to the public about the Canadian Nuclear Fuel Waste Management Program as well as the opportunities for public involvement in the direction and development of the disposal concept through government inquiries and commissions and specific initiatives undertaken by AECL. Public viewpoints and the major issues identified by the public to be of particular concern and importance in evaluating the acceptability of the concept are described. In addition, how the issues have been addressed during the development of the disposal concept or how they could be addressed during implementation of the disposal concept are presented. There is also discussion of public perspectives of risk, the ethical aspects of nuclear fuel waste disposal, and public involvement in siting a nuclear fuel waste disposal facility. The Canadian Nuclear Fuel Waste Management Program is funded jointly by AECL and Ontario Hydro under the auspices of the CANDU Owners Group. (author)

  5. Life cycle assessment of camelina oil derived biodiesel and jet fuel in the Canadian Prairies

    International Nuclear Information System (INIS)

    Li, Xue; Mupondwa, Edmund

    2014-01-01

    This study evaluated the environmental impact of biodiesel and hydroprocessed renewable jet fuel derived from camelina oil in terms of global warming potential, human health, ecosystem quality, and energy resource consumption. The life cycle inventory is based on production activities in the Canadian Prairies and encompasses activities ranging from agricultural production to oil extraction and fuel conversion. The system expansion method is used in this study to avoid allocation and to credit input energy to co-products associated with the products displaced in the market during camelina oil extraction and fuel processing. This is the preferred allocation method for LCA analysis in the context of most renewable and sustainable energy programs. The results show that greenhouse gas (GHG) emissions from 1 MJ of camelina derived biodiesel ranged from 7.61 to 24.72 g CO 2 equivalent and 3.06 to 31.01 kg CO 2 /MJ equivalent for camelina HRJ fuel. Non-renewable energy consumption for camelina biodiesel ranged from 0.40 to 0.67 MJ/MJ; HRJ fuel ranged from − 0.13 to 0.52 MJ/MJ. Camelina oil as a feedstock for fuel production accounted for the highest contribution to overall environmental performance, demonstrating the importance of reducing environmental burdens during the agricultural production process. Attaining higher seed yield would dramatically lower environmental impacts associated with camelina seed, oil, and fuel production. The lower GHG emissions and energy consumption associated with camelina in comparison with other oilseed derived fuel and petroleum fuel make camelina derived fuel from Canadian Prairies environmentally attractive. - Highlights: • LCA of camelina-derived biodiesel and jet fuel was based on the Canadian Prairies. • Overall, camelina-derived biodiesel had lower GHG emissions than is biojet fuel. • Camelina jet fuel had lower non-renewable energy (NRE) use than its biodiesel. • Camelina biofuels reduced GHG emissions and NRE use

  6. Life cycle assessment of camelina oil derived biodiesel and jet fuel in the Canadian Prairies

    Energy Technology Data Exchange (ETDEWEB)

    Li, Xue; Mupondwa, Edmund, E-mail: Edmund.Mupondwa@agr.gc.ca

    2014-05-01

    This study evaluated the environmental impact of biodiesel and hydroprocessed renewable jet fuel derived from camelina oil in terms of global warming potential, human health, ecosystem quality, and energy resource consumption. The life cycle inventory is based on production activities in the Canadian Prairies and encompasses activities ranging from agricultural production to oil extraction and fuel conversion. The system expansion method is used in this study to avoid allocation and to credit input energy to co-products associated with the products displaced in the market during camelina oil extraction and fuel processing. This is the preferred allocation method for LCA analysis in the context of most renewable and sustainable energy programs. The results show that greenhouse gas (GHG) emissions from 1 MJ of camelina derived biodiesel ranged from 7.61 to 24.72 g CO{sub 2} equivalent and 3.06 to 31.01 kg CO{sub 2}/MJ equivalent for camelina HRJ fuel. Non-renewable energy consumption for camelina biodiesel ranged from 0.40 to 0.67 MJ/MJ; HRJ fuel ranged from − 0.13 to 0.52 MJ/MJ. Camelina oil as a feedstock for fuel production accounted for the highest contribution to overall environmental performance, demonstrating the importance of reducing environmental burdens during the agricultural production process. Attaining higher seed yield would dramatically lower environmental impacts associated with camelina seed, oil, and fuel production. The lower GHG emissions and energy consumption associated with camelina in comparison with other oilseed derived fuel and petroleum fuel make camelina derived fuel from Canadian Prairies environmentally attractive. - Highlights: • LCA of camelina-derived biodiesel and jet fuel was based on the Canadian Prairies. • Overall, camelina-derived biodiesel had lower GHG emissions than is biojet fuel. • Camelina jet fuel had lower non-renewable energy (NRE) use than its biodiesel. • Camelina biofuels reduced GHG emissions and NRE

  7. Technologies for the management of radioactive waste from nuclear power plants and back end nuclear fuel cycle activities. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-02-01

    This document includes 79 presentations delivered at the symposium. The topics discussed include: requirements, options and strategies for waste management; supporting infrastructural needs; waste arising and waste minimization at sources; treatment, conditioning and interim storage of low and intermediate level waste from operation of facilities; treatment, conditioning and interim storage of spent fuel and high level waste; disposal of radioactive waste; decommissioning waste management. Each paper has been indexed separately.

  8. Technologies for the management of radioactive waste from nuclear power plants and back end nuclear fuel cycle activities. Proceedings

    International Nuclear Information System (INIS)

    2001-01-01

    This document includes 79 presentations delivered at the symposium. The topics discussed include: requirements, options and strategies for waste management; supporting infrastructural needs; waste arising and waste minimization at sources; treatment, conditioning and interim storage of low and intermediate level waste from operation of facilities; treatment, conditioning and interim storage of spent fuel and high level waste; disposal of radioactive waste; decommissioning waste management. Each paper has been indexed separately

  9. Removal of actinides from high-level wastes generated in the reprocessing of commercial fuels

    International Nuclear Information System (INIS)

    Bond, W.D.; Leuze, R.E.

    1975-09-01

    Progress is reported on a technical feasibility study of removing the very long-lived actinides (uranium, neptunium, plutonium, americium, and curium) from high-level wastes generated in the commercial reprocessing of spent nuclear fuels. The study was directed primarily at wastes from the reprocessing of light water reactor (LWR) fuels and specifically to developing satisfactory methods for reducing the actinide content of these wastes to values that would make 1000-year-decayed waste comparable in radiological toxicity to natural uranium ore deposits. Although studies are not complete, results thus far indicate the most promising concept for actinide removal includes both improved recovery of actinides in conventional fuel reprocessing and secondary processing of the high-level wastes. Secondary processing will be necessary for the removal of americium and curium and perhaps some residual plutonium. Laboratory-scale studies of separations methods that appear most promising are reported and conceptual flowsheets are discussed. (U.S.)

  10. The disposal of Canada's nuclear fuel waste: the biosphere model, BIOTRAC, for postclosure assessment

    International Nuclear Information System (INIS)

    Davis, P.A.; Zach, R.; Stephens, M.E.; Amiro, B.D.; Bird, G.A.; Reid, J.A.K.; Sheppard, M.I.; Sheppard, S.C.; Stephenson, M.

    1993-01-01

    The nuclear fuel waste management concept of Canada calls for disposal of the waste in a vault mined deep in plutonic rock of the Canadian Shield. The technical feasibility of this concept, and its impact on the environment and human health, will be documented in an Environmental Impact statement (EIS) by AECL. The present report is one of nine EIS primary references. The report describes the BIOTRAC model, which is used to trace nuclide movement from the geosphere through the biosphere and to calculate time-dependent environmental concentrations and radiological doses to humans and other biota for the postclosure phase. These concentrations and doses are crucial for evaluating the safety and environmental acceptability of the concept in terms of chemical and radiological toxicity. BIOTRAC was developed specifically to assess the impacts of a used-fuel disposal vault. It is a comprehensive, generic model with distributed or probabilistic parameter values to account for spatial and temporal variability and uncertainty. It is composed of four separate but closely linked submodels representing surface waters, soils, the atmosphere and the food chain. It also includes a unique model for predicting radiological doses to non-human biota, represented by generic target organisms. The mathematical formulation of each submodel is derived in detail and interpreted physically, and all the assumptions are fully evaluated and discussed. It is shown how the parameter values and distributions adopted for each submodel are derived from the available data. The interfaces between the submodels, and between BIOTRAC and the geosphere model, are presented in detail. Fluctuations in the physical state of the biosphere are accounted for through the parameter distributions. Major environmental changes, such as those caused by continental glaciation, are addressed quantitatively and through reasoned arguments, which indicate that radiological doses to humans will not increase suddenly or

  11. Estimating the cost of disposal for Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    Ates, Y.

    1996-07-01

    Atomic Energy of Canada Ltd (AECL) prepared an Environmental Impact Statement and nine supporting Primary Reference Documents on the concept for disposal of Canada's nuclear fuel waste. This report summarizes the basis of the cost estimate which is provided in the primary reference document on engineering for a disposal facility. The scope of the cost estimate is explained by describing the key features of the disposal facility design, by noting the major assumptions made in preparing the estimates, and by listing the included and excluded cost components. An activity-based project planning and control method is explained whereby the project schedule, costs, and personnel requirements are interlinked; forming an integrated perspective on the total project life cycle. The summary and distribution of costs in each project stage by major facility or activity are presented. The results of studies which reviewed the overall cost estimate are also described. These studies indicate that, within the scope, the estimate is reasonable and compares well with similar international studies. (author)

  12. Nuclear fuel waste management - biosphere program highlights - 1978 to 1996

    Energy Technology Data Exchange (ETDEWEB)

    Zach, R

    1997-07-01

    The biosphere program in support of the development of the disposal concept for Canadian nuclear fuel waste since 1978 is scheduled for close-out. AECL`s Environmental Science Branch (ESB) was mainly responsible for work in this program. In order to preserve as much information as possible, this report highlights many of the key achievements of the program, particularly those related to the development of the BIOTRAC biosphere model and its supporting research. This model was used for the assessment and review of the disposal concept in an environmental impact statement (EIS). The report also treats highlights related to alternative models, external scientific/technical reviews, EIS feedback, and the international BIOMOVS model validation program. Furthermore, it highlights basic aspects of future modelling and research needs in relation to siting a disposal facility. In this, feedback from the various reviews and the EIS is taken into account. Appendices of the report include listings of key ESB staff involved in the program, all the scientific/technical reports and papers produced under the program, contracts let to outside agencies, and issues raised by various participants or intervenors during the EIS review. Although the report is concerned with close-out of the biosphere program, it also provides valuable information for a continuing program concerned with siting a disposal facility. One of the conclusions of the report is that such a program is essential for successfully siting such a facility. (author) Refs.

  13. Nuclear fuel waste management - biosphere program highlights - 1978 to 1996

    International Nuclear Information System (INIS)

    Zach, R.

    1997-07-01

    The biosphere program in support of the development of the disposal concept for Canadian nuclear fuel waste since 1978 is scheduled for close-out. AECL's Environmental Science Branch (ESB) was mainly responsible for work in this program. In order to preserve as much information as possible, this report highlights many of the key achievements of the program, particularly those related to the development of the BIOTRAC biosphere model and its supporting research. This model was used for the assessment and review of the disposal concept in an environmental impact statement (EIS). The report also treats highlights related to alternative models, external scientific/technical reviews, EIS feedback, and the international BIOMOVS model validation program. Furthermore, it highlights basic aspects of future modelling and research needs in relation to siting a disposal facility. In this, feedback from the various reviews and the EIS is taken into account. Appendices of the report include listings of key ESB staff involved in the program, all the scientific/technical reports and papers produced under the program, contracts let to outside agencies, and issues raised by various participants or intervenors during the EIS review. Although the report is concerned with close-out of the biosphere program, it also provides valuable information for a continuing program concerned with siting a disposal facility. One of the conclusions of the report is that such a program is essential for successfully siting such a facility. (author)

  14. Radioactive waste management plan for the PBMR (Pty) Ltd fuel plant

    International Nuclear Information System (INIS)

    Makgae, Mosidi E.

    2009-01-01

    The Pebble Bed Modular Reactor (Pty) Ltd Fuel Plant (PFP) radioactive waste management plan caters for waste from generation, processing through storage and possible disposal. Generally, the amount of waste that will be generated from the PFP is Low and Intermediate Level Waste. The waste management plan outlines all waste streams and the management options for each stream. It also discusses how the Plant has been designed to ensure radioactive waste minimisation through recycling, recovery, reuse, treatment before considering disposal. Compliance to the proposed plan will ensure compliance with national legislative requirements and international good practice. The national and the overall waste management objective is to ensure that all PFP wastes are managed appropriately by utilising processes that minimize, reduce, recover and recycle without exposing employees, the public and the environment to unacceptable impacts. Both International Atomic Energy Agency (IAEA) and Department of Minerals and Energy (DME) principles act as a guide in the development of the strategy in order to ensure international best practice, legal compliance and ensuring that the impact of waste on employees, environment and the public is as low as reasonably achievable. The radioactive waste classification system stipulated in the Radioactive Waste Management Policy and Strategy 2005 will play an important role in classifying radioactive waste and ensuring that effective management is implemented for all waste streams, for example gaseous, liquid or solid wastes.

  15. World Nuclear Association position statement: Safe management of nuclear waste and used nuclear fuel

    International Nuclear Information System (INIS)

    Saint-Pierre, Sylvain

    2006-01-01

    This WNA Position Statement summarises the worldwide nuclear industry's record, progress and plans in safely managing nuclear waste and used nuclear fuel. The global industry's safe waste management practices cover the entire nuclear fuel-cycle, from the mining of uranium to the long-term disposal of end products from nuclear power reactors. The Statement's aim is to provide, in clear and accurate terms, the nuclear industry's 'story' on a crucially important subject often clouded by misinformation. Inevitably, each country and each company employs a management strategy appropriate to a specific national and technical context. This Position Statement reflects a confident industry consensus that a common dedication to sound practices throughout the nuclear industry worldwide is continuing to enhance an already robust global record of safe management of nuclear waste and used nuclear fuel. This text focuses solely on modern civil programmes of nuclear-electricity generation. It does not deal with the substantial quantities of waste from military or early civil nuclear programmes. These wastes fall into the category of 'legacy activities' and are generally accepted as a responsibility of national governments. The clean-up of wastes resulting from 'legacy activities' should not be confused with the limited volume of end products that are routinely produced and safely managed by today's nuclear energy industry. On the significant subject of 'Decommissioning of Nuclear Facilities', which is integral to modern civil nuclear power programmes, the WNA will offer a separate Position Statement covering the industry's safe management of nuclear waste in this context. The paper's conclusion is that the safe management of nuclear waste and used nuclear fuel is a widespread, well-demonstrated reality. This strong safety record reflects a high degree of nuclear industry expertise and of industry responsibility toward the well-being of current and future generations. Accumulating

  16. Emerging Trends in the Nuclear Fuel Cycle: Implications for Waste Management

    International Nuclear Information System (INIS)

    Spradley, L.; Camper, L.; Rehmann, M.

