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Nuclear Fuels
05 Nuclear fuels (scientific, technical) biomass. Closure of the equations must be performed by modelling the Reynolds stresses for both phases. The results of a simplified version (first step) of the model are presented.
The aqueous geochemistry of neptunium: dynamic control of soluble concentrations with applications to nuclear waste disposal 61101664
Kaszuba, J.P. er al. Environ. Sci. Technol., 1999, 33, (24), 44274433. The valence state of Np, one of the most important radionuclides of concern for long-term emplacement of nuclear waste, primarily defines its geochemical reactions and migration behaviour. The authors evaluate how redox potential and solid-phase stability interact and influence Np solubility and aqueous speciation in natural systems. Np thermodynamical data for the most important valence states for natural waters, +IV and +V, are updated to correct database inconsistencies. The most significant changes are as follows: (1) NpzOs(cr) is two orders of magnitude more stable than reported previously, (2) the stability of NpOzOH (aqueous) is reduced, (3) NpOz(OH)tand mixed Np(V) hydroxo-carbonato species become important at high pH, and (4) Np(OH)s- is disregarded as a valid species. As a result, NpzOs and NP(OH)~ (am) are the stable solids in aquifers of low ionic strength, Np solubility decreases in the pH range IO-12 and increases at pH >12, and both redox potential and Np(OH)d (am) solubility product control soluble Np concentrations at neutral pH and Eh between -0.2 and 0.3. These relations are important for effective nuclear waste package design, such as including cement as an engineered barrier and evaluating impacts of discharged solutions on natural waters in release scenarios at nuclear waste storage facilities.
Thermal conversion of plastics waste in secondary petroleum-derived bitumens
and that of activated carbon is about 400 mg/g. Both residual carbon and activated carbon follow Freundlich Thermal Adsorptive Model, with physical adsorption. The primary difference between residual carbon and activated carbon is the smaller adsorptive amount of residual carbon. But, in adsorbing reactive dyes from effluent, residual carbon removes dyes more effectively than activated carbon.
01101666 Treatment of fossil fuel combustion gases Morimoto, T. Jpn. Kokai Tokkyo Koho JP 11 319,477 [99 319,477] (Cl. BOlD53/50), 24 Nov 1999, Appl. 1998/130,152, 13 May 1998. 6. (In Japanese) The title process comprises mixing fossil fuel combustion gases with aqueous NasCOs at the downstream of the combustion apparatus. The process is useful for neutralization of SO, contained in the combustion gases.
01/01669
Utilization of ash from industrial boilers
Eur. Comm., [Rep.] EUR, 1999, l-115. The overall aim of the project on utilization of ash from industrial boilers (pulverized coal-fired combustors and circulating fluidized bed combustors) were to determine the characteristics of the residues from selected boilers, to assess their variability with boiler operation, and to identify potential common outlets for these residues. The leaching characteristics of both ashes were assessed in a laboratory shake leaching test. The specific utilization options currently being pursued are for Portland cement, concrete, precast concrete masonry units, pozzolanic pulverized fuel ash cement, masonry units structural concrete, and air bricks and gratings for wall ventilation.
01101665
Polaczek, J. et al. P&n. Adr. Technol., 1999, 10, (IO), 567-569. Three petroleum-derived secondary bitumens were used as a medium for thermolysis of poly(ethylene terephthalate), poly(viny1 chloride), polyethylene and a typical waste plastics mixture (mainly polyolefins). The conversion carried out at 30&35o”C resulted in the formation of homogeneous brittle resin-like masses (ring-and-ball softening point above 120°C) intended for practical use.
Thermogravimetric FTIR spectroscopy of hydrocarbon fuel residues
01101666
Zanier, A. J. Therm. Anal. Calorim., 1999, 56, (3), 1389-1396. Although thermogravimetric analysis (TG) has become an indispensable tool for the analysis and characterization of materials, its scope is limited as no information is obtained about the qualitative aspects of the evolved gases during the thermal decomposition. For processes involving mass loss, a powerful technique to provide this missing information is Fourier transform IR spectroscopy (FTIR) in combination with TG. It supplies a comprehensive understanding of thermal events in a reliable and meaningful way as data are obtained from a single sample under the same conditions. The coupling TG/FTIR is used in fuel analysis for the identification of residual volatiles, to determine their sequence of release and to resolve thermogravimetric curves. In this work, the usefulness of TG/FTIR for characterizing middle distillate fuel residues is illustrated with some typical examples of recent application. A Bio-Rad FTS 25 FTIR spectrometer coupled with a TA Instruments TGA 2950 thermogravimetric analyser was used for data acquisition. The results obtained demonstrate the utility of this combined technique in determining the decomposition pathway of tarry materials at various stages of pyrolysis, thereby allowing new insights into the complex thermal behaviour of hydrocarbon residual systems.
Treatment of dyeing effluent by residual carbon from oil-fired fly ash
01101670 Waste still recovery process using sodium tripolyphosphate Partington, B. Verity, D.B. Brit. UK Pat. Appl. GB 2,334,034 (Cl. ClOM175/00), 11 Aug 1999, GB Appl. 1998/2,563, 6 Feb 1998. 17. A process for removal of metals from spent oil involves (1) dissolving an inorganic metal-binding agent in water to form an aqueous solution, (2) mixing the solution with metal-containing spent oil, (3) removing metals from the spent oil in the form of metal compounds formed from the metals and the metal-binding agent, (4) separating the mixture into an oil phase and an aqueous phase, (5) separating the oil phase from the aqueous phase and metal compounds to produce a processed oil with a significantly lower metal content, and optionally (6) separating the metal compounds from the aqueous phase. Preferably, the inorganic metal-binding agent is a tripolyphosphate compound (e.g. Na tripolyphosphate). Optionally, electrolytes (e.g. NaNOs or compound alkoxylate compounds can be added for an improved separation of the oil and aqueous phases. Nonmetal contaminants may be removed with addition of an ethoxylated C6-12 fatty amine of the cocoamine family. The recovered oil can be recycled to production of lubricating oils, transformer oils, and hydraulic fluids or used as a fuel oil.
05
NUCLEAR Scientific,
FUELS
technical
01101667
Tsai, MS. ef al. Kuangye (Taipei), 1999, 43, (2), 49-56. (In Chinese) Oil-fired fly ash is collected from dust collector in industry boilers. The waste dust is composed of carbon from unburnt heavy-oil, oxide and water soluble sulphate. Based on the heavy-oil consumption, it is estimated that the annual production of oil-fired by ash is about 60000 tons in Taiwan. Because there is 12% valuable metals such as vanadium and nickel in the oil-fired fly ash, these valuable metals are recovered by leaching methods. The main component, 40-80% carbon, in oil-fired fly ash is not recycled; it comes out as a large amount of residue called ‘residual carbon’. The object of this research works is to recycle this residual carbon, especially for the practical use in adsorption. The result of basic physicochemical analyses and adsorptive experiment shows that the carbon content of residual carbon is above 80%, the residual carbon has the adsorptive ability as activated carbon. The following are some comparable properties between residual carbon and activated carbon: the residual carbon has much more macropores, the specific area of residual carbon is 23-33 m3/g which is 1135 that of activated carbon, the iodine value of residual carbon is 137-195 mg/g which is l/6-1/4 that of activated carbons. Besides, the adsorptive amount of residual-carbon is 58-39 mg/g in the adsorptive experiments, 202
Fuel and Energy Abstracts
May 2001
01/01671 A concept of the multipurpose liquid metallicfueled fast reactor system (MPFR) Endo, H. ef al. Progress in Nuclear Energy, 2000, 37, (l-4), 291-298. Against fossil fuels, the nuclear energy is the only alternative energy source in the next century. Such energy source as the future nuclear power plant is expected to meet the following requirements. First, high temperature output for the multiple energy conversion capability as the electricity generation and the production of alternative fuels (hydrogen), which can be used widely in transportation systems. Second, the capability for siting close to the energy consumption are a without onsite refuelling. Third, the capability for nuclear fuel breeding and incineration of long-live fission products, and fourth, the harmonization between active and passive safety features. This paper describes the basic concept of the Multipurpose liquid metallic-fuelled Fast Reactor system (MPFR), which satisfies all mentioned requirements with introducing the U-Pu-x (x: Mn, Fe, Co) liquid metallic alloys for the fuel. We can obtain such characteristics as high operational temperature of the reactor (between 550°C and 12OO’C) and elongation of the core operational lifetime by the inherent fission product separation in the liquid fuel by using these alloys. The enhanced self-
05 Nuclear fuels (economics, policy, supplies, forecasts) controllability is achieved by the thermal expansion of liquid fuel; and the re-criticality phenomenon at the core compaction events can be eliminated by discharging of the liquid fuel from the core. 01101672 A conceptual design study on innovative FBR Kasai, S. er al. Progress in Nuclecrr Energy, 2000, 37, (l-4) 131-136. An Actinide Recycle Reactor (ARR) with ductless fuel assemblies and mixed nitride fuel is studied in accordance with an Advanced Fuel Recycle System. The core is designed so that yield more economical efficiencies (high breeding ratio and high burnup), safety aspects (high low void reactivity coefficient and Doppler reactivity coefficient, reactor dynamic characteristics) in comparison with mixed oxide or metal fuel on a suitable condition. Preliminary calculations about key parameters of the core design performances had been done to compare with mixed oxide or metal fuel. Results show that the mixed nitride fuel with a sodium bond and ZrH has promising capacity.
