Nuclear-fuel-cycle education: Module 1. Nuclear fuel cycle overview

International Nuclear Information System (INIS)

Eckhoff, N.D.

1981-07-01

This educational module is an overview of the nuclear-fule-cycle. The overview covers nuclear energy resources, the present and future US nuclear industry, the industry view of nuclear power, the International Nuclear Fuel Cycle Evaluation program, the Union of Concerned Scientists view of the nuclear-fuel-cycle, an analysis of this viewpoint, resource requirements for a model light water reactor, and world nuclear power considerations

Prediction and attendance of Angra 2 nuclear power plant cycle extension

International Nuclear Information System (INIS)

Dias, Amory; Ferreira Junior, Decio Brandes M.; Morgado, Mario Monteiro; Santos, Barbara Oliveira dos; Oliveira, Monica Georgia Nunes

2007-01-01

The Report Project Nuclear and Thermohydraulic (RPNT) of the Nuclear Power Plant Angra 2 previews extension of the cycle, using a feedback of core reactor reactivity, through the reduction of the moderator average temperature and power. In this phase, the reactor power remains almost invariable. Furthermore, the extension of cycle can be stretch after the limit of the temperature reduction has been reached, through of reactor power fall until the determined date for the end cycle and the start outage for the next cycle. The proposal of this work is to show the Power Plant results during the phase of moderator temperature reduction and to compare with the predict values obtained from reactivity balance calculation methodology used for the Reactor Physics. In general, the results of this work can collaborate for the extension behavior evaluation of the cycles of the Nuclear Power Plant 2, being used the procedure of cooling reduction average temperature, as well as, it will also collaborate for methodology qualification applied for the Reactor Physics during the reactivity balance calculation. (author)

Nuclear and radiological safety nuclear power nuclear fuel cycle and waste management

International Nuclear Information System (INIS)

1997-05-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety, Nuclear Power and Nuclear Fuel Cycle and Waste Management and issued during the period of 1995-1996. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (Arabic, Chinese, French, Russian or Spanish), but all these papers have abstracts in English

Nuclear power and the possibility of alternative fuel cycles

International Nuclear Information System (INIS)

Engelmann, P.

1979-01-01

Concern about the societal implications, potential risks and the possibility of nuclear weapons proliferation has slowed down the growth of nuclear energy. Assuming a further moderate growth of nuclear power in the Federal Republic of Germany several fuel cycle and reactor strategies can the followed without exhausting the nuclear the resources before the year 2100. The uranium demand of various reactor strategies with LWR's FBR's and HTR's is compared for two demand cases in the FRG. While recycling of spent fuel seems necessary in any case, it is shown that the Th/U cycle can provide a realistic alternative to the U/Pu cycle. The parallel introduction of both cycles appears as the best solution, as it reduces the overall risks and leads to minimum uranium demand. The risk of nuclear proliferation does not vary considerably with the fuel cycle applied; it can, however, be reduced to acceptable levels by safeguards methods and institutional means. (orig.) [de

Development of web based performance analysis program for nuclear power plant turbine cycle

International Nuclear Information System (INIS)

Park, Hoon; Yu, Seung Kyu; Kim, Seong Kun; Ji, Moon Hak; Choi, Kwang Hee; Hong, Seong Ryeol

2002-01-01

Performance improvement of turbine cycle affects economic operation of nuclear power plant. We developed performance analysis system for nuclear power plant turbine cycle. The system is based on PTC (Performance Test Code), that is estimation standard of nuclear power plant performance. The system is developed using Java Web-Start and JSP(Java Server Page)

Safe and effective nuclear power plant life cycle management towards decommissioning

International Nuclear Information System (INIS)

2002-08-01

The objective of this publication is to promote and communicate the need for a longer-term perspective among senior managers and policy or strategy makers for decisions that have the potential to affect the life cycle management of a nuclear power plant including decommissioning. The following sections provide practical guidance in the subject areas that might have the potential to have such an impact. The publication should be used as an aid to help strategic planning take place in an informed way through the proper consideration of any longer-term decisions to enforce recognition of the point that decommissioning is a part of the whole life cycle of a nuclear power plant. The guidance contained in this publication is relevant to all life cycle stages of a nuclear power plant, with particular emphasis on how these decisions have the potential to impact effective decommissioning. The intended users of this publication are: Strategic decision makers within a Utility through all the various life cycle stages; The senior representatives of the owners of a nuclear power plant. This publication is divided into two basic sections. Section 2 provides guidance on the topics considered generic inputs to plant life cycle management and Section 3 provides guidance on the topics that contribute to effective decommissioning

The nuclear power cycle; Le cycle de l'energie nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

Fifty years after the first nuclear reactor come on-line, nuclear power is fourth among the world's primary energy sources, after oil, coal and gas. In 2002, there were 441 reactors in operation worldwide. The United States led the world with 104 reactors and an installed capacity of 100,000 MWe, or more than one fourth of global capacity. Electricity from nuclear energy represents 78% of the production in France, 57% in Belgium, 46% in Sweden, 40% in Switzerland, 39% in South Korea, 34% in Japan, 30% in Germany, 30% in Finland, 26% in Spain, 22% in Great Britain, 20% in the United States and 16% in Russia. Worldwide, 32 reactors are under construction, including 21 in Asia. This information document presents the Areva activities in the nuclear power cycle: the nuclear fuel, the nuclear reactors, the spent fuel reprocessing and recycling and nuclear cleanup and dismantling. (A.L.B.)

Specific safety aspects of the water-steam cycle important to nuclear power plant project

International Nuclear Information System (INIS)

Lobo, C.G.

1986-01-01

The water-steam cycle in a nuclear power plant is similar to that used in conventional power plants. Some systems and components are required for the safe nuclear power plant operation and therefore are designed according to the safety criteria, rules and regulations applied in nuclear installations. The aim of this report is to present the safety characteristics of the water-steam cycle of a nuclear power plant with pressurized water reactor, as applied for the design of the nuclear power plants Angra 2 and Angra 3. (Author) [pt

Development of the fuel-cycle costs in nuclear power stations with light-water reactors

International Nuclear Information System (INIS)

Brosch, R.; Moraw, G.; Musil, G.; Schneeberger, M.

1976-01-01

The authors investigate the fuel-cycle costs in nuclear power stations with light-water reactors in the Federal Republic of Germany in the years 1966 to 1976. They determine the effect of the price development for the individual components of the nuclear fuel cycle on the fuel-cycle costs averaged over the whole power station life. Here account is taken also of inflation rates and the change in the DM/US $ parity. In addition they give the percentage apportionment of the fuel-cycle costs. The authors show that real fuel-cycle costs for nuclear power stations with light-water reactors in the Federal Republic of Germany have risen by 11% between 1966 and 1976. This contradicts the often repeated reproach that fuel costs in nuclear power stations are rising very steeply and are no longer competitive. (orig.) [de

The nuclear fuel cycle versus the carbon cycle

International Nuclear Information System (INIS)

Ewing, R.C.

2005-01-01

Nuclear power provides approximately 17% of the world's electricity, which is equivalent to a reduction in carbon emissions of ∼0.5 gigatonnes (Gt) of C/yr. This is a modest reduction as compared with global emissions of carbon, ∼7 Gt C/yr. Most analyses suggest that in order to have a significant and timely impact on carbon emissions, carbon-free sources, such as nuclear power, would have to expand total production of energy by factors of three to ten by 2050. A three-fold increase in nuclear power capacity would result in a projected reduction in carbon emissions of 1 to 2 Gt C/yr, depending on the type of carbon-based energy source that is displaced. This three-fold increase utilizing present nuclear technologies would result in 25,000 metric tonnes (t) of spent nuclear fuel (SNF) per year, containing over 200 t of plutonium. This is compared to a present global inventory of approximately 280,000 t of SNF and >1,700 t of Pu. A nuclear weapon can be fashioned from as little as 5 kg of 239 Pu. However, there is considerable technological flexibility in the nuclear fuel cycle. There are three types of nuclear fuel cycles that might be utilized for the increased production of energy: open, closed, or a symbiotic combination of different types of reactor (such as, thermal and fast neutron reactors). The neutron energy spectrum has a significant effect on the fission product yield, and the consumption of long-lived actinides, by fission, is best achieved by fast neutrons. Within each cycle, the volume and composition of the high-level nuclear waste and fissile material depend on the type of nuclear fuel, the amount of burn-up, the extent of radionuclide separation during reprocessing, and the types of materials used to immobilize different radionuclides. As an example, a 232 Th-based fuel cycle can be used to breed fissile 233 U with minimum production of Pu. In this paper, I will contrast the production of excess carbon in the form of CO 2 from fossil fuels with

COMPARISON OF S-CO2 POWER CYCLES FOR NUCLEAR ENERGY

Directory of Open Access Journals (Sweden)

Ladislav Vesely

2016-12-01

Full Text Available The supercritical carbon dioxide (S-CO2 is a possible cooling system for the new generations of nuclear reactors and fusion reactors. The S-CO2 power cycles have several advantages over other possible coolants such as water and helium. The advantages are the compression work, which is lower than in the case of helium, near the critical point and the S-CO2 is more compact than water and helium. The disadvantage is so called Pinch point which occurs in the regenerative heat exchanger. The pinch point can be eliminated by an arrangement of the cycle or using a mixture of CO2. This paper describes the S-CO2 power cycles for nuclear fission and fusion reactors.

Study on economic potential of nuclear-gas combined cycle power generation in Chinese market

International Nuclear Information System (INIS)

Zhou Zhiwei; Bian Zhiqiang; Yang Mengjia

2004-01-01

Facing the challenges of separation of electric power plant and grid, and the deregulation of Chinese electricity supplying market in near future, nuclear power plants mainly operated as based load at the present regulated market should look for new operation mode. The economics of electric generation with nuclear-natural gas combined cycle is studied based on current conditions of natural gas and nuclear power plants in China. The results indicate that the technology development of nuclear-natural gas combined cycle for power generation is of potential prospects in Chinese electric market. (authors)

Economic aspects of the development of nuclear power and fuel-cycle plants in the USSR

International Nuclear Information System (INIS)

Dergachev, N.P.; Kruglov, A.K.; Sedov, V.M.; Shuklin, S.V.

1977-01-01

Different possible versions of the construction programme for nuclear power stations and fuel-cycle plants in the USSR are discussed in relation to the target level of installed electrical capacity for 1980 and the predictions for the year 2000. The likely structure of the nuclear power industry is considered and the role of nuclear power stations with fast reactors is discussed, including their effect on the natural uranium supply situation. The effect of the development of fuel-cycle plants and of the organization of the reprocessing of fuel from nuclear power stations on the rate of introduction of fast reactor stations is analysed, and the effect of the technical and economic characteristics of fuel-cycle plants on the economic indices of nuclear power is studied. (author)

Open-Phase Condition Detecting System for Transformers in Nuclear Power Plant

International Nuclear Information System (INIS)

Ha, Che-Wung; Lee, Do-Hwan

2015-01-01

Recently, several events involving the loss of one of the three phases of the offsite power circuit occurred in the US nuclear power plants (NPPs).. In some cases, the open-phase condition existed undetected for an extended period and in other case, was not properly responded to. Accordingly, the Nuclear Regulatory Commission (NRC) requested all license holders to take corrective actions to address the open-phase condition. It was also requested that all holders or applicant for a standard design certification (DC) include a description of a protection system to detect and separate the open circuit into design control document (DCD). Currently, NPPs including Duke Energy, Exelon, and institutes including Electric Power Research Institute (EPRI) are working together to resolve issues associated with detecting an open-phase condition. This paper, using Electromagnetic Transients Program (EMTP), presents a system to detect and address the loss of one of three phases of the offsite power circuit connected to main, auxiliary and standby transformers, which is hard to be detected in the current protection system. This paper, using EMTP, presents a system to detect and address the loss of one of three phases of the offsite power circuit running to MT, UAT or SAT which is hard to be detected in the current protection system. The system presented in this paper will be useful not only for the KHNP to meet the NRC requirement, but also for nuclear power plants at home and abroad to take corrective actions to provide protection from a single phase open circuit condition for offsite power sources

Open-Phase Condition Detecting System for Transformers in Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Ha, Che-Wung; Lee, Do-Hwan [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Recently, several events involving the loss of one of the three phases of the offsite power circuit occurred in the US nuclear power plants (NPPs).. In some cases, the open-phase condition existed undetected for an extended period and in other case, was not properly responded to. Accordingly, the Nuclear Regulatory Commission (NRC) requested all license holders to take corrective actions to address the open-phase condition. It was also requested that all holders or applicant for a standard design certification (DC) include a description of a protection system to detect and separate the open circuit into design control document (DCD). Currently, NPPs including Duke Energy, Exelon, and institutes including Electric Power Research Institute (EPRI) are working together to resolve issues associated with detecting an open-phase condition. This paper, using Electromagnetic Transients Program (EMTP), presents a system to detect and address the loss of one of three phases of the offsite power circuit connected to main, auxiliary and standby transformers, which is hard to be detected in the current protection system. This paper, using EMTP, presents a system to detect and address the loss of one of three phases of the offsite power circuit running to MT, UAT or SAT which is hard to be detected in the current protection system. The system presented in this paper will be useful not only for the KHNP to meet the NRC requirement, but also for nuclear power plants at home and abroad to take corrective actions to provide protection from a single phase open circuit condition for offsite power sources.

Uranium requirements for advanced fuel cycles in expanding nuclear power systems

International Nuclear Information System (INIS)

Banerjee, S.; Tamm, H.

1978-01-01

When considering advanced fuel cycle strategies in rapidly expanding nuclear power systems, equilibrium analyses do not apply. A computer simulation that accounts for system delay times and fissile inventories has been used to study the effects of different fuel cycles and different power growth rates on uranium consumption. The results show that for a given expansion rate of installed capacity, the main factors that affect resource requirements are the fissile inventory needed to introduce the advanced fuel cycle and the conversion (or breeding) ratio. In rapidly expanding systems, the effect of fissile inventory dominates, whereas in slowly expanding systems, conversion or breeding ratio dominates. Heavy-water-moderated and -cooled reactors, with their high conversion ratios, appear to be adaptable vehicles for accommodating fuel cycles covering a wide range of initial fissile inventories. They are therefore particularly suitable for conserving uranium over a wide range of nuclear power system expansion rates

Life-cycle cost assessment of seismically base-isolated structures in nuclear power plants

International Nuclear Information System (INIS)

Wang, Hao; Weng, Dagen; Lu, Xilin; Lu, Liang

2013-01-01

Highlights: • The life-cycle cost of seismic base-isolated nuclear power plants is modeled. • The change law of life-cycle cost with seismic fortification intensity is studied. • The initial cost of laminated lead rubber bearings can be expressed as the function of volume. • The initial cost of a damper can be expressed as the function of its maximum displacement and tonnage. • The use of base-isolation can greatly reduce the expected damage cost, which leads to the reduction of the life-cycle cost. -- Abstract: Evaluation of seismically base-isolated structural life-cycle cost is the key problem in performance based seismic design. A method is being introduced to address the life-cycle cost of base-isolated reinforced concrete structures in nuclear power plants. Each composition of life-cycle cost is analyzed including the initial construction cost, the isolators cost and the excepted damage cost over life-cycle of the structure. The concept of seismic intensity is being used to estimate the expected damage cost, greatly simplifying the calculation. Moreover, French Cruas nuclear power plant is employed as an example to assess its life-cycle cost, compared to the cost of non-isolated plant at the same time. The results show that the proposed method is efficient and the expected damage cost is enormously reduced because of the application of isolators, which leads to the reduction of the life-cycle cost of nuclear power plants

Politics of nuclear power and fuel cycle

International Nuclear Information System (INIS)

Uddin, R.

2007-01-01

-is likely to remain evolving depending on regional and global affairs. Opposition or support for nuclear technology is also likely to be a function of regional and global politics. In response to such pressures, IAEA is organizing a workshop of 140 countries to discuss proposals to guarantee countries' supply of nuclear fuel (September 19-21-, 2006; Vienna). Premise and Question: A single nuclear power plant in a country may be good for the prestige of the country, but such units are unlikely to make a major impact on the energy scene. Hence, in order for nuclear power to play a significant role, countries that decide to 'go nuclear,' would most likely want to diversify a significant fraction of their electricity generating capacity (and possibly heating and, in the future, hydrogen production) to nuclear, possibly requiring at least few and possibly many nuclear power plants. In order to proceed with the nuclear option, these countries would expect a certain level of long term assurance on the fuel supply. What is the kind of options that would satisfy the needs of these countries and at the same time addressing the non-proliferation concerns? Options: The options available to countries for their nuclear program can be categorized as follows. A. Fully indigenous program with complete development of power plants and fuel cycle. B. Fully or partly indigenous program for power plant development; while depending on international consortium for fuel supply and waste treatment. C. Rely on international consortia to build and operate all aspects of nuclear power plants (with local manpower). Others: A total of around fifty to seventy five countries are likely to be interested in nuclear power in the next fifty years. These can be divided in to the three groups (A-C) given above. It is likely that, with time, there will be some expectation to move to higher levels (C to B and B to A). Countries already in group A and those willing to start in group C do not pose an issue. It is

A New Dynamic Model for Nuclear Fuel Cycle System Analysis

International Nuclear Information System (INIS)

Choi, Sungyeol; Ko, Won Il

2014-01-01

The evaluation of mass flow is a complex process where numerous parameters and their complex interaction are involved. Given that many nuclear power countries have light and heavy water reactors and associated fuel cycle technologies, the mass flow analysis has to consider a dynamic transition from the open fuel cycle to other cycles over decades or a century. Although an equilibrium analysis provides insight concerning the end-states of fuel cycle transitions, it cannot answer when we need specific management options, whether the current plan can deliver these options when needed, and how fast the equilibrium can be achieved. As a pilot application, the government brought several experts together to conduct preliminary evaluations for nuclear fuel cycle options in 2010. According to Table 1, they concluded that the closed nuclear fuel cycle has long-term advantages over the open fuel cycle. However, it is still necessary to assess these options in depth and to optimize transition paths of these long-term options with advanced dynamic fuel cycle models. A dynamic simulation model for nuclear fuel cycle systems was developed and its dynamic mass flow analysis capability was validated against the results of existing models. This model can reflects a complex combination of various fuel cycle processes and reactor types, from once-through to multiple recycling, within a single nuclear fuel cycle system. For the open fuel cycle, the results of the developed model are well matched with the results of other models

Comparative analysis of methods and tools for open and closed fuel cycles modeling: MESSAGE and DESAE

International Nuclear Information System (INIS)

Andrianov, A.A.; Korovin, Yu.A.; Murogov, V.M.; Fedorova, E.V.; Fesenko, G.A.

2006-01-01

Comparative analysis of optimization and simulation methods by the example of MESSAGE and DESAE programs is carried out for nuclear power prospects and advanced fuel cycles modeling. Test calculations for open and two-component nuclear power and closed fuel cycle are performed. Auxiliary simulation-dynamic model is developed to specify MESSAGE and DESAE modeling approaches difference. The model description is given [ru

Life cycle assessment for coordination development of nuclear power and electric vehicle

International Nuclear Information System (INIS)

Liu Hong; Wang Yingrong

2010-01-01

Energy, environment and climate change have become focus political topics. In this paper, the life cycle assessment for cooperation development of nuclear power and electric vehicle were analyzed from the view of energy efficiency and pollutant emissions. The assessment results show that the pathway of nuclear power coupled with electric vehicle is better than coal electric power coupled with electric vehicle and normal gasoline coupled with internal combustion engine powered vehicle in terms of the environmental and energy characteristics. To charge the electric vehicle, instead of water power station, can safeguard the stable operation of nuclear power station. The results could provide consulted for coordination development of nuclear power, electric vehicle and brain power electric net. (authors)

Nuclear power, nuclear fuel cycle and waste management: Status and trends, 1993

International Nuclear Information System (INIS)

1993-09-01

This report was jointly prepared by the Division of Nuclear Power and the Division of Nuclear Fuel Cycle and Waste Management as part of an annual overview of both global nuclear industry activities and related IAEA programmes. This year's report focuses on activities during 1992 and the status at the end of that year. The trends in the industry are projected to 2010. Special events and highlights of IAEA activities over the past year are also presented. Refs, figs and tabs

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

International Nuclear Information System (INIS)

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

2015-01-01

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

Social awareness on nuclear fuel cycle

International Nuclear Information System (INIS)

Tanigaki, Toshihiko

2006-01-01

In the present we surveyed public opinion regarding the nuclear fuel cycle to find out about the social awareness about nuclear fuel cycle and nuclear facilities. The study revealed that people's image of nuclear power is more familiar than the image of the nuclear fuel cycle. People tend to display more recognition and concern towards nuclear power and reprocessing plants than towards other facilities. Comparatively speaking, they tend to perceive radioactive waste disposal facilities and nuclear power plants as being highly more dangerous than reprocessing plants. It is found also that with the exception of nuclear power plants don't know very much whether nuclear fuel cycle facilities are in operation in Japan or not. The results suggests that 1) the relatively mild image of the nuclear fuel cycle is the result of the interactive effect of the highly dangerous image of nuclear power plants and the less dangerous image of reprocessing plants; and 2) that the image of a given plant (nuclear power plant, reprocessing plant, radioactive waste disposal facility) is influenced by the fact of whether the name of the plant suggests the presence of danger or not. (author)

The future of nuclear power determines tasks of Ukraines nuclear fuel cycle

International Nuclear Information System (INIS)

Paton, B.Ye.; Neklyudov, I.M.; Krasnorutskij, V.S.

2013-01-01

This study provides a brief analysis on the status and development of nuclear power in the world. The present results of physical and engineering development demonstrate that in the longer term, nuclear energy as a key macro energy source is able to secure the existence and development of mankind. Based on the demand for sustainable socioeconomic existence of Ukraine as a state, there have been determined major tasks for the development of nuclear fuel cycle of Ukraine that have to be implemented at present and in the medium term

International conference on innovative technologies for nuclear fuel cycles and nuclear power. Book of extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

A wide range of issues relevant to the innovative technologies for nuclear power cycle and nuclear power were addressed. The 7 sessions of the conference were entitled: (1) no title; (2) needs, prospects and challenges for innovation; (3) evolution of technical, social, economic and political conditions; (4) panel on challenges for the deployment of innovative technologies; (5) international programmes on innovative nuclear systems; (6) innovative nuclear systems and related R and D programmes; (7) concluding panel.

Summary of nuclear power and fuel cycle data in OECD Member countries

International Nuclear Information System (INIS)

1983-03-01

A questionnaire on Electricity Generation, Nuclear Power and Fuel Cycle Data is distributed annually to OECD Member countries. Member countries were asked to provide, where available, various statistics for the previous calendar year (1982) and modified projections up to the year 2000. Tables 1 to 8 are based on the responses received and update the March 1982 issue. Tables 3 to 8 show the revised electricity, nuclear power and fuel cycle supply and demand projections in OECD Member countries to the year 2000. Figure 1 illustrates the contribution of the different fuel sources to the OECD's electricity generation from 1974 to 1982. Figure 2 shows the nuclear share of electricity generation in the OECD countries for 1982 and 1985. Figure 3 gives the fuel cycle supply and demand from the Tables 5, 6 and 8 in the OECD area

The Application of Supercritical CO{sub 2} Power Cycle to Various Nuclear Systems

Energy Technology Data Exchange (ETDEWEB)

Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of)

2015-10-15

The main reason why the S-CO{sub 2} Brayton cycle has these advantages is that the compressor operates near the critical point of CO{sub 2} (30.98 .deg. C, 7.38MPa) to reduce the compression work significantly compared to the other Brayton cycles. In this paper, various applications of supercritical CO{sub 2} power cycle to nuclear systems will be presented and summarized. The S-CO{sub 2} cycle can achieve relatively high efficiency within the mild turbine inlet temperature range (450 - 850 .deg. C) compared with other power conversion systems. The main benefit of the S-CO{sub 2} cycle is the small size of the overall system and its application includes not only the next generation nuclear reactors but also conventional water-cooled reactors too. Various layouts were compared and the recompression cycle shows the best efficiency. The layout is suitable for application to advanced nuclear reactor systems. To evaluate the S-CO{sub 2} cycle performance, various countries constructed and demonstrated S-CO{sub 2} integral system test loops and similar research works are ongoing in Korea as well. However, to evaluate the commercial S-CO{sub 2} power systems, development of a large scale (> 10 MW) prototype S-CO{sub 2} system is necessary.

Nuclear power. Nuclear fuel cycle and waste management. 1990-2002. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2002-02-01

This document lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Power, Nuclear Fuel Cycle and Waste Management, issued during the period 1990-2002. It gives a short abstract of these publications along with contents and their costs

Nuclear power economic database

International Nuclear Information System (INIS)

Ding Xiaoming; Li Lin; Zhao Shiping

1996-01-01

Nuclear power economic database (NPEDB), based on ORACLE V6.0, consists of three parts, i.e., economic data base of nuclear power station, economic data base of nuclear fuel cycle and economic database of nuclear power planning and nuclear environment. Economic database of nuclear power station includes data of general economics, technique, capital cost and benefit, etc. Economic database of nuclear fuel cycle includes data of technique and nuclear fuel price. Economic database of nuclear power planning and nuclear environment includes data of energy history, forecast, energy balance, electric power and energy facilities

Nuclear design report for Yonggwang nuclear power plant unit 2 cycle 7

International Nuclear Information System (INIS)

Zee, Sung Kyun; Choi, Gyoo Hwan; Lee, Ki Bog; Park, Sang Yoon

1993-02-01

This report presents nuclear design calculations for Cycle 7 of Yonggwang Unit 2. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 64 KOFA's enriched by nominally 3.70 w/o U235. Among the KOFA's, 40 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 7 amounts to 367 EFPD corresponding to a cycle burnup of 14770 MWD/MTU. (Author)

Nuclear power and the nuclear fuel cycle

International Nuclear Information System (INIS)

1988-06-01

The percentage of electricity generated by nuclear energy in each of the 26 countries that operated nuclear power plants in 1987 is given. The current policy and programs of some of these countries is described. News concerning uranium mining, enrichment, reprocessing and waste management is also included. Data in the form of a generalized status summary for all power reactors (> 30 MWEN) prepared from the nuclear power reactor data files of ANSTO is shown

Spallator and APEX nuclear fuel cycle: a new option for nuclear power

International Nuclear Information System (INIS)

Steinberg, M.

1982-01-01

A new nuclear fuel cycle is described which provides a long term supply of nuclear fuel for the thermal LWR nuclear power reactors and eliminates the need for long-term storage of radioactive waste. Fissile fuel is produced by the Spallator which depends on the production of spallation neutrons by the interaction of high-energy (1 to 2 GeV) protons on a heavy-metal target. The neutrons are absorbed in a surrounding natural-uranium or thorium blanket in which fissile Pu-239 to U-233 is produced. Advances in linear accelerator technology makes it possible to design and construct a high-beam-current continuous-wave proton linac for production purposes. The target is similar to a sub-critical reactor and produces heat which is converted to electricity for supplying the linac. The Spallator is a self-sufficient fuel producer, which can compete with the fast breeder. The APEX fuel cycle depends on recycling the transuranics and long-lived fission products while extracting the stable and short-lived fission products when reprocessing the fuel. Transmutation and decay within the fuel cycle and decay of short-lived fission products external to the fuel cycle eliminates the need for long-term geological age shortage of fission-product waste

Spallator and APEX nuclear fuel cycle: a new option for nuclear power

Energy Technology Data Exchange (ETDEWEB)

Steinberg, M.

1982-01-01

A new nuclear fuel cycle is described which provides a long term supply of nuclear fuel for the thermal LWR nuclear power reactors and eliminates the need for long-term storage of radioactive waste. Fissile fuel is produced by the Spallator which depends on the production of spallation neutrons by the interaction of high-energy (1 to 2 GeV) protons on a heavy-metal target. The neutrons are absorbed in a surrounding natural-uranium or thorium blanket in which fissile Pu-239 to U-233 is produced. Advances in linear accelerator technology makes it possible to design and construct a high-beam-current continuous-wave proton linac for production purposes. The target is similar to a sub-critical reactor and produces heat which is converted to electricity for supplying the linac. The Spallator is a self-sufficient fuel producer, which can compete with the fast breeder. The APEX fuel cycle depends on recycling the transuranics and long-lived fission products while extracting the stable and short-lived fission products when reprocessing the fuel. Transmutation and decay within the fuel cycle and decay of short-lived fission products external to the fuel cycle eliminates the need for long-term geological age shortage of fission-product waste.

Summary of nuclear power and fuel cycle data in OECD member countries

International Nuclear Information System (INIS)

1986-04-01

A questionnaire on Electricity Generation, Nuclear Power and Fuel Cycle Data is distributed annually to OECD Member Countries. In the questionnaire of January 1986, countries were asked to provide historical data for 1984 and 1985 and most likely projections up to the year 2005. The replies to the questionnaire are presented in this Summary. Not all countries have revised or made new projections since the April 1985 issue. Too few countries were able to provide projections beyond 2000 to include data for 2005 in this year's Summary. Data for 1985 are in some cases provisional. Where no data were available the Secretariat made estimates, based on information of IEA, IAEA, the previous Brown Book, OECD/IEA Energy Statistics and other sources. The electricity generation and production data for fuel cycle services refer to those facilities located within the country, and thus exclude imports. The fuel cycle requirements, however, refer to the amounts of fuel cycle services necessary for national nuclear power programmes. The Addendum contains an analysis of the present and past projections for OECD nuclear capacity to 2000

Nuclear design report for Yonggwang nuclear power plant unit 4 cycle 2

International Nuclear Information System (INIS)

Park, Chan Oh; Park, Sang Yoon; Yoo, Choon Sung; Ryu, Hyo Sang; Park, Jin Ha; Cho, Young Chul; Song, Jae Woong; Lee Chung Chan.

1996-10-01

This report presents nuclear design calculations for Cycle 2 of Yonggwang Unit 4. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths, and operational limits. In addition, the report contains necessary data for the startup tests and for the assurance of shutdown margin during reactor operation. The reload core consists of 48 fresh KSFAs. Among the 48 fresh KSFAs, 32 fuel assemblies contain burnable poison rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 2 amounts to 275 EFPD corresponding to a cycle burnup of 10,100 MWD/MTU. (author). 31 tabs., 92 figs., 7 refs

Nuclear design report for Ulchin nuclear power plant unit 1, cycle 7

Energy Technology Data Exchange (ETDEWEB)

Kim, Yong Rae; Park, Yong soo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-04-01

This report presents nuclear design calculations for Cycle 7 of Ulchin Unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 56 KOFA`s enriched by nominally 4.00 w/o U{sub 235}. Among the KOFA`s 36 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 7 amounts to 355 EFPD corresponding to a cycle burnup of 14280 MWD/MTU. (Author) 8 refs., 55 figs., 21 tabs.

Nuclear design report for Kori nuclear power plant unit 4 cycle 8

Energy Technology Data Exchange (ETDEWEB)

Zee, Sung Kyoon; Jung, Yil Sub; Kim, Si Yung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1993-07-01

This report presents nuclear design calculations for cycle 8 of Kori unit 4. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 76 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s 48 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 8 amounts to 421 EFPD corresponding to a cycle burnup of 16950 MWD/MTU. (Author) 8 refs., 55 figs., 17 tabs.

Nuclear design report for Kori nuclear power plant unit 1, cycle 13

Energy Technology Data Exchange (ETDEWEB)

Zee, Sung Kyun; Moon, Bok Ja; Cho, Byeong Ho; Jung, Yil Sup [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1993-04-01

This report presents nuclear design calculations for cycle 13 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 44 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 16 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 13 amounts to 355 EFPD corresponding to a cycle burnup of 13240 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs.

Nuclear design report for Yonggwang nuclear power plant unit 1 cycle 9

Energy Technology Data Exchange (ETDEWEB)

Cho, Young chul; Kim, Jae Hak; Song, Jae Woong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-03-01

This report presents nuclear design calculations for Cycle 6 of Yonggwng Unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 76 KOFA`s enriched by nominally 4.00 w/o U{sub 235}. Among the KOFA`s, 60 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 9 amounts to 434 EFPD corresponding to a cycle burnup of 17470 MWD/MTU. (Author) 8 refs., 55 figs., 19 tabs.

Nuclear design report for Ulchin nuclear power plant unit 1, cycle 6

Energy Technology Data Exchange (ETDEWEB)

Zee, Sung Kyun; Kim, Yong Rae; Park, Yong Soo; Cho, Byeong Ho; Lee, Sang Keun; Ahn, Dawk Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1993-12-01

This report presents nuclear design calculations for cycle 6 of Ulchin unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 64 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 32 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 6 amounts to 369 EFPD corresponding to a cycle burnup of 14850 MWD/MTU. (Author) 8 refs., 55 figs., 17 tabs.