    2009-01-01

    There are emerging trends in the nuclear fuel cycle that have implications for waste management. This paper will discuss activities in both the front-end and back-end of the nuclear fuel cycle for the U.S. Nuclear Regulatory Commission (NRC)-regulated entities. Particular focus will be given to the front-end which includes uranium recovery facilities, conversion facilities, and enrichment facilities. The back-end activities include progress on the proposed high-level waste geologic repository at Yucca Mountain, NV and efforts to reprocess spent nuclear fuel or down-blend HEU. While there are potential environmental impacts due to construction and dismantling of fuel cycle facilities, this paper focuses on the operational waste stream that will need to be managed as a result of fuel-cycle facilities. (authors)

  17. Conversion of Mixed Plastic Wastes (High Density Polyethylene and Polypropylene) into Liquid Fuel

    International Nuclear Information System (INIS)

    Chaw Su Su Hmwe; Tint Tint Kywe; Moe Moe Kyaw

    2010-12-01

    In this study, mixed plastic wastes were converted into liquid fuels. Mixed plastic wastes used were high density polyethylene (HDPE) and polypropylene (PP). The pyrolysis of mixed plastic waste to liquid fuel was carried out with and without prepared zeolite catalyst.The catalyst was characterized by X-ray Diffraction (XRD). This catalyst was pre-treated for activation. The experiments were carried out at temperature range of 350-410C.Physical properties (density, kinematic, viscosity,refractive index)of prepared liquid fuel samples were measured. From this study, yields of liquid fuel and gas fuel were found to be 41-64% and 15-35% respectively. As for by products, char was obtained as the yield percentages from 9 to 14% and wax (yield% - 1 to 14) was formed during pyrolysis.

  18. Waste management state-of-the-art review for mixed-oxide fuel fabrication facilities

    International Nuclear Information System (INIS)

    Woodsum, H.C.; Goodman, J.

    1977-11-01

    This report provides a state-of-the-art review of the waste management for mixed-oxide (MOX) fuel fabrication facilities. The intent of this report is to focus on those processes and regulatory issues which have a direct bearing on existing and anticipated future management of transuranic (TRU) wastes from a commercial MOX fuel fabrication faciity. Recent government agency actions are reviewed with regard to their impact on existing and projected waste management regulations; and it is concluded that acceleration in the development of regulations, standards, and criteria is one of the most important factors in the implementation of improved MOX plant waste management techniques. ERDA development programs pertaining to the management of TRU wastes have been reviewed and many promising methods for volume reduction of both solid and liquid wastes are discussed. For solid wastes, these methods include compaction, shredding and baling, combustion, acid digestion, and decontamination by electropolishing or by electrolytic treatment. For liquid wastes, treatment options include evaporation, drying, calcination, flocculation, ion exchange, filtration, reverse osmosis, combustion (of combustible organics), and bioprocessing. Based on this review, it is recommended that ERDA continue with its combustible solid waste volume reduction program and complete these development activities by 1979. Following this, a critical evaluation of solid waste volume reduction techniques should be made to select the most promising systems for a commercial MOX fuel facility

  19. Studies of the combustion of coal/refuse derived fuels using thermogravimetric-Fourier transform infrared-mass spectrometry

    International Nuclear Information System (INIS)

    Lu, Huagang; Li, Jigui; Lloyd, W.G.

    1995-01-01

    According to a report of the Environmental Protection Agency (EPA), 'Characterization of Municipal Solid Waste (MSW) in the United States', the total MSW produced in the U.S. increased from 179 million tons in 1988 to 195 million tons in 1990. The EPA predicted that the country would produce about 216 million tons of garbage in the year 2000. The amount of waste generated and the rapidly declining availability of sanitary landfills has forced most municipalities to evaluate alternative waste management technologies for reducing the volume of waste sent to landfills. The fraction of MSW that is processed by such technologies as separation and recycling, composting, and waste-to-energy was forecast to increase from a few percent today to 30-40% by the year 2000. Waste-to-energy conversion of MSW can appear to be attractive because of the energy recovered, the economic value of recycled materials, and the cost savings derived from reduced landfill usage. However, extra care needs to be taken in burning MSW or refuse-derived fuel (RDF) to optimize the operating conditions of a combustor so that the combustion takes place in an environmentally acceptable manner. For instance, polychlorinated dibenzodioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs) have been found in the precipitator fly ash and flue gas of some incinerator facilities in the United States and Europe. The amount of PCDDs and PCDFs occurs only in the parts-per-billion to parts-per-trillion range, but these chlorinated organics exhibit very high toxicity (LD 50 < 10 μg/Kg). The compound 2,3,7,8-tetrachlorodibenzodioxin has been found to be acnegenic, carcinogenic, and teratogenic. This has slowed or even stopped the construction and operation of waste-to-energy plants

  20. Studies of the combustion of coal/refuse derived fuels using thermogravimetric-Fourier transform infrared-mass spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Lu, Huagang; Li, Jigui; Lloyd, W.G.

    1995-11-01

    According to a report of the Environmental Protection Agency (EPA), `Characterization of Municipal Solid Waste (MSW) in the United States`, the total MSW produced in the U.S. increased from 179 million tons in 1988 to 195 million tons in 1990. The EPA predicted that the country would produce about 216 million tons of garbage in the year 2000. The amount of waste generated and the rapidly declining availability of sanitary landfills has forced most municipalities to evaluate alternative waste management technologies for reducing the volume of waste sent to landfills. The fraction of MSW that is processed by such technologies as separation and recycling, composting, and waste-to-energy was forecast to increase from a few percent today to 30-40% by the year 2000. Waste-to-energy conversion of MSW can appear to be attractive because of the energy recovered, the economic value of recycled materials, and the cost savings derived from reduced landfill usage. However, extra care needs to be taken in burning MSW or refuse-derived fuel (RDF) to optimize the operating conditions of a combustor so that the combustion takes place in an environmentally acceptable manner. For instance, polychlorinated dibenzodioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs) have been found in the precipitator fly ash and flue gas of some incinerator facilities in the United States and Europe. The amount of PCDDs and PCDFs occurs only in the parts-per-billion to parts-per-trillion range, but these chlorinated organics exhibit very high toxicity (LD{sub 50} < 10 {mu}g/Kg). The compound 2,3,7,8-tetrachlorodibenzodioxin has been found to be acnegenic, carcinogenic, and teratogenic. This has slowed or even stopped the construction and operation of waste-to-energy plants.

  1. Radiation effects in glass and glass-ceramic waste forms for the immobilization of CANDU UO2 fuel reprocessing waste

    International Nuclear Information System (INIS)

    Tait, J.C.

    1993-05-01

    AECL has investigated three waste forms for the immobilization of high-level liquid wastes that would arise if used CANDU fuels were reprocessed at some time in the future to remove fissile materials for the fabrication of new power reactor fuel. These waste forms are borosilicate glasses, aluminosilicate glasses and titanosilicate glass-ceramics. This report discusses the potential effects of alpha, beta and gamma radiation on the releases of radionuclides from these waste forms as a result of aqueous corrosion by groundwaters that would be present in an underground waste disposal vault. The report discusses solid-state damage caused by radiation-induced atomic displacements in the waste forms as well as irradiation of groundwater solutions (radiolysis), and their potential effects on waste-form corrosion and radionuclide release. The current literature on radiation effects on borosilicate glasses and in ceramics is briefly reviewed, as are potential radiation effects on specialized waste forms for the immobilization of 129 I, 85 Kr and 14 C. (author). 104 refs., 9 tabs., 5 figs

  2. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement. Volume 1, Appendix B: Idaho National Engineering Laboratory Spent Nuclear Fuel Management Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel.

  3. Combustion and emission characteristics of diesel engine fueled with diesel-like fuel from waste lubrication oil

    International Nuclear Information System (INIS)

    Wang, Xiangli; Ni, Peiyong

    2017-01-01

    Highlights: • 100% diesel-like fuel from waste lubricating oil was conducted in a diesel engine. • Good combustion and fuel economy are achieved without engine modifications. • Combustion duration of DLF is shorter than diesel. • NOx and smoke emissions with the DLF are slightly higher than pure diesel. - Abstract: Waste lubricant oil (WLO) is one of the most important types of the energy sources. WLO cannot be burned directly in diesel engines, but can be processed to be used as diesel-like fuel (DLF) to minimize its harmful effect and maximize its useful values. Moreover, there are some differences in physicochemical properties between WLO and diesel fuel. In order to identify the differences in combustion and emission performance of diesel engine fueled with the two fuels, a bench test of a single-cylinder direct injection diesel engine without any engine modification was investigated at four engine speeds and five engine loads. The effects of the fuels on fuel economic performance, combustion characteristics, and emissions of hydrocarbons (HC), carbon monoxide (CO), nitrogen oxides (NOx) and smoke were discussed. The DLF exhibits longer ignition delay period and shorter combustion duration than diesel fuel. The test results indicate that the higher distillation temperatures of the DLF attribute to the increase of combustion pressure, temperature and heat release rate. The brake specific fuel consumption (BSFC) of the DLF compared to diesel is reduced by about 3% at 3000 rpm under light and medium loads. The DLF produces slightly higher NOx emissions at middle and heavy loads, somewhat more smoke emissions at middle loads, and notably higher HC and CO emissions at most measured points than diesel fuel. It is concluded that the DLF can be used as potential available fuel in high-speed diesel engines without any problems.

  4. Liquid fuel obtain from polypropylene (PP-5) and high density polyethylene (HDPE-2) waste plastics mixture

    Energy Technology Data Exchange (ETDEWEB)

    Sarker, Moinuddin; Rashid, Mohammad Mamunor; Rahman, Md. Sadikur; Molla, Mohammed [Department of Research and Development, Natural State Research Inc, Stamford, (United States)

    2011-07-01

    Plastics are made by combination of small based molecules to form monomers. The monomers are then joined together by chemical polymerization mechanism to form polymers also known as plastics. These plastics contain various elements such as carbon, hydrogen, oxygen, nitrogen, chlorine and sul fur. The use of plastics is vastly expanded and it is being used in every sector of the world. However, using plastics does have a negative aspect, after use they end up in our landfill as waste causing numerous health and environmental problems. Landfill waste plastics release harmful gases due to the presence of carbon, chlorine and sul fur in them into the atmosphere causing climates to change drastically, equivalent to the effects of greenhouse gases (GHG) emission. To overcome these environmental issues, scientists have already developed many methods to converting these waste plastics into energy and fuel . We developed one new methods thermal cracking conversion to convert these waste plastics into usable liquid fuel . Thermal cracking conversion is a process to shorten the long chain hydrocarbons to produce liquid fuel in the absence of a catalyst. The thermal degradation process of the waste plastics long chain hydrocarbon to makes short chain hydrocarbon fuel. The fuel produced has been analyzed and tested according to standard methods. Key words: fuel , hydrocarbon, waste plastic, thermal degradation, conversion, GC/MS.

  5. Liquid fuel obtain from polypropylene (PP-5) and high density polyethylene (HDPE-2) waste plastics mixture

    International Nuclear Information System (INIS)

    Sarker, Moinuddin; Rashid, Mohammad Mamunor; Rahman, Md. Sadikur; Molla, Mohammed

    2011-01-01

    Plastics are made by combination of small based molecules to form monomers. The monomers are then joined together by chemical polymerization mechanism to form polymers also known as plastics. These plastics contain various elements such as carbon, hydrogen, oxygen, nitrogen, chlorine and sul fur. The use of plastics is vastly expanded and it is being used in every sector of the world. However, using plastics does have a negative aspect, after use they end up in our landfill as waste causing numerous health and environmental problems. Landfill waste plastics release harmful gases due to the presence of carbon, chlorine and sul fur in them into the atmosphere causing climates to change drastically, equivalent to the effects of greenhouse gases (GHG) emission. To overcome these environmental issues, scientists have already developed many methods to converting these waste plastics into energy and fuel . We developed one new methods thermal cracking conversion to convert these waste plastics into usable liquid fuel . Thermal cracking conversion is a process to shorten the long chain hydrocarbons to produce liquid fuel in the absence of a catalyst. The thermal degradation process of the waste plastics long chain hydrocarbon to makes short chain hydrocarbon fuel. The fuel produced has been analyzed and tested according to standard methods. Key words: fuel , hydrocarbon, waste plastic, thermal degradation, conversion, GC/MS

  6. Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility

    International Nuclear Information System (INIS)

    Dippre, M. A.

    2003-01-01

    A spent nuclear fuels (SNF) repackaging and storage facility was designed for the Idaho National Engineering and Environmental Laboratory (INEEL), with nuclear solid waste processing capability. Nuclear solid waste included contaminated or potentially contaminated spent fuel containers, associated hardware, machinery parts, light bulbs, tools, PPE, rags, swabs, tarps, weld rod, and HEPA filters. Design of the nuclear solid waste processing facilities included consideration of contractual, regulatory, ALARA (as low as reasonably achievable) exposure, economic, logistical, and space availability requirements. The design also included non-attended transfer methods between the fuel packaging area (FPA) (hot cell) and the waste processing area. A monitoring system was designed for use within the FPA of the facility, to pre-screen the most potentially contaminated fuel canister waste materials, according to contact- or non-contact-handled capability. Fuel canister waste materials which are not able to be contact-handled after attempted decontamination will be processed remotely and packaged within the FPA. Noncontact- handled materials processing includes size-reduction, as required to fit into INEEL permitted containers which will provide sufficient additional shielding to allow contact handling within the waste areas of the facility. The current design, which satisfied all of the requirements, employs mostly simple equipment and requires minimal use of customized components. The waste processing operation also minimizes operator exposure and operator attendance for equipment maintenance. Recently, discussions with the INEEL indicate that large canister waste materials can possibly be shipped to the burial facility without size-reduction. New waste containers would have to be designed to meet the drop tests required for transportation packages. The SNF waste processing facilities could then be highly simplified, resulting in capital equipment cost savings, operational

  7. Application of cascading thermoelectric generator and cooler for waste heat recovery from solid oxide fuel cells

    International Nuclear Information System (INIS)

    Zhang, Houcheng; Kong, Wei; Dong, Feifei; Xu, Haoran; Chen, Bin; Ni, Meng

    2017-01-01

    Highlights: • Cascading thermoelectric devices are proposed to recover waste heat from SOFCs. • A theoretical model is developed to analyze the new hybrid system performance. • Performance parameters for evaluating the hybrid system are specified. • Feasibility and effectiveness of the proposed system are demonstrated. • Effects of some important parameters on the system performance are discussed. - Abstract: Besides electricity generation, solid oxide fuel cells (SOFCs) produce a significant amount of waste heat, which needs to be immediately removed to ensure the normal operation of SOFCs. If the waste heat is recovered through bottoming thermal devices, the global efficiency of SOFCs can be improved. In this study, a new hybrid system mainly consisting of a thermoelectric generator, a thermoelectric cooler and an SOFC is proposed to recover the waste heat from SOFC for performance enhancement. The thermodynamic and electrochemical irreversible losses in each component are fully considered. An analytical relationship between the SOFC operating current density and the thermoelectric devices dimensionless electric current is derived, from which the range of SOFC operating current density that permits the thermoelectric devices to effectively work is determined. The equivalent power output and efficiency for the hybrid system are specified under different operating current density regions. The feasibility and effectiveness are illustrated by comparing the proposed hybrid system with the stand-alone SOFC. It is found that the power density and efficiency of the proposed system allow 2.3% and 4.6% larger than that of the stand-alone SOFC, respectively. Finally, various parametric analyses are performed to discuss the effects of some design and operation parameters on the hybrid system performance.