OllOl973 A design study on MOX-fueled small fast reactors for standardiza;ion of a small fast unclear reactor system Uto, N. e( al. Progress in Nuclear Energy, 2000, 37, (l-4), 283-290. A way of development to standardize a small fast nuclear reactor system, which is considered one of the suitable concepts at next generation for satisfying such needs as generality, small dependence on natural resources, safety and non-proliferation, is proposed. This process consists of three steps: the first is to demonstrate the basic system within a short period based on current techniques, the second is to achieve greatly higher economy, and the final is to standardize the commercial system that can economically compete with or overcome current light water reactors. A technical investigation is conducted on the performance of a mixed-oxide (MOX)-fuelled small fast reactor with a reflector-driven reactivity control system to satisfy the needs at the first step, considering plenty of accomplishments on the MOX fuel and its advantage for limiting the duration of development to the level required at the stage. The results obtained from a series of neutronic and thermal-hydraulic calculations show the feasibility of a small fast reactor that produces the electric power of about 50 MW, achieves about two-year consecutive operation with high safety performance and is greatly flexible for updating the system. A mixed-nitride-fuelled core is found to be promising past the first stage.
01101674 Characterization and durability testing of a glassbonded ceramic waste form Johnson, S.G. er al. Ceram. Trans., 1999, 93, 313-320. Argonne National Laboratory is developing a glass-bonded ceramic (zeolite 4A) waste form for encapsulating the fission products and transuranics from the conditioning of metallic reactor fuel:This waste form is currently being scaled to the multikilogram size for encapsulation of actual high level waste. This paper describes characterization and durability testing used to evaluate the product of the waste treatment process. The emphasis is on results from application of glass durability tests such as X-ray diffraction and SEM. The information presented forms the basis for a suite of tests utilized for assessing product quality during scale-up and parametric testing.
Conceptual design of multi-purpose heat reactor ‘nuclear heat generator’
01101675
Uchiyama, Y. ef al. Progress in Nucleur Energy, 2000, 37, (l-4), 277282. Small beat reactors can apply to on site demand such as district heat and air conditioning, industrial process heat, greenhouse, a seawater desalination in urban and rural areas. The purpose of this paper is to design conceptually a multi-purpose reactor named ‘Nuclear Heat Generator (NHG)’ which could be installed in energy consuming area. The reactor of 1 MWt output is designed without any needs for fuel exchange and decommissioning on site. This cassette typed reactor vessel with sealing is transported to specified fuel fabrication shop every 3-4 years in order to exchange used fuels. Steam generators are involved in the self-pressurized integrated reactor with natural circulation. Generated steam pressure from heating reactor is 0.88 MPa (saturated) which is so less than that of current water reactors. Under low steam pressure it is considerably easy to make design of containment vessel and safety device. For economic competition overcoming scale demerit it will be necessary for the cassette type reactor to optimize its system design for the multi-production effect as well as modular construction and recycling system. 01101676 Design study of the demonstration FBR in Japan Inagaki, T. el al. Progress in Nuclear Energy, 2000, 37, (l-4), 119-124. The objective of the plant design study Phase 2, conducted by the Japan Atomic Power Company since 1997 for 3 years, is to accomplish a plant overall concept of the Demonstrative FBR (DFBR) that has economical potential toward commercialization and offers high reliability to plant operators not to cause a long unexpected shutdown resulting from a trouble, i.e. sodium leakage or fires. This has been successfully achieved by establishment of a plant overall design of 672
MWe consisting of the reactor system with drastically simplified internals, the compact and double walled coolant boundaries, the well rationalized fuel handling system, the BOP systems introducing up-todate LWR equipment, and the compact reactor building. The plant construction cost has been estimated based on the quantity of materials to be about 130% on the bases of a 1000 MW LWR, which is well contented with the requirement. The DFBR plant concept, having economical potential toward commercialization, safety and reliability, has been established in the plant design study Phase 2. 01101677 Desirability of small reactors, HTGR in particular Tsuchie, Y. Progress in Nuclear Energy, 2000, 37, (l-4). 253-258. Small reactors of about 100-300 Mwe, High Temperature Gas Cooled Reactors (HTGRs) in particular, are considered desirable in future, based on the following ways of thinking; Global scale enhancement of nuclear energy is considered necessary from reduction of environmental impact point of view. Small reactors are desirable, due to (a) enhanced safety in terms of fuel inventory and inherent safety, then (b) easier plant siting near populated or industrial area, (c) more flexible development, planning and construction than larger reactors by finer adjustment with demand, and (d) economic competitiveness attainable by means of adoption of more rationalized systems categorization, simpler and modularized design, mass production in factory, less work at construction site, and marketability including that of developing countries. In such ways, small reactors can be economically designed, constructed and operated, by conquering ‘scale de-merit’, in contrast with scale merit of larger reactors as seen in current LWRs. Small HTGRs, in particular, are mostly desirable and promising, from view points of wider applications, such as electricity use, wise range of heat uses and/or cogeneration, Pu burning with high efficiency, wider fuel cycle options, using U, Pu and/or Th, with or without reprocessing, and development stages, where not only test reactor programmes for development and demonstration but also realization programmes are already going on towards commercial operation start in 2005-2010. Development programmes on small HTGR, related global activities and cost evaluations by developers and JAPC are shown, and steps towards their global scale commercializations are proposed.
What is the potential use of thorium in the future energy production technology?
OllO1678
Unak, T. Progress in Nuclear Energy, 2000, 37, (l-4), 137-144. Today’s nuclear technology has principally been based on the use of fissile U-235 and Pu-239. While the natural thorium isotope Th-232 can finally be transformed to a fissile U-233 nucleus following a thermal neutron capture reaction, the existence of thorium in the nature and its potential use in the nuclear technology were not unfortunately into account with a sufficient importance. This was probably because of the geological availability of natural resources of thorium and uranium. Global distributions of thorium and uranium reserves clearly indicate that in general some developed countries such as the USA, Canada, Australia have considerable uranium reserves and contrarily only some developing countries such as Brazil, Turkey, India, Egypt have considerable thorium reserves as being totally about 70% of the global reserve. All technical parameters obtained from the studies on thorium fuel cycle during the last 50 years indicate that thorium fuel cycle can be .use.d in most of reactor types..already operated. In addition, accelerated-driven hybrid systems promise to use the thorium based nuclear fuels. So, thorium will probably be a nuclear material much more valuable than uranium in the future. For this reason, all developing countries having thorium reserves should focus their technological attentions to the evaluation of their national thorium resources like in the case of India. In this paper a brief story on the studies of thorium and its potential use in the future energy production technology have been summarized.
