WorldWideScience

Sample records for nuclear fuel export

  1. German nuclear fuel exports and imports 1990

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    The statistics compiled by the German Federal Office for Trade and Industry (Bundesamt fuer Wirtschaft) for the Federal Ministry for the Environment, Conservation of Nature, and Reactor Safety of imports and exports of nuclear fuels and source materials in 1990 show a major rise by 46.3% in imports and a pronounced drop by 44.3% in exports, compared to the levels in the previous year. Source material for the purposes of the statistics refers only to uranium concentrate. Quantitatively, the biggest import items are source materials, depleted uranium, and uranium enriched 3% to 10%. Exports of unirradiated material quantitatively comprise mainly depleted uranium, source materials, and uranium enriched up to 10%. (orig.) [de

  2. German nuclear fuel exports and imports 1991

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The statistics compiled by the German Federal Office for Trade and Industry (Bundesamt fuer Wirtschaft) for the Federal Ministry for the Environment, Conservation of Nature, and Reactor Safety of imports and exports of nuclear fuels and source materials in 1991 show a major drop by 33.8% in imports and a pronounced rise by 191.5% in exports, compared to the levels in the previous year. Source material for the purposes of these statistics refers only to uranium concentrate. Quantitatively, the biggest import items are source materials, depleted uranium, and uranium enriched up to 3%. Exports of unirradiated material quantitatively comprise mainly depleted uranium, source material, and uranium enriched up to 10%. (orig.) [de

  3. German imports and exports of nuclear fuels in 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This statistics of imports and exports of nuclear fuels and raw materials in 1980, compiled by Bundesamt for the Federal Minister of the Interior, shows a strong decrease of imports by 44.2% and a slight reduction of exports by 3.8%. The figures for 1979 are presented for comparison. (orig./UA) [de

  4. Germany's imports and exports of nuclear fuels in 1981

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    The statistics of imports and exports of nuclear fuels and basic materials which is set up by the Federal Authority for trade and industry for the Ministry of the Interior shows for 1981 (without taking the basic materials into account) a slight increase by 5% on the imports' side and also a slight increase by 10,5% on the exports' side. (orig./UA) [de

  5. German imports and exports of nuclear fuels in 1978

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The imports of nuclear fuels into the Federal Republic of Germany in 1978 rose by 67.9% to 1967 t over the previous year's level. Uranium enrichment in the Soviet Union resulted in a major rise in imports of natural uranium and re-imports of depleted uranium. Exports rose by 96.3% to 577 t. (orig./UA) [de

  6. Nuclear fuels imports and exports of the Federal Republic of Germany 1989

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The statistics compiled by the Federal Office for the Economy (Bundesamt fuer Wirtschaft) on behalf of the German Federal Ministry for the Environment, Nature Conservation and Reactor Safety of the imports and exports of nuclear fuels and source material in 1989 show a drop in imports by 29.5% and a considerable increase in exports by 104%. For comparison, the relevant figures of the preceding year are given in brackets throughout this statistical survey. (orig.) [de

  7. 1987 nuclear fuel imports and exports of the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The statistics of imports and exports of nuclear fuels and source materials compiled by the German Federal Office for Industry (Bundesamt fuer Wirtschaft) and the Federal Ministry for the Environment, Protection of Nature, and Reactor Safety (Bundesministerium fuer Umwelt, Naturschutz und Reaktorsicherheit) shows a 29.1% increase in imports and a 16.9% decrease of exports in 1987 compared to the previous year. A major rise was experienced in imports of natural uranium, uranium enriched up to 3% and to 3-10%, and plutonium, while there was a decline in imports of depleted uranium, source materials, and more highly enriched uranium. Uranium enriched 3-10%, highly enriched uranium, and plutonium were exported in larger quantities, while only smaller quantities of depleted uranium, source materials, natural uranium, uranium enriched up to 3%, and uranium enriched 10-85% were exported. (orig.) [de