  8. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement

    International Nuclear Information System (INIS)

    1994-06-01

    The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel

  9. Report of the DOD-DOE Workshop on Converting Waste to Energy Using Fuel Cells

    Science.gov (United States)

    2011-10-01

    cell research, development, and demonstration. Along with the general program overview, Dr. Satyapal highlighted the vast amount of biogas resources...Page ii DOD-DOE Workshop Summary on Converting Waste to Energy Using Fuel Cells List of Tables Table 1. Comparison by Generator Type: Based on 40...Table 2. Typical Composition of Biogas from Various Waste Streams ....................................................... 8 Table D-1

  10. Integrated Data Base for 1989: Spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1989-11-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1988. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected defense-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, commercial reactor and fuel cycle facility decommissioning waste, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous, highly radioactive materials that may require geologic disposal. 45 figs., 119 tabs

  11. Radionuclide compositions of spent fuel and high level waste from commercial nuclear reactors

    International Nuclear Information System (INIS)

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

    1984-10-01

    This report provides information on radionuclide compositions of spent fuel and high level waste produced during reprocessing. The reactor types considered are Magnox, AGR, PWR and CFR. The activities of the radionuclides are calculated using the FISPIN code. The results are presented in a form suitable for radioactive waste management calculations. (author)

  12. Stabilization of high-level waste from a chloride volatility nuclear fuel reprocessing system

    International Nuclear Information System (INIS)

    Smith, L.A.; Thornton, T.A.

    1979-01-01

    Methods for stabilizing high-level waste from a chloride volatility thorium-based fuel coprocessing system have been studied. The waste, which is present as chloride salts, is combined with SiO 2 or Al 2 O 3 and pyrohydrolyzed to remove the chloride ions. The resulting solid is then combined with a flux and glassified. 3 figures, 4 tables

  13. Integrated data base for 1990: US spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1990-10-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1989. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 22 refs., 48 figs., 109 tabs

  14. Integrated Data Base for 1991: US spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1991-10-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1990. These data are based on the most reliable information available form government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated generally through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 160 refs., 61 figs., 142 tabs

  15. Indirect Determination of Chemical Composition and Fuel Characteristics of Solid Waste

    DEFF Research Database (Denmark)

    Riber, Christian; Christensen, Thomas Højlund

    Determination of chemical composition of solid waste can be performed directly or indirectly by analysis of combustion products. The indirect methodology instrumented by a full scale incinerator is the only method that can conclude on elements in trace concentrations. These elements are of great...... interest in evaluating waste management options by for example LCA modeling. A methodology description of indirect determination of chemical composition and fuel properties of waste is provided and validated by examples. Indirect analysis of different waste types shows that the chemical composition...... is significantly dependent on waste type. And the analysis concludes that the transfer of substances in the incinerator is a function of waste chemical content, incinerator technology and waste physical properties. The importance of correct representation of rare items in the waste with high concentrations...

  16. Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste

    Energy Technology Data Exchange (ETDEWEB)

    R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

    2010-02-01

    This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

  17. Preparation of the National Radioactive Waste and Spent Fuel Management Programme in Slovenia

    International Nuclear Information System (INIS)

    Kralj, M.; Zeleznik, N.; Mele, I.; Veselic, M.

    2006-01-01

    The first separate National Radioactive Waste and Spent Fuel Management Programme (National Programme) was prepared in Slovenia in 2005, as a separate part of the National Environmental Action Programme that was adopted in June 2005. In the previous National Environmental Action Programme from the year 1999, the radioactive waste and spent fuel management was mentioned only briefly in the paragraph on radiation and nuclear safety with two main objectives: to provide an effective management of radioactive waste, and to keep the environmental ionising radiation under control. The new National Programme from 2005 includes all topics being relevant for the management of the radioactive waste and spent fuel, from the legislation and identification of different waste streams in Slovenia, to the management of radioactive waste and spent fuel, the decommissioning of nuclear facilities and management of (TE)NORM. It deals also with the relevant actors in the radioactive waste management, communication and information activities, and the financial aspects of the radioactive waste and spent fuel management. The National Programme was already adopted by the Slovenian Government in October 2005 and will go to Parliament proceedings. The Technical bases for the National Programme was prepared by ARAO and presented to the government in the beginning of 2005. The frames for this document were taken from relevant strategic documents: the Programme of decommissioning the nuclear power plant Krsko and the radioactive waste and spent fuel management, prepared in 2004 by Slovenian and Croatian experts (ARAO and APO), the Proposal of LILW Management Strategy (1999), the Strategy of Spent Fuel Management (1996), and the Resolution on the National Energy Programme (2004). ARAO made a detailed study on the amount and types of radioactive waste produced in Slovenia and future arising with emphasis on the minimization on radioactive waste production. It considered all producers of LILW and

  18. A novel waste form for disposal of spent-nuclear-fuel reprocessing waste: A vitrifiable cement

    International Nuclear Information System (INIS)

    Gougar, M.L.D.; Scheetz, B.E.; Siemer, D.D.

    1999-01-01

    A cement capable of being hot isostatically pressed into a glass ceramic has been proposed as the waste form for spent-nuclear-fuel reprocessing wastes at the Idaho National Engineering and Environmental Laboratory (INEEL). This intermediate cement, with a composition based on that of common glasses, has been designed and tested. The cement formulations included mixed INEEL wastes, blast furnace slag, reactive silica, and INEEL soil or vermiculite, which were activated with potassium or sodium hydroxide. Following autoclave processing, the cements were characterized. X-ray diffraction analysis revealed three notable crystalline phases: quartz, calcite, and fluorite. Results of compressive strength testing ranged from 1452 and 4163 psi, exceeding the US Nuclear Regulatory Commission (NRC)-suggested standard of >500 psi. From American National Standards Institute/American Nuclear Society 16.1-1986 leach testing, effective diffusivities for Cs were determined to be on the order of 10 -11 to 10 -10 cm 2 /s and for Sr were 10 -12 cm 2 /s, which are four orders of magnitude less than diffusivities in some other radwaste materials. Average leach indices (LI) were 9.6 and 11.9 for Cs and Sr, respectively, meeting the NRC Standard of LI > 6. The 28-day Materials Characterization Center-1 leach testing resulted in normalized elemental mass losses between 0.63 and 28 g/(m 2 ·day) for Cs and between 0.34 and 0.70 g/(m 2 ·day) industry-accepted standard while Cs losses indicate a process sensitive parameter

  19. EDRP public local inquiry, UKAEA/BNFL precognition on: PFR fuel reprocessing and radioactive waste management at Dounreay

    International Nuclear Information System (INIS)

    Pugh, O.

    1986-01-01

    A description of PFR fuel reprocessing at Dounreay is given, including brief details of fuel assembly transport, dismantling, chemical separation processes and reprocessing experience. The origin of radioactive wastes from PFR reprocessing, and the types of radioactive waste are outlined. The management of radioactive waste, including storage, treatment and disposal is described. (U.K.)

  20. Method for recovering palladium and technetium values from nuclear fuel reprocessing waste solutions

    Science.gov (United States)

    Horwitz, E. Philip; Delphin, Walter H.

    1979-07-24

    A method for recovering palladium and technetium values from nuclear fuel reprocessing waste solutions containing these and other values by contacting the waste solution with an extractant of tricaprylmethylammonium nitrate in an inert hydrocarbon diluent which extracts the palladium and technetium values from the waste solution. The palladium and technetium values are recovered from the extractant and from any other coextracted values with a strong nitric acid strip solution.

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

    International Nuclear Information System (INIS)

    Herscovich de Pahissa, Marta

    2007-01-01

    Geological disposal of spent nuclear fuel and high level waste from reprocessing, properly conditioned, is described. This issue is a major challenge related to radioactive waste management. Several options are analyzed, such as application of separation and transmutation to high level waste before final disposal; need of multinational repositories; a phased approach to deep geological disposal and long term surface storage. Bearing in mind this information, a future article will report the state of art in the world. (author) [es

  2. Handling of spent nuclear fuel and final storage of vitrified high level reprocessing waste

    International Nuclear Information System (INIS)

    1978-01-01

    The report gives a general summary of the Swedish KBS-project on management and disposal of vitrified reprocessed waste. Its final aim is to demostrate that the means of processing and managing power reactor waste in an absolutely safe way, as stipulated in the Swedish so called Conditions Act, already exist. Chapters on Storage facility for spent fuel, Intermidiate storage of reprocessed waste, Geology, Final repository, Transportation, Protection, and Siting. (L.E.)

  3. Utilization of waste coconut coir dust as a source of fuel

    Energy Technology Data Exchange (ETDEWEB)

    Festin, T.F.; Jose, W.I.

    1979-01-01

    A review on the production of a gaseous fuel by the pyrolysis of waste coir dust, which is a by-product in the manufacturing of coir fibers from coconut husks. Experimental and pilot-plant studies on the pyrolysis of coir dust are discussed and the properties of the dust and the fuel gas produced are given. (Refs. 13).

  4. Wood wastes and residues generated along the Colorado Front Range as a potential fuel source

    Science.gov (United States)

    Julie E. Ward; Kurt H. Mackes; Dennis L. Lynch

    2004-01-01

    Throughout the United States there is interest in utilizing renewable fuel sources as an alternative to coal and nat-ural gas. This project was initiated to determine the availability of wood wastes and residues for use as fuel in ce-ment kilns and power plants located along the Colorado Front Range. Research was conducted through literature searches, phone surveys,...

  5. Fuel cycle and waste newsletter, Vol. 3, No. 3, December 2007

    International Nuclear Information System (INIS)

    2007-12-01

    This issue of the Fuel Cycle and Waste Newsletter reports on the IAEA's International Conference on Research Reactors which focused on sharing the latest scientific, technical and safety information related to research reactors including projects on design, construction and commissioning of new research facilities. This issue further covers reports of some of the activities performed by the Division of Nuclear Fuel Cycle and Waste Technology including information on upgrading radioactive waste management facilities, aqueous homogeneous reactors for isotope production, activities of the contact experts group in 2007, current activities related to HEU minimization, repatriation of radioactive sources in Nigeria, the 2007 TWGNFCO (Nuclear Fuel Cycle Options and Spent Fuel Management) meeting, the stakeholder involvement in decommissioning (draft technical report in preparation), initial activities of the International Decommissioning Network (IDN), spent fuel publications, the thorium fuel cycle, the Nuclear Fuel Cycle Simulation System (NFCSS). Finally, it presents a bibliography of recent publications of IAEA's Division of Nuclear Fuel Cycle and Waste Technology as well as a list of Meetings in 2008

  6. Thermophysical properties of composite fuel based on T grade coal (Alardinskoe deposit) and timber industry wastes

    Science.gov (United States)

    Yankovsky, S. A.; Tolokolnikov, A. A.; Gubin, V. E.; Slyusarskiy, K. V.; Zenkov, A. V.

    2017-09-01

    Results of experimental studies of composite fuel thermal decomposition processes based on T grade coal (Alardinskoe deposit) and timber industry wastes (fine wood) are presented. C, H, N, S weight percentage of each component of composite fuel was determined experimentally. It has been established that with an increase in wood concentration up to 50% in composite fuel, its energy characteristics decrease by less than 3.6%, while the yield of fly ash is 39.7%. An effective composite fuel composition has been defined as 50%/50%. Results of performed experimental studies suggest that it is possible to use composite fuels based on coal and wood at thermal power plants.

  7. 10 CFR 51.52 - Environmental effects of transportation of fuel and waste-Table S-4.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Environmental effects of transportation of fuel and waste... Environmental effects of transportation of fuel and waste—Table S-4. Under § 51.50, every environmental report... detailed analysis of the environmental effects of transportation of fuel and wastes to and from the reactor...

  8. Integrated data management system for radioactive waste and spent fuel in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Park, Yong Taek [Korea Power Engineering Co., Inc., Yongin (Korea, Republic of)

    2002-05-15

    An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Through the system, the five principles(independence, openness, clearance, efficiency and reliance) of safety regulation can be realized and public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted. By providing reliable information and openness within the international nuclear community can be ensured and efficient support of international agreements among contracting parties can be ensured. By operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management), the system can compensate for the imperfections in safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible for holistic control and reorganization of the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy so as to integrate safe management and unit safe disposal. To meet this objectives, design of the database system structure and the study of input/output data validation and verification methodology was performed during the second phase of this project.

  9. Backfill formulations for a nuclear fuel waste disposal vault

    International Nuclear Information System (INIS)

    Yong, R.N.; Boonsinsuk, P.; Wong, G.; Ming, X.D.; Caporuscio, F.; Lytle, P.

    1987-01-01

    Atomic Energy of Canada Limited and Ontario Hydro are studying the concept of disposing of nuclear fuel wastes in a vault within the Canadian Shield. After nuclear waste containers have been emplaced in a vault, the vault will have to be backfilled permanently. A suitable backfill material should have low hydraulic conductivity and high radionuclide sorption capacity. The research was done with a goal of recommending a specification for formulating this backfill material. This report suggests that such a backfill material should be a mixture of coarse aggregates and swelling clay. Actual trial mixtures were prepared using crushed granite and natural Lake Agassiz clay. Various trial mixtures were subjected to constant-head permeability tests. The results indicate that the hydraulic conductivity of the aggregate-clay mixtures could be close to those of the clay (by itself) when the clay content was in the range of 25% or more. The resulting hydraulic conductivity of about 10 -10 m/s is considered to be low, especially since the maximum grain size is 19.1 mm. Selected mixtures were evaluated for free swell and swelling pressure, both of which increased with increasing clay content. When the clay content was 25%, the free swell was about 4%, compared with 6% for the 100% clay. The corresponding swelling pressure was about 16 kPa - in comparison to 48 kPa for the 100% clay. These results indicate that the proposed backfill material should contain about 25% clay, with a maximum grain size of 19.1 mm. The selected mixture was also tested to evaluate the effects of mixing methods, load-carrying capacity and compaction techniques suitable for the underground vault conditions. The proposed backfill material appeared to perform satisfactorily according to the criteria demanded. The backfill material proposed was further tested for its behaviour during water intake. The unsaturated hydraulic conductivity was found to be approximately 10 -10 m/s and the swelling pressure was

  10. Performance of borosilicate glass, Synroc and spent fuel as nuclear waste forms

    International Nuclear Information System (INIS)

    Lutze, W.; Grambow, B.; Ewing, R.C.

    1990-01-01

    Presently, there are three prominent waste forms under consideration for the disposal of high-level waste: Borosilicate glass and Synroc for high-level radioactive waste from fuel reprocessing and spent fuel as the waste form for non-reprocessed fuel. Using the present experimental data base, one may compare the performance of these three waste forms under repository relevant conditions. In low water flow regimes and at temperatures less than 100 degree C, the fractional release rates of all three waste forms are low, on the order of 10-7/d or less and may decrease with time. Under these conditions the three waste forms behave similarly. At elevated temperatures or in high flow regimes, the durability of borosilicate glass will be much less than that of Synroc, and thus, for certain disposal schemes (e.g., deep burial) Synroc is preferable. All predictions of the long-term behavior are based on the extrapolation of short term experimental data, we point out that appropriate and useful natural analogues are available for each of these waste forms and should be used in the performance assessment of each waste form's long-term behavior. 14 refs

  11. Summary of non-US national and international fuel cycle and radioactive waste management programs 1982

    International Nuclear Information System (INIS)

    Harmon, K.M.; Kelman, J.A.

    1982-08-01

    Brief program overviews of fuel cycle, spent fuel, and waste management activities in the following countries are provided: Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, German Federal Republic, India, Italy, Japan, Republic of Korea, Mexico, Netherlands, Pakistan, South Africa, Spain, Sweden, Switzerland, Taiwan, USSR, and the United Kingdom. International nonproliferation activities, multilateral agreements and projects, and the international agencies specifically involved in the nuclear fuel cycle are also described

  12. Summary of non-US national and international fuel cycle and radioactive waste management programs 1982

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K.M.; Kelman, J.A.