Economics, policy, supplies, forecasts 01/01679 Clean development mechanism and nuclear energy in Chitia Dong, F. Hong, L Progress in Nuclear Energy, 2000, 37, (14) 107-I I I. With economy developing rapidly and energy demand increasing promptly, the environmental pollution was intensified in China. In order to achieve economy sustainable development, the electricity industry must adjust existing energy structure and adopt new efficiency clean generation technology. However, in exiting electricity planning, nuclear energy develops slowly due to lack of funds and technology. The Clean Development Mechanism (CDM) provided an opportunity and challenge for developing country parties in achieving sustainable development. The ‘Clean Development Mechanism’ (CDM) was proposed by the Kyoto Protocol to the United Nation Framework Convention on Climate Change. It aims at assisting developing country Fual and Energy Abstracts
May 2001
203
05 Nuclear fuels (economics,
policy, supplies, forecasts)
parties to achieve sustainable development, and assisting developed country parties to achieve their obligation of emission reduction promised in the Kyoto Protocol in lower cost. It means it is a mutual beneficial mechanism that could be implemented between developed and developing countries. Therefore there is much interest in CDM by international bodies. 01/01660 Considering the next generation of nuclear power plants Marcus, G.H. Progress in Nuclerrr Energy, 2000, 37, (l-4), 5-10 Nuclear power will be needed for future energy demands, which are expected to grow at different rates around the world. The opportunities for building new nuclear power plants around the world will be depend on need, energy demand growth, and issues related to global warming and climate change. However, four major barriers exist for the expansion of nuclear power: economics, proliferation, safety, and waste. These issues must be addressed in the ongoing research and development of nuclear energy technology and applications. The evolution of nuclear power plant technology is presented as four distinct design generations: (1) prototypes, (2) current operating plants, (3) advanced light water reactor technology, and (4) revolutionary design concepts (i.e. Generation IV) that are now under development. The U.S. DOE Nuclear Energy Research Initiative (NERI) programme is focused on the research and development of Generation IV designs that are safe, economic, proliferation-resistant, and will address current waste issues. NERI provides grants for independently peer-reviewed proposals from universities, national laboratories and industry for advanced nuclear research and development. Several NERI projects awarded in 1999 are described in terms of how they remove barriers to nuclear power plant expansion. Another DOE effort, the Accelerator Transmutation of Waste program, will seek to reduce and ameliorate civilian reactor waste. The Accelerator Transmutation of Waste programme will involve a six-year sciencebased research plan to define key technical issues. Finally, the need for international collaboration is stressed for fourth-generation nuclear power technology development. 01101661 Environmental concerns and changing attitudes Bisconti, AS. Progress in Nuclear Energy, 2000, 37, (IA), 77-80. As environmental concerns grow, there is new evidence that attitudes toward nuclear energy are changing. Changes documented in the United States may indicate the possibilities on a global scale. Attitudes are changing within the U.S. nuclear industry and among policymakers and the public. Underlying these changes is the growing recognition of the key role nuclear energy plays in protecting the environment. 01101662 Global electrification and nuclear power: toward sustainable growth in the new millennium Kim, J.H. Starr, C. Progress in Nuclear Energy, 2000, 37, (14). 11-18. The new millennium will present daunting challenges for the world community: how to sustain prosperity while preserving the global environment in the presence of increasing world population. Science and technology hold the keys to resolving this well-publicized ‘trilemma’ of balancing economy and environment under the increasing burden of population growth. Technologies have been developing rapidly in recent years and their impact is being felt in every corner of the global community. It is expected that the process will only accelerate and expand in the new millennium. This, together with people’s aspirations for better life, will put enormous demands on energy production. Thus, energy and environment will remain two poles of a central global issue in the new century. Electricity’s role in mitigating environmental degradation is well known and global electrification promises the best hope for achieving globally sustainable growth. The question is then how to produce energy that can generate electricity harmoniously with environment. Nuclear power offers the best answer, as it is one of the few non-carbon sources that can produce electricity in significant quantity. In examining the big picture of global priorities for the new millennium, the role of electrification and nuclear power is brought to the fore in the context of globally sustainable growth, and a strategic roadmap for revival of nuclear option is proposed. 01/01663 Nuclear energy strategy in the environment of utility business deregulation Minematsu, A. Progress in Nuclear Energy, 2000, 37, (IA), 25-30. Nuclear power has contributed to the reduction and stabilization of electricity rate in Japan. However, its economic competitiveness has been eroding since mid-1980s. Deregulation is hitting nuclear power just at the time its competitiveness is declining, and it poses a threat to drive short-sighted market orientation and precludes long-term focus on achieving a balance between ‘environmental agenda’ and ‘competitiveness in market’. Lowering the electricity rate is one of the important agenda to improve the nation’s industrial competitiveness in the global market. However, it will be very difficult to win the competition of gas and oil prices with other developed countries in 204
Fuel and Energy
Abstracts
May 2001
Europe and North America due to a handicap of long transportation distance. Only nuclear power and natural energy have no relation to such a handicap of economic distance from resources. Without securing economic superiority of those energy sources, Japan will not be able to clear the handicap of energy costs. The Japanese utilities are trying hard to regain the competitive edge of nuclear power. We have established short-term strategies for both existing and new LWRs as wells a long-term strategy for technological development. With these strategies we will be able to regain the competitiveness of nuclear power. 01101664 Nuclear power under the clean development mechanism Ikemoto, I. Kanda, K. Progress in Nuclerrr Etiergr, 2000, 37, (l-4), 8994. Not a few developing countries have been following a policy of positively introducing nuclear power to meet the predicted increase in energy demand in future, however, nuclear power development needs technically and financially advanced infrastructures. It is essential for the developing countries to receive technical and financial supports from a developed country or countries, in relation to procurement of funds, education/training of operation/maintenance personnel, assurance of safety, nuclear non-proliferation and safeguard, etc., when they seek to introduced or develop nuclear power. It is expected that the developed countries would actively invest in the introduction or development of nuclear power plants in the developing countries, if the investing countries can get emission reduction credits through the Clean Development Mechanism (CDM) defined in the Article 12 of the Kyoto Protocol of the COP-3. This paper examines effectiveness of the CDM, when it is used as an institutional means of funds raising and technical infrastructure development that are expected to be the greatest obstacles to introducing nuclear power in the developing countries, and proposes the guidelines which are specifically necessary to realize it. Funds that can be raised by Japan to a nuclear power project of developing country in return of the emission right of greenhouse gases were calculated, substituting coal-fired thermal power plants with nuclear power. 01101665 Regulatory policies and the future of nuclear power Marcus, G.H. Progress in Nuclear Energy, 2000, 37, (l-4), 65-70. This paper reviews some of the national policies and regulatory decisions that have the potential to affect the production of electricity from nuclear power. It is shown that many policies and regulatory initiatives are introduced to meet objectives other than determining the mix of electricity supply resources, such as reducing the cost of electricity or protecting public health and safety. Nevertheless, such policies and requirements can have a substantial effect on the competitiveness of present nuclear power plants, as well as on prospects for future nuclear power plants. Because electricity from nuclear power can substitute for electricity from fossil fuels, policies and regulations which affect the competitiveness of nuclear power can have an effect on the production of carbon emissions, and therefore can compete with, or complement, national environmental objectives. ~~sli;~~
Roles of nucliar
energy
in Japan’s
future energy
Sato, 0. et ol. Progress in Nuclear Energy, 2000, 37, (l-4), 95-100. The roles of nuclear energy in Japan’s future energy systems were analysed from the viewpoint of securing stable energy supply and reducing carbon dioxide (CO*) emissions. The MARKAL model, developed in the Energy Technology Systems Analysis Programme (ETSAP) of the IEA, was used for establishing several energy scenarios with different assumptions on the availability of nuclear energy, natural gas, and a COz disposal option. Nuclear energy was assumed to apply for synthetic fuel production as well as for conventional electric power generation. By comparing the COz emissions and system costs between these energy scenarios, following results were obtained. Without nuclear energy, the COz emissions will hardly be reduced because of substantial increases in coal utilization. COz disposal will be effective in reducing the emissions, however at much higher costs than the case with nuclear energy. The expansion of natural gas imports, if alone, will not reduce the emissions at enough low levels. 01101667
The history and the prospects of Japanese nuclear power development program Tsujikura, Y. Progress in Nuclear Energy, 2000, 37, (l-4), 55-58. FBRs are regarded as the most probable option among non-fossil energy resources which will underpin the future energy demand in Japan, considering the effective uranium utilization and the need to lower the burden on the natural environment. However, it will take a long time to utilize FBRs due to a number of pending technical issues and improvements of cost efficiency. For the time being, therefore, light water reactors will continue to play a dominant role in power generation: thus, it is urgently necessary to establish the quasi-domestic
06 Electrical power supply and utilization (scientific, technical) nuclear fuel cycle for them, especially in the field of enrichment and spent fuel reprocessing-a goal of the Japanese nuclear policy since the dawn. Furthermore, public acceptance is significant factor which must be considered. This can best be achieved by more safety performance of light water reactors and through publication of extensive information, including decisions by the industry and government.