Nuclear design report for Ulchin nuclear power plant unit 2, cycle 6

Energy Technology Data Exchange (ETDEWEB)

Park, Chan Oh; Park, Jin Ha; Kim, Yong Rae; Park, Sang Yoon; Lee, Jong Chul; Baik, Joo Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-08-01

This report presents nuclear design calculations for cycle 6 of Ulchin unit 2. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 64 KOFA`s enriched by nominally 3.80 w/o U{sub 235}. Among the KOFA`s, 36 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 6 amounts to 388 EFPD corresponding to a cycle burnup of 15610 MWD/MTU. (Author) 8 refs., 55 figs., 17 tabs.

Nuclear design report for Yonggwang nuclear power plant unit 1, cycle 8

International Nuclear Information System (INIS)

Cho, Young Chul; Kim, Jae Hak; Park, Sang Yoon; Zee, Sung Kyun; Lee, Sang Keun; Ahn, Dawk Hwan

1993-10-01

This report presents nuclear design calculations for cycle 8 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 76 KOFA's enriched by nominally 3.70 w/o U 235 . Among the KOFA's, 56 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 8 amounts to 447 EFPD corresponding to a cycle burnup of 18020 MWD/MTU. (Author) 8 refs., 39 figs., 17 tabs

Nuclear design report for Ulchin nuclear power plant unit 2 cycle 5

International Nuclear Information System (INIS)

Park, Jin Ha; Park, Yong Soo; Cho, Byeong Ho; Zee, Sung Kyun; Lee, Sang Keun; Ahn, Dawk Hwan

1993-09-01

This report presents nuclear design calculations for cycle 5 of Ulchin unit it 2. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 48 KOFA's enriched by nominally 3.50 w/o U 235 . Among the KOFA's, 20 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 5 amounts to 293 EFPD corresponding to a cycle burnup of 11780 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs

Nuclear design report for Yonggwang nuclear power plant unit 1, cycle 8

Energy Technology Data Exchange (ETDEWEB)

Cho, Young Chul; Kim, Jae Hak; Park, Sang Yoon; Zee, Sung Kyun; Lee, Sang Keun; Ahn, Dawk Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1993-10-01

This report presents nuclear design calculations for cycle 8 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 76 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 56 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 8 amounts to 447 EFPD corresponding to a cycle burnup of 18020 MWD/MTU. (Author) 8 refs., 39 figs., 17 tabs.

11-th International conference Nuclear power safety and nuclear education - 2009. Abstracts. Part 1. Session: Safety of nuclear technology; Innovative nuclear systems and fuel cycle; Nuclear knowledge management

International Nuclear Information System (INIS)

2009-01-01

The book includes abstracts of the 11-th International conference Nuclear power safety and nuclear education - 2009 (29 Sep - 2 Oct, 2009, Obninsk). Problems of safety of nuclear technology are discussed, innovative nuclear systems and fuel cycles are treated. Abstracts on professional education for nuclear power and industry are presented. Nuclear knowledge management are discussed

Nuclear design report for Yonggwang nuclear power plant unit 3 cycle 2

Energy Technology Data Exchange (ETDEWEB)

Zee, Sung Kyun; Song, Jae Woong; Song, Jae Seung; Park, Sang Yoon; Yoo, Choon Sung; Baek, Byung Chan; Ryu, Hyo Sang; Park, Jin Ha; Cho, Young Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-01-01

This report presents nuclear design calculations for Cycle 2 of Yonggwang Unit 3. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths, and operational limits. In addition, the report contains necessary data for the startup tests and for the assurance of shutdown margin during reactor operation. The reload core consists of 48 fresh Korean Standard Fuel Assemblies (KSFAs)and 129 burned KSFAs. Among the 48 fresh KSFAs, 32 fuel assemblies contain burnable poison rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 2 amounts to 276 EFPD corresponding to a cycle burnup of 10,160 MWD/MTU. 95 figs., 31 tabs., 7 refs. (Author) .new.

Nuclear design report for Ulchin nuclear power plant unit 2 cycle 5

Energy Technology Data Exchange (ETDEWEB)

Park, Jin Ha; Park, Yong Soo; Cho, Byeong Ho; Zee, Sung Kyun; Lee, Sang Keun; Ahn, Dawk Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1993-09-01

This report presents nuclear design calculations for cycle 5 of Ulchin unit it 2. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 48 KOFA`s enriched by nominally 3.50 w/o U{sub 235}. Among the KOFA`s, 20 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 5 amounts to 293 EFPD corresponding to a cycle burnup of 11780 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs.

Development of nuclear fuel cycle technologies - bases of long-term provision of fuel and environmental safety of nuclear power

International Nuclear Information System (INIS)

Solonin, M.I.; Polyakov, A.S.; Zakharkin, B.S.; Smelov, V.S.; Nenarokomov, E.A.; Mukhin, I.V.

2000-01-01

To-day nuclear power is one of the options, however, to-morrow it may become the main source of the energy, thus, providing for the stable economic development for the long time to come. The availability of the large-scale nuclear power in the foreseeable future is governed by not only the safe operation of nuclear power plants (NPP) but also by the environmentally safe management of spent nuclear fuel, radioactive waste conditioning and long-term storage. More emphasis is to be placed to the closing of the fuel cycle in view of substantial quantities of spent nuclear fuel arisings. The once-through fuel cycle that is cost effective at the moment cannot be considered to be environmentally safe even for the middle term since the substantial build-up of spent nuclear fuel containing thousands of tons Pu will require the resolution of the safe management problem in the nearest future and is absolutely unjustified in terms of moral ethics as a transfer of the responsibility to future generations. The minimization of radioactive waste arisings and its radioactivity is only feasible with the closed fuel cycle put into practice and some actinides and long-lived fission radionuclides burnt out. The key issues in providing the environmentally safe fuel cycle are efficient processes of producing fuel for NPP, radionuclide after-burning included, a long-term spent nuclear fuel storage and reprocessing as well as radioactive waste management. The paper deals with the problems inherent in producing fuel for NPP with a view for the closed fuel cycle. Also discussed are options of the fuel cycle, its effectiveness and environmental safety with improvements in technologies of spent nuclear fuel reprocessing and long-lived radionuclide partitioning. (authors)

Development of nuclear fuel cycle technologies - bases of long-term provision of fuel and environmental safety of nuclear power

Energy Technology Data Exchange (ETDEWEB)

Solonin, M I; Polyakov, A S; Zakharkin, B S; Smelov, V S; Nenarokomov, E A; Mukhin, I V [SSC, RF, A.A. Bochvar ALL-Russia Research Institute of Inorganic Materials, Moscow (Russian Federation)

2000-07-01

To-day nuclear power is one of the options, however, to-morrow it may become the main source of the energy, thus, providing for the stable economic development for the long time to come. The availability of the large-scale nuclear power in the foreseeable future is governed by not only the safe operation of nuclear power plants (NPP) but also by the environmentally safe management of spent nuclear fuel, radioactive waste conditioning and long-term storage. More emphasis is to be placed to the closing of the fuel cycle in view of substantial quantities of spent nuclear fuel arisings. The once-through fuel cycle that is cost effective at the moment cannot be considered to be environmentally safe even for the middle term since the substantial build-up of spent nuclear fuel containing thousands of tons Pu will require the resolution of the safe management problem in the nearest future and is absolutely unjustified in terms of moral ethics as a transfer of the responsibility to future generations. The minimization of radioactive waste arisings and its radioactivity is only feasible with the closed fuel cycle put into practice and some actinides and long-lived fission radionuclides burnt out. The key issues in providing the environmentally safe fuel cycle are efficient processes of producing fuel for NPP, radionuclide after-burning included, a long-term spent nuclear fuel storage and reprocessing as well as radioactive waste management. The paper deals with the problems inherent in producing fuel for NPP with a view for the closed fuel cycle. Also discussed are options of the fuel cycle, its effectiveness and environmental safety with improvements in technologies of spent nuclear fuel reprocessing and long-lived radionuclide partitioning. (authors)

Electricity, nuclear power and fuel cycle in OECD countries

International Nuclear Information System (INIS)

1988-01-01

A questionnaire on Electricity Generation, Nuclear Power and Fuel Cycle Data is distributed annually to OECD Member Countries. In the questionnaire of January 1988, countries were asked to provide data for 1986 and 1987 and most likely projections up to the year 2005. The replies to the questionnaire (or estimates for unavailable data) are presented in this Booklet. Data for 1987 are provisional for several countries. The data on electricity generation and electric capacity are presented to the year 2005, and the data on fuel cycle services to the year 2000. The Addendum contains an analysis of the present and past projections for installed nuclear capacity to 2000. It shows the total capacity of those plants connected to the grid, under construction and firmly planned to be in operation in 2000 as 282 GWe. The new projection of 300 GWe is above this estimate, indicating that some countries are considering further expansion of their nuclear capacities within this time-frame [fr

Nuclear Power, Nuclear Fuel Cycle and Sustainable Development in a Changing World

International Nuclear Information System (INIS)

Arakawa, Yoshitaka

2000-01-01

Important changes concerning nuclear energy are coming to the fore, such as economic competitiveness compared to other energy resources, requirement for severe measures to mitigate man-made greenhouse gas (GHG) emission, due to the rise of energy demand in Central and Eastern Europe and Asia and to the greater public concern with respect to the nuclear safety, particularly related to spent fuel and radioactive waste disposal. Global safety culture, as well as well focused nuclear research and development programs for safer and more efficient nuclear technology manifest themselves in a stronger and effective way. Information and data on nuclear technology and safety are disseminated to the public in timely, accurate and understandable fashion. Nuclear power is an important contributor to the world's electricity needs. In 1999, it supplied roughly one sixth of global electricity. The largest regional percentage of electricity generated through nuclear power last year was in western Europe (30%). The nuclear power shares in France, Belgium and Sweden were 75%, 58% and 47%, respectively. In North America, the nuclear share was 20% for the USA and 12% for Canada. In Asia, the highest figures were 43% for the Republic of Korea and 36% for Japan. In 1998, twenty-three nations produced uranium of which, the ten biggest producers (Australia, Canada, Kazakhstan, Namibia, Niger, the Russian Federation, South Africa, Ukraine, USA and Uzbekistan) supplied over 90% of the world's output. In 1998, world uranium production provided only about 59% of world reactor requirements. In OECD countries, the 1998 production could only satisfy 39% of the demand. The rest of the requirements were satisfied by secondary sources including civilian and military stockpiles, uranium reprocessing and re-enrichment of depleted uranium. With regard to the nuclear fuel industry, an increase in fuel burnup, higher thermal rates, longer fuel cycle and the use of mixed uranium-plutonium oxide (MOX

Alternative fuel cycle options: performance characteristics and impact on nuclear power growth potential

International Nuclear Information System (INIS)

Chang, Y.I.; Till, C.E.; Rudolph, R.R.; Deen, J.R.; King, M.J.

1977-09-01

The fuel utilization characteristics for LWR, SSCR, CANDU and LMFBR reactor concepts are quantified for various fuel cycle options, including once-through cycles, thorium cycles, and denatured cycles. The implications of various alternative reactor deployment strategies on the long-term nuclear power growth potential are then quantified in terms of the maximum nuclear capacity that can be achieved and the growth pattern over time, subject to the constraint of a fixed uranium-resource base. The overall objective of this study is to shed light on any large differences in the long-term potential that exist between various alternative reactor/fuel cycle deployment strategies

Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system

International Nuclear Information System (INIS)

Gurin, Andrey V.; Alekseev, P.N.

2017-01-01

This paper presents a study of scenarios of transition to a closed fuel cycle in the system of nuclear power, built basing on resource availability requirements at the stage of full life-cycle reactors. Conventionally, there are three main scenarios for the development of nuclear energy: with VVER reactors operating in an open fuel cycle; with VVER reactors operating in a closed fuel cycle; and co-operating VVER and BN, operating in a closed fuel cycle. For the considered scenarios, a quantitative estimation of change in time of material balances were performed, including spent fuel balance, balance of plutonium, reprocessed and depleted uranium, radioactive waste, and the analysis of the fuel component of the cost of electricity.

Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system

Energy Technology Data Exchange (ETDEWEB)

Gurin, Andrey V. [National Research Centre ' ' Kurchatov Institute' ' , Moscow (Russian Federation); Alekseev, P.N.

2017-09-15

This paper presents a study of scenarios of transition to a closed fuel cycle in the system of nuclear power, built basing on resource availability requirements at the stage of full life-cycle reactors. Conventionally, there are three main scenarios for the development of nuclear energy: with VVER reactors operating in an open fuel cycle; with VVER reactors operating in a closed fuel cycle; and co-operating VVER and BN, operating in a closed fuel cycle. For the considered scenarios, a quantitative estimation of change in time of material balances were performed, including spent fuel balance, balance of plutonium, reprocessed and depleted uranium, radioactive waste, and the analysis of the fuel component of the cost of electricity.

Electricity, nuclear power and fuel cycle in OECD countries, main data 1987

International Nuclear Information System (INIS)

1987-01-01

A questionnaire on Electricity Generation. Nuclear Power and Fuel Cycle Data is distributed annually to OECD Member Countries. In the questionnaire of January 1987, countries were asked to provide historical data for 1985 and 1986 and most likely projections up to the year 2005. The replies to the questionnaire or the results of the discussions between national correspondents and the Secretariat are presented in this Booklet. The Secretariat has, in some cases, referred to IEA's electricity-related data and IAEA's nuclear plant data. Where data were still unavailable the Secretariat made estimates based on information from other sources. Data for 1986 are provisional for several countries. The data on electricity generation and electric capacity are presented to the year 2005, and the data on fuel cycle services to the year 2000. The installed nuclear capacity of the OECD countries for the year 2000 is estimated at 340 GWe, a 25 GWe reduction from the estimate in the 1986 Booklet. This reduction is mainly due to revised lower projections of electricity demand. The Addendum contains an analysis of the present and past projections for installed nuclear capacity to 2000. It shows the total capacity of those plants connected to the grid, under construction and firmly planned to be in operation in 2000 as 294 GWe. The new projection of 340 GWe is well above this estimate, indicating that some countries are still planning to expand their nuclear capacities. In only one country does it appear that planned expansion has been affected specifically by the Chernobyl accident. The electricity generation and production data for fuel cycle services refer to those facilities located within the country, and thus exclude imports. The fuel cycle requirements, however, refer to the amounts of fuel cycle materials and services necessary for national nuclear power programmes

Nuclear power. Volume 1. Nuclear power plant design

International Nuclear Information System (INIS)

Pedersen, E.S.

1978-01-01

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

IAEA activities on nuclear fuel cycle 1997

Energy Technology Data Exchange (ETDEWEB)

Oi, N [International Atomic Energy Agency, Vienna (Austria). Nuclear Fuel Cycle and Materials Section

1997-12-01

The presentation discussing the IAEA activities on nuclear fuel cycle reviews the following issues: organizational charts of IAEA, division of nuclear power and the fuel cycle, nuclear fuel cycle and materials section; 1997 budget estimates; budget trends; the nuclear fuel cycle programme.

IAEA activities on nuclear fuel cycle 1997

International Nuclear Information System (INIS)

Oi, N.

1997-01-01

The presentation discussing the IAEA activities on nuclear fuel cycle reviews the following issues: organizational charts of IAEA, division of nuclear power and the fuel cycle, nuclear fuel cycle and materials section; 1997 budget estimates; budget trends; the nuclear fuel cycle programme

'Crud' detection and evaluation during the Embalse nuclear power plant's thermal cycle for powers of 100%

International Nuclear Information System (INIS)

Fernandez, A.; Rosales, A.H.; Mura, V.R.; Sentupery, C.; Rascon, H.

1987-01-01

This paper describes the 'crud' measurements performed during the Embalse nuclear power plant's thermal cycle for a power of 100% (645 MWe) under different purification conditions. The aim of this work is to optimize the four steam generators' tube plate cleaning in function of the sweeping produced by their purification. (Author)

Optimization in the scale of nuclear power generation and the economy of nuclear power

International Nuclear Information System (INIS)

Suzuki, Toshiharu

1983-01-01

In the not too distant future, the economy of nuclear power will have to be restudied. Various conditions and circumstances supporting this economy of nuclear power tend to change, such as the decrease in power demand and supply, the diversification in base load supply sources, etc. The fragility in the economic advantage of nuclear power may thus be revealed. In the above connection, on the basis of the future outlook of the scale of nuclear power generation, that is, the further reduction of the current nuclear power program, and of the corresponding supply and demand of nuclear fuel cycle quantities, the aspect of the economic advantage of nuclear power was examined, for the purpose of optimizing the future scale of nuclear power generation (the downward revision of the scale, the establishment of the schedule of nuclear fuel cycle the stagnation of power demand and nuclear power generation costs). (Mori, K.)

Thorium fuel for light water reactors - reducing proliferation potential of nuclear power fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Galperin, A; Radkowski, A [Ben-Gurion Univ. of the Negev, Beersheba (Israel)

1996-12-01

The proliferation potential of the light water reactor fuel cycle may be significantly reduced by utilization of thorium as a fertile component of the nuclear fuel. The main challenge of Th utilization is to design a core and a fuel cycle, which would be proliferation-resistant and economically feasible. This challenge is met by the Radkowsky Thorium Reactor (RTR) concept. So far the concept has been applied to a Russian design of a 1,000 MWe pressurized water reactor, known as a WWER-1000, and designated as VVERT. The following are the main results of the preliminary reference design: * The amount of Pu contained in the RTR spent fuel stockpile is reduced by 80% in comparison with a VVER of a current design. * The isotopic composition of the RTR-Pu greatly increases the probability of pre-initiation and yield degradation of a nuclear explosion. An extremely large Pu-238 content causes correspondingly large heat emission, which would complicate the design of an explosive device based on RTR-Pu. The economic incentive to reprocess and reuse the fissile component of the RTR spent fuel is decreased. The once-through cycle is economically optimal for the RTR core and cycle. To summarize all the items above: the replacement of a standard (U-based) fuel for nuclear reactors of current generation by the RTR fuel will provide an inherent barrier for nuclear weapon proliferation. This inherent barrier, in combination with existing safeguard measures and procedures is adequate to unambiguously disassociate civilian nuclear power from military nuclear power. * The RTR concept is applied to existing power plants to assure its economic feasibility. Reductions in waste disposal requirements, as well as in natural U and fabrication expenses, as compared to a standard WWER fuel, provide approximately 20% reduction in fuel cycle (authors).

A novel nuclear combined power and cooling system integrating high temperature gas-cooled reactor with ammonia–water cycle

International Nuclear Information System (INIS)

Luo, Chending; Zhao, Fuqiang; Zhang, Na

2014-01-01

Highlights: • We propose a novel nuclear ammonia–water power and cooling cogeneration system. • The high temperature reactor is inherently safe, with exhaust heat fully recovered. • The thermal performances are improved compared with nuclear combined cycle. • The base case attains an energy efficiency of 69.9% and exergy efficiency of 72.5%. • Energy conservation and emission reduction are achieved in this cogeneration way. - Abstract: A nuclear ammonia–water power and refrigeration cogeneration system (NAPR) has been proposed and analyzed in this paper. It consists of a closed high temperature gas-cooled reactor (HTGR) topping Brayton cycle and a modified ammonia water power/refrigeration combined bottoming cycle (APR). The HTGR is an inherently safe reactor, and thus could be stable, flexible and suitable for various energy supply situation, and its exhaust heat is fully recovered by the mixture of ammonia and water in the bottoming cycle. To reduce exergy losses and enhance outputs, the ammonia concentrations of the bottoming cycle working fluid are optimized in both power and refrigeration processes. With the HTGR of 200 MW thermal capacity and 900 °C/70 bar reactor-core-outlet helium, the system achieves 88.8 MW net electrical output and 9.27 MW refrigeration capacity, and also attains an energy efficiency of 69.9% and exergy efficiency of 72.5%, which are higher by 5.3%-points and 2.6%-points as compared with the nuclear combined cycle (NCC, like a conventional gas/steam power-only combined cycle while the topping cycle is a closed HTGR Brayton cycle) with the same nuclear energy input. Compared with conventional separate power and refrigeration generation systems, the fossil fuel saving (based on CH 4 ) and CO 2 emission reduction of base-case NAPR could reach ∼9.66 × 10 4 t/y and ∼26.6 × 10 4 t/y, respectively. The system integration accomplishes the safe and high-efficiency utilization of nuclear energy by power and refrigeration

Analysis of environmental impact phase in the life cycle of a nuclear power plant

International Nuclear Information System (INIS)

Hernandez del M, C.

2015-01-01

The life-cycle analysis covers the environmental aspects of a product throughout its life cycle. The focus of this study was to apply a methodology of life-cycle analysis for the environmental impact assessment of a nuclear power plant by analyzing international standards ISO 14040 and 14044. The methodology of life-cycle analysis established by the ISO 14044 standard was analyzed, as well as the different impact assessment methodologies of life cycle in order to choose the most appropriate for a nuclear power plant; various tools for the life-cycle analysis were also evaluated, as is the use of software and the use of databases to feed the life cycle inventory. The functional unit chosen was 1 KWh of electricity, the scope of analysis ranging from the construction and maintenance, disposal of spent fuel to the decommissioning of the plant, the manufacturing steps of the fuel were excluded because in Mexico is not done this stage. For environmental impact assessment was chosen the Recipe methodology which evaluates up to 18 impact categories depending on the project. In the case of a nuclear power plant were considered only categories of depletion of the ozone layer, climate change, ionizing radiation and formation of particulate matter. The different tools for life-cycle analysis as the methodologies of impact assessment of life cycle, different databases or use of software have been taken according to the modeling of environmental sensitivities of different regions, because in Mexico the methodology for life-cycle analysis has not been studied and still do not have all the tools necessary for the evaluation, so the uncertainty of the data supplied and results could be higher. (Author)

Nuclear power in Asia

Energy Technology Data Exchange (ETDEWEB)

Hagen, Ronald E.

1998-08-01

Contains Executive Summary and Chapters on: Nuclear Energy in the Asian context; Types of nuclear power reactors used in Asia; A survey of nuclear power by country; The economics of nuclear power; Fuels, fuel cycles and reprocessing; Environmental issues and waste disposal; The weapons issues and nuclear power; Conclusions. (Author)

The development of an integrated nuclear fuel-cycle industry to meet the needs of the Italian nuclear power programme

International Nuclear Information System (INIS)

Angelini, A.M.; Badolato, G.; Clementel, E.

1977-01-01

The paper summarizes the Italian nuclear power station programme, recently approved by the Government, and illustrates the main reasons for the programme, which are in line with those presented at the Geneva Conference in 1971, and which lead to the consideration that nuclear energy is the main source for meeting practically all new electric power requirements in Italy. The implementation of this programme involves considerable nuclear fuel-cycle services, ranging from uranium supply to waste disposal. The industrial strategy to meet these needs is discussed. Technical and economic factors affecting such strategy, both for the fuel cycle as a whole and for its individual phases, are considered. Attention is focused on problems typical of the Italian situation and on various ways of solving them. A prominent feature of the Italian situation is the lack of sizeable domestic uranium resources, which makes it even more important to try, by local industrial efforts, to cover the phases of the cycle subsequent to uranium supply, so as to increase as much as possible the fraction of added value produced inside the country. The present status of the Italian nuclear fuel-cycle industry is reviewed in detail, and its capability of supporting the nuclear programme is analysed. Future development plans are discussed, taking into account the possibility of European co-operation. While the focus is on short- and medium-term programmes, the long-term nuclear programmes are discussed, such as those based on fast breeders, and stress is laid on the need to build up as quickly as possible a strong nuclear fuel-cycle industry. (author)

Several perspectives on water-chemical cycles for nuclear power stations equipped with type VVER and RBMK reactors

International Nuclear Information System (INIS)

Mamet, A.P.; Mamet, V.A.; Pashevich, V.I.; Nazarenko, P.N.

1982-01-01

Water-chemical cycles for loops I and II of VVER reactors are discussed. These cycles are mixed ammonia-sodium with a variable concentration of boric acid and ammonia hydrazine with a pH factor of 9.1 +/- 0.1. New water-chemical cycles are considered for use in both existing and new nuclear power plants. Application of these new water-chemical cycles showed produce a significant improvement in operating conditions of nuclear power plants. Upon accumulation of sufficient operating experience with these cycles, it should be possible to raise the issue of revising applicable standard documentation

Analysis of floor technology scheme in open-top construction of nuclear power project

International Nuclear Information System (INIS)

Zhang Shuxia; Lu Qinwu; Han Xiaoping

2014-01-01

Open-top construction is general technology in Ⅲ generation in nuclear power project. Because traditional floor structure and its form board upholding doesn't meet open-top construction, four floor scheme are presented, whose characters, advantages and disadvantages, and its application are summarized. The research results will help to the application of open-top construction. (authors)

Nuclear power

International Nuclear Information System (INIS)

Abd Khalik Wood

2005-01-01

This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

Direct cycle type nuclear power plant

International Nuclear Information System (INIS)

Tagawa, Hisato; Ibe, Hidefumi.

1990-01-01

In a direct cycle type nuclear power plant such as BWR type reactor, since oxygen atoms in reactor water are actuvated by neutron irradiation in the reactor core, carry over of the thus formed radioactive nitrogen atoms causes increase in the dosage in a turbine system. Since 16 N accompanies in the main steams in the chemical form of 16 NO, it can not effectively be removed in a nitrogen removing device. In view of the above, hydrogen atom concentration is reduced by adding metals having high reaction with hydrogen atoms, for example, silver ions, chromium ions, or ruthenium ions are added to reactor water. Then, equilibrium concentration of 16 NO in water is reduced by suppressing the reaction: 16 NO 2 + H → 16 NO + OH. (T.M.)

Nuclear power performance and safety. V.5. Nuclear fuel cycle

International Nuclear Information System (INIS)

1988-01-01

The International Conference on Nuclear Power Performance and Safety, organized by the International Atomic Energy Agency, was held at the Austria Centre Vienna (ACV) in Vienna, Austria, from 28 September to 2 October 1987. The objective of the Conference was to promote an exchange of worldwide information on the current trends in the performance and safety of nuclear power and its fuel cycle, and to take a forward look at the expectations and objectives for the 1990s. Policy decisions for waste management have already been taken in many countries and the 1990s should be a period of demonstration and implementation of these policies. As ilustrated by data presented from a number of countries, many years of experience in radioactive waste management have been achieved and the technology exists to implement the national plans and policies that have been developed. The establishment of criteria, the development of safety performance methodology and site investigation work are key activities essential to the successful selection, characterization and construction of geological repositories for the final disposal of radioactive waste. Considerable work has been done in these areas over the last ten years and will continue into the 1990s. However, countries that are considering geological disposal for high level waste now recognize the need for relating the technical aspects to public understanding and acceptance of the concept and decision making activities. The real challenge for the 1990s in waste disposal will be successfully to integrate technological activities within a process which responds to institutional and public concern. Volume 5 of the Proceedings comprehends the contributions on waste management in the 1990s. Decontamination and decommissioning, waste management, treatment and disposal, nuclear fuel cycle - present and future. Enrichment services and advanced reactor fuels, improvements in reactor fuel utilization and performance, spent fuel management

Nuclear design report for Kori nuclear power plant unit 1, cycle 14

Energy Technology Data Exchange (ETDEWEB)

Park, Chan Oh; Kim, Joo Young; Park, Sang Yoon; Song, Jae Woong; Lee, Chong Chul; Baik, Joo Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-06-01

This report presents nuclear design calculations for cycle 14 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 44 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 16 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 14 amounts to 366 EFPD corresponding to a cycle burnup of 13680 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs. nozzle by vortex formation during mid-loop operation condition are experimentally investigated. The critical submergence is determined for various types of suction nozzle, and the measurements of velocity distribution are performed in the flow fields near the t-shaped suction nozzle. (Author) 11 refs., 41 figs., 13 tabs.

Romanian nuclear fuel cycle development

International Nuclear Information System (INIS)

Rapeanu, S.N.; Comsa, Olivia

1998-01-01

Romanian decision to introduce nuclear power was based on the evaluation of electricity demand and supply as well as a domestic resources assessment. The option was the introduction of CANDU-PHWR through a license agreement with AECL Canada. The major factors in this choice have been the need of diversifying the energy resources, the improvement the national industry and the independence of foreign suppliers. Romanian Nuclear Power Program envisaged a large national participation in Cernavoda NPP completion, in the development of nuclear fuel cycle facilities and horizontal industry, in R and D and human resources. As consequence, important support was being given to development of industries involved in Nuclear Fuel Cycle and manufacturing of equipment and nuclear materials based on technology transfer, implementation of advanced design execution standards, QA procedures and current nuclear safety requirements at international level. Unit 1 of the first Romanian nuclear power plant, Cernavoda NPP with a final profile 5x700 Mw e, is now in operation and its production represents 10% of all national electricity production. There were also developed all stages of FRONT END of Nuclear Fuel Cycle as well as programs for spent fuel and waste management. Industrial facilities for uranian production, U 3 O 8 concentrate, UO 2 powder and CANDU fuel bundles, as well as heavy water plant, supply the required fuel and heavy water for Cernavoda NPP. The paper presents the Romanian activities in Nuclear Fuel Cycle and waste management fields. (authors)

Transient evaluation using EMTP at single open phase with the offsite power transformer for the emergency power supply systems of nuclear power plants

International Nuclear Information System (INIS)

Shimada, Yoshio

2017-01-01

The emergency power supply systems of nuclear power plants, as the objects of this research, are critical in supplying stable electric power to such systems as the emergency core cooling system (ECCS), and in maintaining safety of the nuclear power reactor; this was apparent in the accident at the Fukushima Daiichi Nuclear Power Station. The Nuclear Regulatory Commission (USNRC) issued regulatory documents (BL 2012-011, IN 2012-032), and has commenced evaluations on newly discovered vulnerability in the design of power supply systems which cannot be detected with under-voltage protection relays, with certain kinds of configuration of coils and iron core structures, such as when the offsite power supply side is a Y-connection and the load side is a ⊿-connection etc., when the detection of single open phase fault with the circuit of a transformer which is without a ground fault connected to the offsite power supply system. This report uses simulation by the electro magnetic transients program (EMTP) and clearly describe the response at the time of the power supply single open phase without ground fault for various configuration of coils and various iron core structures of the three-phase transformer, and identify the important issues in the response of emergency power supply systems and the safety related components of representative domestic PWR plants when the single open phase fault occurred without ground fault. This report describes the results of the simulations of operations of the protection relays of the emergency power supply systems and the safety related components of representative a domestic PWR plant with EMTP. This report explains the method to detect open-phase when the transformer is no-load which United States Electric Power Research Institute (EPRI) developed. As the detailed analyses data from EPRI related to the detection method concerned have not been disclosed officially yet, in this paper, the quantitative and detailed verification results

Fuel cycle strategies for growth of nuclear power in India

International Nuclear Information System (INIS)

Purushotham, D.S.C.; Balu, K.