    1982-08-01

    Brief program overviews of fuel cycle, spent fuel, and waste management activities in the following countries are provided: Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, German Federal Republic, India, Italy, Japan, Republic of Korea, Mexico, Netherlands, Pakistan, South Africa, Spain, Sweden, Switzerland, Taiwan, USSR, and the United Kingdom. International nonproliferation activities, multilateral agreements and projects, and the international agencies specifically involved in the nuclear fuel cycle are also described.

  13. Literature survey on metal waste form for metallic waste from electrorefiners for the electrometallurgical treatment of spent metallic fuels

    International Nuclear Information System (INIS)

    Nishimura, Tomohiro

    2003-01-01

    This report summarizes the recent results of the metal waste form development activities at the Argonne National Laboratory in the USA for high-level radioactive metallic waste (stainless-steel (SS) cladding hulls, zirconium (Zr), noble-metal fission products (NMFPs), etc.) from electrorefiners for the electrometallurgical treatment of spent metallic fuels. Their main results are as follows: (1) SS- 15 wt.% Zr- ∼4 wt.% NMFPs alloy was selected as the metal waste form, (2) metallurgical data, properties, long-term corrosion data, etc. of the alloy have been collected, (3) 10-kg ingots have been produced in hot tests and a 60-kg production machine is under development. The following research should be made to show the feasibility of the metal waste form in Japan: (1) degradation assessment of the metal waste form in Japanese geological repository environments, and (2) clarification of the maximum allowable contents of NMFPs. (author)

  14. Radionuclide Inventories for DOE SNF Waste Stream and Uranium/Thorium Carbide Fuels

    International Nuclear Information System (INIS)

    K.L. Goluoglu

    2000-01-01

    The objective of this calculation is to generate radionuclide inventories for the Department of Energy (DOE) spent nuclear fuel (SNF) waste stream destined for disposal at the potential repository at Yucca Mountain. The scope of this calculation is limited to the calculation of two radionuclide inventories; one for all uranium/thorium carbide fuels in the waste stream and one for the entire waste stream. These inventories will provide input in future screening calculations to be performed by Performance Assessment to determine important radionuclides

  15. Full scale tests on remote handled FFTF fuel assembly waste handling and packaging

    International Nuclear Information System (INIS)

    Allen, C.R.; Cash, R.J.; Dawson, S.A.; Strode, J.N.

    1986-01-01

    Handling and packaging of remote handled, high activity solid waste fuel assembly hardware components from spent FFTF reactor fuel assemblies have been evaluated using full scale components. The demonstration was performed using FFTF fuel assembly components and simulated components which were handled remotely using electromechanical manipulators, shielding walls, master slave manipulators, specially designed grapples, and remote TV viewing. The testing and evaluation included handling, packaging for current and conceptual shipping containers, and the effects of volume reduction on packing efficiency and shielding requirements. Effects of waste segregation into transuranic (TRU) and non-transuranic fractions also are discussed

  16. Remotely replaceable fuel and feed nozzles for the new waste calcining facility calciner vessel

    International Nuclear Information System (INIS)

    Fletcher, R.D.; Carter, J.A.; May, K.W.

    1978-01-01

    The development and testing of remotely replaceable fuel and feed nozzles for calcination of liquid radioactive wastes in the calciner vessel of the New Waste Calcining Facility being built at the Idaho National Engineering Laboratory is described. A complete fuel nozzle assembly was fabricated and tested at the Remote Maintenance Development Facility to evolve design refinements, identify required support equipment, and develop handling techniques. The design also provided for remote replacement of the nozzle support carriage and adjacent feed and fuel pipe loops using two pairs of master-slave manipulators

  17. Volume reduction technology development for solid wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Oh, Won Zin; Lee, Kune Woo; Song, Kee Chan; Choi, Wang Kyu; Kim, Young Min

    1998-07-01

    A great deal of solid wastes, which have various physical, chemical, and radiological characteristics, are generated from the nuclear fuel cycle facility as well as radioactive gaseous and liquid wastes. The treatment of the large quantity of solid wastes from the nuclear fuel cycle have great technical, economical and social effects on the domestic policy decision on the nuclear fuel cycle, such as operation and maintenance of the facility, waste disposal, etc. Cement immobilization, super compaction, and electrochemical dissolution were selected as the volume reduction technologies for solid wastes, which will generated from the domestic nuclear fuel cycle facility in the future. And the assessment of annual arisings and the preliminary conceptual design of volume reduction processes were followed. Electrochemical decontamination of α-radionuclides from the spent fuel hulls were experimentally investigated, and showed the successful results. However, β/γ radioactivity did not reduce to the level below which hulls can be classified as the low-level radioactive waste and sent to the disposal site for the shallow land burial. The effects of the various process variables in the electrochemical decontamination were experimentally analysed on the process. (author). 32 refs., 32 tabs., 52 figs

  18. Refuse derived fuels in Cement Kilns: Italian experience

    International Nuclear Information System (INIS)

    Del Borghi, M.; Strazza, C.; Del Borghi, A.

    2009-01-01

    This study investigates the results of a year (2006) of air emissions gathering in the various Italian cement plants, and, in particular, on 73 kilns subdivided by production class, kiln type and alternative fuels use for type and quantity. The emission parameters considered have been: total dust, SO 2 , NOx, CO, TOC, HCl, HF, metals, PAH and PCDD/F. The work has involved a comparison between the results of the average concentrations detected for the various pollutants, separately for the plants using only traditional fuels and using also alternative fuels. The obtained results show that the use of alternative fuels by the 22 kilns investigated has not any influence on the emission values of the pollutants examined; on the contrary, in certain cases these emissions result less than the limits legally allowed for the use of traditional fuels. A comparison between the results obtained from the Italian kilns and those published by Cembureau from 200 European kilns, confirms that the emission performances of cement kilns appear independent for the use of alternative fuels with the percentages usually employed. This study also highlights the benefits on the global environmental balance for the use of RDF as alternative fuel. [it

  19. Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 1

    International Nuclear Information System (INIS)

    Wuschke, D.M.; Gillespie, P.A.; Main, D.E.

    1985-07-01

    The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second assessment was performed in 1984 and is documented in the Second Interim assessment of the Canadian Concept for Nuclear Fuel Waste Disposal Volumes 1 to 4. This volume, entitled Summary, is a condensation of Volumes 2, 3 and 4. It briefly describes the Canadian nuclear fuel waste disposal concept, and the methods and results of the second interim pre-closure and post-closure assessments of that concept. 46 refs

  20. A Novel Fuel/Reactor Cycle to Implement the 300 Years Nuclear Waste Policy Approach - 12377

    Energy Technology Data Exchange (ETDEWEB)

    Carelli, M.D.; Franceschini, F.; Lahoda, E.J. [Westinghouse Electric Company LLC., Cranberry Township, PA (United States); Petrovic, B. [Georgia Institute of Technology, Atlanta, GA (United States)

    2012-07-01

    A thorium-based fuel cycle system can effectively burn the currently accumulated commercial used nuclear fuel and move to a sustainable equilibrium where the actinide levels in the high level waste are low enough to yield a radiotoxicity after 300 years lower than that of the equivalent uranium ore. The second step of the Westinghouse approach to solving the waste 'problem' has been completed. The thorium fuel cycle has indeed the potential of burning the legacy TRU and achieve the waste objective proposed. Initial evaluations have been started for the third step, development and selection of appropriate reactors. Indications are that the probability of show-stoppers is rather remote. It is, therefore, believed that development of the thorium cycle and associated technologies will provide a permanent solution to the waste management. Westinghouse is open to the widest collaboration to make this a reality. (authors)

  1. The disposal of Canada's nuclear fuel waste: postclosure assessment of a reference system

    International Nuclear Information System (INIS)

    Goodwin, B.W.; McConnell, D.B.; Andres, T.H.

    1994-01-01

    The concept for disposal of Canada's nuclear fuel waste is based on a vault located deep in plutonic rock of the Canadian Shield. We document in this report a method to assess the long-term impacts of a disposal facility for nuclear fuel waste. The assessment integrates relevant information from engineering design studies, site investigations, laboratory studies, expert judgment and detailed mathematical analyses to evaluate system performance in terms of safety criteria, guidelines and standards. The method includes the use of quantitative tools such as the Systems Variability Analysis computer Code (SYVAC) to deal with parameter uncertainty and the use of reasoned arguments based on well-established scientific principles. We also document the utility of the method by describing its application to a hypothetical implementation of the concept called the reference disposal system. The reference disposal system generally conforms to the overall characteristics of the concept, except we have made some specific site and design choices so that the assessment would be more realistic. To make the reference system more representative of a real system, we have used the geological observations of the AECL's Whiteshell Research Area located near Lac du Bonnet, Manitoba, to define the characteristics of the geosphere and the groundwater flow system. This research area has been subject to more than a decade of geological and hydrological studies. The analysis of the reference disposal system provides estimates of radiological and chemical toxicity impacts on members of a critical group and estimates of possible impacts on the environment. The latter impacts include estimates of radiation dose to nonhuman organisms. Other quantitative analyses examine the use of derived constraints to improve the margin of safety, the effectiveness of engineered and natural barriers, and the sensitivity of the results to influential features, events, and processes of the reference disposal

  2. Removal potential of toxic 2378-substituted PCDD/F from incinerator flue gases by waste-derived activated carbons.

    Science.gov (United States)

    Hajizadeh, Yaghoub; Onwudili, Jude A; Williams, Paul T

    2011-06-01

    The application of activated carbons has become a commonly used emission control protocol for the removal or adsorption of persistent organic pollutants from the flue gas streams of waste incinerators. In this study, the 2378-substituted PCDD/F removal efficiency of three types of activated carbons derived from the pyrolysis of refuse derived fuel, textile waste and scrap tyre was investigated and compared with that of a commercial carbon. Experiments were carried out in a laboratory scale fixed-bed reactor under a simulated flue gas at 275°C with a reaction period of four days. The PCDD/F in the solid matrices and exhaust gas, were analyzed using gas chromatography coupled with a triple quadrupole mass spectrometer. In the absence of activated carbon adsorbent, there was a significant increase in the concentration of toxic PCDD/F produced in the reacted flyash, reaching up to 6.6 times higher than in the raw flyash. In addition, there was a substantial release of PCDD/F into the gas phase, which was found in the flue gas trapping system. By application of the different commercial, refuse derived fuel, textile and tyre activated carbons the total PCDD/F toxic equivalent removal efficiencies in the exhaust gas stream were 58%, 57%, 64% and 52%, respectively. In general, the removal of the PCDDs was much higher with an average of 85% compared to PCDFs at 41%. Analysis of the reacted activated carbons showed that there was some formation of PCDD/F, for instance, a total of 60.6 μg I-TEQ kg(-1) toxic PCDD/F was formed in the refuse derived fuel activated carbon compared to 34 μg I-TEQ kg(-1) in the commercial activated carbon. The activated carbons derived from the pyrolysis of waste, therefore, showed good potential as a control material for PCDD/F emissions in waste incinerator flue gases. Copyright © 2011 Elsevier Ltd. All rights reserved.

  3. Radioactive wastes. Commune convention about the safety of spent fuel management and about the radioactive waste management

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    This common convention do not give detailed safety standards but general obligations whom objective is the development of a safety culture in the world. It concerns the spent fuels (valuable and valued by the reprocessing) and radioactive wastes (matter without any later use). (N.C.)

  4. NWTS program criteria for mined geologic disposal of nuclear waste: functional requirements and performance criteria for waste packages for solidified high-level waste and spent fuel

    International Nuclear Information System (INIS)

    1982-07-01

    The Department of Energy (DOE) has primary federal responsibility for the development and implementation of safe and environmentally acceptable nuclear waste disposal methods. Currently, the principal emphasis in the program is on emplacement of nuclear wastes in mined geologic repositories well beneath the earth's surface. A brief description of the mined geologic disposal system is provided. The National Waste Terminal Storage (NWTS) program was established under DOE's predecessor, the Energy Research and Development Administration, to provide facilities for the mined geologic disposal of radioactive wastes. The NWTS program includes both the development and the implementation of the technology necessary for designing, constructing, licensing, and operating repositories. The program does not include the management of processing radioactive wastes or of transporting the wastes to repositories. The NWTS-33 series, of which this document is a part, provides guidance for the NWTS program in the development and implementation of licensed mined geologic disposal systems for solidified high-level and transuranic (TRU) wastes. This document presents the functional requirements and performance criteria for waste packages for solidified high-level waste and spent fuel. A separate document to be developed, NWTS-33(4b), will present the requirements and criteria for waste packages for TRU wastes. The hierarchy and application of these requirements and criteria are discussed in Section 2.2

  5. Application of fuel cell for pyrite and heavy metal containing mining waste

    Science.gov (United States)

    Keum, H.; Ju, W. J.; Jho, E. H.; Nam, K.

    2015-12-01

    Once pyrite and heavy metal containing mining waste reacts with water and air it produces acid mine drainage (AMD) and leads to the other environmental problems such as contamination of surrounding soils. Pyrite is the major source of AMD and it can be controlled using a biological-electrochemical dissolution method. By enhancing the dissolution of pyrite using fuel cell technology, not only mining waste be beneficially utilized but also be treated at the same time by. As pyrite-containing mining waste is oxidized in the anode of the fuel cell, electrons and protons are generated, and electrons moves through an external load to cathode reducing oxygen to water while protons migrate to cathode through a proton exchange membrane. Iron-oxidizing bacteria such as Acidithiobacillus ferrooxidans, which can utilize Fe as an electron donor promotes pyrite dissolution and hence enhances electrochemical dissolution of pyrite from mining waste. In this study mining waste from a zinc mine in Korea containing 17 wt% pyrite and 9% As was utilized as a fuel for the fuel cell inoculated with A. ferrooxidans. Electrochemically dissolved As content and chemically dissolved As content was compared. With the initial pH of 3.5 at 23℃, the dissolved As concentration increased (from 4.0 to 13 mg/L after 20 d) in the fuel cell, while it kept decreased in the chemical reactor (from 12 to 0.43 mg/L after 20 d). The fuel cell produced 0.09 V of open circuit voltage with the maximum power density of 0.84 mW/m2. Dissolution of As from mining waste was enhanced through electrochemical reaction. Application of fuel cell technology is a novel treatment method for pyrite and heavy metals containing mining waste, and this method is beneficial for mining environment as well as local community of mining areas.

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

    International Nuclear Information System (INIS)

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

    1998-08-01

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

  7. Survey of a technology to introduce the waste-fueled power generation. Basic manual for introduction of the waste-fueled power generation; Haikibutsu hatsuden donyu gijutsu chosa. Haikibutsu hatsuden donyu kihon manual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    Local government offices, etc., which are expected to shoulder responsibility for introducing the waste-fueled power generation, want to need exact information on technical information concerning the waste-fueled power generation and the method to materialize the introduction plan, etc. Therefore, Electric Power Development Co. surveyed and studied it under the contract with NEDO. The results were collected together as a basic manual for introduction of the waste-fueled power generation. As an outline of the waste-fueled power generation, the manual explains the significance, the present situation and potentials, the waste-fueled power system, an outline of working out the waste-fueled power generation plan, an outline of construction and operation/maintenance of the waste-fueled power generation, an outline of various systems relating to the waste-fueled power generation, etc. As the items for the study of making a concrete plan for power generation equipment, the manual explains the amount of refuse to be incinerated, the present status of generation capacity as viewed from the quality of refuse, the quality of refuse and the design of power generation equipment, boiler efficiency, power generation efficiency, construction cost and operation cost, etc. In addition, the paper describes a case study of the waste-fueled power generation plan. 118 figs., 39 tabs.