01101686 The role of nuclear power in the sustainable energy future of Korea
Lim, C.Y. et al. Progress in Nuclear Energy, 2000, 37, (l-4), 81-87. The purpose of this study is to analyse the role of nuclear power in the sustainable energy supply future of Korea. For this purpose, an energyeconomy interaction model of the computational general equilibrium approach, the Korean Energy and Environmental Policy model was adapted. The model is a non-linear optimization model that maximizes the discounted value of Korean economic utility. The model operates over the time horizon of 1995-2040 in annual steps. Some scenarios are established in accordance with three possible nuclear growth rate and the strength of the carbon tax imposed. At first, business as usual nuclear growth scenario was set up and maintaining the current installed capacity and phasing out the nuclear power options are considered. After that, the investigation has been done on each scenario in the case that a tax for COz emission regulation was imposed. Results show that limiting COz emissions with a nuclear phase out scenario will have the most serious impact on the economic welfare compared with the other scenarios. If the COz emission target will be imposed in Korea in the foreseeable future, nuclear power will play an important role in mitigating the economic impacts. This analysis gives us a chance to consider the trade-offs between the most important energy issues of today - concerns with the risk of nuclear power, those involving future climate change, and energy security.
06
ELECTRICAL POWER SUPPLY AND UTILIZATION Scientific, technical
01/01669 A study of electronic shorting in IBDA-deposited Lipon films
Vereda, F. ef al. Journal of Power Sources, 2000, 89, (2), 201-205. Because a near term goal of our research is to obtain optimal performance LiCoO$lithium phosphorus oxynitride (Lipon)/C thin film batteries, and due to the major importance of the electrolyte in any battery, we have recently been attempting to better understand the causes of electronic shorting in our Lipon electrolyte films. After studying the residual and temperature-dependent stress of these films and observing cracking after they had undergone a temperature change from 300°C to room temperature, we adopted a model in which the thermal expansion coefficient mismatch between Lipon and our glass substrates accounted for the cracking and therefore led to the shorting. This model was also supported by evidence that Al films (which had thermal expansion coefficients close to that of Lipon and proved to act as ‘buffer layers’ by preventing cracking of Lipon when glass/Al/Lipon structures were cooled from 300°C to room temperature) were successfully used to produce short-free Al/Lipon/Al devices.
01101690 Addition of a thin-film inorganic solid electrolyte (Lipon) as a protective film in lithium batteries with a liquid electrolyte
Dudney, N. J. Journal of Power Sources, 2000, 89, (2), 176-179. Three rechargeable lithium cells have been fabricated using thin films of Li and sputter-deposited Li,Mnz. v04 as the electrodes, and a LiPF6 organic liquid electrolyte. Cells we@cycled up to I8 times between 4.5 and 2.5 V at 25°C both with and without the addition of the thin-film lithium phosphorus oxynitride solid electrolyte, known as Lipon. Of the cells tested, the Lipon film was most effective in maximizing the capacity and cycling efficiency when deposited in direct contact with the cathode; however, a significant improvement over the Lipon-free cell was also observed with Lipon sandwiched between layers of the liquid electrolyte. In the latter case, the Lipon was deposited onto a microporous polypropylene separator membrane.
01101691 batteries
Anodes for secondary lithium batteries and the
Tanno, S. er ul. Jpn. Kokai Tokkyo Koho JP II 312,520 [99 312,5201] (Cl. HOlM4/58), 9 Nov 1999, Appl. 1998/132.649, 27 Apr 1998. 6. (In Japanese) The anodes contain mesophase carbon fibres and fluid coke having disorde_re$ layer structure.
01101692 Carbon-based air electrodes carrying MnOz in zinc-air batteries
Wei, Z. el al. Journal qf Power Sources, 2000, 91, (2), 83-85. Catalysts prepared from the carbon black impregnated with manganous nitrate solution and then heated at temperature from 270°C to 450°C were investigated. It was found that the impregnated catalysts heated at temperature of 340°C exhibited the best catalytic activity for oxygen reduction in alkaline electrolyte. It was also found that the XRD spectra of pyrolytic MnOz from manganous nitrate over 340°C were different from those below 340°C. The enhanced catalysis of air electrodes was ascribed to the formation of MnOz crystal with d-value of 2.72 A as the impregnated-catalysts was heated at temperature of 340°C. The other factors in preparation of air electrodes were also discussed.
01101693 Characteristics of surface films formed at a mesocarbon microbead electrode in a Li-ion battery Kim, J.-S. Park, Y.-T. JournulofPoirer Sources, 2000, 91, (2), 172-176. An investigation is made on the interfacial phenomena of commercially available mesocarbon microbeads (MCMB) as the carhop lithium electrode in an electrolyte, which consists of 1 M LiPFs dissolved in an equal mixture of ethylene carbonate (EC) and diethyl carbonate (DEC). Once the charge-discharge of lithium (Li) proceeds, a surface film is formed on the MCMB carbon electrode, and its thickness increases with cycle number. The growth of the surface film with cycle number is observed by a scanning electron microscope and the surface resistance by means of AC impedance measurements. A continuous decrease in the charge capacity with cycle number is found and is related to film growth. The surface films are composed of solvated Li compounds, as shown by surface-sensitive Fourier transform infrared (FT-IR) spectroscopy.
OVO1694 Coal methane in regional power generation Krasuik, N.N. el al. Ugof’, 1999, 3, 71-73. (In Russian) The reserves and production of methane from coal bed degassing prospects for its use for power generation are discussed.
and
01/01695 Comparison of lithium-polymer cell performance with unity and nonunity transference numbers
Thomas, K.E. e/ al. Journal of Power Sources, 2000, 89, (2) 132-138. This work compares the performance of lithium batteries with polymer electrolytes with unity (‘ionomer’) and nonunity (‘polymer electrolyte’) transference numbers. The study is performed with respect to a particular cell chemistry, Li metal polymer LiVsOis-composite electrode, which is currently a top candidate for use in electric vehicles. Cell performance was modelled to determine the best possible performance of cells containing four different electrolytes: ‘ideal’ polymer membrane and ionomer with properties defined by USABC goals, and the presently best available polymer electrolyte and ionomer. Positive electrode thickness, porosity, and current density were varied to find the cell geometry with the highest combined energy density and peak power performance for cells with each electrolyte, and concentration and potential profiles are examined to determine the limitations of the electrolytes. The results show that at 4o”C, the ‘ideal’ polymer electrolyte can provide 104 W h/kg and 99 W kg, the ‘ideal’ ionomer can provide 94 W h/kg and 58 Wdkg, an s/ the currently available electrolytes can provide about one-fifth of these values.