2002-01-01

Nuclear power has been identified as an essential component to meet the growing energy demand of India. The three stage fuel cycle strategy to achieve this with the available resources envisages the use of natural uranium in PHWRs in the first stage, the plutonium-uranium/plutonium-thorium cycles in Fast reactors/Advanced HWRs in the second stage, followed by exploitation of essentially U233 in the third stage. The technologies necessary for this programme, mainly through the back-end of the fuel cycle including reprocessing, waste management and recycle of Pu have been developed accordingly, as a direct result of the closed fuel cycle policy followed by us from the very beginning. This paper addresses the considerations involved in several activities taken up in our programme, their current status and plans for the future. (author)

Regulation at nuclear fuel cycle

International Nuclear Information System (INIS)

2002-01-01

This bulletin contains information about activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD). In this leaflet the role of the UJD in regulation at nuclear fuel cycle is presented. The Nuclear Fuel Cycle (NFC) is a complex of activities linked with production of nuclear fuel for nuclear reactors as a source of energy used for production of electricity and heat, and of activities linked with spent nuclear fuel handling. Activities linked with nuclear fuel (NF) production, known as the Front-End of Nuclear Fuel Cycle, include (production of nuclear fuel from uranium as the most frequently used element). After discharging spent nuclear fuel (SNF) from nuclear reactor the activities follow linked with its storage, reprocessing and disposal known as the Back-End of Nuclear Fuel Cycle. Individual activity, which penetrates throughout the NFC, is transport of nuclear materials various forms during NF production and transport of NF and SNF. Nuclear reactors are installed in the Slovak Republic only in commercial nuclear power plants and the NFC is of the open type is imported from abroad and SNF is long-term supposed without reprocessing. The main mission of the area of NFC is supervision over: - assurance of nuclear safety throughout all NFC activities; - observance of provisions of the Treaty on Non-Proliferation of Nuclear Weapons during nuclear material handling; with an aim to prevent leakage of radioactive substances into environment (including deliberated danage of NFC sensitive facilities and misuse of nuclear materials to production of nuclear weapons. The UJD carries out this mission through: - assessment of safety documentation submitted by operators of nuclear installations at which nuclear material, NF and SNF is handled; - inspections concentrated on assurance of compliance of real conditions in NFC, i.e. storage and transport of NF and SNF; storage, transport and disposal of wastes from processing of SNF; with assumptions of the safety

Feasibility study for application of mixture working fluid cycle to nuclear reactor power plant

International Nuclear Information System (INIS)

Takeuchi, Yutaka; Ohshima, Iwao; Shiomi, Hirozo; Miyamae, Nobuhiko; Hiramatsu, Miki; Montani, Mitsuto

1999-01-01

There exists a large amount of unused energy in nuclear power plants. However, it consists of relatively low temperature energy, so it is difficult to generate electricity by the conventional water-steam cycle. In order to utilize such low temperature energy, we applied a mixture working fluid cycle called as the Kalina cycle to a light water nuclear reactor power plant. The Kalina cycle uses a working fluid composed of ammonia and water to create a variable temperature boiling process. We applied a saturation type Kalina cycle with single stage ammonia-water separation process as a bottoming cycle to a conventional water-steam cycle of a 1100MWe class BWR as an example case. The input heat source is the exhaust or the partial extraction of a low pressure turbine (LPT). A steady state chemical process modeling code ASPENPLUS was used for the sensitivity analyses. The maximum efficiency was calculated to be realized when using the lowest heat sink temperature, 8degC. The additional electrical output is about 95 MWe when using the exhaust of LPT and is about 127 MWe when using the partial extraction of LPT. Namely, about 4.3% of the exhaust heat for the former case and about 5.8% for the latter case can be utilized as electrical power, respectively. (author)

RAAN Conference. Support of Nuclear Power. Opening talk

International Nuclear Information System (INIS)

Valeca, Serban

2002-01-01

Nuclear power in Romania was initiated on the basis of CANDU reactor type technology, an option found to fulfill the requirements for a sustainable economic development, to support the electric energy demand of the country and to ensure the population and environment protection. The construction of the Cernavoda NPP was heavily based on the Romanian industry participation and basic and applied nuclear research national resources. The experience acquired from Cernavoda NPP Unit 1 will be fructified in the construction of Units 2-5 to be built. The Romanian Ministry of Education and Research implemented a nuclear national program for research and development taking into account the European Union requirements and recommendations, the cooperation with the IAEA - Vienna and the Romanian government policy on short and medium terms in the nuclear field. The research-development program targeted: the reactor physics and nuclear fuel management; the operation safety of Cernavoda NPP Unit 1; improvement of technological solutions for Cernavoda NPP; improvement of nuclear fuel cycle technology; risk assesment and evaluation of the radiological impact upon the environment; behavior of the materials submitted to operational conditions in the reactor and nuclear facilities; radiation safeguards; application of nuclear technologies and methods in industry, agriculture, health and other sectors of social life. The author highlights also relating topics concerning legislation, financing and international cooperation. He stresses the important role of the Romanian Agency for nuclear activities, R.A.A.N. through the Institute of Nuclear Research at Pitesti, the Center for Technological Engineering for Nuclear Objectives at Bucharest and the Heavy Water Plant at Drobeta Turnu Severin

Closed Brayton cycle power conversion systems for nuclear reactors :

Energy Technology Data Exchange (ETDEWEB)

Wright, Steven A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lipinski, Ronald J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Vernon, Milton E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sanchez, Travis [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2006-04-01

This report describes the results of a Sandia National Laboratories internally funded research program to study the coupling of nuclear reactors to gas dynamic Brayton power conversion systems. The research focused on developing integrated dynamic system models, fabricating a 10-30 kWe closed loop Brayton cycle, and validating these models by operating the Brayton test-loop. The work tasks were performed in three major areas. First, the system equations and dynamic models for reactors and Closed Brayton Cycle (CBC) systems were developed and implemented in SIMULINKTM. Within this effort, both steady state and dynamic system models for all the components (turbines, compressors, reactors, ducting, alternators, heat exchangers, and space based radiators) were developed and assembled into complete systems for gas cooled reactors, liquid metal reactors, and electrically heated simulators. Various control modules that use proportional-integral-differential (PID) feedback loops for the reactor and the power-conversion shaft speed were also developed and implemented. The simulation code is called RPCSIM (Reactor Power and Control Simulator). In the second task an open cycle commercially available Capstone C30 micro-turbine power generator was modified to provide a small inexpensive closed Brayton cycle test loop called the Sandia Brayton test-Loop (SBL-30). The Capstone gas-turbine unit housing was modified to permit the attachment of an electrical heater and a water cooled chiller to form a closed loop. The Capstone turbine, compressor, and alternator were used without modification. The Capstone systems nominal operating point is 1150 K turbine inlet temperature at 96,000 rpm. The annular recuperator and portions of the Capstone control system (inverter) and starter system also were reused. The rotational speed of the turbo-machinery is controlled by adjusting the alternator load by using the electrical grid as the load bank. The SBL-30 test loop was operated at

Nuclear power, nuclear fuel cycle and waste management, 1986-1999. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2000-04-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with nuclear power and nuclear fuel cycle and waste management and issued during the period of 1986-1999. Some earlier titles which form part of an established series or are still considered of importance have been included. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain papers in languages other than English, but all of these papers have abstracts in English

Nuclear power generation and fuel cycle report 1997

International Nuclear Information System (INIS)

1997-09-01

Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East

Nuclear power generation and fuel cycle report 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

The nuclear fuel cycle associated with the operation of nuclear ...

African Journals Online (AJOL)

The nuclear power option has been mentioned as an alternative for Ghana but the issue of waste management worries both policy makers and the public. In this paper, the nuclear fuel cycle associated with the operation of nuclear power plants (NPPs) for electric power generation has been extensively reviewed. Different ...

Reactor pressure vessel life cycle management at the Calvert Cliffs Nuclear Power Plant

International Nuclear Information System (INIS)

Doroshuk, B.W.; Bowman, M.E.; Henry, S.A.; Pavinich, W.A.; Lapides, M.E.

1993-01-01

Life Cycle Management (LCM) seeks to manage the aging process of important systems, structures, and components during licensed operation. The goal of Baltimore Gas and Electric Company's (BG and E) Life Cycle Management Program is to assure attainment of 40 years of operation and to preserve the option of an additional 20 years of operation for the Calvert Cliffs Nuclear Power Plant (CCNPP). Since the reactor pressure vessel (RPV) has been identified as one of the most critical components with regard to long-term operation of a nuclear power plant, BG and E initiated actions to manage life limiting or aging issues for the CCNPP RPVs. To achieve long-term operation, technical RPV issues must be effectively managed. This paper describes methods BG and E uses for managing RPV age-related degradation. (author)

Report of “the 2013 international forum on peaceful use of nuclear energy, nuclear non-proliferation and nuclear security. Ensuring nuclear non-proliferation and nuclear security of nuclear fuel cycle options in consideration of the accident at TEPCO's Fukushima Daiichi Nuclear Power Station”

International Nuclear Information System (INIS)

Yamamura, Tsukasa; Suda, Kazunori; Tomikawa, Hirofumi; Suzuki, Mitsutoshi; Kuno, Yusuke; Mochiji, Toshiro

2014-03-01

The Japan Atomic Energy Agency (JAEA) held “International Forum on Peaceful Use of Nuclear Energy, Nuclear Non-proliferation and Nuclear Security – Ensuring Nuclear Non-Proliferation and Nuclear Security of Nuclear Fuel Cycle Options in consideration of the Accident at TEPCO's Fukushima Daiichi Nuclear Power Station –” on 3 and 4 December 2013, with the Japan Institute of International Affairs (JIIA) and School of Engineering, The University of Tokyo, as co-hosts. In the Forum, officials from Japan, the United States, France and International Atomic Energy Agency (IAEA) explained their efforts regarding peaceful use of nuclear energy and nuclear non-proliferation. Discussion was made in two panels, entitled “Nuclear non-proliferation and nuclear security measures of nuclear fuel cycle options in consideration of the Accident at TEPCO's Fukushima Daiichi Nuclear Power Station” and “Roles of safeguards and technical measures for ensuring nuclear non-proliferation for nuclear fuel cycle options”. In the first panel based on the implications of the Accident at TEPCO's Fukushima Daiichi Nuclear Power Station on the domestic and global nuclear energy use and increased interest in the back end of nuclear fuel cycle, discussion was made on nuclear non-proliferation and nuclear security challenges on both fuel cycle options from the policy and institutional viewpoints whereas in the second panel the roles of safeguards and proliferation resistant nuclear technology including plutonium burning technology in ensuring nuclear non-proliferation and nuclear security in the back end of nuclear fuel cycle were discussed. Officials and experts from Japan, IAEA, the United States, France and Republic of Korea participated in the panel and made contributions to active discussion. This report includes abstracts of keynote speeches, summaries of two panel discussions and materials of the presentations in the forum. The editors take full responsibility for the wording

Nuclear fuel cycle scenarios at CGNPC

International Nuclear Information System (INIS)

Xiao, Min; Zhou, Zhou; Nie, Li Hong; Mao, Guo Ping; Hao, Si Xiong; Shen, Kang

2008-01-01

Established in 1994, China Guangdong Nuclear Power Holding Co. (CGNPC) now owns two power stations GNPS and LNPS Phase I, with approximate 4000 MWe of installed capacity. With plant upgrades, advanced fuel management has been introduced into the two plants to improve the plant economical behavior with the high burnup fuel implemented. For the purpose of sustainable development, some preliminary studies on nuclear fuel cycle, especially on the back-end, have been carried out at CGNPC. According to the nuclear power development plan of China, the timing for operation and the capacity of the reprocessing facility are studied based on the amount of the spent fuel forecast in the future. Furthermore, scenarios of the fuel cycles in the future in China with the next generation of nuclear power were considered. Based on the international experiences on the spent fuel management, several options of spent fuel reprocessing strategies are investigated in detail, for example, MOX fuel recycling in light water reactor, especially in the current reactors of CGNPC, spent fuel intermediated storage, etc. All the investigations help us to draw an overall scheme of the nuclear fuel cycle, and to find a suitable road-map to achieve the sustainable development of nuclear power. (authors)

Strategy of nuclear power in Korea, non-nuclear-weapon state and peaceful use of nuclear power

International Nuclear Information System (INIS)

Nagasaki, Takao

2005-01-01

The nuclear power plant started at Kori in Korea in April, 1978. Korea has carried out development of nuclear power as a national policy. The present capacity of nuclear power plants takes the sixes place in the world. It supplies 42% total power generation. The present state of nuclear power plant, nuclear fuel cycle facility, strategy of domestic production of nuclear power generation, development of next generation reactor and SMART, strategy of export in corporation with industry, government and research organization, export of nuclear power generation in Japan, nuclear power improvement project with Japan, Korea and Asia, development of nuclear power system with nuclear diffusion resistance, Hybrid Power Extraction Reactor System, radioactive waste management and construction of joint management and treatment system of spent fuel in Asia are stated. (S.Y.)

The nuclear fuel cycle

International Nuclear Information System (INIS)

1998-05-01

After a short introduction about nuclear power in the world, fission physics and the French nuclear power plants, this brochure describes in a digest way the different steps of the nuclear fuel cycle: uranium prospecting, mining activity, processing of uranium ores and production of uranium concentrates (yellow cake), uranium chemistry (conversion of the yellow cake into uranium hexafluoride), fabrication of nuclear fuels, use of fuels, reprocessing of spent fuels (uranium, plutonium and fission products), recycling of energetic materials, and storage of radioactive wastes. (J.S.)

Life cycle analysis on carbon emissions from power generation – The nuclear energy example

International Nuclear Information System (INIS)

Nian, Victor; Chou, S.K.; Su, Bin; Bauly, John

2014-01-01

Highlights: • This paper discusses about a methodology on the life cycle analysis of power generation using nuclear as an example. • The methodology encompasses generic system, input–output, and boundaries definitions. • The boundaries facilitate the use of Kaya Identity and decomposition technique to identify carbon emission streams. - Abstract: A common value of carbon emission factor, t-CO 2 /GWh, in nuclear power generation reported in the literature varies by more than a factor of 100. Such a variation suggests a margin of uncertainty and reliability. In this study, we employ a bottom-up approach to better define the system, its input and output, and boundaries. This approach offers improved granularity at the process level and consistency in the results. Based on this approach, we have developed a methodology to enable comparison of carbon emissions from nuclear power generation. The proposed methodology employs the principle of energy balance on a defined power generation system. The resulting system boundary facilitates the use of the “Kaya Identity” and the decomposition technique to identify the carbon emission streams. Using nuclear power as a case study, we obtained a carbon emission factor of 22.80 t-CO 2 /GWh, which falls to within 2.5% of the median of globally reported LCA results. We demonstrate that the resulting methodology could be used as a generic tool for life cycle analysis of carbon emissions from other power generation technologies and systems

Back-end of the nuclear fuel cycle

International Nuclear Information System (INIS)

Choi, J.S.

2002-01-01

Current strategies of the back-end nuclear fuel cycles are: (1) direct-disposal of spent fuel (Open Cycle), and (2) reprocessing of the spent fuel and recycling of the recovered nuclear materials (Closed Cycle). The selection of these strategies is country-specific, and factors affecting selection of strategy are identified and discussed in this paper. (author)

Prospects for and problems of using light-water supercritical-pressure coolant in nuclear reactors in order to increase the efficiency of the nuclear fuel cycle

International Nuclear Information System (INIS)

Alekseev, P. N.; Semchenkov, Yu. M.; Sedov, A. A.; Subbotin, S. A.; Chibinyaev, A. V.

2011-01-01

Trends in the development of the power sector of the Russian and world power industries both at present time and in the near future are analyzed. Trends in the rise of prices for reserves of fossil and nuclear fuels used for electricity production are compared. An analysis of the competitiveness of electricity production at nuclear power plants as compared to the competitiveness of electricity produced at coal-fired and natural-gas-fired thermal power plants is performed. The efficiency of the open nuclear fuel cycle and various versions of the closed nuclear fuel cycle is discussed. The requirements on light-water reactors under the scenario of dynamic development of the nuclear power industry in Russia are determined. Results of analyzing the efficiency of fuel utilization for various versions of vessel-type light-water reactors with supercritical coolant are given. Advantages and problems of reactors with supercritical-pressure water are listed.

Optimization of preventive maintenance cycle based on experimental feedback in nuclear power plants

International Nuclear Information System (INIS)

Shi Jie

2010-01-01

The preventive replacement method based on the experimental feedback was introduced. In this method, the initial preventive replacement cycle was acquired by expert votes. The preventive replacement cycle combined with the operation experience of the equipment was gained by means of Bayesian theorem. The Optimized preventive replacement cycle can be acquired by comparing the two probabilities that no fault occurs within the cycle. This method was tested on the switches which were used in Daya Bay Nuclear Power Plant and the results indicated its validity. (authors)

Nuclear steam power plant cycle performance calculations supported by power plant monitoring and results computer

International Nuclear Information System (INIS)

Bettes, R.S.

1984-01-01

The paper discusses the real time performance calculations for the turbine cycle and reactor and steam generators of a nuclear power plant. Program accepts plant measurements and calculates performance and efficiency of each part of the cycle: reactor and steam generators, turbines, feedwater heaters, condenser, circulating water system, feed pump turbines, cooling towers. Presently, the calculations involve: 500 inputs, 2400 separate calculations, 500 steam properties subroutine calls, 200 support function accesses, 1500 output valves. The program operates in a real time system at regular intervals

Principles of provision concerning the back-end of the fuel cycle of nuclear power plants find application

International Nuclear Information System (INIS)

1977-01-01

The Ministry of the Interior has asked the Laender on the 14th June 1977, to apply forthwith the 'principles of provision concerning the back-end of the fuel cycle of nuclear power plants' as a minimum pre-condition for waste management in licensing procedures for nuclear power stations. The 'principles' were part of a report, elaborated by a Bund/Laender working group at a undersecretary-of-state level on questions concerning the back-end of the fuel cycle of nuclear power plants. The report was favourably acknowledged during a meeting of the Federal Chancellor and the Minister-Presidents of the Laender on May 6th, 1977. The principles are presented. (orig./HP) [de

Nuclear plant life cycle management implementation guide. Final report

International Nuclear Information System (INIS)

Sliter, G.E.; Negin, C.A.

1998-11-01

Nuclear power plants, as baseload suppliers of electricity, are major corporate assets. As the nuclear industry enters its fourth decade as a major producer of clean electricity, the structure of the utility industry is undergoing a historical landmark transition from economic deregulation to a competitive, market-driven industry. An integral part of competition is to manage the operation of the key asset, the plant, in the long term, thereby enhancing its long-term profitability. Life cycle management (LCM) is a well-known technical-economic decision-making process for any large industrial facility. LCM optimizes the service life of a facility and maximizes its life-cycle asset value. LCM integrates aging management (maintaining the availability of costly-to-replace components and structures) with asset management (plant valuation and investment strategies that account for economic, performance, regulatory, and environmental uncertainties). LCM involves predicting maintenance, repair, and other capital costs for a nuclear unit far into the future, as well as planning and managing strategic issues such as waste disposal, fuel storage, decommissioning, and public acceptance. This Life Cycle Management Implementation Guide introduces the reader to the LCM concept and its benefits, describes the elements and activities associated with an LCM program (most of which already exist in all plants), gives an overview of asset and aging management, and provides key references related to life cycle management for nuclear power plants. It also summarizes the major elements of life cycle management required for license renewal or, for newer plants, keeping open the option of license renewal

Nuclear power complexes and economic-ecological problems of nuclear power development

International Nuclear Information System (INIS)

Dollezhal', N.A.; Bobolovich, V.N.; Emel'yanov, I.Ya.

1977-01-01

The effect of constructing NPP's at separate sites in densely populated areas on economic efficiency of nuclear power and its ecological implications has been investigated. Locating NPP's and nuclear fuel cycle plants at different sites results in large scale shipments of fresh and spent nuclear fuels and radioactive wastes. The fact increases the risk of a detrimental environmental impact, duration of the external fuel cycle, and worsens, in the end, nuclear power economics. The prudence of creating nuclear parks is discussed. The parks may be especially efficient if the program of developing NPP's with fast breeder reactors is a success. Comparative evaluations show that from economic standpoint deployment of nuclear parks in the European part of the USSR has no disadvantage before construction of separate NPP's and supporting fuel cycle facilities of equivalent capacity, even if the construction of nuclear parks runs dearer by 30% than assumed. The possibility for nuclear parks to meet a part of demand for ''off-peak'' energy production, district heating and process heat production is also shortly discussed

Economic analysis of extended cycles in the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Hernandez N, H.; Hernandez M, J.L.; Francois L, J.L.

2004-01-01

The present work presents a preliminary analysis of economic type of extended cycles of operation of the Unit One in the Laguna Verde nuclear power plant. It is analysed an equilibrium cycle of 18 months firstly, with base to the Plan of Use of Energy of the Federal Commission of Electricity, being evaluated the cost of the energy until the end of the useful life of the plant. Later on an alternative recharge scenario is presented with base to an equilibrium cycle of 24 months, implemented to the beginning of the cycle 11, without considering transition cycles. It is added in both cycles the cost of the substitution energy, considering the unitary cost of the fuel of a dual thermoelectric power station of 350 M We and evaluating in each operation cycle, in both scenarios, the value of the substitution energy. The results show that a reduction of the days of recharge in the cycle of 24 months could make this option but favorable economically. The duration of the period of recharge rebounds in considerable grade in the cost of energy generation for concept of fuel. (Author)

Web-based turbine cycle performance analysis for nuclear power plants

International Nuclear Information System (INIS)

Heo, Gyun Young; Lee, Sung Jin; Chang, Soon Heung; Choi, Seong Soo

2000-01-01

As an approach to improve the economical efficiency of operating nuclear power plants, a thermal performance analysis tool for steam turbine cycle has been developed. For the validation and the prediction of the signals used in thermal performance analysis, a few statistical signal processing techniques are integrated. The developed tool provides predicted performance calculation capability that is steady-state wet steam turbine cycle simulation, and measurement performance calculation capability which determines component- and cycle-level performance indexes. Web-based interface with all performance analysis is implemented, so even remote users can achieve performance analysis. Comparing to ASME PTC6 (Performance Test Code 6), the focusing point of the developed tool is historical performance analysis rather than single accurate performance test. The proposed signal processing techniques are validated using actual plant signals, and turbine cycle models are tested by benchmarking with a commercial thermal analysis tool

International Symposium on Nuclear Energy SIEN 2007. Nuclear Power - A New Challenge

International Nuclear Information System (INIS)

Stiopol, Mihaela

2007-01-01

The Symposium organized by Romanian Nuclear Energy Association, AREN, in co-operation with Romanian Atomic Forum, ROMATOM, was primarily targeting the expert community involved in developing new nuclear power projects and implementing the National Nuclear Program. The symposium was also open as a dicussion and information forum for scientists, engineers, technicians and students interested in scietific and technologic topics of Nuclear Power such as: - Developing the new nuclear technologies; - Identifying new avenues for developing nuclear programs; - strengthening the public confidence and support in nuclear power technology as the energy resource fulfilling most safely the environment protection requirements with the lowest cost-efficient power technology and as the most secure, sustainable solution satisfying the ever raising energy demand. Thus the main objectives was to analyse the New Challenges of Nuclear Power for near future and long-term sustainable socio-economic development. The Symposium was structured in 5 sessions covering the following topics: S1. Developing the new nuclear technologies; S2. Operation, inspection and maintenance; S3. Enhancing nuclear safety features; S4. Fuel cycle and waste management; S5. Public acceptance and confidence strengthening. A poster session of 8 presentations and a workshop completed the Symposium works. Three topics were selected for the workshop as follows: QA Management within the European Integration; Young generation 'Building the Future'; Women in Nuclear and the EU Nuclear Programs Developing

Economic Analysis of Several Nuclear Fuel Cycles

International Nuclear Information System (INIS)

Ko, Won Il; Gao, Fanxing; Kim, Sung Ki

2012-01-01

Economics is one of the essential criteria to be considered for the future deployment of the nuclear power. With regard to the competitive power market, the cost of electricity from nuclear power plants is somewhat highly competitive with those from the other electricity generations, averaging lower in cost than fossil fuels, wind, or solar. However, a closer look at the nuclear power production brings an insight that the cost varies within a wide range, highly depending on a nuclear fuel cycle option. The option of nuclear fuel cycle is a key determinant in the economics, and therefrom, a comprehensive comparison among the proposed fuel cycle options necessitates an economic analysis for thirteen promising options based on the material flow analysis obtained by an equilibrium model as specified in the first article (Modeling and System Analysis of Different Fuel Cycle Options for Nuclear Power Sustainability (I): Uranium Consumption and Waste Generation). The objective of the article is to provide a systematic cost comparison among these nuclear fuel cycles. The generation cost (GC) generally consists of a capital cost, an operation and maintenance cost (O and M cost), a fuel cycle cost (FCC), and a decontaminating and decommissioning (D and D) cost. FCC includes a frontend cost and a back-end cost, as well as costs associated with fuel recycling in the cases of semi-closed and closed cycle options. As a part of GC, the economic analysis on FCC mainly focuses on the cost differences among fuel cycle options considered and therefore efficiently avoids the large uncertainties of the Generation-IV reactor capital costs and the advanced reprocessing costs. However, the GC provides a more comprehensive result covering all the associated costs, and therefrom, both GC and FCC have been analyzed, respectively. As a widely applied tool, the levelized cost (mills/KWh) proves to be a fundamental calculation principle in the energy and power industry, which is particularly

Evaluation and Optimization of a Supercritical Carbon Dioxide Power Conversion Cycle for Nuclear Applications

International Nuclear Information System (INIS)

Harvego, Edwin A.; McKellar, Michael G.

2011-01-01

There have been a number of studies involving the use of gases operating in the supercritical mode for power production and process heat applications. Supercritical carbon dioxide (CO2) is particularly attractive because it is capable of achieving relatively high power conversion cycle efficiencies in the temperature range between 550 C and 750 C. Therefore, it has the potential for use with any type of high-temperature nuclear reactor concept, assuming reactor core outlet temperatures of at least 550 C. The particular power cycle investigated in this paper is a supercritical CO2 Recompression Brayton Cycle. The CO2 Recompression Brayton Cycle can be used as either a direct or indirect power conversion cycle, depending on the reactor type and reactor outlet temperature. The advantage of this cycle when compared to the helium Brayton Cycle is the lower required operating temperature; 550 C versus 850 C. However, the supercritical CO2 Recompression Brayton Cycle requires an operating pressure in the range of 20 MPa, which is considerably higher than the required helium Brayton cycle operating pressure of 8 MPa. This paper presents results of analyses performed using the UniSim process analyses software to evaluate the performance of the supercritical CO2 Brayton Recompression Cycle for different reactor outlet temperatures. The UniSim model assumed a 600 MWt reactor power source, which provides heat to the power cycle at a maximum temperature of between 550 C and 750 C. The UniSim model used realistic component parameters and operating conditions to model the complete power conversion system. CO2 properties were evaluated, and the operating range for the cycle was adjusted to take advantage of the rapidly changing conditions near the critical point. The UniSim model was then optimized to maximize the power cycle thermal efficiency at the different maximum power cycle operating temperatures. The results of the analyses showed that power cycle thermal efficiencies in

Fuel cycle management by the electric enterprises and spanish nuclear Power plants

International Nuclear Information System (INIS)

Celma, E. M.; Gonzalez, C.; Lopez, J. V.; Melara, J.; Lopez, L.; Martinez, J. C.; Culbras, F.; Blanco, J.; Francia, L.

2015-01-01

The Nuclear Fuel Group reports to the Technology Committee of the UNESA Nuclear Energy Committee, and is constituted by representatives of both the Spanish Utilities and the Nuclear Power Plants. The Group addresses the nuclear plant common issues in relation to the operation and management of the nuclear fuel in their different stages of the Fuel Cycle. The article reviews the activities developed by the Group in the Front-End, mainly in the monitoring of international programs that define criteria to improve the Fuel Reliability and in the establishment of common bases for the implementation of changes in the regulation applying the nuclear fuel. Concerning the Back-End the Group focuses on those activities of coordination with third parties related to the management of used fuel. (Author)

Aspects of nuclear safety at power plants and fuel cycle plants in the USSR

International Nuclear Information System (INIS)

Kozlov, N.I.; Efimov, E.; Dubovskij, B.G.; Dikarev, V.; Lyubchenko, V.; Kruglov, A.K.

1977-01-01

The paper discusses the problems of organizing inspection monitoring of power plants including the development of some regulations and norms and the interaction between the USSR State Nuclear Safety Organization, scientific and designing organizations and power plants. The principles of computer use to work out advice for operational staff and warning signals and commands for the reactor control and protection system are discussed. Some attention is turned to the importance of using high-speed computers to calculate prompt reactivity values and to determine impurity concentrations in the coolant and margins to permissible operational limits. In particular, reactimeters are considered as signal generators in monitor and protection systems. Some problems of nuclear safety inspection, the issue and inculcation of some regulations and operational documents on nuclear safety, and instrumentation of plants reprocessing or processing fuel elements are presented. Methods of determining the critical parameters of technological units are described, together with the fundamental principles of fuel cycle plant nuclear safety, providing margin coefficients, accounting for deviations from the normal operational process and other problems, as well as methods of keeping the restrictions on nuclear safety requirements at fuel cycle plants. (author)

World nuclear fuel cycle requirements 1991

Energy Technology Data Exchange (ETDEWEB)

1991-10-10

The nuclear fuel cycle consists of mining and milling uranium ore, processing the uranium into a form suitable for generating electricity, burning'' the fuel in nuclear reactors, and managing the resulting spent nuclear fuel. This report presents projections of domestic and foreign requirements for natural uranium and enrichment services as well as projections of discharges of spent nuclear fuel. These fuel cycle requirements are based on the forecasts of future commercial nuclear power capacity and generation published in a recent Energy Information Administration (EIA) report. Also included in this report are projections of the amount of spent fuel discharged at the end of each fuel cycle for each nuclear generating unit in the United States. The International Nuclear Model is used for calculating the projected nuclear fuel cycle requirements. 14 figs., 38 tabs.

World nuclear fuel cycle requirements 1991

International Nuclear Information System (INIS)

1991-01-01

The nuclear fuel cycle consists of mining and milling uranium ore, processing the uranium into a form suitable for generating electricity, ''burning'' the fuel in nuclear reactors, and managing the resulting spent nuclear fuel. This report presents projections of domestic and foreign requirements for natural uranium and enrichment services as well as projections of discharges of spent nuclear fuel. These fuel cycle requirements are based on the forecasts of future commercial nuclear power capacity and generation published in a recent Energy Information Administration (EIA) report. Also included in this report are projections of the amount of spent fuel discharged at the end of each fuel cycle for each nuclear generating unit in the United States. The International Nuclear Model is used for calculating the projected nuclear fuel cycle requirements. 14 figs., 38 tabs

Steam water cycle chemistry of liquid metal cooled innovative nuclear power reactors

International Nuclear Information System (INIS)

Yurmanov, Victor; Lemekhov, Vadim; Smykov, Vladimir

2012-09-01

The Federal Target Program (FTP) of Russian Federation 'Nuclear Energy Technologies of the New Generation for 2010-2015 and for Perspective up to 2020' is aimed at development of advanced nuclear energy technologies on the basis of closed fuel cycle with fast reactors. There are advanced fast reactor technologies of the 4. generation with liquid metal cooled reactors. Development stages of maturity of fast sodium cooled reactor technology in Russia includes experimental reactors BR-5/10 (1958-2002) and BOR-60 (since 1969), nuclear power plants (NPPs) with BN-350 (1972-1999), BN-600 (since 1980), BN-800 (under construction), BN-1200 (under development). Further stage of development of fast sodium cooled reactor technology in Russia is commercialization. Lead-bismuth eutectic fast reactor technology has been proven at industrial scale for nuclear submarines in former Soviet Union. Lead based technology is currently under development and need for experimental justification. Current status and prospects of State Corporation 'Rosatom' participation in GIF activities was clarified at the 31. Meeting of Policy Group of the International Forum 'Generation-IV', Moscow, May 12-13, 2011. In June, 2010, 'Rosatom' joined the Sodium Fast Reactor Arrangement as an authorized representative of the Russian Government. It was also announced the intention of 'Rosatom' to sign the Memorandum on Lead Fast Reactor based on Russia's experience with lead-bismuth and lead cooled fast reactors. In accordance with the above FTP some innovative liquid metal cooled reactors of different design are under development in Russia. Gidropress, well known as WER designer, develops innovative lead-bismuth eutectic cooled reactor SVBR-100. NIKIET develops innovative lead cooled reactor BRESTOD-300. Some other nuclear scientific centres are also involved in this activity, e.g. Research and Development Institute for Power Engineering (RDIPE). Optimum

The IFR modern nuclear fuel cycle

International Nuclear Information System (INIS)

Hannum, W.H.

1991-01-01

Nuclear power is an essential component of the world's energy supply. The IFR program, by returning to fundamentals, offers a fresh approach to closing the nuclear fuel cycle. This closed fuel cycle represents the ultimate in efficient resource utilization and environmental accountability. 35 refs., 2 tabs

Nuclear power publications

International Nuclear Information System (INIS)

1982-01-01

This booklet lists 69 publications on nuclear energy available free from some of the main organisations concerned with its development and operation in the UK. Headings are: general information; the need for nuclear energy; the nuclear industry; nuclear power stations; fuel cycle; safety; waste management. (U.K.)

Nuclear power in the developing countries

International Nuclear Information System (INIS)

Perera, J.

1984-01-01

The subject is covered in chapters, entitled: the general energy situation (including nuclear power); the nuclear fuel cycle; the history of nuclear power in the third world; economic considerations; environmental considerations (including general environmental effects of power generation; radiation; normal fuel cycle operation; nuclear waste management; accidents; sabotage; health and safety regulations); political considerations (nuclear weapons proliferation; technology transfer; energy independence and national prestige); the suppliers (mainly USA, France, West Germany, Canada, UK, USSR); Sub-Saharan Africa; the Arab World and Israel; Central Asia; South and East Asia; Latin America; conclusions. (U.K.)

The IFR modern nuclear fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Hannum, W.H.

1991-01-01

Nuclear power is an essential component of the world's energy supply. The IFR program, by returning to fundamentals, offers a fresh approach to closing the nuclear fuel cycle. This closed fuel cycle represents the ultimate in efficient resource utilization and environmental accountability. 35 refs., 2 tabs.

The nuclear fuel cycle; Le cycle du combustible nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

After a short introduction about nuclear power in the world, fission physics and the French nuclear power plants, this brochure describes in a digest way the different steps of the nuclear fuel cycle: uranium prospecting, mining activity, processing of uranium ores and production of uranium concentrates (yellow cake), uranium chemistry (conversion of the yellow cake into uranium hexafluoride), fabrication of nuclear fuels, use of fuels, reprocessing of spent fuels (uranium, plutonium and fission products), recycling of energetic materials, and storage of radioactive wastes. (J.S.)

Dictionary of nuclear power

International Nuclear Information System (INIS)

Koelzer, W.