  8. Spent Nuclear Fuel Option Study on Hybrid Reactor for Waste Transmutation

    International Nuclear Information System (INIS)

    Hong, Seong Hee; Kim, Myung Hyun

    2016-01-01

    DUPIC nuclear fuel can be used in hybrid reactor by compensation of subcritical level through (U-10Zr) fuel. Energy production performance of Hyb-WT with DUPIC is grateful because it has high EM factor and performs waste transmutation at the same time. However, waste transmutation performance should be improved by different fissile fuel instead of (U-10Zr) fuel. SNF (Spent Nuclear Fuel) disposal is one of the problems in the nuclear industry. FFHR (Fusion-Fission Hybrid Reactor) is one of the most attractive option on reuse of SNF as a waste transmutation system. Because subcritical system like FFHR has some advantages compared to critical system. Subcritical systems have higher safety potential than critical system. Also, there is suppressed excess reactivity at BOC (Beginning of Cycle) in critical system, on the other hand there is no suppressed reactivity in subcritical system. Our research team could have designed FFHR for waste transmutation; Hyb-WT. Various researches have been conducted on fuel and coolant option for optimization of transmutation performance. However, Hyb-WT has technical disadvantage. It is required fusion power (Pfus) which is the key design parameter in FFHR is increased for compensation of decreasing subcritical level. As a result, structure material integrity is damaged under high irradiation condition by increasing Pfus. Also, deep burn of reprocessed SNF is limited by weakened integrity of structure material. Therefore, in this research, SNF option study will be conducted on DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactor) fuel, TRU fuel and DUPIC + TRU mixed fuel for optimization of Hyb-WT performance. Goal of this research is design check for low required fusion power and high waste transmutation. In this paper, neutronic analysis is conducted on Hyb-WT with DUPIC nuclear fuel. When DUPIC nuclear fuel is loaded in fast neutron system, supplement fissile materials need to be loaded together for compensation of low criticality

  9. Spent Nuclear Fuel Option Study on Hybrid Reactor for Waste Transmutation

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Seong Hee; Kim, Myung Hyun [Kyung Hee University, Yongin (Korea, Republic of)

    2016-05-15

    DUPIC nuclear fuel can be used in hybrid reactor by compensation of subcritical level through (U-10Zr) fuel. Energy production performance of Hyb-WT with DUPIC is grateful because it has high EM factor and performs waste transmutation at the same time. However, waste transmutation performance should be improved by different fissile fuel instead of (U-10Zr) fuel. SNF (Spent Nuclear Fuel) disposal is one of the problems in the nuclear industry. FFHR (Fusion-Fission Hybrid Reactor) is one of the most attractive option on reuse of SNF as a waste transmutation system. Because subcritical system like FFHR has some advantages compared to critical system. Subcritical systems have higher safety potential than critical system. Also, there is suppressed excess reactivity at BOC (Beginning of Cycle) in critical system, on the other hand there is no suppressed reactivity in subcritical system. Our research team could have designed FFHR for waste transmutation; Hyb-WT. Various researches have been conducted on fuel and coolant option for optimization of transmutation performance. However, Hyb-WT has technical disadvantage. It is required fusion power (Pfus) which is the key design parameter in FFHR is increased for compensation of decreasing subcritical level. As a result, structure material integrity is damaged under high irradiation condition by increasing Pfus. Also, deep burn of reprocessed SNF is limited by weakened integrity of structure material. Therefore, in this research, SNF option study will be conducted on DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactor) fuel, TRU fuel and DUPIC + TRU mixed fuel for optimization of Hyb-WT performance. Goal of this research is design check for low required fusion power and high waste transmutation. In this paper, neutronic analysis is conducted on Hyb-WT with DUPIC nuclear fuel. When DUPIC nuclear fuel is loaded in fast neutron system, supplement fissile materials need to be loaded together for compensation of low criticality

  10. Combustion Characterization of Bio-derived Fuels and Additives

    DEFF Research Database (Denmark)

    Hashemi, Hamid

    Climate change has become a serious concern nowadays. The main reason is believed to be the high emission of greenhouse gases, namely CO2 which is mainly produced from the combustion of fossil fuels. At the same time, energy demand has increased exponentially while the energy supply mainly depends...... on fossil fuels, especially for transportation. The practical strategy to address such problems in medium term is to increase the efficiency of combustion-propelled energy-production systems, as well as to reduce the net release of CO2 and other harmful pollutants, likely by using nonconventional fuels....... Modern internal combustion engines such as Homogeneous Charge Compression Ignition (HCCI) engines are more efficient and fuel-flexible compared to the conventional engines, making opportunities to reduce the release of greenhouse and other polluting gases to the environment. Combustion temperature...

  11. Process and equipment qualification of the ceramic and metal waste forms for spent fuel treatment

    International Nuclear Information System (INIS)

    Marsden, Ken; Knight, Collin; Bateman, Kenneth; Westphal, Brian; Lind, Paul

    2005-01-01

    The electrometallurgical process for treating sodium-bonded spent metallic fuel at the Materials and Fuels Complex of the Idaho National Laboratory separates actinides and partitions fission products into two waste forms. The first is the metal waste form, which is primarily composed of stainless steel from the fuel cladding. This stainless steel is alloyed with 15w% zirconium to produce a very corrosion-resistant metal which binds noble metal fission products and residual actinides. The second is the ceramic waste form which stabilizes fission product-loaded chloride salts in a sodalite and glass composite. These two waste forms will be packaged together for disposal at the Yucca Mountain repository. Two production-scale metal waste furnaces have been constructed. The first is in a large argon-atmosphere glovebox and has been used for equipment qualification, process development, and process qualification - the demonstration of process reliability for production of the DOE-qualified metal waste form. The second furnace will be transferred into a hot cell for production of metal waste. Prototype production-scale ceramic waste equipment has been constructed or procured; some equipment has been qualified with fission product-loaded salt in the hot cell. Qualification of the remaining equipment with surrogate materials is underway. (author)

  12. Study utilization of extractable petroleum hydrocarbons biodegradation waste as the main material for making solid fuels

    Science.gov (United States)

    Hendrianie, Nuniek; Juliastuti, Sri Rachmania; Ar-rosyidah, Fanny Husna; Rochman, Hilal Abdur

    2017-05-01

    Nowadays the existence of energy sources of oil and was limited. Therefore, it was important to searching for new innovations of renewable energy sources by utilizing the waste into a source of energy. On the other hand, the process of extractable petroleum hydrocarbons biodegradation generated sludge that had calorific value and untapped. Because of the need for alternative sources of energy innovation with the concept of zero waste and the fuel potential from extractable petroleum hydrocarbons biodegradation waste, so it was necessary to study the use of extractable petroleum hydrocarbons biodegradation waste as the main material for making solid fuel. In addition, sawdust is a waste that had a great quantities and also had a high calorific value to be mixed with extractable petroleum hydrocarbons biodegradation waste. The purpose of this study was to determine the characteristics of the extractable petroleum hydrocarbons biodegradation waste and to determine the potential and a combination of a mixture of extractable petroleum hydrocarbons biodegradation waste and sawdust which has the best calorific value. The variables of this study was the composition of the waste and sawdust as follows 1:1; 1:3; and 3:1 (mass of sawdust : mass of waste) and time of sawdust carbonization was 10, 15 and 20 minutes. Sawdust was carbonized to get the high heating value. The characteristic of main material and fuel analysis performed with proximate analysis. While the calorific value analysis was performed with a bomb calorimeter. From the research, it was known that extractable petroleum hydrocarbons biodegradation waste had a moisture content of 3.06%; volatile matter 19.98%; ash content of 0.56%; fixed carbon content of 76.4% and a calorific value of 717 cal/gram. And a mixture that had the highest calorific value (4286.5 cal/gram) achieved in comparison sawdust : waste (3:1) by carbonization of sawdust for 20 minutes.

  13. Strategic environmental assessment of the national programme for the safe management of spent fuel and radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Steinhoff, Mathias; Kallenbach-Herbert, Beate; Claus, Manuel [Oeko-Institut e.V. Darmstadt (Germany); and others

    2015-03-27

    The report on the strategic environmental audit for the national waste disposal program covers the following issues: aim of the study, active factors, environmental objectives; description and evaluation of environmental impact including site selection criteria for final repositories of heat generating radioactive waste, intermediate storage of spent fuel elements and waste from reprocessing plants, disposal of wastes retrieved from Asse II; hypothetical zero variants.

  14. Strategic environmental assessment of the national programme for the safe management of spent fuel and radioactive waste

    International Nuclear Information System (INIS)

    Steinhoff, Mathias; Kallenbach-Herbert, Beate; Claus, Manuel

    2015-01-01

    The report on the strategic environmental audit for the national waste disposal program covers the following issues: aim of the study, active factors, environmental objectives; description and evaluation of environmental impact including site selection criteria for final repositories of heat generating radioactive waste, intermediate storage of spent fuel elements and waste from reprocessing plants, disposal of wastes retrieved from Asse II; hypothetical zero variants.

  15. Climate impacts from import of waste fuels; Klimatpaaverkan fraan import av braennbart avfall

    Energy Technology Data Exchange (ETDEWEB)

    Haraldsson, Maarten; Sundberg, Johan (Profu, Moelndal (Sweden))

    2009-04-15

    Imports of combustible waste has increased in recent years and imported waste has become an increasingly important fuel in the Swedish district heating systems. The projections for the next few years show that the imports can be much higher, partly due to reduced amounts of waste in the wake of economic downturn the world economy, partly because several new incinerators will be put into operation. In a environmental perspective, imports are controversial and it has been proposed that imports should be restricted. This report provides an assessment of the climate impact of importing waste for combustion. The report shows that greenhouse gas emissions due to imports of waste to the Swedish district heating plants in 2007 was reduced by 500 000 tonnes of carbon dioxide. This is equivalent to the emissions from 300 000 Swedes car journeys a year, or 2.5% of the total emission reduction target set by the Government for the non-trading sector until 2020. Imports of wood waste-chips accounts for the largest reduction, but the study shows that imports of other types of waste contribute to a reduction in emissions of greenhouse gases. The reasons for the reduction is that the use of imported waste fuel substitute for other heating and electricity generation, which gives the consequence that emissions are avoided. The largest emission reductions are obtained, however, by the importation of household waste by replacing the alternative waste treatment of the corresponding waste in the country of origin. In the countries from which imports of waste currently takes place there is a lack of treatment capacity for organic waste. The alternative treatment available is primarily deposition. This treatment causes significant emissions of methane, which is a very strong greenhouse gas. The shipment of waste that occur as a result of imports gives a marginal contribution of greenhouse gases, compared against the emission reductions outlined above

  16. Sorption and chromatographic techniques for processing liquid waste of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Gelis, V.M.; Milyutin, V.V.; Chuveleva, E.A.; Maslova, G.B.; Kudryavtseva, S.P.; Firsova, L.A.; Kozlitin, E.A.

    2000-01-01

    In the spent nuclear fuel processing procedures the significant quantity of high level liquid waste containing long-lived high toxic radionuclides of cesium, strontium, promethium, americium, curium, etc. is generated. Separation of those radionuclides from the waste not merely simplifies the further safe waste handling but also reduces the waste processing operation costs due to the market value of certain individual radionuclide preparations. Recovery and separation of high grade pure long-lived radionuclide preparations is frequently performed by means of chromatographic techniques. (authors)

  17. Radioactive waste and the back part of fuel cycle of nuclear installations in Slovakia

    International Nuclear Information System (INIS)

    Koprda, V.

    2004-01-01

    This article is devoted to radioactive waste (RAW) management, an integrated system starting with collection and sorting of RAW through its storage, treatment, conditioning, handling and transport up to its disposal. Some notes will touch also the near surface depository of low level and intermediate level radioactive waste in Mochovce, and the long-term storage of waste improper for such type of disposal, and also some words will be addressed to the development and research of a deep geological depository for disposal spent fuel from nuclear power plant and long-lived radioactive waste. (author)

  18. Intermediate storage of radioactive waste and spent nuclear fuel at the Kola Peninsula

    International Nuclear Information System (INIS)

    Bohmer, N.

    1999-01-01

    The problem of nuclear waste and disused nuclear submarines are a product of the arms race and the Cold War. Russia still continues to build new nuclear submarines, but there are very few provisions being made to properly store old nuclear submarines, and develop sufficient storage facilities for spent nuclear fuel and other radioactive waste. A solution to this problem is proposed: to construct a new regional interim storage facilities at Kola for the spent nuclear fuel instead of transporting it to Mayak, the existing reprocessing plant. This storage should have the capacity to handle the fuel in the existing storage and the fuel still on board of retired nuclear submarines. Its lifetime should be 50 years. later it would be possible to make a decision on the future of this fuel

  19. Can lignocellulosic hydrocarbon liquids rival lignocellulose-derived ethanol as a future transport fuel?

    Directory of Open Access Journals (Sweden)

    Yao Ding

    2012-11-01

    Full Text Available Although transport fuels are currently obtained mainly from petroleum, alternative fuels derived from lignocellulosic biomass (LB have drawn much attention in recent years in light of the limited reserves of crude oil and the associated environmental issues. Lignocellulosic ethanol (LE and lignocellulosic hydrocarbons (LH are two typical representatives of the LB-derived transport fuels. This editorial systematically compares LE and LB from production to their application in transport fuels. It can be demonstrated that LH has many advantages over LE relative to such uses. However, most recent studies on the production of the LB-derived transport fuels have focused on LE production. Hence, it is strongly recommended that more research should be aimed at developing an efficient and economically viable process for industrial LH production.

  20. Regeneration and localization of radioactive waste in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Egorov, N.N.; Kudryavtsev, E.G.; Nikipelov, B.V.; Polyakov, A.S.; Zakharkin, B.S.; Mamaev, L.A.

    1993-01-01

    Normal functioning of the nuclear-power industry is only possible with a closed fuel cycle, including regeneration of the spent fuel from atomic power plants, the production and recycling of the secondary fuel, and localization of the radioactive waste. Despite the diversity of contemporary attitudes toward the structure of the nuclear fuel cycle around the world, the closure of the fuel cycle has been fundamental to the atomic-power industry in the USSR since the very beginning, and has taken on even greater significance in Russia today. From the beginning, the idea of a closed fuel cycle has been based essentially on one fundamental criterion: the concept of expanded productivity on the basis of fuel regeneration, i.e., the economic factor. Important as economic factors are, safety issues have taken on great significance in recent years: not only power-station reactors but all the ancillary stages of the fuel cycle must meet fundamentally new reliability, safety, and environmental hazards. The RT-1 plant is a versatile operation, regenerating spent fuel from VVER-440, BN-350, and BN-600 reactors, nuclear icebreakers and submarines, research reactors, and other power units. The plant can reprocess 400 ton/year of basic VVER-440 fuel. World-class modern processes have been introduced at the plant, meeting the necessary quality standards: zonal planning, remote operation to eliminate direct contact of the staff with radioactive material, extensive monitoring and control systems, multistage gas-purification systems, and new waste-treatment methods

  1. A summary of the program and progress to 1984 December of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.

    1986-08-01

    The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fifth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1984 are described in this report. 74 refs

  2. Implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Stewart, L.; Tonkay, D.

    2004-01-01

    This paper discusses the implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The Joint Convention: establishes a commitment with respect to safe management of spent nuclear fuel and radioactive waste; requires the Parties to ''take appropriate steps'' to ensure the safety of their spent fuel and waste management activities, but does not delineate standards the Parties must meet; and seeks to attain, through its Contracting Parties, a higher level of safety with respect to management of their spent nuclear fuel, disused sealed sources, and radioactive waste

  3. Management and disposal of used nuclear fuel and reprocessing wastes

    International Nuclear Information System (INIS)

    1983-01-01

    The subject is dealt with in chapters, entitled: introduction (general statement of problem); policy framework (criteria for waste management policy); waste management and disposal, as practised and planned (general; initial storage; reprocessing and conditioning of reprocessing wastes; intermediate storage; transportation; packaging; disposal); international co-operation. Details of the situation in each country concerned (Australia, Belgium, Canada, France, Federal Republic of Germany, Spain, Sweden, Switzerland and United Kingdom) are included as annexes. (U.K.)

  4. Fuel cycle and waste newsletter, Vol. 5, No. 2, August 2009

    International Nuclear Information System (INIS)

    2009-08-01

    The articles in this issue of the newsletter of the Division of Nuclear Fuel Cycle and Waste Technology cover information about the IAEA International Conference on Remediation of Land Contaminated by Radioactive Material Residues which took place in Astana, Kazakhstan. The main focus was on legacy sites from uranium mining and milling activities. The Waste Technology Section of the Department of Nuclear Energy reports on its three major areas: the development and implementation of mechanisms for better waste technology transfer and information exchange; the promotion of sustainable and safer processes and procedures for managing the radioactive waste; and the provision of peer reviews and direct technical assistance related to waste management, decommissioning and environmental remediation. Further information is provided on the International Symposium on Uranium Raw Material for the Nuclear Fuel Cycle, URAM 2009, which was hosted by the IAEA; on the spent fuel management activities in the Nuclear Fuel Cycle and Materials Section; on advanced nuclear fuel cycles; on recent IAEA activities in the area of radiation materials science; on the discussion of the Contact Expert Group (CEG) on the operation of Mayak at the occasion of the CEG workshop on Management of Spent Nuclear Fuel and Radioactive Waste: Regulatory and Licensing Issues which took place in St. Petersburg, Russian federation; on the Research Reactor Group fellowship training; on a new technology for the conditioning of disused high activity radioactive sources in a mobile hot cell; on the Beijing International Ministerial Conference on Nuclear Energy in the 21th Century; on the development of a national RWM (Radioactive Waste Management) policy and infrastructure as a condition for implementing a nuclear energy programme; on IAEA data resources and the Joint Convention on the Safety of Spent Fuel and Radioactive waste Management; on the IAEA Coordinated Research Project (CRP) on the behaviours of

  5. Non-fuel cycle radioactive waste policy in Turkey

    International Nuclear Information System (INIS)

    Demirel, H.

    2003-01-01

    Radioactive wastes generated in Turkey are mostly low level radioactive waste generated from the operation of one research reactor, research centers and universities, hospitals, and from radiological application of various industries. Disused sealed sources which potentially represent medium and high radiological risks in Turkey are mainly Am-241, Ra-226, Kr-85, Co-60, Ir-192 and Cs-137. All radioactive waste produced in Turkey is collected, segregated, conditioned and stored at CWPSF. Main components of the facility are listed below: Liquid waste is treated in chemical processing unit where precipitation is applied. Compactable solids are compressed in a compaction cell. Spent sources are embedded into cement mortar with their original shielding. If the source activities are in several millicuries, sometimes dismantling is applied and segregated sources are conditioned in shielded drums. Due to increasing number of radiation and nuclear related activities, the waste facility of CNAEM is now becoming insufficient to meet the storage demand of the country. TAEA is now in a position to establish a new radioactive waste management facility and studies are now being carried out on the selection of best place for the final storage of processed radioactive wastes. Research and development studies in TAEA should continue in radioactive waste management with the aim of improving data, models, and concepts related to long-term safety of disposal of long-lived waste

  6. Session 1984-1985. Radioactive waste. Minutes of evidence, Monday 13 May 1985. British Nuclear Fuels plc

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    The Environment Select Committee of the House of Commons received a memorandum from British Nuclear Fuels plc on the treatment and preparation for disposal of radioactive wastes, under the headings: introduction; waste categories; waste management policy; waste arisings; waste treatment plans; appendix I - British Nuclear Fuels plc; appendix II - the nuclear fuel cycle for Magnox, AGR and LWR reactors; appendix III - control of liquid radioactive discharges from Sellafield and their environmental impact. Representatives of BNF plc were examined on the subject of the memorandum and the minutes of evidence are recorded.

  7. Session 1984-85. Radioactive waste. Minutes of evidence, Monday 13 May 1985. British Nuclear Fuels plc

    International Nuclear Information System (INIS)

    1985-01-01

    The Environment Select Committee of the House of Commons received a memorandum from British Nuclear Fuels plc on the treatment and preparation for disposal of radioactive wastes, under the headings: introduction; waste categories; waste management policy; waste arisings; waste treatment plans; appendix I - British Nuclear Fuels plc; appendix II - the nuclear fuel cycle for Magnox, AGR and LWR reactors; appendix III - control of liquid radioactive discharges from Sellafield and their environmental impact. Representatives of BNF plc were examined on the subject of the memorandum and the minutes of evidence are recorded. (U.K.)

  8. Risk analysis methodology for spent fuel repositories in bedded salt: methodlogy summary and differences between spent fuel and high level wastes

    International Nuclear Information System (INIS)

    Pepping, R.E.; Chu, M.S.

    1981-06-01

    In the absence of spent fuel reprocessing plans, unreprocessed spent fuel has become a candidate waste form for geologic disposal. In order to understand the public health risks from such disposal and to gain insights into the factors that influence them, a methodology is needed to combine the effects of site geology and hydrology, physical and chemical properties of the waste form, and the details of the engineering design. This report outlines such a methodology which the authors currently are applying to the analysis of unreprocessed spent fuel disposal. The methodology is the same methodology as was developed to describe the risks from geologic disposal of wastes from reprocessed spent fuel. The difference between spent fuel wastes and wastes from reprocessing that may affect the applicability of the methodology are highlighted

  9. Waste management system alternatives for treatment of wastes from spent fuel reprocessing

    International Nuclear Information System (INIS)

    McKee, R.W.; Swanson, J.L.; Daling, P.M.

    1986-09-01

    This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases

  10. Utilization of waste cooking oil as an alternative fuel for Turkey.

    Science.gov (United States)

    Arslan, Ridvan; Ulusoy, Yahya

    2017-04-03

    This study is based on three essential considerations concerning biodiesel obtained from waste cooking oil: diesel engine emissions of biodiesel produced from waste cooking oil, its potential in Turkey, and policies of the Turkish government about environmentally friendly alternative fuels. Emission tests have been realized with 35.8 kW, four-cylinder, four-stroke, direct injection diesel tractor engine. Test results are compared with Euro non-road emission standards for diesel fuel and five different blends of biodiesel production from waste cooking oil. The results of the experimental study show that the best blends are B10 and B20 as they show the lowest emission level. The other dimensions of the study include potential analysis of waste cooking oil as diesel fuels, referring to fuel price policies applied in the past, and proposed future policies about the same issues. It was also outlined some conclusions and recommendations in connection with recycling of waste oils as alternative fuels.

  11. Fuel-related Emissions from the Croatian Municipal Solid Waste Collection System in 2013: Mixed Municipal Waste

    Directory of Open Access Journals (Sweden)

    Anamarija Grbeš

    2018-01-01

    Full Text Available Waste removal (collection and landfilling in the Republic of Croatia is the responsibility of the municipalities and local governments in 21 administrative units (counties. They entrust the respective economic activity to 208 private and public companies specialized in waste collection and treatment. Organised waste collection affects 99 % of the population. The mixed waste from households and enterprises is at various frequencies collected at the door (kerbside collection and transported by truck to a landfill, or processing plant. This article aims to estimate fuel consumption and fuel-related airborne emissions from the collection of mixed municipal waste in Croatia in 2013. The input data and emission results are shown for Croatia and each Croatian county, in total, and relative to the number of inhabitants and mass of collected waste. Annual consumption of diesel for the collection of mixed waste is estimated at 10.6 million litres. At the county level, fuel consumption ranges from 87 thousand litres to 2.2 million litres, on average 504 thousand litres per county. Total emission of CO2 is estimated at 28 000 t, which at county level ranges from 231 to 5711 t. Relative emission ranges from 3.3 to 13 kg CO2 per capita (average 6.6 kg per capita, or 8.6–28.1 kg t−1 of municipal waste (average 17 kg CO2 per ton of municipal waste. The average values of CO2 emission from MSW collection that should also be the target values are 7–9 kg for mixed waste, and 8–15 kg CO2 for separate waste streams. Apart from CO2 emission, this research estimates emission of other, diesel combustion related compounds, such as NOx, CO, lubricant related CO2, NMVOC, PM, f-BC, N2O, SO2, NH3, Pb, ID[1,2,3-cd]P, B[k]F, B[b]F, B[a]P, as well as total distance of transport.

  12. Category 2 and 4 investigation-derived waste readiness evaluation plan

    International Nuclear Information System (INIS)

    Ludowise, J.D.

    1996-08-01

    This Readiness Evaluation Plan presents the methodology used to assess the readiness for loading investigation-derived waste drums on trucks for transport to the Environmental Restoration Disposal Facility. The scope of this plan includes an assessment of the organizations, procedures, and regulatory approvals necessary for the handling of investigation-derived waste containers and the subsequent transportation of materials to the Environmental Restoration Disposal Facility

  13. Handling of spent nuclear fuel and final storage of nitrified high level reprocessing waste

    International Nuclear Information System (INIS)

    The following stages of handling and transport of the fuel on its way to final storage are dealt with in the report. 1) The spent nuclear fuel is stored at the power station or in the central fuel storage facility awaiting reprocessing. 2) The fuel is reprocessed, i.e. uranium, plutonium and waste are separated from each other. Reprocessing does not take place in Sweden. The highlevel waste is vitrified and can be sent back to Sweden in the 1990s. 3) Vitrified waste is stored for about 30 years awaiting deposition in the final repository. 4) The waste is encapsulated in highly durable materials to prevent groundwater from coming into contact with the waste glass while the radioactivity of the waste is still high. 5) The canisters are emplaced in a final repository which is built at a depth of 500 m in rock of low permeability. 6) All tunnels and shafts are filled with a mixture of clay and sand of low permeability. A detailed analysis of possible harmful effects resulting from normal acitivties and from conceivable accidents is presented in a special section. (author)

  14. The nuclear fuel cycle, From the uranium mine to waste disposal

    International Nuclear Information System (INIS)

    2002-09-01

    Fuel is a material that can be burnt to provide heat. The most familiar fuels are wood, coal, natural gas and oil. By analogy, the uranium used in nuclear power plants is called 'nuclear fuel', because it gives off heat too, although, in this case, the heat is obtained through fission and not combustion. After being used in the reactor, spent nuclear fuel can be reprocessed to extract recyclable energy material, which is why we speak of the nuclear fuel cycle. This cycle includes all the following industrial operations: - uranium mining, - fuel fabrication, - use in the reactor, - reprocessing the fuel unloaded from the reactor, - waste treatment and disposal. 'The nuclear fuel cycle includes an array of industrial operations, from uranium mining to the disposal of radioactive waste'. Per unit or mass (e.g. per kilo), nuclear fuel supplies far more energy than a fossil fuel (coal or oil). When used in a pressurised water reactor, a kilo of uranium generates 10,000 times more energy than a kilo of coal or oil in a conventional power station. Also, the fuel will remain in the reactor for a long time (several years), unlike conventional fuels, which are burnt up quickly. Nuclear fuel also differs from others in that uranium has to undergo many processes between the time it is mined and the time it goes into the reactor. For the sake of simplicity, the following pages will only look at nuclear fuel used in pressurised water reactors (or PWRs), because nuclear power plants consisting of one or more PWRs are the most widely used around the world. (authors)

  15. Methods for conversion of lignocellulosic-derived products to transportation fuel precursors

    Science.gov (United States)

    Lilga, Michael A.; Padmaperuma, Asanga B.

    2017-10-03

    Methods are disclosed for converting a biomass-derived product containing levulinic acid and/or gamma-valerolactone to a transportation fuel precursor product containing diesel like hydrocarbons. These methods are expected to produce fuel products at a reduced cost relative to conventional approaches.

  16. EVALUATION OF TIRE-DERIVED FUEL FOR USE IN NITROGEN OXIDE REDUCTION BY REBURNING

    Science.gov (United States)

    Tire-derived fuel (TDF) was tested in a small-scale (44 kW or 150,000 Btu/hr) combustor to determine its feasibility as a fuel for use in reburning for control of nitrogen oxide (NO). TDF was gravity-fed into upward flowing combustion gases from a primary natural gas flame doped ...

  17. Solid recovered fuels in the cement industry with special respect to hazardous waste.

    Science.gov (United States)

    Thomanetz, Erwin

    2012-04-01

    Cements with good technical properties have been produced in Europe since the nineteenth century and are now worldwide standardized high-quality mass products with enormous production numbers. The basic component for cement is the so-called clinker which is produced mainly from raw meal (limestone plus clay plus sands) in a rotary kiln with preheater and progressively with integrated calciner, at temperatures up to 1450 °C. This process requires large amounts of fossil fuels and is CO₂-intensive. But most CO₂ is released by lime decomposition during the burning process. In the 1980s the use of alternative fuels began--firstly in the form of used oil and waste tyres and then increasingly by pre-conditioned materials from commercial waste and from high calorific industrial waste (i.e. solid recovered fuel (SRF))--as well as organic hazardous waste materials such as solvents, pre-conditioned with sawdust. Therefore the cement industry is more and more a competitor in the waste-to-energy market--be it for municipal waste or for hazardous waste, especially concerning waste incineration, but also for other co-incineration plants. There are still no binding EU rules identifying which types of SRF or hazardous waste could be incinerated in cement kilns, but there are some well-made country-specific 'positive lists', for example in Switzerland and Austria. Thus, for proper planning in the cement industry as well as in the waste management field, waste disposal routes should be considered properly, in order to avoid surplus capacities on one side and shortage on the other.

  18. Shale-oil-derived additives for fuel oils

    International Nuclear Information System (INIS)

    Raidma, E.; Leetsman, L.; Muoni, R.; Soone, Y.; Zhiryakov, Y.

    2002-01-01

    Studies have shown that the oxidation, wearing, and anticorrosive properties of shale oil as an additive to liquid fuels and oils enable to improve the conditions of their use. Studies conducted by Institute of Oil Shale have shown that it is possible, on the basis of shale oil produced by Viru Keemia Grupp AS (Viru Chemistry Group Ltd.) and, particularly, on the basis of its fractions 230-320 and 320-360 deg C to produce efficient and stable additives for liquid fuels to improve their combustion and storage properties. In the production of additives from shale oil the prerequisite taken into account is its complexity of composition and high concentration of neutral and phenolic oxygen compounds. Additives produced from shale oil have multifunctional properties which enable to improve operational data of liquid fuels and to increase the power of diesel engines and boilers. (author)

  19. Summary of national and international fuel cycle and radioactive waste management programs, 1984

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

    1984-07-01

    Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories.

  20. Summary of national and international fuel cycle and radioactive waste management programs, 1984

    International Nuclear Information System (INIS)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

    1984-07-01

    Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories

  1. Minimization of actinide waste by multi-recycling of thoriated fuels in the EPR reactor

    Directory of Open Access Journals (Sweden)

    Nuttin A.

    2012-02-01

    Full Text Available The multi-recycling of innovative uranium/thorium oxide fuels for use in the European Pressurized water Reactor (EPR has been investigated. If increasing quantities of 238U, the fertile isotope in standard UO2 fuel, are replaced by 232Th, then a greater yield of new fissile material (233U is produced during the cycle than would otherwise be the case. This leads to economies of natural uranium of around 45% if the uranium in the spent fuel is multi-recycled. In addition we show that minor actinide and plutonium waste inventories are reduced and hence waste radio-toxicities and decay heats are up to a factor of 20 lower after 103 years. Two innovative fuel types named S90 and S20, ThO2 mixed with 90% and 20% enriched UO2 respectively, are compared as an alternative to standard uranium oxide (UOX and uranium/plutonium mixed oxide (MOX fuels at the longest EPR fuel discharge burn-ups of 65 GWd/t. Fissile and waste inventories are examined, waste radio-toxicities and decay heats are extracted and safety feedback coefficients are calculated.

  2. Analysis of economic impacts on waste management and disposal in different nuclear fuel cycles

    International Nuclear Information System (INIS)

    1979-09-01

    The costs for waste management and disposal have been estimated for the comparison of the seven reference fuel cycles selected by INFCE working group 7, covering the waste management of all steps in each fuel cycle: mining and milling, conversion and enrichment, fuel fabrication, reactor operation, reprocessing or spent fuel packaging, and disposal in a geologic formation (salt or hard rock). Values for a large variety of parameters had to be assumed. The cost figures as broken down in detail in the report have been calculated for an electricity production of 50 Gigawatt-years per year. The sum totals amount to about 8 to 17 million US (as of January 1, 1978) per Gigawattyear electricity produced, depending on the fuel cycle and on the geologic host formation of the repository. No savings should be obtained for a larger capacity, but a capacity of 10 Gigawatt would entail figures 10 to 25% higher. This result has to be seen under the perspective of the sometimes conservative and arbitrary assumptions of WG 7 with respect to waste arisings and their disposal. Furthermore, as compared to the revenues for the electricity sold, the relative difference between the reference fuel cycles in costs of waste management and disposal does not appear to be significant, as they range only from 1 to 2% of the total electricity costs

  3. Management of legacy spent nuclear fuel wastes at the Chalk River Laboratories: operating experience and progress towards waste remediation

    International Nuclear Information System (INIS)

    Cox, D.S.; Bainbridge, I.B.; Greenfield, K.R.

    2006-01-01

    AECL has been managing and storing a diversity of spent nuclear fuel, arising from operations at its Chalk River Laboratories (CRL) site over more than 50 years. A subset of about 22 tonnes of research reactor fuels, primarily metallic uranium, have been identified as a high priority for remediation, based on monitoring and inspection that has determined that these fuels and their storage containers are corroding. This paper describes the Fuel Packaging and Storage (FPS) project, which AECL has launched to retrieve these fuels from current storage, and to emplace them in a new above-ground dry storage system, as a prerequisite step to decommissioning some of the early-design waste storage structures at CRL. The retrieved fuels will be packaged in a new storage container, and subjected to a cold vacuum drying process that will remove moisture, and thereby reduce the extent of future corrosion and degradation. The FPS project will enable improved interim storage to be implemented for legacy fuels at CRL, until a decision is made on the ultimate disposition of legacy fuels in Canada. (author)

  4. Relative radiological risks derived from different TENORM wastes in Malaysia.

    Science.gov (United States)

    Ismail, B; Teng, I L; Muhammad Samudi, Y

    2011-11-01

    In Malaysia technologically enhanced naturally occurring radioactive materials (TENORM) wastes are mainly the product of the oil and gas industry and mineral processing. Among these TENORM wastes are tin tailing, tin slag, gypsum and oil sludge. Mineral processing and oil and gas industries produce large volume of TENORM wastes that has become a radiological concern to the authorities. A study was carried out to assess the radiological risk related to workers working at these disposal sites and landfills as well as to the members of the public should these areas be developed for future land use. Radiological risk was assessed based on the magnitude of radiation hazard, effective dose rates and excess cancer risks. Effective dose rates and excess cancer risks were estimated using RESRAD 6.4 computer code. All data on the activity concentrations of NORM in wastes and sludges used in this study were obtained from the Atomic Energy Licensing Board, Malaysia, and they were collected over a period of between 5 and 10 y. Results obtained showed that there was a wide range in the total activity concentrations (TAC) of nuclides in the TENORM wastes. With the exception of tin slag and tin tailing-based TENORM wastes, all other TENORM wastes have TAC values comparable to that of Malaysia's soil. Occupational Effective Dose Rates estimated in all landfill areas were lower than the 20 mSv y(-1) permissible dose limit. The average Excess Cancer Risk Coefficient was estimated to be 2.77×10(-3) risk per mSv. The effective dose rates for residents living on gypsum and oil sludge-based TENORM wastes landfills were estimated to be lower than the permissible dose limit for members of the public, and was also comparable to that of the average Malaysia's ordinary soils. The average excess cancer risk coefficient was estimated to be 3.19×10(-3) risk per mSv. Results obtained suggest that gypsum and oil sludge-based TENORM wastes should be exempted from any radiological regulatory

  5. Steam generators lay-up optimization and derived wastes reduction

    International Nuclear Information System (INIS)

    Rabeau, A.M.; Viricel, L.; Foct, F.; Lemaire, P.; Moreaux, D.

    2002-01-01

    Today, EDF plants face a new release permit after a steam generators (SGs) wet lay-up, so that the legal authorizations for wastes release to the environment, renewed or being renewed by the safety authorities, allow smallest quantities of wastes than earlier. In this context, EDF studies the optimization of SGs lay-up conditions, and especially of the hydrazine concentration, in order to reduce the liquid wastes releases to the environment, while keeping low corrosion conditions. At the same time, EDF examines a treatment for hydrazine elimination in liquid wastes before their releases. An experimental study has been conducted in order to evaluate the efficiency of hydrazine to control materials corrosion and of nitrogen gas phase to deaerate water. The consequences of lay-up conditions on carbon steel corrosion has also been studied. In the absence of an efficient alternative reagent, hydrazine remains necessary but implies a great care due to its carcinogenic risks and to its toxicity for aquatic organisms. This choice implies studying a method for hydrazine elimination before its release to the environment. The hydrazine elimination from SGs lay-up wastes could be achieved within about one day, by adding about 700 to 800 liters of 30% hydrogen peroxide solution to eliminate 100 kg hydrazine. Copper sulfate would have to be added if copper is not present in the wastes; the copper content in the wastes should be around 100 to 200 μg/kg for the reaction to be fast enough, which is consistent with the legal authorization for copper release to the environment. The nuclear power plants would have to adjust the quantity of hydrogen peroxide to add to the wastes to be treated, based on the quantity of hydrazine to eliminate, in order to avoid any excess of hydrogen peroxide in the wastes at the end of the treatment, since this species is not allowed to be released to the environment. Moreover, the hydrogen peroxide treatment should not have any significant impact on

  6. Relative radiological risks derived from different TENORM wastes in Malaysia

    International Nuclear Information System (INIS)

    Ismail, B.; Teng, I. L.; Muhammad samudi, Y.

    2011-01-01

    In Malaysia technologically enhanced naturally occurring radioactive materials (TENORM) wastes are mainly the product of the oil and gas industry and mineral processing. Among these TENORM wastes are tin tailing, tin slag, gypsum and oil sludge. Mineral processing and oil and gas industries produce large volume of TENORM wastes that has become a radiological concern to the authorities. A study was carried out to assess the radiological risk related to workers working at these disposal sites and landfills as well as to the members of the public should these areas be developed for future land use. Radiological risk was assessed based on the magnitude of radiation hazard, effective dose rates and excess cancer risks. Effective dose rates and excess cancer risks were estimated using RESRAD 6.4 computer code. All data on the activity concentrations of NORM in wastes and sludges used in this study were obtained from the Atomic Energy Licensing Board (Malaysia), and they were collected over a period of between 5 and 10 y. Results obtained showed that there was a wide range in the total activity concentrations (TAC) of nuclides in the TENORM wastes. With the exception of tin slag and tin tailing-based TENORM wastes, all other TENORM wastes have TAC values comparable to that of Malaysia's soil. Occupational Effective Dose Rates estimated in all landfill areas were lower than the 20 mSv y -1 permissible dose limit. The average Excess Cancer Risk Coefficient was estimated to be 2.77 x 10 -3 risk per mSv. The effective dose rates for residents living on gypsum and oil sludge-based TENORM wastes landfills were estimated to be lower than the permissible dose limit for members of the public, and was also comparable to that of the average Malaysia's ordinary soils. The average excess cancer risk coefficient was estimated to be 3.19 x 10 -3 risk per mSv. Results obtained suggest that gypsum and oil sludge-based TENORM wastes should be exempted from any radiological regulatory

  7. The situation in Italy of radiactive wastes and spent fuels

    International Nuclear Information System (INIS)

    1986-01-01

    After having done a classification of radioactive wastes, some principles of radioprotection referred to the management and disposal are established according to their nature. Methods and responsabilities for the management of wastes are reported together with a description of the present situation in Italy.Finally studies carried out and under way in this field are described

  8. Integrated data base for 1988: Spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1988-09-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1987. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected defense-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reportd for miscellaneous, highly radioactive materials that may require geologic disposal. 89 refs., 46 figs., 104 tabs

  9. Integrated data base for 1986: spent fuel and radioactive waste inventories, projections, and characteristics. Revision 2

    International Nuclear Information System (INIS)

    1986-09-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US Department of Energy (DOE) radioactive wastes through December 31, 1985, based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. Current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the expected defense-related and private industrial and institutional activities and the latest DOE/Energy Information Administration (EIA) projections of US commercial nuclear power growth. The materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or calculated isotopic compositions

  10. Evaluation of alternative spent fuel waste package concepts for a repository in Basalt

    International Nuclear Information System (INIS)

    Hall, G.V.B.; Nair, B.R.

    1986-01-01

    The United States government has established a program for the disposal of spent nuclear fuel and high-level radioactive waste. The Nuclear Waste Policy Act (NWPA) of 1982 requires the first nuclear waste repository to begin receiving high-level radioactive waste in 1998. One of the potentially acceptable sites currently being evaluated is the Hanford Site in the Pasco Basin in the state of Washington where the host rock is basalt. Under the direction of the United States Department of Energy (DOE), Rockwell International's Rockwell Hanford Operations (RHO) has initiated the Basalt Waste Isolation Project (BWIP). The BWIP must design waste packages for emplacement in the repository. As part of the BWIP waste package development program, several alternative designs were considered for the disposal of spent nuclear fuel. This paper describes the concepts that were evaluated, the criteria that was developed for judging their relative merits, and the methodology that was employed. The results of the evaluation show that a Pipe-In-Tunnel design, which uses a long carbon steel pipe for the containment barrier for multiple packages of consolidated spent fuel, has the highest rating. Other designs which had high ratings are also discussed

  11. Integrated Data Base for 1992: US spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1992-10-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1991. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal

  12. Overview of the US program for developing a waste disposal system for spent nuclear fuel and high-level waste

    International Nuclear Information System (INIS)

    Kay, C.E.

    1988-01-01

    Safe disposal of spent nuclear fuel and radioactive high-level waste (HLW) has been a matter of national concern ever since the first US civilian nuclear reactor began generating electricity in 1957. Based on current projections of commercial generating capacity, by the turn of the century, there will be >40,000 tonne of spent fuel in the Untied States. In addition to commercial spent fuel, defense HLW is generated in the United States and currently stored at three US Department of Energy (DOE) sites: The Nuclear Waste Policy Amendments Act of 1987 provided for financial incentives to host a repository or a monitored retrievable storage (MRS) facility; mandated the areas in which DOE's siting efforts should concentrate (Yucca Mountain, Nevada); required termination of site-specific activities at other sites; required a resisting process for an MRS facility, which DOE had proposed as an integral part of the waste disposal system; terminated all activities for identifying candidates for a second repository; established an 11-member Nuclear Waste Technical Review Board; established a three-member MRS commission to be appointed by heads of the US Senate and House; directed the President to appoint a negotiator to seek a state or Indian tribe willing to host a repository or MRS facility at a suitable site and to negotiate terms and conditions under which the state or tribe would be willing to host such a facility; and amended, adjusted, or established other requirements contained in the 1982 law

  13. Fuel cycle and waste newsletter, Vol. 5, No. 1, April 2009

    International Nuclear Information System (INIS)

    2009-04-01

    The articles in this issue of the newsletter of the Division of Nuclear Fuel Cycle and Waste Technology cover a broad range of activities ranging from support of uranium mining to the disposal of radioactive waste. The lead article discusses the important subject of how to ensure the sustainable management of disused sealed radioactive sources and in particular how to dispose of them. This is a topic that will become important for most Member States. One option is disposal in deep boreholes, a concept that has been developed and evaluated but as yet needs to be implemented in a Member State. Another article concerns a new network that is under preparation, the Environet network on environmental remediation. This follows up on the successful introduction of networks for research for geological disposal, decommissioning and low-level waste disposal. The network concept provides a forum for exchange of information between the countries with experience and for transfer of knowledge to the countries initiating similar work. It is thus a very useful tool to both strengthen capabilities and provide technical cooperation assistance, through hands-on training courses, site visits and fellowships. Further information is provided on the Reactor Conference - RRFM 2009 which was hosted by the IAEA, the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO); on the repackaging of the degraded spent nuclear fuel currently stored in the fuel basins at the RA research reactor at the Vinca Institute of Nuclear Sciences, Belgrade, Serbia; on the international workshop on Disposal of Radioactive Waste at Intermediate Depth which was hosted by the Republic of Korea; on the upsurge in uranium production cycle activity; on national fuel cycle strategies; on experiences and plans of the disposal of radioactive waste and spent nuclear fuel in the Russian Federation (CEG Meeting); on the 2nd annual TWGRR (Technical Working Group on Research Reactors) meeting; on the EC

  14. Re-evaluating neptunium in uranyl phases derived from corroded spent fuel

    International Nuclear Information System (INIS)

    Fortner, J. A.; Finch, R. J.; Kropf, A. J.; Cunnane, J. C.; Chemical Engineering

    2004-01-01

    Interest in mechanisms that may control radioelement release from corroded commercial spent nuclear fuel (CSNF) has been heightened by the selection of the Yucca Mountain site in Nevada as the repository for high-level nuclear waste in the United States. Neptunium is an important radionuclide in repository models owing to its relatively long half-life and its high aqueous mobility as neptunyl [Np(V)O+2]. The possibility of neptunium sequestration into uranyl alteration phases produced by corroding CSNF would suggest-a process for lowering neptunium concentration and subsequent migration from a geologic repository. However, there remains little experimental evidence that uranyl compounds will, in fact, serve as long-term host phases for the retention of neptunium under conditions expected in a deep geologic repository. To directly explore this possibility, we examined specimens of uranyl alteration phases derived from humid-air-corroded CSNF by X-ray absorption spectroscopy to better determine neptunium uptake in these phases. Although neptunium fluorescence was readily observed from as-received CSNF, it was not observed from the uranyl alteration rind. We establish upper limits for neptunium incorporation into CSNF alteration phases that are significantly below previously reported concentrations obtained by using electron energy loss spectroscopy (EELS). We attribute the discrepancy to a plural-scattering event that creates a spurious EELS peak at the neptunium-MV energy

  15. Derivation of residual radionuclide inventory guidelines for implace closure of high-level waste tanks

    International Nuclear Information System (INIS)

    Yuan, L.; Yuan, Y.