01101696 Design and evaluation of combined cycle system with solid oxide fuel cell and gas turbine
Tanaka, K. ei al. Fuel, 2000, 79, (12) 1493-1507. This study describes the basic design/evaluation of a combined cycle power generation system using solid oxide fuel cells in conjunction with a gas turbine. Factors included are system performance and cost/energy pay-back times (CPTEPT). Total generation efficiency (En,) was analysed from the standpoint of plane size, cell performance, working pressure/temperature, steam carbon ratio, fuel/air utilization ratios (I/r/U,) and turbine inlet temperature (TIT). A calculation method for determining the system life cycle cost and input energy requirements is also proposed. Results show that E,s is higher than that for conventional power plants; it has a working temperature/pressure of 1073 K/0.4 MPa, E,s = 68.3% with CPT = 9.3 years and EPT = 0.71 years with load following capability from 60 to 121% nominal load. The main parameters for determining &, CPT and EPT were found to be working temperature, cell performance, L’a and TIT limitation. Also discussed in detail are development areas and targets. Fuel and Energy Abstracts
May 2001 205
The aqueous geochemistry of neptunium: dynamic control of soluble concentrations with applications to nuclear waste disposal 61101664
Kaszuba, J.P. er al. Environ. Sci. Technol., 1999, 33, (24), 44274433. The valence state of Np, one of the most important radionuclides of concern for long-term emplacement of nuclear waste, primarily defines its geochemical reactions and migration behaviour. The authors evaluate how redox potential and solid-phase stability interact and influence Np solubility and aqueous speciation in natural systems. Np thermodynamical data for the most important valence states for natural waters, +IV and +V, are updated to correct database inconsistencies. The most significant changes are as follows: (1) NpzOs(cr) is two orders of magnitude more stable than reported previously, (2) the stability of NpOzOH (aqueous) is reduced, (3) NpOz(OH)tand mixed Np(V) hydroxo-carbonato species become important at high pH, and (4) Np(OH)s- is disregarded as a valid species. As a result, NpzOs and NP(OH)~ (am) are the stable solids in aquifers of low ionic strength, Np solubility decreases in the pH range IO-12 and increases at pH >12, and both redox potential and Np(OH)d (am) solubility product control soluble Np concentrations at neutral pH and Eh between -0.2 and 0.3. These relations are important for effective nuclear waste package design, such as including cement as an engineered barrier and evaluating impacts of discharged solutions on natural waters in release scenarios at nuclear waste storage facilities.
Thermal conversion of plastics waste in secondary petroleum-derived bitumens
and that of activated carbon is about 400 mg/g. Both residual carbon and activated carbon follow Freundlich Thermal Adsorptive Model, with physical adsorption. The primary difference between residual carbon and activated carbon is the smaller adsorptive amount of residual carbon. But, in adsorbing reactive dyes from effluent, residual carbon removes dyes more effectively than activated carbon.
01101666 Treatment of fossil fuel combustion gases Morimoto, T. Jpn. Kokai Tokkyo Koho JP 11 319,477 [99 319,477] (Cl. BOlD53/50), 24 Nov 1999, Appl. 1998/130,152, 13 May 1998. 6. (In Japanese) The title process comprises mixing fossil fuel combustion gases with aqueous NasCOs at the downstream of the combustion apparatus. The process is useful for neutralization of SO, contained in the combustion gases.
01/01669
Utilization of ash from industrial boilers
Eur. Comm., [Rep.] EUR, 1999, l-115. The overall aim of the project on utilization of ash from industrial boilers (pulverized coal-fired combustors and circulating fluidized bed combustors) were to determine the characteristics of the residues from selected boilers, to assess their variability with boiler operation, and to identify potential common outlets for these residues. The leaching characteristics of both ashes were assessed in a laboratory shake leaching test. The specific utilization options currently being pursued are for Portland cement, concrete, precast concrete masonry units, pozzolanic pulverized fuel ash cement, masonry units structural concrete, and air bricks and gratings for wall ventilation.
01101665
Polaczek, J. et al. P&n. Adr. Technol., 1999, 10, (IO), 567-569. Three petroleum-derived secondary bitumens were used as a medium for thermolysis of poly(ethylene terephthalate), poly(viny1 chloride), polyethylene and a typical waste plastics mixture (mainly polyolefins). The conversion carried out at 30&35o”C resulted in the formation of homogeneous brittle resin-like masses (ring-and-ball softening point above 120°C) intended for practical use.
Thermogravimetric FTIR spectroscopy of hydrocarbon fuel residues
01101666
Zanier, A. J. Therm. Anal. Calorim., 1999, 56, (3), 1389-1396. Although thermogravimetric analysis (TG) has become an indispensable tool for the analysis and characterization of materials, its scope is limited as no information is obtained about the qualitative aspects of the evolved gases during the thermal decomposition. For processes involving mass loss, a powerful technique to provide this missing information is Fourier transform IR spectroscopy (FTIR) in combination with TG. It supplies a comprehensive understanding of thermal events in a reliable and meaningful way as data are obtained from a single sample under the same conditions. The coupling TG/FTIR is used in fuel analysis for the identification of residual volatiles, to determine their sequence of release and to resolve thermogravimetric curves. In this work, the usefulness of TG/FTIR for characterizing middle distillate fuel residues is illustrated with some typical examples of recent application. A Bio-Rad FTS 25 FTIR spectrometer coupled with a TA Instruments TGA 2950 thermogravimetric analyser was used for data acquisition. The results obtained demonstrate the utility of this combined technique in determining the decomposition pathway of tarry materials at various stages of pyrolysis, thereby allowing new insights into the complex thermal behaviour of hydrocarbon residual systems.
Treatment of dyeing effluent by residual carbon from oil-fired fly ash
01101670 Waste still recovery process using sodium tripolyphosphate Partington, B. Verity, D.B. Brit. UK Pat. Appl. GB 2,334,034 (Cl. ClOM175/00), 11 Aug 1999, GB Appl. 1998/2,563, 6 Feb 1998. 17. A process for removal of metals from spent oil involves (1) dissolving an inorganic metal-binding agent in water to form an aqueous solution, (2) mixing the solution with metal-containing spent oil, (3) removing metals from the spent oil in the form of metal compounds formed from the metals and the metal-binding agent, (4) separating the mixture into an oil phase and an aqueous phase, (5) separating the oil phase from the aqueous phase and metal compounds to produce a processed oil with a significantly lower metal content, and optionally (6) separating the metal compounds from the aqueous phase. Preferably, the inorganic metal-binding agent is a tripolyphosphate compound (e.g. Na tripolyphosphate). Optionally, electrolytes (e.g. NaNOs or compound alkoxylate compounds can be added for an improved separation of the oil and aqueous phases. Nonmetal contaminants may be removed with addition of an ethoxylated C6-12 fatty amine of the cocoamine family. The recovered oil can be recycled to production of lubricating oils, transformer oils, and hydraulic fluids or used as a fuel oil.
05
NUCLEAR Scientific,
FUELS
technical
01101667
Tsai, MS. ef al. Kuangye (Taipei), 1999, 43, (2), 49-56. (In Chinese) Oil-fired fly ash is collected from dust collector in industry boilers. The waste dust is composed of carbon from unburnt heavy-oil, oxide and water soluble sulphate. Based on the heavy-oil consumption, it is estimated that the annual production of oil-fired by ash is about 60000 tons in Taiwan. Because there is 12% valuable metals such as vanadium and nickel in the oil-fired fly ash, these valuable metals are recovered by leaching methods. The main component, 40-80% carbon, in oil-fired fly ash is not recycled; it comes out as a large amount of residue called ‘residual carbon’. The object of this research works is to recycle this residual carbon, especially for the practical use in adsorption. The result of basic physicochemical analyses and adsorptive experiment shows that the carbon content of residual carbon is above 80%, the residual carbon has the adsorptive ability as activated carbon. The following are some comparable properties between residual carbon and activated carbon: the residual carbon has much more macropores, the specific area of residual carbon is 23-33 m3/g which is 1135 that of activated carbon, the iodine value of residual carbon is 137-195 mg/g which is l/6-1/4 that of activated carbons. Besides, the adsorptive amount of residual-carbon is 58-39 mg/g in the adsorptive experiments, 202
Fuel and Energy Abstracts
May 2001
01/01671 A concept of the multipurpose liquid metallicfueled fast reactor system (MPFR) Endo, H. ef al. Progress in Nuclear Energy, 2000, 37, (l-4), 291-298. Against fossil fuels, the nuclear energy is the only alternative energy source in the next century. Such energy source as the future nuclear power plant is expected to meet the following requirements. First, high temperature output for the multiple energy conversion capability as the electricity generation and the production of alternative fuels (hydrogen), which can be used widely in transportation systems. Second, the capability for siting close to the energy consumption are a without onsite refuelling. Third, the capability for nuclear fuel breeding and incineration of long-live fission products, and fourth, the harmonization between active and passive safety features. This paper describes the basic concept of the Multipurpose liquid metallic-fuelled Fast Reactor system (MPFR), which satisfies all mentioned requirements with introducing the U-Pu-x (x: Mn, Fe, Co) liquid metallic alloys for the fuel. We can obtain such characteristics as high operational temperature of the reactor (between 550°C and 12OO’C) and elongation of the core operational lifetime by the inherent fission product separation in the liquid fuel by using these alloys. The enhanced self-
05 Nuclear fuels (economics, policy, supplies, forecasts) controllability is achieved by the thermal expansion of liquid fuel; and the re-criticality phenomenon at the core compaction events can be eliminated by discharging of the liquid fuel from the core. 01101672 A conceptual design study on innovative FBR Kasai, S. er al. Progress in Nuclecrr Energy, 2000, 37, (l-4) 131-136. An Actinide Recycle Reactor (ARR) with ductless fuel assemblies and mixed nitride fuel is studied in accordance with an Advanced Fuel Recycle System. The core is designed so that yield more economical efficiencies (high breeding ratio and high burnup), safety aspects (high low void reactivity coefficient and Doppler reactivity coefficient, reactor dynamic characteristics) in comparison with mixed oxide or metal fuel on a suitable condition. Preliminary calculations about key parameters of the core design performances had been done to compare with mixed oxide or metal fuel. Results show that the mixed nitride fuel with a sodium bond and ZrH has promising capacity.