2012-06-01

The actualized version (June 2012) of the dictionary on nuclear power includes all actualizations and new inputs since the last version of 2001. The original publication dates from 1980. The dictionary includes definitions, terms, measuring units and helpful information on the actual knowledge concerning nuclear power, nuclear fuel cycle, nuclear facilities, radioactive waste management, nuclear physics, reactor physics, isotope production, biological radiation effects, and radiation protection.

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume III. Resources and fuel cycle facilities

International Nuclear Information System (INIS)

1980-06-01

The ability of uranium supply and the rest of the nuclear fuel cycle to meet the demand for nuclear power is an important consideration in future domestic and international planning. Accordingly, the purpose of this assessment is to evaluate the adequacy of potential supply for various nuclear resources and fuel cycle facilities in the United States and in the world outside centrally planned economy areas (WOCA). Although major emphasis was placed on uranium supply and demand, material resources (thorium and heavy water) and facility resources (separative work, spent fuel storage, and reprocessing) were also considered

Nuclear power in perspective

International Nuclear Information System (INIS)

Addinall, E.; Ellington, H.

1982-01-01

The subject is covered in chapters: (the nature of nuclear power) the atomic nucleus - a potential source of energy; how nuclear reactors work; the nuclear fuel cycle; radioactivity - its nature and biological effects; (why we need nuclear power) use of energy in the non-communist world -the changing pattern since 1950; use of energy - possible future scenarios; how our future energy needs might be met; (a possible long term nuclear strategy) the history of nuclear power; a possible nuclear power strategy for the Western World; (social and environmental considerations) the hazards to workers in the nuclear power industry; the hazards to the general public (nuclear power industry; reactor operation; transport of radioactive materials; fuel reprocessing; radioactive waste disposal; genetic hazards); the threat to democratic freedom and world peace. (U.K.)

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

Technical support for open-cycle MHD program

Energy Technology Data Exchange (ETDEWEB)

None

1978-05-01

The support program for open-cycle MHD at Argonne National Lab is developing the analytical tools needed to investigate the performance of the major components in the combined-cycle MHD/steam power system. The analytical effort is centered on the primary components of the system that are unique to MHD and also on the integration of these analytical representations into a model of the entire power producing system. The present project activities include modeling of the combustor, MHD channel, slag separator, and the high-temperature air preheater. In addition, these models are combined into a complete system model, which is at present capable of carrying out optimizations of the entire system on either thermodynamic efficiency or with less confidence, cost of electrical power. Also, in support of the open-cycle program, considerable effort has gone into the formulation of a CDIF Test Plan and a National MHD Test Program.

Recent situation of the establishment of nuclear fuel cycle

International Nuclear Information System (INIS)

Hoshiba, Shizuo

1982-01-01

In Japan, the development of nuclear power as principal petroleum substitute is actively pursued. Nuclear power generation now accounts for about 17 % of the total power generation in Japan. The business related to nuclear fuel cycle should be established by private enterprises. The basic policy in the establishment of nuclear fuel cycle is the stabilized supply of natural uranium, raise in domestic production of enriched uranium, dFomestic fuel reprocessing in principle, positive plutonium utilization, and so on. After explaining this basic policy, the present situation and problems in the establishment of nuclear fuel cycle are described: securing of uranium resources, securing of enriched uranium, reprocessing of used fuel, utilization of plutonium, management of radioactive wastes. (Mori, K.)

Nuclear closed-cycle gas turbine (HTGR-GT): dry cooled commercial power plant studies

International Nuclear Information System (INIS)

McDonald, C.F.; Boland, C.R.

1979-11-01

Combining the modern and proven power conversion system of the closed-cycle gas turbine (CCGT) with an advanced high-temperature gas-cooled reactor (HTGR) results in a power plant well suited to projected utility needs into the 21st century. The gas turbine HTGR (HTGR-GT) power plant benefits are consistent with national energy goals, and the high power conversion efficiency potential satisfies increasingly important resource conservation demands. Established technology bases for the HTGR-GT are outlined, together with the extensive design and development program necessary to commercialize the nuclear CCGT plant for utility service in the 1990s. This paper outlines the most recent design studies by General Atomic for a dry-cooled commercial plant of 800 to 1200 MW(e) power, based on both non-intercooled and intercooled cycles, and discusses various primary system aspects. Details are given of the reactor turbine system (RTS) and on integrating the major power conversion components in the prestressed concrete reactor vessel

Nuclear energy technology: theory and practice of commercial nuclear power

International Nuclear Information System (INIS)

Knief, R.A.

1982-01-01

Reviews Nuclear Energy Technology: Theory and Practice of Commercial Nuclear Power by Ronald Allen Knief, whose contents include an overview of the basic concepts of reactors and the nuclear fuel cycle; the basics of nuclear physics; reactor theory; heat removal; economics; current concerns at the front and back ends of the fuel cycle; design descriptions of domestic and foreign reactor systems; reactor safety and safeguards; Three Mile Island; and a brief overview of the basic concepts of nuclear fusion. Both magnetic and inertial confinement techniques are clearly outlined. Also reviews Nuclear Fuel Management by Harry W. Graves, Jr., consisting of introductory subjects (e.g. front end of fuel cycle); core physics methodology required for fuel depletion calculations; power capability evaluation (analyzes physical parameters that limit potential core power density); and fuel management topics (economics, loading arrangements and core operation strategies)

Nuclear power development on the basis of new concepts of nuclear reactors and fuel cycle

International Nuclear Information System (INIS)

Adamov, E.O.; Orlov, V.V.

2001-01-01

Current state of nuclear power in the world has been considered and the reasons for its falling short of the great expectations relating to its vigorous development in the outgoing century are considered. Anticipated energy demand of the mankind in the next century is evaluated, suggesting that with exhausted resources of cheap fossil fuel and ecological restrictions it can be satisfied by means of a new nuclear technology meeting the requirements of large-scale power generation in terms of safety and economic indices, moreover, the technology can be elaborated in the context of achievements made in civil and military nuclear engineering. Since the developing countries are the most interested parties, it is just their initiative in the development of nuclear technology at the next stage that could provide an impetus for its actual advance. It is shown that large-scale development of nuclear power, being adequate to increase in energy demand, is possible even if solely large NPP equipped with breeders providing BR (1 are constructed). Requirements for the reactor and fuel cycle technologies are made, their major aspects being: efficient utilization of Pu accumulated and reduction of U specific consumption by at least an order of magnitude, natural inherent safety and deterministic elimination of accidents involving high radioactive releases, assurance of a balance between radiation hazard posed by radioactive wastes disposed and uranium extracted from the ground, nuclear weapons nonproliferation due to fuel reprocessing ruling out potentiality of Pu diversion, reduction of the new generation reactor costs below the costs of today's LWR. (authors)

Impacts of nuclear fuel cycle costs on nuclear power generating costs

International Nuclear Information System (INIS)

Bertel, E.; Naudet, G.

1989-01-01

Fuel cycle costs are one of the main parameters to evaluate the competitiveness of various nuclear strategies. The historical analysis based on the French case shows the good performances yet achieved in mastering elementary costs in order to limit global fuel cycle cost escalation. Two contrasted theoretical scenarios of costs evolution in the middle and long term have been determined, based upon market analysis and technological improvements expected. They are used to calculate the global fuel cycle costs for various fuel management options and for three strategies of nuclear deployment. The results illustrate the stability of the expected fuel cycle costs over the long term, to be compared to the high incertainty prevailing for fossil fueled plants. The economic advantages of advanced technologies such as MOX fueled PWRs are underlined

Nuclear Fuel Cycle Introductory Concepts

Energy Technology Data Exchange (ETDEWEB)

Karpius, Peter Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-02

The nuclear fuel cycle is a complex entity, with many stages and possibilities, encompassing natural resources, energy, science, commerce, and security, involving a host of nations around the world. This overview describes the process for generating nuclear power using fissionable nuclei.

Nuclear Fuel Cycle Introductory Concepts

International Nuclear Information System (INIS)

Karpius, Peter Joseph

2017-01-01

The nuclear fuel cycle is a complex entity, with many stages and possibilities, encompassing natural resources, energy, science, commerce, and security, involving a host of nations around the world. This overview describes the process for generating nuclear power using fissionable nuclei.

Nuclear power: major issues for France's industrial, energy and environmental policies

International Nuclear Information System (INIS)

Fouquet, F.; Vincent, C.; Iglesias, F.

2007-01-01

France ranks second in the world as producer of electricity from atomic power, and first in Europe. Thanks to its nuclear plants, the country's rates of CO 2 emissions per inhabitant and in proportion to its GDP are among the lowest in the EU. French nuclear power is a success story: it employs more than 110.000 people, and AREVA has become a world leader in the fuel cycle and in the design and construction of power plants. Recently passed laws will help maintain a lasting technological advance for France: a deliberate commitment to develop nuclear power systems and an appointment with parliament in 2015 (before the underground depository for spent fuel is opened), guaranteed funding for further research. (authors)

Improvement in recuperative gas cycles by means of a heat generator partly by-passing the recuperator. Application to open and closed cycles and to various kinds of energy

International Nuclear Information System (INIS)

Tilliette, Z.P.; Pierre, B.

1979-01-01

A particular arrangement applicable to open or closed recuperative gas cycles and consisting of a heat generator partly by-passing the low pressure side of the recuperator is proven to enhance advantages of gas cycles for energy production. The cogeneration of both power with a high efficiency owing to the recuperator and high temperature process heat becomes possible and economically attractive. Furthermore, additional possibilities appear for power generation by combined gas and steam or ammonia cycles. In any case the overall utilization coefficient of the primary energy is increased and the combined production of low or medium temperature heat can also be improved. The great operation flexibility of the system for combined energy generation is worth being emphasized: the by-pass arrangement involves no significant change in the operation conditions of the main turbocompressor as the heat output varies. Applications of this arrangement are made to: - open and closed gas cycle, power plants; - fossil, nuclear and solar energies. The overall heat conversion efficiency is tentatively estimated in order to appreciate the energy conversion capability of the investigated power plants

Opening speech: nuclear power today - the situation in germany

International Nuclear Information System (INIS)

Gueldner, R.

2005-01-01

Nuclear power is experiencing an upswing worldwide. High prices of conventional fuels, discussions about the long-term continuity of supply, rising energy requirements, and the search for efficient ways of protecting the climate have moved nuclear power back into focus in a positive way. This is also true for Germany. In this country, nuclear power has gone through twelve very successful months since the 2004 Nuclear Technology Conference in Duesseldorf, as is borne out by the performance of all nuclear power plants in Germany. A change of mood towards a positive view of nuclear power is taking place in Germany. It is also seen, however, that the ''problem'' of final storage, which has been solved technically, is in urgent need of a political solution. German know-how in nuclear technology enjoys a high reputation internationally. For manufacturers and the associated supplier industries, this means excellent market opportunities, also for future projects, in view of worldwide demand. Various nuclear projects have progressed at long last: The Heinz Meier-Leibnitz research reactor (FRM-II) has been commissioned; the final stage of expansion of the Urenco uranium enrichment plant in Gronau has been approved; the license for a capacity increase in the ANF fuel fabrication plant in Lingen has been granted. Nuclear power is enjoying a high reputation also in the European Union. Major expansion plans exist in Asia, while increases in power and performance as well as life extensions can be observed in the United States. The world needs a sustainable energy mix - with nuclear power. (orig.)

Perspective of nuclear fuel cycle for sustainable nuclear energy

International Nuclear Information System (INIS)

Fukuda, K.; Bonne, A.; Kagramanian, V.

2001-01-01

Nuclear power, on a life-cycle basis, emits about the same level of carbon per unit of electricity generated as wind and solar power. Long-term energy demand and supply analysis projects that global nuclear capacities will expand substantially, i.e. from 350 GW today to more than 1,500 GW by 2050. Uranium supply, spent fuel and waste management, and a non-proliferation nuclear fuel cycle are essential factors for sustainable nuclear power growth. An analysis of the uranium supply up to 2050 indicates that there is no real shortage of potential uranium available if based on the IIASA/WEC scenario on medium nuclear energy growth, although its market price may become more volatile. With regard to spent fuel and waste management, the short term prediction foresees that the amount of spent fuel will increase from the present 145,000 tHM to more than 260,000 tHM in 2015. The IPCC scenarios predicted that the spent fuel quantities accumulated by 2050 will vary between 525 000 tHM and 3 210 000 tHM. Even according to the lowest scenario, it is estimated that spent fuel quantity in 2050 will be double the amount accumulated by 2015. Thus, waste minimization in the nuclear fuel cycle is a central tenet of sustainability. The proliferation risk focusing on separated plutonium and resistant technologies is reviewed. Finally, the IAEA Project INPRO is briefly introduced. (author)

The nuclear fuel cycle

International Nuclear Information System (INIS)

Patarin, L.

2002-01-01

This book treats of the different aspects of the industrial operations linked with the nuclear fuel, before and after its use in nuclear reactors. The basis science of this nuclear fuel cycle is chemistry. Thus a recall of the elementary notions of chemistry is given in order to understand the phenomena involved in the ore processing, in the isotope enrichment, in the fabrication of fuel pellets and rods (front-end of the cycle), in the extraction of recyclable materials (residual uranium and plutonium), and in the processing and conditioning of wastes (back-end of the fuel cycle). Nuclear reactors produce about 80% of the French electric power and the Cogema group makes 40% of its turnover at the export. Thus this book contains also some economic and geopolitical data in order to clearly position the stakes. The last part, devoted to the management of wastes, presents the solutions already operational and also the research studies in progress. (J.S.)

Nuclear power

International Nuclear Information System (INIS)

Anon.

1980-01-01

The committee concludes that the nature of the proliferation problem is such that even stopping nuclear power completely could not stop proliferation completely. Countries can acquire nuclear weapons by means independent of commercial nuclear power. It is reasonable to suppose if a country is strongly motivated to acquire nuclear weapons, it will have them by 2010, or soon thereafter, no matter how nuclear power is managed in the meantime. Unilateral and international diplomatic measures to reduce the motivations that lead to proliferation should be high on the foreign policy agenda of the United States. A mimimum antiproliferation prescription for the management of nuclear power is to try to raise the political barriers against proliferation through misuse of nuclear power by strengthening the Non-Proliferation Treaty, and to seek to raise the technological barriers by placing fuel-cycle operations involving weapons-usable material under international control. Any such measures should be considered tactics to slow the spread of nuclear weapons and thus earn time for the exercise of statesmanship. The committee concludes the following about technical factors that should be considered in formulating nuclear policy: (1) rate of growth of electricity use is a primary factor; (2) growth of conventional nuclear power will be limited by producibility of domestic uranium sources; (3) greater contribution of nuclear power beyond 400 GWe past the year 2000 can only be supported by advanced reactor systems; and (4) several different breeder reactors could serve in principle as candidates for an indefinitely sustainable source of energy

Nuclear power, nuclear fuel cycle and waste management: Status and trends 1995. Part C of the IAEA Yearbook 1995

International Nuclear Information System (INIS)

1995-09-01

This report was jointly prepared by the Division of Nuclear Power and the Division of Nuclear Fuel Cycle and Waste Management as part of an annual overview of both global nuclear industry activities and related IAEA programmes. This year's report focuses on activities during 1994 and the status at the end of that year. The trends in the industry are projected to 2010. Special events and highlights of IAEA activities over the past year are also presented. Refs, figs and tabs

Nuclear Power, nuclear fuel cycle and waste management: Status and trends 1996. Part C of the IAEA yearbook 1996

International Nuclear Information System (INIS)

1996-09-01

This report was jointly prepared by the Division of Nuclear Power and the Division of Nuclear Fuel Cycle and Waste Management as part of an annual overview of both global nuclear industry activities and related IAEA programmes. This year's report focuses on activities during 1995 and the status at the end of that year. The trends in the industry are projected to the year 2010. Special events and highlights of IAEA activities over the past year are also presented. Refs, figs, tabs

Nuclear power - a reliable future

International Nuclear Information System (INIS)

Valeca, Serban

2002-01-01

The Ministry of Education and Research - Department of Research has implemented a national Research and Development program taking into consideration the following: - the requirements of the European Union on research as a factor of development of the knowledge-based society; - the commitments to the assimilation and enforcement of the recommendations of the European Union on nuclear power prompted by the negotiations of the sections 'Science and Research' and ' Energy' of the aquis communautaire; - the major lines of interest in Romania in the nuclear power field established by National Framework Program of Cooperation with IAEA, signed on April 2001; - the short and medium term nuclear options of the Romanian Government; - the objectives of the National Nuclear Plan. The major elements of the nuclear research and development program MENER (Environment, Energy, Resources) supported by the Department of Research of the Ministry of Education and Research are the following: - reactor physics and nuclear fuel management; - operation safety of the Power Unit 1 of Cernavoda Nuclear Electric Power Station; - improved nuclear technological solutions at the Cernavoda NPP; - development of technologies for nuclear fuel cycle; - operation safety of the other nuclear plants in Romania; - assessment of nuclear risks and estimation of the radiological impact on the environment; - behavior of materials under the reactor service conditions and environmental conditions; - design of nuclear systems and equipment for the nuclear power stations and nuclear facilities; - radiological safety; - application of nuclear techniques and technologies in industry, agriculture, medicine and other fields of social life. Research to develop high performance methods and equipment for monitoring nuclear impact on environment are conducted to endorse the measures for radiation protection. Also mentioned are the research on implementing a new type of nuclear fuel cycle in CANDU reactors as well as

International Nuclear Fuel Cycle Fact Book. Revision 5

International Nuclear Information System (INIS)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

1985-01-01

This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate

International Nuclear Fuel Cycle Fact Book. Revision 5

Energy Technology Data Exchange (ETDEWEB)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

1985-01-01

This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

International nuclear fuel cycle fact book. Revision 4

Energy Technology Data Exchange (ETDEWEB)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-03-01

This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

International nuclear fuel cycle fact book. Revision 4

International Nuclear Information System (INIS)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-03-01

This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate

New trends in nuclear power engineering development

International Nuclear Information System (INIS)

Krasin, A.K.

1974-01-01

The specific features are considered of three designs of nuclear power plants with fast reactors: three-circuit nuclear power plant with liquid sodium as primary and secondary coolant, in the third circuit water vapor being used as turbine working medium, dual cycle nuclear power plant with pressurized helium as primary coolant and water vapor as turbine working medium, direct cycle nuclear power plant with a dissociating gas (nitrogen tetroxide N 2 O 4 ) as reactor coolant and turbine working medium. The version of the direct cycle nuclear power plant with dissociating N 2 O 4 was proposed and being developed by the Institute of Nuclear Engineering of the Academy of Sciencies of the BSSR. The thermal and physical properties of the dissociating gas allow a high-power-density reactor core to be used with a hard neutron spectra resulting in a high breeding ratio and a short doubling time. The pressure range from 150 to 170 bar was proven for this coolant under laboratory conditions and structural materials were chosen that ensure all the components of the direct cycle nuclear power plant to be workable. At present it is difficult to say which of the three versions is the most advantageous. The further development of a full-scale prototypes of a commercial nuclear power plant with a fast reactor and investigation of their technical and economic parameters remain the problems of utmost importance. A possible use of nuclear reactors is shortly considered for process heat production, in ferrous metallurgy, for hydrogen and new isotope production, and for radiation chemistry as well

Environmental Health Impacts of Nuclear Fuel Cycle With Emphasis to Monitoring and Radiological Safety Control System

International Nuclear Information System (INIS)

Gad Allah, A.A.; El- Shanshory, A.I.

2010-01-01

Security of energy supply and global climatic changes due to carbon dioxide gas emission of fissile fuels encouraged many developed countries for planning to introduce nuclear power for energy generation. Recently, nuclear power provides approximately 20 % of the world's electricity, which is equivalent to a reduction in carbon emissions of 0.5 Gt of C/year. This is a modest contribution to the reduction of global carbon emissions, 6.5 Gt C/year. There are three types of nuclear fuel cycles that might be utilized for the increased production of energy: open, closed, or a symbiotic combination of different reactor types (such as thermal and fast neutron reactors). Within each cycle, the volume and composition of the nuclear waste and fissile material depend on the type of nuclear fuel, the amount of burn-up, the extent of radionuclide separation during reprocessing, and the types of material used to immobilize different radionuclides. Most analyses suggest that in order to have a significant impact on carbon emissions. By the year 2050, carbon free sources, such as nuclear power, would have to expand total energy production by a factor of three to ten. A three-fold increase in nuclear power capacity would result in a projected reduction in carbon emissions of 1 to 2 Gt C/year, depending on the type of the carbon-based energy source. This paper reviews, discusses and evaluates the relation between the different types of fuel cycles and their environmental impacts. The paper investigates the environmental impacts of the nuclear fuel cycle compared to fossil fuel energy system.. It also reviews the impact of an expansion of this scale on the generation of nuclear waste and fissile material that might be diverted to the production of nuclear weapons. Investigations of different wastes fissile and fertile mater in the fuel cycle have been estimated. The paper provides an overview of the main contaminates in the waste streams and effluents from nuclear fuel cycle

EPRI nuclear fuel-cycle accident risk assessment

International Nuclear Information System (INIS)

Anon.

1981-01-01

The present results of the nuclear fuel-cycle accident risk assessment conducted by the Electric Power Research Institute show that the total risk contribution of the nuclear fuel cycle is only approx. 1% of the accident risk of the power plant; hence, with little error, the accident risk of nuclear electric power is essentially that of the power plant itself. The power-plant risk, assuming a very large usage of nuclear power by the year 2005 is only approx. 0.5% of the radiological risk of natural background. The smallness of the fuel-cycle risk relative to the power-plant risk may be attributed to the lack of internal energy to drive an accident and the small amount of dispersible material. This work aims at a realistic assessment of the process hazards, the effectiveness of confinement and mitigation systems and procedures, and the associated likelihood of errors and the estimated size of errors. The primary probabilistic estimation tool is fault-tree analysis, with the release source terms calculated using physicochemical processes. Doses and health effects are calculated with CRAC (Consequences of Reactor Accident Code). No evacuation or mitigation is considered; source terms may be conservative through the assumption of high fuel burnup (40,000 MWd/t) and short cooling period (90 to 150 d); high-efficiency particulate air filter efficiencies are derived from experiments

Commercialization of nuclear fuel cycle business

International Nuclear Information System (INIS)

Yakabe, Hideo

1998-01-01

Japan depends on foreign countries almost for establishing nuclear fuel cycle. Accordingly, uranium enrichment, spent fuel reprocessing and the safe treatment and disposal of radioactive waste in Japan is important for securing energy. By these means, the stable supply of enriched uranium, the rise of utilization efficiency of uranium and making nuclear power into home-produced energy can be realized. Also this contributes to the protection of earth resources and the preservation of environment. Japan Nuclear Fuel Co., Ltd. operates four business commercially in Rokkasho, Aomori Prefecture, aiming at the completion of nuclear fuel cycle by the technologies developed by Power Reactor and Nuclear Fuel Development Corporation and the introduction of technologies from foreign countries. The conditions of location of nuclear fuel cycle facilities and the course of the location in Rokkasho are described. In the site of about 740 hectares area, uranium enrichment, burying of low level radioactive waste, fuel reprocessing and high level waste control have been carried out, and three businesses except reprocessing already began the operation. The state of operation of these businesses is reported. Hereafter, efforts will be exerted to the securing of safety through trouble-free operation and cost reduction. (K.I.)

Nuclear power experience

International Nuclear Information System (INIS)

1983-01-01

The International Conference on Nuclear Power Experience, organized by the International Atomic Energy Agency, was held at the Hofburg Conference Center, Vienna, Austria, from 13 to 17 September 1982. Almost 1200 participants and observers from 63 countries and 20 organizations attended the conference. The 239 papers presented were grouped under the following seven main topics: planning and development of nuclear power programmes; technical and economic experience of nuclear power production; the nuclear fuel cycle; nuclear safety experience; advanced systems; international safeguards; international co-operation. The proceedings are published in six volumes. The sixth volume contains a complete Contents of Volume 1 to 5, a List of Participants, Authors and Transliteration Indexes, a Subject Index and an Index of Papers by Number

Evaluation and optimization of a supercritical carbon dioxide power conversion cycle for nuclear applications

International Nuclear Information System (INIS)

Harvego, Edwin A.; McKellar, Michael G.

2011-01-01

There have been a number of studies involving the use of gases operating in the supercritical mode for power production and process heat applications. Supercritical carbon dioxide (CO 2 ) is particularly attractive because it is capable of achieving relatively high power conversion cycle efficiencies in the temperature range between 550degC and 750degC. Therefore, it has the potential for use with any type of high-temperature nuclear reactor concept, assuming reactor core outlet temperatures of at least 550degC. The particular power cycle investigated in this paper is a supercritical CO 2 recompression Brayton Cycle. The CO 2 recompression Brayton Cycle can be used as either a direct or indirect power conversion cycle, depending on the reactor type and reactor outlet temperature. The advantage of this cycle when compared to the helium Brayton Cycle is the lower required operating temperature; 550degC versus 750degC. However, the supercritical CO 2 recompression Brayton Cycle requires a high end operating pressure in the range of 20 MPa, which is considerably higher than the required helium Brayton cycle high end operating pressure of 7 MPa. This paper presents results of analyses performed using the UniSim process analyses software to evaluate the performance of the supercritical CO 2 recompression Brayton cycle for different reactor coolant outlet temperatures and mass flow rates. The UniSim model assumed a 600 MWt reactor power source, which provides heat to the power cycle at a maximum temperature of between 550degC and 850degC. Sensitivity calculations were also performed to determine the affect of reactor coolant mass flow rates for a reference reactor coolant outlet temperature of 750degC. The UniSim model used realistic component parameters and operating conditions to model the complete power conversion system. CO 2 properties were evaluated, and the operating range for the cycle was adjusted to take advantage of the rapidly changing conditions near the

Ecological problems of nuclear power

Energy Technology Data Exchange (ETDEWEB)

Babaev, N S; Demin, V F; Kuz' min, I I; Stepanchikov, V I [Gosudarstvennyj Komitet po Ispol' zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii

1978-10-01

Modern power sources including nuclear one are characterized. Basic information on radiation protection of man and biosphere is presented. Problems of radiation effect of nuclear fuel cycle enterprises on population and environment are discussed. Comparative evaluation of nuclear and thermal power effect on biosphere is made. It is shown that nuclear power is the safest power source at the present development state. The conclusion is drawn that the use of nuclear energy controlled and limited by scientifically founded norms does not present radiation hazard for population and environment.

Nuclear power in perspective

International Nuclear Information System (INIS)

Ringwood, A.E.

1980-01-01

The nuclear power debate hinges upon three major issues: radioactive waste disposal, reactor safety and proliferation. An alternative strategy for waste disposal is advocated which involves disposing of the radwaste (immobilized in SYNROC, a titanate ceramic waste form) in deep (4 km) drill-holes widely dispersed throughout the entire country. It is demonstrated that this strategy possesses major technical (safety) advantages over centralized, mined repositories. The comparative risks associated with coal-fired power generation and with the nuclear fuel cycle have been evaluated by many scientists, who conclude that nuclear power is far less hazardous. Considerable improvements in reactor design and safety are readily attainable. The nuclear industry should be obliged to meet these higher standards. The most hopeful means of limiting proliferation lies in international agreements, possibly combined with international monitoring and control of key segments of the fuel cycle, such as reprocessing

Energy analysis of nuclear power plants and their fuel cycle

International Nuclear Information System (INIS)

Held, C.; Moraw, G.; Schneeberger, M.; Szeless, A.

1977-01-01

Energy analysis has become an increasingly feasible and practical additional method for evaluating the engineering, economic and environmental aspects of power producing systems. Energy analysis compares total direct and indirect energy investment into construction and operation of power plants with their lifetime energy output. Statically we have applied this method to nuclear power producing sytems and their fuel cycles. Results were adapted to countries with various levels of industrialization and resources. With dynamic energy analysis different scenarios have been investigated. For comparison purposes fossil fueled and solar power plants have also been analyzed. By static evaluation it has been shown that for all types of power plants the energy investment for construction is shortly after plant startup being repaid by energy output. Static analyses of nuclear and fossil fuels have indicated values of fuel concentrations below which more energy is required for their utilization than can be obtained from the plants they fuel. In a further step these global results were specifically modified to the economic situations of countries with various levels of industrialization. Also the influence of energy imports upon energy analysis has been discussed. By dynamic energy analyses the cumulative energy requirements for specific power plant construction programs have been compared with their total energy output. Investigations of this sort are extremely valuable not only for economic reasons but especially for their usefulness in showing the advantages and disadvantages of a specific power program with respect to its alternatives. Naturally the impact of these investigations on the fuel requirements is of importance especially because of the today so often cited ''valuable cumulated fossil fuel savings''

Country nuclear power profiles. 2000 ed

International Nuclear Information System (INIS)

2001-03-01

The preparation of Country Nuclear Power Profiles was initiated within the framework of the IAEA programme on assessment and feedback of nuclear power plant performance. It responded to a need for a database and a technical document containing a description of the economic situation, the energy and the electricity sector and the primary organizations involved in nuclear power in IAEA Member States. In 1998, the first edition of the Country Nuclear Power Profiles was published focusing on the overall economic, energy and electricity situation in the country and on its nuclear power industrial structure and organizational framework. The compilation was made based on of 29 Member States with operating nuclear power plants by the end of 1995 and incorporated the 'Fact Sheets' on international, multilateral and bilateral agreements as collected by EXPO. In May 1999, an Advisory Group Meeting was organized with the purpose of updating the information in the Country Nuclear Power Profiles of each country, to reflect the new approaches and conditions of the national nuclear power programmes. The impact of the open electricity market, privatization and deregulation on the nuclear sector was an important aspect recommended by the experts to be taken in consideration. It was also recommended to periodically review the status and trends of nuclear industries in IAEA Member States and exchange information among experts of the lessons learned from the countries engaged in nuclear programmes, with a view to update the profiles at two year intervals. This second edition covers the changes in the new environment in the electricity as well as in the nuclear sector, be it that the situation differs from country to country. In general, the information is updated to 1999. For the preparation of this second edition, the IAEA received contributions from all 31 countries with operating power plants by the end of 1999, as well as Italy and the Islamic Republic of Iran. A database has been

Nuclear fuel cycles : description, demand and supply estimates

International Nuclear Information System (INIS)

Gadallah, A.A.; Abou Zahra, A.A.; Hammad, F.H.

1985-01-01

This report deals with various nuclear fuel cycles description as well as the world demand and supply estimates of materials and services. Estimates of world nuclear fuel cycle requirements: nuclear fuel, heavy water and other fuel cycle services as well as the availability and production capabilities of these requirements, are discussed for several reactor fuel cycle strategies, different operating and under construction fuel cycle facilities in some industrialized and developed countries are surveyed. Various uncertainties and bottlenecks which are recently facing the development of some fuel cycle components are also discussed, as well as various proposals concerning fuel cycle back-end concepts. finally, the nuclear fuel cycles activities in some developing countries are reviewed with emphasis on the egyptian plans to introduce nuclear power in the country. 11 fig., 16 tab

Nuclear power life cycle management, managing nuclear knowledge, and nuclear security. Introductory statement to the 5th scientific forum during the 46th session of the IAEA General Conference. Vienna, 17 September 2002

International Nuclear Information System (INIS)

ElBaradei, M.

2002-01-01

The document reproduces the text of the introductory statement made by the Director General of the IAEA at the 5th scientific forum organized during the 46th session of the IAEA General Conference, Vienna, 17 september 2002, on the nuclear power life cycle management, managing nuclear knowledge, and nuclear security. In the area of nuclear power life cycle management two aspects were emphasized: licence extension and facility decommissioning. Nuclear knowledge management includes ensuring the continued availability of the qualified personnel. Nuclear security must be considered for all nuclear applications, in a manner that encompasses all phases of nuclear activity - the use, storage and transport of nuclear and other radioactive material, as well as the design, operation, and decommissioning of nuclear facilities

Nuclear power at present and in the future. Sweden and the rest of the world

International Nuclear Information System (INIS)

2010-06-01

The report provides by no means a complete picture of nuclear power. There are a number of issues not covered, such as environmental impacts caused by the nuclear plants used (with the exception of the greenhouse gases that highlights some of report), the link with nuclear weapons and waste disposal. The share of nuclear power in Sweden in 2010 is higher than the average for the world The global net installed power of nuclear power in early 2010 was just over 370 GW e distributed over 436 nuclear power plants. In 2007, global electricity generation from nuclear power was about 14 percent of total electricity generation, compared with 44 percent in Sweden. The average availability for nuclear power plants was about 82 percent between 2005 and 2007. During the same period the availability in Swedish plants was lose to 84 percent. The Swedish availability has fallen, in 2004 the availability was comparable to that in Finland, which amounted to just over 94 percent between 2005 and 2007. The expansion of nuclear power may be limited by technical challenges in manufacturing infrastructure and a shortage of skilled labor. There is only a few reactor suppliers in the market and the quality demand of the material is much higher than for other major projects. Whether nuclear power is competitive with alternative investments or not is uncertain. The investment costs for building new reactors is high but the operational and maintenance costs are low compared to many other types of power sources. In an Emission Trading System nuclear power competitivity with fossil options increases. Nuclear power is a power source with low greenhouse gas emissions over its life cycle. Uranium is a limited resource and like other natural resources limited to a number of countries. Most nuclear reactors are also dependent on enrichment of the natural uranium. If an open or closed nuclear fuel cycle is used is crucial for how long the uranium reserves will last and how nuclear energy can grow

Cooling of nuclear power stations with high temperature reactors and helium turbine cycles

International Nuclear Information System (INIS)

Foerster, S.; Hewing, G.