  8. 1988 nuclear fuel imports and exports of the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The statistic of imports and exports of nuclear fuels and source materials compiled by the Federal Office for Industry on behalf of the Federal Ministry for the Environment, Nature Conservation, and Reactor Safety show a 32.3% decrease in imports and a 17.6% increase in exports in 1988 compared to the previous year. Most of the imports are made up of source materials, natural uranium, and uranium enriched up to 10%. The term 'source material' as used in these statistics refers only to uranium concentrate. A considerable increase is reported in imports of uranium enriched 3 to 10% and of plutonium. All other products have suffered major or minor decreases. (orig.)

  9. Russian nuclear industry exports

    International Nuclear Information System (INIS)

    Gorbatchev, A.

    2016-01-01

    Rosatom is the world leader for the export of nuclear technologies. 34 reactors of Russian technology are being built or planned worldwide. Most reactors proposed by Rosatom are third generation VVER-1200 units with an electric power output of 1200 MWe. Although the nuclear island is always built by Rosatom, the remain of the plant can be subcontracted to other enterprises and European companies are sought because they would bring a european quality touch to Russian works. One of the main assets of Rosatom is to propose an integrated offer from supplying nuclear fuel to managing nuclear waste via the turnkey building of nuclear power plants. Another important asset is the financial assistance of the Russian state through state credit or the support from Russian national banks that appears to be a decisive advantage in the international competition to win markets. We have to temper the Russian export perspectives by noting that most projects are set in countries that are prone to instabilities and that the economic crisis affecting Russia has a negative impact on its financial means. (A.C.)

  10. Nuclear export controls

    International Nuclear Information System (INIS)

    Thorne, C.E.

    1999-01-01

    One approach to describing the multilateral nuclear export controls is to do it according to time. This led to an interesting discovery, i.e. multilateral export controls have been defined by four distinct periods, the forst two of abut five years each, the second two about twice as long. These time periods have another interesting property. The two suppliers groups, which we will discuss in detail, have alternated in dominance over nearly thirty years. After describing the historical developments, the status of the present situation in multilateral nuclear export controls is examined, with the strengths and weaknesses. The future of multilateral nuclear export controls and possible ways that might be taken are considered

  11. Nuclear power plant exports

    International Nuclear Information System (INIS)

    Degot, D.

    1987-01-01

    Framatome export expertise is discussed. Framatome can accept different types of contracts - for the supply of nuclear steam supply systems or for nuclear islands (both of which can be produced solely by Framatome) or for complete plants. Cooperation with the local industry is possible -this can involve technology transfer. Examples of exports in the following countries are given; Belgium (where there is close cooperation between Framatome and two major companies), South Africa (where Framatome has been involved in the building of a two-992 MWe unit at Koeberg), South Korea (where Framatome is building two-900 MWe nuclear islands in cooperation with Korean industry, Knu 9 and Knu 10) and China (where Framatome is to build two-1000 MWe class pressurized water reactors at Daya Bay). As well as supplying the French domestic nuclear market Framatome is a major force in the future of nuclear power in the world. (UK)

  12. Export and import provisions for nuclear materials and power plants

    International Nuclear Information System (INIS)

    Malsch, M.G.

    1976-01-01

    The present paper deals with 1) statutory requirements for export and import licensing of nuclear reactors and fuels; 2) regulations and procedures to issuance of exportlicenses; 3) environmental impact of export licensing; 4) licensing of reactor equipment; 5) recent restrictions on imports and exports of nuclear fuels. (RW) [de

  13. 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

  14. Nuclear exporters cartel

    International Nuclear Information System (INIS)

    Mandelbaum, M.

    1977-01-01

    Events that have transpired in the past few years that have caused renewed concern about the spread of nuclear weapons are reviewed. Many proposals have been made recently for keeping the bomb from spreading. The author feels that the most novel and intriguing of them is the one advanced by Senator Abraham Ribicoff and Steven J. Baker; in their proposal, the world market for nuclear reactors would be divided into precisely defined shares among the industrial nations that now manufacture them for export; each exporter would be guaranteed a certain number of sales annually; and each would pledge not to sell uranium enrichment or plutonium reprocessing technology, as Germany did to Brazil. This might not halt proliferation, but it would give the world a few more years to find a solution

  15. The NPT and nuclear export controls

    International Nuclear Information System (INIS)

    Berkhout, F.

    1992-01-01

    Controls on the export of nuclear materials and technology were originally imposed in wartime and under the United States Atomic Energy Act of 1946 to restrict the supply of uranium. But there was no international agreement until the mid 1960s; before that the United States, Canada, France and the Soviet Union imposed export controls on a national basis. The Non-Proliferation Treaty, especially Articles I-IV, set out the first world wide controls on the nuclear trade. These articles are explained in the context of the relevant Committees (the Zangger Committee, the Committee on the Assurance of Supply, the National Export Committee and the Coordinating Committee for Multilateral Export Control) and Guidelines (the Nuclear Suppliers Guidelines and the International Nuclear Fuel Cycle Evaluation). Recent developments which have a bearing on nuclear trade, such as the single European market, the emergence of new supplies and the break-up of the Soviet Union, are considered. (UK)

  16. Nuclear plants: France and the export market

    International Nuclear Information System (INIS)

    Economic contingencies are causing the French industry to expand its activity abroad. After a review of the nuclear industry in France: uranium extraction, enrichment, irradiated fuel reprocessing and France's present programme; the competitive market among countries exporting and countries interested in importing nuclear power plants are examined. Finally France's position in the world nuclear power plant market is outlined with that of its foreign competitors [fr

  17. Feasibility study for Zaporozhye Nuclear Power Plant spent fuel dry storage facility in Ukraine. Export trade information

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    This document reports the results of a Feasibility Study sponsored by a TDA grant to Zaporozhye Nuclear Power Plant (ZNPP) in Ukraine to study the construction of storage facilities for spent nuclear fuel. It provides pertinent information to U.S. companies interested in marketing spent fuel storage technology and related business to countries of the former Soviet Union or Eastern Europe.

  18. 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

  19. 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

  20. Challenges to nuclear export controls today

    International Nuclear Information System (INIS)

    Chatelus, R.; Sevini, F.; Janssens, W.; Michel, Q.

    2014-01-01

    Nuclear energy and nuclear proliferation programs are potentially inter-twinned, which is a point to be taken into account when analysing the development of civil nuclear energy, both domestically and as foreign investment. International agreements ensure that the adhering countries fulfil their obligations and do not abuse civil nuclear programs for the production of nuclear weapons. Uranium enrichment is the process currently most focused on in this respect by recent news and recent technological and commercial developments. But also the so-called reactor-based pathway, with extraction of plutonium from spent nuclear fuel by reprocessing remains in the spotlight of inspectors. Two of the main and complementary pillars on which the prevention of such diversion relies, are Strategic Export Control and International Safeguards. Strategic export control is a key barrier against nuclear proliferation. In many countries including the EU, it is set by a legal framework, envisaging implementation, enforcement and prosecution. The goods that can exported only with authorisations are those identified by the international export control regimes; primarily the Nuclear Suppliers Group in the case of nuclear items. It is complemented by nuclear safeguards measures, and especially in the past few years, by the IAEA State Level concept, which looks at the overall country's potential, including its industrial structure to derive conclusions on the absence of undeclared activities. However, the strict control of goods and knowledge is a moving target, since technological developments, globalisation and the intensifying exchange of information via the worldwide web offer increasing opportunities to proliferators to acquire sensitive items and competencies, and create bigger challenges to enforcement, calling for new responses. Research and development programmes must be directed towards supporting the adaptation of current proliferation containment systems to these new

  1. Nuclear Export of Messenger RNA

    Directory of Open Access Journals (Sweden)

    Jun Katahira

    2015-03-01

    Full Text Available Transport of messenger RNA (mRNA from the nucleus to the cytoplasm is an essential step of eukaryotic gene expression. In the cell nucleus, a precursor mRNA undergoes a series of processing steps, including capping at the 5' ends, splicing and cleavage/polyadenylation at the 3' ends. During this process, the mRNA associates with a wide variety of proteins, forming a messenger ribonucleoprotein (mRNP particle. Association with factors involved in nuclear export also occurs during transcription and processing, and thus nuclear export is fully integrated into mRNA maturation. The coupling between mRNA maturation and nuclear export is an important mechanism for providing only fully functional and competent mRNA to the cytoplasmic translational machinery, thereby ensuring accuracy and swiftness of gene expression. This review describes the molecular mechanism of nuclear mRNA export mediated by the principal transport factors, including Tap-p15 and the TREX complex.

  2. Nuclear Export of Messenger RNA

    Science.gov (United States)

    Katahira, Jun

    2015-01-01

    Transport of messenger RNA (mRNA) from the nucleus to the cytoplasm is an essential step of eukaryotic gene expression. In the cell nucleus, a precursor mRNA undergoes a series of processing steps, including capping at the 5' ends, splicing and cleavage/polyadenylation at the 3' ends. During this process, the mRNA associates with a wide variety of proteins, forming a messenger ribonucleoprotein (mRNP) particle. Association with factors involved in nuclear export also occurs during transcription and processing, and thus nuclear export is fully integrated into mRNA maturation. The coupling between mRNA maturation and nuclear export is an important mechanism for providing only fully functional and competent mRNA to the cytoplasmic translational machinery, thereby ensuring accuracy and swiftness of gene expression. This review describes the molecular mechanism of nuclear mRNA export mediated by the principal transport factors, including Tap-p15 and the TREX complex. PMID:25836925

  3. Nuclear export controls and nuclear safeguards

    International Nuclear Information System (INIS)

    Sevini, F.

    2013-01-01

    The export control of dual use goods has developed since the early seventies to counter nuclear proliferation. The paper provides an overview of dual-use export control issues also in relation with the Additional Protocol to the Comprehensive Safeguards Agreement, which requires States to provide declarations of the export of the controlled items listed in its Annex II, derived from the Nuclear Suppliers Group Trigger list. Recommendations for improvement are proposed. On the EU level, the paper summarises the framework set by the European Council Regulation 428/2009, requiring Member States to impose control on exports, brokering and transit of dual use goods. The Regulation includes the so-called 'EU dual-use control list' integrating the lists of dual-use items defined by the international regimes and requires also the control on intangible technology transfers as foreseen by U.N. Security Council Resolution 1540. ESARDA has recently launched a new sub-Working Group on export control, which raised large interest and may evolve to a full-fledged working group. Export control may provide an opportunity of technical collaboration between ESARDA and INMM. The paper is followed by the slides of the presentation. (author)

  4. Export financing of nuclear power plants - banks experience

    International Nuclear Information System (INIS)

    Loeber

    1977-01-01

    1) Dimension and volume of the export financing of a nuclear power plant: 1.1) export orders of a new dimension; 1.2) individual loans occurring in connection with the export of a nuclear power plant: a) financial loans for maturities falling due under the export portion of the project; b) financial loans for the settlement of down- and interim payments to be made in connection with the export portion of the project; c) financial loans for the payment of local costs; d) loans for the financing of fuel elements; 2) governmental export insurance; 3) export financing in the individual industrial countries: USA, France, Great Britain, Japan (EXIMBANK), FRG. (orig./HP) [de

  5. Nuclear safeguards and export controls

    International Nuclear Information System (INIS)

    Mueller, H.

    1994-01-01

    Precisely from the perspective of the two most important nonnuclear weapons states, Japan and Germany, the safeguards and arms control agendas have not been finally dealt with. Because of their central position in the nonproliferation regime as nuclear suppliers and states with large nuclear energy industries, both countries are compelled to take a leading role in pursuing future reforms. In the dialogue with the nonaligned, this leadership position is helped by their nonnuclear status. In fact, Japan and Germany have some interests in common with the nonaligned states, such as the expansion of safeguards in the nuclear weapons states. To be sure, both Japan and Germany will pursue such interests with due regard to the interests of their friends and allies. For Japan, maintaining a close relationship with the United States is as important as shaping viable relations with China. Initiatives and controversies on nuclear policy must be weighed against this interest. By the same token, Germany must take into account the dense network of relations with its allies and with Russia, in addition to the German-French friendship. This will always set limits to Germany's readiness to confront the nuclear weapons states on nuclear issues. This, however, does not mean that both countries must shut up when the P 5 speak. The nuclear weapons register and the extension of the ''erga omnes'' rule in export controls, for example, should not be relegated to the dustbin of history, just because some friendly nuclear powers don't like these ideas. (orig.)

  6. 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.)

  7. Exporting nuclear engineering and the government's viewpoint

    International Nuclear Information System (INIS)

    Schill, H.

    1986-01-01

    The reasons for the government's positive attitude to nuclear engineering exports are explained, especially with regard to them being a compensation of the decreasing domestic demand. The federal government considers such exports to be necessary and correct for economical and energy-political reasons. Their contribution reaches from accompanying measures to the provision of state guarantees of export financing activities. (UA) [de

  8. Study on the establishment of effective nuclear export system

    International Nuclear Information System (INIS)

    Kim, Byung Koo; So, Dong Sup; Baik, Dae Hyun; Kwack, Eun Ho; Shin, Jang Soo; Yoon, Wan Ki; Park, Wan Soo; Kim, Hyun Tae.

    1997-02-01

    To improve Korean nuclear export control system, the modification of the present export license procedure for the nuclear equipment and materials and the classification of control items and their related technologies are required. And it is also necessary to make a database of the original countries who have the right of prior consent. For the efficient export control of LWR items to DPRK, it is desirable to manage the export license scheme of nuclear reactor facility as a total package, and to prepare a control regime for the retransfer of nuclear reactor component such as reactor coolant pump and nuclear fuel whose technologies are not self-reliant. It is especially essential to prepare a systematic procedure for the supply of nuclear equipment and materials to DPRK in order to meet international guidelines of NSG and others through an accord on the nuclear cooperation between Republic of Korea (ROK) and DPRK. The principal elements to be included in the accord are the range of cooperation, the restriction within the peaceful uses, prior consent right in case of retransfer of important nuclear reactor components and of storage, transfer and changes of nuclear fuels, application of safeguards to the supplied Trigger list items, physical protection of nuclear material, requirement of the return of nuclear equipment and materials, and restriction right for the suspension or termination of the agreement. (author). 40 refs., 5 tabs., 8 figs

  9. 10 CFR 110.21 - General license for the export of special nuclear material.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR... per year to any one country. (2) Special nuclear material in fuel elements as replacements for damaged...

  10. Nuclear exportation and importation - the Brazilian situation

    International Nuclear Information System (INIS)

    Lavos Coimbra, G.

    1986-01-01

    The author proposes to set up a working group which should be responsible for the compilation of laws, procedures, and national policies for the nuclear importation and exportation in the supplying and receiving countries. Shared international views would simplify the flow of imports and exports between the countries. The author describes the different phases of exportation and importation of nuclear material are processed in her country, Brazil. (CW) [de

  11. 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

  12. Exporting nuclear engineering and the industry's viewpoint

    International Nuclear Information System (INIS)

    Barthelt, K.

    1986-01-01

    Nuclear energy offers all possibilities to reduce the energy problems in the world which arise with the world-wide increasing population and the energy demand connected with it. The Federal Republic of Germany lives on the exports of refined technical methods which also include nuclear engineering. The exports of nuclear engineering should lead to a technology transfer with guidance and training on an equal basis between the industrial and developing countries. The preconditions of exporting nuclear-technical systems are a well-functioning domestic market and a certain support by the government, especially with regard to giving guarantees for the special exports risks of these big projects. On the other hand, exports are also needed in order to be able to continue providing high-level technology for the domestic market. (UA) [de

  13. Nuclear export controls - Closing the gaps

    International Nuclear Information System (INIS)

    Schmidt, Fritz W.

    2005-01-01

    Concerns over a nuclear 'black market' have focused international attention on the effectiveness of nuclear export controls. IAEA Director General Mohamed ElBaradei has stated that the emergence of a multinational illicit network demonstrated the inadequacy of the present export control system, that international cooperation on export controls lay on informal arrangements that were not only not binding but also limited in membership, and that export control information was not systematically shared with the IAEA. This criticism, often heard on the political level, does not really do justice to the work of export control groups. The emergence of a multinational illicit network does not necessarily prove failures in export control systems. Criminal activities, by definition, try to circumvent existing rules and regulations, or they exploit the absence of such rules on State level. To fight such individual cases is not so much a task of regular export control systems, whose function lies primarily in establishing standards and procedures for export controls on State level, but rather the task for intelligence services and their international cooperation. The basis of the export control regime is the Nuclear Non-Proliferation Treaty (NPT). Export controls can - and do - play an important role in fostering this universality goal by demanding the implementation of internationally agreed security standards in recipient countries before export licenses are granted. Drawn from the deliberations in the NPT conferences, the current standards to be demanded as conditions of supply are the following: Safeguards, Physical Protection, National export control provisions. According to the NPT system, export controls require IAEA verification in the recipient country. In addition, export controls enable States to provide information to the IAEA on exports and imports as required by the Additional Protocol. The 2005 NPT Review Conference will be an opportunity to review developments

  14. How the Eximbank helps US nuclear exporters

    International Nuclear Information System (INIS)

    Moore, J.L. Jr.

    1981-01-01

    The way in which the Export-Import Bank operates in support of the United States nuclear industry noting particularly its flexibility in responding to changing needs and budget constraints is described. (author)

  15. Exporting apocalypse: CANDU reactors and nuclear proliferation

    International Nuclear Information System (INIS)

    McKay, Paul.

    The author believes that the peaceful use of nuclear technology leads inevitably to the production of nuclear weapons, and that CANDU reactors are being bought by countries that are likely to build bombs. He states that exports of reactors and nuclear materials cannot be defended and must be stopped

  16. Nuclear exports. Parliamentary control and confidentiality

    International Nuclear Information System (INIS)

    Feldmann, Ulrike

    2015-01-01

    With its decision taken on 21. October 2014 (Az.: 2 BvE 5/11) the Federal Constitutional Court (BVerfG) decided during court proceedings between administrative bodies on the scope and limits of the parliamentary right of information. Even though the proceeding did not deal with nuclear exports but arm exports, foreign trade law, however, does not only designate an export licence obligation for military weapons but also for so called dual-use goods meaning goods, which can be used both for friendly as well as for military purposes. The export of these goods requires according to the so-called Dual-Use Regulation (EG) 428/2009 a licence. Annex I category 0 of the regulation (EG) 428/2009 lists a variety of nuclear materials, plants and equipment items for which this licence applies. In the same manner as arm exports, also exports of nuclear dual-use goods are being discussed in a special cabinet committee, the Federal Security Council (BSR), which shall coordinate cross-departmentally the German security and defence policy under consideration of economic interests and which categorises its results, according to the rules of procedure, as confidential. Also legally not regulated but common ''preliminary enquiries'' at the responsible Federal Ministry or rather Federal Office of Economics and Export Control by companies which plan an export and want to affirm the general approval for their export business prior to conclusion of contract take not only place for arm exports but also for nuclear dual-use goods. The decision by the Federal Constitutional Court can be applied to consultations about the authorisation of nuclear dual-use goods.

  17. Improved nuclear fuel element

    International Nuclear Information System (INIS)

    Gordon, G.M.; Cowan, R.L. II; Davies, J.H.

    1975-01-01

    A nuclear fuel element is described. It includes a central nuclear fuel core and a composite cladding composed of a substrate, the inner face of which is coated with copper, nickel, iron or one of their alloys. The nuclear fuel is selected from uranium compounds, plutonium compounds or mixtures thereof. The substrate is selected from zirconium and zirconium alloys [fr

  18. 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

  19. 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

  20. 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)

  1. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1981-01-01

    An array of rods comprising zirconium alloy sheathed nuclear fuel pellets assembled to form a fuel element for a pressurised water reactor is claimed. The helium gas pressure within each rod differs substantially from that of its closest neighbours

  2. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1984-01-01

    The fuel elements for a pressurised water reactor comprise arrays of rods of zirconium alloy sheathed nuclear fuel pellets. The helium gas pressure within each rod differs substantially from that of its closest neighbours

  3. Improved nuclear fuel element

    International Nuclear Information System (INIS)

    Gordon, G.M.; Cowan, R.L. II.

    1975-01-01

    A nuclear fuel element is described. It includes a central nuclear fuel core and a composite cladding, composed of a substrate with two coatings on its inner face, the first coating being a diffusion barrier and the second a metal coating. The metal coating is in copper, nickel or iron. The substrate is a zirconium alloy. The diffusion barrier is in chromium or chromium alloy. The nuclear fuel is a uranium or plutonium compound or a mixture of both [fr

  4. 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

  5. Fuel-consumption reflects increasing export

    International Nuclear Information System (INIS)

    TREND

    2003-01-01

    Fuel consumption in Slovakia has been substantially rising during the first three months of this year. During January and February about 6 percent more petrol and 15 percent more diesel fuel were sold compared to last year. Retail sales were growing even faster, informed president of Slovak Association of Petroleum Industry and Trade (SAPPO), Karoly Robak. He considers this an evidence of a substantial economic growth. The export is executed in form of freight transport (lorries), as this, together with agriculture, is the largest diesel fuel consumer. K. Robak, who at the same time is the Deputy General Manager For Retail at Slovnaft, a.s., Bratislava, expects the sales of fuel to grow by about 8 percent this year. Low prices due to a weaker US dollar should only support these tendencies. Last year the sales grew by 8,3 percent and in retail business the increase exceeded 10 percent. At the moment there are about 700 petrol stations in Slovakia (SAPPO) and over 330 out of them are owned by Slovnaft. The sale of fuel is now moving more to the retail business - to petrol stations as the price difference between retail and wholesale is decreasing. Last year for instance the wholesale recorded an increase in sales of diesel by 6,5 percent whereas retail sales grew by 17 percent. With petrol the situation was similar - 6,4 increase in retail sales and 2,5 percent in wholesale. (Author)

  6. 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.)

  7. Notice to exporters on products prohibited from export (nuclear material, equipment and large nuclear units)

    International Nuclear Information System (INIS)

    1988-01-01

    In order to ensure that the policy to avoid the proliferation of nuclear weapons is complied with, the French Administration applies stricter controls over the export of certain sensitive products, materials and equipment. To this effect, lists of such products, materials and equipment are published in the form of Notices to exporters and periodically revised. This Notice repeals and replaces the previous Notice published in the Official Gazette of 21 January 1986. Annex I contains the list of materials whose export is subject to nuclear non-proliferation controls. Annex II lists the equipment whose export is subject to the same controls. Annex III includes the list of large nuclear units for which an application for prior approval of export must be submitted to the Administrations concerned. (NEA) [fr

  8. 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

  9. Nuclear technology and the export control laws

    International Nuclear Information System (INIS)

    Munroe, J.L.; Pankratz, M.C.; Hogsett, V.H.; Lundy, A.S.

    1988-01-01

    Three basic US laws regulate the export of commodities, services, and technical data. People working in nuclear fields need to know of these laws and their impact on professional endeavors. Export of technical data means the communication of any information by oral, written, or any other means to foreign nationals within or outside the US. The medium for the communication may be a model, blueprint, sketch, or any other device that can convey information. If the data relates to items on one of the control lists, a license must be sought from the appropriated federal agency. The Militarily Critical Technologies List (MCTL), though not itself a control list, plays a major role in determining what technical data will require a validated license. The US Department of Energy (DOE), through Technical Working Gorup (TWG) 11, is responsible for the Nuclear Technology chapter of the MCTL. TWG 11 also prepares the Nuclear Technology Reference Book (NTRB), a classified guide to sensitive nuclear technology

  10. The politics of nuclear exports in West Germany

    International Nuclear Information System (INIS)

    Haeckel, E.

    1983-01-01

    The subject is discussed under the headings: nuclear energy and policy making in West Germany; the significance of nuclear exports for West Germany (industrial employment; table of reactors exported); the significance of the German role in international nuclear commerce (world politics; table of national shares in world nuclear exports); export policy of the Federal Government (adherence to IAEA safeguards; Non-Proliferation Treaty; international cooperation). (U.K.)

  11. 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

  12. 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)

  13. The nuclear fuel cycle

    International Nuclear Information System (INIS)

    Vernaz, Etienne

    2015-10-01

    The author proposes an overview of the different steps of the nuclear fuel cycle: uranium mining (applied processes, formation of Yellow Cake), conversion into uranium hexafluoride (UF 6 ) for enrichment purposes, enrichment (physical methods and plants), nuclear fuel fabrication (description of a fuel assembly), physical, chemical and radiological evolution of the nuclear fuel in the reactor, spent fuel warehousing, spent fuel processing (dissolution, methods of liquid/liquid extraction, output products), effluents and by-products, recycling of valuable materials (URE, MOX, RNR and others), waste containment for the different waste types regarding their radioactivity level and lifetime (vitrification, shell compacting, cementation, and other processes). The author also presents the French policy and choices regarding spent fuel processing and waste management

  14. 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.)

  15. Loviisa nuclear fuel service

    International Nuclear Information System (INIS)

    Haegg, P.E.; Koskivirta, O.

    1990-01-01

    The nuclear fuel service of the both units of Loviisa NPS is based on longterm fresh fuel purchasing contracts and longterm spent fuel return contracts. These contracts belong to the Soviet delivery package of Loviisa NPS and they have been made separately for the both units for their whole lifetime. The Soviet contract party is v/o Techsnabexport. Fresh fuel is ordered at the beginning of the year preceding the delivery year. The delivery takes place about one and half years earlier than the fuel is loaded into reactor. The irradiation time of the fuel is typically three years (partly two years). Spent fuel is stored at site in different storage pools five years before its returning to tbe Soviet Union. Altogether the nuclear fuel is staying at Loviisa about ten years

  16. 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.

  17. 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)

  18. 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.)

  19. 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.)

  20. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

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

    1983-07-01

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

  1. Nuclear Fuel Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Michael F. Simpson; Jack D. Law

    2010-02-01

    This is an a submission for the Encyclopedia of Sustainable Technology on the subject of Reprocessing Spent Nuclear Fuel. No formal abstract was required for the article. The full article will be attached.

  2. Nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    White, D.

    1981-01-01

    A simple friction device for cutting nuclear fuel wrappers comprising a thin metal disc clamped between two large diameter clamping plates. A stream of gas ejected from a nozzle is used as coolant. The device may be maintained remotely. (author)

  3. