World nuclear fuel cycle

International Nuclear Information System (INIS)

Anon.

1979-01-01

A coloured pull-out wall chart is presented showing the fuel cycle interests of the world. Place names are marked and symbols are used to indicate regions associated with uranium or thorium deposits, mining, milling, enrichment, reprocessing and fabrication. (UK)

The nuclear fuel elements' world market and the position of the Argentine Republic as producer

International Nuclear Information System (INIS)

Biondo, C.D.

1983-01-01

The development of the nuclear fuel elements' industry is analyzed, both in the present and projected world market, up to the year 2000, in the light of the situation affecting the nucleoelectric industry. By means of the offer/demand function, an analysis is made of the behaviour of the fuel elements' market throughout the fuel cycle structure. The regional unbalances between availability and demand of uranium resources are considered, as well as the factors having an unfavorable incidence on the fuel cycle's economic equation. The economic structure to be used for the calculation of the nucleoelectric generating cost is presented, in order to situate, within said nuclear economy, the component corresponding to the fuel cycle cost. Emphasis is placed on the 'front end' stages of the fuel cycle, but also considering those stages belonging to the 'back end'. Argentina's fuel elements market and its present and projected nucleoelectric park are analyzed, indicating their relative position in the world market. (R.J.S.) [es

Nuclear power and the nuclear fuel cycle

International Nuclear Information System (INIS)

Hardy, C.J.; Silver, J.M.

1985-09-01

The report provides data and assessments of the status and prospects of nuclear power and the nuclear fuel cycle. The report discusses the economic competitiveness of nuclear electricity generation, the extent of world uranium resources, production and requirements, uranium conversion and enrichment, fuel fabrication, spent fuel treatment and radioactive waste management. A review is given of the status of nuclear fusion research

Nuclear power and the nuclear fuel cycle

International Nuclear Information System (INIS)

Scurr, I.F.; Silver, J.M.

1990-01-01

Australian Nuclear Science and Technology Organization maintains an ongoing assessment of the world's nuclear technology developments, as a core activity of its Strategic Plan. This publication reviews the current status of the nuclear power and the nuclear fuel cycle in Australia and around the world. Main issues discussed include: performances and economics of various types of nuclear reactors, uranium resources and requirements, fuel fabrication and technology, radioactive waste management. A brief account of the large international effort to demonstrate the feasibility of fusion power is also given. 11 tabs., ills

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.)

Nuclear fuel

International Nuclear Information System (INIS)

Azevedo, J.B.L. de.

1980-01-01

All stages of nuclear fuel cycle are analysed with respect to the present situation and future perspectives of supply and demand of services; the prices and the unitary cost estimation of these stages for the international fuel market are also mentioned. From the world resources and projections of uranium consumption, medium-and long term analyses are made of fuel availability for several strategies of use of different reactor types. Finally, the cost of nuclear fuel in the generation of electric energy is calculated to be used in the energetic planning of the electric sector. (M.A.) [pt

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

International Nuclear Information System (INIS)

Saint-Pierre, Sylvain

2006-01-01

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

Nuclear fuel cycle information workshop

International Nuclear Information System (INIS)

1983-01-01

This overview of the nuclear fuel cycle is divided into three parts. First, is a brief discussion of the basic principles of how nuclear reactors work; second, is a look at the major types of nuclear reactors being used and world-wide nuclear capacity; and third, is an overview of the nuclear fuel cycle and the present industrial capability in the US

World nuclear performance report 2016. A new study by World Nuclear Association

Energy Technology Data Exchange (ETDEWEB)

Cobb, Jonathan [World Nuclear Association, London (United Kingdom)

2016-08-15

A larger number of nuclear power units are under construction than at any other time in the last 25 years, and with another ten new reactors coming online 2015 demonstrated improving new build performance all round. The existing global fleet, totally 439 by year-end, generated roughly 10 % of the world's electricity, making up around one-third of the world's low-carbon electricity supply. Nevertheless, there are challenges ahead for the global nuclear industry. The World Nuclear Association's vision for the future global electricity system consists of a diverse mix of low-carbon technologies - where renewables, nuclear and a fossil fuels work together in harmony to ensure a reliable, affordable and clean energy supply.

World nuclear performance report 2016. A new study by World Nuclear Association

International Nuclear Information System (INIS)

Cobb, Jonathan

2016-01-01

A larger number of nuclear power units are under construction than at any other time in the last 25 years, and with another ten new reactors coming online 2015 demonstrated improving new build performance all round. The existing global fleet, totally 439 by year-end, generated roughly 10 % of the world's electricity, making up around one-third of the world's low-carbon electricity supply. Nevertheless, there are challenges ahead for the global nuclear industry. The World Nuclear Association's vision for the future global electricity system consists of a diverse mix of low-carbon technologies - where renewables, nuclear and a fossil fuels work together in harmony to ensure a reliable, affordable and clean energy supply.

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

World nuclear outlook 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-29

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

World nuclear outlook 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-01

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2010 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for three different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

World nuclear outlook 1994

International Nuclear Information System (INIS)

1994-12-01

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2010 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for three different scenarios through 2040 are developed for the Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries

World nuclear outlook 1995

International Nuclear Information System (INIS)

1995-01-01

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed for the Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries

Spent fuel accumulations and arisings in 'fuel user' states: implications for a world nuclear partnership

International Nuclear Information System (INIS)

Lineberry, M.J.

2007-01-01

Consider the question: In a GNEP world, what are the implications of current spent fuel inventories and possible future accumulations in 'fuel user' states? The inventory today (∼95,000 MTHM) and the growth rate (∼4,000 MTHM/yr) in likely fuel user states is roughly twice that in the U.S., and thus the problem is substantial. The magnitude of the issue increases if, as is expected, fuel user states grow their nuclear capacity. For purposes of illustration, 2% annual growth assumed in this study. There is an implied imperative to remove spent fuel inventories from fuel user states in some reasonable time (if the spent fuel backlog cannot be cleared by 2100, what motivation is there for GNEP today?). Clearing the backlog requires massive reprocessing capacity, but that makes no economic or strategic sense until the advanced burner reactors are developed and deployed. Thus, burner reactor development is the pacing item with any practical GNEP schedule. With regard to economics, cost estimates for reprocessing (which drive key GNEP costs) are much too disparate today. The disparities must be lessened in order to permit rational decision-making. (author)

Future trends in nuclear fuels

International Nuclear Information System (INIS)

Guitierrez, J.E.

2006-01-01

This series of transparencies presents: the fuel management cycle and key areas (security of supplies, strategies and core management, reliability, spent fuel management), the world nuclear generating capacity, concentrate capacity, enrichment capacity, and manufacturing capacity forecasts, the fuel cycle strategies and core management (longer cycles, higher burnups, power up-rates, higher enrichments), the Spanish nuclear generation cost, the fuel reliability (no defects, robust designs, operational margins, integrated fuel and core design), spent fuel storage (design and safety criteria, fuel performance and integrity). (J.S.)

Prospects for the world nuclear energy market

Energy Technology Data Exchange (ETDEWEB)

1976-04-01

Over the last few years projections of nuclear power generating capacity growth for the next two decades have progressively decreased. Dwindling load growth, increasing load lead time, costs of delays and high cost inflation, industrial recession, and fuel cycle delays are discussed as the main causes of the setback. The state of the fuel cycle business in the world market is examined and data are presented and discussed for predicted world supply and demand. Nuclear plans and fuel policies and requirements are then examined for individual countries.

Nuclear fuel strategies

International Nuclear Information System (INIS)

Rippon, S.

1989-01-01

The paper reports on two international meetings on nuclear fuel strategies, one organised by the World Nuclear Fuel Market in Seville (Spain) October 1988, and the other organised by the American and European nuclear societies in Washington (U.S.A.) November 1988. At the Washington meeting a description was given of the uranium supply and demand market, whereas free trade in uranium was considered in Seville. Considerable concern was expressed at both meetings on the effect on the uranium and enrichment services market of very low prices for spot deals being offered by China and the Soviet Union. Excess enrichment capacity, the procurement policies of the USA and other countries, and fuel cycle strategies, were also discussed. (U.K.)

World situation of atomic energy and nuclear fuel cycle

International Nuclear Information System (INIS)

Szili, G.

1978-01-01

At the International Conference organized by the IAEA in May 1976, several sections dealt with problems of the production of atomic energy and of the nuclear fuel cycle. However, the whole spectrum of these problems was discussed including problems of economic policy, politics and ethical problems, too. Reports were presented on trends of the development of atomic energy in developed and developing countries. Besides the systems of nuclear power plants and the trends of their development, the Conference attached prominent importance to the supply of nuclear fuels and to the fuel cycle, respectively. Owing to important factors, the reprocessing of the spent nuclear fuel was emphasized. The problem area of the treatment of radioactive wastes, the protection of workers in immediate contact and of environment against radiations, the possibilities of ensuring nuclear safety, the degrees of hazards and the methods of protection of fast breeder reactors and up-to-date equipments were discussed. In contrast to earlier conferences the complex problem of the correlation of atomic energy to public opinion played an important role, too. (P.J.)

Nuclear fuel and energy policy

International Nuclear Information System (INIS)

Ahmed, S.B.

1979-01-01

This book examines the uranium resource situation in relation to the future needs of the nuclear economy. Currently the United States is the world's leading producer and consumer of nuclear fuels. In the future US nuclear choices will be highly interdependent with the rest of the world as other countries begin to develop their own nuclear programs. Therefore the world's uranium resource availability has also been examined in relation to the expected growth in the world nuclear industry. Based on resource evaluation, the study develops an economic framework for analyzing and describing the behavior of the US uranium mining and milling industry. An econometric model designed to reflect the underlying structure of the physical processes of the uranium mining and milling industry has been developed. The purpose of this model is to forecast uranium prices and outputs for the period 1977 to 2000. Because uncertainty has sometimes surrounded the economic future of the uranium markets, the results of the econometric modeling should be interpreted with great care and restrictive assumptions. Another aspect of this study is to provide much needed information on the operations of government-owned enrichment plants and the practices used by the government in the determination of fuel enrichment costs. This study discusses possible future developments in enrichment supply and technologies and their implications for future enrichment costs. A review of the operations involving the uranium concentrate conversion to uranium hexafluoride and fuel fabrication is also provided. An economic analysis of these costs provides a comprehensive view of the front-end costs of the nuclear fuel cycle

The Nuclear Fuel Cycle Information System

International Nuclear Information System (INIS)

1987-02-01

The Nuclear Fuel Cycle Information System (NFCIS) is an international directory of civilian nuclear fuel cycle facilities. Its purpose is to identify existing and planned nuclear fuel cycle facilities throughout the world and to indicate their main parameters. It includes information on facilities for uranium ore processing, refining, conversion and enrichment, for fuel fabrication, away-from-reactor storage of spent fuel and reprocessing, and for the production of zirconium metal and Zircaloy tubing. NFCIS currently covers 271 facilities in 32 countries and includes 171 references

Nuclear fuels and development of nuclear fuel elements

International Nuclear Information System (INIS)

Sundaram, C.V.; Mannan, S.L.

1989-01-01

Safe, reliable and economic operation of nuclear fission reactors, the source of nuclear power at present, requires judicious choice, careful preparation and specialised fabrication procedures for fuels and fuel element structural materials. These aspects of nuclear fuels (uranium, plutonium and their oxides and carbides), fuel element technology and structural materials (aluminium, zircaloy, stainless steel etc.) are discussed with particular reference to research and power reactors in India, e.g. the DHRUVA research reactor at BARC, Trombay, the pressurised heavy water reactors (PHWR) at Rajasthan and Kalpakkam, and the Fast Breeder Test Reactor (FBTR) at Kalpakkam. Other reactors like the gas-cooled reactors operating in UK are also mentioned. Because of the limited uranium resources, India has opted for a three-stage nuclear power programme aimed at the ultimate utilization of her abundant thorium resources. The first phase consists of natural uranium dioxide-fuelled, heavy water-moderated and cooled PHWR. The second phase was initiated with the attainment of criticality in the FBTR at Kalpakkam. Fast Breeder Reactors (FBR) utilize the plutonium and uranium by-products of phase 1. Moreover, FBR can convert thorium into fissile 233 U. They produce more fuel than is consumed - hence, the name breeders. The fuel parameters of some of the operating or proposed fast reactors in the world are compared. FBTR is unique in the choice of mixed carbides of plutonium and uranium as fuel. Factors affecting the fuel element performance and life in various reactors e.g. hydriding of zircaloys, fuel pellet-cladding interaction etc. in PHWR and void swelling; irradiation creep and helium embrittlement of fuel element structural materials in FBR are discussed along with measures to overcome some of these problems. (author). 15 refs., 9 tabs., 23 figs

Price formation and market mechanisms in world nuclear fuel markets

International Nuclear Information System (INIS)

Neff, T.L.

1991-01-01

The structure of world markets for uranium, UF6 and enriched uranium product (EUP) have changed greatly since the 1970s. In the old model, firms specializing in mining, conversion, enrichment and fabrication played independent and sequential steps in the making of nuclear fuel. The great majority of users dealt directly with primary suppliers. Competition took place among suppliers at each stage of the fuel cycle and price formation occurred independently for each stage. Long-term contracts directly between primary supplier and end user dominated, whether for U3O8, conversion, enrichment or fabrication. The old model is effectively gone. uranium producers compete with traders, some of whom can offer a much larger menu of products and terms than primary suppliers. Where once there was a straight engineering-like sequence of processing from uranium to EUP for end use, today things are often reversed and far more complicated, with de-enrichment, de-conversion, loans, swaps, and other transactions. Those able to bring financial and entrepreneurial skills to bear on this complexity have an advantage. Long-term contracts between primary producers and end users no longer dominate new transactions, especially in the critical role of price formation - the process of determining or discovery of the market price. These changes have raised the question of whether participants in the nuclear fuel market need, or could benefit from, new institutional mechanisms, specifically some sort of formal exchange or commodity market

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2003-01-01

The Japan Atomic Industrial Forum (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2002 was made up on bases of answers on questionnaires from 65 electric power companies and other nuclear organizations in 28 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

Spent nuclear fuel storage - Basic concept

International Nuclear Information System (INIS)

Krempel, Ascanio; Santos, Cicero D. Pacifici dos; Sato, Heitor Hitoshi; Magalhaes, Leonardo de

2009-01-01

According to the procedures adopted in others countries in the world, the spent nuclear fuel elements burned to produce electrical energy in the Brazilian Nuclear Power Plant of Angra do Reis, Central Nuclear Almirante Alvaro Alberto - CNAAA will be stored for a long time. Such procedure will allow the next generation to decide how they will handle those materials. In the future, the reprocessing of the nuclear fuel assemblies could be a good solution in order to have additional energy resource and also to decrease the volume of discarded materials. This decision will be done in the future according to the new studies and investigations that are being studied around the world. The present proposal to handle the nuclear spent fuel is to storage it for a long period of time, under institutional control. Therefore, the aim of this paper is to introduce a proposal of a basic concept of spent fuel storage, which involves the construction of a new storage building at site, in order to increase the present storage capacity of spent fuel assemblies in CNAAA installation; the concept of the spent fuel transportation casks that will transfer the spent fuel assemblies from the power plants to the Spent Fuel Complementary Storage Building and later on from this building to the Long Term Intermediate Storage of Spent Fuel; the concept of the spent fuel canister and finally the basic concept of the spent fuel long term storage. (author)

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.

Building world-wide nuclear industry success stories - Safe management of nuclear waste and used nuclear fuel

International Nuclear Information System (INIS)

Saint-Pierre, S.

2005-01-01

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

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

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.

Spent nuclear fuel storage

International Nuclear Information System (INIS)

Romanato, Luiz Sergio

2005-01-01

When a country becomes self-sufficient in part of the nuclear cycle, as production of fuel that will be used in nuclear power plants for energy generation, it is necessary to pay attention for the best method of storing the spent fuel. Temporary storage of spent nuclear fuel is a necessary practice and is applied nowadays all over the world, so much in countries that have not been defined their plan for a definitive repository, as well for those that already put in practice such storage form. There are two main aspects that involve the spent fuels: one regarding the spent nuclear fuel storage intended to reprocessing and the other in which the spent fuel will be sent for final deposition when the definitive place is defined, correctly located, appropriately characterized as to several technical aspects, and licentiate. This last aspect can involve decades of studies because of the technical and normative definitions at a given country. In Brazil, the interest is linked with the storage of spent fuels that will not be reprocessed. This work analyses possible types of storage, the international panorama and a proposal for future construction of a spent nuclear fuel temporary storage place in the country. (author)

What's the rest of the world doing with its spent nuclear fuel?

Energy Technology Data Exchange (ETDEWEB)

Isaacs, T. [Stanford Univ. and Lawrence Livermore National Laboratory, Palo Alto, California (United States)], E-mail: Isaacs2@llnl.gov

2008-07-01

This paper discusses the storage of spent nuclear fuel by countries around the world. At the present time, all countries are storing it. A small number of countries are reprocessing it for recycling. Essentially all countries are preparing for eventual disposal of end waste form. There is much uncertainty and controversy over what should and will happen.

The prospects for the world nuclear energy market

International Nuclear Information System (INIS)

Anon.

1976-01-01

Over the last few years projections of nuclear power generating capacity growth for the next two decades have progressively decreased. Dwindling load growth, increasing load lead time, costs of delays and high cost inflation, industrial recession and fuel cycle delays are discussed as the main causes of the setback. The state of the fuel cycle business in the world market is examined and data are presented and discussed for predicted world supply and demand. Nuclear plans and fuel policies and requirements are then examined for individual countries. (U.K.)

Nuclear power plants in the world

International Nuclear Information System (INIS)

2008-01-01

The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2007/2008 was made up on bases of answers on questionnaires from electric power companies and other nuclear organizations around the world by JAIF. This report is comprised of 18 items, and contains generating capacity of the plants; effect of the Niigata-ken chuetsu-oki earthquake; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities, and so forth. (J.P.N.)

Nuclear Power Plants in the World

International Nuclear Information System (INIS)

2004-01-01

The Japan Atomic Industrial Forum, Inc. (JAIF) used every year to summarize a trend survey on the private nuclear power plants in the world in a shape of the 'Nuclear power plants in the world'. In this report, some data at the end of 2003 was made up on bases of answers on questionnaires from 81 electric power companies and other nuclear organizations in 33 countries and regions around the world by JAIF. This report is comprised of 19 items, and contains generating capacity of the plants; current status of Japan; trends of generating capacity of operating the plants, the plant orders and generating capacity of the plants; world nuclear capacity by reactor type; status of MOX use in the world; location of the plants; the plants in the world; directory of the plants; nuclear fuel cycle facilities; and so forth. (J.P.N.)

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.

On the nuclear fuel and fossil fuel reserves

International Nuclear Information System (INIS)

Fettweis, G.

1978-01-01

A short discussion of the nuclear fuel and fossil fuel reserves and the connected problem of prices evolution is presented. The need to regard fuel production under an economic aspect is emphasized. Data about known and assessed fuel reserves, world-wide and with special consideration of Austria, are reviewed. It is concluded that in view of the fuel reserves situation an energy policy which allows for a maximum of options seems adequate. (G.G.)

An introduction to the nuclear fuel cycle

International Nuclear Information System (INIS)

Leuze, R.E.

1986-01-01

This overview of the nuclear fuel cycle is divided into three parts. First, is a brief discussion of the basic principles of how nuclear reactors work;second, is a look at the major types of nuclear reactors being used and world-wide nuclear capacity;and third, is an overview of the nuclear fuel cycle and the present industrial capability in the US. 34 figs., 10 tabs

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.

Present supply and demand on the world uranium market and decision of the nuclear fuel cycle policy

International Nuclear Information System (INIS)

Zhang Luqing

1994-01-01

The present supply and demand relationship on the world uranium market due to the change of international situation in the last years is described and the falling price on the world uranium market is estimated. It is pointed out that the falling price would continue for a long time. Based on it the three different policy decisions on the back-end of nuclear fuel cycle are analysed

Trouble at the world's nuclear dustbin

International Nuclear Information System (INIS)

Adkins, J.

1984-01-01

Radioactive discharges from the Windscale nuclear fuel reprocessing plant in England's lake district temporarily closed 15 miles of shoreline and continues to raise safety questions in this recreational area. The plant receives high-level radioactive wastes and spent fuel from 36 power plants around the world for reprocessing. The site is also a storage point for 1550 tons of oxide waste waiting for additional reprocessing capacity. Pipelines carry 2.2 million gallons of low-level wastes into the Irish Sea each day. Five hundred pounds of weapons grade plutonium also entered the sea from a World War II munitions depot. Accidents have also contributed to the radioactive debris that has accumulated on sandy beaches. Pressure from Greenpeace and the Barrow Action Group helped to expedite an extensive cleanup program, but activity on the beaches is still highly restricted. British Nuclear Fuels remains undaunted by its negative public relations problems. 4 figures

The nuclear fuel cycle industry. World situation: the place of the French industry

International Nuclear Information System (INIS)

Sornein, J.

1978-01-01

The decision taken the day following the end of the second world war to create a French industry for the nuclear fuel cycle, the speed and dimension of its development from 1946 to 1966, the strengthening of its acquired knowledge during the following five years, lastly, the fact that, since 1972, it was able to make great strides, will have been in short the fruit of the remarkable continuity of an unfailing political will. Consequently it was possible beyond doubt, as soon as the ineluctable consequences of the oil crisis were evaluated, to give the French nuclear fuel cycle industry the new objectives which will succeed in granting it a foremost dimension on the international scale. In the three branches constituting the base of this industry (natural, enrichment, reprocessing), all these objectives will be reached by 1985. Their realization will permit our country to cover, in all security, not only its domestic needs but also to pursue a policy to sell materials and services for export at competitive prices [fr

Spent nuclear fuel management. Moving toward a century of spent fuel management: A view from the halfway mark

International Nuclear Information System (INIS)

Shephard, L.

2004-01-01

Full text: A half-century ago, President Eisenhower in his 1953 'Atoms for Peace' speech, offered nuclear technology to other nations as part of a broad nuclear arms control initiative. In the years that followed, the nuclear power generation capabilities of many nations has helped economic development and contributed to the prosperity of the modern world. The growth of nuclear power, while providing many benefits, has also contributed to an increasing global challenge over safe and secure spent fuel management. Over 40 countries have invested in nuclear energy, developing over 400 nuclear power reactors. Nuclear power supplies approximately 16% of the global electricity needs. With the finite resources and challenges of fossil fuels, nuclear power will undoubtedly become more prevalent in the future, both in the U.S. and abroad. We must address this inevitability with new paradigms for managing a global nuclear future. Over the past fifty years, the world has come to better understand the strong interplay between all elements of the nuclear fuel cycle, global economics, and global security. In the modern world, the nuclear fuel cycle can no longer be managed as a simple sequence of technological, economic and political challenges. Rather it must be seen, and managed, as a system of strongly interrelated challenges. Spent fuel management, as one element of the nuclear fuel system, cannot be relegated to the back-end of the fuel cycle as only a disposal or storage issue. There exists a wealth of success and experience with spent fuel management over the past fifty years. We must forge this experience with a global systems perspective, to reshape the governing of all aspects of the nuclear fuel cycle, including spent fuel management. This session will examine the collective experience of spent fuel management enterprises, seeking to shape the development of new management paradigms for the next fifty years. (author)

Proceedings of the 2006 International Meeting on LWR fuel performance 'Nuclear Fuel: Addressing the future' - TopFuel 2006 Transactions

International Nuclear Information System (INIS)

2006-01-01

From 22-26 October, 340 researchers, nuclear engineers and scientists from across Europe and beyond congregated in the ancient university city of Salamanca, Spain, to discuss the challenges facing the developers and manufacturers of new high-performance nuclear fuels-fuels that will help meet current and future energy demand and reduce man's over dependence upon CO 2 -emitting fossil fuels. TopFuel is an annual topical meeting organised by ENS, the American Nuclear Society and the Atomic Energy Society of Japan. This year it was co-sponsored by the IAEA, the OECD/NEA and the Spanish Nuclear Society (SNE). TopFuel's primary objective was to bring together leading specialists in the field from around the world to analyse advances in nuclear fuel management technology and to use the findings of the latest cutting-edge research to help manufacture the high performance nuclear fuels of today and tomorrow. The TopFuel 2006 agenda revolved around ten technical sessions dedicated to priority issues such as security of supply, new fuel and reactor core designs, fuel cycle strategies and spent fuel management. Among the many topics under discussion were new developments in fuel performance modelling, advanced fuel assembly design and the improved conditioning and processing of spent fuel. During the week, a poster exhibition also gave delegates the opportunity to display and discuss the results of their latest work and to network with fellow professionals. One important statement to emerge from TopFuel 2006 was that the world has enough reserves of uranium to support the large-scale and long-term production of nuclear energy. The OECD/NEA and the IAEA recently published a report entitled Uranium 2005: Resources, Production and Demand (the Red Book). The report, which makes a comprehensive assessment of uranium supplies and projected demand up until the year 2025, concludes by saying 'the uranium resource base is adequate to meet projected future requirements'. With the

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.)

Nuclear fuels

International Nuclear Information System (INIS)

Gangwani, Saloni; Chakrabortty, Sumita

2011-01-01

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

Fission products in the spent nuclear fuel from czech nuclear power plants

International Nuclear Information System (INIS)

Lelek, V.; Mikisek, M.; Marek, T.

1999-01-01

The nuclear power is expected to become a supply able to cover a significant part of the world energetic demand in future. But its big disadvantage, the risk of the spent nuclear fuel, has to be solved. The aim of this paper is to make simple estimates of the upper limits of amounts of the most dangerous spent fuel components and their compounds produced in Czech Republic until 2040. Our estimates are independent on particular type reactor (only on its power) and so they can be carried out for any nuclear fuel cycle. (Authors)

Nuclear energy and the developing world

International Nuclear Information System (INIS)

Mustafa, A.

1982-01-01

The importance of cooperation between the developed and developing countries with regard to nuclear power is discussed. Moves towards global interdependence were strengthened when OAPEC was set up with proposals for cooperation and depletion of world reserves of gas and oil will encourage this. Developing countries will increasingly look to nuclear power to meet their energy needs, particularly in the light of depleting oil and gas reserves, their increasing cost and the possible 'greenhouse effect' produced by fossil fuels. International cooperation concerning uranium reserves, reprocessing and technology transfer may need World Bank funding. (U.K.)

Nuclear Fuel Leasing, Recycling and proliferation: Modeling a Global View

International Nuclear Information System (INIS)

Crozat, M P; Choi, J; Reis, V H; Hill, R

2004-01-01

On February 11, 2004, U.S. President George W. Bush, in a speech to the National Defense University stated: ''The world must create a safe, orderly system to field civilian nuclear plants without adding to the danger of weapons proliferation. The world's leading nuclear exporters should ensure that states have reliable access at reasonable cost to fuel for civilian reactors, so long as those states renounce enrichment and reprocessing. Enrichment and reprocessing are not necessary for nations seeking to harness nuclear energy for peaceful purposes.'' This concept would require nations to choose one of two paths for civilian nuclear development: those that only have reactors and those that contain one or more elements of the nuclear fuel cycle, including recycling. ''Fuel cycle'' states would enrich uranium, manufacture and lease fuel to ''reactor'' states and receive the reactor states' spent fuel. All parties would accede to stringent security and safeguard standards, embedded within a newly invigorated international regime. Reactor states would be relieved of the financial, environmental (and political) burden of enriching and manufacturing fuel and dealing with spent fuel. Fuel cycle states would potentially earn money on leasing the fuel and perhaps on sales of reactors to the reactor states. Such a leasing concept is especially interesting in scenarios which envision growth in nuclear power, and an important consideration for such a nuclear growth regime is the role of recycling of civilian spent fuel. Recycling holds promise for improved management of spent fuel and efficient utilization of resources, but continues to raise the specter of a world with uncontrolled nuclear weapons proliferation. If done effectively, a fuel-leasing concept could help create a political and economic foundation for significant growth of clean, carbon-free nuclear power while providing a mechanism for significant international cooperation to reduce proliferation concern. This

The situation of the nuclear energy in the world

International Nuclear Information System (INIS)

Souza, Jair Albo Marques de

1996-12-01

This work presents an overview of the nuclear energy in the world. It approaches the following main topics: kinds of nuclear power plants; operation experience of the nuclear plants; environmental and social aspects of the nuclear energy; economic aspects of the nuclear energy; development of the reactors technology and supply of the nuclear fuel

Overview of the nuclear fuel cycle

International Nuclear Information System (INIS)

Leuze, R.E.

1982-01-01

The use of nuclear reactors to provide electrical energy has shown considerable growth since the first nuclear plant started commercial operation in the mid 1950s. Although the main purpose of this paper is to review the fuel cycle capabilities in the United States, the introduction is a brief review of the types of nuclear reactors in use and the world-wide nuclear capacity

Overview of the nuclear fuel cycle

International Nuclear Information System (INIS)

Leuze, R.E.

1981-01-01

The use of nuclear reactors to provide electrical energy has shown considerable growth since the first nuclear plant started commercial operation in the mid 1950s. Although the main purpose of this paper is to review the fuel cycle capabilities in the United States, the introduction is a brief review of the types of nuclear reactors in use and the world-wide nuclear capacity

Nuclear Fuel Cycle Objectives

International Nuclear Information System (INIS)

2013-01-01

One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world'. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property'. The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in member States, implementing organizations, academia and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The Nuclear Energy Basic Principles is the highest level publication in the IAEA Nuclear Energy Series, and describes the rationale and vision for the peaceful uses of nuclear energy. It presents eight Basic Principles on which nuclear energy systems should be based to fulfil nuclear energy's potential to help meet growing global energy needs. The Nuclear Energy Series Objectives are the second level publications. They describe what needs to be considered and the specific goals to be achieved at different stages of implementation, all of which are consistent with the Basic Principles

Nuclear fuel for VVER reactors. Actual state and trends

International Nuclear Information System (INIS)

Molchanov, V.

2011-01-01

The main tasks concerning development of FA design, development and modernization of structural materials, improvement of technology of structural materials manufacturing and FA fabrication and development of methods and codes are discussed in this paper. The main features and expected benefit of implementation of second generation and third generation fuel assembly for VVER-440 Nuclear Fuel are given. A brief review of VVER-440 and VVER-1000 Nuclear Fuel development before 1997 since 2010 is shown. A summary of VVER-440 and VVER-1000 Nuclear Fuel Today, including details about TVSA-PLUS, TVSA-ALFA, TVSA-12 and NPP-2006 Phase 2 tasks (2010-2012) is presented. In conclusion, as a result of large scope of R and D performed by leading enterprises of nuclear industry modern nuclear fuel for VVER reactors is developed, implemented and successfully operated. Fuel performance (burnup, lifetime, fuel cycles, operating reliability, etc.) meets the level of world's producers of nuclear fuel for commercial reactors

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

To support the evaluation of R and D needs and relevant technology requirements for future nuclear fuel cycles, the OECD/NEA WPFC Expert Group on Advanced Fuel Cycle Scenarios was created in 2010, replacing the WPFC Expert Group on Fuel Cycle Transition Scenario Studies (1) to assemble, organise and understand the scientific issues of advanced fuel cycles and (2) to provide a framework for assessing specific national needs related to the implementation of advanced fuel cycles. In this framework, a simulation of world transition scenarios towards possible future fuel cycles with fast reactors has been performed, using both a homogeneous and a heterogeneous approach involving different world regions. In fact, it has been found that a crucial feature of any world scenario study is to provide not only trends for an idealised 'homogeneous' description of the world, but also trends for different regions in the world, selected with simple criteria (mostly of geographical type), in order to apply different hypotheses to energy demand growth, different fuel cycle strategies and different reactor types implementation in the different regions. This approach was an attempt to avoid focusing on selected countries, in particular on those where no new spectacular energy demand growth is expected, but to provide trends and conclusions that account for the features of countries that will be major future players in the world's energy development. The heterogeneous approach considered a subdivision of the world in four main macro-regions (where countries have been grouped together according to their economic development dynamics). An original global electricity production envelope was used in simulations and a specific regional energy share was defined. In the regional approach two different fuel cycles were analysed: a once-through LWR cycle was used as the reference and a transition to fast reactor closed cycle to enable a better management of resources and minimisation of waste

International nuclear fuel cycle evaluation (INFCE)

International Nuclear Information System (INIS)

Schlupp, C.

1986-07-01

The study describes and analyzes the structures, the procedures and decision making processes of the International Nuclear Fuel Cycle Evaluation (INFCE). INFCE was agreed by the Organizing Conference to be a technical and analytical study and not a negotiation. The results were to be transmitted to governments for their consideration in developing their nuclear energy policies and in international discussions concerning nuclear energy cooperation and related controls and safeguards. Thus INFCE provided a unique example for decision making by consensus in the nuclear world. It was carried through under mutual respect for each country's choices and decisions, without jeopardizing their respective fuel cycle policies or international co-operation agreements and contracts for the peaceful use of nuclear energy, provided that agreed safeguards are applied. (orig.)

Nuclear energetics all over the world

International Nuclear Information System (INIS)

Wojcik, T.

2000-01-01

The actual state and tendencies of nuclear power further development for different world regions have been presented and discussed. The problem of safety of energetic nuclear reactors, radioactive waste management and related problems have been discussed in respect of regulations in different countries. The economical aspects of nuclear energetics in comparison with different fossil fuel power plants exploitation costs has been presented as well. The official state of international organizations (IAEA, WANO, HASA etc.) have been also shown in respect to subject presented

Review of world nuclear power programs

International Nuclear Information System (INIS)

Rippon, S.

1978-01-01

Political, economic and environmental decisions are still affecting the growth of nuclear power generation throughout the world, but there are signs that proven past performance and increasing prices of energy from conventional sources are becoming overriding factors. In the USA, some uncertainty has been created by the moratorium on reprocessing enacted by the 1978 Non-Proliferation Act. The uncertainty has spread to importers of nuclear fuel and technology, but there is increasing international acceptance of the International Nuclear Fuel Cycle Evaluation. Isotope separation capacity to be installed by the US government, by the joint European organization Urenco and by the French Eurodif should ease the supply of fuel. There is little progress on waste-management policy in the USA, but in Germany a company (DWK) has been formed and a site for a rocksalt repository has been designated at Gorleben. In the UK the Windscale inquiry has a positive significance for nuclear energy generally as well as for reprocessing. An inquiry in Sweden has also come to positive conclusions. The status of nuclear energy in these and a number of other countries is discussed in terms of political and national policies. (N.D.H.)

The current and perspective problems of nuclear power fuel supply

International Nuclear Information System (INIS)

Solonin, M.I.; Konovalov, I.I.

2003-01-01

Conception of fuel supply is comprised of supplying of natural uranium resources, nuclear fuel production including engineering stages of refining, enriching, production, use of secondary uranium and plutonium raw materials. The structure of nuclear fuel cycle is considered. Enterprises of the Russian nuclear fuel cycle, world recourses and fundamental producers of uranium are performed, demands in natural uranium of Russian and frontier NPP to 2010 are demonstrated. Dynamics of the development of separate methods - diffusion and centrifugal is presented as well as parameters of fuel supply at Russian and frontier NPP are compared [ru

Nuclear fuel cycle techniques

International Nuclear Information System (INIS)

Pecqueur, Michel; Taranger, Pierre

1975-01-01

The production of fuels for nuclear power plants involves five principal stages: prospecting of uranium deposits (on the ground, aerial, geochemical, geophysical, etc...); extraction and production of natural uranium from the deposits (U content of ores is not generally high and a chemical processing is necessary to obtain U concentrates); production of 235 U enriched uranium for plants utilizing this type of fuel (a description is given of the gaseous diffusion process widely used throughout the world and particularly in France); manufacture of suitable fuel elements for the different plants; reprocessing of spent fuels for the purpose of not only recovering the fissile materials but also disposing safely of the fission products and other wastes [fr

Nuclear fuel for light water reactors

International Nuclear Information System (INIS)

Etemad, A.

1976-01-01

The goal of the present speech is to point out some of the now-a-day existing problems related to the fuel cycle of light water reactors and to foresee their present and future solutions. Economical aspects of nuclear power generation have been considerably improving, partly through technological advancements and partly due to the enlargement of unit capacity. The fuel cycle, defined in the course of this talk, discusses the exploration, mining, ore concentration, purification, conversion, enrichment, manufacturing of fuel elements, their utilization in a reactor, their discharge and subsequent storage, reprocessing, and their re-use or disposal. Uranium market in the world and the general policy of several uranium owning countries are described. The western world requirement for uranium until the year 2000, uranium resources and the nuclear power programs in the United States, Australia, Canada, South Africa, France, India, Spain, and Argentina are discussed. The participation of Iran in a large uranium enrichment plant based on French diffusion technology is mentioned

Integration of the military and civilian nuclear fuel cycles in Russia

International Nuclear Information System (INIS)

Bukharin, O.

1994-01-01

This paper describes the close integration of the civil and military nuclear fuel cycles in Russia. Individual processing facilities, as well as the flow of nuclear material, are described as they existed in the 1980s and as they exist today. The end of the Cold War and the breakup of the Soviet Union weakened the ties between the two nuclear fuel cycles, but did not separate them. Separation of the military and civilian nuclear fuel cycles would facilitate Russia's integration into the world's nuclear fuel cycle and its participation in international non-proliferation regimes

Topfuel '95: Fuel for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1995-01-01

In early 1995, 425 nuclear power stations with an installed capacity of 360 263 MW were in operation in 30 countries of the world, and a total of 60 units with a capacity of 53 580 MWe were being cnstructed in 18 countries. The supply of nuclear fuels to these nuclear power stations was the central issue of the Topfuel '95 - Topical Meeting on Nuclear Fuel. More than 350 experts from 23 countries had been invited to Wuerzburg by the Kerntechnische Gesellschaft (KTG) and the European Nuclear Society (ENS). The conference was accompanied by an exhibition at which twelve inernational fuel cycle enterprises presented their products, processes, and problem solutions. The poster session in the hall of the Cogress Center Wuerzburg exhibited 42 contributions which are be discussed in the second part of the conference report. (orig./UA) [de

Siemens technology transfer and cooperation in the nuclear fuel area

International Nuclear Information System (INIS)

Holley, H.-P.; Fuchs, J. H.; Rothenbuecher, R. A.

1997-01-01

Siemens is a full-range supplier in the area of nuclear power generation with broad experience and activities in the field of nuclear fuel. Siemens has developed advanced fuel technology for all types fuel assemblies used throughout the world and has significant experience worldwide in technology transfer in the field of nuclear fuel. Technology transfer and cooperation has ranged between the provision of mechanical design advice for a specific fuel design and the erection of complete fabrication plants for commercial operation in 3 countries. In the following the wide range of Siemens' technology transfer activities for both fuel design and fuel fabrication technologies are shown

The roles of industry for internationalization of nuclear fuel cycle

International Nuclear Information System (INIS)

Choi, Jor-Shan; Oda, Takuji; Tanaka, Satoru; Kuno, Yusuke

2011-01-01

To meet increasing energy demand and counter climate change, nuclear energy is expected to expand during the next decades in both developed and developing countries. The Fukushima accident in Japan in March 2011 may dampen the expansion, but it would proceed and continue when the Fukushima lessons are learned. This expansion, most visibly in Asian would be accompanied with complex and intractable challenges to global stability and nuclear security, notably, on 'how to reduce security and proliferation concerns if nuclear power is introduce and when used fuel is generated in less stable regions of the world?' The answers to the question may lie in the possibility of multilateral control of nuclear materials and technologies in the nuclear fuel cycle, including the provision of a 'cradle-to-grave' fuel cycle service, presumably by the nuclear industries and their respective governments. This paper evaluates the importance of such industry-government cooperative initiative and explores into the roles which the nuclear industry should play to ensure that the world would not be 'creating proliferation when expanding the application of nuclear power to emerging nuclear countries'. (author)

The nuclear fuel cycle, an overview

International Nuclear Information System (INIS)

Ballery, J.L.; Cazalet, J.; Hagemann, R.

1995-01-01

Because uranium is widely distributed on the face of the Earth, nuclear energy has a very large potential as an energy source in view of future depletion of fossil fuel reserves. Also future energy requirements will be very sizeable as populations of developing countries are often growing and make the energy question one of the major challenges for the coming decades. Today, nuclear contributes some 340 GWe to the energy requirements of the world. Present and future nuclear programs require an adequate fuel cycle industry, from mining, refining, conversion, enrichment, fuel fabrication, fuel reprocessing and the storage of the resulting wastes. The commercial fuel cycle activities amount to an annual business in the 7-8 billions of US Dollars in the hands of a large number of industrial operators. This paper gives details about companies and countries involved in each step of the fuel cycle and about the national strategies and options chosen regarding the back end of the fuel cycle (waste storage and reprocessing). These options are illustrated by considering the policy adopted in three countries (France, United Kingdom, Japan) versed in reprocessing. (J.S.). 13 figs., 2 tabs

Nuclear fuel

International Nuclear Information System (INIS)

D Hondt, P.

1998-01-01

The research and development programme on nuclear fuel at the Belgian Nuclear Research Centre SCK/CEN is described. The objective of this programme is to enhance the quantitative prediction of the operational limits of nuclear fuel and to assess the behaviour of fuel under incidental and accidental conditions. Progress is described in different domains including the modelling of fission gas release in LWR fuel, thermal conductivity, basic physical phenomena, post-irradiation examination for fuel performance assessment, and conceptual studies of incidental and accidental fuel experiments

Nuclear fuel reprocessing in the UK

International Nuclear Information System (INIS)

Allardice, R.; Harris, D.; Mills, A.

1983-01-01

Nuclear fuel reprocessing has been carried out on an industrial scale in the United Kingdom since 1952. Two large reprocessing plants have been constructed and operated at Windscale, Cumbria and two smaller specialized plants have been constructed and operated at Dounreay, Northern Scotland. At the present time, the second of the two Windscale plants is operating, and Government permission has been given for a third reprocessing plant to be built on that site. At Dounreay, one of the plants is operating in its original form, whilst the second is now operating in a modified form, reprocessing fuel from the prototype fast reactor. This chapter describes the development of nuclear fuel reprocessing in the UK, commencing with the research carried out in Canada immediately after the Second World War. A general explanation of the techniques of nuclear fuel reprocessing and of the equipment used is given. This is followed by a detailed description of the plants and processes installed and operated in the UK

Nuclear fuel reprocessing in the UK

International Nuclear Information System (INIS)

Allardice, R.H.; Harris, D.W.; Mills, A.

1983-01-01

Nuclear fuel reprocessing has been carried out on an industrial scale in the United Kingdom since 1952. Two large reprocessing plants have been constructed and operated at Windscale, Cumbria and two smaller specialized plants have been constructed and operated at Dounreay, Northern Scotland. At the present time, the second of the two Windscale plants is operating, and Government permission has been given for a third reprocessing plant to be built on that site. At Dounreay, one of the plants is operating in its original form, whilst the second is now operating in a modified form, reprocessing fuel from the prototype fast reactor. This chapter describes the development of nuclear fuel reprocessing in the UK, commencing with the research carried out in Canada immediately after the Second World War. A general explanation of the techniques of nuclear fuel reprocessing and of the equipment used is given. This is followed by a detailed description of the plants and processes installed and operated in the UK. (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)

Spent nuclear fuel transport problems

International Nuclear Information System (INIS)

Kondrat'ev, A.N.; Kosarev, Yu.A.; Yulikov, E.I.

1977-01-01

The paper considers the problems of shipping spent fuel from nuclear power stations to reprocessing plants and also the principal ways of solving these problems with a view to achieving maximum economy and safety in transport. The increase in the number of nuclear power plants in the USSR will entail an intensification of spent-fuel shipments. Higher burnup and the need to reduce cooling time call for heavier and more complex shipping containers. The problem of shipping spent fuel should be tackled comprehensively, bearing in mind the requirements of safety and economy. One solution to these problems is to develop rational and cheap designs of such containers. In addition, the world-wide trend towards more thorough protection of the environment against pollution and of the health of the population requires the devotion of constant attention to improving the reliability and safety of shipments. The paper considers the prospects for nuclear power development in the USSR and in other member countries of the CMEA (1976-1980), the composition and design of some Soviet packaging assemblies, the appropriate cooling time for spent fuel from thermal reactor power stations, procedures for reducing fuel-shipping costs, some methodological problems of container calculation and design, and finally problems of testing and checking containers on test rigs. (author)

The nuclear fuel cycle light and shadow

International Nuclear Information System (INIS)

Giraud, A.

1977-01-01

The nuclear fuel cycle industry has a far reaching effect on future world energy developments. The growth in turnover of this industry follows a known patterm; by 1985 this turnover will have reached a figure of 2 billion dollars. Furthermore, the fuel cycle plays a determining role in ensuring the physical continuity of energy supplies for countries already engaged in the nuclear domain. Finally, the development of this industry is subject to economic and political constraints which imply the availability of raw materials, technological know-how, and production facilities. Various factors which could have an adverse influence on the cycle: technical, economic, or financial difficulties, environmental impact, nuclear safety, theft or diversion of nuclear materials, nuclear weapon, proliferation risks, are described, and the interaction between the development of the cycle, energy independance, and the fulfillment of nuclear energy programs is emphasized. It is concluded that the nuclear fuel cycle industry is confronted with difficulties due to its extremely rapid growth rate (doubling every 5 years); it is a long time since such a growth rate has been experienced by any heavy industry. The task which lays before us is difficult, but the fruit is worth the toil, as it is the fuel cycle which will govern the growth of the nuclear industry [fr

Current issues in the transport of radioactive waste and spent fuel: work by the World Nuclear Transport Institute

Energy Technology Data Exchange (ETDEWEB)

Neau, H-J.; Bonnardel-Azzarelli, B. [World Nuclear Transport Inst., London (United Kingdom)

2014-07-01

Various kinds of radioactive waste are generated from nuclear power and fuel cycle facilities. These materials have to be treated, stored and eventually sent to a repository site. Transport of wastes between these various stages is crucial for the sustainable utilization of nuclear energy. The IAEA Regulations for the Safe Transport of Radioactive Material (SSR-6) have, for many decades, provided a safe and efficient framework for radioactive materials transport and continue to do so. However, some shippers have experienced that in the transport of certain specific radioactive wastes, difficulties can be encountered. For example, some materials produced in the decommissioning of nuclear facilities are unique in terms of composition or size and can be difficult to characterize as surface contaminated objects (SCO) or homogeneous. One way WNTI (World Nuclear Transport Institute) helps develop transport methodologies is through the use of Industry Working Groups, bringing together WNTI members with common interests, issues and experiences. The Back-End Transport Industry Working Group focuses on the following issues currently. - Characterization of Waste: techniques and methods to classify wastes - Large Objects: slightly contaminated large objects (ex. spent steam generators) transport - Dual Use Casks: transportable storage casks for spent nuclear fuels, including the very long term storage of spent fuel - Fissile Exceptions: new fissile exceptions provisions of revised TS-R-1 (SSR-6) The paper gives a broad overview of current issues for the packaging and transport of radioactive wastes and the associated work of the WNTI. (author)

Multilateral controls of nuclear fuel-cycle in Asia

International Nuclear Information System (INIS)

Choi, Jor-Shan

2010-01-01

To meet increasing energy demand and climate change issues, nuclear energy is expected to expand during the next decades in both developed and developing countries. This expansion, most visibly in Asian countries would no doubt be accompanied with complex and intractable challenges to global peace and security, notably in the back-end of the nuclear fuel cycle. What to do with the growing stocks of spent fuel in existing nuclear programs? And how to reduce proliferation concerns when spent fuels are generated in less stable regions of the world? The answers to these questions may lie in the possibility of multilateral (or regional) control of nuclear materials and technologies in the back-end of nuclear fuel cycle. One of the areas of interest is technology, e.g., spent fuel treatment (reprocessing) for long term sustainability and environmental-friendly disposal of radioactive wastes, as an alternative to directly disposing spent fuel in geologic repository. The other is to seek for regional centers for centralized interim spent fuel storage which can eventually turn into disposal facilities. Such centers could help facilitate the possibilities of spent fuel take-back/take-away from countries located in less stable regions for fix-period storage. (author)

The situation of the nuclear energy in the world (Oct. 1991)

International Nuclear Information System (INIS)

1991-10-01

This work presents an overview of the nuclear energy in the world. It approaches the following main topics: kinds of nuclear power plants; operation experience of the nuclear plants; environmental and social aspects of the nuclear energy; economic aspects of the nuclear energy; development of the reactors technology and supply of the nuclear fuel

The situation of the nuclear energy in the world (Sep. 1992)

International Nuclear Information System (INIS)

Souza, Jair Albo Marques de

1992-09-01

This work presents an overview of the nuclear energy in the world. It approaches the following main topics: kinds of nuclear power plants; operation experience of the nuclear plants; environmental and social aspects of the nuclear energy; economic aspects of the nuclear energy; development of the reactors technology and supply of the nuclear fuel

Resources of nuclear fuels and materials

Energy Technology Data Exchange (ETDEWEB)

Kawamura, K [Tokyo Inst. of Tech. (Japan); Kamiyama, Teiji; Hayashi, S; Hida, Noboru; Okano, T

1974-11-01

In this explanatory article, data on the world resources of nuclear fuels and materials, their production, and the present state of utilization are presented by specialists in varied fields. Main materials taken up are uranium, thorium, beryllium, zirconium, niobium, rare earth elements, graphite, and materials for nuclear fusion (heavy hydrogen and tritium). World reserves and annual production of these materials listed in a number of tables are cited from statistics of the period 1970-1973 or given by estimation. These data may be used as valuable numerical data for various projects and problems of atomic power industries.

Paths to a nuclear world with reliable safeguards

International Nuclear Information System (INIS)

Zebroski, E.L.

1978-01-01

The effectiveness of safeguards in the nuclear industry in reducing proliferation is surveyed. Several basic topics relative to proliferation which are discussed are: (1) ''the recognition that 'proliferation' encompasses at least four different issues which may require distinct approaches and policies;'' (2) ''in the context of the regulatory process by which the perceived risks to society are managed;'' (3) ''in the context of the realistic options and objectives for an attainable world nuclear structure;'' and (4) ''in the perception of the public and of decision-makers of the attainable reduction in risks - and at what costs - and the recognition of the extent to which some costs have already been accrued.'' Options open to the world are: (1) a structured nuclear world, (2) an unstructured nuclear world, or (3) a benign energy world. Current US policy of denial of nuclear energy by indefinite delay is seen as indirectly pointing the US toward option 1 or 3, as the basic cause of American economic decline, and as a root cause of many international tensions resulting from the US decline. Certain alternate approaches to a breeder-type reactor program or to fuel reprocessing which should contribute to a more proliferation-resistant nuclear program are briefly discussed

Nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Nakano, H [Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)

1976-10-01

It is expected that nuclear power generation will reach 49 million kW in 1985 and 129 million kW in 1995, and the nuclear fuel having to be supplied and processed will increase in proportion to these values. The technical problems concerning nuclear fuel are presented on the basis of the balance between the benefit for human beings and the burden on the human beings. Recently, especially the downstream of nuclear fuel attracts public attention. Enriched uranium as the raw material for light water reactor fuel is almost monopolized by the U.S., and the technical information has not been published for fear of the diversion to nuclear weapons. In this paper, the present situations of uranium enrichment, fuel fabrication, transportation, reprocessing and waste disposal and the future problems are described according to the path of nuclear fuel cycle. The demand and supply of enriched uranium in Japan will be balanced up to about 1988, but afterwards, the supply must rely upon the early establishment of the domestic technology by centrifugal separation method. No problem remains in the fabrication of light water reactor fuel, but for the fabrication of mixed oxide fuel, the mechanization of the production facility and labor saving are necessary. The solution of the capital risk for the construction of the second reprocessing plant is the main problem. Japan must develop waste disposal techniques with all-out efforts.

The Nuclear Fuel Cycle

International Nuclear Information System (INIS)

2011-08-01

This brochure describes the nuclear fuel cycle, which is an industrial process involving various activities to produce electricity from uranium in nuclear power reactors. The cycle starts with the mining of uranium and ends with the disposal of nuclear waste. The raw material for today's nuclear fuel is uranium. It must be processed through a series of steps to produce an efficient fuel for generating electricity. Used fuel also needs to be taken care of for reuse and disposal. The nuclear fuel cycle includes the 'front end', i.e. preparation of the fuel, the 'service period' in which fuel is used during reactor operation to generate electricity, and the 'back end', i.e. the safe management of spent nuclear fuel including reprocessing and reuse and disposal. If spent fuel is not reprocessed, the fuel cycle is referred to as an 'open' or 'once-through' fuel cycle; if spent fuel is reprocessed, and partly reused, it is referred to as a 'closed' nuclear fuel cycle.

Supply assurance in the nuclear fuel cycle

International Nuclear Information System (INIS)

Neff, T.L.; Jacoby, H.D.

1979-01-01

Nuclear fuel assurance, in the face of world and political uncertainties, is interrelated with nuclear technology development plans and international safeguards considerations. This has led some countries to accelerate their commitments to nuclear commercialization faster than necessary and has made non-proliferation policies harder to enforce. Fuel assurance is described on a national basis in three time scales: short-term, or resilience to supply interruptions; mid-term, or contract conditions in which governments make commitments to purchase or deliver; and long-term, or resource adequacy. A review of former assurance problems and current trends in the enrichment and uranium markets indicates that supplier concentration is no longer the major problem so much as non-proliferation actions. The present state of unstable equilibrium is expected to move in the direction of less fuel-supply assurance for countries having a small market or not subscribing to non-proliferation criteria. The authors, while generally optimistic that the fuel-supply system will function, express concern that policies for fuel stockpiles and the condition of uranium markets need improvement. 21 references

Approaches for Securing the Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Kim, Jae San; Kim, Min Su; Jo, Seong Youn

2007-01-01

The greatest challenge to international nuclear nonproliferation regime is posed by nuclear energy's dual nature for both peaceful and military purposes. Uranium enrichment and spent nuclear fuel (SNF) reprocessing (sensitive nuclear technologies) are critical from the non-proliferation viewpoint because they may be used to produce weapons-grade nuclear materials. Therefore, since 1970s the world community started to develop further measures to curb the spread of sensitive nuclear technologies. The establishment of a Nuclear Suppliers Group (NSG) in 1975 was one such measure. The NSG united countries which voluntarily agreed to coordinate their legislation regarding export of nuclear materials, equipment and technologies to countries not possessing nuclear weapons. Alongside measures to limit the spread of sensitive nuclear technologies, multilateral approaches to the nuclear fuel cycle (NFC) started to be discussed. It's becoming increasingly important to link the objective need for an expanded use of nuclear energy with strengthening nuclear non-proliferation by preventing the spread of sensitive nuclear technologies and securing access for interested countries to NFC products and services

Nuclear fuels

International Nuclear Information System (INIS)

2008-01-01

The nuclear fuel is one of the key component of a nuclear reactor. Inside it, the fission reactions of heavy atoms, uranium and plutonium, take place. It is located in the core of the reactor, but also in the core of the whole nuclear system. Its design and properties influence the behaviour, the efficiency and the safety of the reactor. Even if it represents a weak share of the generated electricity cost, its proper use represents an important economic stake. Important improvements remain to be made to increase its residence time inside the reactor, to supply more energy, and to improve its robustness. Beyond the economical and safety considerations, strategical questions have to find an answer, like the use of plutonium, the management of resources and the management of nuclear wastes and real technological challenges have to be taken up. This monograph summarizes the existing knowledge about the nuclear fuel, its behaviour inside the reactor, its limits of use, and its R and D tracks. It illustrates also the researches in progress and presents some key results obtained recently. Content: 1 - Introduction; 2 - The fuel of water-cooled reactors: aspect, fabrication, behaviour of UO 2 and MOX fuels inside the reactor, behaviour in loss of tightness situation, microscopic morphology of fuel ceramics and evolution under irradiation - migration and localisation of fission products in UOX and MOX matrices, modeling of fuels behaviour - modeling of defects and fission products in the UO 2 ceramics by ab initio calculations, cladding and assembly materials, pellet-cladding interaction, advanced UO 2 and MOX ceramics, mechanical behaviour of the fuel assembly, fuel during a loss of coolant accident, fuel during a reactivity accident, fuel during a serious accident, fuel management inside reactor cores, fuel cycle materials balance, long-term behaviour of the spent fuel, fuel of boiling water reactors; 3 - the fuel of liquid metal fast reactors: fast neutrons radiation

Fuel and nuclear fuel cycle

International Nuclear Information System (INIS)

Prunier, C.

1998-01-01

The nuclear fuel is studied in detail, the best choice and why in relation with the type of reactor, the properties of the fuel cans, the choice of fuel materials. An important part is granted to the fuel assembly of PWR type reactor and the performances of nuclear fuels are tackled. The different subjects for research and development are discussed and this article ends with the particular situation of mixed oxide fuels ( materials, behavior, efficiency). (N.C.)

The World Nuclear University: Addressing global needs. London, 4 September 2003. Inauguration ceremony, World Nuclear University

International Nuclear Information System (INIS)

ElBaradei, M.

2003-01-01

For some time, there has been a growing awareness of the need for succession planning in the nuclear industry, to ensure that we cultivate a new generation of young people with the proper education and skills to replace the aging nuclear workforce as its members retire. Today's inauguration of the 'World Nuclear University' (WNU) is the most substantive action taken to date to address this need. This is a challenge, because the widespread perception clearly exists that nuclear energy is a dying field. The IAEA, with its constituency of 135 Member States, is hopeful that this will truly become a World Nuclear University. Almost 2 billion people, nearly one third of the population of the planet, remain without access to modern energy supplies - a shortfall that could be addressed, at least in part, by nuclear energy. But any major expansion in the future use of nuclear power will only be feasible if the nuclear industry is successful in developing innovative reactor and fuel cycle technology - as well as operational and regulatory approaches - that effectively address concerns related to cost competitiveness, safety and security, proliferation resistance and waste disposal. And global development needs go well beyond the electricity sector. The IAEA's recognition of these situations underlies our assistance to Member States, through which we try to address areas of high national priority wherever nuclear technology provides the best option for success. A significant part of that effort lies in the development of human capacity - through training and education in how to apply nuclear technology safely and effectively. 'Atoms for Peace' is a vision nearly five decades old, focused on using nuclear science for the advancement of humankind. It is my hope that this 'World Nuclear University' can be an effective instrument towards the achievement of that vision

Romanian nuclear fuel program

International Nuclear Information System (INIS)

Budan, O.

1999-01-01

The paper presents and comments the policy adopted in Romania for the production of CANDU-6 nuclear fuel before and after 1990. The CANDU-6 nuclear fuel manufacturing started in Romania in December 1983. Neither AECL nor any Canadian nuclear fuel manufacturer were involved in the Romanian industrial nuclear fuel production before 1990. After January 1990, the new created Romanian Electricity Authority (RENEL) assumed the responsibility for the Romanian Nuclear Power Program. It was RENEL's decision to stop, in June 1990, the nuclear fuel production at the Institute for Nuclear Power Reactors (IRNE) Pitesti. This decision was justified by the Canadian specialists team findings, revealed during a general, but well enough technically founded analysis performed at IRNE in the spring of 1990. All fuel manufactured before June 1990 was quarantined as it was considered of suspect quality. By that time more than 31,000 fuel bundles had already been manufactured. This fuel was stored for subsequent assessment. The paper explains the reasons which provoked this decision. The paper also presents the strategy adopted by RENEL after 1990 regarding the Romanian Nuclear Fuel Program. After a complex program done by Romanian and Canadian partners, in November 1994, AECL issued a temporary certification for the Romanian nuclear fuel plant. During the demonstration manufacturing run, as an essential milestone for the qualification of the Romanian fuel supplier for CANDU-6 reactors, 202 fuel bundles were produced. Of these fuel bundles, 66 were part of the Cernavoda NGS Unit 1 first fuel load (the balance was supplied by Zircatec Precision Industries Inc. ZPI). The industrial nuclear fuel fabrication re-started in Romania in January 1995 under AECL's periodical monitoring. In December 1995, AECL issued a permanent certificate, stating the Romanian nuclear fuel plant as a qualified and authorised CANDU-6 fuel supplier. The re-loading of the Cernavoda NGS Unit 1 started in the middle

Nuclear fuel cycle facilities in the world (excluding the centrally planned economies)

International Nuclear Information System (INIS)

1979-01-01

Information on the existing, under construction and planned fuel cycle facilities in the various countries is presented. Some thirty countries have activities related to different nuclear fuel cycle steps and the information covers the capacity, status, location, and the names of owners of the facilities

Nuclear fuel element

International Nuclear Information System (INIS)

1974-01-01

A nuclear fuel element for use in the core of a nuclear reactor is disclosed. A heat conducting fission product retaining metal liner of a refractory metal is incorporated in the fuel element between the cladding and the nuclear fuel to inhibit mechanical interaction between the nuclear fuel and the cladding, to isolate fission products and nuclear fuel impurities from contacting the cladding, and to improve the axial thermal peaking gradient along the length of the fuel rod. The metal liner can be in the form of a tube or hollow cylindrical column, a foil of single or multiple layers in the shape of a hollow cylindrical column, or a coating on the internal surface of the cladding. Preferred refractory metal materials are molybdenum, tungsten, rhenium, niobium and alloys of the foregoing metals

Nuclear fuel element

International Nuclear Information System (INIS)

Thompson, J.R.; Rowland, T.C.

1976-01-01

A nuclear fuel element for use in the core of a nuclear reactor is disclosed. A heat conducting, fission product retaining metal liner of a refractory metal is incorporated in the fuel element between the cladding and the nuclear fuel to inhibit mechanical interaction between the nuclear fuel and the cladding, to isolate fission products and nuclear fuel impurities from contacting the cladding and to improve the axial thermal peaking gradient along the length of the fuel rod. The metal liner can be in the form of a tube or hollow cylindrical column, a foil of single or multiple layers in the shape of a hollow cylindrical column, or a coating on the internal surface of the cladding. Preferred refractory metal materials are molybdenum, tungsten, rhenium, niobium and alloys of the foregoing metals

Operational Experience of Nuclear Fuel in Finnish Nuclear Power Plants (with Emphasis on WWER Fuel)

International Nuclear Information System (INIS)

Teraesvirta, R.

2009-01-01

The four operating nuclear reactors in Finland, Loviisa-1 and -2 and Olkiluoto-1 and -2 have now operated approximately 30 years. The overall operational experience has been excellent. Load factors of all units have been for years among the highest in the world. The development of the fuel designs during the years has enabled remarkable improvement in the fuel performance in terms of burnup. Average discharge burnup has increased more than 30 percent in all Finnish reactor units. A systematic inspection of spent fuel assemblies, and especially all failed fuel assemblies, is a good and useful practise employed in Finland. A possibility to inspect the fuel on site using a pool side inspection facility is a relatively economic way to find out root causes of fuel failures and thereby facilitate developing remedies to prevent similar failures in the future

Proliferation Resistant Nuclear Reactor Fuel

International Nuclear Information System (INIS)

Gray, L.W.; Moody, K.J.; Bradley, K.S.; Lorenzana, H.E.

2011-01-01

Global appetite for fission power is projected to grow dramatically this century, and for good reason. Despite considerable research to identify new sources of energy, fission remains the most plentiful and practical alternative to fossil fuels. The environmental challenges of fossil fuel have made the fission power option increasingly attractive, particularly as we are forced to rely on reserves in ecologically fragile or politically unstable corners of the globe. Caught between a globally eroding fossil fuel reserve as well as the uncertainty and considerable costs in the development of fusion power, most of the world will most likely come to rely on fission power for at least the remainder of the 21st century. Despite inevitable growth, fission power faces enduring challenges in sustainability and security. One of fission power's greatest hurdles to universal acceptance is the risk of potential misuse for nefarious purposes of fissionable byproducts in spent fuel, such as plutonium. With this issue in mind, we have discussed intrinsic concepts in this report that are motivated by the premise that the utility, desirability, and applicability of nuclear materials can be reduced. In a general sense, the intrinsic solutions aim to reduce or eliminate the quantity of existing weapons usable material; avoid production of new weapons-usable material through enrichment, breeding, extraction; or employ engineering solutions to make the fuel cycle less useful or more difficult for producing weapons-usable material. By their nature, these schemes require modifications to existing fuel cycles. As such, the concomitants of these modifications require engagement from the nuclear reactor and fuel-design community to fully assess their effects. Unfortunately, active pursuit of any scheme that could further complicate the spread of domestic nuclear power will probably be understandably unpopular. Nevertheless, the nonproliferation and counterterrorism issues are paramount, and

International co-operation in the supply of nuclear fuel and fuel cycle services

International Nuclear Information System (INIS)

Sievering, N.F. Jr.

1977-01-01

Recent changes in the United States' nuclear policy, in recognition of the increased proliferation risk, have raised questions of US intentions in international nuclear fuel and fuel-cycle service co-operation. This paper details those intentions in relation to the key elements of the new policy. In the past, the USA has been a world leader in peaceful nuclear co-operation with other nations and, mindful of the relationships between civilian nuclear technology and nuclear weapon proliferation, remains strongly committed to the Non-Proliferation Treaty, IAEA safeguards and other elements concerned with international nuclear affairs. Now, in implementing President Carter's nuclear initiatives, the USA will continue its leading role in nuclear fuel and fuel-cycle co-operation in two ways, (1) by increasing its enrichment capacity for providing international LWR fuel supplies and (2) by taking the lead in solving the problems of near and long-term spent fuel storage and disposal. Beyond these specific steps, the USA feels that the international community's past efforts in controlling the proliferation risks of nuclear power are necessary but inadequate for the future. Accordingly, the USA urges other similarly concerned nations to pause with present developments and to join in a programme of international co-operation and participation in a re-assessment of future plans which would include: (1) Mutual assessments of fuel cycles alternative to the current uranium/plutonium cycle for LWRs and breeders, seeking to lessen proliferation risks; (2) co-operative mechanisms for ensuring the ''front-end'' fuel supply including uranium resource exploration, adequate enrichment capacity, and institutional arrangements; (3) means of dealing with short-, medium- and long-term spent fuel storage needs by means of technical co-operation and assistance and possibly establishment of international storage or repository facilities; and (4) for reprocessing plants, and related fuel

The role of nuclear power in the world

International Nuclear Information System (INIS)

Goodman, E.I.

1977-01-01

The role of nuclear energy in the world is discussed from the near term and long term. For the period through the mid 1980s sufficient nuclear capacity is considered critical to forestall serious shortages of oil and possible high prices leading to economic stagnation. Over the next 30-35 years it is estimated that world nuclear power will reach a capacity of approx. 3 million megawatts electrical when world electrical capacity will be about 8 million megawatts. With this nuclear capacity and if a annual growth rate of 5% is achieved for coal, oil and gas would remain at their present rate of consumption and would be increasingly reserved for specialized uses where substitution is not feasible. Caution is stressed, however, especially in using long term forecasts except for overall guidance and even in short term projections frequent up-dating and revision is recommended. The factors which have inhibited nuclear power growth are discussed including: 1) rapidly rising capital costs and financing problems, 2) rising and uncertain fuel cycle costs, 3) uncertainties in licensing and public acceptance. Despite the foregoing, nuclear power still retains an economic edge over fossil-fired units in substantial portions of the world. Assuming satisfactory solution of its major problems it is estimated that about 27-40% of the electrical capacity of developing countries will be nuclear by the year 2000. This nuclear capacity will comprise approx. 20% of the world's total nuclear power capacity around the turn of the century. (orig.) [de

Commercial nuclear power: prospects for the United States and the world

International Nuclear Information System (INIS)

1986-01-01

This analysis report presents the current status and outlook for commercial nuclear power reactors for all countries in the world outside centrally planned economic areas (WOCA). Information regarding operable reactors in countries with centrally planned economies is presented in an appendix. The report provides documentation of the US nuclear capacity and generation projections through 1995. Projections for US nuclear capacity and generation through 2020 are presented for various nuclear power supply scenarios. These long-term projections are provided in support of the Department of Energy's activities pertaining to the Nuclear Waste Policy Act of 1982 and are used to produce the projections of fuel cycle requirements and spent fuel discharges

U.S. spent fuel transportation security in the post 9/11 world

International Nuclear Information System (INIS)

Anne, Catherine; Patterson, John; Williams, Blake

2002-01-01

On September 11, 2002 the terrible tragedies in New York, Pennsylvania and Washington, DC changed the world forever. Security issues not only impact our daily lives, but are also in a state flux concerning the shipment of spent nuclear fuel in the United States. The formation of the Homeland Security Advisory System and Interim Compensatory Measures from the NRC, along with other security measures, have affected the way we transport spent nuclear fuel. This paper describes the challenging and demanding way that security is planned, implemented and maintained in support of spent fuel shipments in the United States. (author)

Nuclear fuel element

International Nuclear Information System (INIS)

Yamamoto, Seigoro.

1994-01-01

Ultrafine particles of a thermal neutron absorber showing ultraplasticity is dispersed in oxide ceramic fuels by more than 1% to 10% or lower. The ultrafine particles of the thermal neutron absorber showing ultrafine plasticity is selected from any one of ZrGd, HfEu, HfY, HfGd, ZrEu, and ZrY. The thermal neutron absorber is converted into ultrafine particles and solid-solubilized in a nuclear fuel pellet, so that the dispersion thereof into nuclear fuels is made uniform and an absorbing performance of the thermal neutrons is also made uniform. Moreover, the characteristics thereof, for example, physical properties such as expansion coefficient and thermal conductivity of the nuclear fuels are also improved. The neutron absorber, such as ZrGd or the like, can provide plasticity of nuclear fuels, if it is mixed into the nuclear fuels for showing the plasticity. The nuclear fuel pellets are deformed like an hour glass as burning, but, since the end portion thereof is deformed plastically within a range of a repulsive force of the cladding tube, there is no worry of damaging a portion of the cladding tube. (N.H.)

Nuclear fuel supplies

International Nuclear Information System (INIS)

1960-01-01

When the International Atomic Energy Agency was set up nearly three years ago, it was widely believed that it would soon become a world bank or broker for the supply of nuclear fuel. Some observers now seem to feel that this promise has been rather slow to come to fruition. A little closer analysis would, however, show that the promise can be fulfilled only in a certain objective context, and to the extent that this context exists, the development of the Agency's role has been commensurate with the actual needs of the situation

Nuclear Fuel Reprocessing

International Nuclear Information System (INIS)

Simpson, Michael F.; Law, Jack D.

2010-01-01

This is a submission for the Encyclopedia of Sustainable Technology on the subject of Reprocessing Spent Nuclear Fuel. Nuclear reprocessing is the chemical treatment of spent fuel involving separation of its various constituents. Principally, it is used to recover useful actinides from the spent fuel. Radioactive waste that cannot be re-used is separated into streams for consolidation into waste forms. The first known application of nuclear reprocessing was within the Manhattan Project to recover material for nuclear weapons. Currently, reprocessing has a peaceful application in the nuclear fuel cycle. A variety of chemical methods have been proposed and demonstrated for reprocessing of nuclear fuel. The two most widely investigated and implemented methods are generally referred to as aqueous reprocessing and pyroprocessing. Each of these technologies is described in detail in Section 3 with numerous references to published articles. Reprocessing of nuclear fuel as part of a fuel cycle can be used both to recover fissionable actinides and to stabilize radioactive fission products into durable waste forms. It can also be used as part of a breeder reactor fuel cycle that could result in a 14-fold or higher increase in energy utilization per unit of natural uranium. Reprocessing can also impact the need for geologic repositories for spent fuel. The volume of waste that needs to be sent to such a repository can be reduced by first subjecting the spent fuel to reprocessing. The extent to which volume reduction can occur is currently under study by the United States Department of Energy via research at various national laboratories and universities. Reprocessing can also separate fissile and non-fissile radioactive elements for transmutation.

Nuclear fuel elements

International Nuclear Information System (INIS)

Nakai, Keiichi

1983-01-01

Purpose: To decrease the tensile stresses resulted in a fuel can as well as prevent decladding of fuel pellets into the bore holes by decreasing the inner pressure within the nuclear fuel element. Constitution: A fuel can is filled with hollow fuel pellets, inserted with a spring for retaining the hollow fuel pellets with an appropriate force and, thereafter, closely sealed at the both ends with end plugs. A cylindrical body is disposed into the bore holes of the hollow fuel pellets. Since initial sealing gases and/or gaseous nuclear fission products can thus be excluded from the bore holes where the temperature is at the highest level, the inner pressure of the nuclear fuel element can be reduced to decrease the tensile strength resulted to the fuel can. Furthermore, decladding of fuel pellets into the bore holes can be prevented. (Moriyama, K.)

Nuclear fuel assembly

International Nuclear Information System (INIS)

Anthony, A.J.

1980-01-01

A bimetallic spacer means is cooperatively associated with a nuclear fuel assembly and operative to resist the occurrence of in-reactor bowing of the nuclear fuel assembly. The bimetallic spacer means in one embodiment of the invention includes a space grid formed, at least principally, of zircaloy to the external surface of which are attached a plurality of stainless steel strips. In another embodiment the strips are attached to fuel pins. In each of the embodiments, the stainless steel strips during power production expand outwardly to a greater extent than do the members to which the stainless steel strips are attached, thereby forming stiff springs which abut against like bimetallic spacer means with which the other nuclear fuel assemblies are provided in a given nuclear reactor core to thus prevent the occurrence of in-reactor bowing of the nuclear fuel assemblies. (author)

Factors which could limit the nuclear fuel cycle development

International Nuclear Information System (INIS)

Pecqueur, M.; Barre, B.

1977-01-01

The nuclear fuel cycle is a most important industry for the energy future of the world. It has also a leading part as regards the physical continuity of energy supply of the countries engaged in the nuclear field. The development of this industry is subject to the economic or political constraints involved by the availability of raw materials, technologies or production means. The various limiting factors which could affect the different stages of the fuel cycle are linked with the technical, economic and financial aspects, with the impact on the environment, nuclear safety, risks of non-pacific uses and proliferation of arms. Interesting to note is also the correlation between the fuel cycle development and the problems of energy independence and security of nuclear programs. As a conclusion, the nuclear fuel cycle industry is confronted to difficulties due to its extremely rapid growth (doubling time 5 years) which only few heavy industries have encountered for long periods. It is more over submitted to the political and safety constraints always linked with nuclear matters. The task is therefore a difficult one. But the objective is worth-while since it is a condition to the development of nuclear industry [fr

Say no to fossil fuels and yes to nuclear energy

International Nuclear Information System (INIS)

Raghava Chari, S.

2011-01-01

Mistaken notion and wrongful fear of nuclear energy based on the horrors of the second world war bombing of Nagasaki and Hiroshima and accidents at Chernobyl and Three mile island and lately the Fukushima nuclear plant meltdown to earthquake and and tsunami have developed antagonism to nuclear energy (NE) and clouded its usefulness as a practical, clean, environment friendly and affordable alternate source of energy. Such antagonism has slowed down research on NE and its adoption on a much wider scale, the crying need of the day. There is a motivated disinformation campaign against nuclear energy in India as witnessed from the ongoing agitation at Kudankulam in Tamil Nadu and Jaitapur in Maharashtra. In fact nuclear energy is the only practical alternative energy source to meet the ever increasing energy needs of the world particularly the developing nations, and to save the world from the greenhouse ill effects of massive carbon dioxide and other emissions from burning fossil fuels like coal, oil and natural gas. Emissions from fossil fuel burning including radioactive emissions are hundreds of times more in weight and volume and far more hazardous than from an equal capacity nuclear plant. In fact there are no greenhouse gases (CO 2 ), acid rain gases (SO 2 ) or carcinogen emissions (NO x ) from nuclear plants. The accident rates and severity of accidents owing to nuclear plants is much lower as compared to fossil fuel power generation. Last but not the least NE offers economic freedom from the clutches of the few monopolistic oil producing countries, which charge exorbitant oil prices and cripple the finances of developing nations. (author)

Development for analysis system of rods enrichment of nuclear fuels

International Nuclear Information System (INIS)

Rojas C, E.L.

1998-01-01

Nuclear industry is strongly regulated all over the world and quality assurance is important in every nuclear installation or process related with it. Nuclear fuel manufacture is not the exception. ININ was committed to manufacture four nuclear fuel bundles for the CFE nucleo electric station at Laguna Verde, Veracruz, under General Electric specifications and fulfilling all the requirements of this industry. One of the quality control requisites in nuclear fuel manufacture deals with the enrichment of the pellets inside the fuel bundle rods. To achieve the quality demanded in this aspect, the system described in this work was developed. With this system, developed at ININ it is possible to detect enrichment spikes since 0.4 % in a column of pellets with a 95 % confidence interval and to identify enrichment differences greater than 0.2 % e between homogeneous segments, also with a 95 % confidence interval. ININ delivered the four nuclear fuel bundles to CFE and these were introduced in the core of the nuclear reactor of Unit 1 in the fifth cycle. Nowadays they are producing energy and have shown a correct mechanical performance and neutronic behavior. (Author)

International Nuclear Fuel Cycle Evaluation

International Nuclear Information System (INIS)

Carnesale, A.

1980-01-01

As nuclear power expands globally, so too expands the capability for producing nuclear weapons. The International Nuclear Fuel Cycle Evaluation (INFCE) was organized in 1977 for the purpose of exploring two areas: (1) ways in which nuclear energy can be made available to help meet world energy needs, and (2) means by which the attendant risk of weapons proliferation can be held to a minimum. INFCE is designed for technical and analytical study rather than negotiation. Its organizational structure and issues under consideration are discussed. Some even broader issues that emerge from consideration of the relationships between the peaceful and military use of nuclear energy are also discussed. These are different notions of the meaning of nuclear proliferation, nuclear export policy, the need of a nuclear policy to be both a domestic as well as a foreign one, and political-military measures that can help reduce incentives of countries to acquire nuclear weapons of their own

Role of Halden Reactor Project for world-wide nuclear energy development

Energy Technology Data Exchange (ETDEWEB)

McGrath, M.A.; Volkov, B.

2011-07-01

The great interest for utilization of nuclear materials to produce energy in the middle of last century needed special investigations using first class research facilities. Common problems in the area of nuclear fuel development motivated the establishment of joint research efforts. The OECD Halden Reactor Project (HRP) is a good example of such a cooperative research effort, which has been performing for more than 50 years. During that time, the Halden Reactor evolved from a prototype heavy water reactor envisaged as a power source for different applications to a research reactor that is able to simulate in-core conditions of modern commercial power reactors. The adaptability of the Halden Reactor enables the HRP to be an important international test facility for nuclear fuels and materials development. The long-term international cooperation is based on the flexible HRP organizational structure which also provides the continued success. [1,2] This paper gives a brief history of the Halden Reactor Project and its contribution to world-wide nuclear energy development. Recent expansion of the Project to the East and Asian countries may also assist and stimulate the development of a nuclear industry within these countries. The achievements of the HRP rely on the versatility of the research carried out in the reactor with reliable testing techniques and in-pile instrumentation. Diversification of scientific activity in the areas of development of alternative energy resources and man-machine technology also provide the HRP with a stable position as one of the leaders in the world scientific community. All of these aspects are described in this paper together with current experimental works, including the investigation of ULBA (Kazakhstan) production fuel in comparison with other world fuel suppliers, as well as other future and prospective plans of the Project.(Author)

Role of Halden Reactor Project for world-wide nuclear energy development

International Nuclear Information System (INIS)

McGrath, M.A.; Volkov, B.

2011-01-01

The great interest for utilization of nuclear materials to produce energy in the middle of last century needed special investigations using first class research facilities. Common problems in the area of nuclear fuel development motivated the establishment of joint research efforts. The OECD Halden Reactor Project (HRP) is a good example of such a cooperative research effort, which has been performing for more than 50 years. During that time, the Halden Reactor evolved from a prototype heavy water reactor envisaged as a power source for different applications to a research reactor that is able to simulate in-core conditions of modern commercial power reactors. The adaptability of the Halden Reactor enables the HRP to be an important international test facility for nuclear fuels and materials development. The long-term international cooperation is based on the flexible HRP organizational structure which also provides the continued success. [1,2] This paper gives a brief history of the Halden Reactor Project and its contribution to world-wide nuclear energy development. Recent expansion of the Project to the East and Asian countries may also assist and stimulate the development of a nuclear industry within these countries. The achievements of the HRP rely on the versatility of the research carried out in the reactor with reliable testing techniques and in-pile instrumentation. Diversification of scientific activity in the areas of development of alternative energy resources and man-machine technology also provide the HRP with a stable position as one of the leaders in the world scientific community. All of these aspects are described in this paper together with current experimental works, including the investigation of ULBA (Kazakhstan) production fuel in comparison with other world fuel suppliers, as well as other future and prospective plans of the Project.(Author)

Final disposal of spent fuels and high activity waste: status and trends in the world. Part 2

International Nuclear Information System (INIS)

Herscovich de Pahissa, Marta

2008-01-01

The proper management of spent fuel arising from nuclear power production is a key issue for the sustainable development of nuclear energy. Some countries have adopted reprocessing of spent fuel and part of them has continued to develop and improve closed fuel cycle technologies; some other countries have adopted a direct final disposal. The objective in this article is to provide an update on the latest development in the world related with the geological disposal of spent nuclear fuel and high level wastes. (author) [es

Nuclear energy and the fossil fuels

Energy Technology Data Exchange (ETDEWEB)

Folinsbee, R E

1970-01-01

The energy phenomenon of the first half of this century has been the increase in the use of petroleum and natural gas as fuels. World demand for petroleum energy has been increasing at the rate of 11% per yr. This demand is unsustainable, for the supply, as with any exhaustible resource, is limited. The continental energy policy is essentially one of integrating the North American supply and demand picture for the fossil fuels, using oil and gas from the interior of the continent to supply demand from the interior and using overseas supplies, up the limit of national security, for energy users farthest removed from these sources. The economics of expensive pipeline transportation as against cheap supertankers dictates this policy. Beyond any shadow of a doubt, the fuel of the future will be nuclear, and for this century almost entirely the energy of fission rather than of fusion. Recent estimates suggest that as much as 50% of the energy for the U.S. will be nuclear by the year 2,000, and for Canada the more modest National Energy Board estimate holds that in 1990, 35% of Canadian electric generation will be by nuclear power reactors concentrated in the fuel-starved province of Ontario. (17 refs.)

Highlights of the IAEA scientific forum: Nuclear science: Physics helping the world

International Nuclear Information System (INIS)

Richter, B.

2005-01-01

The conclusions drawn at the Scientific Forum during the 49th regular Session of the IAEA General Conference entitled 'Nuclear Physics: Helping the World' are as follows. Physics is indeed helping the world and the IAEA, applications of nuclear are continuing to grow, nuclear power is likely to increase dramatically, work on 'Beyond Kyoto' should begin and nuclear should be part of any 'Clean Development Mechanism'. IAEA should look again at the role of R and D in safeguards, IAEA should look at safety issues in newly nuclear countries, internationalizing the fuel cycle is right IF one can do it

The nuclear fuel cycle, From the uranium mine to waste disposal

International Nuclear Information System (INIS)

2002-09-01

Fuel is a material that can be burnt to provide heat. The most familiar fuels are wood, coal, natural gas and oil. By analogy, the uranium used in nuclear power plants is called 'nuclear fuel', because it gives off heat too, although, in this case, the heat is obtained through fission and not combustion. After being used in the reactor, spent nuclear fuel can be reprocessed to extract recyclable energy material, which is why we speak of the nuclear fuel cycle. This cycle includes all the following industrial operations: - uranium mining, - fuel fabrication, - use in the reactor, - reprocessing the fuel unloaded from the reactor, - waste treatment and disposal. 'The nuclear fuel cycle includes an array of industrial operations, from uranium mining to the disposal of radioactive waste'. Per unit or mass (e.g. per kilo), nuclear fuel supplies far more energy than a fossil fuel (coal or oil). When used in a pressurised water reactor, a kilo of uranium generates 10,000 times more energy than a kilo of coal or oil in a conventional power station. Also, the fuel will remain in the reactor for a long time (several years), unlike conventional fuels, which are burnt up quickly. Nuclear fuel also differs from others in that uranium has to undergo many processes between the time it is mined and the time it goes into the reactor. For the sake of simplicity, the following pages will only look at nuclear fuel used in pressurised water reactors (or PWRs), because nuclear power plants consisting of one or more PWRs are the most widely used around the world. (authors)

Possible development of the world-wide improvement of nuclear energy considering economical, social and political aspects

International Nuclear Information System (INIS)

Jaek, W.

1981-01-01

Accepting the fact that the growing world energy demand cannot be met in the long term without an increasing use of nuclear energy one has to pay more attention to its possible expansion and consequently also to the geographical distribution of nuclear plants in the world. Due to future large scale deployment problems may arise in the areas of uranium supply, waste disposal, nonprofileration, safeguards, acceptability, and nuclear transfer. Based on the World Energy Conference (1977) global energy scenario a country-by-country analysis has been made to evaluate the possible contribution of nuclear energy in each country within the next 40 years. Against this background the problems of the head- and tail-end of the nuclear fuel cycle are discussed in detail and compared with the international trade of nonnuclear fuels. (orig.) [de

Sufficiency of the Nuclear Fuel

International Nuclear Information System (INIS)

Pevec, D.; Knapp, V.; Matijevic, M.

2008-01-01

Estimation of the nuclear fuel sufficiency is required for rational decision making on long-term energy strategy. In the past an argument often invoked against nuclear energy was that uranium resources are inadequate. At present, when climate change associated with CO 2 emission is a major concern, one novel strong argument for nuclear energy is that it can produce large amounts of energy without the CO 2 emission. Increased interest in nuclear energy is evident, and a new look into uranium resources is relevant. We examined three different scenarios of nuclear capacity growth. The low growth of 0.4 percent per year in nuclear capacity is assumed for the first scenario. The moderate growth of 1.5 percent per year in nuclear capacity preserving the present share in total energy production is assumed for the second scenario. We estimated draining out time periods for conventional resources of uranium using once through fuel cycle for the both scenarios. For the first and the second scenario we obtained the draining out time periods for conventional uranium resources of 154 years and 96 years, respectively. These results are, as expected, in agreement with usual evaluations. However, if nuclear energy is to make a major impact on CO 2 emission it should contribute much more in the total energy production than at present level of 6 percent. We therefore defined the third scenario which would increase nuclear share in the total energy production from 6 percent in year 2020 to 30 percent by year 2060 while the total world energy production would grow by 1.5 percent per year. We also looked into the uranium requirement for this scenario, determining the time window for introduction of uranium or thorium reprocessing and for better use of uranium than what is the case in the once through fuel cycle. The once through cycle would be in this scenario sustainable up to about year 2060 providing most of the expected but undiscovered conventional uranium resources were turned

Role of ion chromatograph in nuclear fuel fabrication process at Nuclear Fuel Complex

International Nuclear Information System (INIS)

Balaji Rao, Y.; Prasada Rao, G.; Prahlad, B.; Saibaba, N.

2012-01-01

The present paper discusses the different applications of ion chromatography followed in nuclear fuel fabrication process at Nuclear Fuel Complex. Some more applications of IC for characterization of nuclear materials and which are at different stages of method development at Control Laboratory, Nuclear Fuel Complex are also highlighted

Regeneration and localization of radioactive waste in the nuclear fuel cycle

International Nuclear Information System (INIS)

Egorov, N.N.; Kudryavtsev, E.G.; Nikipelov, B.V.; Polyakov, A.S.; Zakharkin, B.S.; Mamaev, L.A.

1993-01-01

Normal functioning of the nuclear-power industry is only possible with a closed fuel cycle, including regeneration of the spent fuel from atomic power plants, the production and recycling of the secondary fuel, and localization of the radioactive waste. Despite the diversity of contemporary attitudes toward the structure of the nuclear fuel cycle around the world, the closure of the fuel cycle has been fundamental to the atomic-power industry in the USSR since the very beginning, and has taken on even greater significance in Russia today. From the beginning, the idea of a closed fuel cycle has been based essentially on one fundamental criterion: the concept of expanded productivity on the basis of fuel regeneration, i.e., the economic factor. Important as economic factors are, safety issues have taken on great significance in recent years: not only power-station reactors but all the ancillary stages of the fuel cycle must meet fundamentally new reliability, safety, and environmental hazards. The RT-1 plant is a versatile operation, regenerating spent fuel from VVER-440, BN-350, and BN-600 reactors, nuclear icebreakers and submarines, research reactors, and other power units. The plant can reprocess 400 ton/year of basic VVER-440 fuel. World-class modern processes have been introduced at the plant, meeting the necessary quality standards: zonal planning, remote operation to eliminate direct contact of the staff with radioactive material, extensive monitoring and control systems, multistage gas-purification systems, and new waste-treatment methods

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

Nuclear fuel lease accounting

International Nuclear Information System (INIS)

Danielson, A.H.

1986-01-01

The subject of nuclear fuel lease accounting is a controversial one that has received much attention over the years. This has occurred during a period when increasing numbers of utilities, seeking alternatives to traditional financing methods, have turned to leasing their nuclear fuel inventories. The purpose of this paper is to examine the current accounting treatment of nuclear fuel leases as prescribed by the Financial Accounting Standards Board (FASB) and the Federal Energy Regulatory Commission's (FERC's) Uniform System of Accounts. Cost accounting for leased nuclear fuel during the fuel cycle is also discussed

Introduction of Thorium in the Nuclear Fuel Cycle. Short- to long-term considerations

International Nuclear Information System (INIS)

Allibert, M.; Merle-Lucotte, E.; Ghetta, V.; Ault, T.; Krahn, S.; Wymer, R.; Croff, A.; Baron, P.; Chauvin, N.; Eschbach, R.; Rimpault, G.; Serp, J.; Bergeron, A.; Bromley, B.; Floyd, M.; Hamilton, H.; Hyland, B.; Wojtaszek, D.; McDonald, M.; Collins, E.; Cornet, S.; Michel-Sendis, F.; ); Feinberg, O.; Ignatiev, V.; Hesketh, K.; Kelly, J.F.; Porsch, D.; Vidal, J.; Taiwo, T.; Uhlir, J.; Van Den Durpel, L.; Van Den Eynde, G.; Vitanza, C.; Butler, Gregg; Cornet, Stephanie; Dujardin, Thierry; Greneche, Dominique; Nordborg, Claes; Rimpault, Gerald; Van Den Durpel, Luc; Michel-Sendis, Franco

2015-01-01

Since the beginning of the nuclear era, significant scientific attention has been given to thorium's potential as a nuclear fuel. Although the thorium fuel cycle has never been fully developed, the opportunities and challenges that might arise from the use of thorium in the nuclear fuel cycle are still being studied in many countries and in the context of diverse international programmes around the world. This report provides a scientific assessment of thorium's potential role in nuclear energy both in the short to longer term, addressing diverse options, potential drivers and current impediments to be considered if thorium fuel cycles are to be pursued. (authors)

Boosting nuclear fuels

International Nuclear Information System (INIS)

Demarthon, F.; Donnars, O.; Dupuy-Maury, F.

2002-01-01

This dossier gives a broad overview of the present day status of the nuclear fuel cycle in France: 1 - the revival of nuclear power as a solution to the global warming and to the increase of worldwide energy needs; 2 - the security of uranium supplies thanks to the reuse of weapon grade highly enriched uranium; 3 - the fabrication of nuclear fuels from the mining extraction to the enrichment processes, the fabrication of fuel pellets and the assembly of fuel rods; 4 - the new composition of present day fuels (UO x and chromium-doped pellets); 5 - the consumption of plutonium stocks and the Corail and Apa fuel assemblies for the reduction of plutonium stocks and the preservation of uranium resources. (J.S.)

Nuclear fuel pellet loading apparatus

International Nuclear Information System (INIS)

Gerkey, K.S.

1979-01-01

An automatic apparatus for loading a predetermined amount of nuclear fuel pellets into a nuclear fuel element to be used in a nuclear reactor is described. The apparatus consists of a vibratory bed capable of supporting corrugated trays containing rows of nuclear fuel pellets and arranged in alignment with the open ends of several nuclear fuel elements. A sweep mechanism is arranged above the trays and serves to sweep the rows of fuel pellets onto the vibratory bed and into the fuel element. A length detecting system, in conjunction with a pellet stopping mechanism, is also provided to assure that a predetermined amount of nuclear fuel pellets are loaded into each fuel element

Fast Neutron Emission Tomography of Used Nuclear Fuel Assemblies

Science.gov (United States)

Hausladen, Paul; Iyengar, Anagha; Fabris, Lorenzo; Yang, Jinan; Hu, Jianwei; Blackston, Matthew

2017-09-01

Oak Ridge National Laboratory is developing a new capability to perform passive fast neutron emission tomography of spent nuclear fuel assemblies for the purpose of verifying their integrity for international safeguards applications. Most of the world's plutonium is contained in spent nuclear fuel, so it is desirable to detect the diversion of irradiated fuel rods from an assembly prior to its transfer to ``difficult to access'' storage, such as a dry cask or permanent repository, where re-verification is practically impossible. Nuclear fuel assemblies typically consist of an array of fuel rods that, depending on exposure in the reactor and consequent ingrowth of 244Cm, are spontaneous sources of as many as 109 neutrons s-1. Neutron emission tomography uses collimation to isolate neutron activity along ``lines of response'' through the assembly and, by combining many collimated views through the object, mathematically extracts the neutron emission from each fuel rod. This technique, by combining the use of fast neutrons -which can penetrate the entire fuel assembly -and computed tomography, is capable of detecting vacancies or substitutions of individual fuel rods. This paper will report on the physics design and component testing of the imaging system. This material is based upon work supported by the U.S. Department of Energy, Office of Defense Nuclear Nonproliferation Research and Development within the National Nuclear Security Administration, under Contract Number DE-AC05-00OR22725.

Safe nuclear power for the Third World

International Nuclear Information System (INIS)

Johnson, W.R.; Lyon, C.F.; Redick, J.R.

1989-01-01

It is clear that using nuclear power for the generation of electricity is one way of reducing the emissions of CO 2 and other gases that contribute to the greenhouse effect. Equally clear is the fact that the reduction can be magnified by converting domestic, commercial, and industrial power-consuming activities from the direct use of fossil fuel sources to electrical energy. A major area for future progress in limiting CO 2 emissions is in the Third World, where population growth and expectations for a higher social and economic standard of living portend vast increases in future energy use. A number of problems come to mind as one contemplates the widespread expansion of nuclear energy use into the Third World. The authors propose a method involving the marriage of two currently evolving concepts by which nuclear electrical generation can be expanded throughout the world in a manner that will address these problems. The idea is to form multinational independent electric generating companies, or nuclear electric companies (NECs), that would design, build, operate, and service a standardized fleet of nuclear power plants. The plants would be of the Integral Fast Reactor (IFR) design, now under development at Argonne National Laboratory, and, in particular, a commercial conceptualization of the IFR sponsored by General Electric Company, the Power Reactor Inherently Safe Module (PRISM)

Thorium-based nuclear fuel: current status and perspectives

International Nuclear Information System (INIS)

1987-03-01

Until the present time considerable efforts have already been made in the area of fabrication, utilization and reprocessing of Th-based fuels for different types of reactors, namely: by FRG and USA - for HTRs; FRG and Brazil, Italy - for LWRs; India - for HWRs and FBRs. Basic research of thorium fuels and thorium fuel cycles are also being undertaken by Australia, Canada, China, France, FRG, Romania, USSR and other countries. Main emphasis has been given to the utilization of thorium fuels in once-through nuclear fuel cycles, but in some projects closed thorium-uranium or thorium-plutonium fuel cycles are also considered. The purpose of the Technical Committee on the Utilization of Thorium-Based Nuclear Fuel: Current Status and Perspective was to review the world thorium resources, incentives for further exploration, obtained experience in the utilization of Th-based fuels in different types of reactors, basic research, fabrication and reprocessing of Th-based fuels. As a result of the panel discussion the recommendations on future Agency activities and list of major worldwide activities in the area of Th-based fuel were developed. A separate abstract was prepared for each of the 9 papers in this proceedings series

World nuclear atlas. A step toward energy transition

International Nuclear Information System (INIS)

Lepage, Corinne; Laborde, Xemartin

2015-01-01

Illustrated by more than 120 maps and figures, this book proposes an overview of the world nuclear industry, of its development, and of the various strategies chosen within the perspective of energy transition. It proposes an overview of the status of nuclear energy in the world (presentation of the nuclear energy, development during the X X century, uranium production, fuel production and processing, the nuclear reactor industry), addresses the main controversies (health and environmental impact, waste management, opacity of the information, major accidents), the new challenges faced by the nuclear sector (a difficult assessment of huge costs, competition with renewable energies, a competitive environment, a technological uncertainty, transparency and democracy), the solutions chosen by big countries (USA, China, India, Japan, Europe, the German energy transition), and proposes a focus on France which is the only country which chose an all-nuclear strategy (history, nuclear installations, main actors, the myth of the French energy independence, the post-Fukushima French fleet, the case of the Fessenheim reactor, the EPR in question, the challenge of waste storage with the Cigeo project, the debate on the nuclear cost)

World-wide French experience in research reactor fuel cycle transportation

International Nuclear Information System (INIS)

Raisonnier, D.

1997-01-01

Since 1963 Transnucleaire has safely performed a large number of national and international transports of radioactive material. Transnucleaire has also designed and supplied suitable packagings for all types of nuclear fuel cycle radioactive material from front-end and back-end products and for power or for research reactors. Transportation of the nuclear fuel material for power reactors is made on a regular and industrial basis. The transportation of material for the research reactor fuel cycle is quite different due to the small quantities involved, the categorisation of material and the numerous places of delivery world-wide. Adapted solutions exist, which require a reactive organisation dealing with all the transportation issues for LEU and HEU products as metal, oxide, fresh fuel elements, spent fuel elements including supply of necessary transport packaging and equipment. This presentation will: - explain the choices made by Transnucleaire and its associates to provide and optimise the corresponding services, - demonstrate the capability to achieve, through reliable partnership, transport operations involving new routes, specific equipment and new political constraints while respecting sophisticated safety and security regulations. (author)

The situation of nuclear power in the world

International Nuclear Information System (INIS)

1995-03-01

This report presents a world panorama of nuclear power for electricity generation purposes. The economic aspects, the fuel cycle market, the reactor technology development, as well as environmental aspects are presented. This report is updated annually and the present issue covers the situation up to December 1993. (F.E.). 196 refs, 23 figs, 28 tabs

Securing the nuclear fuel cycle: What next?

International Nuclear Information System (INIS)

Ruchkin, S.V.; Loginov, V.Y.

2006-01-01

international levels. The article is outlining what has been done in this area since then, and what are the prospects for development of multilateral approaches in the use of nuclear energy. One of the instruments to enhance the security of supply of NFC products and services suggested in the experts' report is reinforcement of existing market mechanisms. In this connection it looked quite logical for the World Nuclear Association (WNA) to set up, in August 2005, a dedicated working group comprising experts from the world nuclear industry. Representatives of the four leading world uranium enrichment services suppliers were in the group: AREVA (France), TENEX (Russia), URENCO (Germany, the Netherlands and UK), and USEC (US). As a result, in May 2006, the WNA produced a report entitled 'Ensuring Security of Supply in the International Nuclear Fuel Cycle' (see WNA website at www.world-nuclear.org/security.pdf). The report's most important highlights are discussed. .In September 2005, the six enrichment services supplier-States, under the leadership of the US, set up an intergovernmental working group to develop a multilateral mechanism for reliable access to nuclear fuel (RANF). The group presented its proposal to IAEA Member States in June 2006 and consultations continue on the next steps regarding their offer, under certain conditions, to provide low enriched uranium to States not pursuing sensitive nuclear activities. On 25 January, 2006 Russian President Vladimir Putin announced an initiative to develop a Global Nuclear Power Infrastructure (GNPI) capable of providing secured and non-discriminatory (equal) access to the benefits of nuclear energy to all interested countries in strict compliance with non-proliferation requirements. Establishment of a network of international NFC centers (INFCC), including enrichment services, under IAEA safeguards will become a key element of such an infrastructure. The GNPI-INFCC initiative is aimed primarily at countries who are developing

The final disposal facility of spent nuclear fuel

International Nuclear Information System (INIS)

Prvakova, S.; Necas, V.

2001-01-01

Today the most serious problem in the area of nuclear power engineering is the management of spent nuclear fuel. Due to its very high radioactivity the nuclear waste must be isolated from the environment. The perspective solution of nuclear fuel cycle is the final disposal into geological formations. Today there is no disposal facility all over the world. There are only underground research laboratories in the well developed countries like the USA, France, Japan, Germany, Sweden, Switzerland and Belgium. From the economical point of view the most suitable appears to build a few international repositories. According to the political and social aspect each of the country prepare his own project of the deep repository. The status of those programmes in different countries is described. The development of methods for the long-term management of radioactive waste is necessity in all countries that have had nuclear programmes. (authors)

Fuel choice, nuclear energy, climate and carbon

International Nuclear Information System (INIS)

Shpyth, A.

2012-01-01

For the second time since the start of commercial nuclear electricity generation, an accident has the world wondering if uranium will be among the future fuel choices in electricity production. Unfortunate when one considers the low-carbon footprint of this energy option. An accident involving a nuclear power plant, or more appropriately the perceived risks associated with an accident at a nuclear power plant, is but one of the issues that makes the impact assessment process related to nuclear energy projects challenging. Other aspects, including the time scales associated with their siting, licensing, operation and decommissioning, also contribute to the challenge. Strategic environmental assessments for future fuel choices in electricity generation, particularly ones that consider the use of life cycle assessment information, would allow for the effective evaluation of the issues identified above. But more importantly from an impact assessment perspective, provide for a comparative assertion for public disclosure on the environmental impacts of fuel choice. This would provide the public and government decision makers with a more complete view of the role nuclear energy may be able to play in mitigating the climate and carbon impacts of increased electricity production, and place issues of cost, complexity and scale in a more understandable context.

Nuclear fuel accounting

International Nuclear Information System (INIS)

Aisch, D.E.

1977-01-01

After a nuclear power plant has started commercial operation the actual nuclear fuel costs have to be demonstrated in the rate making procedure. For this purpose an accounting system has to be developed which comprises the following features: 1) All costs associated with nuclear fuel shall be correctly recorded; 2) it shall be sufficiently flexible to cover also deviations from proposed core loading patterns; 3) it shall be applicable to different fuel cycle schemes. (orig./RW) [de

World's energy appetite may crave nuclear power

International Nuclear Information System (INIS)

Fulkerson, W.; Anderson, T.D.

1996-01-01

As scientists come to agree that global warming is a real phenomenon, it may be time to jumpstart the stalled nuclear industry. World population is expected to double by the end of the 21st century, and the lion's share of growth will be in developing nations. open-quotes More people and more economic activity will require more energy,close quotes say William Fulkerson, a senior fellow at the Joint Institute for Energy and the Environment in Knoxville, Tennessee, and Truman D. Anderson, formerly director of planning at Oak Ridge National Laboratory. There are only three viable options to fossil fuel plants, the authors say: nuclear fission, nuclear fusion, and such renewable energy sources as solar and wind. The advantages of nuclear energy are well known, the authors say. open-quotes It emits no greenhouse gases, and potentially it can be expanded almost without limit anywhere in the world, providing the controversies that surround it can be resolved.close quotes However, to garner public acceptance, a new generation of supersafe nuclear reactors, invulnerable to terrorism and conversion to weapons, will need to be developed, the authors say

Nuclear Fuel Cycle Information System. A directory of nuclear fuel cycle facilities. 2009 ed

International Nuclear Information System (INIS)

2009-04-01

The Nuclear Fuel Cycle Information System (NFCIS) is an international directory of civilian nuclear fuel cycle facilities, published online as part of the Integrated Nuclear Fuel Cycle Information System (iNFCIS: http://www-nfcis.iaea.org/). This is the fourth hardcopy publication in almost 30 years and it represents a snapshot of the NFCIS database as of the end of 2008. Together with the attached CD-ROM, it provides information on 650 civilian nuclear fuel cycle facilities in 53 countries, thus helping to improve the transparency of global nuclear fuel cycle activities

From the nuclear world

International Nuclear Information System (INIS)

Anon.

2017-01-01

This document gathers pieces of information from around the world concerning nuclear industry. The most relevant ones are the following. AREVA NP and EDF have created a new society EDVANCE to combine their engineering teams in the fields of reactor core design and construction. The German Constitutional Court considers as illegal the nuclear fuel tax that was implemented in 2010 to balance public finance and fund the remediation of the Ass salt mine. In France on the Tricastin AREVA's site the ATLAS laboratory has opened its doors, it is the laboratory that will perform all the environmental and industrial analyses of this site. In Japan the reactors 3 and 4 of the Takahama power plant have resumed operations. Today 5 nuclear power reactors are operating on Japanese soil. The Indian government has announced its intention to build heavy water cooled nuclear reactors based on an Indian design. 22 reactors are operating in India representing a total of 6780 MW and 5 others are being built. According to the 'SMR Start' consortium public-private partnership contracts have to be promoted in order to launch the small modular reactor (SMR) technology. (A.C.)

Some aspects of nuclear fuel economics

International Nuclear Information System (INIS)

Timm, M.

1975-01-01

The paper reviews the economic aspects of nuclear fuel based on the year 1975. The focus of attention is on the well-established light-water reactors, which for the time being, and also for the foreseeable future, account for the bulk of the world's nuclear power capacity. The author describes the principal economic aspects of the light-water fuel cycle components and discusses their future development to the extent that this can be foreseen. Various approaches to the formulation of the contract for the supply of light-water fuel are discussed on the basis of the established procedure. After some introductory comments on methods of calculating specific fuel costs, the author describes the main results of fuel cycle calculations. The economic aspects of nuclear fuel for other types of reactors are discussed in the sequence in which it is planned to introduce such reactors commercially. The economic data available apply to reactors ranging from the heavy-water-moderated type, through helium-cooled high-temperature reactors, to the fast breeders, and are based more and more on results of feasibility studies and less on practical operational experience. For this reason the author discusses only the basic data of importance, as viewed from the present-day stand-point, and mentions the emerging trends. It should be pointed out, however, that a comprehensive description of this kind can only show the situation at a given moment. Numerous political, economic and technological influences are in a state of permanent flux, hence economic data and developments may easily change within a short time. (author)

Market-sharing approach to the world nuclear sales problem

International Nuclear Information System (INIS)

Ribicoff, A.A.

1976-01-01

The recent decisions by West Germany and France to sell nuclear fuel facilities to Brazil and Pakistan, respectively, mark the first sharp divergence by major industrial nations from long-established U.S. nonproliferation policy. Thus far, the U.S. has been ineffective in seeking to persuade Germany and France not to proceed with them. This indicates a serious weakness in the execution of American nonproliferation policy, which if left uncorrected, could result in the rapid spread of nuclear weapons material and capability around the world. It is clear that complex problems are raised by the concept of market-sharing. A principal advocate, Dr. Lawrence Scheinman from ERDA, says that traditional arguments against market-sharing do not qualify as reasons against the concept. He does identify three basic arguments against market-sharing, which the author discusses in this article, namely: (1) reactor market-sharing is contrary to U.S. anti-cartel policy and in violation of antitrust laws; (2) other nuclear supplier countries would reject a market-sharing arrangement; and (3) the recipient countries of the Third World would view it as a nuclear cartel and refuse to do business with it. The author advocates that at the very least, the U.S. should enter the next round of supplier negotiations prepared to propose multinational arrangements for closing the commercial nuclear fuel cycle and for making all weapons-grade material generated by the fuel cycle unavailable to any nation on a sovereign basis. The U.S. should also make clear that it would view with the gravest concern the continuation of the present export policies of West Germany and France

From the nuclear world

International Nuclear Information System (INIS)

Anon.

2015-01-01

This document gathers pieces of information concerning nuclear industry worldwide. The most relevant are the following ones. China has announced the construction between 2020 and 2025 of the biggest particle accelerator in the world. The Finn government has agreed with the project of a spent fuel storage center, it was the last administrative step before the launching of the construction works. The quality of the steel of the pressure vessel of the Olkiluoto EPR has been assessed by the Finn nuclear safety authority (STUK). The French nuclear safety authority (ASN) has launched a test program for assessing the resistance of the pressure vessel of the Flamanville EPR as a consequence of the recent discovery of defects in the composition of the steel. A robot called SX1 has been designed to measure radiation in a continuous way by strolling about in a nuclear facility. As a consequence of a tense relationship with Russia, the Turkish government has stopped the construction (by Rosatom) of the Akkuyu nuclear plant. The Belgian government and the Electrabel company have signed an agreement for a 10 year extension of the operating life of the Doel 1 and 2 reactors. Chinese authorities have approved the construction of 4 new third generation reactors. (A.C.)

Nuclear fuel element

International Nuclear Information System (INIS)

Penrose, R.T.; Thompson, J.R.

1976-01-01

A method of protecting the cladding of a nuclear fuel element from internal attack and a nuclear fuel element for use in the core of a nuclear reactor are disclosed. The nuclear fuel element has disposed therein an additive of a barium-containing material and the barium-containing material collects reactive gases through chemical reaction or adsorption at temperatures ranging from room temperature up to fuel element plenum temperatures. The additive is located in the plenum of the fuel element and preferably in the form of particles in a hollow container having a multiplicity of gas permeable openings in one portion of the container with the openings being of a size smaller than the size of the particles. The openings permit gases and liquids entering the plenum to contact the particles. The additive is comprised of elemental barium or a barium alloy containing one or more metals in addition to barium such as aluminum, zirconium, nickel, titanium and combinations thereof. 6 claims, 3 drawing figures

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

Device for separating, purifying and recovering nuclear fuel material, impurities and materials from impurity-containing nuclear fuel materials or nuclear fuel containing material

International Nuclear Information System (INIS)

Sato, Ryuichi; Kamei, Yoshinobu; Watanabe, Tsuneo; Tanaka, Shigeru.

1988-01-01

Purpose: To separate, purify and recover nuclear fuel materials, impurities and materials with no formation of liquid wastes. Constitution: Oxidizing atmosphere gases are introduced from both ends of a heating furnace. Vessels containing impurity-containing nuclear fuel substances or nuclear fuel substance-containing material are continuously disposed movably from one end to the other of the heating furnace. Then, impurity oxides or material oxides selectively evaporated from the impurity-containing nuclear fuel substances or nuclear fuel substance-containing materials are entrained in the oxidizing atmosphere gas and the gases are led out externally from a discharge port opened at the intermediate portion of the heating furnace, filters are disposed to the exit to solidify and capture the nuclear fuel substances and traps are disposed behind the filters to solidify and capture the oxides by spontaneous air cooling or water cooling. (Sekiya, K.)

Strengthening the nuclear nonproliferation regime: focus on the civilian nuclear fuel cycle

International Nuclear Information System (INIS)

Saltiel, David H.; Pregenzer, Arian Leigh

2005-01-01

Leaders around the world and across the ideological spectrum agree that the global nonproliferation regime is facing a serious test. The emergence of sophisticated terrorist networks, black markets in nuclear technology, and technological leaps associated with globalization have conspired to threaten one of the most successful examples of international cooperation in history. The rampant proliferation of nuclear weapons that was predicted at the start of the nuclear age has been largely held in check and the use of those weapons avoided. Nonetheless, with the thirty-fifth anniversary of the Treaty on the Nonproliferation of Nuclear Weapons (NPT), the threat of nuclear proliferation seems more serious than ever. Although experts readily concede that there exist many pathways to proliferation, the threat posed by the misuse of the civilian nuclear fuel cycle has received considerable recent attention. While the connection between nuclear energy and nonproliferation has been a topic of discussion since the dawn of the nuclear age, world events have brought the issue to the forefront once again. United States President George W. Bush and International Atomic Energy Agency (IAEA) Director General Mohammad ElBaradei are among those who have highlighted proliferation risks associated with civilian nuclear power programs and called for revitalizing the nuclear nonproliferation regime to address new threats. From the possibility of diversion or theft of nuclear material or technology, to the use of national civilian programs as a cover for weapons programs - what some have called latent proliferation - the fuel cycle appears to many to represent a glaring proliferation vulnerability. Just as recognition of these risks is not new, neither is recognition of the many positive benefits of nuclear energy. In fact, a renewed interest in exploiting these benefits has increased the urgency of addressing the risks. Global energy demand is expected to at least double by the middle of

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

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 proliferation-resistance and safeguards for future nuclear fuel cycle

International Nuclear Information System (INIS)

Kuno, Y.; Inoue, N.; Senzaki, M.

2009-01-01

Corresponding to the world nuclear security concerns, future nuclear fuel cycle (NFC) should have high proliferation-resistance (PR) and physical protection (PP), while promotion of the peaceful use of the nuclear energy must not be inhibited. In order to accomplish nuclear non-proliferation from NFC, a few models of the well-PR systems should be developed so that international community can recognize them as worldwide norms. To find a good balance of 'safeguard-ability (so-called extrinsic measure or institutional barrier)' and 'impede-ability (intrinsic feature or technical barrier)' will come to be essential for NFC designers to optimize civilian nuclear technology with nuclear non-proliferation, although the advanced safeguards with high detectability can still play a dominant role for PR in the states complying with full institutional controls. Accomplishment of such goal in a good economic efficiency is a future key challenge

Nuclear proliferation-resistance and safeguards for future nuclear fuel cycle

Science.gov (United States)

Kuno, Y.; Inoue, N.; Senzaki, M.

2009-03-01

Corresponding to the world nuclear security concerns, future nuclear fuel cycle (NFC) should have high proliferation-resistance (PR) and physical protection (PP), while promotion of the peaceful use of the nuclear energy must not be inhibited. In order to accomplish nuclear non-proliferation from NFC, a few models of the well-PR systems should be developed so that international community can recognize them as worldwide norms. To find a good balance of 'safeguard-ability (so-called extrinsic measure or institutional barrier)' and 'impede-ability (intrinsic feature or technical barrier)' will come to be essential for NFC designers to optimize civilian nuclear technology with nuclear non-proliferation, although the advanced safeguards with high detectability can still play a dominant role for PR in the states complying with full institutional controls. Accomplishment of such goal in a good economic efficiency is a future key challenge.

Plutonium Discharge Rates and Spent Nuclear Fuel Inventory Estimates for Nuclear Reactors Worldwide

Energy Technology Data Exchange (ETDEWEB)

Brian K. Castle; Shauna A. Hoiland; Richard A. Rankin; James W. Sterbentz

2012-09-01

This report presents a preliminary survey and analysis of the five primary types of commercial nuclear power reactors currently in use around the world. Plutonium mass discharge rates from the reactors’ spent fuel at reload are estimated based on a simple methodology that is able to use limited reactor burnup and operational characteristics collected from a variety of public domain sources. Selected commercial reactor operating and nuclear core characteristics are also given for each reactor type. In addition to the worldwide commercial reactors survey, a materials test reactor survey was conducted to identify reactors of this type with a significant core power rating. Over 100 material or research reactors with a core power rating >1 MW fall into this category. Fuel characteristics and spent fuel inventories for these material test reactors are also provided herein.

Application of United Nations Framework Classification – 2009 (UNFC-2009) to nuclear fuel resources

International Nuclear Information System (INIS)

Tulsidas, H.; Hanly, A.; Li, S.; Miezitis, Y.; Carson, L.; Hall, S.; Van Gosen, B.; Vance, R.; Mukusheva, A.; Villas-Bôas, R.; Griffiths, C.; Ross, J.; MacDonald, D.; Bankes, P.

2014-01-01

Nuclear energy currently provides approximately 15% of the world’s electricity, utilized in about 30 countries. As many countries are planning to expand capacity or introduce nuclear power into the energy mix, the demand for uranium fuel is expected to increase. Reactors suitable for utilizing thorium as fuel are also being developed for deployment in the long-term. Since nuclear power is capital intensive and uranium feedstock is required for a nuclear reactor life of between 40 and 60 years, operators need assurance of a reliable uranium supply. Comprehensive and up-to-date information on the worldwide supply of nuclear fuel resources is therefore essential for planning and implementation of nuclear power programmes. Information on resources are provided through the bi-annual Organisation for Economic Co-operation and Development / Nuclear Energy Agency – International Atomic Energy Agency (OECD-NEA/IAEA ) report “Uranium: Resources, Production and Demand” (the “Red Book”) and the online datasets of World Distribution of Uranium Deposits (UDEPO) and World Thorium Deposits and Resources (ThDEPO).

Research on assurance system of nuclear fuel supply (Contract research)

International Nuclear Information System (INIS)

Kobayashi, Naoki; Naoi, Yosuke; Wakabayashi, Shuji; Tazaki, Makiko; Senzaki, Masao

2010-03-01

Assurance of supply (AOS) of nuclear fuel is a special arrangement in case of nuclear fuel supply disruption caused by political reasons other than nonproliferation. It aims to support a stable supply of nuclear fuel while avoiding unnecessary spread of sensitive enrichment technology. Current discussions on AOS have been initiated by the IAEA Director-General's article published in The Economist entitled 'Towards a Safer World' Oct. 2003. Since then, various proposals on AOS have been presented. In order to facilitate international discussions on AOS, authors have conducted studies of AOS system based on Japanese Government's proposal 'IAEA Standby Arrangement System (INFCIRC/683)'. In this paper, we gave an overview of discussions on AOS since World War II, and elaborated on some of current proposals. We have been able to discuss feasibility of AOS system more specifically by including additional costs and period required for AOS, and to present a system which could work as a practical system. Issues we have tried to tackle here include definitions of AOS, and roles of consumer states, supplier states, IAEA and nuclear industries. We present some solutions including broadening coverage of AOS, declaration by supplier states on AOS, establishing advisory committee in the IAEA on the actual application of AOS, and setting up an IAEA fund for AOS. (author)

Development of Nuclear Fuel Remote Fabrication Technology

International Nuclear Information System (INIS)

Lee, Jung Won; Yang, M. S.; Kim, S. S. and others

2005-04-01

The aim of this study is to develop the essential technology of dry refabrication using spent fuel materials in a laboratory scale on the basis of proliferation resistance policy. The emphasis is placed on the assessment and the development of the essential technology of dry refabrication using spent fuel materials. In this study, the remote fuel fabrication technology to make a dry refabricated fuel with an enhanced quality was established. And the instrumented fuel pellets and mini-elements were manufactured for the irradiation testing in HANARO. The design and development technology of the remote fabrication equipment and the remote operating and maintenance technology of the equipment in hot cell were also achieved. These achievements will be used in and applied to the future back-end fuel cycle and GEN-IV fuel cycle and be a milestone for Korea to be an advanced nuclear country in the world

Performance of water cooled nuclear power reactor fuels in India – Defects, failures and their mitigation

International Nuclear Information System (INIS)

Ganguly, Chaitanyamoy

2015-01-01

Water cooled and moderated nuclear power reactors account for more than 95% of the operating reactors in the world today. Light water reactors (LWRs) consisting of pressurized water reactor (PWR), their Russian counterpart namely VVER and boiling water reactor (BWR) will continue to dominate the nuclear power market. Pressurized heavy water reactor (PHWR), also known as CANDU, is the backbone of the nuclear power program in India. Updates on LWR and PHWR fuel performance are being periodically published by IAEA, OECD-NEA and the World Nuclear Association (WNA), highlighting fuel failure rate and the mitigation of fuel defects and failures. These reports clearly indicate that there has been significant improvement in in – pile fuel performance over the years and the present focus is to achieve zero fuel failure in high burn up and high performance fuels. The present paper summarizes the status of PHWR and LWR fuel performance in India, highlighting the manufacturing and the related quality control and inspection steps that are being followed at the PHWR fuel fabrication plant in order to achieve zero manufacturing defect which could contribute to achieving zero in – pile failure rate in operating and upcoming PHWR units in India. (author)

Nuclear fuels

International Nuclear Information System (INIS)

Beauvy, M.; Berthoud, G.; Defranceschi, M.; Ducros, G.; Guerin, Y.; Limoge, Y.; Madic, Ch.; Santarini, G.; Seiler, J.M.; Sollogoub, P.; Vernaz, E.; Guillet, J.L.; Ballagny, A.; Bechade, J.L.; Bonin, B.; Brachet, J.Ch.; Delpech, M.; Dubois, S.; Ferry, C.; Freyss, M.; Gilbon, D.; Grouiller, J.P.; Iracane, D.; Lansiart, S.; Lemoine, P.; Lenain, R.; Marsault, Ph.; Michel, B.; Noirot, J.; Parrat, D.; Pelletier, M.; Perrais, Ch.; Phelip, M.; Pillon, S.; Poinssot, Ch.; Vallory, J.; Valot, C.; Pradel, Ph.; Bonin, B.; Bouquin, B.; Dozol, M.; Lecomte, M.; Vallee, A.; Bazile, F.; Parisot, J.F.; Finot, P.; Roberts, J.F.

2009-01-01

Fuel is one of the essential components in a reactor. It is within that fuel that nuclear reactions take place, i.e. fission of heavy atoms, uranium and plutonium. Fuel is at the core of the reactor, but equally at the core of the nuclear system as a whole. Fuel design and properties influence reactor behavior, performance, and safety. Even though it only accounts for a small part of the cost per kilowatt-hour of power provided by current nuclear power plants, good utilization of fuel is a major economic issue. Major advances have yet to be achieved, to ensure longer in-reactor dwell-time, thus enabling fuel to yield more energy; and improve ruggedness. Aside from economics, and safety, such strategic issues as use of plutonium, conservation of resources, and nuclear waste management have to be addressed, and true technological challenges arise. This Monograph surveys current knowledge regarding in-reactor behavior, operating limits, and avenues for R and D. It also provides illustrations of ongoing research work, setting out a few noteworthy results recently achieved. Content: 1 - Introduction; 2 - Water reactor fuel: What are the features of water reactor fuel? 9 (What is the purpose of a nuclear fuel?, Ceramic fuel, Fuel rods, PWR fuel assemblies, BWR fuel assemblies); Fabrication of water reactor fuels (Fabrication of UO 2 pellets, Fabrication of MOX (mixed uranium-plutonium oxide) pellets, Fabrication of claddings); In-reactor behavior of UO 2 and MOX fuels (Irradiation conditions during nominal operation, Heat generation, and removal, The processes involved at the start of irradiation, Fission gas behavior, Microstructural changes); Water reactor fuel behavior in loss of tightness conditions (Cladding, the first containment barrier, Causes of failure, Consequences of a failure); Microscopic morphology of fuel ceramic and its evolution under irradiation; Migration and localization of fission products in UOX and MOX matrices (The ceramic under irradiation

Nuclear fuels

Energy Technology Data Exchange (ETDEWEB)

Beauvy, M.; Berthoud, G.; Defranceschi, M.; Ducros, G.; Guerin, Y.; Limoge, Y.; Madic, Ch.; Santarini, G.; Seiler, J.M.; Sollogoub, P.; Vernaz, E.; Guillet, J.L.; Ballagny, A.; Bechade, J.L.; Bonin, B.; Brachet, J.Ch.; Delpech, M.; Dubois, S.; Ferry, C.; Freyss, M.; Gilbon, D.; Grouiller, J.P.; Iracane, D.; Lansiart, S.; Lemoine, P.; Lenain, R.; Marsault, Ph.; Michel, B.; Noirot, J.; Parrat, D.; Pelletier, M.; Perrais, Ch.; Phelip, M.; Pillon, S.; Poinssot, Ch.; Vallory, J.; Valot, C.; Pradel, Ph.; Bonin, B.; Bouquin, B.; Dozol, M.; Lecomte, M.; Vallee, A.; Bazile, F.; Parisot, J.F.; Finot, P.; Roberts, J.F

2009-07-01

Fuel is one of the essential components in a reactor. It is within that fuel that nuclear reactions take place, i.e. fission of heavy atoms, uranium and plutonium. Fuel is at the core of the reactor, but equally at the core of the nuclear system as a whole. Fuel design and properties influence reactor behavior, performance, and safety. Even though it only accounts for a small part of the cost per kilowatt-hour of power provided by current nuclear power plants, good utilization of fuel is a major economic issue. Major advances have yet to be achieved, to ensure longer in-reactor dwell-time, thus enabling fuel to yield more energy; and improve ruggedness. Aside from economics, and safety, such strategic issues as use of plutonium, conservation of resources, and nuclear waste management have to be addressed, and true technological challenges arise. This Monograph surveys current knowledge regarding in-reactor behavior, operating limits, and avenues for R and D. It also provides illustrations of ongoing research work, setting out a few noteworthy results recently achieved. Content: 1 - Introduction; 2 - Water reactor fuel: What are the features of water reactor fuel? 9 (What is the purpose of a nuclear fuel?, Ceramic fuel, Fuel rods, PWR fuel assemblies, BWR fuel assemblies); Fabrication of water reactor fuels (Fabrication of UO{sub 2} pellets, Fabrication of MOX (mixed uranium-plutonium oxide) pellets, Fabrication of claddings); In-reactor behavior of UO{sub 2} and MOX fuels (Irradiation conditions during nominal operation, Heat generation, and removal, The processes involved at the start of irradiation, Fission gas behavior, Microstructural changes); Water reactor fuel behavior in loss of tightness conditions (Cladding, the first containment barrier, Causes of failure, Consequences of a failure); Microscopic morphology of fuel ceramic and its evolution under irradiation; Migration and localization of fission products in UOX and MOX matrices (The ceramic under

Approach to securing of stable nuclear fuel supplies

International Nuclear Information System (INIS)

Koike, Kunihisa; Imamura, Isao; Noda, Tetsuya

2010-01-01

With the dual objectives of not only ensuring stable electric power supplies but also preventing global warming, the construction of new nuclear power plants is being planned in many countries throughout the world. Toshiba and Westinghouse Electric Company (WEC), a member of the Toshiba Group, are capable of supplying both boiling water reactor (BWR) and pressurized water reactor (PWR) plants to satisfy a broad range of customer requirements. Furthermore, to meet the growing demand for the securing of nuclear fuel supplies, Toshiba and WEC have been promoting the strengthening and further expansion of supply chains in the fields of uranium production, uranium hexafluoride (UF 6 ) conversion, uranium enrichment, and fuel fabrication. (author)

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 proliferation-resistance and safeguards for future nuclear fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Kuno, Y. [Japan Atomic Energy Agency (JAEA) Nuclear-Non-proliferation Science and Technology Centre (NPSTC), 2-4 Shirane Shirakata, Tokai-mura, Ibaraki, 319-1195 (Japan); University of Tokyo, Nuclear Engineering and Management, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan)], E-mail: kuno.yusuke@jaea.go.jp; Inoue, N. [Japan Atomic Energy Agency (JAEA) Nuclear-Non-proliferation Science and Technology Centre (NPSTC), 2-4 Shirane Shirakata, Tokai-mura, Ibaraki, 319-1195 (Japan); University of Tokyo, Nuclear Engineering and Management, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan); Senzaki, M. [Japan Atomic Energy Agency (JAEA) Nuclear-Non-proliferation Science and Technology Centre (NPSTC), 2-4 Shirane Shirakata, Tokai-mura, Ibaraki, 319-1195 (Japan)

2009-03-15

Corresponding to the world nuclear security concerns, future nuclear fuel cycle (NFC) should have high proliferation-resistance (PR) and physical protection (PP), while promotion of the peaceful use of the nuclear energy must not be inhibited. In order to accomplish nuclear non-proliferation from NFC, a few models of the well-PR systems should be developed so that international community can recognize them as worldwide norms. To find a good balance of 'safeguard-ability (so-called extrinsic measure or institutional barrier)' and 'impede-ability (intrinsic feature or technical barrier)' will come to be essential for NFC designers to optimize civilian nuclear technology with nuclear non-proliferation, although the advanced safeguards with high detectability can still play a dominant role for PR in the states complying with full institutional controls. Accomplishment of such goal in a good economic efficiency is a future key challenge.

Spent fuel management and closed nuclear fuel cycle

International Nuclear Information System (INIS)

Kudryavtsev, E.G.

2012-01-01

Strategic objectives set by Rosatom Corporation in the field of spent fuel management are given. By 2030, Russia is to create technological infrastructure for innovative nuclear energy development, including complete closure of the nuclear fuel cycle. A target model of the spent NPP nuclear fuel management system until 2030 is analyzed. The schedule for key stages of putting in place the infrastructure for spent NPP fuel management is given. The financial aspect of the problem is also discussed [ru

Nuclear fuel assembly

International Nuclear Information System (INIS)

Hayashi, Hiroshi; Watari, Yoshio; Hizahara, Hiroshi; Masuoka, Ryuzo.

1970-01-01

When exchanging nuclear fuel assemblies during the operation of a nuclear reactor, melting of fuel bodies, and severence of tubular claddings is halted at the time of insertion by furnishing a neutron absorbing material such as B 10 , Cd, Gd or the like at the forward end of the fuel assembly to thereby lower the power peak at the forward ends of the fuel elements to within tolerable levels and thus prevent both fuel liquification and excessive expansion. The neutron absorbing material may be attached in the form of a plate to the fuel assembly forward tie plate, or may be inserted as a pellet into the front end of the tubular cladding. (Owens, K.J.)

Enduring Nuclear Fuel Cycle, Proceedings of a panel discussion

Energy Technology Data Exchange (ETDEWEB)

Walter, C. E., LLNL

1997-11-18

The panel reviewed the complete nuclear fuel cycle in the context of alternate energy resources, energy need projections, effects on the environment, susceptibility of nuclear materials to theft, diversion, and weapon proliferation. We also looked at ethical considerations of energy use, as well as waste, and its effects. The scope of the review extended to the end of the next century with due regard for world populations beyond that period. The intent was to take a long- range view and to project, not forecast, the future based on ethical rationales, and to avoid, as often happens, long-range discussions that quickly zoom in on only the next few decades. A specific nuclear fuel cycle technology that could satisfy these considerations was described and can be applied globally.

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

Electromagnetic Acoustic Test of the Artificial Defects for a Plate-type Nuclear Fuel

International Nuclear Information System (INIS)

Jung, Hyun Kyu; Kim, Dong Min; Lee, Yoon Sang; Cheong, Yong Moo

2011-01-01

Most research and test reactors use the nuclear fuel plates which are consisted of a fuel meat in aluminum alloy. Last year, KAERI signed a deal with the Jordan Atomic Energy Commission to build the research reactor and have to supply the plate-type nuclear fuels. For the demands of world market, KAERI started the research and development of the plate-type fuel elements and endeavored to achieve a localization of the plate-type fuel fabrication. For the inspection of plate-type fuel elements to be used in Research Reactors, an immersion pulse-echo ultrasonic technique was applied. This inspection was done under immersion condition, so a nuclear fuel was immersed to be prone to corrosion and needed to have time and cost due to an additional process. The sample that will be examined is a non-ferromagnetic material such as aluminum with a good acousto-elastic property, which requires an effective inspection of a bond quality for a nuclear fuel under a manufacturing environment. The purpose of this study is to investigate the feasibility of an Electromagnetic Acoustic Transducer (EMAT) technology for an automated inspection of a nuclear fuel without water

WNA position statement on safe management of nuclear waste and used nuclear fuel

International Nuclear Information System (INIS)

Saint-Pierre, S.

2006-01-01

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

Plutonium in an enduring fuel cycle

International Nuclear Information System (INIS)

Pillay, K.K.S.

1998-05-01

Nuclear fuel cycles evolved over the past five decades have allowed many nations of the world to enjoy the benefits of nuclear energy, while contributing to the sustainable consumption of the world's energy resources. The nuclear fuel cycle for energy production suffered many traumas since the 1970s because of perceived risks of proliferation of nuclear weapons. However, the experience of the past five decades has shown that the world community is committed to safeguarding all fissile materials and continuing the use of nuclear energy resources. Decisions of a few nations to discard spent nuclear fuels in geologic formations are contrary to the goals of an enduring nuclear fuel cycle and sustainable development being pursued by the world community. The maintenance of an enduring nuclear fuel cycle is dependent on sensible management of all the resources of the fuel cycle, including spent fuels

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2000-01-01

This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1999 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1999; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; grid connection forecasts; world electric power market; electronuclear owners and share holders in EU, capacity and load factor; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; 1999 gross load factor by operator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

Method of manufacturing nuclear fuel pellet

International Nuclear Information System (INIS)

Oguma, Masaomi; Masuda, Hiroshi; Hirai, Mutsumi; Tanabe, Isami; Yuda, Ryoichi.

1989-01-01

In a method of manufacturing nuclear fuel pellets by compression molding an oxide powder of nuclear fuel material followed by sintering, a metal nuclear material is mixed with an oxide powder of the nuclear fuel material. As the metal nuclear fuel material, whisker or wire-like fine wire or granules of metal uranium can be used effectively. As a result, a fuel pellet in which the metal nuclear fuel is disposed in a network-like manner can be obtained. The pellet shows a great effect of preventing thermal stress destruction of pellets upon increase of fuel rod power as compared with conventional pellets. Further, the metal nuclear fuel material acts as an oxygen getter to suppress the increase of O/M ratio of the pellets. Further, it is possible to reduce the swelling of pellet at high burn-up degree. (T.M.)

The cycle of the nuclear fuel used in EDF power plants

International Nuclear Information System (INIS)

2011-11-01

This document briefly indicates the different stages of the nuclear fuel cycle, from the purchase of natural uranium to waste storage. It also indicates the main responsibilities of EDF regarding this fuel cycle (to secure supplies, to organise material transportation, to process and store used fuels and associated wastes). It presents the different associated processes: uranium extraction, purification and concentration, conversion or fluoridation, enrichment. It briefly describes the fuel assembly fabrication, and indicates the main uranium producers in the world. Other addressed steps are: the transportation of fuel assembly, fuel loading, and spent fuel management, the processing of spent fuel and radioactive wastes

Nuclear fuel banks

International Nuclear Information System (INIS)

Anon.

2010-01-01

In december 2010 IAEA gave its agreement for the creation of a nuclear fuel bank. This bank will allow IAEA to help member countries that renounce to their own uranium enrichment capacities. This bank located on one or several member countries will belong to IAEA and will be managed by IAEA and its reserve of low enriched uranium will be sufficient to fabricate the fuel for the first load of a 1000 MW PWR. Fund raising has been successful and the running of the bank will have no financial impact on the regular budget of the IAEA. Russia has announced the creation of the first nuclear fuel bank. This bank will be located on the Angarsk site (Siberia) and will be managed by IAEA and will own 120 tonnes of low-enriched uranium fuel (between 2 and 4.95%), this kind of fuel is used in most Russian nuclear power plants. (A.C.)

South Korea's nuclear fuel industry

International Nuclear Information System (INIS)

Clark, R.G.

1990-01-01

March 1990 marked a major milestone for South Korea's nuclear power program, as the country became self-sufficient in nuclear fuel fabrication. The reconversion line (UF 6 to UO 2 ) came into full operation at the Korea Nuclear Fuel Company's fabrication plant, as the last step in South Korea's program, initiated in the mid-1970s, to localize fuel fabrication. Thus, South Korea now has the capability to produce both CANDU and pressurized water reactor (PWR) fuel assemblies. This article covers the nuclear fuel industry in South Korea-how it is structures, its current capabilities, and its outlook for the future

Nuclear weapons proliferation as a world order problem

International Nuclear Information System (INIS)

Falk, R.

1977-01-01

World-order concerns have intensified recently in light of mounting evidence that a weapons capability will soon be within easy reach of more and more governments and of certain nongovernmental groupings as well. One reliable source estimates that by 1985 as many as fifty countries could ''produce enough plutonium each year for at least several dozen nuclear explosives.'' In an even more immediate sense, ''economic competition among nuclear suppliers today could soon lead to a world in which twenty or more nations are but a few months from a nuclear weapons force.'' Three developments have created this ''world order'' sense of concern: (1) increased pace of civilian nuclear power deployment globally as a consequence of rising oil prices, unreliability of oil supplies, and reality of dwindling oil reserves in any case; (2) actuality of India's nuclear explosion in May 1974 which demonstrated vividly how any state that pursues a ''civilian'' program can also develop its own weapons capability; and (3) the intensification of competition for international nuclear sales which makes it increasingly evident that nonproliferation goals are no longer compatible with the pursuit of national commercial advantage; essentially, this reality has emerged from a break in the American monopoly over civilian nuclear technology and the willingness of French and German suppliers to provide all elements of the nuclear fuel cycle, including enrichment and reprocessing facilities,to any nation that feels it can afford to buy them; the German-Brazilian deal (worth at least $4 billion) has proven to be the equivalent in the commercial realm of India's ''peaceful'' nuclear explosion. Such developments disclose the alarming prospect that easier access to nuclear technology will make it relatively simple and thus more likely for a beleaguered government or a desperate political actor of any sort to acquire and possibly use nuclear weapons

Dissolving method for nuclear fuel oxide

International Nuclear Information System (INIS)

Tomiyasu, Hiroshi; Kataoka, Makoto; Asano, Yuichiro; Hasegawa, Shin-ichi; Takashima, Yoichi; Ikeda, Yasuhisa.

1996-01-01

In a method of dissolving oxides of nuclear fuels in an aqueous acid solution, the oxides of the nuclear fuels are dissolved in a state where an oxidizing agent other than the acid is present together in the aqueous acid solution. If chlorate ions (ClO 3 - ) are present together in the aqueous acid solution, the chlorate ions act as a strong oxidizing agent and dissolve nuclear fuels such as UO 2 by oxidation. In addition, a Ce compound which generates Ce(IV) by oxidation is added to the aqueous acid solution, and an ozone (O 3 ) gas is blown thereto to dissolve the oxides of nuclear fuels. Further, the oxides of nuclear fuels are oxidized in a state where ClO 2 is present together in the aqueous acid solution to dissolve the oxides of nuclear fuels. Since oxides of the nuclear fuels are dissolved in a state where the oxidizing agent is present together as described above, the oxides of nuclear fuels can be dissolved even at a room temperature, thereby enabling to use a material such as polytetrafluoroethylene and to dissolve the oxides of nuclear fuels at a reduced cost for dissolution. (T.M.)

Nuclear fuels policy. Report of the Atlantic Council's Nuclear Fuels Policy Working Group

International Nuclear Information System (INIS)

Anon.

1976-01-01

This Policy Paper recommends the actions deemed necessary to assure that future U.S. and non-Communist countries' nuclear fuels supply will be adequate, considering the following: estimates of modest growth in overall energy demand, electrical energy demand, and nuclear electrical energy demand in the U.S. and abroad, predicated upon the continuing trends involving conservation of energy, increased use of electricity, and moderate economic growth (Chap. I); possibilities for the development and use of all domestic resources providing energy alternatives to imported oil and gas, consonant with current environmental, health, and safety concerns (Chap. II); assessment of the traditional energy sources which provide current alternatives to nuclear energy (Chap. II); evaluation of realistic expectations for additional future energy supplies from prospective technologies: enhanced recovery from traditional sources and development and use of oil shales and synthetic fuels from coal, fusion and solar energy (Chap. II); an accounting of established nuclear technology in use today, in particular the light water reactor, used for generating electricity (Chap. III); an estimate of future nuclear technology, in particular the prospective fast breeder (Chap. IV); current and projected nuclear fuel demand and supply in the U.S. and abroad (Chaps. V and VI); the constraints encountered today in meeting nuclear fuels demand (Chap. VII); and the major unresolved issues and options in nuclear fuels supply and use (Chap. VIII). The principal conclusions and recommendations (Chap. IX) are that the U.S. and other industrialized countries should strive for increased flexibility of primary energy fuel sources, and that a balanced energy strategy therefore depends on the secure supply of energy resources and the ability to substitute one form of fuel for another

The situation of the nuclear energy in the world; A situacao da energia nucleoeletrica no mundo

Energy Technology Data Exchange (ETDEWEB)

Souza, Jair Albo Marques de [and others

1996-12-01

This work presents an overview of the nuclear energy in the world. It approaches the following main topics: kinds of nuclear power plants; operation experience of the nuclear plants; environmental and social aspects of the nuclear energy; economic aspects of the nuclear energy; development of the reactors technology and supply of the nuclear fuel.

Synergistic production of hydrogen using fossil fuels and nuclear energy application of nuclear-heated membrane reformer

International Nuclear Information System (INIS)

Hori, M.; Matsui, K.; Tashimo, M.; Yasuda, I.

2004-01-01

Processes and technologies to produce hydrogen synergistically by the steam reforming reaction using fossil fuels and nuclear heat are reviewed. Formulas of chemical reactions, required heats for reactions, saving of fuel consumption or reduction of carbon dioxide emission, possible processes and other prospects are examined for such fossil fuels as natural gas, petroleum and coal. The 'membrane reformer' steam reforming with recirculation of reaction products in a closed loop configuration is considered to be the most advantageous among various synergistic hydrogen production methods. Typical merits of this method are: nuclear heat supply at medium temperature below 600 deg. C, compact plant size and membrane area for hydrogen production, efficient conversion of feed fuel, appreciable reduction of carbon dioxide emission, high purity hydrogen without any additional process, and ease of separating carbon dioxide for future sequestration requirements. With all these benefits, the synergistic production of hydrogen by membrane reformer using fossil fuels and nuclear energy can be an effective solution in this century for the world which has to use. fossil fuels any way to some extent while reducing carbon dioxide emission. For both the fossil fuels industry and the nuclear industry, which are under constraint of resource, environment and economy, this production method will be a viable symbiosis strategy for the coming hydrogen economy era. (author)

Overview of Nuclear Fuel-Cycle Policy and the Role of the Nuclear Safety Commission in Japan

International Nuclear Information System (INIS)

Higashi, K.; Nishinosono, S.

2008-01-01

Since the first generation of electricity by the Japan Power Demonstration Reactor in 1963, Japan has been extensively developing nuclear technologies solely for peaceful purposes. The country now operates 55 nuclear power plants consisted of BWRs and PWRs. Although Japan is one of the largest consumers of energy in the world, the country has very limited domestic energy resources. Therefore, Japan considers the nuclear power generation very important as plutonium and uranium recovered from spent fuels can be used in new nuclear fuels as quasi-domestic energy resource. For recycle use of nuclear fuels, the establishment of nuclear fuel recycling technologies including reprocessing technologies is essential. Since 1977, Japan has been recovering plutonium and uranium by a small scale reprocessing plant built by French technology. Recently, 800 ton/year scale commercial reprocessing plant is under construction. After overcoming the current technical problem in the vitrification facility, the commercial plant is expected to be in full operation soon. Concerning the disposal of radioactive wastes, which arises from nuclear utilization, sallow land disposal has already been implemented and medium depth (50 to 100 m) disposal plan is in progress. For high-level waste, possible candidate sites for disposal are being sought. In this paper, the statuses of nuclear power plants and of nuclear fuel cycle facilities in Japan are summarized. As safety is essential for these nuclear installations, safety regulations in Japan are briefly presented from the viewpoint of Nuclear Safety Commission. Furthermore, as the most significant recent safety issue in Japan, the impacts of the large near-site earthquake hit Kashiwazaki-Kariwa NPP last July are reported.(author)

Quality management of nuclear fuel

International Nuclear Information System (INIS)

2006-01-01

The Guide presents the quality management requirements to be complied with in the procurement, design, manufacture, transport, receipt, storage, handling and operation of nuclear fuel. The Guide also applies to control rods and shield elements to be placed in the reactor. The Guide is mainly aimed for the licensee responsible for the procurement and operation of fuel, for the fuel designer and manufacturer and for other organisations, whose activities affect fuel quality and the safety of fuel transport, storage and operation. General requirements for nuclear fuel are presented in Section 114 of the Finnish Nuclear Energy Decree and in Section 15 of the Government Decision (395/1991). Regulatory control of the safety of fuel is described in Guides YVL6.1, YVL6.2 and YVL6.3. An overview of the regulatory control of nuclear power plants carried out by STUK (Radiation and Nuclear Safety Authority, Finland) is clarified in Guide YVL1.1

Spent nuclear fuel storage device and spent nuclear fuel storage method using the device

International Nuclear Information System (INIS)

Tani, Yutaro

1998-01-01

Storage cells attachably/detachably support nuclear fuel containing vessels while keeping the vertical posture of them. A ventilation pipe which forms air channels for ventilating air to the outer circumference of the nuclear fuel containing vessel is disposed at the outer circumference of the nuclear fuel containing vessel contained in the storage cell. A shielding port for keeping the support openings gas tightly is moved, and a communication port thereof can be aligned with the upper portion of the support opening. The lower end of the transporting and containing vessel is placed on the shielding port, and an opening/closing shutter is opened. The gas tightness is kept by the shielding port, the nuclear fuel containing vessel filled with spent nuclear fuels is inserted to the support opening and supported. Then, the support opening is closed by a sealing lid. (I.N.)

Nuclear fuels accounting interface: River Bend experience

International Nuclear Information System (INIS)

Barry, J.E.

1986-01-01

This presentation describes nuclear fuel accounting activities from the perspective of nuclear fuels management and its interfaces. Generally, Nuclear Fuels-River Bend Nuclear Group (RBNG) is involved on a day-by-day basis with nuclear fuel materials accounting in carrying out is procurement, contract administration, processing, and inventory management duties, including those associated with its special nuclear materials (SNM)-isotopics accountability oversight responsibilities as the Central Accountability Office for the River Bend Station. As much as possible, these duties are carried out in an integrated, interdependent manner. From these primary functions devolve Nuclear Fuels interfacing activities with fuel cost and tax accounting. Noting that nuclear fuel tax accounting support is of both an esoteric and intermittent nature, Nuclear Fuels-RBNG support of developments and applications associated with nuclear fuel cost accounting is stressed in this presentation

Advances in nuclear fuel technology. 3. Development of advanced nuclear fuel recycle systems

International Nuclear Information System (INIS)

Arie, Kazuo; Abe, Tomoyuki; Arai, Yasuo

2002-01-01

Fast breeder reactor (FBR) cycle technology has a technical characteristics flexibly easy to apply to diverse fuel compositions such as plutonium, minor actinides, and so on and fuel configurations. By using this characteristics, various feasibilities on effective application of uranium resources based on breeding of uranium of plutonium for original mission of FBR, contribution to radioactive wastes problems based on amounts reduction of transuranium elements (TRU) in high level radioactive wastes, upgrading of nuclear diffusion resistance, extremely upgrading of economical efficiency, and so on. In this paper, were introduced from these viewpoints, on practice strategy survey study on FBR cycle performed by cooperation of the Japan Nuclear Cycle Development Institute (JNC) with electric business companies and so on, and on technical development on advanced nuclear fuel recycle systems carried out at the Central Research Institute of Electric Power Industry, Japan Atomic Energy Research Institute, and so on. Here were explained under a vision on new type of fuels such as nitride fuels, metal fuels, and so on as well as oxide fuels, a new recycle system making possible to use actinides except uranium and plutonium, an 'advanced nuclear fuel cycle technology', containing improvement of conventional wet Purex method reprocessing technology, fuel manufacturing technology, and so on. (G.K.)

Transportation of spent nuclear fuels

International Nuclear Information System (INIS)

Meguro, Toshiichi

1976-01-01

The spent nuclear fuel taken out of reactors is cooled in the cooling pool in each power station for a definite time, then transported to a reprocessing plant. At present, there is no reprocessing plant in Japan, therefore the spent nuclear fuel is shipped abroad. In this paper, the experiences and the present situation in Japan are described on the transport of the spent nuclear fuel from light water reactors, centering around the works in Tsuruga Power Station, Japan Atomic Power Co. The spent nuclear fuel in Tsuruga Power Station was first transported in Apr. 1973, and since then, about 36 tons were shipped to Britain by 5 times of transport. The reprocessing plant in Japan is expected to start operation in Apr. 1977, accordingly the spent nuclear fuel used for the trial will be transported in Japan in the latter half of this year. Among the permission and approval required for the transport of spent nuclear fuel, the acquisition of the certificate for transport casks and the approval of land and sea transports are main tasks. The relevant laws are the law concerning the regulations of nuclear raw material, nuclear fuel and reactors and the law concerning the safety of ships. The casks used in Tsuruga Power Station and EXL III type, and the charging of spent nuclear fuel, the decontamination of the casks, the leak test, land transport with a self-running vehicle, loading on board an exclusive carrier and sea transport are briefly explained. The casks and the ship for domestic transport are being prepared. (Kato, I.)

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)

Romanian nuclear fuel fabrication and in-reactor fuel operational experience

International Nuclear Information System (INIS)

Budan, O.

2003-01-01

A review of the Romanian nuclear program since mid 60's is made. After 1990, the new Romanian nuclear power authority, RENEL-GEN, elaborated a realistic Nuclear Fuel Program. This program went through the Romanian nuclear fuel plant qualification with the Canadian (AECL and ZPI) support, restarting in January 1995 of the industrial nuclear fuel production, quality evaluation of the fuel produced before 1990 and the recovery of this fuel. This new policy produced good results. FCN is since 1995 the only CANDU fuel supplier from outside Canada recognised by AECL as an authorised CANDU fuel manufacturer. The in-reactor performances and behaviour of the fuel manufactured by FCN after its qualification have been excellent. Very low - more then five times lesser than the design value - fuel defect rate has been recorded up to now and the average discharge of this fuel was with about 9% greater than the design value. Since mid 1998 when SNN took charge of the production of nuclear generated electricity, FCN made significant progresses in development and procurement of new and more efficient equipment and is now very close to double its fuel production capacity. After the completion of the recovery of the fuel produced before June 1990, FCN is already prepared to shift its fuel production to the so-called 'heavy' bundle containing about 19.3 kg of Uranium per bundle

Feasibility of Electromagnetic Acoustic Evaluation for Quality Test of a Plate-type Nuclear Fuel

International Nuclear Information System (INIS)

Jung, Hyun Kyu; Lee, Yoon Sang; Cheong, Yong Moo

2010-01-01

Most research and test reactors use the nuclear fuel plates which are consisted of a fuel core in aluminum alloy. Recently KAERI signed a deal with the Jordan Atomic Energy Commission to build the research reactor and have to supply the plate-type nuclear fuels. For the demands of world market, KAERI started the research and development of the plate-type fuel elements and endeavored to achieve a localization of fuel fabrication. For the inspection of plate-type fuel elements to be used in Research Reactors, an immersion pulse-echo ultrasonic technique was applied. This inspection was done with water, so a nuclear fuel was immersed to be prone to corrosion and needed to have time and cost due to an additional process. The sample that will be examined within this paper is a non-ferromagnetic material such as aluminum which has a good acousto-elastic property, for an effective inspection of a bond quality for a nuclear fuel under a manufacturing environment. The purpose of this study is to investigate the feasibility of an EMAT technology for an automated inspection of a nuclear fuel without water

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)

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2003-01-01

This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

World electricity generation, nuclear power, and oil markets

International Nuclear Information System (INIS)

1990-01-01

Striking changes have characterized the world's production and use of energy over the past 15 years. Most prominent have been the wide price fluctuations, politicization of world oil prices and supply, along with profound changes in patterns of production and consumption. This report, based on a study by energy analysts at Science Concepts, Inc., in the United States, traces changes in world energy supply since 1973-74 - the time of the first oil ''price shocks''. In so doing, it identifies important lessons for the future. The study focused in particular on the role of the electric power sector because the growth in fuel use in it has been accomplished without oil. Instead, the growth has directly displaced oil. In the pre-1973 era, the world relied increasingly on oil for many energy applications, including the production of electricity. By 1973, more than on-fourth of the world's electricity was produced by burning oil. By 1987, however, despite a large increase in electric demand, the use of oil was reigned back to generating less than 10% of the world's electricity. Nuclear power played a major role in this turnaround. From 1973-87, analysts at Science Concepts found, nuclear power displaced the burning of 11.7 billion barrels of oil world-wide and avoided US $323 billion in oil purchases

Nuclear reactors and fuel cycle

International Nuclear Information System (INIS)

2014-01-01

The Nuclear Fuel Center (CCN) of IPEN produces nuclear fuel for the continuous operation of the IEA-R1 research reactor of IPEN. The serial production started in 1988, when the first nuclear fuel element was delivered for IEA-R1. In 2011, CCN proudly presents the 100 th nuclear fuel element produced. Besides routine production, development of new technologies is also a permanent concern at CCN. In 2005, U 3 O 8 were replaced by U 3 Si 2 -based fuels, and the research of U Mo is currently under investigation. Additionally, the Brazilian Multipurpose Research Reactor (RMB), whose project will rely on the CCN for supplying fuel and uranium targets. Evolving from an annual production from 10 to 70 nuclear fuel elements, plus a thousand uranium targets, is a huge and challenging task. To accomplish it, a new and modern Nuclear Fuel Factory is being concluded, and it will provide not only structure for scaling up, but also a safer and greener production. The Nuclear Engineering Center has shown, along several years, expertise in the field of nuclear, energy systems and correlated areas. Due to the experience obtained during decades in research and technological development at Brazilian Nuclear Program, personnel has been trained and started to actively participate in design of the main system that will compose the Brazilian Multipurpose Reactor (RMB) which will make Brazil self-sufficient in production of radiopharmaceuticals. The institution has participated in the monitoring and technical support concerning the safety, licensing and modernization of the research reactors IPEN/MB-01 and IEA-R1. Along the last two decades, numerous specialized services of engineering for the Brazilian nuclear power plants Angra 1 and Angra 2 have been carried out. The contribution in service, research, training, and teaching in addition to the development of many related technologies applied to nuclear engineering and correlated areas enable the institution to fulfill its mission that is

Nuclear reactors and fuel cycle

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-01

The Nuclear Fuel Center (CCN) of IPEN produces nuclear fuel for the continuous operation of the IEA-R1 research reactor of IPEN. The serial production started in 1988, when the first nuclear fuel element was delivered for IEA-R1. In 2011, CCN proudly presents the 100{sup th} nuclear fuel element produced. Besides routine production, development of new technologies is also a permanent concern at CCN. In 2005, U{sub 3}O{sub 8} were replaced by U{sub 3}Si{sub 2}-based fuels, and the research of U Mo is currently under investigation. Additionally, the Brazilian Multipurpose Research Reactor (RMB), whose project will rely on the CCN for supplying fuel and uranium targets. Evolving from an annual production from 10 to 70 nuclear fuel elements, plus a thousand uranium targets, is a huge and challenging task. To accomplish it, a new and modern Nuclear Fuel Factory is being concluded, and it will provide not only structure for scaling up, but also a safer and greener production. The Nuclear Engineering Center has shown, along several years, expertise in the field of nuclear, energy systems and correlated areas. Due to the experience obtained during decades in research and technological development at Brazilian Nuclear Program, personnel has been trained and started to actively participate in design of the main system that will compose the Brazilian Multipurpose Reactor (RMB) which will make Brazil self-sufficient in production of radiopharmaceuticals. The institution has participated in the monitoring and technical support concerning the safety, licensing and modernization of the research reactors IPEN/MB-01 and IEA-R1. Along the last two decades, numerous specialized services of engineering for the Brazilian nuclear power plants Angra 1 and Angra 2 have been carried out. The contribution in service, research, training, and teaching in addition to the development of many related technologies applied to nuclear engineering and correlated areas enable the institution to

Activities of the IAEA Nuclear Energy Department in the area of fuel engineering

International Nuclear Information System (INIS)

Bychkov, A.; ); Inozemtsev, V.; )

2012-01-01

The IAEA presentation provides an outlook on the current status and projections of nuclear power development in the world taking into account the affect of the Fukushima accident, as well as information about the IAEA Action Plan on Nuclear Safety that was unanimously enforced by 151 Member States at the IAEA General Conference in September 2011. Details are given about the implementation tools of the sub-programme 'Nuclear Power Reactor Fuel Engineering': Technical Meetings, Coordinated Research Projects, and Expert Reviews. This information about recent, on-going and planned IAEA activities related to fuel R and D, design, manufacturing, in-reactor behaviour and operational experience will be useful for specialists interested in corresponding publications or for those planning participation in the IAEA projects. Particular emphasis is made on CQCNF priority subjects, including preparation of the IAEA Nuclear Energy Series Guide on Quality and Reliability of Fuel for Water-Cooled Power Reactors, where the expert group from the Nuclear Fuel Complex in Hyderabad was among the key contributors. (author)

Nuclear fuel element

International Nuclear Information System (INIS)

Mogard, J.H.

1977-01-01

A nuclear fuel element is disclosed for use in power producing nuclear reactors, comprising a plurality of axially aligned ceramic cylindrical fuel bodies of the sintered type, and a cladding tube of metal or metal alloys, wherein said cladding tube on its cylindrical inner surface is provided with a plurality of slightly protruding spacing elements distributed over said inner surface

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

Improved moulding material for addition to nuclear fuel particles to produce nuclear fuel elements

International Nuclear Information System (INIS)

Miertschin, G.N.; Leary, D.F.

1976-01-01

A suggestion is made to improve the moulding materials used to produce carbon-contained nuclear fuel particles by a coke-reducing added substance. The nuclear fuel particles are meant for the formation of fuel elements for gas-cooled high-temperature nuclear reactors. The moulding materials are above all for the formation of coated particles which are burnt in situ in nuclear fuel element chambers out of 'green' nuclear fuel bodies. The added substance improves the shape stability of the particles forming and prevents a stiding or bridge formation between the particles or with the surrounding walls. The following are named as added substances: 1) Polystyrene and styrene-butadiene-Co polymers (mol. wt. between 5oo and 1,000,000), 2) aromatic compounds (mol. wt. 75 to 300), 3) saturated hydrocarbon polymers (mol. wt. 5,000 to 1,000,000). Additional release agents further improve the properties in the same direction (e.g. alcohols, fatty acids, amines). (orig.) [de

Nuclear fuel reprocessing: A time for decision

International Nuclear Information System (INIS)

O'Donnell, A.J.; Sandbery, R.O.

1983-01-01

Availability of adequate supplies of energy at an affordable cost is essential to continued growth of the world's economics. The tie between economic growth and electricity usage is particularly strong and the pervasive wordwide trend toward increasing electrification shows no signs of abating. Very few viable alternatives are available for supplying the projected increase in baseload electric generating capacity in the next several decades, and most industrialized nations have chosen nuclear power to play a major role. Sustained growth of nuclear power can only be achieved, however, by reprocessing spent fuel to recover and utilize the residual uranium and plutonium energy values

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER

Energy Technology Data Exchange (ETDEWEB)

BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-06-01

OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from

Nuclear fuel cycle in Japan : status and perspective

International Nuclear Information System (INIS)

Suzuki, Atsuyuki

1996-01-01

Nearly one third of electricity in Japan is being generated by nuclear fission primarily by light-water reactors. The industries to supply uranium fuel for these reactors have been well established including the capability for uranium enrichment. From the onset of nuclear program in Japan, a country with thin energy resources, the emphasis has been placed on maximizing the efficiency of uranium utilization. Thus the national nuclear program set forth by the Japan Atomic Energy Commission has consistently called for the establishment of closed fuel cycle, or for recycling of nuclear fuel. As part of such efforts in private sectors, the first commercial reprocessing plant is now under construction at Rokkasho-mura. The program to develop technologies for recycling nuclear fuel in a fast reactor system is also in progress steadily under the governmental support, while the Monju accident casts a long shadow on the future of fast reactor development in Japan. Even though the price of uranium has been stable at relatively low level in recent years, the uranium market in the longer time range is somewhat unpredictable. In Asian countries, a rapid growth of nuclear power production is foreseen in the 21st century. Under such circumstances, the effort to pursue the recycling option in Japan is important not only for its own energy security but also for stabilization of future uranium market in the world. The recycling option can also offer more flexible, easier and safer ways of radioactive waste management. Since the recycling option means utilization of plutonium in an industrial scale, special attention is inevitably required from the viewpoint of nuclear non-proliferation. It is the Japan's national policy to develop recycling technologies in compliance with the NPT and IAEA safeguard system as well as to maintain the transparency of its developmental program. (author)

Nuclear energy, insignificant use in comparison with mineral fuels

International Nuclear Information System (INIS)

Mostafa, Md.G.

1999-01-01

Human civilization based on energy. From the primitive stage human needs a power or energy source to exist in the world. Energy is the basis of Industrial civilization, without it modern life would cease to exist. Most of the growth of the world energy consumption grew from 20% in 1970 to 31% in 1990. There is general approbation that in the next decades this trend will continue. But we have seen that during the 1970s the world began a painful adjustment to the vulnerability of energy supplies. Last three decades world had fallen into energy crisis three times. So the world has to face a great challenge to (1) Ensure the availability of energy, (2) Reduce the cost of energy, (3) Reduce the impact on environment caused by using fossil fuels. The increase in global demand for energy is expected to be met from several energy sources. And which sources of energy would take part to alleviate the energy need in the world. There are several factors to choose the energy sources. Many European countries now thinking that the future demand of energy would be mitigated by sustainable energy. In this connection many countries have initiated to develop renewable energy technologies that would make possible them to diminish fossil fuel consumption and its attendant problems. Now-a-days the nuclear Engineer and Scientist claimed that there is no danger to be associated with atomic power stations. But still now about the safety and economy of nuclear power have a number of unanswered questions: What are the effects of low-level radiation over long period? How can nuclear power's waste products, which will be dangerous for centuries, be permanently isolated from the environment? Etc. Because of atomic power is till associated in the public mind with the destructive force of atomic bombs, how could the Nuclear power keep an important role in future energy demand in the world? If it is possible to over come the danger of atomic power by ensuring the modern technology and highest

Nuclear energy, insignificant use in comparison with mineral fuels

Energy Technology Data Exchange (ETDEWEB)

Mostafa, Md.G. [DDC Ltd., Dhaka (Bangladesh). Computer Center

1999-07-01

Human civilization based on energy. From the primitive stage human needs a power or energy source to exist in the world. Energy is the basis of Industrial civilization, without it modern life would cease to exist. Most of the growth of the world energy consumption grew from 20% in 1970 to 31% in 1990. There is general approbation that in the next decades this trend will continue. But we have seen that during the 1970s the world began a painful adjustment to the vulnerability of energy supplies. Last three decades world had fallen into energy crisis three times. So the world has to face a great challenge to (1) Ensure the availability of energy, (2) Reduce the cost of energy, (3) Reduce the impact on environment caused by using fossil fuels. The increase in global demand for energy is expected to be met from several energy sources. And which sources of energy would take part to alleviate the energy need in the world. There are several factors to choose the energy sources. Many European countries now thinking that the future demand of energy would be mitigated by sustainable energy. In this connection many countries have initiated to develop renewable energy technologies that would make possible them to diminish fossil fuel consumption and its attendant problems. Now-a-days the nuclear Engineer and Scientist claimed that there is no danger to be associated with atomic power stations. But still now about the safety and economy of nuclear power have a number of unanswered questions: What are the effects of low-level radiation over long period? How can nuclear power's waste products, which will be dangerous for centuries, be permanently isolated from the environment? Etc. Because of atomic power is till associated in the public mind with the destructive force of atomic bombs, how could the Nuclear power keep an important role in future energy demand in the world? If it is possible to over come the danger of atomic power by ensuring the modern technology and highest

Nuclear fuel assembly

International Nuclear Information System (INIS)

Wakamatsu, Mitsuo.

1974-01-01

Object: To improve a circulating flow passage of coolant so as to be able to accurately detect the temperature of coolant, rare gases contained, and the like. Structure: A fuel assembly comprising a flow regulating lattice provided with a plurality of communication holes in an axial direction, said lattice being positioned at the upper end of an outer tube in which nuclear fuel elements are received, and a neutron shielding body having a plurality of spiral coolant flow passages disposed between the lattice and the nuclear fuel elements, whereby a coolant comprised of liquid sodium or the like, which moves up passing through the coolant flow passages and the flow regulating passage, is regulated and passed through a detector mounted at the upper part of the flow regulating lattice to detect coolant temperature, flow rate, and rare gases or the like as the origin of nuclear fission contained in the coolant due to breakage of fuel elements. (Kamimura, M.)

Operation of Nuclear Fuel Based on Reprocessed Uranium for VVER-type Reactors in Competitive Nuclear Fuel Cycles

Energy Technology Data Exchange (ETDEWEB)

Troyanov, V.; Molchanov, V.; Tuzov, A. [TVEL Corporation, 49 Kashirskoe shosse, Moscow 115409 (Russian Federation); Semchenkov, Yu.; Lizorkin, M. [RRC ' Kurchatov Institute' (Russian Federation); Vasilchenko, I.; Lushin, V. [OKB ' Gidropress' (Russian Federation)

2009-06-15

Current nuclear fuel cycle of Russian nuclear power involves reprocessed low-enriched uranium in nuclear fuel production for some NPP units with VVER-type LWR. This paper discusses design and performance characteristics of commercial nuclear fuel based on natural and reprocessed uranium. It presents the review of results of commercial operation of nuclear fuel based on reprocessed uranium on Russian NPPs-unit No.2 of Kola NPP and unit No.2 of Kalinin NPP. The results of calculation and experimental validation of safe fuel operation including necessary isotope composition conformed to regulation requirements and results of pilot fuel operation are also considered. Meeting the customer requirements the possibility of high burn-up achieving was demonstrated. In addition the paper compares the characteristics of nuclear fuel cycles with maximum length based on reprocessed and natural uranium considering relevant 5% enrichment limitation and necessity of {sup 236}U compensation. The expedience of uranium-235 enrichment increasing over 5% is discussed with the aim to implement longer fuel cycles. (authors)

Nuclear fuel pellet charging device

International Nuclear Information System (INIS)

Komuro, Kojiro.

1990-01-01

The present invention concerns a nuclear fuel pellet loading device, in which nuclear fuel pellets are successively charged from an open end of a fuel can while rotating the can. That is, a fuel can sealed at one end with an end plug and opened at the other end is rotated around its pipe axis as the center on a rotationally diriving table. During rotation of the fuel can, nuclear fuel pellets are successively charged by means of a feed rod of a feeding device to the inside of the fuel can. The fuel can is rotated while being supported horizontally and the fuel pellets are charged from the open end thereof. Alternatively, the fuel can is rotated while being supported obliquely and the fuel pellets are charged gravitationally into the fuel can. In this way, the damages to the barrier of the fuel can can be reduce. Further, since the fuel pellets can be charged gravitationally by rotating the fuel can while being supported obliquely, the damages to the barrier can be reduced remarkably. (I.S.)

The status of nuclear fuel cycle system analysis for the development of advanced nuclear fuel cycles

Energy Technology Data Exchange (ETDEWEB)

Ko, Won Il; Kim, Seong Ki; Lee, Hyo Jik; Chang, Hong Rae; Kwon, Eun Ha; Lee, Yoon Hee; Gao, Fanxing [KAERI, Daejeon (Korea, Republic of)

2011-11-15

The system analysis has been used with different system and objectives in various fields. In the nuclear field, the system can be applied from uranium mining to spent fuel reprocessing or disposal which is called the nuclear fuel cycle. The analysis of nuclear fuel cycle can be guideline for development of advanced fuel cycle through integrating and evaluating the technologies. For this purpose, objective approach is essential and modeling and simulation can be useful. In this report, several methods which can be applicable for development of advanced nuclear fuel cycle, such as TRL, simulation and trade analysis were explained with case study

Nuclear reactor fuel element splitter

International Nuclear Information System (INIS)

Yeo, D.

1976-01-01

A method and apparatus are disclosed for removing nuclear fuel from a clad fuel element. The fuel element is power driven past laser beams which simultaneously cut the cladding lengthwise into at least two longitudinal pieces. The axially cut lengths of cladding are then separated, causing the nuclear fuel contained therein to drop into a receptacle for later disposition. The cut lengths of cladding comprise nuclear waste which is disposed of in a suitable manner. 6 claims, 10 drawing figures

Nuclear fuel elements

International Nuclear Information System (INIS)

Ainsworth, K.F.

1979-01-01

A nuclear fuel element is described having a cluster of nuclear fuel pins supported in parallel, spaced apart relationship by transverse cellular braces within coaxial, inner and outer sleeves, the inner sleeve being in at least two separate axial lengths, each of the transverse braces having a peripheral portion which is clamped peripherally between the ends of the axial lengths of the inner sleeve. (author)

A Path Forward to Advanced Nuclear Fuels: Spectroscopic Calorimetry of Nuclear Fuel Materials

International Nuclear Information System (INIS)

Tobin, J.G.

2009-01-01

The goal is to relieve the shortage of thermodynamic and kinetic information concerning the stability of nuclear fuel alloys. Past studies of the ternary nuclear fuel UPuZr have demonstrated constituent redistribution when irradiated or with thermal treatment. Thermodynamic data is key to predicting the possibilities of effects such as constituent redistribution within the fuel rods and interaction with cladding materials

Cost and availability of nuclear fuel in the 1980's

International Nuclear Information System (INIS)

Kelly, M.J.; Baldwin, J.S.; Martin, S.C.

1980-01-01

Due to the decrease in expected nuclear reactor capacity growth, all portions of the fuel cycle can fulfill reactor needs throughout the 1980's with no expansion required except for fuel fabrication, where such expansion is already in the permit and regulatory system. As a result, fuel cycle costs should not increase faster than the rate of inflation with the possible exception of enrichment costs. It is likely that uranium will remain very competitive with coal as a fuel on a dollars per million Btu basis. However, increasing capital costs for reactors may change this scenario. It is unlikely that any new reactor orders will be placed before the mid 1980's as forecast by Electrical World owing to a directive by Congress to the Nuclear Regulatory Commission to rewrite the Code of Federal Regulations, Parts 50, 51 and 100 to better define siting regulations

Spent nuclear fuel disposal liability insurance

International Nuclear Information System (INIS)

Martin, D.W.

1984-01-01

This thesis examines the social efficiency of nuclear power when the risks of accidental releases of spent fuel radionuclides from a spent fuel disposal facility are considered. The analysis consists of two major parts. First, a theoretical economic model of the use of nuclear power including the risks associated with releases of radionuclides from a disposal facility is developed. Second, the costs of nuclear power, including the risks associated with a radionuclide release, are empirically compared to the costs of fossil fuel-fired generation of electricity. Under the provisions of the Nuclear Waste Policy Act of 1982, the federally owned and operated spent nuclear fuel disposal facility is not required to maintain a reserve fund to cover damages from an accidental radionuclide release. Thus, the risks of a harmful radionuclide release are not included in the spent nuclear fuel disposal fee charged to the electric utilities. Since the electric utilities do not pay the full, social costs of spent fuel disposal, they use nuclear fuel in excess of the social optimum. An insurance mechanism is proposed to internalize the risks associated with spent fueled disposal. Under this proposal, the Federal government is required to insure the disposal facility against any liabilities arising from accidental releases of spent fuel radionuclides

Nuclear fuel deformation phenomena

International Nuclear Information System (INIS)

Van Brutzel, L.; Dingreville, R.; Bartel, T.J.

2015-01-01

Nuclear fuel encounters severe thermomechanical environments. Its mechanical response is profoundly influenced by an underlying heterogeneous microstructure but also inherently dependent on the temperature and stress level histories. The ability to adequately simulate the response of such microstructures, to elucidate the associated macroscopic response in such extreme environments is crucial for predicting both performance and transient fuel mechanical responses. This chapter discusses key physical phenomena and the status of current modelling techniques to evaluate and predict fuel deformations: creep, swelling, cracking and pellet-clad interaction. This chapter only deals with nuclear fuel; deformations of cladding materials are discussed elsewhere. An obvious need for a multi-physics and multi-scale approach to develop a fundamental understanding of properties of complex nuclear fuel materials is presented. The development of such advanced multi-scale mechanistic frameworks should include either an explicit (domain decomposition, homogenisation, etc.) or implicit (scaling laws, hand-shaking,...) linkage between the different time and length scales involved, in order to accurately predict the fuel thermomechanical response for a wide range of operating conditions and fuel types (including Gen-IV and TRU). (authors)

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

Nuclear fuel rod loading apparatus

International Nuclear Information System (INIS)

King, H.B.

1981-01-01

A nuclear fuel loading apparatus, incorporating a microprocessor control unit, is described which automatically loads nuclear fuel pellets into dual fuel rods with a minimum of manual involvement and in a manner and sequence to ensure quality control and accuracy. (U.K.)

Experience with nuclear fuel utilization in Bulgaria

Energy Technology Data Exchange (ETDEWEB)

Harizanov, Y [Committee on the Use of Atomic Energy for Peaceful Purposes, Sofia (Bulgaria)

1997-12-01

The presentation on experience with nuclear fuel utilization in Bulgaria briefly reviews the situation with nuclear energy in Bulgaria and then discusses nuclear fuel performance (amount of fuel loaded, type of fuel, burnup, fuel failures, assemblies deformation). 2 tabs.

Improved nuclear fuel element

International Nuclear Information System (INIS)

Klepfer, H.H.

1974-01-01

A nuclear fuel element is described which comprises: 1) an elongated clad container, 2) a layer of high lubricity material being disposed in and adjacent to the clad container, 3) a low neutron capture cross section metal liner being disposed in the clad container and adjacent to the layer, 4) a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, 5) an enclosure integrally secured and sealed at each end of the container, and a nuclear fuel material retaining means positioned in the cavity. (author)

IAEA activities on nuclear fuel

International Nuclear Information System (INIS)

Basak, U.

2011-01-01

In this paper a brief description and the main objectives of IAEA Programme B on Nuclear fuel cycle are given. The following Coordinated Research Projects: 1) FUel performance at high burn-up and in ageing plant by management and optimisation of WAter Chemistry Technologies (FUWAC ); 2) Near Term and Promising Long Term Options for Deployment of Thorium Based Nuclear Energy; 3) Fuel Modelling (FUMEX-III) are shortly described. The data collected by the IAEA Expert Group of Fuel Failures in Water Cooled Reactors including information about fuel failure cause for PWR (1994-2006) and failure mechanisms for BWR fuel (1994-2006) are shown. The just published Fuel Failure Handbook as well as preparation of a Monograph on Zirconium including an overview of Zirconium for nuclear applications are presented. The current projects in Sub-programme B2 - Power Reactor Fuel Engineering are also listed

The fuel of nuclear reactors

International Nuclear Information System (INIS)

1995-03-01

This booklet is a presentation of the different steps of the preparation of nuclear fuels performed by Cogema. The documents starts with a presentation of the different French reactor types: graphite moderated reactors, PWRs using MOX fuel, fast breeder reactors and research reactors. The second part describes the fuel manufacturing process: conditioning of nuclear materials and fabrication of fuel assemblies. The third part lists the different companies involved in the French nuclear fuel industry while part 4 gives a short presentation of the two Cogema's fuel fabrication plants at Cadarache and Marcoule. Part 5 and 6 concern the quality assurance, the safety and reliability aspects of fuel elements and the R and D programs. The last part presents some aspects of the environmental and personnel protection performed by Cogema. (J.S.)

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)

Reprocessing of spent nuclear fuel

International Nuclear Information System (INIS)

Kidd, S.

2008-01-01

The closed fuel cycle is the most sustainable approach for nuclear energy, as it reduces recourse to natural uranium resources and optimises waste management. The advantages and disadvantages of used nuclear fuel reprocessing have been debated since the dawn of the nuclear era. There is a range of issues involved, notably the sound management of wastes, the conservation of resources, economics, hazards of radioactive materials and potential proliferation of nuclear weapons. In recent years, the reprocessing advocates win, demonstrated by the apparent change in position of the USA under the Global Nuclear Energy Partnership (GNEP) program. A great deal of reprocessing has been going on since the fourties, originally for military purposes, to recover plutonium for weapons. So far, some 80000 tonnes of used fuel from commercial power reactors has been reprocessed. The article indicates the reprocessing activities and plants in the United Kigdom, France, India, Russia and USA. The aspect of plutonium that raises the ire of nuclear opponents is its alleged proliferation risk. Opponents of the use of MOX fuels state that such fuels represent a proliferation risk because the plutonium in the fuel is said to be 'weapon-use-able'. The reprocessing of used fuel should not give rise to any particular public concern and offers a number of potential benefits in terms of optimising both the use of natural resources and waste management.

Review of oxidation rates of DOE spent nuclear fuel : Part 1 : nuclear fuel

International Nuclear Information System (INIS)

Hilton, B.A.

2000-01-01

The long-term performance of Department of Energy (DOE) spent nuclear fuel (SNF) in a mined geologic disposal system depends highly on fuel oxidation and subsequent radionuclide release. The oxidation rates of nuclear fuels are reviewed in this two-volume report to provide a baseline for comparison with release rate data and technical rationale for predicting general corrosion behavior of DOE SNF. The oxidation rates of nuclear fuels in the DOE SNF inventory were organized according to metallic, Part 1, and non-metallic, Part 2, spent nuclear fuels. This Part 1 of the report reviews the oxidation behavior of three fuel types prototypic of metallic fuel in the DOE SNF inventory: uranium metal, uranium alloys and aluminum-based dispersion fuels. The oxidation rates of these fuels were evaluated in oxygen, water vapor, and water. The water data were limited to pure water corrosion as this represents baseline corrosion kinetics. Since the oxidation processes and kinetics discussed in this report are limited to pure water, they are not directly applicable to corrosion rates of SNF in water chemistry that is significantly different (such as may occur in the repository). Linear kinetics adequately described the oxidation rates of metallic fuels in long-term corrosion. Temperature dependent oxidation rates were determined by linear regression analysis of the literature data. As expected the reaction rates of metallic fuels dramatically increase with temperature. The uranium metal and metal alloys have stronger temperature dependence than the aluminum dispersion fuels. The uranium metal/water reaction exhibited the highest oxidation rate of the metallic fuel types and environments that were reviewed. Consequently, the corrosion properties of all DOE SNF may be conservatively modeled as uranium metal, which is representative of spent N-Reactor fuel. The reaction rate in anoxic, saturated water vapor was essentially the same as the water reaction rate. The long-term intrinsic

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.)

Current Status of World Nuclear Fuel Cycle Technology (I): Canada and Latin America

International Nuclear Information System (INIS)

Choi, Hang Bok; Ko, Won Il

2007-05-01

Canada produces about one third of the world's uranium mine output, most of it from two new mines. After 2007 Canadian production is expected to increase further as more new mines come into production. About 15% of Canada's electricity comes from nuclear power, using indigenous technology, and 18 reactors provide over 12,500 MWe of power. Mexico has two nuclear reactors generating almost 5% of its electricity. Its first commercial nuclear power reactor began operating in 1989. There is some government support for expanding nuclear energy to reduce reliance on natural gas. Argentina has two nuclear reactors generating nearly one tenth of its electricity. Its first commercial nuclear power reactor began operating in 1974. Brazil has two nuclear reactors generating 4% of its electricity. Its first commercial nuclear power reactor began operating in 1982

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)

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

Prospects of nuclear power in fossil fuel saving

International Nuclear Information System (INIS)

Chernavskij, S.Ya.

1984-01-01

Economic aspects of the World energy situation are considered. The growth in the world prices for energy and energy resources has demanded to reconstruct the structure of both consumers and primary energy resources. The nuclear power development is one of the most important aspects of this reconstruction. In connection with its development the acceptability of nuclear power technology and possible spheres of its application in different fields of power engineering are considered. When discussing these problems one pays the main attention to the psychological effect and potential measures for its compensation. A forecast estimate is given of specific capital investments in and expenditures on electric energy production for NPPs and conventional power stations for the considered period of 30 years. The estimates are differentiated for the European and Asian parts of the country. The problems of developing nuclear central heating-and-power plants and nuclear thermal stations are discussed. It is pointed out that presently no sufficient experience has been gained in their commerical operation to discuss for sure the prospects of their wide-scale utilization. Results of calculations are presented showing that in the range of high-temperature processes the use of electric energy based on the nuclear power development is more efficient than direct combustion of fossil fuel as estimated with respect to its export at the world market prices

International nuclear fuel cycle evaluation

International Nuclear Information System (INIS)

Witt, P.

1980-01-01

In the end of February 1980, the two-years work on the International Nuclear Fuel Cycle Evaluation (INFCE) was finished in Vienna with a plenary meeting. INFCE is likely to have been a unique event in the history of international meetings: It was ni diplomatic negotiation meeting, but a techno-analytical investigation in which the participants tenaciously shuggled for many of the formulations. Starting point had been a meeting initiated by President Carter in Washington in Oct. 1979 after the World Economy Summit Meeting in London. The results of the investigation are presented here in a brief and popular form. (orig./UA) [de

Nuclear fuel cycle

International Nuclear Information System (INIS)

1993-01-01

Status of different nuclear fuel cycle phases in 1992 is discussed including the following issues: uranium exploration, resources, supply and demand, production, market prices, conversion, enrichment; reactor fuel technology; spent fuel management, as well as trends of these phases development up to the year 2010. 10 refs, 11 figs, 15 tabs

Air Shipment of Highly Enriched Uranium Spent Nuclear Fuel from Romania

International Nuclear Information System (INIS)

Allen, K.J.; Bolshinsky, I.; Biro, L.L.; Budu, M.E.; Zamfir, N.V.; Dragusin, M.

2010-01-01

Romania safely air shipped 23.7 kilograms of Russian-origin highly enriched uranium (HEU) spent nuclear fuel from the VVR-S research reactor at Magurele, Romania, to the Russian Federation in June 2009. This was the world's first air shipment of spent nuclear fuel transported in a Type B(U) cask under existing international laws without special exceptions for the air transport licenses. This shipment was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in cooperation with the Romania National Commission for Nuclear Activities Control (CNCAN), the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH), and the Russian Federation State Corporation Rosatom. The shipment was transported by truck to and from the respective commercial airports in Romania and the Russian Federation and stored at a secure nuclear facility in Russia where it will be converted into low enriched uranium. With this shipment, Romania became the 3. country under the RRRFR program and the 14. country under the GTRI program to remove all HEU. This paper describes the work, equipment, and approvals that were required to complete this spent fuel air shipment. (authors)

Performance of candu-6 fuel bundles manufactured in romania nuclear fuel plant

International Nuclear Information System (INIS)

Bailescu, A.; Barbu, A.; Din, F.; Dinuta, G.; Dumitru, I.; Musetoiu, A.; Serban, G.; Tomescu, A.

2013-01-01

The purpose of this article is to present the performance of nuclear fuel produced by Nuclear Fuel Plant (N.F.P.) - Pitesti during 1995 - 2012 and irradiated in units U1 and U2 from Nuclear Power Plant (N.P.P.) Cernavoda and also present the Nuclear Fuel Plant (N.F.P.) - Pitesti concern for providing technology to prevent the failure causes of fuel bundles in the reactor. This article presents Nuclear Fuel Plant (N.F.P.) - Pitesti experience on tracking performance of nuclear fuel in reactor and strategy investigation of fuel bundles notified as suspicious and / or defectives both as fuel element and fuel bundle, it analyzes the possible defects that can occur at fuel bundle or fuel element and can lead to their failure in the reactor. Implementation of modern technologies has enabled optimization of manufacturing processes and hence better quality stability of achieving components (end caps, chamfered sheath), better verification of end cap - sheath welding. These technologies were qualified by Nuclear Fuel Plant (N.F.P.) - Pitesti on automatic and Computer Numerical Control (C.N.C.) programming machines. A post-irradiation conclusive analysis which will take place later this year (2013) in Institute for Nuclear Research Pitesti (the action was initiated earlier this year by bringing a fuel bundle which has been reported defective by pool visual inspection) will provide additional information concerning potential damage causes of fuel bundles due to manufacturing processes. (authors)

Development of high burnup nuclear fuel technology

International Nuclear Information System (INIS)

Suk, Ho Chun; Kang, Young Hwan; Jung, Jin Gone; Hwang, Won; Park, Zoo Hwan; Ryu, Woo Seog; Kim, Bong Goo; Kim, Il Gone

1987-04-01

The objectives of the project are mainly to develope both design and manufacturing technologies for 600 MWe-CANDU-PHWR-type high burnup nuclear fuel, and secondly to build up the foundation of PWR high burnup nuclear fuel technology on the basis of KAERI technology localized upon the standard 600 MWe-CANDU- PHWR nuclear fuel. So, as in the first stage, the goal of the program in the last one year was set up mainly to establish the concept of the nuclear fuel pellet design and manufacturing. The economic incentives for high burnup nuclear fuel technology development are improvement of fuel utilization, backend costs plant operation, etc. Forming the most important incentives of fuel cycle costs reduction and improvement of power operation, etc., the development of high burnup nuclear fuel technology and also the research on the incore fuel management and safety and technologies are necessary in this country

International project on innovative nuclear reactors and fuel cycles

International Nuclear Information System (INIS)

Cherepnin, Yu.S.; Bezzubtsev, V.S.; Gabaraev, B.A.

2002-01-01

Positive changes are currently taking place in nuclear power in the world. Power generation at Nuclear Power Plants (NPPs) is increasing and new units construction and completion rates are growing in some of leading countries. Considerable efforts are made for improving the safety of operating NPPs, effective use of nuclear fuel and solving the spent nuclear fuel and radioactive waste problems. Simultaneously, work are undertaken to develop new reactor technologies to reduce the fundamental drawbacks of conventional nuclear power, namely: insufficient safety, spent fuel and waste handling problems, nuclear material proliferation risk and poor economic competitiveness as compared to fossil-fuel energy sources. One the most important events in this field is an international project implemented by three agencies (OECD-IEA, OECD-NEA, IAEA) for comparative evaluation of new projects, development of Generation IV reactors underway in the US in cooperation with a number of Western countries and, finally, the initiative by Russian President V.V. Putin for consolidation the efforts of interested countries under auspices of IAEA to solve the problem of energy support for sustainable development of humankind, radical solution of non-proliferation problems and environmental sanitation of the Planet of Earth. The 44-th General Conference of IAEA in September 2000 supported the Initiative of Russian President and called all interested countries to unite efforts under the Agency's auspices in the International Project on Innovative Nuclear Reactors and Fuel Cycles to consider and select the most acceptable nuclear technologies of the 21-st century with regard for the drawbacks of today's nuclear power. Main objectivities of INPRO: Promotion of the availability of nuclear power for sustainable satisfaction of the energy needs in 21-st century; Consolidation of efforts by all interested INPRO participating countries (both owners and users of technologies) for joint development of

Study Of Thorium As A Nuclear Fuel.

Directory of Open Access Journals (Sweden)

Prakash Humane

2017-10-01

Full Text Available Conventional fuel sources for power generation are to be replacing by nuclear power sources like nuclear fuel Uranium. But Uranium-235 is the only fissile fuel which is in 0.72 found in nature as an isotope of Uranium-238. U-238 is abundant in nature which is not fissile while U-239 by alpha decay naturally converted to Uranium- 235. For accompanying this nuclear fuel there is another nuclear fuel Thorium is present in nature is abundant can be used as nuclear fuel and is as much as safe and portable like U-235.

Nuclear fuel burn-up economy

International Nuclear Information System (INIS)

Matausek, M.

1984-01-01

In the period 1981-1985, for the needs of Utility Organization, Beograd, and with the support of the Scientific Council of SR Srbija, work has been performed on the study entitled 'Nuclear Fuel Burn-up Economy'. The forst [phase, completed during the year 1983 comprised: comparative analysis of commercial NPP from the standpoint of nuclear fuel requirements; development of methods for fuel burn-up analysis; specification of elements concerning the nuclear fuel for the tender documentation. The present paper gives the short description of the purpose, content and results achieved in the up-to-now work on the study. (author)

Criticality Calculations for a Typical Nuclear Fuel Fabrication Plant with Low Enriched Uranium

International Nuclear Information System (INIS)

Elsayed, Hade; Nagy, Mohamed; Agamy, Said; Shaat, Mohmaed

2013-01-01

The operations with the fissile materials such as U 235 introduce the risk of a criticality accident that may be lethal to nearby personnel and can lead the facility to shutdown. Therefore, the prevention of a nuclear criticality accident should play a major role in the design of a nuclear facility. The objectives of criticality safety are to prevent a self-sustained nuclear chain reaction and to minimize the consequences. Sixty criticality accidents were occurred in the world. These are accidents divided into two categories, 22 accidents occurred in process facilities and 38 accidents occurred during critical experiments or operations with research reactor. About 21 criticality accidents including Japan Nuclear Fuel Conversion Co. (JCO) accident took place with fuel solution or slurry and only one accident occurred with metal fuel. In this study the nuclear criticality calculations have been performed for a typical nuclear fuel fabrication plant producing nuclear fuel elements for nuclear research reactors with low enriched uranium up to 20%. The calculations were performed for both normal and abnormal operation conditions. The effective multiplication factor (k eff ) during the nuclear fuel fabrication process (Uranium hexafluoride - Ammonium Diuranate conversion process) was determined. Several accident scenarios were postulated and the criticalities of these accidents were evaluated. The computer code MCNP-4B which based on Monte Carlo method was used to calculate neutron multiplication factor. The criticality calculations Monte Carlo method was used to calculate neutron multiplication factor. The criticality calculations were performed for the cases of, change of moderator to fuel ratio, solution density and concentration of the solute in order to prevent or mitigate criticality accidents during the nuclear fuel fabrication process. The calculation results are analyzed and discussed

Metal plutonium conversion to components of nuclear reactor fuel

International Nuclear Information System (INIS)

Subbotin, V.G.; Panov, A.V.; Mashirev, V.P.

2000-01-01

Capabilities of different technologies for plutonium conversion to the fuel components of nuclear reactors are studied. Advantages and shortcomings of aqueous and nonaqueous methods of plutonium treatment are shown. Proposals to combine and coordinate efforts of world scientific and technological community in solving problems concerning plutonium of energetic and weapon origin treatment were put forward. (authors)

Metal plutonium conversion to components of nuclear reactor fuel

Energy Technology Data Exchange (ETDEWEB)

Subbotin, V.G.; Panov, A.V. [Russian Federal Nuclear Center, ALL-Russian Science and Research, Institute of Technical Physics, Snezhinsk (Russian Federation); Mashirev, V.P. [ALL-Russian Science and Research Institute of Chemical Technology, Moscow (Russian Federation)

2000-07-01

Capabilities of different technologies for plutonium conversion to the fuel components of nuclear reactors are studied. Advantages and shortcomings of aqueous and nonaqueous methods of plutonium treatment are shown. Proposals to combine and coordinate efforts of world scientific and technological community in solving problems concerning plutonium of energetic and weapon origin treatment were put forward. (authors)

Current Status of World Nuclear Fuel Cycle Technology (I): Canada and Latin America

Energy Technology Data Exchange (ETDEWEB)

Choi, Hang Bok; Ko, Won Il

2007-05-15

Canada produces about one third of the world's uranium mine output, most of it from two new mines. After 2007 Canadian production is expected to increase further as more new mines come into production. About 15% of Canada's electricity comes from nuclear power, using indigenous technology, and 18 reactors provide over 12,500 MWe of power. Mexico has two nuclear reactors generating almost 5% of its electricity. Its first commercial nuclear power reactor began operating in 1989. There is some government support for expanding nuclear energy to reduce reliance on natural gas. Argentina has two nuclear reactors generating nearly one tenth of its electricity. Its first commercial nuclear power reactor began operating in 1974. Brazil has two nuclear reactors generating 4% of its electricity. Its first commercial nuclear power reactor began operating in 1982.

Nuclear power and its fuel cycle

International Nuclear Information System (INIS)

Wymer, R.G.

1986-01-01

A series of viewgraphs describes the nuclear fuel cycle and nuclear power, covering reactor types, sources of uranium, enrichment of uranium, fuel fabrication, transportation, fuel reprocessing, and radioactive wastes

International auspices for the storage of spent nuclear fuel as a nonproliferation measure

International Nuclear Information System (INIS)

O'Brien, J.N.

1981-01-01

The maintenance of spent nuclear fuel from power reactors will pose problems regardless of how or when the debate over reprocessing is resolved. At present, many reactor sites contain significant buildups of spent fuel stored in holding pools, and no measure short of shutting down reactors with no remaining storage capacity will alleviate the need for away-from-reactor storage. Although the federal government has committed itself to dealing with the spent fuel problem, no solution has been reached, largely because of a debate over differing projections of storage capacity requirements. Proliferation of weapons grade nuclear material in many nations presents another pressing issue. If nations with small nuclear programs are forced to deal with their own spent fuel accumulations, they will either have to reprocess it indigenously or contract to have it reprocessed in a foreign reprocessing plant. In either case, these nations may eventually possess sufficient resources to assemble a nuclear weapon. The problem of spent fuel management demands real global solutions, and further delay in solving the problem of spent nuclear fuel accumulation, both nationally and globally, can benefit only a small class of elected officials in the short term and may inflict substantial costs on the American public, and possibly the world

Nuclear fuel quality assurance

International Nuclear Information System (INIS)

1976-01-01

Full text: Quality assurance is used extensively in the design, construction and operation of nuclear power plants. This methodology is applied to all activities affecting the quality of a nuclear power plant in order to obtain confidence that an item or a facility will perform satisfactorily in service. Although the achievement of quality is the responsibility of all parties participating in a nuclear power project, establishment and implementation of the quality assurance programme for the whole plant is a main responsibility of the plant owner. For the plant owner, the main concern is to achieve control over the quality of purchased products or services through contractual arrangements with the vendors. In the case of purchase of nuclear fuel, the application of quality assurance might be faced with several difficulties because of the lack of standardization in nuclear fuel and the proprietary information of the fuel manufacturers on fuel design specifications and fuel manufacturing procedures. The problems of quality assurance for purchase of nuclear fuel were discussed in detail during the seminar. Due to the lack of generally acceptable standards, the successful application of the quality assurance concept to the procurement of fuel depends on how much information can be provided by the fuel manufacturer to the utility which is purchasing fuel, and in what form and how early this information can be provided. The extent of information transfer is basically set out in the individual vendor-utility contracts, with some indirect influence from the requirements of regulatory bodies. Any conflict that exists appears to come from utilities which desire more extensive control over the product they are buying. There is a reluctance on the part of vendors to permit close insight of the purchasers into their design and manufacturing procedures, but there nevertheless seems to be an increasing trend towards release of more information to the purchasers. It appears that

Vibratory-compacted (vipac/sphere-pac) nuclear fuels - a comparison with pelletized nuclear fuels

Energy Technology Data Exchange (ETDEWEB)

Chidester, K.; Rubin, J. [Los Alamos National Lab., NM (United States); Thompson, M

2001-07-01

In order to achieve the packing densities required for nuclear fuel stability, economy and performance, the fuel material must be densified. This has traditionally been performed by high-temperature sintering. (At one time, fuel densification was investigated using cold/hot swaging. However, this fabrication method has become uncommon.) Alternatively, fuel can be densified by vibratory compaction (VIPAC). During the late 1950's and into the 1970's, in the U.S., vibratory compaction fuel was fabricated and test irradiated to evaluate its applicability compared to the more traditional pelletized fuel for nuclear reactors. These activities were primarily focused on light water reactors (LWR) but some work was performed for fast reactors. This paper attempts to summarize these evaluations and proposes to reconsider VIPAC fuel for future use. (author)

Vibratory-compacted (vipac/sphere-pac) nuclear fuels - a comparison with pelletized nuclear fuels

International Nuclear Information System (INIS)

Chidester, K.; Rubin, J.; Thompson, M.

2001-01-01

In order to achieve the packing densities required for nuclear fuel stability, economy and performance, the fuel material must be densified. This has traditionally been performed by high-temperature sintering. (At one time, fuel densification was investigated using cold/hot swaging. However, this fabrication method has become uncommon.) Alternatively, fuel can be densified by vibratory compaction (VIPAC). During the late 1950's and into the 1970's, in the U.S., vibratory compaction fuel was fabricated and test irradiated to evaluate its applicability compared to the more traditional pelletized fuel for nuclear reactors. These activities were primarily focused on light water reactors (LWR) but some work was performed for fast reactors. This paper attempts to summarize these evaluations and proposes to reconsider VIPAC fuel for future use. (author)

Progress of the United States foreign research reactor spent nuclear fuel acceptance program

International Nuclear Information System (INIS)

Huizenga, D.G.; Clapper, M.; Thrower, A.W.

2002-01-01

The United States Department of Energy (DOE), in consultation with the Department of State (DOS), adopted the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel in May 1996. To date, the Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program has completed 23 shipments. Almost 5000 spent fuel assemblies from eligible research reactors throughout the world have been accepted into the United States under this program. Over the past year, another cross-country shipment of fuel was accomplished, as well as two additional shipments in the fourth quarter of calendar year 2001. These shipments attracted considerable safeguards oversight since they occurred post September 11. Recent guidance from the Nuclear Regulatory Commission (NRC) pertaining to security and safeguards issues deals directly with the transport of nuclear material. Since the Acceptance Program has consistently applied above regulatory safety enhancements in transport of spent nuclear fuel, this guidance did not adversely effect the Program. As the Program draws closer to its termination date, an increased number of requests for program extension are received. Currently, there are no plans to extend the policy beyond its current expiration date; therefore, eligible reactor operators interested in participating in this program are strongly encouraged to evaluate their inventory and plan for future shipments as soon as possible. (author)

Nuclear fuel element

International Nuclear Information System (INIS)

Knowles, A.N.

1979-01-01

A nuclear fuel-containing body for a high temperature gas cooled nuclear reactor is described which comprises a flat plate in which the nuclear fuel is contained as a dispersion of fission product-retaining coated fuel particles in a flat sheet of graphitic or carbonaceous matrix material. The flat sheet is clad with a relatively thin layer of unfuelled graphite bonded to the sheet by being formed initially from a number of separate preformed graphitic artefacts and then platen-pressed on to the exterior surfaces of the flat sheet, both the matrix material and the artefacts being in a green state, to enclose the sheet. A number of such flat plates are supported edge-on to the coolant flow in the bore of a tube made of neutron moderating material. Where a number of tiers of plates are superimposed on one another, the abutting edges are chamfered to reduce vibration. (author)

Sustainable electricity supply in the world by 2050 for economic growth and automotive fuel

International Nuclear Information System (INIS)

Kruger, P.

2010-01-01

Over the next 40 years, the combustion of fossil fuels for generation of electricity and vehicle transportation will be significantly reduced. In addition to the business-as-usual growth in electric energy demand for the growing world population, new electricity-intensive industries, such as battery electric vehicles and hydrogen fuel-cell vehicles will result in further growth in world consumption of electric energy. Planning for a sustainable supply of electric energy in the diverse economies of the world should be carried out with appropriate technology for selecting the appropriate large-scale energy resources based on their specific energy. Analysis of appropriate technology for the available large-scale energy resources with diminished use of fossil fuel combustion shows that sustainable electricity supply can be achieved with equal contributions of renewable energy resources for large numbers of small-scale distributed applications and nuclear energy resources for the smaller number of large-scale centralised applications. (author)

The evolving nuclear fuel cycle

International Nuclear Information System (INIS)

Gale, J.D.; Hanson, G.E.; Coleman, T.A.

1993-01-01

Various economics and political pressures have shaped the evolution of nuclear fuel cycles over the past 10 to 15 yr. Future trends will no doubt be similarly driven. This paper discusses the influences that long cycles, high discharge burnups, fuel reliability, and costs will have on the future nuclear cycle. Maintaining the economic viability of nuclear generation is a key issue facing many utilities. Nuclear fuel has been a tremendous bargain for utilities, helping to offset major increases in operation and maintenance (O ampersand M) expenses. An important factor in reducing O ampersand M costs is increasing capacity factor by eliminating outages

Nuclear fuel cycle modelling using MESSAGE

International Nuclear Information System (INIS)

Guiying Zhang; Dongsheng Niu; Guoliang Xu; Hui Zhang; Jue Li; Lei Cao; Zeqin Guo; Zhichao Wang; Yutong Qiu; Yanming Shi; Gaoliang Li

2017-01-01

In order to demonstrate the possibilities of application of MESSAGE tool for the modelling of a Nuclear Energy System at the national level, one of the possible open nuclear fuel cycle options based on thermal reactors has been modelled using MESSAGE. The steps of the front-end and back-end of nuclear fuel cycle and nuclear reactor operation are described. The optimal structure for Nuclear Power Development and optimal schedule for introducing various reactor technologies and fuel cycle options; infrastructure facilities, nuclear material flows and waste, investments and other costs are demonstrated. (author)

The potential of fission nuclear power in resolving global climate change under the constraints of nuclear fuel resources and once-through fuel cycles

International Nuclear Information System (INIS)

Knapp, Vladimir; Pevec, Dubravko; Matijevic, Mario

2010-01-01

Nuclear fission is receiving new attention as a developed source of carbon-free energy. A much larger number of nuclear reactors would be needed for a major impact on carbon emission. The crucial question is whether it can be done without increasing the risk of nuclear proliferation. Specifically, can a larger nuclear share in world energy production, well above the present 6%, be achieved in the next few decades without adding the proliferation-sensitive technologies of reprocessing spent fuel and recycling plutonium to the problems of the unavoidable use of enrichment technology? The answer depends on the available uranium resources. We first looked for the maximum possible nuclear build-up in the 2025-2065 period under the constraints of the estimated uranium resources and the use of once-through nuclear fuel technology. Our results show that nuclear energy without reprocessing could reduce carbon emission by 39.6% of the total reduction needed to bring the WEO 2009 Reference Scenario prediction of total GHG emissions in 2065 to the level of the WEO 450 Scenario limiting global temperature increase to 2 deg. C. The less demanding strategy of the nuclear replacement of all non-CCS coal power plants retiring during the 2025-2065 period would reduce emission by 26.1%.

International Summer School on Nuclear Fuel

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

In cooperation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on nuclear fuel in the period August 28 September 1, 2000. The summer school was primarily intended for people who wanted to become acquainted with fuel-related subjects and issues without being experts. It was especially hoped that the summer school would serve to transfer knowledge to the ''young generation'' in the field of nuclear fuel. Experts from Halden Project member organisations gave the following presentations: (1) Overview of the nuclear community, (2) Criteria for safe operation and design of nuclear fuel, (3) Fuel design and fabrication, (4) Cladding Manufacturing, (5) Overview of the Halden Reactor Project, (6) Fuel performance evaluation and modelling, (7) Fission gas release, and (8) Cladding issues. Except for the Overview, which is a written paper, the other contributions are overhead figures from spoken lectures.

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

Material input of nuclear fuel

International Nuclear Information System (INIS)

Rissanen, S.; Tarjanne, R.

2001-01-01

The Material Input (MI) of nuclear fuel, expressed in terms of the total amount of natural material needed for manufacturing a product, is examined. The suitability of the MI method for assessing the environmental impacts of fuels is also discussed. Material input is expressed as a Material Input Coefficient (MIC), equalling to the total mass of natural material divided by the mass of the completed product. The material input coefficient is, however, only an intermediate result, which should not be used as such for the comparison of different fuels, because the energy contents of nuclear fuel is about 100 000-fold compared to the energy contents of fossil fuels. As a final result, the material input is expressed in proportion to the amount of generated electricity, which is called MIPS (Material Input Per Service unit). Material input is a simplified and commensurable indicator for the use of natural material, but because it does not take into account the harmfulness of materials or the way how the residual material is processed, it does not alone express the amount of environmental impacts. The examination of the mere amount does not differentiate between for example coal, natural gas or waste rock containing usually just sand. Natural gas is, however, substantially more harmful for the ecosystem than sand. Therefore, other methods should also be used to consider the environmental load of a product. The material input coefficient of nuclear fuel is calculated using data from different types of mines. The calculations are made among other things by using the data of an open pit mine (Key Lake, Canada), an underground mine (McArthur River, Canada) and a by-product mine (Olympic Dam, Australia). Furthermore, the coefficient is calculated for nuclear fuel corresponding to the nuclear fuel supply of Teollisuuden Voima (TVO) company in 2001. Because there is some uncertainty in the initial data, the inaccuracy of the final results can be even 20-50 per cent. The value

Redundancy of Supply in the International Nuclear Fuel Fabrication Market: Are Fabrication Services Assured?

International Nuclear Information System (INIS)

Seward, Amy M.; Toomey, Christopher; Ford, Benjamin E.; Wood, Thomas W.; Perkins, Casey J.

2011-01-01

For several years, Pacific Northwest National Laboratory (PNNL) has been assessing the reliability of nuclear fuel supply in support of the U.S. Department of Energy/National Nuclear Security Administration. Three international low enriched uranium reserves, which are intended back up the existing and well-functioning nuclear fuel market, are currently moving toward implementation. These backup reserves are intended to provide countries credible assurance that of the uninterrupted supply of nuclear fuel to operate their nuclear power reactors in the event that their primary fuel supply is disrupted, whether for political or other reasons. The efficacy of these backup reserves, however, may be constrained without redundant fabrication services. This report presents the findings of a recent PNNL study that simulated outages of varying durations at specific nuclear fuel fabrication plants. The modeling specifically enabled prediction and visualization of the reactors affected and the degree of fuel delivery delay. The results thus provide insight on the extent of vulnerability to nuclear fuel supply disruption at the level of individual fabrication plants, reactors, and countries. The simulation studies demonstrate that, when a reasonable set of qualification criteria are applied, existing fabrication plants are technically qualified to provide backup fabrication services to the majority of the world's power reactors. The report concludes with an assessment of the redundancy of fuel supply in the nuclear fuel market, and a description of potential extra-market mechanisms to enhance the security of fuel supply in cases where it may be warranted. This report is an assessment of the ability of the existing market to respond to supply disruptions that occur for technical reasons. A forthcoming report will address political disruption scenarios.

Research on assurance system of nuclear fuel supply (Contract research)

International Nuclear Information System (INIS)

Kobayashi, Naoki; Naoi, Yosuke; Wakabayashi, Shuji; Tazaki, Makiko; Senzaki, Masao

2010-08-01

Assurance of supply (AOS) of nuclear fuel is a special arrangement in case of nuclear fuel supply disruption caused by political reasons other than nonproliferation. It aims to support a stable supply of nuclear fuel while avoiding spread of sensitive enrichment technology. Current discussions on AOS have been initiated by the IAEA Director-General's article published in The Economist entitled 'Towards a Safer World' Oct. 2003. Since then, various proposals on AOS have been presented. In order to facilitate international discussions on AOS, authors have conducted studies of AOS system based on Japanese Government's proposal 'IAEA Standby Arrangement System (INFCIRC/683)'. In this paper, we have been able to discuss feasibility of AOS system more specifically by including additional costs and period required for AOS, and to present a system which could work as a practical system. Issues we have tried to tackle here include definitions of AOS, and roles of consumer States, supplier States, IAEA and nuclear industries. We present some solutions including broadening coverage of AOS, declaration by supplier States on AOS, establishing advisory committee in the IAEA on the actual application of AOS, and setting up an IAEA fund for AOS. (author)

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.)

Spent Nuclear Fuel project, project management plan

International Nuclear Information System (INIS)

Fuquay, B.J.

1995-01-01

The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

World status - nuclear power

International Nuclear Information System (INIS)

Holmes, A.

1984-01-01

The problems of nuclear power are not so much anti-nuclear public opinion, but more the decrease of electricity consumption growth rate and the high cost of building reactors. Because of these factors, forecasts of world nuclear capacity have had to be reduced considerably over the last three years. The performance of reactors is considered. The CANDU reactor remains the world's best performer and overall tends to out-perform larger reactors. The nuclear plant due to come on line in 1984 are listed by country; this shows that nuclear capacity will increase substantially over a short period. At a time of stagnant demand this will make nuclear energy an important factor in the world energy balance. Nuclear power stations in operation and under construction in 1983 are listed and major developments in commercial nuclear power in 1983 are taken country by country. In most, the report is the same; national reactor ordering cut back because the expected increase in energy demand has not happened. Also the cost-benefit of nuclear over other forms of energy is no longer as favourable. The export opportunities have also declined as many of the less developed countries are unable to afford reactors. (U.K.)

CO2 and the world energy system: The role of nuclear power

International Nuclear Information System (INIS)

Fulkerson, W.; Jones, J.E. Jr.

1989-01-01

The greenhouse effect, and other transnational and global environment, health and safety issues, require energy system planning on an international scale. Consideration of equity between nations and regions, particularly between the industrialized and developing countries, is an essential ingredient. For the immediate future, the next several decades at least, fossil fuels will remain the predominant energy sources. More efficient use of energy seems to be the only feasible strategy for the near to mid-term to provide growing energy services for the world economy while moderating the increasing demand for fossil fuels. In the longer term, nonfossil sources are essential for a sustainable world energy system, and nuclear power can play an important, if not dominant, role. The challenge is to design and implement a safe and economic nuclear power world enterprise which is socially acceptable and is complimentary to other nonfossil sources. The elements of such an enterprise seem clear and include: much safer reactors, preferably passively safe, which can be developed at various scales; development of economic resource extension technologies; effective and permanent waste management strategies; and strengthened safeguards against diversion of nuclear materials to weapons. All of these elements can best be developed as cooperative international efforts. In the process, institutional improvements are equally as important as technological improvements; the two must proceed hand-in-hand. 14 refs., 4 figs., 1 tab

CO2 and the world energy system: the role of nuclear power

International Nuclear Information System (INIS)

Fulkerson, W.; Jones, J.E. Jr.

1992-01-01

The greenhouse effect, and other transnational and global environment, health and safety issues, require energy system planning on an international scale. Consideration of equity between nations and regions, particularly between the industrialized and developing countries, is an essential ingredient. For the immediate future, the next several decades at least, fossil fuels will remain the predominant energy sources. More efficient use of energy seems to be the only feasible strategy for the near to mid-term to provide growing energy services for the world economy while moderating the increasing demand for fossil fuels. In the longer term, nonfossil sources are essential for a sustainable world energy system, and nuclear power can play an important, if not dominant, role. The challenge is to design and implement a safe and economic nuclear power world enterprise which is socially acceptable and is complimentary to other nonfossil sources. The elements of such an enterprise seem clear and include: much safer reactors, preferably passively safe, which can be deployed at various scales; development of economic resource extension technologies; effective and permanent waste management strategies; and strengthened safeguards against diversion of nuclear materials to weapons. All of these elements can best be developed as cooperative international efforts. In the process, institutional improvements are equally as important as technological improvements; the two must proceed hand-in-hand. (orig.)

The impact of the multilateral approach to the nuclear fuel cycle in Malaysia's nuclear fuel cycle policy

International Nuclear Information System (INIS)

Baharuddin, B.; Ferdinand, P.

2014-01-01

Since the Pakistan-India nuclear weapon race, the North Korean nuclear test and the September 11 attack revealed Abdul Qadeer Khan's clandestine nuclear black market and the fear that Iran's nuclear program may be used for nuclear weapon development, scrutiny of activities related to nuclear technologies, especially technology transfer has become more stringent. The nuclear supplier group has initiated a multilateral nuclear fuel cycle regime with the purpose of guaranteeing nuclear fuel supply and at the same time preventing the spread of nuclear proliferation. Malaysia wants to develop a programme for the peaceful use of nuclear energy and it needs to accommodate itself to this policy. When considering developing a nuclear fuel cycle policy, the key elements that Malaysia needs to consider are the extent of the fuel cycle technologies that it intends to acquire and the costs (financial and political) of acquiring them. Therefore, this paper will examine how the multilateral approach to the nuclear fuel cycle may influence Malaysia's nuclear fuel cycle policy, without jeopardising the country's rights and sovereignty as stipulated under the NPT. (authors)

Alternatives for nuclear fuel disposal

International Nuclear Information System (INIS)

Ramirez S, J. R.; Badillo A, V.; Palacios H, J.; Celis del Angel, L.

2010-10-01

The spent fuel is one of the most important issues in the nuclear industry, currently spent fuel management is been cause of great amount of research, investments in the construction of repositories or constructing the necessary facilities to reprocess the fuel, and later to recycle the plutonium recovered in thermal reactors. What is the best solution? or, What is the best technology for a specific solution? Many countries have deferred the decision on selecting an option, while other works actively constructing repositories and others implementing the reprocessing facilities to recycle the plutonium obtained from nuclear spent fuel. In Mexico the nuclear power is limited to two reactors BWR type and medium size. So the nuclear spent fuel discharged has been accommodated at reactor's spent fuel pools. Originally these pools have enough capacity to accommodate spent fuel for the 40 years of designed plant operation. However, currently is under process an extended power up rate to 20% of their original power and also there are plans to extend operational life for 20 more years. Under these conditions there will not be enough room for spent fuel in the pools. So this work describes some different alternatives that have been studied in Mexico to define which will be the best alternative to follow. (Author)

Multilateral approach to the back end of the nuclear fuel cycle in Asia-Pacific?

International Nuclear Information System (INIS)

Lim, Eunjung

2016-01-01

In spite of the nearly unprecedented scale of the Fukushima Daiichi Nuclear Accident which caused countries around the world to review their nuclear power systems and to rethink their nuclear power expansion plans, nuclear power capacity continues to grow, spearheaded by the Asia-Pacific region. The Asia-Pacific has become a major emerging market for nuclear energy industry, which indicates that the management of spent nuclear fuel is likely to be a nuisance for the countries in this region in the coming decades. By reviewing the history of discussions on multilateral approaches to the back end of the nuclear fuel cycle and examining relevant empirical cases, this article aims to explore the feasibility of a multilateral approach to the back end of the nuclear fuel cycle in this region and provide some policy suggestions to enhance nuclear governance in the Asia-Pacific. - Highlights: • The Asia-Pacific has become a huge emerging market for nuclear power industry. • Asian-Pacific countries operating reactors lack solution for spent nuclear fuel. • Multilateral approach is attractive, but hard to be realized. • The main obstacle is variations in policies for SNF management among the Asia-Pacific countries. • The country that should take its initiative in this field is the United States.

Long-term global nuclear energy and fuel cycle strategies

International Nuclear Information System (INIS)

Krakowski, R.A.

1997-01-01

The Global Nuclear Vision Project is examining, using scenario building techniques, a range of long-term nuclear energy futures. The exploration and assessment of optimal nuclear fuel-cycle and material strategies is an essential element of the study. To this end, an established global E 3 (energy/economics/environmental) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Consistent nuclear energy scenarios are constructed using this multi-regional E 3 model, wherein future demands for nuclear power are projected in price competition with other energy sources under a wide range of long-term demographic (population, workforce size and productivity), economic (price-, population-, and income-determined demand for energy services, price- and population-modified GNP, resource depletion, world-market fossil energy prices), policy (taxes, tariffs, sanctions), and top-level technological (energy intensity and end-use efficiency improvements) drivers. Using the framework provided by the global E 3 model, the impacts of both external and internal drivers are investigated. The ability to connect external and internal drivers through this modeling framework allows the study of impacts and tradeoffs between fossil- versus nuclear-fuel burning, that includes interactions between cost, environmental, proliferation, resource, and policy issues

Long-term global nuclear energy and fuel cycle strategies

Energy Technology Data Exchange (ETDEWEB)

Krakowski, R.A. [Los Alamos National Lab., NM (United States). Technology and Safety Assessment Div.

1997-09-24

The Global Nuclear Vision Project is examining, using scenario building techniques, a range of long-term nuclear energy futures. The exploration and assessment of optimal nuclear fuel-cycle and material strategies is an essential element of the study. To this end, an established global E{sup 3} (energy/economics/environmental) model has been adopted and modified with a simplified, but comprehensive and multi-regional, nuclear energy module. Consistent nuclear energy scenarios are constructed using this multi-regional E{sup 3} model, wherein future demands for nuclear power are projected in price competition with other energy sources under a wide range of long-term demographic (population, workforce size and productivity), economic (price-, population-, and income-determined demand for energy services, price- and population-modified GNP, resource depletion, world-market fossil energy prices), policy (taxes, tariffs, sanctions), and top-level technological (energy intensity and end-use efficiency improvements) drivers. Using the framework provided by the global E{sup 3} model, the impacts of both external and internal drivers are investigated. The ability to connect external and internal drivers through this modeling framework allows the study of impacts and tradeoffs between fossil- versus nuclear-fuel burning, that includes interactions between cost, environmental, proliferation, resource, and policy issues.

Impact of Multilateral Approaches for Assurances of Nuclear Fuel Supply

Energy Technology Data Exchange (ETDEWEB)

Lee, Han Myung; Lee, B. W.; Ko, H. S.; Ryu, J. S.; Yang, M. H.; Oh, K. B.; Lee, K. S

2007-12-15

This study consists of 3 parts : analysis of the characteristics of the recent proposals for a nuclear fuel supply and the progress of them, responses from various sectors in the world, and measures for them. In response to recent proposals, majority of countries possessing sensitive nuclear fuel facilities are supportive in general. In contrast, many countries not possessing such facilities are reluctant about the proposals. To satisfy both parties, an ideal proposal could suggest measures to assure a non-proliferation as well as measures to acquire confidence from the so-called user nations. To get strong support from all countries concerned, the proposal should contain some critical elements such as clear attractiveness for a participation, equal opportunities for the participating countries, voluntarily in decision on a participation, and a gradual approach to remove any future obstacles encountered. The criteria to judge a legitimate need of a country for the introduction of nuclear fuel facilities should be prepared by a consensus. Compliance of a nonproliferation obligation, scale of an economy, and an energy security can be proposed as such criteria.

Impact of Multilateral Approaches for Assurances of Nuclear Fuel Supply

International Nuclear Information System (INIS)

Lee, Han Myung; Lee, B. W.; Ko, H. S.; Ryu, J. S.; Yang, M. H.; Oh, K. B.; Lee, K. S.

2007-12-01

This study consists of 3 parts : analysis of the characteristics of the recent proposals for a nuclear fuel supply and the progress of them, responses from various sectors in the world, and measures for them. In response to recent proposals, majority of countries possessing sensitive nuclear fuel facilities are supportive in general. In contrast, many countries not possessing such facilities are reluctant about the proposals. To satisfy both parties, an ideal proposal could suggest measures to assure a non-proliferation as well as measures to acquire confidence from the so-called user nations. To get strong support from all countries concerned, the proposal should contain some critical elements such as clear attractiveness for a participation, equal opportunities for the participating countries, voluntarily in decision on a participation, and a gradual approach to remove any future obstacles encountered. The criteria to judge a legitimate need of a country for the introduction of nuclear fuel facilities should be prepared by a consensus. Compliance of a nonproliferation obligation, scale of an economy, and an energy security can be proposed as such criteria

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)

Autonomous dynamic decision making in a nuclear fuel cycle simulator

International Nuclear Information System (INIS)

Pelakauskas, Martynas; Auzans, Aris; Schneider, Erich A.; Tkaczyk, Alan H.

2013-01-01

Highlights: • Objective criteria based decision making in a nuclear fuel cycle simulator. • Simulation driven by an evolving performance metric. • Implementation of the model in a nuclear fuel cycle simulator. • Verification of dynamic decision making based on uranium price evolution. -- Abstract: Growing energy demand and the push to move toward carbon-free ways of electricity generation have renewed the world's interest in nuclear energy. Due to the high technical and economic uncertainties related to nuclear energy, simulation tools have become a necessity in order to plan and evaluate possible nuclear fuel cycles (NFCs). Most of the NFC simulators today work by running the simulation with a user-defined set of facility build orders and preferences. While this allows for a simple way to change the simulation conditions, it may not always lead to optimal results and strongly relies on the user defining the correct parameters. This study looks into the possibility of using the expected cost of electricity (CoE) as the driving build decision variable instead of relying on user-defined build orders. This is a first step toward a more general decision making strategy in dynamic fuel cycle simulation. For this purpose, additional modules were implemented in an NFC simulator, VEGAS, with the consumption dependent price of uranium as a time-varying NFC cost component that drives the cost competitiveness of available NFC options. The model was demonstrated to verify the correct operation of a CoE-driven NFC simulator

Spent nuclear fuel in Bulgaria

International Nuclear Information System (INIS)

Peev, P.; Kalimanov, N.

1999-01-01

The development of the nuclear energy sector in Bulgaria is characterized by two major stages. The first stage consisted of providing a scientific basis for the programme for development of the nuclear energy sector in the country and was completed with the construction of an experimental water-water reactor. At present, spent nuclear fuel from this reactor is placed in a water filled storage facility and will be transported back to Russia. The second stage consisted of the construction of the 6 NPP units at the Kozloduy site. The spent nuclear fuel from the six units is stored in at reactor pools and in an additional on-site storage facility which is nearly full. In order to engage the government of the country with the on-site storage problems, the new management of the National Electric Company elaborated a policy on nuclear fuel cycle and radioactive waste management. The underlying policy is de facto the selection of the 'deferred decision' option for its spent fuel management. (author)

The world nuclear market and its prospects

International Nuclear Information System (INIS)

Anon.

2010-07-01

This market study of the nuclear industry presents: 1 - the dynamics of nuclear markets: organisation of the nuclear industry (fuel cycle, reactors), market analysis and key figures (uranium production, conversion and enrichment, fuel fabrication, reactor manufacturing, spent fuel reprocessing), strengths in presence and competition structure (companies ranking, market shares, positioning); 2 - nuclear renaissance and its basis: a suitable answer to the present day energy and environmental challenges (carbon-free energy and low volatility of fuel price), conjunction of favourable conditions (security of fuel supplies, political support, necessity of plants renewal), three main uncertainties (waste management, safety aspect, public opinion weight); 3 - perspectives of development at the 2030 prospects: data (scope of renaissance, market size), sector reconfiguration scenarios (evolution of competition, reconfiguration paths, concentration trend); 4 - analysis of the strategy of 13 companies, suppliers of the nuclear industry, with their key figures, positioning and strategy (production capacity, partnerships, external growth investments, new technical developments etc.). (J.S.)

Improved nuclear fuel element

International Nuclear Information System (INIS)

1974-01-01

A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has a metal liner disposed between the cladding and the nuclear fuel material and a high lubricity material in the form of a coating disposed between the liner and the cladding. The liner preferably has a thickness greater than the longest fission product recoil distance and is composed of a low neutron capture cross-section material. The liner is preferably composed of zirconium, an alloy of zirconium, niobium or an alloy of niobium. The liner serves as a preferential reaction site for volatile impurities and fission products and protects the cladding from contact and reaction with such impurities and fission products. The high lubricity material acts as an interface between the liner and the cladding and reduces localized stresses on the cladding due to fuel expansion and cracking of the fuel

Nuclear fuel storage facility

International Nuclear Information System (INIS)

Matsumoto, Takashi; Isaka, Shinji.

1987-01-01

Purpose: To increase the spent fuel storage capacity and reduce the installation cost in a nuclear fuel storage facility. Constitution: Fuels handled in the nuclear fuel storage device of the present invention include the following four types: (1) fresh fuels, (2) 100 % reactor core charged fuels, (3) spent fuels just after taking out and (4) fuels after a certain period (for example one half-year) from taking out of the reactor. Reactivity is high for the fuels (1), and some of fuels (2), while low in the fuels (3) (4), Source intensity is strong for the fuels (3) and some of the fuels (2), while it is low for the fuels (1) and (4). Taking notice of the fact that the reactivity, radioactive source intensity and generated after heat are different in the respective fuels, the size of the pool and the storage capacity are increased by the divided storage control. While on the other hand, since the division is made in one identical pool, the control method becomes important, and the working range is restricted by means of a template, interlock, etc., the operation mode of the handling machine is divided into four, etc. for preventing errors. (Kamimura, M.)

Proceeding of the Fifth Scientific Presentation on Nuclear Fuel Cycle: Development of Nuclear Fuel Cycle Technology in Third Millennium

International Nuclear Information System (INIS)

Suripto, A.; Sastratenaya, A.S.; Sutarno, D.

2000-01-01

The proceeding contains papers presented in the Fifth Scientific Presentation on Nuclear Fuel Element Cycle with theme of Development of Nuclear Fuel Cycle Technology in Third Millennium, held on 22 February in Jakarta, Indonesia. These papers were divided by three groups that are technology of exploration, processing, purification and analysis of nuclear materials; technology of nuclear fuel elements and structures; and technology of waste management, safety and management of nuclear fuel cycle. There are 35 papers indexed individually. (id)

Development for analysis system of rods enrichment of nuclear fuels; Desarrollo de un sistema de analisis de enriquecimiento de barras de combustible nuclear

Energy Technology Data Exchange (ETDEWEB)

Rojas C, E.L

1998-11-01

Nuclear industry is strongly regulated all over the world and quality assurance is important in every nuclear installation or process related with it. Nuclear fuel manufacture is not the exception. ININ was committed to manufacture four nuclear fuel bundles for the CFE nucleo electric station at Laguna Verde, Veracruz, under General Electric specifications and fulfilling all the requirements of this industry. One of the quality control requisites in nuclear fuel manufacture deals with the enrichment of the pellets inside the fuel bundle rods. To achieve the quality demanded in this aspect, the system described in this work was developed. With this system, developed at ININ it is possible to detect enrichment spikes since 0.4 % in a column of pellets with a 95 % confidence interval and to identify enrichment differences greater than 0.2 % e between homogeneous segments, also with a 95 % confidence interval. ININ delivered the four nuclear fuel bundles to CFE and these were introduced in the core of the nuclear reactor of Unit 1 in the fifth cycle. Nowadays they are producing energy and have shown a correct mechanical performance and neutronic behavior. (Author)

Clean energy : nuclear energy world

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-10-15

This book explains the nuclear engineering to kids with easy way. There are explanations of birth of nuclear energy such as discover of nuclear and application of modern technology of nuclear energy, principles and structure of nuclear power plant, fuel, nuclear waste management, use of radiation for medical treatment, food supplies, industry, utilization of neutron. It indicates the future of nuclear energy as integral nuclear energy and nuclear fusion energy.

Romanian nuclear fuel program: past, present and future

International Nuclear Information System (INIS)

Budan, O.; Rotaru, I.; Galeriu, C.A.

1997-01-01

The paper presents and comments the policy adopted in Romania for the production of CANDU-6 nuclear fuel before and after 1990. In this paper the word 'past' refers to the period before 1990 and 'present' to the 1990-1997 period. The CANDU-6 nuclear fuel manufacturing started in Romania in December 1983. Neither AECL nor any Canadian nuclear fuel manufacturer were involved in the Romanian industrial nuclear fuel production before 1990. After January 1990, the new created Romanian Electricity Authority (RENEL) assumed the responsibility for the Romanian Nuclear Power Program. It was RENEL's decision to stop, in June 1990, the nuclear fuel production at the Institute for Nuclear Power Reactors (IRNE) Pitesti. This decision was justified by the Canadian specialists team findings, revealed during a general, but well enough technically founded analysis performed at IRNE in the spring of 1990. All fuel manufactured before June 1990 was quarantined as it was considered of suspect quality. By that time more than 31,000 fuel bundles had already been manufactured. This fuel was stored for subsequent assessment. The paper explains the reasons which provoked this decision. The paper also presents the strategy adopted by RENEL after 1990 regarding the Romanian Nuclear Fuel Program. After a complex program done by Romanian and Canadian partners, in November 1994, AECL issued a temporary certification for the Romanian nuclear fuel plant. During the demonstration manufacturing run, as an essential milestone for the qualification of the Romanian fuel supplier for CANDU-6 reactors, 202 fuel bundles were produced. Of these fuel bundles, 66 were part of the Cernavoda NGS Unit 1 first fuel load (the balance was supplied by Zircatec Precision Industries Inc. - ZPI). The industrial nuclear fuel fabrication re-started in Romania in January 1995 under AECL's periodical monitoring. In December 1995, AECL issued a permanent certificate, stating the Romanian nuclear fuel plant as a qualified

Status of research reactor spent fuel world-wide

International Nuclear Information System (INIS)

Ritchie, I.G.

2004-01-01

Results compiled in the research reactor spent fuel database are used to assess the status of research reactor spent fuel world-wide. Fuel assemblies, their types, enrichment, origin of enrichment and geological distribution among the industrialised and developed countries of the world are discussed. Fuel management practices in wet and dry storage facilities and the concerns of reactor operators about long-term storage of their spent fuel are presented and some of the activities carried out by the International Atomic Energy Agency to address the issues associated with research reactor spent fuel are outlined. (author)

International guidelines for fire protection at nuclear installations including nuclear fuel plants, nuclear fuel stores, teaching reactors, research establishments

International Nuclear Information System (INIS)

The guidelines are recommended to designers, constructors, operators and insurers of nuclear fuel plants and other facilities using significant quantities of radioactive materials including research and teaching reactor installations where the reactors generally operate at less than approximately 10 MW(th). Recommendations for elementary precautions against fire risk at nuclear installations are followed by appendices on more specific topics. These cover: fire protection management and organization; precautions against loss during construction alterations and maintenance; basic fire protection for nuclear fuel plants; storage and nuclear fuel; and basic fire protection for research and training establishments. There are numerous illustrations of facilities referred to in the text. (U.K.)

Review of nuclear power costs around the world

International Nuclear Information System (INIS)

Bennett, L.L.; Karousakis, P.M.; Moynet, G.

1983-01-01

This paper presents highlights of nuclear power costs around the world from studies carried out by the IAEA and by UNIPEDE. Emphasis is placed on trends within each country of key parameters which affect both investment costs and total power generation costs, including construction and project durations, size of units, regulatory environment, scope of project, fuel cycle costs and general economic conditions. A synthesis of these trends, taking into consideration both nuclear and coal-fired plant capital and fuel costs as they are estimated to evolve in the near and medium term, is presented in terms of nuclear-to-coal cost ratios for both plant investment costs and total generating costs. The plant investment costs are expressed as ''overnight'' or ''fore'' costs, in constant money, for plants expected to enter commercial operation in the early 1990s. Pertinent assumptions are based on conditions prevailing in the particular country under review. These studies indicate that in most countries nuclear plant investment costs are rising more rapidly than the costs for coal-fired plants. A major cause for the rapid rise in nuclear plant costs is the drastic lengthening of project duration in most countries. France, as a notable exception, has been able to maintain a stable and reasonably short project time. In spite of the rapidly escalating nuclear plant investment costs, nuclear electricity generation has an economic advantage over coal in Europe and Canada and is competitive with coal in the eastern and midwestern parts of the United States of America (USA). The availability of abundant, low-cost coal gives coal-fired generation an economic advantage in the western USA. (author)

Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

International Nuclear Information System (INIS)

Ewing, Rodney C.

2003-01-01

The successful disposal of spent nuclear fuel (SNF) is one of the most serious challenges to the successful completion of the nuclear fuel cycle and the future of nuclear power generation. In the United States, 21 percent of the electricity is generated by 107 commercial nuclear power plants (NPP), each of which generates 20 metric tons of spent nuclear fuel annually. In 1996, the total accumulation of spent nuclear fuel was 33,700 metric tons of heavy metal (MTHM) stored at 70 sites around the country. The end-of-life projection for current nuclear power plants (NPP) is approximately 86,000 MTHM. In the proposed nuclear waste repository at Yucca Mountain over 95% of the radioactivity originates from spent nuclear fuel. World-wide in 1998, approximately 130,000 MTHM of SNF have accumulated, most of it located at 236 NPP in 36 countries. Annual production of SNF is approximately 10,000 MTHM, containing about 100 tons of ''reactor grade'' plutonium. Any reasonable increase in the proportion of energy production by NPP, i.e., as a substitute for hydrocarbon-based sources of energy, will significantly increase spent nuclear fuel production. Spent nuclear fuel is essentially UO 2 with approximately 4-5 atomic percent actinides and fission product elements. A number of these elements have long half-lives hence, the long-term behavior of the UO 2 is an essential concern in the evaluation of the safety and risk of a repository for spent nuclear fuel. One of the unique and scientifically most difficult aspects of the successful disposal of spent nuclear fuel is the extrapolation of short-term laboratory data (hours to years) to the long time periods (10 3 to 10 5 years) as required by the performance objectives set in regulations, i.e. 10 CFR 60. The direct verification of these extrapolations or interpolations is not possible, but methods must be developed to demonstrate compliance with government regulations and to satisfy the public that there is a reasonable basis for

Nuclear fuel

International Nuclear Information System (INIS)

Quinauk, J.P.

1990-01-01

Since 1985, Fragema has been marketing and selling the Advanced Fuel Assemby AFA whose main features are its zircaloy grids and removable top and bottom nozzles. It is this product, which exists for several different fuel assembly arrays and heights, that will be employed in the reactors at Daya Bay. Fragema employs gadolinium as the consumable poison to enable highperformance fuel management. More recently, the company has supplied fuel assemblies of the mixed-oxide(MOX) and enriched reprocessed uranium type. The reliability level of the fuel sold by Fragema is one of the highest in the world, thanks in particular to the excellence of the quality assurance and quality control programs that have been implemented at all stages of its design and manufacture

Nuclear fuel element leak detection system

International Nuclear Information System (INIS)

John, C.D. Jr.

1978-01-01

Disclosed is a leak detection system integral with a wall of a building used to fabricate nuclear fuel elements for detecting radiation leakage from the nuclear fuel elements as the fuel elements exit the building. The leak detecting system comprises a shielded compartment constructed to withstand environmental hazards extending into a similarly constructed building and having sealed doors on both ends along with leak detecting apparatus connected to the compartment. The leak detecting system provides a system for removing a nuclear fuel element from its fabrication building while testing for radiation leaks in the fuel element

Chemical characterization of nuclear fuel materials

International Nuclear Information System (INIS)

Ramakumar, K.L.

2011-01-01

India is fabricating nuclear fuels for various types of reactors, for example, (U-Pu) MOX fuel of varying Pu content for boiling water reactors (BWRs), pressurized heavy water reactors (PHWRs), prototype fast breeder reactors (PFBRs), (U-Pu) carbide fuel fast breeder test reactor (FBTR), and U-based fuels for research reactors. Nuclear fuel being the heart of the reactor, its chemical and physical characterisation is an important component of this design. Both the fuel materials and finished fuel products are to be characterised for this purpose. Quality control (both chemical and physical) provides a means to ensure that the quality of the fabricated fuel conforms to the specifications for the fuel laid down by the fuel designer. Chemical specifications are worked out for the major and minor constituents which affect the fuel properties and hence its performance under conditions prevailing in an operating reactor. Each fuel batch has to be subjected to comprehensive chemical quality control for trace constituents, stoichiometry and isotopic composition. A number of advanced process and quality control steps are required to ensure the quality of the fuels. Further more, in the case of Pu-based fuels, it is necessary to extract maximum quality data by employing different evaluation techniques which would result in minimum scrap/waste generation of valuable plutonium. The task of quality control during fabrication of nuclear fuels of various types is both challenging and difficult. The underlying philosophy is total quality control of the fuel by proper mix of process and quality control steps at various stages of fuel manufacture starting from the feed materials. It is also desirable to adapt more than one analytical technique to increase the confidence and reliability of the quality data generated. This is all the most required when certified reference materials are not available. In addition, the adaptation of non-destructive techniques in the chemical quality

The global nuclear energy partnership and the spent fuel take-back provision

International Nuclear Information System (INIS)

Bresee, James C.

2007-01-01

The Global Nuclear Energy Partnership (GNEP) was announced by Secretary of Energy Samuel Bodman in February 2006 (1). Its purpose is to expand the use of nuclear energy throughout the world under conditions which would help reduce the threat of nuclear weapons proliferation. Its success would be based on agreements among certain nations that are signatories to the Non- Proliferation Treaty and have extensive current fuel cycle capabilities. The agreements would be for such fuel cycle nations to provide other non-fuel cycle nations with power reactors sized to match their energy needs and power distribution characteristics, fresh nuclear reactor fuel (perhaps under a leasing arrangement), and waste management services, provided that the non-fuel cycle countries agree to refrain from obtaining fuel cycle capabilities. The waste management services would include taking back the non-fuel cycle spent nuclear fuel for processing within the fuel cycle country followed by fast spectrum power reactor consumption of the spent fuel's contained transuranic elements (TRU, including neptunium, plutonium, americium and curium). All agreements between fuel cycle countries and non-fuel cycle countries would be under the auspices of the International Atomic Energy Agency (IAEA) and may involve three-party contracts involving the fuel-cycle state, the non-fuel cycle state and the IARA (2). To be a full participant in such a world-wide program, the United States will need to add to its current uranium enrichment and reactor construction capabilities two no-longer available capabilities: a facility or facilities for reprocessing of spent power reactor fuel and fast spectrum reactors to fission the spent fuel's transuranic contents. In addition, an Advanced Fuel Cycle Facility at a national laboratory will be needed to provide research and development support for the closed fuel cycles of the future. Ironically, both the processing of irradiated nuclear fuel and the operation of fast

Nuclear fuel preheating system

International Nuclear Information System (INIS)

Andrea, C.

1975-01-01

A nuclear reactor new fuel handling system which conveys new fuel from a fuel preparation room into the reactor containment boundary is described. The handling system is provided with a fuel preheating station which is adaptd to heat the new fuel to reactor refueling temperatures in such a way that the fuel is heated from the top down so that fuel element cladding failure due to thermal expansions is avoided. (U.S.)

AN ANALYTICAL FRAMEWORK FOR ASSESSING RELIABLE NUCLEAR FUEL SERVICE APPROACHES: ECONOMIC AND NON-PROLIFERATION MERITS OF NUCLEAR FUEL LEASING

International Nuclear Information System (INIS)

Kreyling, Sean J.; Brothers, Alan J.; Short, Steven M.; Phillips, Jon R.; Weimar, Mark R.

2010-01-01

The goal of international nuclear policy since the dawn of nuclear power has been the peaceful expansion of nuclear energy while controlling the spread of enrichment and reprocessing technology. Numerous initiatives undertaken in the intervening decades to develop international agreements on providing nuclear fuel supply assurances, or reliable nuclear fuel services (RNFS) attempted to control the spread of sensitive nuclear materials and technology. In order to inform the international debate and the development of government policy, PNNL has been developing an analytical framework to holistically evaluate the economics and non-proliferation merits of alternative approaches to managing the nuclear fuel cycle (i.e., cradle-to-grave). This paper provides an overview of the analytical framework and discusses preliminary results of an economic assessment of one RNFS approach: full-service nuclear fuel leasing. The specific focus of this paper is the metrics under development to systematically evaluate the non-proliferation merits of fuel-cycle management alternatives. Also discussed is the utility of an integrated assessment of the economics and non-proliferation merits of nuclear fuel leasing.

Selection and evaluation of nuclear fuel cycle strategies. Technical and economic aspects

International Nuclear Information System (INIS)

Clarke, F.J.P.; Main, F.K.

1983-01-01

The original choices of thermal reactors and fuel cycles were largely determined by specific national circumstances and by experience and facilities acquired from defence-related programmes. These led to the development of LWRs in the USA and to the natural uranium/gas/graphite system in the United Kingdom and France, while Canada selected the HWR. Most countries with nuclear power programmes saw the plutonium-fuelled fast reactor, with its breeding potential, as the means to ensure that exhaustion of economic uranium resources would not prematurely curtail the contribution of nuclear power to world energy supplies. Fuel reprocessing was essential to this fuel cycle or indeed to other recycling options to make better use of the available uranium; it was also favoured for waste management reasons. Early expectations of nuclear power growth suggested that a transition from thermal to fast reactors would occur during the present century but the urgency has been reduced by world economic recession, slower increases in nuclear capacity and the continued availability of supplies of low-priced uranium. Reprocessing costs have risen and economics of scale favour large plants, which are therefore most likely to be built in countries with substantial thermal reactor capacities; these countries will be able to provide reprocessing services to others. As the ultimate strategic need for fast reactors has not been reduced by this slowdown it is important to continue the development and demonstration of fast-reactor technology and the associated fuel cycles. Uncertainties in future fuel prices mean that it could be advantageous to introduce fast reactors as soon as they become an economic, although not necessarily the most economic, choice. Notably, fast reactors may be installed initially when and where they become economic compared to coal-fired generation, in order to lay the foundation for more rapid expansion when economic break-even with thermal reactors occurs. (author)

Nuclear fuel element

International Nuclear Information System (INIS)

Hirama, H.

1978-01-01

A nuclear fuel element comprises an elongated tube having upper and lower end plugs fixed to both ends thereof and nuclear fuel pellets contained within the tube. The fuel pellets are held against the lower end plug by a spring which is supported by a setting structure. The setting structure is maintained at a proper position at the middle of the tube by a wedge effect caused by spring force exerted by the spring against a set of balls coacting with a tapered member of the setting structure thereby wedging the balls against the inner wall of the tube, and the setting structure is moved free by pushing with a push bar against the spring force so as to release the wedge effect

The chemistry of nuclear fuel waste disposal

International Nuclear Information System (INIS)

Wiles, D.R.

2002-01-01

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

Nuclear fuel tax in court

International Nuclear Information System (INIS)

Leidinger, Tobias

2014-01-01

Besides the 'Nuclear Energy Moratorium' (temporary shutdown of eight nuclear power plants after the Fukushima incident) and the legally decreed 'Nuclear Energy Phase-Out' (by the 13th AtG-amendment), also the legality of the nuclear fuel tax is being challenged in court. After receiving urgent legal proposals from 5 nuclear power plant operators, the Hamburg fiscal court (4V 154/13) temporarily obliged on 14 April 2014 respective main customs offices through 27 decisions to reimburse 2.2 b. Euro nuclear fuel tax to the operating companies. In all respects a remarkable process. It is not in favour of cleverness to impose a political target even accepting immense constitutional and union law risks. Taxation 'at any price' is neither a statement of state sovereignty nor one for a sound fiscal policy. Early and serious warnings of constitutional experts and specialists in the field of tax law with regard to the nuclear fuel tax were not lacking. (orig.)

Evolutionary developments of advanced PWR nuclear fuels and cladding materials

International Nuclear Information System (INIS)

Kim, Kyu-Tae

2013-01-01

Highlights: • PWR fuel and cladding materials development processes are provided. • Evolution of PWR advanced fuel in U.S.A. and in Korea is described. • Cutting-edge design features against grid-to-rod fretting and debris are explained. • High performance data of advanced grids, debris filters and claddings are given. -- Abstract: The evolutionary developments of advanced PWR fuels and cladding materials are explained with outstanding design features of nuclear fuel assembly components and zirconium-base cladding materials. The advanced PWR fuel and cladding materials development processes are also provided along with verification tests, which can be used as guidelines for newcomers planning to develop an advanced fuel for the first time. The up-to-date advanced fuels with the advanced cladding materials may provide a high level of economic utilization and reliable performance even under current and upcoming aggressive operating conditions. To be specific, nuclear fuel vendors may achieve high fuel burnup capability of between 45,000 and 65,000 MWD/MTU batch average, overpower thermal margin of as much as 15% and longer cycle length up to 24 months on the one hand and fuel failure rates of around 10 −6 on the other hand. However, there is still a need for better understanding of grid-to-rod fretting wear mechanisms leading to major PWR fuel defects in the world and subsequently a driving force for developing innovative spacer grid designs with zero fretting wear-induced fuel failure

Nuclear fuel cycle simulation system (VISTA)

International Nuclear Information System (INIS)

2007-02-01

The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. The VISTA model needs isotopic composition of spent nuclear fuel in order to make estimations of the material arisings from the nuclear reactor operation. For this purpose, in accordance with the requirements of the VISTA code, a new module called Calculating Actinide Inventory (CAIN) was developed. CAIN is a simple fuel depletion model which requires a small number of input parameters and gives results in a very short time. VISTA has been used internally by the IAEA for the estimation of: spent fuel discharge from the reactors worldwide, Pu accumulation in the discharged spent fuel, minor actinides (MA) accumulation in the spent fuel, and in the high level waste (HLW) since its development. The IAEA decided to disseminate the VISTA tool to Member States using internet capabilities in 2003. The improvement and expansion of the simulation code and the development of the internet version was started in 2004. A website was developed to introduce the simulation system to the visitors providing a simple nuclear material flow calculation tool. This website has been made available to Member States in 2005. The development work for the full internet version is expected to be fully available to the interested parties from IAEA Member States in 2007 on its website. This publication is the accompanying text which gives details of the modelling and an example scenario

Nuclear fuel manufacture

International Nuclear Information System (INIS)

Costello, J.M.

1980-09-01

The technologies used to manufacture nuclear fuel from uranium ore are outlined, with particular reference to the light water reactor fuel cycle. Capital and operating cost estimates for the processing stages are given, and the relevance to a developing uranium industry in Australia is discussed

Nuclear fuel cycle

International Nuclear Information System (INIS)

Niedrig, T.

1987-01-01

Nuclear fuel supply is viewed as a buyer's market of assured medium-term stability. Even on a long-term basis, no shortage is envisaged for all conceivable expansion schedules. The conversion and enrichment facilities developed since the mid-seventies have done much to stabilize the market, owing to the fact that one-sided political decisions by the USA can be counteracted efficiently. In view of the uncertainties concerning realistic nuclear waste management strategies, thermal recycling and mixed oxide fuel elements might increase their market share in the future. Capacities are being planned accordingly. (orig.) [de

Study on the high-precision laser welding technology of nuclear fuel elements processing

Energy Technology Data Exchange (ETDEWEB)

Kim, Soo Sung; Yang, M. S.; Kim, W. K.; Lee, D. Y

2001-01-01

The proper welding method for appendage of bearing pads and spacers of PHWR nuclear fuel elements is considered important in respect to the soundness of weldments and the improvement of the performance of nuclear fuels during the operation in reactor. The probability of welding defects of the appendage parts is mostly apt to occur and it is connected directly with the safty and life prediction of the nuclear reactor in operation. Recently there has been studied all over the world to develope welding technology by laser in nuclear fuel processing, and the appendage of bearing pads and spacers of PHWR nuclear fuel elements. Therefore, the purpose of this study is to investigate the characteristics of the laser welded specimens and make some samples for the appendage of bearing pads of PHWR nuclear fuel elements. This study will be also provide the basic data for the fabrications of the appendage of bearing pads and spacers. Especially the laser welding is supposed to be used in the practical application such as precise materials manufacturing fields. In this respect this technology is not only a basic advanced technology with wide applications but also likely to be used for the development of directly applicable technologies for industries, with high potential benefits derived in the view point of economy and industry.

Study on the high-precision laser welding technology of nuclear fuel elements processing

International Nuclear Information System (INIS)

Kim, Soo Sung; Yang, M. S.; Kim, W. K.; Lee, D. Y.

2001-01-01

The proper welding method for appendage of bearing pads and spacers of PHWR nuclear fuel elements is considered important in respect to the soundness of weldments and the improvement of the performance of nuclear fuels during the operation in reactor. The probability of welding defects of the appendage parts is mostly apt to occur and it is connected directly with the safty and life prediction of the nuclear reactor in operation. Recently there has been studied all over the world to develope welding technology by laser in nuclear fuel processing, and the appendage of bearing pads and spacers of PHWR nuclear fuel elements. Therefore, the purpose of this study is to investigate the characteristics of the laser welded specimens and make some samples for the appendage of bearing pads of PHWR nuclear fuel elements. This study will be also provide the basic data for the fabrications of the appendage of bearing pads and spacers. Especially the laser welding is supposed to be used in the practical application such as precise materials manufacturing fields. In this respect this technology is not only a basic advanced technology with wide applications but also likely to be used for the development of directly applicable technologies for industries, with high potential benefits derived in the view point of economy and industry

Sustainability Features of Nuclear Fuel Cycle Options

Directory of Open Access Journals (Sweden)

Stefano Passerini

2012-09-01

Full Text Available The nuclear fuel cycle is the series of stages that nuclear fuel materials go through in a cradle to grave framework. The Once Through Cycle (OTC is the current fuel cycle implemented in the United States; in which an appropriate form of the fuel is irradiated through a nuclear reactor only once before it is disposed of as waste. The discharged fuel contains materials that can be suitable for use as fuel. Thus, different types of fuel recycling technologies may be introduced in order to more fully utilize the energy potential of the fuel, or reduce the environmental impacts and proliferation concerns about the discarded fuel materials. Nuclear fuel cycle systems analysis is applied in this paper to attain a better understanding of the strengths and weaknesses of fuel cycle alternatives. Through the use of the nuclear fuel cycle analysis code CAFCA (Code for Advanced Fuel Cycle Analysis, the impact of a number of recycling technologies and the associated fuel cycle options is explored in the context of the U.S. energy scenario over 100 years. Particular focus is given to the quantification of Uranium utilization, the amount of Transuranic Material (TRU generated and the economics of the different options compared to the base-line case, the OTC option. It is concluded that LWRs and the OTC are likely to dominate the nuclear energy supply system for the period considered due to limitations on availability of TRU to initiate recycling technologies. While the introduction of U-235 initiated fast reactors can accelerate their penetration of the nuclear energy system, their higher capital cost may lead to continued preference for the LWR-OTC cycle.

Nuclear fuel cycle and legal regulations

International Nuclear Information System (INIS)

Shimoyama, Shunji; Kaneko, Koji.

1980-01-01

Nuclear fuel cycle is regulated as a whole in Japan by the law concerning regulation of nuclear raw materials, nuclear fuel materials and reactors (hereafter referred to as ''the law concerning regulation of reactors''), which was published in 1957, and has been amended 13 times. The law seeks to limit the use of atomic energy to peaceful objects, and nuclear fuel materials are controlled centering on the regulation of enterprises which employ nuclear fuel materials, namely regulating each enterprise. While the permission and report of uses are necessary for the employment of nuclear materials under Article 52 and 61 of the law concerning regulation of reactors, the permission provisions are not applied to three kinds of enterprises of refining, processing and reprocessing and the persons who install reactors as the exceptions in Article 52, when nuclear materials are used for the objects of the enterprises themselves. The enterprises of refining, processing and reprocessing and the persons who install reactors are stipulated respectively in the law. Accordingly the nuclear material regulations are applied only to the users of small quantity of such materials, namely universities, research institutes and hospitals. The nuclear fuel materials used in Japan which are imported under international contracts including the nuclear energy agreements between two countries are mostly covered by the security measures of IAEA as internationally controlled substances. (Okada, K.)

Nuclear fuel activities in Canada

Energy Technology Data Exchange (ETDEWEB)

Cox, D S [Fuel Development Branch, Chalk River Labs., AECL (Canada)

1997-12-01

Nuclear fuel activities in Canada are considered in the presentation on the following directions: Canadian utility fuel performance; CANDU owner`s group fuel programs; AECL advanced fuel program (high burnup fuel behaviour and development); Pu dispositioning (MOX) activities. 1 tab.

Economy and the fuel market

International Nuclear Information System (INIS)

1994-01-01

The nuclear fuel manufacturing constitutes a considerable venture for the competitiveness of the nuclear power sector although it represents a relatively modest fraction (around 4%) of the nuclear kWh cost. The COGEMA group is participating through its branches in the control of the most part (32%) of the world manufacturing capacity of fuel for PWR. Amounting up to 242 operating installations this reactor type is the most widespread in the world. The paper discusses the costs, the fuel clients and the fuel suppliers. Data concerning the boiling water and fast neutron reactors, geographical localization of the PWR and VVER reactors all over the world, the PWR and fuel for PWR manufacturers are also presented

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)

Renewed conception of nuclear sharing in solving the world power problems

International Nuclear Information System (INIS)

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

1996-01-01

The necessity of measures for timely preparation of new technologies for replacement of chemical fuel is discussed in connection with forecasted triplication of the world electrical energy production in the middle of the century. Nuclear fission is considered practically as the only version for stabilization of the oil and gas resources consumption. Development of nuclear technologies is concentrated at their evolutionary improvement. The fast reactors are considered in forecasts and programs to be used basically for the burnup of plutonium and long-living nuclides, accumulated in the light-water reactors

Nuclear fuel replacement device

International Nuclear Information System (INIS)

Ritz, W.C.; Robey, R.M.; Wett, J.F.

1984-01-01

A fuel handling arrangement for a liquid metal cooled nuclear reactor having a single rotating plug eccentric to the fuel core and a fuel handling machine radially movable along a slot in the plug with a transfer station disposed outside the fuel core but covered by the eccentric plug and within range of movement of said fuel handling machine to permit transfer of fuel assemblies between the core and the transfer station. (author)

Device for reprocessing nuclear fuels

International Nuclear Information System (INIS)

Hatano, Mamoru.

1981-01-01

Purpose: To readily discharge a nuclear fuel by burning the nuclear fuel as it is without a pulverizing step and removing the graphite and other coated fuel particles. Constitution: An oxygen supply pipe is connected to the lower portion of a discharge chamber having an inlet for the fuel, and an exhaust pipe is connected to the upper portion of the chamber. The fuel mounted on a metallic gripping member made of metallic material is inserted from the inlet, the gripping member is connected through a conductor to a voltage supply unit, oxygen is then supplied through the oxygen supply tube to the discharge chamber, the voltage supply unit is subsequently operated, and discharge takes place among the fuels. Thus, high heat is generated by the discharge, the graphite carbon of the fuel is burnt, silicon carbide is destroyed and decomposed, the isolated nuclear fuel particles are discharged from the exhaust port, and the combustion gas and small embers are exhausted from the exhaust tube. Accordingly, radioactive dusts are not so much generated as when using a mechanical pulverizing means, and prescribed objective can be achieved. (Yoshino, Y.)

Nuclear energy and its fuel cycle, prospects to 2025

International Nuclear Information System (INIS)

1987-01-01

Nuclear power will supply an increasing share of the world's electricity but will expand more slowly than had been expected, and no shortages of uranium or other fuel cycle services are foreseen before the end of the century. While exploration for new uranium deposits should continue to ensure long-term supplies, advances in reactor design and enrichment and reprocessing techniques could achieve reductions in uranium demand

ENUSA in the international market of nuclear fuel

International Nuclear Information System (INIS)

Gutierrez, J. E.; Gonzalez, R.

2002-01-01

ENUSA Industrias Avanzadas, s. a. has a promising future into the nuclear fuel world market evolving from a starting model of a state owned company focused on the Spanish market and using exclusively the technology coming from their American partners, to a current model of a modern company where technological innovation, the competitiveness and the quality are key factors in the developments of his business. ENUSA is a company oriented to the export sustained by the integrated services provided to the Spanish nuclear sector,where Europe is his natural market, but open to seek opportunities together with his technological partners into the American and Japanese market. (Author)

The case for innovation in nuclear reactor and fuel cycle designs

International Nuclear Information System (INIS)

Mourogov, V. M.

2000-01-01

Nuclear power is an important contributor to the world's electricity needs. In 1999 it supplied more than one-sixth of global electricity. Due to the fact that it is a capital intensive and sophisticated technology, the larger part of world nuclear capacity, i.e. 83 %, is concentrated in the industrialized countries, mainly OECD countries and economies in transition in Central and Eastern Europe (see table I and table II). Nuclear Power plays an important role in those industrialized countries by ensuring their energy independence, helping to keep the air clean and reducing carbon emissions. The development of nuclear power in industrialized countries was reached through intensive development of reactor manufacturing capabilities and a sophisticated fuel cycle infrastructure. The competitiveness of nuclear power was reached through developing large scale reactors units, between 1000-1600 MWe and aggressive NPP construction programmes. It is understood that waste management becomes economical within national waste repository concepts when the total national nuclear capacity reaches several GWe. Nuclear power plants are introduced in large electricity grids and they are used mainly for base load electricity generation

Reprocessing of nuclear fuels

International Nuclear Information System (INIS)

Hatfield, G.W.

1960-11-01

One of the persistent ideas concerning nuclear power is that the fuel costs are negligible. This, of course, is incorrect and, in fact, one of the major problems in the development of economic nuclear power is to get the cost of the fuel cycles down to an acceptable level. The irradiated fuel removed from the nuclear power reactors must be returned as fresh fuel into the system. Aside from the problems of handling and shipping involved in the reprocessing cycles, the two major steps are the chemical separation and the refabrication. The chemical separation covers the processing of the spent fuel to separate and recover the unburned fuel as well as the new fuel produced in the reactor. This includes the decontamination of these materials from other radioactive fission products formed in the reactor. Refabrication involves the working and sheathing of recycled fuel into the shapes and forms required by reactor design and the economics of the fabrication problem determines to a large extent the quality of the material required from the chemical treatment. At present there appear to be enough separating facilities in the United States and the United Kingdom to handle the recycling of fuel from power reactors for the next few years. However, we understand the costs of recycling fuel in these facilities will be high or low depend ing on whether or not the capital costs of the plant are included in the processing cost. Also, the present plants may not be well adapted to carry out the chemical processing of the very wide variety of power reactor fuel elements which are being considered and will continue to be considered over the years to come. (author)

Nuclear fuel assembly

International Nuclear Information System (INIS)

Ito, Arata; Wakamatsu, Mitsuo.

1976-01-01

Object: To permit the coolant in an FBR type reactor to enter from the entrance nozzle into a nuclear fuel assembly without causing cavitation. Structure: In a nuclear fuel assembly, which comprises a number of thin fuel pines bundled together at a uniform spacing and enclosed within an outer cylinder, with a handling head connected to an upper portion of the outer cylinder and an entrance nozzle connected to a lower portion of the cylinder, the inner surface of the entrance nozzle is provided with a buffer member and an orifice successively in the direction of flow of the coolant. The coolant entering from a low pressure coolant chamber into the entrance nozzle strikes the buffer member and is attenuated, and thereafter flows through an orifice into the outer cylinder. (Horiuchi, T.)

Crushing method for nuclear fuel powder

International Nuclear Information System (INIS)

Hasegawa, Shin-ichi; Tsuchiya, Haruo.

1997-01-01

A crushing medium is contained in mill pots disposed at the circumferential periphery of a main axis. The diameter of each mill pot is determined such that powdery nuclear fuels containing aggregated powders and ground and mixed powders do not reach criticality. A plurality of mill pots are revolved in the direction of the main axis while each pots rotating on its axis. Powdery nuclear fuels containing aggregated powders are conveyed to a supply portion of the moll pot, and an inert gas is supplied to the supply portion. The powdery nuclear fuels are supplied from the supply portion to the inside of the mill pots, and the powdery nuclear fuels containing aggregated powders are crushed by centrifugal force caused by the rotation and the revolving of the mill pots by means of the crushing medium. UO 2 powder in uranium oxide fuels can be crushed continuously. PuO 2 powder and UO 2 powder in MOX fuels can be crushed and mixed continuously. (I.N.)

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.

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)