1977-01-01

On nuclear power stations with high temperature reactors and helium turbine cycles (HTR-single circuits) the residual heat from the energy conversion process in the primary and intermediate coolers is removed from cycled gas, helium. Water, which is circulated for safety reasons through a closed circuit, is used for cooling. The primary and intermediate coolers as well as other cooling equipment of the power plant are installed within the reactor building. The heat from the helium turbine cycle is removed to the environment most effectively by natural draught cooling towers. In this way a net plant efficiency of about 40% is attainable. The low quantities of residual heat thereby produced and the high (in comparison with power stations with steam turbine cycles) cooling agent pressure and cooling water reheat pressure in the circulating coolers enable an economically favourable design of the overall 'cold end' to be expected. In the so-called unit range it is possible to make do with one or two cooling towers. Known techniques and existing operating experience can be used for these dry cooling towers. After-heat removal reactor shutdown is effected by a separate, redundant cooling system with forced air dry coolers. The heat from the cooling process at such locations in the power station is removed to the environment either by a forced air dry cooling installation or by a wet cooling system. (orig.) [de

International nuclear power status 2001

International Nuclear Information System (INIS)

Lauritzen, B.; Majborn, B.; Nonboel, E.; Oelgaard, P.L.

2002-04-01

This report is the eighth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2001, the report contains: 1) General trends in the development of nuclear power; 2) Nuclear terrorism; 3) Statistical information on nuclear power production (in 2000); 4) An overview of safety-relevant incidents in 2001; 5) The development in West Europe; 6) The development in East Europe; 7) The development in the rest of the world; 8) Development of reactor types; 9) The nuclear fuel cycle; 10) International nuclear organisations. (au)

Nuclear power and public opinion

Energy Technology Data Exchange (ETDEWEB)

1984-01-01

The diversity of factors involved in nuclear power development and the complexity of public attitudes towards this source of energy have raised the nuclear debate to a topic of national significance in all the OECD countries with nuclear programmes and even in some countries which have not embarked on the nuclear course. This study examines the different experiences of seventeen member countries and underlines basic approaches and practices aimed at winning greater public acceptance for nuclear power. The first part of the study is a country-by-country presentation of public acceptance activities and the role of the various public or private bodies involved. There is also a description of the background energy situation and the place of nuclear power, the evolution of the nuclear debate and a review of present public and political attitudes to nuclear energy. In the second part, some of the notable factors which determine public attitudes to, and perception of, nuclear energy have been assembled. The study points, in particular, to a number of general principles which require continuous implementation, not least because they contribute to placing nuclear energy in its proper context for the public. Vigorous government leadership in making energy choices, long term efforts in energy education, and open information policies can go a long way towards resolving many doubts about nuclear energy in the public mind. But, perhaps, above all, it is the continuing demonstration of the safe and efficient industrial operation of plants in the nuclear fuel cycle which will have the strongest influence on public opinion. In addition to these basic principles, the study calls attention to some of the most successful means of improving communication between the authorities and the public, notably at the local level. The contribution to the decision-making process of public participation is also evaluated in the light of recent national experiences.

Nuclear power and public opinion

International Nuclear Information System (INIS)

1984-01-01

The diversity of factors involved in nuclear power development and the complexity of public attitudes towards this source of energy have raised the nuclear debate to a topic of national significance in all the OECD countries with nuclear programmes and even in some countries which have not embarked on the nuclear course. This study examines the different experiences of seventeen member countries and underlines basic approaches and practices aimed at winning greater public acceptance for nuclear power. The first part of the study is a country-by-country presentation of public acceptance activities and the role of the various public or private bodies involved. There is also a description of the background energy situation and the place of nuclear power, the evolution of the nuclear debate and a review of present public and political attitudes to nuclear energy. In the second part, some of the notable factors which determine public attitudes to, and perception of, nuclear energy have been assembled. The study points, in particular, to a number of general principles which require continuous implementation, not least because they contribute to placing nuclear energy in its proper context for the public. Vigorous government leadership in making energy choices, long term efforts in energy education, and open information policies can go a long way towards resolving many doubts about nuclear energy in the public mind. But, perhaps, above all, it is the continuing demonstration of the safe and efficient industrial operation of plants in the nuclear fuel cycle which will have the strongest influence on public opinion. In addition to these basic principles, the study calls attention to some of the most successful means of improving communication between the authorities and the public, notably at the local level. The contribution to the decision-making process of public participation is also evaluated in the light of recent national experiences

Co-operation of the CMEA member countries in the developing power reactors of various types, including some aspects of their nuclear fuel cycles

International Nuclear Information System (INIS)

Barbur, I.; Barchenkov, A.; Molnar, L; Panasenkov, A.; Tolpygo, V.; Hake, V.; Shcherbinin, B.

1977-01-01

The report gives an account of the problems of projected development of atomic power and evaluates its role in the fuel and power complex and long-range development of interconnected power systems of the CMEA member countries. The report emphasizes the importance of scientific and technical co-operation in the creation of power reactors on thermal and fast neutrons with 1000-1500 MW unit electric capacity as well as in the elaboration of nuclear plants for heating services. It notes the positive experience of the International scientific and research group of scientists of the CMEA member countries carrying out reactor-physical studies on the critical assembly and its contribution to the elaboration of power reactors. The report contains basic conclusions from the development forecast for nuclear power of the CMEA member countries up to 1990 including forecasting methodology; role of nuclear power plants in saving natural and enriched uranium for a projected period; impact of nuclear power development rates on its structure (thermal and fast reactor ratio); relation between the beginning of mass commissioning of nuclear power plants with fast reactors and the integral demand for nuclear fuel; scale of required capacities of fuel cycle services; time dependence of fuel cycle on nuclear fuel requirements. It examines the problems and lists the results of scientific and technical co-operation of the CMEA member countries in the field of fuel cycle, including the transport of spent nuclear fuel, its recovery, reprocessing and radioactive waste disposal. Particular questions of co-operation of the CMEA member countries to secure radiation safety of nuclear power plants and environmental protection are analyzed. The report notes the role of international economic associations - ''Interatomenergo'' and ''Interatominstrument'' - in the accelerated development of nuclear power on the basis of cooperation and specialization in the manufacture of equipment for nuclear power

Benefits and hazards of nuclear power

International Nuclear Information System (INIS)

Barnert, H.; Borsch, P.; Feldmann, A.; Merz, E.; Muench, E.; Oesterwind, D.; Voss, A.; Wolters, J.

1979-09-01

Compilation of a seminar at the KFA Juelich on topical problems of nuclear power. Subjects: Energy demand, its expected development and possibilities of coverage; physical fundamentals and technical realisation of power generation by nuclear fission; fuel cycle problems and solutions; effects of radioactive radiation; safety of nuclear power plants and the nuclear hazard as compared with other hazards. (orig./RW) [de

Securing a safer, greener, expandable nuclear fuel cycle supply chain for future power production

International Nuclear Information System (INIS)

Capus, Georges

2009-01-01

After looking at what is necessary to sustainably ensure the global nuclear power plant fleet expansion, it becomes appearant that advanced reactor design should be accompanied with a greener and more flexible fuel cycle capability. The financial crisis has invaded all the front pages and our thoughts. However it has not rescheduled the growth of world population or reduced the desire of people in emerging economies to achieve a higher level of 'development'; nor has it alleviated climate change issues that demand CO2 constrained power sources. What is the outlook for nuclear power? On a worldwide basis, we have today a significant fleet of nuclear power plants, operating well, upgrading output, extending lifetime, and producing not only a safe reliable flow of electricity but a good flow of cash as well. For the countries hosting significant shares of this fleet, their nuclear power plants are increasingly precious assets, and despite the financial crisis, most of them are considering expansion of their nuclear fleets. For the others, the desire to access such a reliable and ultimately cheap source of energy will last longer than the temporary difficulties to get its financing. In short, the outlook for a massive phase of new nuclear builds remains very likely. Then comes the consequential issue of the nuclear fuel supply chain. From uranium exploration and production to back end solutions, most of the existing facilities were designed and startup decades ago. The question is therefore, does this supply chain offer the requested characteristics to sustain the nuclear power plants fleet for the long run? By requested characteristics, it is meant not only adequate capacity and improvement of quality, but also environmentally friendly new designs and processes. This paper is aimed at recalling the current situation of the supply chain, then at describing the status of major projects, and finally at identifying some gaps and issues

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-01-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the ''front end'' and ''back end'' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of the Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-10-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the 'front end' and 'back end' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of The Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

Scientific forum during the 46th regular session of the IAEA General Conference. Topical issues: Nuclear Power - Life Cycle Management; Managing Nuclear Knowledge; Nuclear Security. Programme and synopses

International Nuclear Information System (INIS)

2002-01-01

In response to the recommendations of several Agency advisory committees, to address issues related to nuclear power life cycle management, knowledge management in the field of nuclear power, and security of radiation sources and other nuclear material the IAEA is organizing the scientific forum to be held during the General Conference. The purpose of the meeting is to sharpen awareness and understanding of the emerging concerns about the aging of nuclear power plants, maintenance and preservation of knowledge and expertise in nuclear science, technology and applications, to emphasise the significance of security and physical protection of radiation sources and other radioactive material, and to better comprehend the role of the Agency in these processes

International nuclear fuel cycle fact book. Revision 6

International Nuclear Information System (INIS)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

1986-01-01

The International Fuel Cycle Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2

NUCLEAR POWER PLANT

Science.gov (United States)

Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

1963-05-14

A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

Nuclear fuel cycle assessment of India: A technical study for U.S.-India cooperation

Science.gov (United States)

Krishna, Taraknath Woddi Venkat

The recent civil nuclear cooperation proposed by the Bush Administration and the Government of India has heightened the necessity of assessing India's nuclear fuel cycle inclusive of nuclear materials and facilities. This agreement proposes to change the long-standing U.S. policy of preventing the spread of nuclear weapons by denying nuclear technology transfer to non-NPT signatory states. The nuclear tests in 1998 have convinced the world community that India would never relinquish its nuclear arsenal. This has driven the desire to engage India through civilian nuclear cooperation. The cornerstone of any civilian nuclear technological support necessitates the separation of military and civilian facilities. A complete nuclear fuel cycle assessment of India emphasizes the entwinment of the military and civilian facilities and would aid in moving forward with the separation plan. To estimate the existing uranium reserves in India, a complete historical assessment of ore production, conversion, and processing capabilities was performed using open source information and compared to independent reports. Nuclear energy and plutonium production (reactor- and weapons-grade) was simulated using declared capacity factors and modern simulation tools. The three-stage nuclear power program entities and all the components of civilian and military significance were assembled into a flowsheet to allow for a macroscopic vision of the Indian fuel cycle. A detailed view of the nuclear fuel cycle opens avenues for technological collaboration. The fuel cycle that grows from this study exploits domestic thorium reserves with advanced international technology and optimized for the existing system. To utilize any appreciable fraction of the world's supply of thorium, nuclear breeding is necessary. The two known possibilities for production of more fissionable material in the reactor than is consumed as fuel are fast breeders or thermal breeders. This dissertation analyzes a thermal

Nuclear power and weapons proliferation

International Nuclear Information System (INIS)

Greenwood, T.; Rathjens, C.W.; Ruina, J.

1977-01-01

The relationship between nuclear weapons development and nuclear electric power is examined. A brief description of nuclear weapons design is first given. This is then followed by a discussion of various aspects of nuclear power technology and of how they affect a nuclear weapon programme. These include fuel cycles, chemical reprocessing of spent fuel, uranium enrichment, and the control of dissemination of nuclear technology. In conclusion there is a discussion of possible political and institutional controls for limiting nuclear proliferation. (U.K.)

Nuclear power technology system with molten salt reactor for transuranium nuclides burning in closed fuel cycle

International Nuclear Information System (INIS)

Alekseev, P.N.; Dudnikov, A.A.; Ignatiev, V.V.; Prusakov, V.N.; Ponomarev-Stepnoy, N.N.; Subbotin, S.A.

2000-01-01

A concept of nuclear power technology system with homogeneous molten salt reactors for burning and transmutation of long-lived radioactive toxic nuclides is considered in the paper. Disposition of such reactors in enterprises of fuel cycle allows to provide them with power and facilitate solution of problems with rad waste with minimal losses. (Authors)

Nuclear energy: The role of innovation. Vienna, 23 June 2003. Conference on innovative technologies for nuclear fuel cycles and nuclear power

International Nuclear Information System (INIS)

ElBaradei, M.

2003-01-01

First, the scope of our vision for the future of nuclear power must be global. While we often point out that nuclear power currently provides about 16% of global electricity, we note less often that some 83% of nuclear capacity is concentrated in industrialized countries. If nuclear power is to play a major role in meeting this demand for additional energy, it will require innovative approaches - both technological and otherwise - to match the needs of users not only in industrialized but also in developing countries. Secondly, innovation must be responsive to concerns that remain about nuclear power, and should be 'smart' in taking into account new developments and expected future trends. For example, innovation should ensure that new reactor and fuel cycle technologies incorporate inherent safety features, proliferation resistant characteristics, and reduced generation of waste. Consideration should be given to physical protection and other characteristics that will reduce the vulnerability of nuclear facilities and materials to theft, sabotage and terrorist acts. Awareness of needs other than electricity generation can help to make the nuclear contribution more substantial. Third, nuclear innovation efforts should be co-operative and collaborative in nature. The most important outcome of this collaboration may be, as I have already suggested, a better understanding of user needs and requirements worldwide. The IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was developed with precisely this objective in mind - to engender the broadest possible international collaboration, to permit the scientific and technological innovation that would ensure that nuclear energy remains a viable option for future generations. INPRO recently completed its work on defining user requirements related to economics, safety, proliferation resistance and the environment, bringing Phase 1A of the project to a close. The INPRO Steering Committee last

Financing the nuclear fuel cycle

International Nuclear Information System (INIS)

Stephany, M.

1975-01-01

While conventional power stations usually have fossil fuel reserves for only a few weeks, nuclear power stations, because of the relatively long time required for uranium processing from ore extraction to the delivery of the fuel elements and their prolonged in-pile time, require fuel reserves for a period of several years. Although the specific fuel costs of nuclear power stations are much lower than those of conventional power stations, this results in consistently higher financial requirements. But the problems involved in financing the nuclear fuel do not only include the aspect of financing the requirements of reactor operators, but also of financing the facilities of the nuclear fuel cycle. As far as the fuel supply is concerned, the true financial requirements greatly exceed the mere purchasing costs because the costs of financing are rather high as a consequence of the long lead times. (orig./UA) [de

International nuclear power status 2002

International Nuclear Information System (INIS)

Lauritzen, B.; Majborn, B.; Nonboel, E.; Oelgaard, P.L.

2003-03-01

This report is the ninth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2002, the report contains: 1) General trends in the development of nuclear power; 2) Decommissioning of the nuclear facilities at Risoe National Laboratory: 3) Statistical information on nuclear power production (in 2001); 4) An overview of safety-relevant incidents in 2002; 5) The development in West Europe; 6) The development in East Europe; 7) The development in the rest of the world; 8) Development of reactor types; 9) The nuclear fuel cycle; 10) International nuclear organisations. (au)

International nuclear fuel cycle fact book. Revision 6

Energy Technology Data Exchange (ETDEWEB)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

1986-01-01

The International Fuel Cycle Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2.

Development of nuclear power

International Nuclear Information System (INIS)

1960-01-01

The discussion on the development of nuclear power took place on 28 September 1960 in Vienna. In his opening remarks, Director General Cole referred to the widespread opinion that 'the prospect of cheap electricity derived from nuclear energy offers the most exciting prospect for improving the lot of mankind of all of the opportunities for uses of atomic energy'. He then introduced the four speakers and the moderator of the discussion, Mr. H. de Laboulaye, IAEA Deputy Director General for Technical Operations. n the first part of the discussion the experts addressed themselves in turn to four topics put forward by the moderator. These were: the present technical status of nuclear power, the present costs of nuclear power, prospects for future reductions in the cost of nuclear power, and applications of nuclear power in less-developed areas

Contribution of Heavy Water Board in nuclear fuel cycle technologies. Contributed Paper IT-03

International Nuclear Information System (INIS)

Mohanty, P.R.

2014-01-01

The three stage Indian nuclear power programme envisages use of closed nuclear fuel cycle and thorium utilization as its mainstay for long term energy security on sustainable basis. India is committed to realize this objective through the development and deployment of frontier technologies pertaining to all aspects of a closed nuclear fuel cycle. Comprehensive indigenous capabilities have been developed in all aspects of nuclear power and associated fuel cycles. Heavy Water Board (HWB), with its abiding objective of fulfilling demand of heavy water for India's flourishing nuclear power program, is one of the frontrunner in Nuclear Fuel Cycle Technology. HWB is now engaged in wide spectrum of activities in various facets of fuel cycle covering all the three stages of Indian Nuclear Power Programme. HWB is contributing to Nuclear Fuel Cycle through large scale production and sustained supply of key input materials including heavy water, solvents for nuclear hydrometallurgy, 10 B enriched boron etc

Impacts on human health from the coal and nuclear fuel cycles and other technologies associated with electric power generation and transmission

International Nuclear Information System (INIS)

Radford, E.P.

1980-01-01

Major public health impacts of electric power generation and transmission associated with the nuclear fuel cycle and with coal use are evaluated. Only existing technology is evaluated. The only health effects of concern are those leading to definable human disease and injury. Health effects are scaled to a nominal 1000 Megawatt (electric) plant fueled by either option. Comparison of the total health effects to the general public gives: nuclear, 0.03 to 0.05 major health effects per 1000 MWe per year; coal, 0.7 to 3.7 per 1000 MWe per year. Thus for the general public the health risks from the coal cycle are about 50 times greater than for the nuclear cycle. Health effects to workers in the industry are currently quite high. For the nuclear cycle, 4.6 to 5.1 major health impacts per 1000 MWe per year; for coal, 6.5 to 10.9. The two-fold greater risk for the coal cycle is primarily due to high injury rates in coal miners. There is no evidence that electrical transmission contributes any health effects to the general public, except for episodes where broken power lines come in contact with people. For power line workers, the risk is estimated at 0.1 serious injury per 1000 MWe per year

MHR fuel cycle options for future sustainability of nuclear power

International Nuclear Information System (INIS)

Baxter, Alan; Venneri, Francesco; Rodriguez, Carmelo; Fikani, Michael

2005-01-01

The future sustainability of the nuclear option is not significantly tied to the level of resources. For example, current high quality uranium reserves (∼3.34x10 6 tons) are enough for more than 55 years at present consumption rates (IAEA estimate). Doubling of the present uranium ore price (∼$26/kg) could create about a tenfold increase in resources, providing more than 550 years of supply at present rates (World Nuclear Association estimate). There are also thorium reserves which are estimated to be about three times those of uranium, and would allow for a significant increase in annual consumption levels. The key to a sustainable nuclear future is really tied to the political and technical problems of long term waste disposal, and the perceived risks of nuclear weapons proliferation. Thus fuel cycle options for a sustainable nuclear future must address and solve these issues. High temperature, Gas-Cooled, Graphite Moderated, reactors (MHRs) have nuclear and operational characteristics to provide multiple fuel cycle options to solve these issues. Three fuel cycles for the MHD are described in this paper, and their capabilities for meeting a sustainable nuclear future in terms of nuclear waste minimization and destruction, and reduction of proliferation risk, are discussed. (author)

Initial Screening of Thermochemical Water-Splitting Cycles for High Efficiency Generation of Hydrogen Fuels Using Nuclear Power

International Nuclear Information System (INIS)

Brown, L.C.; Funk, J.F.; Showalter, S.K.

1999-01-01

OAK B188 Initial Screening of Thermochemical Water-Splitting Cycles for High Efficiency Generation of Hydrogen Fuels Using Nuclear Power There is currently no large scale, cost-effective, environmentally attractive hydrogen production process, nor is such a process available for commercialization. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Fossil fuels are polluting and carbon dioxide emissions from their combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. Almost 800 literature references were located which pertain to thermochemical production of hydrogen from water and over 100 thermochemical watersplitting cycles were examined. Using defined criteria and quantifiable metrics, 25 cycles have been selected for more detailed study

Impacts on human health from the coal and nuclear fuel cycles and other technologies associated with electric power generation and transmission

International Nuclear Information System (INIS)

Radford, E.P.

1980-07-01

The report evaluates major public health impacts of electric power generation and transmission associated with the nuclear fuel cycle and with coal use. Only existing technology is evaluated. For the nuclear cycle, effects of future use of fuel reprocessing and long-term radioactive waste disposal are briefly considered. The health effects of concern are those leading to definable human disease and injury. Health effects are scaled to numbers of persons and activities associated with a nominal 1000-megawatt electric plant fueled by either option. Comparison of the total health effects to the general public shows that the health risks from the coal cycle are about 50 times greater than for the nuclear cycle (coal, 0.7-3.7 major health effects per 1000 MWe per year; nuclear, 0.03-0.05 per 1000 MWe per year). For workers, these rates are higher. No evidence is found that electrical transmission contributes any health effects to the general public, except when broken power lines come in contact with people

Nuclear power in western society

International Nuclear Information System (INIS)

Franklin, N.L.

1977-01-01

The degree to which problems of public acceptance have contributed to the slowdown in progress of nuclear power in Western European countries and the USA is discussed. Some of the effects on the nuclear power industry, i.e. the electrical utilities, the power station suppliers, and the fuel cycle contractors are described. The problem of the lack of public acceptance is examined by consideration of four areas: the position of the employee working in nuclear installations, opposition from the local community, the question of terrorism and its impact on nuclear policy, and finally, what is felt to constitute the greatest anxiety concerning nuclear power, that of proliferation. (U.K.)

Feasibility and desirability of employing the thorium fuel cycle for power generation - 254

International Nuclear Information System (INIS)

Sehgal, B.R.

2010-01-01

Thorium fuel cycle for nuclear power generation has been considered since the very start of the nuclear power era. In spite of a very large amount of research, experimentation, pilot scale and prototypic scale installations, the thorium fuel was not adopted for large scale power generation [1,2]. This paper reviews the developments over the years on the front and the back-end of the thorium fuel cycle and describes the pros and cons of employing the thorium fuel cycle for large generation of nuclear power. It examines the feasibility and desirability of employing the thorium fuel cycle in concert with the uranium fuel cycle for power generation. (authors)

Clean nuclear power (2. part)

International Nuclear Information System (INIS)

Rocherolles, R.

1998-01-01

The 450 nuclear power plants which produce 24% of world electricity do not generate greenhouse gas effects, but 8,000 tonnes per year of irradiated, radioactive fuel. The first article which was published in the July-August 1997 issue of this journal, described the composition and management of these fuels. This article wish to show the advantage of 'advanced re-processing', which would separate fission products from actinides, in order to incinerate them separately in dedicated fuels and reactors, which, from an ecological point of view, seems more efficient than burying them underground in deep, geological layers. To rid the planet of waste which is continuing to build up, the first step is to build 'incinerators' which will eliminate fission products by slow neutron assisted neutronic capture, and actinides by fast neutron assisted fission. Various projects have been set up, in particular, in Los Alamos, Japan and the CERN. The Carlo Rubbia hybrid machine operating on the well-known thorium cycle is the most advanced project. An incinerator connected up to standard PWR reactor produces no actinide, and reduces the existing stock of plutonium. However, the proper solution, obviously, is to no longer produce waste along with power; second generation nuclear fission will do this. The CERN team bas studied a clean reactor, producing practically no actinides, or fission products, more or less. Thus, the solution to the problem of waste is at hand, and nuclear power will be cleaner that all other types of power. The world market opening up to clean nuclear power is about 1,300 Gigawatts, or 1,300 plants of 1,000 Megawatts. Remarkable progress is taking place under our very eyes; soon we will have clean power in sufficient quantities, at a lower cost than that of other forms of power. (authors)

Concepts for space nuclear multi-mode reactors

International Nuclear Information System (INIS)

Myrabo, L.; Botts, T.E.; Powell, J.R.

1983-01-01

A number of nuclear multi-mode reactor power plants are conceptualized for use with solid core, fixed particle bed and rotating particle bed reactors. Multi-mode systems generate high peak electrical power in the open cycle mode, with MHD generator or turbogenerator converters and cryogenically stored coolants. Low level stationkeeping power and auxiliary reactor cooling (i.e., for the removal of reactor afterheat) are provided in a closed cycle mode. Depending on reactor design, heat transfer to the low power converters can be accomplished by heat pipes, liquid metal coolants or high pressure gas coolants. Candidate low power conversion cycles include Brayton turbogenerator, Rankine turbogenerator, thermoelectric and thermionic approaches. A methodology is suggested for estimating the system mass of multi-mode nuclear power plants as a function of peak electric power level and required mission run time. The masses of closed cycle nuclear and open cycle chemical power systems are briefly examined to identify the regime of superiority for nuclear multi-mode systems. Key research and technology issues for such power plants are also identified

The debate on nuclear power

International Nuclear Information System (INIS)

Bethe, H.A.

1977-01-01

The need for nuclear power is pointed out. The Study Group on Nuclear Fuel Cycles of the American Physical Society has studied the problem of waste disposal in detail and has found that geological emplacement leads to safe waste disposal. The relation between nuclear power and weapons proliferation is discussed. The problem of preventing proliferation is primarily a political problem, and the availability of nuclear power will contribute little to the potential for proliferation. However, to further reduce this contribution, it may be desirable to keep fast-breeder reactors under international control and to use only converters for national reactors. The desirable converter is one which has a high conversion ratio, probably one using the thorium cycle, 233 U, and heavy water as the moderator. The nuclear debate in the United States of America is discussed. Work on physical and technical safeguards in the USA against diversion of fissile materials is mentioned. (author)

Comparison of fuel cycles characteristics for nuclear energy systems based on WWER-TOI and BN-1200 reactors

International Nuclear Information System (INIS)

Kagramanyan, V.S.; Kalashnikov, A.G.; Kapranova, Eh.N.; Puzakov, A.Yu.

2014-01-01

Authors determine the characteristics of the fuel cycle (FC) based on stationary nuclear power system based on WWER-TOI and BN-1200 reactors with fuel of different composition. Characteristics of reactor systems with partial or complete spent nuclear fuel reprocessing and recycling of plutonium are compared to those of the reference system consisting only of WWER-TOI with uranium oxide fuel, operating in an open FC [ru

Nuclear power in the competitive environment

International Nuclear Information System (INIS)

Schlissel, D.A.

1995-01-01

Nuclear power was originally promoted as being able to produce electricity that would be open-quotes too cheap to meter.close quotes However, large construction cost overruns and rapidly rising operating costs caused many nuclear power plants instead to be very expensive sources of electricity. As a result, many nuclear utilities will face increasing cost pressures in the future competitive environment from lower-cost producers. In fact, the threat to nuclear utilities is so severe that many industry analysts are projecting that more that $70 billion of the utilities' remaining investments in nuclear plants will be open-quotes stranded,close quotes i.e., unrecoverable in the competitive environment. Others in the industry have speculated that many of the 150 major U.S. electric utilities, a large number of which are nuclear, could be swept away by competition, leaving fewer than fifty utilities. This paper will examine how utilities are attempting to improve the cost competitiveness of operating today's nuclear power plants. It will also identify some of the potential consequences of competition for nuclear power and the regulatory role of the U.S. Nuclear Regulatory Commission (NRC). Finally, this paper will address how the changing power markets will affect the prospects for the next generation of nuclear power plants

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

1993-01-01

The nuclear fuel cycle covers the procurement and preparation of fuel for nuclear power reactors, its recovery and recycling after use and the safe storage of all wastes generated through these operations. The facilities associated with these activities have an extensive and well documented safety record accumulated over the past 40 years by technical experts and safety authorities. This report constitutes an up-to-date analysis of the safety of the nuclear fuel cycle, based on the available experience in OECD countries. It addresses the technical aspects of fuel cycle operations, provides information on operating practices and looks ahead to future activities

Nuclear power generation modern power station practice

CERN Document Server

1971-01-01

Nuclear Power Generation focuses on the use of nuclear reactors as heat sources for electricity generation. This volume explains how nuclear energy can be harnessed to produce power by discussing the fundamental physical facts and the properties of matter underlying the operation of a reactor. This book is comprised of five chapters and opens with an overview of nuclear physics, first by considering the structure of matter and basic physical concepts such as atomic structure and nuclear reactions. The second chapter deals with the requirements of a reactor as a heat source, along with the diff

The future of nuclear power

International Nuclear Information System (INIS)

Corak, Z.

2004-01-01

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

Nuclear Power and Resource Efficiency—A Proposal for a Revised Primary Energy Factor

Directory of Open Access Journals (Sweden)

Ola Eriksson

2017-06-01

Full Text Available Measuring resource efficiency can be achieved using different methods, of which primary energy demand is commonly used. The primary energy factor (PEF is a figure describing how much energy from primary resources is being used per unit of energy delivered. The PEF for nuclear power is typically 3, which refers to thermal energy released from fission in relation to electricity generated. Fuel losses are not accounted for. However; nuclear waste represents an energy loss, as current plans for nuclear waste management mostly include final disposal. Based on a literature review and mathematical calculations of the power-to-fuel ratio for nuclear power, PEF values for the open nuclear fuel cycle (NFC option of nuclear power and different power mixes are calculated. These calculations indicate that a more correct PEF for nuclear power would be 60 (range 32–88; for electricity in Sweden (41% nuclear power PEF would change from 1.8 to 25.5, and the average PEF for electricity in the European Union (EU would change from 2.5 to 18. The results illustrate the poor resource efficiency of nuclear power, which paves the way for the fourth generation of nuclear power and illustrates the policy implication of using PEFs which are inconsistent with current waste management plans.

Nuclear Fusion Fuel Cycle Research Perspectives

International Nuclear Information System (INIS)

Chung, Hongsuk; Koo, Daeseo; Park, Jongcheol; Kim, Yeanjin; Yun, Sei-Hun

2015-01-01

As a part of the International Thermonuclear Experimental Reactor (ITER) Project, we at the Korea Atomic Energy Research Institute (KAERI) and our National Fusion Research Institute (NFRI) colleagues are investigating nuclear fusion fuel cycle hardware including a nuclear fusion fuel Storage and Delivery System (SDS). To have a better knowledge of the nuclear fusion fuel cycle, we present our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). To have better knowledge of the nuclear fusion fuel cycle, we presented our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). Our efforts to enhance the tritium confinement will be continued for the development of cleaner nuclear fusion power plants

Opening up the future in space with nuclear power

International Nuclear Information System (INIS)

Buden, D.; Angelo, J. Jr.

1985-01-01

Man's extraterrestrial development is dependent on abundant power. For example, space-based manufacturing facilities are projected to have a power demand of 300 kWe by the end of this Century, and several megawatts in the early part of next millennium. The development of the lunar resource base will result in power needs ranging from an initial 100 kW(e) to many megawatts. Human visits to Mars could be achieved using a multimegawatt nuclear electric propulsion system or high thrust nuclear rockets. Detailed exploration of the solar system will also be greatly enhanced by the availability of large nuclear electric propulsion systems. All of these activities will require substantial increases in space power - hundreds of kilowatts to many megawatts. The challenge is clear: how to effectively use nuclear energy to support humanity's expansion into space

The use of energy analysis and indexes of energy efficiency in nuclear power

International Nuclear Information System (INIS)

D'yakonov, E.I.; Ignatenko, E.I.

1991-01-01

The results of calculating the indexes of energy efficiency for NPPs with the WWER-1000 and RBMK-1000 reactors, heat and power NPPs with the WWER-1000 and dictrict heating NPPs with the AST-500 reactor in three fuel cycles, namely, the open one and with uranium and plutonium recycles, are considered. Complex account for the quantity and quality of produced and consumed energy provides for objective evaluation of the indexes of energy efficiency during comparative analysis of nuclear power plants with different types of reactors. It is shown that complex use of the energy produced at a NPP provides for increase of indexes of energy efficiency. The highest indexes are obtained for heat and power NPP with the WWER-1000 reactor in the open fuel cycle, with uranium and plutonium recycle and for NPP with the WWER-1000 reactor with plutonium recycle

Benefits and risks of nuclear power

International Nuclear Information System (INIS)

Barnert, H.; Borsch, P.; Feldmann, A.; Merz, E.; Muench, E.; Oesterwind, D.; Voss, A.