OllOl973 A design study on MOX-fueled small fast reactors for standardiza;ion of a small fast unclear reactor system Uto, N. e( al. Progress in Nuclear Energy, 2000, 37, (l-4), 283-290. A way of development to standardize a small fast nuclear reactor system, which is considered one of the suitable concepts at next generation for satisfying such needs as generality, small dependence on natural resources, safety and non-proliferation, is proposed. This process consists of three steps: the first is to demonstrate the basic system within a short period based on current techniques, the second is to achieve greatly higher economy, and the final is to standardize the commercial system that can economically compete with or overcome current light water reactors. A technical investigation is conducted on the performance of a mixed-oxide (MOX)-fuelled small fast reactor with a reflector-driven reactivity control system to satisfy the needs at the first step, considering plenty of accomplishments on the MOX fuel and its advantage for limiting the duration of development to the level required at the stage. The results obtained from a series of neutronic and thermal-hydraulic calculations show the feasibility of a small fast reactor that produces the electric power of about 50 MW, achieves about two-year consecutive operation with high safety performance and is greatly flexible for updating the system. A mixed-nitride-fuelled core is found to be promising past the first stage.
01101674 Characterization and durability testing of a glassbonded ceramic waste form Johnson, S.G. er al. Ceram. Trans., 1999, 93, 313-320. Argonne National Laboratory is developing a glass-bonded ceramic (zeolite 4A) waste form for encapsulating the fission products and transuranics from the conditioning of metallic reactor fuel:This waste form is currently being scaled to the multikilogram size for encapsulation of actual high level waste. This paper describes characterization and durability testing used to evaluate the product of the waste treatment process. The emphasis is on results from application of glass durability tests such as X-ray diffraction and SEM. The information presented forms the basis for a suite of tests utilized for assessing product quality during scale-up and parametric testing.
Conceptual design of multi-purpose heat reactor ‘nuclear heat generator’
01101675
Uchiyama, Y. ef al. Progress in Nucleur Energy, 2000, 37, (l-4), 277282. Small beat reactors can apply to on site demand such as district heat and air conditioning, industrial process heat, greenhouse, a seawater desalination in urban and rural areas. The purpose of this paper is to design conceptually a multi-purpose reactor named ‘Nuclear Heat Generator (NHG)’ which could be installed in energy consuming area. The reactor of 1 MWt output is designed without any needs for fuel exchange and decommissioning on site. This cassette typed reactor vessel with sealing is transported to specified fuel fabrication shop every 3-4 years in order to exchange used fuels. Steam generators are involved in the self-pressurized integrated reactor with natural circulation. Generated steam pressure from heating reactor is 0.88 MPa (saturated) which is so less than that of current water reactors. Under low steam pressure it is considerably easy to make design of containment vessel and safety device. For economic competition overcoming scale demerit it will be necessary for the cassette type reactor to optimize its system design for the multi-production effect as well as modular construction and recycling system. 01101676 Design study of the demonstration FBR in Japan Inagaki, T. el al. Progress in Nuclear Energy, 2000, 37, (l-4), 119-124. The objective of the plant design study Phase 2, conducted by the Japan Atomic Power Company since 1997 for 3 years, is to accomplish a plant overall concept of the Demonstrative FBR (DFBR) that has economical potential toward commercialization and offers high reliability to plant operators not to cause a long unexpected shutdown resulting from a trouble, i.e. sodium leakage or fires. This has been successfully achieved by establishment of a plant overall design of 672
MWe consisting of the reactor system with drastically simplified internals, the compact and double walled coolant boundaries, the well rationalized fuel handling system, the BOP systems introducing up-todate LWR equipment, and the compact reactor building. The plant construction cost has been estimated based on the quantity of materials to be about 130% on the bases of a 1000 MW LWR, which is well contented with the requirement. The DFBR plant concept, having economical potential toward commercialization, safety and reliability, has been established in the plant design study Phase 2. 01101677 Desirability of small reactors, HTGR in particular Tsuchie, Y. Progress in Nuclear Energy, 2000, 37, (l-4). 253-258. Small reactors of about 100-300 Mwe, High Temperature Gas Cooled Reactors (HTGRs) in particular, are considered desirable in future, based on the following ways of thinking; Global scale enhancement of nuclear energy is considered necessary from reduction of environmental impact point of view. Small reactors are desirable, due to (a) enhanced safety in terms of fuel inventory and inherent safety, then (b) easier plant siting near populated or industrial area, (c) more flexible development, planning and construction than larger reactors by finer adjustment with demand, and (d) economic competitiveness attainable by means of adoption of more rationalized systems categorization, simpler and modularized design, mass production in factory, less work at construction site, and marketability including that of developing countries. In such ways, small reactors can be economically designed, constructed and operated, by conquering ‘scale de-merit’, in contrast with scale merit of larger reactors as seen in current LWRs. Small HTGRs, in particular, are mostly desirable and promising, from view points of wider applications, such as electricity use, wise range of heat uses and/or cogeneration, Pu burning with high efficiency, wider fuel cycle options, using U, Pu and/or Th, with or without reprocessing, and development stages, where not only test reactor programmes for development and demonstration but also realization programmes are already going on towards commercial operation start in 2005-2010. Development programmes on small HTGR, related global activities and cost evaluations by developers and JAPC are shown, and steps towards their global scale commercializations are proposed.
What is the potential use of thorium in the future energy production technology?
OllO1678
Unak, T. Progress in Nuclear Energy, 2000, 37, (l-4), 137-144. Today’s nuclear technology has principally been based on the use of fissile U-235 and Pu-239. While the natural thorium isotope Th-232 can finally be transformed to a fissile U-233 nucleus following a thermal neutron capture reaction, the existence of thorium in the nature and its potential use in the nuclear technology were not unfortunately into account with a sufficient importance. This was probably because of the geological availability of natural resources of thorium and uranium. Global distributions of thorium and uranium reserves clearly indicate that in general some developed countries such as the USA, Canada, Australia have considerable uranium reserves and contrarily only some developing countries such as Brazil, Turkey, India, Egypt have considerable thorium reserves as being totally about 70% of the global reserve. All technical parameters obtained from the studies on thorium fuel cycle during the last 50 years indicate that thorium fuel cycle can be .use.d in most of reactor types..already operated. In addition, accelerated-driven hybrid systems promise to use the thorium based nuclear fuels. So, thorium will probably be a nuclear material much more valuable than uranium in the future. For this reason, all developing countries having thorium reserves should focus their technological attentions to the evaluation of their national thorium resources like in the case of India. In this paper a brief story on the studies of thorium and its potential use in the future energy production technology have been summarized.