    1999-01-01

    Residual radionuclide inventory guidelines were derived for the high-level waste tanks at a vitrification facility. The decommissioning scenario assumed for this derivation was that the tanks were to be stabilized at the present locations and the site is released for unrestricted use following a 100-year institutional control period. It was assumed that loss of institutional control would occur at 100-years following tank closure. The derivation of the residual radionuclide inventory guidelines was based on the requirement that the effective dose equivalent (EDE) to a hypothetical individual who lives in the vicinity of the site should not exceed a dose of 0.15 mSv/yr off-site and 5 mSv/yr on-site following closure of the tanks. The RESRAD computer code, modified for exposure scenarios specific for the site, was used for this evaluation. The results of the derivation indicate that the allowable off-site dose limit will not be exceeded. The estimated potential doses to individuals using water offsite from a creek are negligibly small fractions of the 0.15 mSv/yr allowable dose limit. With an assumed 3% heel remaining in the tanks, the estimated peak dose rate for the future offsite water user is about 0.00025 mSv/yr. The residual radionuclide inventory guidelines derived based on potential doses to the on-site resident farmer indicate that, with the exception of Tc-99 and C-14, a 3% heel remaining in the tanks would not result in doses exceeding the 5 mSv/yr allowable dose limit. For this on-site exposure scenario, the peak dose rates occur at about 2000 years after tank closure. The peak dose rate is calculated to be 25 mSv/yr, with greater than 99% produced by four radionuclides: C-14, Tc-99, Np-237, and Am-241. Ingestion of contaminated vegetation contributes most (90%) of the peak dose. Since the inventories used for the derivation are mostly estimated from fuel depletion calculations. There is a need to determine further the actual inventories of these

  16. Energies and media nr 30. Conditions for the nuclear sector. The fuel cycle and wastes. The usefulness of fuel reprocessing. Wastes

    International Nuclear Information System (INIS)

    2009-10-01

    After some comments on recent events in the nuclear sector in different countries (energy policy and projects in the USA, Europe, China, India, Russia), this issue proposes some explanations on the nuclear fuel cycle and on nuclear wastes: involved processes and products from mining to reprocessing and recycling, usefulness of reprocessing (future opportunities of fast neutron reactors, present usefulness of reprocessing with the recycling of separated fissile materials), impact of reprocessing on the environment in La Hague (gas and liquid releases, release standard definition), and the destiny of wastes

  17. International safeguards relevant to geologic disposal of high-level wastes and spent fuels

    International Nuclear Information System (INIS)

    Pillay, K.K.S.; Picard, R.R.

    1989-01-01

    Spent fuels from once-through fuel cycles placed in underground repositories have the potential to become attractive targets for diversion and/or theft because of their valuable material content and decreasing radioactivity. The first geologic repository in the US, as currently designed, will contain approximately 500 Mt of plutonium, 60,000 Mt of uranium and a host of other fissile and strategically important elements. This paper identifies some of the international safeguards issues relevant to the various proposed scenarios for disposing of the spent fuel. In the context of the US program for geologic disposal of spent fuels, this paper highlights several issues that should be addressed in the near term by US industries, the Department of Energy, and the Nuclear Regulatory Commission before the geologic repositories for spent fuels become a reality. Based on US spent fuel discharges, an example is presented to illustrate the enormity of the problem of verifying spent fuel inventories. The geologic disposal scenario for high-level wastes originating from defense facilities produced a ''practicably irrecoverable'' waste form. Therefore, safeguards issues for geologic disposal of high-level waste now in the US are less pressing. 56 refs. , 2 figs

  18. Perspectives on the closed fuel cycle - Implications for high-level waste matrices

    International Nuclear Information System (INIS)

    Gras, Jean-Marie; Quang, Richard Do; Masson, Herve; Lieven, Thierry; Ferry, Cecile; Poinssot, Christophe; Debes, Michel; Delbecq, Jean-Michel

    2007-01-01

    Nuclear energy accounts for 80% of electricity production in France, generating approximately 1150 t of spent fuel for an electrical output of 420 TWh. Based on a reprocessing-conditioning-recycling strategy, the orientations taken by Electricite de France (EDF) for the mid-term and the far-future are to keep the fleet performances at the highest level, and to maintain the nuclear option fully open by the replacement of present pressurized water reactor (PWR) by new light water reactor (LWR), such as the evolutionary pressurized reactor (EPR) and future Generation IV designs. Adaptations of waste materials to new requirements will come with these orientations in order to meet long-term energy sustainability. In particular, waste materials and spent fuels are expected to meet increased requirements in comparison with the present situation. So the treatment of higher burn-up UO 2 spent fuel and MOX fuel requires determining the performances of glass and other matrices according to several criteria: chemical 'digestibility' (i.e. capacity of glass to incorporate fission products and minor actinides without loss of quality), resistance to alpha self-irradiation, residual power in view of disposal. Considering the long-term evolution of spent MOX fuel in storage, the helium production, the influence of irradiation damages accumulation and the evolution of the microstructure of the fuel pellet need to be known, as well as for the future fuels. Further, the eventual transmutation of minor actinides in fast neutron reactors (FR) of Generation IV, if its interest in optimising high-level waste management is proven, may also raise new challenges about the materials and fuel design. Some major questions in terms of waste materials and spent fuel are discussed in this paper

  19. Experimental Investigation of the Use of Waste Mineral Oils as a Fuel with Organic-Based Mn Additive

    Directory of Open Access Journals (Sweden)

    Bülent Özdalyan

    2018-06-01

    Full Text Available The heat values of waste mineral oils are equal to the heat value of the fuel oil. However, heat value alone is not sufficient for the use of waste minerals oils as fuel. However, the critical physical properties of fuels such as density and viscosity need to be adapted to the system in order to be used. In this study, the engine oils used in the first 10,000 km of the vehicles were used as waste mineral oil. An organic-based Mn additive was synthesized to improve the properties of the waste mineral oil. It was observed that mixing the Mn additive with the waste mineral oil at different doses (4, 8, 12, and 16 ppm improves the viscosity of the waste oil and the flash point. The resulting fuel was evaluated for emission using different loads in a 5 kW capacity generator to compare the fuel with standard diesel fuel and to determine the effect of Mn addition. In the experimental study, it was observed that the emission characteristics of the fuel obtained from waste mineral oil were worse than diesel fuel, but some improvement was observed with Mn addition. As a result, we found that the use of waste mineral oils in engines in fuel standards was not appropriate, but may be improved with additives.

  20. Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    International Nuclear Information System (INIS)

    Harvego, Lisa; Bennett, Brion

    2011-01-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  1. Bioelectricity from students' hostel waste water using microbial fuel cell

    African Journals Online (AJOL)

    Microbial fuel was constructed using two liter plastic transparent chambers representing the cathode and anode poles. The electrodes used were carbon and copper which were utilized in producing a carboncarbon and copper-copper fuel cells respectively. A 1% sodium chloride and 2% agar proton exchange membrane ...

  2. Fuel cycle and waste newsletter. Vol. 3, No. 1, April 2007

    International Nuclear Information System (INIS)

    2007-04-01

    This issue of the Fuel Cycle and Waste Newsletter reports on the international conference on lessons learned from the decommissioning of nuclear facilities and the safe termination of nuclear activities. It discusses the next steps related to the Net-Enabled Waste Management DataBase (NEWMDB) and informs about BOSS (BOrehole disposal of Sealed radioactive Sources), and about predisposal activities in 20067. Furthermore it includes a peer review of the Romanian project for low and intermediate waste disposal - WATRP mission. It stresses the need for research reactor coalitions and centres of excellence and lists a workplan for this initiative, including the complementary Technical Coordination project RER/4/029. The development of inert matrix fuels (IMF) for reducing plutonium stock-piles is discussed, as well as power reactor engineering and spent fuel repackaging preparations at the Vinca institute. Relevant meetings and recent publications are listed

  3. Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms

    Energy Technology Data Exchange (ETDEWEB)

    Weber, William J. [Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering; Zhang, Yanwen [Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering

    2016-09-20

    This is the final report of the NEUP project “Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms.” This project started on July 1, 2012 and was successfully completed on June 30, 2016. This report provides an overview of the main achievements, results and findings through the duration of the project. Additional details can be found in the main body of this report and in the individual Quarterly Reports and associated Deliverables of this project, which have been uploaded in PICS-NE. The objective of this research was to advance understanding and develop validated models on the effects of self-radiation from beta and alpha decay on the response of used nuclear fuel and nuclear waste forms during high-temperature interim storage and long-term permanent disposition. To achieve this objective, model used-fuel materials and model waste form materials were identified, fabricated, and studied.

  4. Relative contributions of natural and waste-derived organics to the subsurface transport of radionuclides

    International Nuclear Information System (INIS)

    Toste, A.P.; Myers, R.B.

    1985-06-01

    Our laboratory is studying the role of organic compounds in the subsurface transport of radionuclides at shallow-land burial sites of low-level nuclear waste, including a commercial site at Maxey Flats, Kentucky, and an aqueous waste disposal site. At the Maxey Flats site, several radionuclides, notably Pu and 60 Co, appear to exist as anionic, organic complexes. Waste-derived organics, particularly chelating agents such as EDTA, HEDTA and associated degradation products (e.g., ED3A), are abundant in aqueous waste leachates and appear to account for the complexation. EDTA, and probably other waste-derived chelating agents as well, are chelated to the Pu and 60 Co in the leachates, potentially mobilizing these radionuclides. In contrast, at the low-level aqueous waste disposal site, naturally-occurring organics, ranging from low molecular weight (MW) acids to high MW humic acids, account for the bulk of the groundwater's organic content. Certain radionuclides, notably 60 Co, 103 Ru and 125 Sb, are mobile as anionic complexes. These radionuclides are clearly associated with higher MW organics, presumably humic and fulvic acids with nominal MW's > 1000. It is clear, therefore, that naturally-occurring organics may play an important role in radionuclide transport, particularly at nuclear waste burial sites containing little in the way of waste-derived organics

  5. Estimation of the Waste Mass from a Pyro-Process of Spent Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Min Soo; Choi, Jong Won; Choi, Heui Joo (and others)

    2008-04-15

    Pyro-Process is now developing to retrieve reusable uranium and TRU, and to reduce the volume of high level waste from a nuclear power plant. In this situation, it is strongly required for the estimation of expected masses and their physical properties of the wastes. In this report, the amount of wastes and their physical properties are presupposed through some assumptions in regard to 10MTHM of Oxide Fuel with 4.5wt% U-235, 45,000 MWD/MTU, and 5yrs cooling. The produced wastes can be divided into three categories such as metal, CWF(Ceramic Waste Form), and VWF(Vitrified Waste Form). The 42 nuclrides in a spent nuclear fuel are distributed into the waste categories on the their physical and thermodynamic properties when they exist in metal, oxide, or chloride forms. The treated atomic groups are Uranium, TRU, Noble metal, Rare earth, Alkali metal, Halogens, and others. The mass of each waste is estimated by the distribution results. The off-gas waste is included into a CWF. The heat generations by the wastes in this Pyro-Process are calculated using a ORIGEN-ARP program. It is possible to estimate the amounts of wastes and their heat generation rates in this Pyro-Process analysis. These information are very helpful to design a waste container and its quantity also can be determined. The number of container and its heat generation rate will be key factor for the construction of interim storage facilities including a underground disposal site.

  6. Economics of National Waste Terminal Storage Spent Fuel Pricing Study

    International Nuclear Information System (INIS)

    1978-05-01

    The methodology for equitably pricing commercial nuclear spent fuel management is developed, and the results of four sample calculations are presented. The spent fuel management program analyzed places encapsulated spent fuel in bedded salt while maintaining long-term retrievability. System design was reasonable but not optimum. When required, privately-owned Away From Reactor (AFR) storage is provided and the spent fuel placed in AFR storage is eventually transported to final storage. Applicable Research and Development and Government Overhead are included. The cost of each component by year was estimated from the most recent applicable data source available. These costs were input to the pricing methodology to establish a one-time charge whose present value exactly recovered the present value of the expenditure flow. The four cases exercised were combinations of a high and a low quantity of spent fuel managed, with a single repository (venture) or a multiple repository (campaign) approach to system financial structure. The price for spent fuel management calculated ranged from 116 to 152 dollars (1978) per kilogram charged initially to the reactor. The effect of spent fuel receiving rate on price is illustrated by the fact that the extremes of price did not coincide with the cases having the extremes of undiscounted cost. These prices for spent fuel management are comparable in magnitude to other fuel cycle costs. The range of variation is small because of compensating effects, i.e., additional costs for high early deliveries (AFR and transportation) versus lower present value of future revenue for later delivery cases. The methodology contains numerous conservative assumptions, provisions for contingencies, and covers the complete set of spent fuel management expenses

  7. Non-fuel cycle radioactive waste policy in Turkey

    International Nuclear Information System (INIS)

    Izmir, A.I.; Uslu, I.

    2001-01-01

    Full text: Introduction. Radioactive wastes generated in Turkey are mostly low level radioactive waste generated from the operation of one research reactor, research centers and universities, hospitals, and from radiological application of various industries. It involves both short-lived and long lived radionuclides. In general, this includes radioactive materials, which are no longer useful and have their origin from practice or intervention both with unsealed and sealed sources. Radioactive Waste Management in Turkey. Utilisation of radioactive materials in Turkey requires special authorisations and falls under legal rules, in particular under the Radiation Safety Regulation of 24th March 2000 (Official Gazette number: 20983) outlining a general regulation for the protection of the population and workers against the danger of ionising radiation and subsequent amendments. There is also a requirement enforced by the Regulations for Radioactive Wastes Exempt from Regulatory Authority Control (published on 15 January 2000, Official Gazette number: 23934) that identifies the limits and other conditions for the discharges of radioactive substances to the environment. Radioactive waste is generally understood as material for which no further use is foreseen, and which has been managed in a system of reporting, authorisation and control as specified in International Atomic Energy Agency (IAEA) recommendations or national legislation. In this paper radioactive waste is considered in two categories: as originated from unsealed sources or from sealed sources. a) Management of Unsealed Sources. Unsealed radionuclides are utilised in human medicine for in vivo diagnosis, metabolic therapy and in vitro biological analysis. The most common types of radionuclides used in Turkey are C-14, Co-57, Cr-51, Fe-59, Ga-67, H-3, I-123, I-125, I-131, In-111, Mo-99, P-32, P-33, Re-186, S-35, Sr-89, Sr-90, Tc-99, Tl-201, Xe-133, Y-90 which are import of radiopharmaceuticals to Turkey in

  8. Coal and wood fuel for electricity production: An environmentally sound solution for waste and demolition wood

    Energy Technology Data Exchange (ETDEWEB)

    Penninks, F.W.M. [EPON, Zwolle (Netherlands)

    1997-12-31

    Waste wood from primary wood processing and demolition presents both a problem and a potential. If disposed in landfills, it consumes large volumes and decays, producing CH{sub 4}, CO{sub 2} and other greenhouse gases. As an energy source used in a coal fired power plant it reduces the consumption of fossil fuels reducing the greenhouse effect significantly. Additional advantages are a reduction of the ash volume and the SO{sub 2} and NO{sub x} emissions. The waste wood requires collection, storage, processing and burning. This paper describes a unique project which is carried out in the Netherlands at EPON`s Gelderland Power Plant (635 MW{sub e}) where 60 000 tonnes of waste and demolition wood will be used annually. Special emphasis is given to the processing of the powdered wood fuel. Therefore, most waste and demolition wood can be converted from an environmental liability to an environmental and economic asset. (author)