1977-03-01

Discussion, in a popular form, of issues of interest for an unemotional information of the public on problems of nuclear power: 1) Energy consumption, its assumed growth, and possible ways of supply; 2) the physical fundamental and technical realisation of power generation by nuclear fission; 3) problems of the fuel cycle and possible solutions; 4) the effects of radioactive radiation; 5) the safety of nuclear power plants and the risks of nuclear power as compared to other technical and natural risks. (orig./HP) [de

Nuclear power generation and nuclear non-proliferation

International Nuclear Information System (INIS)

Rathjens, G.

1979-01-01

The main points existing between nuclear energy development and nuclear non-proliferation policy are reviewed. The solar energy and other energy will replace for nuclear fission energy in the twenty first century, but it may not occur in the first half, and the structure has to be established to continue the development of nuclear fission technology, including breeder reactor technology. In the near future, it should be encouraged to use advanced thermal reactors if they are economic and operated with safety. Miserable results may be created in the worldwide scale, if a serious accident occurs anywhere or nuclear power reactors are utilized for military object. It is estimated to be possible to develop the ability of manufacturing nuclear weapons within two or three years in the countries where the industry is highly developed so as to generate nuclear power. It is also difficult to take measures so that nuclear power generation does not increase nuclear proliferation problems, and it is necessary to mitigate the motive and to establish the international organization. Concensus exists that as the minimum security action, the storage and transportation of materials, which can be directly utilized for nuclear weapons, should be decided by the international system. The most portions of sensitive nuclear fuel cycle should be put under the international management, as far as possible. This problem is discussed in INFCE. Related to the nuclear nonproliferation, the difference of policy in fuel cycle problems between USA and the other countries, the enrichment of nuclear fuel material, especially the reasons to inhibit the construction of additional enrichment facilities, nuclear fuel reprocessing problems, radioactive waste disposal, plutonium stock and plutonium recycle problems are reviewed. (Nakai, Y.)

Development of System Engineering Technology for Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Kim, Hodong; Choi, Iljae

2013-04-01

The development of efficient process for spent fuel and establishment of system engineering technology to demonstrate the process are required to develop nuclear energy continuously. The demonstration of pyroprocess technology which is proliferation resistance nuclear fuel cycle technology can reduce spent fuel and recycle effectively. Through this, people's trust and support on nuclear power would be obtained. Deriving the optimum nuclear fuel cycle alternative would contribute to establish a policy on back-end nuclear fuel cycle in the future, and developing the nuclear transparency-related technology would contribute to establish amendments of the ROK-U. S. Atomic Energy Agreement scheduled in 2014

International issue: the nuclear fuel cycle

International Nuclear Information System (INIS)

Anon.

1982-01-01

In this special issue a serie of short articles of informations are presented on the following topics: the EEC's medium term policy regarding the reprocessing and storage of spent fuel, France's natural uranium supply, the Pechiney Group in the nuclear field, zircaloy cladding for nuclear fuel elements, USSI: a major French nuclear engineering firm, gaseous diffusion: the only commercial enrichment process, the transport of nuclear materials in the fuel cycle, Cogema and spent fuel reprocessing, SGN: a leader in the fuel cycle, quality control of mechanical, thermal and termodynamic design in nuclear engineering, Sulzer's new pump testing station in Mantes, the new look of the Ateliers et Chantiers de Bretagne, tubes and piping in nuclear power plants, piping in pressurized water reactor. All these articles are written in English and in French [fr

The Union view of back end fuel cycle provisions for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1981-01-01

After a long political and technical discussion, the German trade unions united in the German Federation of Labor (DGB) arrived at the finding that back end fuel cycle provisions for nuclear power plants in the Federal Republic of Germany, in addition to the present concept of the Government providing for a reprocessing plant, should also include studies of the alternative possibility to store spent fuel elements over long periods of time, perhaps with a possibility to recover them later. That decision is also based on a report by the Nuclear Technology Working Group of the Metal Workers Union (IG Metall) and the Public Workers Union (OeTV). (orig.) [de

Opportunities and challenges for emerging nuclear power states

International Nuclear Information System (INIS)

Nkong-Njock, V.; Facer, R.I.; Boussaha, A.

2009-01-01

) resources including financial and human, (iv) site selection and transport of radioactive materials and (vi) fuel cycle and waste management including nuclear waste storage and disposal. The proliferation risks associated with the nuclear fuel cycle are issues of concern requiring that nuclear power facilities are operated in an open and transparent manner. But above all that, the main critical and challenging issues in introducing nuclear power in a State is to ensure and maintain the necessary trust and confidence on the nuclear power programme. In this connection and in line with its mandate, the IAEA is devoting increased attention to its special role in advancing nuclear energy and safety around the globe, thus ensuring that Member States use nuclear energy efficiently, safely, securely and with minimal proliferation risk. The IAEA supports the safe and peaceful use of nuclear power by providing standards, guidance, review and assessment, inspections and assistance related to (i) Technology, (ii) Safety and security and (iii) Safeguards. (Author)

International nuclear power status 2000

International Nuclear Information System (INIS)

Lauritzen, B.; Majborn, B.; Nonboel, E.; Oelgaard, P.L.

2001-03-01

This report is the seventh in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2000, the report contains: 1. General trends in the development of nuclear power. 2. Deposition of low-level radioactive waste. 3. Statistical information on nuclear power production (in 1999). 4. An overview of safety-relevant incidents in 2000. 5. The development in Sweden. 6. The development in Eastern Europe. 7. The development in the rest of the world. 8. Trends in the development of reactor types. 9. Trends in the development of the nuclear fuel cycle. (au)

Nuclear power in open energy markets: A case study of Turkey

International Nuclear Information System (INIS)

Erdogdu, Erkan

2007-01-01

For many decades, like many developed countries, Turkey has controlled her electricity sector as a state-owned monopoly. However, faced with rapid electricity demand growth, Turkey started to consider nuclear option. The present paper aims at evaluating both the present status of nuclear power in general and its implications for Turkish energy market in particular. After examining existing nuclear power technology and providing a brief overview of nuclear power economics; it focuses on the repercussions of nuclear power for Turkish energy market. The paper concludes that, in the short run, it may be considered to keep nuclear power within Turkish energy mix because it is an important carbon-free source of power that can potentially make a significant contribution to both Turkey's future electricity supply and efforts to strengthen Turkey's security of supply. However, in the long term, nuclear power should be retained in Turkey only if it has a lower cost than competing technologies

Nuclear power and environmental policy

International Nuclear Information System (INIS)

Pershing, J.

2000-01-01

Nuclear power, which presently accounts for approximately 20% of global electricity generation is still beset with environmental problems. Such problems are found throughout the fuel cycle - from mining and milling to processing, to plant operation and finally to waste disposal. While projected radioactive releases for normal operation is extremely low, much of the environmental risk comes from the potential for accidents. A list of the most significant nuclear accidents that occurred between 1966 and 1999 is given. On the other hand nuclear power offers great environmental benefits particularly when compared to other energy sources: all along the fuel cycle comparatively very few wastes are produced. In a world becoming more and more aware of environmental problems, it seems that there is no definitive conclusion about nuclear energy. (A.C.)

The future of nuclear power in Mexico

International Nuclear Information System (INIS)

Morales, A.A.

1980-01-01

The future of nuclear power in Mexico shows interesting aspects: the nuclear power is the source of energy that can supply large proportions of energy, that the country needs; the Kw/h of nuclear power is the most economic energy; the installation of 20 nucleoelectric plants will grant future jobs, the associated nuclear industry can be nationally integrated in the natural uranium cycle. (author)

Energy policy and nuclear power. Expectations of the power industry

International Nuclear Information System (INIS)

Harig, H.D.

1995-01-01

In the opinion of the power industry, using nuclear power in Germany is a responsible attitude, while opting out of nuclear power is not. Electricity utilities will build new nuclear power plants only if the structural economic and ecological advantages of nuclear power are preserved and can be exploited in Germany. The power industry will assume responsibility for new complex, capital-intensive nuclear plants only if a broad societal consensus about this policy can be reached in this country. The power industry expects that the present squandering of nuclear power resources in Germany will be stopped. The power industry is prepared to contribute to finding a speedy consensus in energy policy, which would leave open all decisions which must not be taken today, and which would not constrain the freedom of decision of coming generations. The electricity utilities remain committed proponents of nuclear power. However, what they sell to their customers is electricity, not nuclear power. (orig.) [de

Implications of using alternate fuel cycles to meet Ontario's nuclear power demand

International Nuclear Information System (INIS)

Lau, J.H.K.

1978-08-01

The use of alternate fuel cycles to meet an assumed nuclear capacity growth rate in Ontario is examined. Two criteria are used: the ability of the alternate fuel cycles to lessen the uranium demand; and the ease of commercialization. The nuclear strategies considered assume the use of the natural uranium cycle and, starting in the year 2000, the gradual introduction of an alternate fuel cycle. The alternate fuel cycles reviewed are enriched uranium, mixed oxides, and a variety of thorium cycles. The cumulative uranium requirement to the year 2070, and the growth and size of the reprocessing and fuel fabrication industries are discussed in detail. Sensitivity analyses on nuclear capacity growth rate, recycling loss and delay time are also described. (auth)

Nuclear Power, Nuclear Fuel Cycle and Waste Management 1980-1994. International Atomic Energy Agency Publications

International Nuclear Information System (INIS)

1995-05-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Power and Nuclear Fuel Cycle and Waste Management issued during the period 1980-1994. Most publications are issued in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (French, Russian or Spanish), but all of these papers have abstracts in English. If publications are also available in other languages than English, this is noted as C for Chinese, F for French, R for Russian and S for Spanish by the relevant ISBN number. It should be noted that prices of books are quoted in Austrian Schillings. The prices do not include local taxes and are subject to change without notice. All books in this catalogue are 16 x 24 cm, paper-bound, unless otherwise stated

Nuclear power in Europe

International Nuclear Information System (INIS)

Perera, J.

2000-01-01

Currently nuclear power accounts for more than 25% of total electricity production in Europe (including Eastern Europe and the former Soviet Union) However, significant new construction is planned in Central and Eastern Europe only, apart from some in France and, possibly in Finland. Many countries in Western Europe have put nuclear construction plans on hold and several have cancelled their nuclear programs. This report looks at the history of nuclear power and its current status in both Eastern and Western Europe. It provides an outline of nuclear fuel cycle facilities, from uranium procurement to final waste disposal. Economic and environmental issues are discussed, as well as the prospect of increased East-West trade and cooperation in the new poso-cold war world. Detailed profiles are provided of all the countries in Western Europe with significant nuclear power programs, as well as profiles of major energy and nuclear companies

Some consideration on nuclear power development. Topics aroused by U.S. proposed 'Generation IV Nuclear Power System

International Nuclear Information System (INIS)

Wang Chuanying; Chen Shiqi

2001-01-01

U.S. proposed 'Generation IV Nuclear Power System' concept. Its origin and proposed goals for it are analyzed; goals are compared with requirements of URD. In particular, discussed issues on nuclear fuel cycle and Non-proliferation. A well-considered nuclear power development plan, paying close attention to international trend and considering comprehensively domestic situation, is expected

Nuclear reactor closed Brayton cycle power conversion system optimization trends for extra-terrestrial applications

International Nuclear Information System (INIS)

Ashe, T.L.; Baggenstoss, W.G.; Bons, R.

1990-01-01

Extra-terrestrial exploration and development missions of the next century will require reliable, low-mass power generation modules of 100 kW e and more. These modules will be required to support both fixed-base and manned rover/explorer power needs. Low insolation levels at and beyond Mars and long periods of darkness on the moon make solar conversion less desirable for surface missions. For these missions, a closed Brayton cycle energy conversion system coupled with a reactor heat source is a very attractive approach. The authors conducted parametric studies to assess optimized system design trends for nuclear-Brayton systems as a function of operating environment and user requirements. The inherent design flexibility of the closed Brayton cycle energy conversion system permits ready adaptation of the system to future design constraints. This paper describes a dramatic contrast between system designs requiring man-rated shielding. The paper also considers the ramification of using indigenous materials to provide reactor shielding for a fixed-base power source

Towards sustainable nuclear power development

International Nuclear Information System (INIS)

Andrianov, Andrei A.; Murogov, Victor M.; Kuptsov, Ilya S.

2014-01-01

The review of the current situation in the nuclear energy sector carried out in this article brings to light key problems and contradictions, development trends and prospects, which finally determine the role and significance of nuclear power as a factor ensuring a sustainable energy development. Authors perspectives on the most appropriate developments of nuclear power, which should be based on a balanced use of proven innovative nuclear technologies and comprehensive multilateral approaches to the nuclear fuel cycle are expressed. The problems of wording appropriate and essential requirements for new countries with respect to their preparedness to develop nuclear programs, taking into account their development level of industry and infrastructure as well as national heritages and peculiarities, are explained. It is also indicated that one of the major components of sustainability in the development of nuclear power, which legitimates its public image as a power technology, is the necessity of developing and promoting the concepts of nuclear culture, nuclear education, and professional nuclear ethics. (orig.)

Towards sustainable nuclear power development

Energy Technology Data Exchange (ETDEWEB)

Andrianov, Andrei A.; Murogov, Victor M.; Kuptsov, Ilya S. [Obninsk Institute for Nuclear Power Engineering of NNRU MEPhl, Obninsk, Kaluga Region (Russian Federation)

2014-05-15

The review of the current situation in the nuclear energy sector carried out in this article brings to light key problems and contradictions, development trends and prospects, which finally determine the role and significance of nuclear power as a factor ensuring a sustainable energy development. Authors perspectives on the most appropriate developments of nuclear power, which should be based on a balanced use of proven innovative nuclear technologies and comprehensive multilateral approaches to the nuclear fuel cycle are expressed. The problems of wording appropriate and essential requirements for new countries with respect to their preparedness to develop nuclear programs, taking into account their development level of industry and infrastructure as well as national heritages and peculiarities, are explained. It is also indicated that one of the major components of sustainability in the development of nuclear power, which legitimates its public image as a power technology, is the necessity of developing and promoting the concepts of nuclear culture, nuclear education, and professional nuclear ethics. (orig.)

Quality factors in the life cycle of software oriented to safety systems in nuclear power plants

International Nuclear Information System (INIS)

Nunez McLeod, J.E.; Rivera, S.S.

1997-01-01

The inclusion of software in safety related systems for nuclear power plants, makes it necessary to include the software quality assurance concept. The software quality can be defined as the adjustment degree between the software and the specified requirements and user expectations. To guarantee a certain software quality level it is necessary to make a systematic and planned set of tasks, that constitute a software quality guaranty plan. The application of such a plan involves activities that should be performed all along the software life cycle, and that can be evaluated through the so called quality factors, due to the fact that the quality itself cannot be directly measured, but indirectly as some of it manifestations. In this work, a software life cycle model is proposed, for nuclear power plant safety related systems. A set os software quality factors is also proposed , with its corresponding classification according to the proposed model. (author) [es

Nuclear power development in Japan

International Nuclear Information System (INIS)

Sugawara, A.

1994-01-01

The energy situation in Japan is briefly outlined. Vulnerability in energy structure of the country is shown by a comparison of primary energy supply patterns of Japan and Western countries. Japan's energy policy consists in reducing dependence on oil, promoting efficient use of energy and increasing use of non-fossil fuels. Nuclear power is a core of alternative energy for petroleum because of stable supply of nuclear fuel, low detrimental emissions and less dependence on the fuel. A short historical review of nuclear power development in Japan is presented. Some future issues as development of entire nuclear fuel cycle, social acceptance, reactor safety and nuclear power economics are also discussed. 6 figs. (R.T.)

Closed-cycle cooling systems for nuclear power plants

International Nuclear Information System (INIS)

Santini, Lorenzo

2006-01-01

The long experience in the field of closed-cycle cooling systems and high technological level of turbo machines and heat exchangers concurs to believe in the industrial realizability of nuclear systems of high thermodynamic efficiency and intrinsic safety [it

Nuclear power industry, 1981

International Nuclear Information System (INIS)

1981-12-01

The intent of this publication is to provide a single volume of resource material that offers a timely, comprehensive view of the nuclear option. Chapter 1 discusses the development of commercial nuclear power from a historical perspective, reviewing the factors and events that have and will influence its progress. Chapters 2 through 5 discuss in detail the nuclear powerplant and its supporting fuel cycle, including various aspects of each element from fuel supply to waste management. Additional dimension is brought to the discussion by Chapters 6 and 7, which cover the Federal regulation of nuclear power and the nuclear export industry. This vast body of thoroughly documented information offers the reader a useful tool in evaluating the record and potential of nuclear energy in the United States

A comparison of nuclear power systems for Brazil using plutonium and binary cycles

International Nuclear Information System (INIS)

Ishiguro, Y.; Fernandes, J.E.

1985-01-01

Nuclear power systems based on plutonium cycle and binary cycle are compared taking into account natural uranium demand and reactor combination. The systems start with PWR type reactors (U5/U8) and change to systems composed exclusively of FBR type reactors or PWR-FBR symbiotic systems. Four loading modes are considered for the PWR and two for the FBR. The FBR is either a LMFBR loaded with PU/U or a LMFBR loaded the binary way. A linear and a non-linear capacity growth and two different criteria for the FBR introduction are considered. The results show that a 100 GWe permanent system can be established in 50 years in all cases, based on 300000 t of natural uranium and in case of delay in the FBR introduction and if a thermal-fast symbiotic system is chosen, a binary cycle could be more advantageous than a plutonium cycle. (F.E.) [pt

Significant incidents in nuclear fuel cycle facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

In contrast to nuclear power plants, events in nuclear fuel cycle facilities are not well documented. The INES database covers all the nuclear fuel cycle facilities; however, it was developed in the early 1990s and does not contain information on events prior to that. The purpose of the present report is to collect significant events and analyze them in order to give a safety related overview of nuclear fuel cycle facilities. Significant incidents were selected using the following criteria: release of radioactive material or exposure to radiation; degradation of items important to safety; and deficiencies in design, quality assurance, etc. which include criticality incidents, fire, explosion, radioactive release and contamination. This report includes an explanation, where possible, of root causes, lessons learned and action taken. 4 refs, 4 tabs.

Significant incidents in nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1996-03-01

In contrast to nuclear power plants, events in nuclear fuel cycle facilities are not well documented. The INES database covers all the nuclear fuel cycle facilities; however, it was developed in the early 1990s and does not contain information on events prior to that. The purpose of the present report is to collect significant events and analyze them in order to give a safety related overview of nuclear fuel cycle facilities. Significant incidents were selected using the following criteria: release of radioactive material or exposure to radiation; degradation of items important to safety; and deficiencies in design, quality assurance, etc. which include criticality incidents, fire, explosion, radioactive release and contamination. This report includes an explanation, where possible, of root causes, lessons learned and action taken. 4 refs, 4 tabs

Nuclear material control systems for nuclear power plants

International Nuclear Information System (INIS)

1975-06-01

Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

Effect of buoyancy on fuel containment in an open-cycle gas-core nuclear rocket engine.

Science.gov (United States)

Putre, H. A.

1971-01-01

Analysis aimed at determining the scaling laws for the buoyancy effect on fuel containment in an open-cycle gas-core nuclear rocket engine, so conducted that experimental conditions can be related to engine conditions. The fuel volume fraction in a short coaxial flow cavity is calculated with a programmed numerical solution of the steady Navier-Stokes equations for isothermal, variable density fluid mixing. A dimensionless parameter B, called the Buoyancy number, was found to correlate the fuel volume fraction for large accelerations and various density ratios. This parameter has the value B = 0 for zero acceleration, and B = 350 for typical engine conditions.

OECD/NEA Ongoing activities related to the nuclear fuel cycle

International Nuclear Information System (INIS)

Cornet, S.M.; McCarthy, K.; Chauvin, N.

2013-01-01

As part of its role in encouraging international collaboration, the OECD Nuclear Energy Agency is coordinating a series of projects related to the Nuclear Fuel Cycle. The Nuclear Science Committee (NSC) Working Party on Scientific Issues of the Nuclear Fuel Cycle (WPFC) comprises five different expert groups covering all aspects of the fuel cycle from front to back-end. Activities related to fuels, materials, physics, separation chemistry, and fuel cycles scenarios are being undertaken. By publishing state-of-the-art reports and organizing workshops, the groups are able to disseminate recent research advancements to the international community. Current activities mainly focus on advanced nuclear systems, and experts are working on analyzing results and establishing challenges associated to the adoption of new materials and fuels. By comparing different codes, the Expert Group on Advanced Fuel Cycle Scenarios is aiming at gaining further understanding of the scientific issues and specific national needs associated with the implementation of advanced fuel cycles. At the back end of the fuel cycle, separation technologies (aqueous and pyrochemical processing) are being assessed. Current and future activities comprise studies on minor actinides separation and post Fukushima studies. Regular workshops are also organized to discuss recent developments on Partitioning and Transmutation. In addition, the Nuclear Development Committee (NDC) focuses on the analysis of the economics of nuclear power across the fuel cycle in the context of changes of electricity markets, social acceptance and technological advances and assesses the availability of the nuclear fuel and infrastructure required for the deployment of existing and future nuclear power. The Expert Group on the Economics of the Back End of the Nuclear Fuel Cycle (EBENFC), in particular, is looking at assessing economic and financial issues related to the long term management of spent nuclear fuel. (authors)

Development of Czechoslovak nuclear power complex

International Nuclear Information System (INIS)

Rajci, T.

1986-01-01

The research project ''Development of the Czechoslovak nuclear power complex'' was undertaken by several Czechoslovak institutions and was coordinated by the Research Institute of the Fuel and Power Complex in Bratislava. Involved in the project was a staff of 170 people. 274 reports were pulished and the cost approached 70 mill. Czechoslovak crowns. The results are characterized of all six partial tasks. Basic information was prepared for the forecast of the solution of fuel and power problems in Czechoslovakia up to the year 2000 and their prospects up to the year 2020. Program MORNAP was written for the development of nuclear power, which models the operation of a power generation and transmission system with a selectable number of nuclear power plants. Another partial task related to the fuel cycle of nuclear power plants with respect to long-term provision and management of nuclear fuel. Nuclear safety was split into three problem groups, viz.: system safety of nuclear power plant operation; radiation problems of nuclear power plant safety; quality assurance of nuclear power plant components. The two remaining tasks were devoted to nuclear power engineering and to civil engineering. (Z.M.). 3 tabs., 1 refs

Dictionary of nuclear power. January 2013 ed.

International Nuclear Information System (INIS)

Koelzer, Winfried

2013-01-01

The actualized version (January 2013) of the dictionary on nuclear power includes all actualizations and new inputs since the last version of 2001. The original publication dates from 1980. The dictionary includes definitions, terms, measuring units and helpful information on the actual knowledge concerning nuclear power, nuclear fuel cycle, nuclear facilities, radioactive waste management, nuclear physics, reactor physics, isotope production, biological radiation effects, and radiation protection.

Cycle Trades for Nuclear Thermal Rocket Propulsion Systems

Science.gov (United States)

White, C.; Guidos, M.; Greene, W.

2003-01-01

Nuclear fission has been used as a reliable source for utility power in the United States for decades. Even in the 1940's, long before the United States had a viable space program, the theoretical benefits of nuclear power as applied to space travel were being explored. These benefits include long-life operation and high performance, particularly in the form of vehicle power density, enabling longer-lasting space missions. The configurations for nuclear rocket systems and chemical rocket systems are similar except that a nuclear rocket utilizes a fission reactor as its heat source. This thermal energy can be utilized directly to heat propellants that are then accelerated through a nozzle to generate thrust or it can be used as part of an electricity generation system. The former approach is Nuclear Thermal Propulsion (NTP) and the latter is Nuclear Electric Propulsion (NEP), which is then used to power thruster technologies such as ion thrusters. This paper will explore a number of indirect-NTP engine cycle configurations using assumed performance constraints and requirements, discuss the advantages and disadvantages of each cycle configuration, and present preliminary performance and size results. This paper is intended to lay the groundwork for future efforts in the development of a practical NTP system or a combined NTP/NEP hybrid system.

Cycle layout studies of S-CO2 cycle for the next generation nuclear system application

International Nuclear Information System (INIS)

Ahn, Yoonhan; Bae, Seong Jun; Kim, Minseok; Cho, Seong Kuk; Baik, Seungjoon; Lee, Jeong Ik; Cha, Jae Eun

2014-01-01

According to the second law of thermodynamics, the next generation nuclear reactor system efficiency can potentially be increased with higher operating temperature. Fig.1 shows several power conversion system efficiencies and heat sources with respect to the system top operating temperature. As shown in Fig.1, the steam Rankine and gas Brayton cycles have been considered as the major power conversion systems more than several decades. In the next generation reactor operating temperature region (450 - 900 .deg. C), the steam Rankine and gas Brayton cycles have limits due to material problems and low efficiency, respectively. Among the future power conversion systems, S-CO 2 cycle is receiving interests due to several benefits including high efficiency under the mild turbine inlet temperature range (450-650 .deg. C), compact turbomachinery and simple layout compared to the steam Rankine cycle. S-CO 2 cycle can show relatively high efficiency under the mild turbine inlet temperature range (450-600 .deg. C) compared to other power conversion systems. The recompression cycle shows the best efficiency among other layouts and it is suitable for the application to advanced nuclear reactor systems. As S-CO 2 cycle performance can vary depending on the layout configuration, further studies on the layouts are required to design a better performing cycle

Nuclear Fuel Cycle Objectives

International Nuclear Information System (INIS)

2013-01-01

. The four Objectives publications include Nuclear General Objectives, Nuclear Power Objectives, Nuclear Fuel Cycle Objectives, and Radioactive Waste management and Decommissioning Objectives. This publication sets out the objectives that need to be achieved in the area of the nuclear fuel cycle to ensure that the Nuclear Energy Basic Principles are satisfied. Within each of these four Objectives publications, the individual topics that make up each area are addressed. The five topics included in this publication are: resources; fuel engineering and performance; spent fuel management and reprocessing; fuel cycles; and the research reactor nuclear fuel cycle

Uranium Resource Availability Analysis of Four Nuclear Fuel Cycle Options

International Nuclear Information System (INIS)

Youn, S. R.; Lee, S. H.; Jeong, M. S.; Kim, S. K.; Ko, W. I.

2013-01-01

Making the national policy regarding nuclear fuel cycle option, the policy should be established in ways that nuclear power generation can be maintained through the evaluation on the basis of the following aspects. To establish the national policy regarding nuclear fuel cycle option, that must begin with identification of a fuel cycle option that can be best suited for the country, and the evaluation work for that should be proceeded. Like all the policy decision, however, a certain nuclear fuel cycle option cannot be superior in all aspects of sustain ability, environment-friendliness, proliferation-resistance, economics, technologies, which make the comparison of the fuel cycle options very complicated. For such a purpose, this paper set up four different fuel cycle of nuclear power generation considering 2nd Comprehensive Nuclear Energy Promotion Plan(CNEPP), and analyzed material flow and features in steady state of all four of the fuel cycle options. As a result of an analysis on material flow of each nuclear fuel cycle, it was analyzed that Pyro-SFR recycling is most effective on U resource availability among four fuel cycle option. As shown in Figure 3, OT cycle required the most amount of U and Pyro-SFR recycle consumed the least amount of U. DUPIC recycling, PWR-MOX recycling, and Pyro-SFR recycling fuel cycle appeared to consumed 8.2%, 12.4%, 39.6% decreased amount of uranium respectively compared to OT cycle. Considering spent fuel can be recycled as potential energy resources, U and TRU taken up to be 96% is efficiently used. That is, application period of limited uranium natural resources can be extended, and it brings a great influence on stable use of nuclear energy

Nuclear power and the carbon dioxide problem

International Nuclear Information System (INIS)

Bijlsma, J.J.; Blok, K.; Turkenburg, W.C.

1989-05-01

This study deals with the question, which contribution can be delivered by nuclear power to the redution of the emission of carbon dioxide (CO 2 ) from the power supply. The emphasis lays upon the following aspects: the emissions of CO 2 which occur in the nuclear-power cycle (the so-called indirect emission of CO 2 power plants); the amount of uranium stocks; the change of CO 2 emission caused by replacement of fossil fuels, in particular coal, by nuclear power. First an energy-analysis of the nuclear power cycle is presented. On the base of this analysis the CO 2 uranium can be calculated. The role of nuclear power in the reduction of CO 2 emission depends on the development of the final power demand. Therefore in this study two scenarios derived from the 'IIASA-low' scenario; 'low-energy'-scenario in which the world-energy consumption remains at about the same level. In the calculations the indirect emissions of CO 2 , also dependent on the ore richness and the technology used, have always been taken into account. In the calculations two uranium-reserve variants of resp. 5.7 and 30 mln. tons have been assumed. From the results of the calculations it can be concluded that whether or not taking account of the indirect emissions of CO 2 in the nuclear power cycle, has only limited effect on the calculated contribution of nuclear power to the solution of the greenhouse effect. The uranium reserves turn out to be determining for the potential contribution of nuclear power. By putting on the surely available reserve of 5.7 mln. tons, or the speculative reserve of 30 mln. tons, with the actual technology, an emission of resp. 130-140 billion and 880 billion tons CO 2 can be avoided in replacing coal. With maximal employment of improved conversion techniques these contributions may be doubled. (H.W.). 40 refs.; 13 figs.; 10 tabs

Potential efficiencies of open- and closed-cycle CO, supersonic, electric-discharge lasers

Science.gov (United States)

Monson, D. J.

1976-01-01

Computed open- and closed-cycle system efficiencies (laser power output divided by electrical power input) are presented for a CW carbon monoxide, supersonic, electric-discharge laser. Closed-system results include the compressor power required to overcome stagnation pressure losses due to supersonic heat addition and a supersonic diffuser. The paper shows the effect on the system efficiencies of varying several important parameters. These parameters include: gas mixture, gas temperature, gas total temperature, gas density, total discharge energy loading, discharge efficiency, saturated gain coefficient, optical cavity size and location with respect to the discharge, and supersonic diffuser efficiency. Maximum open-cycle efficiency of 80-90% is predicted; the best closed-cycle result is 60-70%.

Thermal-CFD Analysis of Combined Solar-Nuclear Cycle Systems.

Energy Technology Data Exchange (ETDEWEB)

Fathi, Nima [Univ. of New Mexico, Albuquerque, NM (United States); McDaniel, Patrick [Univ. of New Mexico, Albuquerque, NM (United States); Vorobieff, Peter [Univ. of New Mexico, Albuquerque, NM (United States); de Oliveira, Cassiano [Univ. of New Mexico, Albuquerque, NM (United States); Rodriguez, Salvador B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Aleyasin, Seyed Sobhan [Univ. of Manitoba (Canada)

2015-09-01

The aim of this paper is evaluating the efficiency of a novel combined solar-nuclear cycle. CFD-Thermal analysis is performed to apply the available surplus heat from the nuclear cycle and measure the available kinetic energy of air for the turbine of a solar chimney power plant system (SCPPS). The presented idea helps to decrease the thermal pollution and handle the water shortage supply for water plant by replacing the cooling tower by solar chimney power plant to get the surplus heat from the available warm air in the secondary loop of the reactor. By applying this idea to a typical 1000 MW nuclear power plant with a 0.33 thermal efficiency, we can increase it to 0.39.

Sensitivity of nuclear fuel cycle cost to uncertainties in nuclear data

International Nuclear Information System (INIS)

Harris, D.R.; Becker, M.; Parvez, A.; Ryskamp, J.M.

1979-01-01

A sensitivity analysis system is developed for assessing the economic implications of uncertainties in nuclear data and related computational methods for light water power reactors. Results of the sensitivity analysis indicate directions for worthwhile improvements in data and methods. Benefits from improvements in data and methods are related to reduction of margins provided by designers to ensure meeting reactor and fuel objectives. Sensitivity analyses are carried out using the batch depletion code FASTCELL, the core analysis code FASTCORE, and the reactor cost code COSTR. FASTCELL depletes a cell using methods comparable to industry cell codes except for a few-group treatment of cell flux distribution. FASTCORE is used with the Haling strategy of fixed power sharing among batches in the core. COSTR computes costs using components and techniques as in industry costing codes, except that COSTR uses fixed payment schedules. Sensitivity analyses are carried out for large commercial boiling and pressurized water reactors. Each few-group nuclear parameter is changed, and initial enrichment is also changed so as to keep the end-of-cycle core multiplication factor unchanged, i.e., to preserve cycle time at the demand power. Sensitivities of equilibrium fuel cycle cost are determined with respect to approx. 300 few-group nuclear parameters, both for a normal fuel cycle and for a throwaway fuel cycle. Particularly large dollar implications are found for thermal and resonance range cross sections in fissile and fertile materials. Sensitivities constrained by adjustment of fission neutron yield so as to preserve agreement with zero exposure integral data also are computed

Current state of nuclear fuel cycles in nuclear engineering and trends in their development according to the environmental safety requirements

Science.gov (United States)

Vislov, I. S.; Pischulin, V. P.; Kladiev, S. N.; Slobodyan, S. M.