Economics, policy, supplies, forecasts 01/01679 Clean development mechanism and nuclear energy in Chitia Dong, F. Hong, L Progress in Nuclear Energy, 2000, 37, (14) 107-I I I. With economy developing rapidly and energy demand increasing promptly, the environmental pollution was intensified in China. In order to achieve economy sustainable development, the electricity industry must adjust existing energy structure and adopt new efficiency clean generation technology. However, in exiting electricity planning, nuclear energy develops slowly due to lack of funds and technology. The Clean Development Mechanism (CDM) provided an opportunity and challenge for developing country parties in achieving sustainable development. The ‘Clean Development Mechanism’ (CDM) was proposed by the Kyoto Protocol to the United Nation Framework Convention on Climate Change. It aims at assisting developing country Fual and Energy Abstracts
May 2001
203
05 Nuclear fuels (economics,
policy, supplies, forecasts)
parties to achieve sustainable development, and assisting developed country parties to achieve their obligation of emission reduction promised in the Kyoto Protocol in lower cost. It means it is a mutual beneficial mechanism that could be implemented between developed and developing countries. Therefore there is much interest in CDM by international bodies. 01/01660 Considering the next generation of nuclear power plants Marcus, G.H. Progress in Nuclerrr Energy, 2000, 37, (l-4), 5-10 Nuclear power will be needed for future energy demands, which are expected to grow at different rates around the world. The opportunities for building new nuclear power plants around the world will be depend on need, energy demand growth, and issues related to global warming and climate change. However, four major barriers exist for the expansion of nuclear power: economics, proliferation, safety, and waste. These issues must be addressed in the ongoing research and development of nuclear energy technology and applications. The evolution of nuclear power plant technology is presented as four distinct design generations: (1) prototypes, (2) current operating plants, (3) advanced light water reactor technology, and (4) revolutionary design concepts (i.e. Generation IV) that are now under development. The U.S. DOE Nuclear Energy Research Initiative (NERI) programme is focused on the research and development of Generation IV designs that are safe, economic, proliferation-resistant, and will address current waste issues. NERI provides grants for independently peer-reviewed proposals from universities, national laboratories and industry for advanced nuclear research and development. Several NERI projects awarded in 1999 are described in terms of how they remove barriers to nuclear power plant expansion. Another DOE effort, the Accelerator Transmutation of Waste program, will seek to reduce and ameliorate civilian reactor waste. The Accelerator Transmutation of Waste programme will involve a six-year sciencebased research plan to define key technical issues. Finally, the need for international collaboration is stressed for fourth-generation nuclear power technology development. 01101661 Environmental concerns and changing attitudes Bisconti, AS. Progress in Nuclear Energy, 2000, 37, (IA), 77-80. As environmental concerns grow, there is new evidence that attitudes toward nuclear energy are changing. Changes documented in the United States may indicate the possibilities on a global scale. Attitudes are changing within the U.S. nuclear industry and among policymakers and the public. Underlying these changes is the growing recognition of the key role nuclear energy plays in protecting the environment. 01101662 Global electrification and nuclear power: toward sustainable growth in the new millennium Kim, J.H. Starr, C. Progress in Nuclear Energy, 2000, 37, (14). 11-18. The new millennium will present daunting challenges for the world community: how to sustain prosperity while preserving the global environment in the presence of increasing world population. Science and technology hold the keys to resolving this well-publicized ‘trilemma’ of balancing economy and environment under the increasing burden of population growth. Technologies have been developing rapidly in recent years and their impact is being felt in every corner of the global community. It is expected that the process will only accelerate and expand in the new millennium. This, together with people’s aspirations for better life, will put enormous demands on energy production. Thus, energy and environment will remain two poles of a central global issue in the new century. Electricity’s role in mitigating environmental degradation is well known and global electrification promises the best hope for achieving globally sustainable growth. The question is then how to produce energy that can generate electricity harmoniously with environment. Nuclear power offers the best answer, as it is one of the few non-carbon sources that can produce electricity in significant quantity. In examining the big picture of global priorities for the new millennium, the role of electrification and nuclear power is brought to the fore in the context of globally sustainable growth, and a strategic roadmap for revival of nuclear option is proposed. 01/01663 Nuclear energy strategy in the environment of utility business deregulation Minematsu, A. Progress in Nuclear Energy, 2000, 37, (IA), 25-30. Nuclear power has contributed to the reduction and stabilization of electricity rate in Japan. However, its economic competitiveness has been eroding since mid-1980s. Deregulation is hitting nuclear power just at the time its competitiveness is declining, and it poses a threat to drive short-sighted market orientation and precludes long-term focus on achieving a balance between ‘environmental agenda’ and ‘competitiveness in market’. Lowering the electricity rate is one of the important agenda to improve the nation’s industrial competitiveness in the global market. However, it will be very difficult to win the competition of gas and oil prices with other developed countries in 204
Fuel and Energy
Abstracts
May 2001
Europe and North America due to a handicap of long transportation distance. Only nuclear power and natural energy have no relation to such a handicap of economic distance from resources. Without securing economic superiority of those energy sources, Japan will not be able to clear the handicap of energy costs. The Japanese utilities are trying hard to regain the competitive edge of nuclear power. We have established short-term strategies for both existing and new LWRs as wells a long-term strategy for technological development. With these strategies we will be able to regain the competitiveness of nuclear power. 01101664 Nuclear power under the clean development mechanism Ikemoto, I. Kanda, K. Progress in Nuclerrr Etiergr, 2000, 37, (l-4), 8994. Not a few developing countries have been following a policy of positively introducing nuclear power to meet the predicted increase in energy demand in future, however, nuclear power development needs technically and financially advanced infrastructures. It is essential for the developing countries to receive technical and financial supports from a developed country or countries, in relation to procurement of funds, education/training of operation/maintenance personnel, assurance of safety, nuclear non-proliferation and safeguard, etc., when they seek to introduced or develop nuclear power. It is expected that the developed countries would actively invest in the introduction or development of nuclear power plants in the developing countries, if the investing countries can get emission reduction credits through the Clean Development Mechanism (CDM) defined in the Article 12 of the Kyoto Protocol of the COP-3. This paper examines effectiveness of the CDM, when it is used as an institutional means of funds raising and technical infrastructure development that are expected to be the greatest obstacles to introducing nuclear power in the developing countries, and proposes the guidelines which are specifically necessary to realize it. Funds that can be raised by Japan to a nuclear power project of developing country in return of the emission right of greenhouse gases were calculated, substituting coal-fired thermal power plants with nuclear power. 01101665 Regulatory policies and the future of nuclear power Marcus, G.H. Progress in Nuclear Energy, 2000, 37, (l-4), 65-70. This paper reviews some of the national policies and regulatory decisions that have the potential to affect the production of electricity from nuclear power. It is shown that many policies and regulatory initiatives are introduced to meet objectives other than determining the mix of electricity supply resources, such as reducing the cost of electricity or protecting public health and safety. Nevertheless, such policies and requirements can have a substantial effect on the competitiveness of present nuclear power plants, as well as on prospects for future nuclear power plants. Because electricity from nuclear power can substitute for electricity from fossil fuels, policies and regulations which affect the competitiveness of nuclear power can have an effect on the production of carbon emissions, and therefore can compete with, or complement, national environmental objectives. ~~sli;~~
Roles of nucliar
energy
in Japan’s
future energy
Sato, 0. et ol. Progress in Nuclear Energy, 2000, 37, (l-4), 95-100. The roles of nuclear energy in Japan’s future energy systems were analysed from the viewpoint of securing stable energy supply and reducing carbon dioxide (CO*) emissions. The MARKAL model, developed in the Energy Technology Systems Analysis Programme (ETSAP) of the IEA, was used for establishing several energy scenarios with different assumptions on the availability of nuclear energy, natural gas, and a COz disposal option. Nuclear energy was assumed to apply for synthetic fuel production as well as for conventional electric power generation. By comparing the COz emissions and system costs between these energy scenarios, following results were obtained. Without nuclear energy, the COz emissions will hardly be reduced because of substantial increases in coal utilization. COz disposal will be effective in reducing the emissions, however at much higher costs than the case with nuclear energy. The expansion of natural gas imports, if alone, will not reduce the emissions at enough low levels. 01101667
The history and the prospects of Japanese nuclear power development program Tsujikura, Y. Progress in Nuclear Energy, 2000, 37, (l-4), 55-58. FBRs are regarded as the most probable option among non-fossil energy resources which will underpin the future energy demand in Japan, considering the effective uranium utilization and the need to lower the burden on the natural environment. However, it will take a long time to utilize FBRs due to a number of pending technical issues and improvements of cost efficiency. For the time being, therefore, light water reactors will continue to play a dominant role in power generation: thus, it is urgently necessary to establish the quasi-domestic
06 Electrical power supply and utilization (scientific, technical) nuclear fuel cycle for them, especially in the field of enrichment and spent fuel reprocessing-a goal of the Japanese nuclear policy since the dawn. Furthermore, public acceptance is significant factor which must be considered. This can best be achieved by more safety performance of light water reactors and through publication of extensive information, including decisions by the industry and government.
01101686 The role of nuclear power in the sustainable energy future of Korea
Lim, C.Y. et al. Progress in Nuclear Energy, 2000, 37, (l-4), 81-87. The purpose of this study is to analyse the role of nuclear power in the sustainable energy supply future of Korea. For this purpose, an energyeconomy interaction model of the computational general equilibrium approach, the Korean Energy and Environmental Policy model was adapted. The model is a non-linear optimization model that maximizes the discounted value of Korean economic utility. The model operates over the time horizon of 1995-2040 in annual steps. Some scenarios are established in accordance with three possible nuclear growth rate and the strength of the carbon tax imposed. At first, business as usual nuclear growth scenario was set up and maintaining the current installed capacity and phasing out the nuclear power options are considered. After that, the investigation has been done on each scenario in the case that a tax for COz emission regulation was imposed. Results show that limiting COz emissions with a nuclear phase out scenario will have the most serious impact on the economic welfare compared with the other scenarios. If the COz emission target will be imposed in Korea in the foreseeable future, nuclear power will play an important role in mitigating the economic impacts. This analysis gives us a chance to consider the trade-offs between the most important energy issues of today - concerns with the risk of nuclear power, those involving future climate change, and energy security.
06
ELECTRICAL POWER SUPPLY AND UTILIZATION Scientific, technical
01/01669 A study of electronic shorting in IBDA-deposited Lipon films
Vereda, F. ef al. Journal of Power Sources, 2000, 89, (2), 201-205. Because a near term goal of our research is to obtain optimal performance LiCoO$lithium phosphorus oxynitride (Lipon)/C thin film batteries, and due to the major importance of the electrolyte in any battery, we have recently been attempting to better understand the causes of electronic shorting in our Lipon electrolyte films. After studying the residual and temperature-dependent stress of these films and observing cracking after they had undergone a temperature change from 300°C to room temperature, we adopted a model in which the thermal expansion coefficient mismatch between Lipon and our glass substrates accounted for the cracking and therefore led to the shorting. This model was also supported by evidence that Al films (which had thermal expansion coefficients close to that of Lipon and proved to act as ‘buffer layers’ by preventing cracking of Lipon when glass/Al/Lipon structures were cooled from 300°C to room temperature) were successfully used to produce short-free Al/Lipon/Al devices.
01101690 Addition of a thin-film inorganic solid electrolyte (Lipon) as a protective film in lithium batteries with a liquid electrolyte
Dudney, N. J. Journal of Power Sources, 2000, 89, (2), 176-179. Three rechargeable lithium cells have been fabricated using thin films of Li and sputter-deposited Li,Mnz. v04 as the electrodes, and a LiPF6 organic liquid electrolyte. Cells we@cycled up to I8 times between 4.5 and 2.5 V at 25°C both with and without the addition of the thin-film lithium phosphorus oxynitride solid electrolyte, known as Lipon. Of the cells tested, the Lipon film was most effective in maximizing the capacity and cycling efficiency when deposited in direct contact with the cathode; however, a significant improvement over the Lipon-free cell was also observed with Lipon sandwiched between layers of the liquid electrolyte. In the latter case, the Lipon was deposited onto a microporous polypropylene separator membrane.
01101691 batteries
Anodes for secondary lithium batteries and the
Tanno, S. er ul. Jpn. Kokai Tokkyo Koho JP II 312,520 [99 312,5201] (Cl. HOlM4/58), 9 Nov 1999, Appl. 1998/132.649, 27 Apr 1998. 6. (In Japanese) The anodes contain mesophase carbon fibres and fluid coke having disorde_re$ layer structure.
01101692 Carbon-based air electrodes carrying MnOz in zinc-air batteries
Wei, Z. el al. Journal qf Power Sources, 2000, 91, (2), 83-85. Catalysts prepared from the carbon black impregnated with manganous nitrate solution and then heated at temperature from 270°C to 450°C were investigated. It was found that the impregnated catalysts heated at temperature of 340°C exhibited the best catalytic activity for oxygen reduction in alkaline electrolyte. It was also found that the XRD spectra of pyrolytic MnOz from manganous nitrate over 340°C were different from those below 340°C. The enhanced catalysis of air electrodes was ascribed to the formation of MnOz crystal with d-value of 2.72 A as the impregnated-catalysts was heated at temperature of 340°C. The other factors in preparation of air electrodes were also discussed.
01101693 Characteristics of surface films formed at a mesocarbon microbead electrode in a Li-ion battery Kim, J.-S. Park, Y.-T. JournulofPoirer Sources, 2000, 91, (2), 172-176. An investigation is made on the interfacial phenomena of commercially available mesocarbon microbeads (MCMB) as the carhop lithium electrode in an electrolyte, which consists of 1 M LiPFs dissolved in an equal mixture of ethylene carbonate (EC) and diethyl carbonate (DEC). Once the charge-discharge of lithium (Li) proceeds, a surface film is formed on the MCMB carbon electrode, and its thickness increases with cycle number. The growth of the surface film with cycle number is observed by a scanning electron microscope and the surface resistance by means of AC impedance measurements. A continuous decrease in the charge capacity with cycle number is found and is related to film growth. The surface films are composed of solvated Li compounds, as shown by surface-sensitive Fourier transform infrared (FT-IR) spectroscopy.
OVO1694 Coal methane in regional power generation Krasuik, N.N. el al. Ugof’, 1999, 3, 71-73. (In Russian) The reserves and production of methane from coal bed degassing prospects for its use for power generation are discussed.
and
01/01695 Comparison of lithium-polymer cell performance with unity and nonunity transference numbers
Thomas, K.E. e/ al. Journal of Power Sources, 2000, 89, (2) 132-138. This work compares the performance of lithium batteries with polymer electrolytes with unity (‘ionomer’) and nonunity (‘polymer electrolyte’) transference numbers. The study is performed with respect to a particular cell chemistry, Li metal polymer LiVsOis-composite electrode, which is currently a top candidate for use in electric vehicles. Cell performance was modelled to determine the best possible performance of cells containing four different electrolytes: ‘ideal’ polymer membrane and ionomer with properties defined by USABC goals, and the presently best available polymer electrolyte and ionomer. Positive electrode thickness, porosity, and current density were varied to find the cell geometry with the highest combined energy density and peak power performance for cells with each electrolyte, and concentration and potential profiles are examined to determine the limitations of the electrolytes. The results show that at 4o”C, the ‘ideal’ polymer electrolyte can provide 104 W h/kg and 99 W kg, the ‘ideal’ ionomer can provide 94 W h/kg and 58 Wdkg, an s/ the currently available electrolytes can provide about one-fifth of these values.
01101696 Design and evaluation of combined cycle system with solid oxide fuel cell and gas turbine
Tanaka, K. ei al. Fuel, 2000, 79, (12) 1493-1507. This study describes the basic design/evaluation of a combined cycle power generation system using solid oxide fuel cells in conjunction with a gas turbine. Factors included are system performance and cost/energy pay-back times (CPTEPT). Total generation efficiency (En,) was analysed from the standpoint of plane size, cell performance, working pressure/temperature, steam carbon ratio, fuel/air utilization ratios (I/r/U,) and turbine inlet temperature (TIT). A calculation method for determining the system life cycle cost and input energy requirements is also proposed. Results show that E,s is higher than that for conventional power plants; it has a working temperature/pressure of 1073 K/0.4 MPa, E,s = 68.3% with CPT = 9.3 years and EPT = 0.71 years with load following capability from 60 to 121% nominal load. The main parameters for determining &, CPT and EPT were found to be working temperature, cell performance, L’a and TIT limitation. Also discussed in detail are development areas and targets. Fuel and Energy Abstracts
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