2016-08-01

The state and trends in the development of nuclear fuel cycles in nuclear engineering, taking into account the ecological aspects of using nuclear power plants, are considered. An analysis of advantages and disadvantages of nuclear engineering, compared with thermal engineering based on organic fuel types, was carried out. Spent nuclear fuel (SNF) reprocessing is an important task in the nuclear industry, since fuel unloaded from modern reactors of any type contains a large amount of radioactive elements that are harmful to the environment. On the other hand, the newly generated isotopes of uranium and plutonium should be reused to fabricate new nuclear fuel. The spent nuclear fuel also includes other types of fission products. Conditions for SNF handling are determined by ecological and economic factors. When choosing a certain handling method, one should assess these factors at all stages of its implementation. There are two main methods of SNF handling: open nuclear fuel cycle, with spent nuclear fuel assemblies (NFAs) that are held in storage facilities with their consequent disposal, and closed nuclear fuel cycle, with separation of uranium and plutonium, their purification from fission products, and use for producing new fuel batches. The development of effective closed fuel cycles using mixed uranium-plutonium fuel can provide a successful development of the nuclear industry only under the conditions of implementation of novel effective technological treatment processes that meet strict requirements of environmental safety and reliability of process equipment being applied. The diversity of technological processes is determined by different types of NFA devices and construction materials being used, as well as by the composition that depends on nuclear fuel components and operational conditions for assemblies in the nuclear power reactor. This work provides an overview of technological processes of SNF treatment and methods of handling of nuclear fuel

Climate Change and Nuclear Power 2013

International Nuclear Information System (INIS)

2013-01-01

Climate change is one of the most important issues facing the world today. Nuclear power can make an important contribution to reducing greenhouse gas emissions while delivering energy in the increasingly large quantities needed for global socioeconomic development. Nuclear power plants produce virtually no greenhouse gas emissions or air pollutants during their operation and only very low emissions over their entire life cycle. The accident at the Fukushima Daiichi nuclear power plant of March 2011 caused deep public anxiety and raised fundamental questions about the future of nuclear energy throughout the world. It was a wake-up call for everyone involved in nuclear power - a reminder that safety can never be taken for granted. Yet, in the wake of the accident, it is clear that nuclear energy will remain an important option for many countries. Its advantages in terms of climate change mitigation are an important reason why many countries intend to introduce nuclear power in the coming decades, or to expand existing programmes. All countries have the right to use nuclear technology for peaceful purposes, as well as the responsibility to do so safely and securely. The International Atomic Energy Agency provides assistance and information to countries that wish to introduce nuclear power. It also provides information for broader audiences engaged in energy, environmental and economic policy making. This report has been substantially revised, updated and extended since the 2012 edition. It summarizes the potential role of nuclear power in mitigating global climate change and its contribution to other development and environmental challenges. The report also examines broader issues relevant to the climate change-nuclear energy nexus, such as cost, safety, waste management and non-proliferation. New developments in resource supply, innovative reactor technologies and related fuel cycles are also presented

Nuclear power for beginners

International Nuclear Information System (INIS)

Croall, S.; Sempler, K.

1978-01-01

A 'comic strip' account of nuclear power, covering weapons and weapons proliferation, reactor accidents involving human errors, radiation hazards, radioactive waste management and the fuel cycle, fast breeder reactors and plutonium, security, public relations and sociological aspects, energy consumption patterns, energy conservation and alternative energy sources, environmental aspects and anti-nuclear activities. (U.K.)

JTEC panel on nuclear power in Japan. Final report

International Nuclear Information System (INIS)

Hansen, K.F.; Behnke, W.B.; Cousin, S.B.; Evans, E.A.; Olander, D.R.

1990-10-01

The report examines the status and direction of nuclear power-related research and development in Japan in six areas: the nuclear fuel cycle, nuclear materials, instrumentation and control technology, CAD/CAM, nuclear safety research, and nuclear plant construction. Overall findings suggest that the nuclear power industry in Japan is at an advanced state of development; in particular, Japan is now technologically self-sufficient. Long-term goals of the Japanese program include closure of the complete fuel cycle and pursuit of the liquid metal fast breeder reactor as the future base system

2007 Winter meeting - opening Address: nuclear power in a relationship of tension between politics, society, and the economy

International Nuclear Information System (INIS)

Hohlefelder, Walter

2007-01-01

Even more so than last year, energy policy is at the very top of the political agenda. The European Commission presented its strategy paper on 'One Energy Policy for Europe', and another energy summit will be held in Germany to pave the way for an energy concept. As far as nuclear power is concerned, the EU Commission clearly and soberly emphasized today's contribution of nuclear power in the EU and, above all, the chances of further expanding the use of nuclear power in the interest of CO 2 avoidance, security of supply, and competitiveness. This makes a reassessment of nuclear power also a matter of national interest. The repository problem can be solved in Germany, provided there is the political will to do so. The sequence of steps leading to a solution is outlined precisely in the so-called Understanding on Nuclear Power of 2001. According to a ruling by the Lueneburg higher administrative court, Konrad, the repository for low-level radioactive waste, can now be expanded and commissioned. There are no objections to the further exploration of the Gorleben salt dome as a repository for high-level radioactive waste. In the course of the energy summit, an open, unbiased discussion about the reassessment of nuclear power must be started. No facts must be created prematurely, such as shutdowns of nuclear power plants. Applications for transfers of electricity quotas for older nuclear power plants are legitimate and correct. The German Atomic Energy Act contains express provisions for this possibility. There is no way past a basic reassessment of nuclear power. It has to be conducted now. (orig.)

The nuclear power development policy of Taipower

International Nuclear Information System (INIS)

Chen, J.H.

1987-01-01

Taipower began its nuclear power epoch in 1978 when the first unit of its First Nuclear Power Station was synchronized to the system on November 1977. At present, Taipower has six units installed in three nuclear power plants, totalling 5144 MW in operation. These units are the mainstay of the 16,600 MW system and have played a significant role in the energy supply of Taiwan. This paper will firstly give a brief overview of Taipower's system, then introduce Taipower's nuclear power policies within the frame of issues on nuclear power economy, nuclear fuel cycle management, nuclear safety and environmental concerns, radioactive waste management, public communications and personnel training. At last, this paper will present the prospect for future nuclear power development in Taiwan with reference to the above discussion. (author)

Energy, electricity and nuclear power

International Nuclear Information System (INIS)

Reuss, P.; Naudet, G.

2008-01-01

After an introduction recalling what energy is, the first part of this book presents the present day energy production and consumption and details more particularly the electricity 'vector' which is an almost perfect form of energy despite the fact that it is not a primary energy source: it must be generated from another energy source and no large scale storage of this energy is possible. The second part of the book is devoted to nuclear energy principles and to the related technologies. Content: 1 - What does energy mean?: the occurrence of the energy concept, the classical notion of energy, energy notion in modern physics, energy transformations, energy conservation, irreversibility of energy transformations, data and units used in the energy domain; 2 - energy production and consumption: energy systems, energy counting, reserves and potentialities of energy resources, production of primary energies, transport and storage of primary energies, energy consumption, energy saving, energy markets and prices, energy indicators; 3 - electric power: specificity of electricity and the electric system, power networks, power generation, electricity storage, power consumption and demand, power generation economics, electricity prices and market; 4 - physical principles of nuclear energy: nuclei structure and binding energy, radioactivity and nuclear reactions, nuclear reactions used in energy generation, basics of fission reactors physics; 5 - nuclear techniques: historical overview, main reactor types used today, perspectives; 6 - fuel cycle: general considerations, uranium mining, conversion, enrichment, fuel fabrication, back-end of the cycle, plutonium recycle in water cooled reactors; 7 - health and environmental aspects of nuclear energy: effects on ionizing radiations, basics of radiation protection, environmental impacts of nuclear energy, the nuclear wastes problem, specific risks; 8 - conclusion; 9 - appendixes (units, physics constants etc..)

A full life cycle nuclear knowledge management framework based on digital system

International Nuclear Information System (INIS)

Wang, Minglu; Zheng, Mingguang; Tian, Lin; Qiu, Zhongming; Li, Xiaoyan

2017-01-01

Highlights: • A full life cycle nuclear power plant knowledge management framework is introduced. • This framework benefits the safe design, construction, operation and maintenance. • This framework enhances safety, economy and reliability of nuclear power plant. - Abstract: The nuclear power plant is highly knowledge-intensive facility. With the rapid advent and development of modern information and communication technology, knowledge management in nuclear industry has been provided with new approaches and possibilities. This paper introduces a full cycle nuclear power plant knowledge management framework based on digital system and tries to find solutions to knowledge creation, sharing, transfer, application and further innovation in nuclear industry. This framework utilizes information and digital technology to build top-tier object driven work environment, automatic design and analysis integration platform, digital dynamic performance Verification & Validation (V&V) platform, collaborative manufacture procedure, digital construction platform, online monitoring and configuration management which benefit knowledge management in NPP full life cycle. The suggested framework will strengthen the design basis of the nuclear power plants (NPPs) and will ensure the safety of the NPP design throughout the whole lifetime of the plant.

18-months fuel cycle engineering and its project management of the Daya Bay Nuclear Power Station

International Nuclear Information System (INIS)

Fu Xiangang; Jiao Ping; Liu Yong; Wu Zhiming

2002-01-01

The author introduces aspects related to the performing of 18-months fuel cycle engineering evaluation to the Daya Bay nuclear power plant, including the assessment on proposed technical solutions, appointment to the contractors, breaking down and implementation of project, experience on the project management and risk control, and etc. And it also briefs the prompting to the localization of the long fuel cycle engineering technology and AFA 3G fuel manufacturing and design technology via adequate technology transferring of this project

Rhodium self-powered neutron detector's lifetime for korean standard nuclear power plants

International Nuclear Information System (INIS)

Yoo, Choon Sung; Kim, Byoung Chul; Park, Jong Ho; Fero, Arnold H.; Anderson, S. L.

2005-01-01

A method to estimate the relative sensitivity of a self-powered rhodium detector for an upcoming cycle is developed by combining the rhodium depletion data from a nuclear design with the site measurement data. This method can be used both by nuclear power plant designers and by site staffs of Korean standard nuclear power plants for determining which rhodium detectors should be replaced during overhauls

Nuclear plant life cycle costs

International Nuclear Information System (INIS)

Durante, R.W.

1994-01-01

Life cycle costs of nuclear power plants in the United States are discussed. The author argues that these costs have been mishandled or neglected. Decommissioning costs have escalated, e.g. from $328 per unit in 1991 to $370 in 1993 for the Sacramento Municipal Utility District, though they still only amount to less than 0.1 cent per kWh. Waste management has been complicated in the U.S. by the decision to abandon civilian reprocessing; by the year 2000, roughly 30 U.S. nuclear power units will have filled their storage pools; dry storage has been delayed, and will be an expense not originally envisaged. Some examples of costs of major component replacement are provided. No single component has caused as much operational disruption and financial penalties as the steam generator. Operation and maintenance costs have increased steadily, and now amount to more than 70% of production costs. A strategic plan by the Nuclear Power Oversight Committee (of U.S. utilities) will ensure that the ability to correctly operate and maintain a nuclear power plant is built into the original design. 6 figs

Nuclear Fuel Cycle System Analysis (II)

Energy Technology Data Exchange (ETDEWEB)

Ko, Won Il; Kwon, Eun Ha; Yoon, Ji Sup; Park, Seong Won

2007-04-15

As a nation develops strategies that provide nuclear energy while meeting its various objectives, it must begin with identification of a fuel cycle option that can be best suitable for the country. For such a purpose, this paper takes four different fuel cycle options that are likely adopted by the Korean government, considering the current status of nuclear power generation and the 2nd Comprehensive Nuclear Energy Promotion Plan (CNEPP) - Once-through Cycle, DUPIC Recycle, Thermal Reactor Recycle and GEN-IV Recycle. The paper then evaluates each option in terms of sustainability, environment-friendliness, proliferation-resistance, economics and technologies. Like all the policy decision, however, a nuclear fuel cycle option can not be superior in all aspects of sustainability, environment-friendliness, proliferation-resistance, economics, technologies and so on, which makes the comparison of the options extremely complicated. Taking this into consideration, the paper analyzes all the four fuel cycle options using the Multi-Attribute Utility Theory (MAUT) and the Analytic Hierarchy Process (AHP), methods of Multi-Attribute Decision Making (MADM), that support systematical evaluation of the cases with multi- goals or criteria and that such goals are incompatible with each other. The analysis shows that the GEN-IV Recycle appears to be most competitive.

Supply and demand estimates for the nuclear fuel cycle

International Nuclear Information System (INIS)

Haussermann, W.; Hogroian, P.; Krymm, R.; Cameron, J.

1977-01-01

Based on the nuclear power growth forecasts described in the papers for Session I.B., estimates of requirements in the nuclear fuel cycle are given, notably concerning: - natural uranium, - enriched uranium, - fuel fabrication services, and - reprocessing services. The influence of realistic scenarios of uranium and plutonium recycling on fuel cycle requirements is discussed. Furthermore, the known plans for uranium and related fuel cycle production capacities are compared with the foreseeable demand. These estimates cover the period between now and the year 2000. However, in order to determine the influence of possible variations in reactor strategies on uranium demand, notably the introduction of breeder reactors, power growth projections and resulting fuel cycle requirements beyond the year 2000 are also briefly considered [fr

Ukrainian Nuclear Society International Conference 'Strategy of the nuclear power development: The choice of Ukraine'

International Nuclear Information System (INIS)

Vishnevskij, I.N.; Trofimenko, A.P.

2001-01-01

Abstracts of the papers presented at the International Conference of the Ukrainian Nuclear Society 'Strategy of the nuclear power development'. The following problems are considered: present situation with the nuclear power and its safety; nuclear fuel cycle development; waste and spent nuclear fuel management; reactors' decommissioning issues; modernization of the NPP with WWER reactors; future reactors; economics of nuclear power; safety culture; legal and regulatory framework, state nuclear regulatory control; PR in nuclear power industry; staff training

Interim report on nuclear power in Ontario

International Nuclear Information System (INIS)

1978-01-01

An exhaustive report is presented on the implications of nuclear electric generation for Ontario's energy future. Such aspects as electrical demand and power planning, the CANDU fuel cycle, the nuclear debate, health, environmental and safety concerns, economics, social impacts and the status of the nuclear industry, uranium resources, ethical and political issues, nuclear weapons proliferation and plant security, and the regulation of nuclear power are dealt with in detail. (E.C.B.)

Ecoloqical problems of nuclear power development

International Nuclear Information System (INIS)

Gerzhmansky, B.

1980-01-01

Vital problems of environmental impacts of the nuclear power complex are elucidated. Different stages of the nuclear fuel cycle are considered. Presented are some quantitative data on the deaths from lung cancer, comparison of cancer risks due to irradiation and a cool-fueled power plant operation, the effects of different types of power plants on the environment and additional risks for the nuclear fuel cycle plants personnel. The ore mining, milling and enrichment, uranium enrichment, fuel fabrication and normal NPP operation are concluded not to present any serious menace for the environment. Comparisons do show that the detremental effects of coal-fueled power plants are much higher. Probability of an accident resulting in release of large amounts of radionuclides is much lower for a contemporary NPP equipped with proved safety systems, than in other industries. Meanwhile it is not possible nowadays to quantitatively evaluate the effects of reprocessing plants on the environment

Thermodynamic analysis and optimization of a Closed Regenerative Brayton Cycle for nuclear space power systems

International Nuclear Information System (INIS)

Ribeiro, Guilherme B.; Braz Filho, Francisco A.; Guimarães, Lamartine N.F.

2015-01-01

Nuclear power systems turned to space electric propulsion differ strongly from usual ground-based power systems regarding the importance of overall size and mass. For propulsion power systems, size and mass are essential drivers that should be minimized during conception processes. Considering this aspect, this paper aims the development of a design-based model of a Closed Regenerative Brayton Cycle that applies the thermal conductance of the main components in order to predict the energy conversion performance, allowing its use as a preliminary tool for heat exchanger and radiator panel sizing. The centrifugal-flow turbine and compressor characterizations were achieved using algebraic equations from literature data. A binary mixture of Helium–Xenon with molecular weight of 40 g/mole is applied and the impact of the components sizing in the energy efficiency is evaluated in this paper, including the radiator panel area. Moreover, an optimization analysis based on the final mass of heat the exchangers is performed. - Highlights: • A design-based model of a Closed Brayton Cycle is proposed for nuclear space needs. • Turbomachinery efficiency presented a strong influence on the system efficiency. • Radiator area presented the highest potential to increase the system efficiency. • There is maximum system efficiency for each total mass of heat exchangers. • Size or efficiency optimization was performed by changing heat exchanger proportion.

Modeling of Turbine Cycles Using a Neuro-Fuzzy Based Approach to Predict Turbine-Generator Output for Nuclear Power Plants

Directory of Open Access Journals (Sweden)

Yea-Kuang Chan

2012-01-01

Full Text Available Due to the very complex sets of component systems, interrelated thermodynamic processes and seasonal change in operating conditions, it is relatively difficult to find an accurate model for turbine cycle of nuclear power plants (NPPs. This paper deals with the modeling of turbine cycles to predict turbine-generator output using an adaptive neuro-fuzzy inference system (ANFIS for Unit 1 of the Kuosheng NPP in Taiwan. Plant operation data obtained from Kuosheng NPP between 2006 and 2011 were verified using a linear regression model with a 95% confidence interval. The key parameters of turbine cycle, including turbine throttle pressure, condenser backpressure, feedwater flow rate and final feedwater temperature are selected as inputs for the ANFIS based turbine cycle model. In addition, a thermodynamic turbine cycle model was developed using the commercial software PEPSE® to compare the performance of the ANFIS based turbine cycle model. The results show that the proposed ANFIS based turbine cycle model is capable of accurately estimating turbine-generator output and providing more reliable results than the PEPSE® based turbine cycle models. Moreover, test results show that the ANFIS performed better than the artificial neural network (ANN, which has also being tried to model the turbine cycle. The effectiveness of the proposed neuro-fuzzy based turbine cycle model was demonstrated using the actual operating data of Kuosheng NPP. Furthermore, the results also provide an alternative approach to evaluate the thermal performance of nuclear power plants.

Development and management of world nuclear power in 2012

International Nuclear Information System (INIS)

2012-01-01

It deals with development and management of nuclear power of foreign countries by the 1st of January 2012 with tables and figures, which includes outline of investigation, operation experience of nuclear power plant of the world, the cardinal number according to the type of operating power plant of the world, using Mox of the world and site of nuclear power plant of the world. There are list of world nuclear power plant, explanation of abbreviations, address book of nuclear power plant of the world and table and figure of major nuclear fuel cycle.

POPCYCLE: a computer code for calculating nuclear and fossil plant levelized life-cycle power costs

International Nuclear Information System (INIS)

Hardie, R.W.

1982-02-01

POPCYCLE, a computer code designed to calculate levelized life-cycle power costs for nuclear and fossil electrical generating plants is described. Included are (1) derivations of the equations and a discussion of the methodology used by POPCYCLE, (2) a description of the input required by the code, (3) a listing of the input for a sample case, and (4) the output for a sample case

The end of cheap electric power from nuclear power plants. 2. ed.

International Nuclear Information System (INIS)

Franke, J.; Viefhues, D.

1984-04-01

The economic efficiency of a nuclear power plant is compared with that of a coal-fired power plant of the same size. A technical and economic computer model was developed which took account of the power plant and all its units as well as the fuel cycle (including intermediate storage and reprocessing). It was found that future nuclear power plants will be inferior to coal-fired power plants in all economic respects. Further, there was no load range in which the cost of electric power generation was more favourable in nuclear power plants than in coal-fired power plants. (orig./HSCH) [de

Nuclear power failure signals end of an era

International Nuclear Information System (INIS)

Mariotte, M.

1996-01-01

In the United States, open-quotes the nuclear industry is dead, kaput, finishedclose quotes says Michael Mariotte, executive director of the Nuclear Information and Resource Service in Washington, D.C. Why? Investors are reluctant to gamble their money on a future generation of supposedly safe, economic nuclear power plants. open-quotes in 1979, the 'safe' Three Mile Island-2 reactor turned a several-hundred-million-dollar investment into a billion-dollar loss in a matter of hours,close quotes Mariotte says. open-quotes In fact, investing in nuclear power at this point would be like investing in the Titanic II.close quotes However, diehard proponents of nuclear energy persist in their optimism for a new nuclear age, Mariotte says. These nuclear backers see the need to replace aging plants with a new generation of safer plants. But would a new generation of reactors really be safer? open-quotes To date, the industry may spur some new nuclear plants, it is more likely to lead to alternative renewable sources of energy that are more economical. open-quotes The nuclear age has ended as a result of inefficiency and unacceptable risks...After 50 years of sustained abuse, the Earth has finally and deservedly entered the end of the nuclear age,close quotes Mariotte says

Nuclear power and the environment: questions and answers

International Nuclear Information System (INIS)

Anon.

1976-01-01

The purpose of this book is to present information and answers to questions about nuclear power and the environment, e.g., questions on its effects on public health, safety, and welfare. Information on the overall U.S. energy outlook, with emphasis on nuclear power generation, is provided. Although proponents of nuclear power, the authors have attempted to present factual information and to maintain objectivity. Included are answers to questions on these aspects of nuclear power: the energy situation and nuclear power; economics and reliability; alternative technologies; radioactivity; biological effects of radiation; transportation in the nuclear fuel cycle; fuel reprocessing and nuclear waste disposal; plutonium toxicity; nuclear plant security; thermal pollution; nuclear power plant siting--earthquakes; nuclear reactor safety; public risk and benefits; nuclear liability and insurance; breeder reactors; and thermonuclear fusion. (232 references)

Sustainable development and nuclear power

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-11-01

Although there is an awareness on both the technical and political levels of the advantages of nuclear power, it is not a globally favoured option in a sustainable energy future. A sizeable sector of public opinion remains hesitant or opposed to its increased use, some even to a continuation at present levels. With various groups calling for a role for nuclear power, there is a need openly and objectively to discuss the concerns that limit its acceptance: the perceived health effects, the consequences of severe accidents, the disposal of high level waste and nuclear proliferation. This brochure discusses these concerns, and also the distinct advantages of nuclear power. Extensive comparisons with other energy sources are made. Figs, tabs.

Sustainable development and nuclear power

International Nuclear Information System (INIS)

1997-11-01

Although there is an awareness on both the technical and political levels of the advantages of nuclear power, it is not a globally favoured option in a sustainable energy future. A sizeable sector of public opinion remains hesitant or opposed to its increased use, some even to a continuation at present levels. With various groups calling for a role for nuclear power, there is a need openly and objectively to discuss the concerns that limit its acceptance: the perceived health effects, the consequences of severe accidents, the disposal of high level waste and nuclear proliferation. This brochure discusses these concerns, and also the distinct advantages of nuclear power. Extensive comparisons with other energy sources are made

Datafile: [nuclear power in] Japan

International Nuclear Information System (INIS)

Anon.

1989-01-01

Japan is third after the USA and France in terms of the Western World's installed nuclear capacity, but it has by far the largest forward programme. Great effort is also being put into the fuel cycle and advanced reactors. There is close co-operation between the government, utilities and manufacturers, but Japan has not sought to export reactors. The government has responded to the growing public opposition to nuclear power with a massive increase in its budget for public relations. Details of the nuclear power programme are given. (author)

Catalogue and classification of technical safety standards, rules and regulations for nuclear power reactors and nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Fichtner, N.; Becker, K.; Bashir, M.

1977-01-01

The present report is an up-dated version of the report 'Catalogue and Classification of Technical Safety Rules for Light-water Reactors and Reprocessing Plants' edited under code No EUR 5362e, August 1975. Like the first version of the report, it constitutes a catalogue and classification of standards, rules and regulations on land-based nuclear power reactors and fuel cycle facilities. The reasons for the classification system used are given and discussed

Fuel/propellant mixing in an open-cycle gas core nuclear rocket engine

International Nuclear Information System (INIS)

Guo, X.; Wehrmeyer, J.A.

1997-01-01

A numerical investigation of the mixing of gaseous uranium and hydrogen inside an open-cycle gas core nuclear rocket engine (spherical geometry) is presented. The gaseous uranium fuel is injected near the centerline of the spherical engine cavity at a constant mass flow rate, and the hydrogen propellant is injected around the periphery of the engine at a five degree angle to the wall, at a constant mass flow rate. The main objective is to seek ways to minimize the mixing of uranium and hydrogen by choosing a suitable injector geometry for the mixing of light and heavy gas streams. Three different uranium inlet areas are presented, and also three different turbulent models (k-var-epsilon model, RNG k-var-epsilon model, and RSM model) are investigated. The commercial CFD code, FLUENT, is used to model the flow field. Uranium mole fraction, axial mass flux, and radial mass flux contours are obtained. copyright 1997 American Institute of Physics

International nuclear power status 1994

International Nuclear Information System (INIS)

Hoejerup, C.F.; Majborn, B.; Oelgaard, P.L.

1995-02-01

This report is the first in a planned series of annual reports covering the international development in the field of nuclear power. The report deals with: statistical information on the electricity produced by nuclear power plants; major safety-related incidents in 1994; the development in Sweden, Eastern Europe, and the rest of the world; the trends of development of a number of reactor types; the trends of development in the fuel cycle. (au)

Nuclear power proliferation

International Nuclear Information System (INIS)

Johnson, B.

1977-01-01

The nuclear industry is experiencing a multiple crisis in which economic, technical and ethical aspects are blended inextricably. Nuclear hardware costs have everywhere soared far beyond inflation in the last five years, largely as a result of delays in programme completion arising from problems of reactor and fuel cycle. Meanwhile, partly as a result of this cost escalation, there is widespread and growing doubt as to whether capital will be available to finance the electricity generating levels projected by the industry and by governments for the 1990s. The nuclear industry is now in trouble at every stage of the fuel cycle. The industry's difficulties have also revealed a lack of overall - but particularly nuclear - energy strategy at either national or international levels, and a lack of will to create regulations and institutional machinery at either of these levels which might reassure both concerned publics and the energy industries themselves. This paper appraises some of the present limitations of international institutions in achieving control and management of nuclear power. (author)

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)

Nuclear power: Issues and misunderstandings

International Nuclear Information System (INIS)

Rosen, M.

2000-01-01

A sizeable sector of the public remains hesitant or opposed to the use of nuclear power. With other groups claiming nuclear power has a legitimate role in energy programs, there is a need to openly and objectively discuss the concerns limiting its acceptance: the perceived health effects, the consequences of severe accidents, and the disposal of high level waste. This paper discusses these concerns using comparisons with other energy sources. (author)

Country nuclear power profiles. 2001 ed

International Nuclear Information System (INIS)

2002-03-01

'internalized' the vast majority of its 'external' costs - those costs, such as environmental impact costs, that are not directly passed on to the consumer. The biggest future challenge for the nuclear industry will be to convince investors of the case for nuclear new-build in a fully deregulated market. Nuclear plants - like hydro-electric plants - have relatively high capital costs, and investors therefore need to be persuaded of the advantages of projects with relatively long pay-back periods. Growing awareness of nuclear's environmental benefits, combined with the need to ensure long-term security of supply, could play a key role here in years to come. The following structure was developed by participating national experts in 1995 and has been used by the national contributors as a guidance to complete their country nuclear power profile: general information; economic indicators; energy situation; energy policy; electricity sector; impact of open electricity market in the nuclear sector; nuclear power situation, (historical development, status and trends of nuclear power); current policy issues; nuclear power industry; apply of NPPs; operation of NPPs; fuel cycle, spent fuel and waste management service supply; research and development activities; international co-operation in the field of nuclear power development and implementation; regulatory framework (safety authority and the licensing process, main national laws and regulations; international, multilateral and bilateral agreements)

Nuclear Power and Safety Division activity

International Nuclear Information System (INIS)

Pazdera, F.

1991-01-01

History of the Division is briefly described. Present research is centered on reliability analyses and thermal hydraulic analyses of transients and accidents. Some results of the safety analyses have been applied at nuclear power plants. A characterization is presented of computer codes for analyzing the behavior of fuel in normal and accident conditions. Research activities in the field of water chemistry and corrosion are oriented to the corrosion process at high temperatures and high pressures, and the related mass and radioactivity transfer; the effect of some chemical processes on primary coolant circuit materials; optimization of PWR filtration systems; and the development of the requisite monitoring instrumentation. A computerized operator support system has been developed, and at present it is tested at the Dukovany nuclear power plant. A program of nuclear fuel cycle strategy and economy has been worked out for nuclear fuel performance evaluation. Various options for better fuel exploitation, alternatives for advanced fuelling, and fuel cycle costs are assessed, and out-of-reactor fuel cycle options are compared. (M.D.). 7 refs., 32 refs

Steps to nuclear power

International Nuclear Information System (INIS)

1975-01-01

The recent increase in oil prices will undoubtedly cause the pace at which nuclear power is introduced in developing countries to quicken in the next decade, with many new countries beginning to plan nuclear power programmes. The guidebook is intended for senior government officials, policy makers, economic and power planners, educationalists and economists. It assumes that the reader has relatively little knowledge of nuclear power systems or of nuclear physics but does have a general technical or management background. Nuclear power is described functionally from the point of view of an alternative energy source in power system expansion. The guidebook is based on an idealized approach. Variations on it are naturally possible and will doubtless be necessary in view of the different organizational structures that already exist in different countries. In particular, some countries may prefer an approach with a stronger involvement of their Atomic Energy Commission or Authority, for which this guidebook has foreseen mainly a regulatory and licensing role. It is intended to update this booklet as more experience becomes available. Supplementary guidebooks will be prepared on certain major topics, such as contracting for fuel supply and fuel cycle requirements, which the present book does not go into very deeply

Synthetic fuel production via carbon neutral cycles with high temperature nuclear reactors as a power source

Energy Technology Data Exchange (ETDEWEB)

Konarek, E.; Coulas, B.; Sarvinis, J. [Hatch Ltd., Mississauga, Ontario (Canada)

2016-06-15

This paper analyzes a number of carbon neutral cycles, which could be used to produce synthetic hydrocarbon fuels. Synthetic hydrocarbons are produced via the synthesis of Carbon Monoxide and Hydrogen. The . cycles considered will either utilize Gasification processes, or carbon capture as a source of feed material. In addition the cycles will be coupled to a small modular Nuclear Reactor (SMR) as a power and heat source. The goal of this analysis is to reduce or eliminate the need to transport diesel and other fossil fuels to remote regions and to provide a carbon neutral, locally produced hydrocarbon fuel for remote communities. The technical advantages as well as the economic case are discussed for each of the cycles presented. (author)

Synthetic fuel production via carbon neutral cycles with high temperature nuclear reactors as a power source

International Nuclear Information System (INIS)

Konarek, E.; Coulas, B.; Sarvinis, J.

2016-01-01

This paper analyzes a number of carbon neutral cycles, which could be used to produce synthetic hydrocarbon fuels. Synthetic hydrocarbons are produced via the synthesis of Carbon Monoxide and Hydrogen. The . cycles considered will either utilize Gasification processes, or carbon capture as a source of feed material. In addition the cycles will be coupled to a small modular Nuclear Reactor (SMR) as a power and heat source. The goal of this analysis is to reduce or eliminate the need to transport diesel and other fossil fuels to remote regions and to provide a carbon neutral, locally produced hydrocarbon fuel for remote communities. The technical advantages as well as the economic case are discussed for each of the cycles presented. (author)

How nuclear power began

International Nuclear Information System (INIS)

Gowing, M.

1987-01-01

Many of the features of the story of nuclear power, both in nuclear weapons and nuclear power stations, derive from their timing. Usually, in the history of science the precise timing of discovery does not make much difference, but in the case of nuclear fission there was the coincidence that crucial discoveries were made and openly published in the same year, 1939, as the outbreak of the Second World War. It is these events of the 1930s and the early post-war era that are mainly discussed. However, the story began a lot earlier and even in the early 1900s the potential power within the atom had been foreseen by Soddy and Rutherford. In the 1930s Enrico Fermi and his team saw the technological importance of their discoveries and took out a patent on their process to produce artificial radioactivity from slow neutron beams. The need for secrecy because of the war, and the personal trusts and mistrusts run through the story of nuclear power. (UK)

World warms to nuclear power

International Nuclear Information System (INIS)

Mortimer, N.

1989-01-01

The greenhouse effect and global warming is a major environmental issue. The nuclear industry has taken this opportunity to promote itself as providing clean energy without implication in either the greenhouse effect or acid rain. However, it is acknowledged that nuclear power does have its own environment concerns. Two questions are posed -does nuclear power contribute to carbon dioxide emissions and can nuclear power provide a realistic long-term solution to global warming? Although nuclear power stations do not emit carbon dioxide, emissions occur during the manufacture of reactor components, the operation of the nuclear fuel cycle and especially, during the mining and processing of the uranium ore. It is estimated that the supply of high grade ores will last only 23 years, beyond that the carbon dioxide emitted during the processing is estimated to be as great as the carbon dioxide emitted from an coal-fired reactor. Fast breeder reactors are dismissed as unable to provide an answer, so it is concluded that nuclear technology has only a very limited role to play in countering global warming.(UK)

Heat exchanger inventory cost optimization for power cycles with one feedwater heater

International Nuclear Information System (INIS)

Qureshi, Bilal Ahmed; Antar, Mohamed A.; Zubair, Syed M.

2014-01-01

Highlights: • Cost optimization of heat exchanger inventory in power cycles is investigated. • Analysis for an endoreversible power cycle with an open feedwater heater is shown. • Different constraints on the power cycle are investigated. • The constant heat addition scenario resulted in the lowest value of the cost function. - Abstract: Cost optimization of heat exchanger inventory in power cycles with one open feedwater heater is undertaken. In this regard, thermoeconomic analysis for an endoreversible power cycle with an open feedwater heater is shown. The scenarios of constant heat rejection and addition rates, power as well as rate of heat transfer in the open feedwater heater are studied. All cost functions displayed minima with respect to the high-side absolute temperature ratio (θ 1 ). In this case, the effect of the Carnot temperature ratio (Φ 1 ), absolute temperature ratio (ξ) and the phase-change absolute temperature ratio for the feedwater heater (Φ 2 ) are qualitatively the same. Furthermore, the constant heat addition scenario resulted in the lowest value of the cost function. For variation of all cost functions, the smaller the value of the phase-change absolute temperature ratio for the feedwater heater (Φ 2 ), lower the cost at the minima. As feedwater heater to hot end unit cost ratio decreases, the minimum total conductance required increases

Transient evaluation using EMTP at one phase opening of the offsite power transformer of the emergency power supply systems for nuclear power plants. This report is a follow-up the last year's

International Nuclear Information System (INIS)

Shimada, Yoshio

2014-01-01

The emergency power supply systems of nuclear power plants, as the objects of this research, are critical to supplying stable electric power to such systems as the emergency core cooling system (ECCS), and to maintaining the safety of the nuclear power reactor; this was apparent from the accident at the Fukushima Daiichi Nuclear Power Station. The USNRC issued regulatory documents (BL 2012-01, IN 2012-03), and has commenced to review those problems which cannot be detected by degraded-voltage protection relays such as new design vulnerability of the power supply systems that are certain kinds of winding structures and iron core structures when the one-phase open fault occurs without a ground fault of the transformer connected to the offsite power supply system, including when the offsite power supply side is a wye connection and the load side is a delta connection etc. The report of the INSS JOURNAL 2013 used simulation by the electro-magnetic transients program (EMTP) and obtained findings that clearly specified the response at the time of the power supply side one-phase open without ground fault of various winding structures and various iron core structures of the three-phase transformer and identified the important issues for the response of emergency power supply systems and the safety related components of representative domestic PWR plants when the one-phase open fault occurred without ground fault. In a continuation of the previous report, this paper summarizes the previous results, and then presents the principles by which normal voltages are maintained by both the primary and the secondary sides when the one-phase open failure without ground fault occurs on the primary side of the transformer, and the results of the analysis of operations of the protection relays of the emergency power systems and the safety related components of representative a domestic PWR plant by the simulation using EMTP. (author)

The industrial nuclear fuel cycle in Argentina

International Nuclear Information System (INIS)

Koll, J.H.; Kittl, J.E.; Parera, C.A.; Coppa, R.C.; Aguirre, E.J.

1977-01-01

The nuclear power program of Argentina for the period 1976-85 is described, as a basis to indicate fuel requirements and the consequent implementation of a national fuel cycle industry. Fuel cycle activities in Argentina were initiated as soon as 1951-2 in the prospection and mining activities through the country. Following this step, yellow-cake production was initiated in plants of limited capacity. National production of uranium concentrate has met requirements up to the present time, and will continue to do so until the Sierra Pintada Industrial Complex starts operation in 1979. Presently, there is a gap in local production of uranium dioxide and fuel elements for the Atucha power station, which are produced abroad using Argentine uranium concentrate. With its background, the argentine program for the installation of nuclear fuel cycle industries is described, and the techno-economical implications considered. Individual projects are reviewed, as well as the present and planned infrastructure needed to support the industrial effort [es

Nuclear safeguards control in nuclear power stations

International Nuclear Information System (INIS)

Boedege, R.; Braatz, U.; Heger, H.

1976-01-01

The execution of the Non-Proliferation Treaty (NPT) has initiated a third phase in the efforts taken to ensure peace by limiting the number of atomic powers. In this phase it is important, above all, to turn into workable systems the conditions imposed upon technology by the different provisions of the Verification Agreement of the NPT. This is achieved mainly by elaborating annexes to the Agreement specifically geared to certain model plants, typical representatives selected for LWR power stations being the plants at Garigliano, Italy (BWR), and Stade, Federal Republic of Germany (PWR). The surveillance measures taken to prevent any diversion of special nuclear material for purposes of nuclear weapons manufacture must be effective in achieving their specific objective and must not impede the circumspect management of operations of the plants concerned. A VDEW working party has studied the technical details of the planned surveillance measures in nuclear power stations in the Federal Republic of Germany and now presents a concept of material balancing by units which meets the conditions imposed by the inspection authority and could also be accepted by the operators of nuclear power stations. The concept provides for uninterrupted control of the material balance areas of the nuclear power stations concerned, allows continuous control of the whole nuclear fuel cycle, is based exclusively on existing methods and facilities, and can be implemented at low cost. (orig.) [de

Greenfield nuclear power for Finland

Energy Technology Data Exchange (ETDEWEB)

Saarenpaa, Tapio

2010-09-15

In Finland, licensing for new nuclear power is ongoing. The political approval is to be completed in 2010. Fennovoima's project is unique in various ways: (i) the company was established only in 2007, (ii) its ownership includes a mixture of local energy companies, electricity-intensive industries and international nuclear competence through E.ON, and (iii) it has two alternative greenfield sites. There are five prerequisites for a successful nuclear power project in a transparent democracy of today: (1) need for additional power capacity, (2) actor prepared to invest, (3) established competence, (4) available site, (5) open communications, and (6) favorable public opinion.

Nuclear power newsletter Vol. 3, no. 1, April 2006

International Nuclear Information System (INIS)

2006-04-01

The topics presented in this newsletter are: Nuclear power technology and operations databases; Message from the Director of the Division of Nuclear Power; Announcement of Mr. Atam Rao, the new Head of Nuclear Power Technology Development Section; Nuclear power plant operating performance and life cycle management; Improving human performance, quality and technical infrastructure; Technology developments and applications for advanced reactors; Recent publications; Planned meetings in 2006; Division of Nuclear Power Web site links; The 7th IAEA - FORATOM Joint Workshop on Successful Management of Organizational Change

Survey of nuclear fuel cycle economics: 1970--1985

International Nuclear Information System (INIS)

Prince, B.E.; Peerenboom, J.P.; Delene, J.G.

1977-03-01

This report is intended to provide a coherent view of the diversity of factors that may affect nuclear fuel cycle economics through about 1985. The nuclear fuel cycle was surveyed as to past trends, current problems, and future considerations. Unit costs were projected for each step in the fuel cycle. Nuclear fuel accounting procedures were reviewed; methods of calculating fuel costs were examined; and application was made to Light Water Reactors (LWR) over the next decade. A method conforming to Federal Power Commission accounting procedures and used by utilities to account for backend fuel-cycle costs was described which assigns a zero net salvage value to discharged fuel. LWR fuel cycle costs of from 4 to 6 mills/kWhr (1976 dollars) were estimated for 1985. These are expected to reach 6 to 9 mills/kWr if the effect of inflation is included

Transition Towards a Sustainable Nuclear Fuel Cycle

International Nuclear Information System (INIS)

McCarthy, K.; Romanello, V.; Schwenk-Ferrero, A.; Vezzoni, B.; Gabrielli, F.; Maschek, W.; Rineiski, A.; Salvatores, M.

2013-01-01

. In this respect, it is considered that the potential future scarcity of uranium resources is not at all unreasonable, but it is a very serious perspective for the regions of the world where the energy demand growth is and will very probably continue to be significant with the use of nuclear energy to meet at least partially that demand. In fact, despite the seriousness of the recent Fukushima Daiichi accident, only a few countries (essentially in the OECD region) have reacted with an abrupt decision to phase out nuclear power. Most countries, where the energy demand growth corresponds to an urgent need to achieve widely improved living standards, have launched or completed extensive reviews of their nuclear programmes, but are also continuing with ongoing construction projects. The results of this study are very much related to the hypotheses made, in particular in terms of energy demand growth. However, some general trends seem to be of a general value and can motivate further studies. It was confirmed in this investigation that a rapid development of fast reactors, especially in areas with expanding economies and strong energy demand growth, is essential for nuclear energy sustainability, for saving natural uranium resources worldwide and for reducing high-level waste generation requiring disposal. A key parameter is the fast reactor doubling time which has to be chosen appropriately in order to meet energy requirements. In the case of an open cycle, a potential increase in pressure on the uranium market could be expected towards the end of the current century. Moreover, the increase in mining needs of unequally distributed resources can be a factor of uncertainty with an impact potentially even more important of uranium cost considerations. It would, however, be a very significant challenge to develop suitable fuel cycle infrastructure especially in the world regions that presently have a limited number of (or no) nuclear power plants. In fact, the needed fuel

Nuclear power fuel cycle

International Nuclear Information System (INIS)

Havelka, S.; Jakesova, L.

1982-01-01

Economic problems are discussed of the fuel cycle (cost of the individual parts of the fuel cycle and the share of the fuel cycle in the price of 1 kWh), the technological problems of the fuel cycle (uranium ore mining and processing, uranium isotope enrichment, the manufacture of fuel elements, the building of long-term storage sites for spent fuel, spent fuel reprocessing, liquid and gaseous waste processing), and the ecologic aspects of the fuel cycle. (H.S.)

Effects of degree of approval and message on utility of nuclear fuel cycle

International Nuclear Information System (INIS)

Tanigaki, Toshihiko

2007-01-01

It is said that the effectiveness of nuclear power generation is the greatest factor contributing to whether or not people support the nuclear power policy. The major objectives of this research are twofold: from among opinions regarding the effectiveness of the nuclear fuel cycle, to clarify what kinds of opinions people support and what kinds of opinions have influenced judgments about the pros and cons of the nuclear fuel cycle; and to measure the extent to which people's awareness of the nuclear fuel cycle is influenced by numerical information that has been added to a nuclear-fuel-cycle-related message that has been created on the basis of results of the survey conducted for the first objective mentioned above. As for the first objective, the survey results revealed that the opinion 'the establishment of a nuclear fuel cycle leads to the effective use of energy resources' did not garner much support from the public. However, it was indicated that people being for or against that opinion may have relatively great effect on their judgment regarding the pros and ons of nuclear fuel cycle establishment. For the second objective, we showed people the messages the nuclear fuel cycle enables effective use of natural uranium' and 'the nuclear fuel cycle enables tens times more effective use of natural uranium' to the latter of which numerical information was added. As a result, we found no difference in people's attitude toward the nuclear fuel cycle even if numerical information was added to a nuclear-fuel-cycle-related message. (author)

To Recycle or Not to Recycle? An Intergenerational Approach to Nuclear Fuel Cycles

NARCIS (Netherlands)

Taebi, B.; Kloosterman, J.L.

2007-01-01

AbstractThis paper approaches the choice between the open and closed nuclear fuel cycles as a matter of intergenerational justice, by revealing the value conflicts in the production of nuclear energy. The closed fuel cycle improve sustainability in terms of the supply certainty of uranium and

International nuclear power status 2001; International kernekraftstatus 2001

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; Majborn, B.; Nonboel, E.; Oelgaard, P.L. (eds.)

2002-04-01

This report is the eighth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2001, the report contains: 1) General trends in the development of nuclear power; 2) Nuclear terrorism; 3) Statistical information on nuclear power production (in 2000); 4) An overview of safety-relevant incidents in 2001; 5) The development in West Europe; 6) The development in East Europe; 7) The development in the rest of the world; 8) Development of reactor types; 9) The nuclear fuel cycle; 10) International nuclear organisations. (au)

Exploring nuclear energy scenarios - implications of technology and fuel cycle choices

International Nuclear Information System (INIS)

Rayment, Fiona; Mathers, Dan; Gregg, Robert

2014-01-01

Nuclear Energy is recognised globally as a mature, reliable low carbon technology with a secure and abundant fuel source. Within the UK, Nuclear Energy is an essential contributor to the energy mix and as such a decision has been made to refresh the current nuclear energy plants to at least replacement of the existing nuclear fleet. This will mean the building of new nuclear power plant to ensure energy production of 16 GWe per annum. However it is also recognised that this may not be enough and as such expansion scenarios ranging from replacement of the existing fleet to 75 GWe nuclear energy capacity are being considered (see appendix). Within these energy scenarios, a variety of options are being evaluated including electricity generation only, electricity generation plus heat, open versus closed fuel cycles, Generation III versus Generation IV systems and combinations of the above. What is clear is that the deciding factor on the type and mix of any energy programme will not be on technology choice alone. Instead a complex mix of Government policy, relative cost of nuclear power, market decisions and public opinion will influence the rate and direction of growth of any future energy programme. The UK National Nuclear Laboratory has supported this work through the use and development of a variety of assessment and modelling techniques. When assessing nuclear energy scenarios, the technology chosen will impact on a number of parameters within each scenario which includes but is not limited to: - Economics, - Nuclear energy demand, - Fuel Supply, - Spent fuel storage / recycle, - Geological repository volumetric and radiological capacity, - Sustainability - effective resource utilisation, - Technology viability and readiness level. A number of assessment and modelling techniques have been developed and are described further. In particular, they examine fuel cycle options for a number of nuclear energy scenarios, whilst exploring key implications for a particular

TOSHIBA CAE system for nuclear power plant

International Nuclear Information System (INIS)

Machiba, Hiroshi; Sasaki, Norio

1990-01-01

TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

French lessons in nuclear power

International Nuclear Information System (INIS)

Valenti, M.

1991-01-01

In stark contrast to the American atomic power experience is that of the French. Even the disaster at Chernobyl in 1986, which chilled nuclear programs throughout Western Europe, did not slow the pace of the nuclear program of the state-owned Electricite de France (EDF), based in Paris. Another five units are under construction and are scheduled to be connected to the French national power grid before the end of 1993. In 1989, the EDF's 58 nuclear reactors supplied 73 percent of French electrical needs, a higher percentage than any other country. In the United States, for example, only about 18 percent of electrical power is derived from the atom. Underpinning the success of nuclear energy in France is its use of standardized plant design and technology. This has been an imperative for the French nuclear power industry since 1974, when an intensive program of nuclear power plant construction began. It was then, in the aftermath of the first oil embargo, that the French government decided to reduce its dependence on imported oil by substituting atomic power sources for hydrocarbons. Other pillars supporting French nuclear success include retrofitting older plants with technological or design advances, intensive training of personnel, using robotic and computer aids to reduce downtime, controlling the entire nuclear fuel cycle, and maintaining a comprehensive public information effort about the nuclear program

Change impact analysis on the life cycle carbon emissions of energy systems – The nuclear example

International Nuclear Information System (INIS)

Nian, Victor

2015-01-01

Highlights: • This paper evaluates the life cycle carbon emission of nuclear power in a scenario based approach. • It quantifies the impacts to the LCA results from the change in design parameters. • The methodology can give indications towards preferred or favorable designs. • The findings contribute to the life cycle inventories of energy systems. - Abstract: The life cycle carbon emission factor (measured by t-CO 2 /GW h) of nuclear power is much lower than those of fossil fueled power generation technologies. However, the fact of nuclear energy being a low carbon power source comes with many assumptions. These assumptions range from system and process definitions, to input–output definitions, to system boundary and cut-off criteria selections, and life cycle inventory dataset. However, there is a somewhat neglected but critical aspect – the design aspect. This refers to the impacts on the life cycle carbon emissions from the change in design parameters related to nuclear power. The design parameters identified in this paper include: (1) the uranium ore grade, (2) the critical process technologies, represented by the average initial enrichment concentration of 235 U in the reactor fuel, and (3) the size of the nuclear power reactor (measured by the generating capacity). If not properly tested, assumptions in the design aspect can lead to an erroneous estimation on the life cycle carbon emission factor of nuclear power. In this paper, a methodology is developed using the Process Chain Analysis (PCA) approach to quantify the impacts of the changes in the selected design parameters on the life cycle carbon emission factor of nuclear power. The concept of doing so broadens the scope of PCAs on energy systems from “one-off” calculation to analysis towards favorable/preferred designs. The findings from the analyses can serve as addition to the life cycle inventory database for nuclear power as well as provide indications for the sustainability of

Analysis of environmental impact phase in the life cycle of a nuclear power plant; Analisis de la fase de impacto ambiental en el ciclo de vida de una central nuclear

Energy Technology Data Exchange (ETDEWEB)

Hernandez del M, C.

2015-07-01

The life-cycle analysis covers the environmental aspects of a product throughout its life cycle. The focus of this study was to apply a methodology of life-cycle analysis for the environmental impact assessment of a nuclear power plant by analyzing international standards ISO 14040 and 14044. The methodology of life-cycle analysis established by the ISO 14044 standard was analyzed, as well as the different impact assessment methodologies of life cycle in order to choose the most appropriate for a nuclear power plant; various tools for the life-cycle analysis were also evaluated, as is the use of software and the use of databases to feed the life cycle inventory. The functional unit chosen was 1 KWh of electricity, the scope of analysis ranging from the construction and maintenance, disposal of spent fuel to the decommissioning of the plant, the manufacturing steps of the fuel were excluded because in Mexico is not done this stage. For environmental impact assessment was chosen the Recipe methodology which evaluates up to 18 impact categories depending on the project. In the case of a nuclear power plant were considered only categories of depletion of the ozone layer, climate change, ionizing radiation and formation of particulate matter. The different tools for life-cycle analysis as the methodologies of impact assessment of life cycle, different databases or use of software have been taken according to the modeling of environmental sensitivities of different regions, because in Mexico the methodology for life-cycle analysis has not been studied and still do not have all the tools necessary for the evaluation, so the uncertainty of the data supplied and results could be higher. (Author)

Independent assessment of forseeable problems in the nuclear fuel cycle

International Nuclear Information System (INIS)

1975-01-01

Information is presented concerning the U. S. nuclear fuel cycle business including investment requirements; nuclear power growth projection; reliability of uranium supply; enrichment facilities; plutonium recycle; safeguards; and insurance

Nuclear power newsletter Vol. 3, no. 4, December 2006

International Nuclear Information System (INIS)

2006-12-01

The topics presented in this newsletter are: The 1st Joint IAEA-EPRI Workshop on Modernization of Instrumentation and Control Systems in Nuclear Power Plants; Message from the Director of the Division of Nuclear Power; Nuclear power plant operation; Management system, infrastructure and training; International Project on Innovative Nuclear Reactors and Fuel Cycles; Technology developments and applications for advanced reactors; Planned meetings in 2007

International nuclear power status 1999; International kernekraftstatus 1999

Energy Technology Data Exchange (ETDEWEB)

Hoejerup, C.F.; Oelgaard, P.L. [eds.

2000-03-01

This report isthe sixth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 1999, the report contains: General trends in the development of nuclear power; The past and possible future of Barsebaeck Nuclear Power Plant; Statistical information on nuclear power production (in 1998); An overview of safety-relevant incidents in 1999; The development in Sweden; The development in Eastern Europe; The development in the rest of the world; Trends in the development of reactor types; Trends in the development of the nuclear fuel cycle. (au)

The nuclear power decisions

International Nuclear Information System (INIS)

Williams, R.

1980-01-01

Nuclear power has now become highly controversial and there is violent disagreement about how far this technology can and should contribute to the Western energy economy. More so than any other energy resource, nuclear power has the capacity to provide much of our energy needs but the risk is now seen to be very large indeed. This book discusses the major British decisions in the civil nuclear field, and the way they were made, between 1953 and 1978. That is, it spans the period between the decision to construct Calder Hall - claimed as the world's first nuclear power station - and the Windscale Inquiry - claimed as the world's most thorough study of a nuclear project. For the period up to 1974 this involves a study of the internal processes of British central government - what the author terms 'private' politics to distinguish them from the very 'public' or open politics which have characterised the period since 1974. The private issues include the technical selection of nuclear reactors, the economic arguments about nuclear power and the political clashes between institutions and individuals. The public issues concern nuclear safety and the environment and the rights and opportunities for individuals and groups to protest about nuclear development. The book demonstrates that British civil nuclear power decision making has had many shortcomings and concludes that it was hampered by outdated political and administrative attitudes and machinery and that some of the central issues in the nuclear debate were misunderstood by the decision makers themselves. (author)

Fuel Cycle Services The Heart of Nuclear Energy

International Nuclear Information System (INIS)

Soedyartomo-Soentono

2007-01-01

Fuel is essential for development whether for survival and or wealth creation purposes. In this century the utilization of fuels need to be improved although energy mix is still to be the most rational choice. The large amount utilization of un-renewable fossil has some disadvantages since its low energy content requires massive extraction, transport, and processing while emitting CO 2 resulting degradation of the environment. In the mean time the advancement of nuclear science and technology has improved significantly the performance of nuclear power plant management of radioactive waste, enhancement of proliferation resistance, and more economic competitiveness. Ever since the last decade of the last century the nuclear renaissance has taken place. This is also due to the fact that nuclear energy does not emit GHG. Although the nuclear fuel offers a virtually limitless source of economic energy, it is only so if the nuclear fuel is reprocessed and recycled. Consequently, the fuel cycle is to be even more of paramount important in the future. The infrastructure of the fuel cycle services world wide has been adequately available. Various International Initiatives to access the fuel cycle services are also offered. However, it is required to put in place the International Arrangements to guaranty secured sustainable supply of services and its peaceful use. Relevant international cooperations are central for proceeding with the utilization of nuclear energy, while this advantagous nuclear energy utilization relies on the fuel cycle services. It is therefore concluded that the fuel cycle services are the heart of nuclear energy, and the international nuclear community should work together to maintain the availability of this nuclear fuel cycle services timely, sufficiently, and economically. (author)

Fuel Cycle Services the Heart of Nuclear Energy

Directory of Open Access Journals (Sweden)

S. Soentono

2007-01-01

Full Text Available Fuel is essential for development whether for survival and or wealth creation purposes. In this century the utilization of fuels need to be improved although energy mix is still to be the most rational choice. The large amount utilization of un-renewable fossil has some disadvantages since its low energy content requires massive extraction, transport, and processing while emitting CO2 resulting degradation of the environment. In the mean time the advancement of nuclear science and technology has improved significantly the performance of nuclear power plant, management of radioactive waste, enhancement of proliferation resistance, and more economic competitiveness. Ever since the last decade of the last century the nuclear renaissance has taken place. This is also due to the fact that nuclear energy does not emit GHG. Although the nuclear fuel offers a virtually limitless source of economic energy, it is only so if the nuclear fuel is reprocessed and recycled. Consequently, the fuel cycle is to be even more of paramount important in the future. The infrastructure of the fuel cycle services worldwide has been adequately available. Various International Initiatives to access the fuel cycle services are also offered. However, it is required to put in place the International Arrangements to guaranty secured sustainable supply of services and its peaceful use. Relevant international co-operations are central for proceeding with the utilization of nuclear energy, while this advantageous nuclear energy utilization relies on the fuel cycle services. It is therefore concluded that the fuel cycle services are the heart of nuclear energy, and the international nuclear community should work together to maintain the availability of this nuclear fuel cycle services timely, sufficiently, and economically.

The role of nuclear power and nuclear propulsion in the peaceful exploration of space

International Nuclear Information System (INIS)

2005-09-01

This publication has been produced within the framework of the IAEA's innovative reactor and fuel cycle technology development activities. It elucidates the role that peaceful space related nuclear power research and development could play in terrestrial innovative reactor and fuel cycle technology development initiatives. This review is a contribution to the Inter-Agency Meeting on Outer Space Activities, and reflects the stepped up efforts of the Scientific and Technical Subcommittee of the Committee on the Peaceful Uses of Outer Space to further strengthen cooperation between international organizations in space related activities. Apart from fostering information exchange within the United Nations organizations, this publication aims at finding new potential fields for innovative reactor and fuel cycle technology development. In assessing the status and reviewing the role of nuclear power in the peaceful exploration of space, it also aims to initiate a discussion on the potential benefits of space related nuclear power technology research and development to the development of innovative terrestrial nuclear systems

Is there a tomorrow for nuclear power generation?

International Nuclear Information System (INIS)

Kanoh, T.

1996-01-01

Critical comments are publicly made about nuclear power generation and the nuclear fuel cycle. This criticism is directed at three areas of concern: accidents, radioactive waste disposal, and proliferation of nuclear weapons. In addition, there are other comments that ask 'Why are there countries pushing for nuclear power generation when other countries around the world are giving it up?' and 'Will further efforts to develop new energy sources and energy conservation not eliminate the nneed for nuclear power generation?' Such critical comments appear in some media more often than those expressing other opinions. Is there really no tomorrow for nuclear power? This question is studied below. (author)

World Health Organization on nuclear power

International Nuclear Information System (INIS)

Anon.

1977-01-01

A report published by the World Health Organization in cooperation with, and at the instigation of, the Belgian authorities, is summarised. The report was prepared by an international multidisciplinary working group, and concentrated on the somatic and genetic risks from ionising radiation, the environmental effects of nuclear power from the mining of uranium to the disposal of waste and the probability and consequences of accidents, sabotage and theft of nuclear materials. In general positive to nuclear power, the report nevertheless recommends for RESEARCH AND EVALUATION IN SEVERAL SECTORS: The duties of the authorities in providing full and open information on the consequences of the exploitation of nuclear power are emphasised. (JIW)

Nuclear fuel cycle system analysis

International Nuclear Information System (INIS)

Ko, W. I.; Kwon, E. H.; Kim, S. G.; Park, B. H.; Song, K. C.; Song, D. Y.; Lee, H. H.; Chang, H. L.; Jeong, C. J.

2012-04-01

The nuclear fuel cycle system analysis method has been designed and established for an integrated nuclear fuel cycle system assessment by analyzing various methodologies. The economics, PR(Proliferation Resistance) and environmental impact evaluation of the fuel cycle system were performed using improved DB, and finally the best fuel cycle option which is applicable in Korea was derived. In addition, this research is helped to increase the national credibility and transparency for PR with developing and fulfilling PR enhancement program. The detailed contents of the work are as follows: 1)Establish and improve the DB for nuclear fuel cycle system analysis 2)Development of the analysis model for nuclear fuel cycle 3)Preliminary study for nuclear fuel cycle analysis 4)Development of overall evaluation model of nuclear fuel cycle system 5)Overall evaluation of nuclear fuel cycle system 6)Evaluate the PR for nuclear fuel cycle system and derive the enhancement method 7)Derive and fulfill of nuclear transparency enhancement method The optimum fuel cycle option which is economical and applicable to domestic situation was derived in this research. It would be a basis for establishment of the long-term strategy for nuclear fuel cycle. This work contributes for guaranteeing the technical, economical validity of the optimal fuel cycle option. Deriving and fulfillment of the method for enhancing nuclear transparency will also contribute to renewing the ROK-U.S Atomic Energy Agreement in 2014

Algebraic approach for the diagnosis of turbine cycles in nuclear power plants

International Nuclear Information System (INIS)

Heo, Gyunyoung; Chang, Soon Heung

2005-01-01

According to plant operating staff's practical needs, authors proposed a diagnosis model to identify the performance degradation of steam turbine cycles in nuclear power plants (NPPs). The essential idea of this study is how to identify the intrinsically degraded component which causes electric loss. Authors found that there were not so many turbine cycle diagnosis applications in NPPs currently because of technical, financial, or social characteristics of the plant. So a great part of the diagnosis has been dependent on operating staff's experience and knowledge. However as economic competition becomes severe, the efficiency staffs is asking for reliable and practical advisory tools. For the solution of these shortcomings, authors proposed a simple and intuitive diagnosis concept based on the superposition rule of degradation phenomena, which can be derived by simple algebra and correlation analysis. Though the superposition rule is not so significant statistically, almost all of the performance indices under normal operation are fairly compatible with this model. Authors developed a prototype model of quantitative root-cause diagnosis and validated the background theory using the simulated data. The turbine cycle advisory system using this model was applied to Gori NPP units 3 and 4

Nuclear-fuel-cycle costs. Consolidated Fuel-Reprocessing Program

International Nuclear Information System (INIS)

Burch, W.D.; Haire, M.J.; Rainey, R.H.

1981-01-01

The costs for the back-end of the nuclear fuel cycle, which were developed as part of the Nonproliferation Alternative Systems Assessment Program (NASAP), are presented. Total fuel-cycle costs are given for the pressurized-water reactor once-through and fuel-recycle systems, and for the liquid-metal fast-breeder-reactor system. These calculations show that fuel-cycle costs are a small part of the total power costs. For breeder reactors, fuel-cycle costs are about half that of the present once-through system. The total power cost of the breeder-reactor system is greater than that of light-water reactor at today's prices for uranium and enrichment

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

The separation of nuclear power from nuclear proliferation

International Nuclear Information System (INIS)

Starr, C.

1979-01-01

There exists world wide a strong common desire to limit nuclear weapons proliferation so as to inhibit or remove the threat of nuclear warfare. While this is a primary international political objective, there has also developed a secondary objective to limit any potential contribution to such nuclear weapons proliferation which might arise by the diversion of weapons material from the civilian nuclear power fuel cycle. This secondary objective is the basis of the present US government policy to defer the reprocessing of nuclear fuels anywhere. This policy has been generally recognized as a temporary expedient to provide time for international reexamination of the problems of weapons proliferation associated with nuclear power. A successful development of the proposed combination of the Fast Breeder Reactor and the Civex fuel reprocessing facility would provide an economical nuclear power source for many centuries which inherently separates nuclear power from the issue of weapons material diversion and proliferation. Further, by so doing, it permits great flexibility in international and national planning for nuclear power, as the issues of fuel dependence and terrorist and subnational diversions disappear. In addition, the expansion of the FBR/Civex system would eat into the LWR spent fuel stockpile, diminishing steadily this relatively accessible plutonium source. And finally, a rapid development of the FBR/Civex for the above reasons would substantially reduce the worldwide concern as to the adequacy of uranium ore supply. (Auth.)

Nuclear power : world and Australia - a long-term view

Energy Technology Data Exchange (ETDEWEB)

Ford, G W.K.

1989-01-01

Developments in world and Australian activities relating to nuclear power and the nuclear fuel cycle are reviewed. Main issues addressed include environment, energy sources, uranium mining, enrichment, reactor design, fuel reprocessing and waste disposal. The benefits for Australia through its involvement in all stages of the nuclear fuel cycle are also discussed.

World nuclear capacity and fuel cycle requirements, November 1993

International Nuclear Information System (INIS)

1993-01-01

This analysis report presents the current status and projections of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. Long-term projections of US nuclear capacity, generation, fuel cycle requirements, and spent fuel discharges for three different scenarios through 2030 are provided in support of the Department of Energy's activities pertaining to the Nuclear Waste Policy Act of 1982 (as amended in 1987). The projections of uranium requirements also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment

Guidebook on the introduction of nuclear power

International Nuclear Information System (INIS)

1982-01-01

This ''Guidebook on the Introduction of Nuclear Power'' has been structured into three parts. The first part contains a survey of nuclear power, with the objective of providing general background information to the reader on the present status and future prospects of nuclear power and on the technical and economic aspects of available power reactor types and nuclear fuel cycles. In the second part of the Guidebook, the special aspects and considerations relevant to the introduction of nuclear power in a country are discussed. The subject is subdivided into three main headings: the technical aspects and national requirements; the safety and environmental considerations; and the international aspects of nuclear power. Emphasis is placed on the tasks to be performed within the country introducing nuclear power, on responsibilities that cannot be delegated and on the need for adequate national infrastructures and long-term commitments. Finally, the third part of the Guidebook contains more detailed information and guidance on the planning and preparatory stages of launching a first nuclear power project, including in particular: nuclear power programme planning, siting, feasibility studies, bidding and contracting. Design, construction and operation are covered in a brief overview for the sake of completeness

Fuel for the next Brazilian nuclear power plants

International Nuclear Information System (INIS)

Lameiras, Fernando S.; Faeda, Kelly Cristina Ferreira

2009-01-01

The conclusion of the Angra III nuclear power plant ends a cycle of the nuclear energy in Brazil that started about forty years ago. Nowadays the country is planning the installation of 4 GWe to 8 GWe of nuclear power up to the year 2030. The nuclear reactors considered for this new cycle should take into account the current technologic development and environment of the nuclear market. They certainly will have significant differences in relation to the Angra I, II, and III reactors. Important impacts may result on the nuclear fuel production chain, e. g., case high temperature reactors were chosen, which can deliver electricity and heat. The differences between the fuels of the candidate reactors after Angra III are analyzed and development lines are suggested to minimize these impacts. (author)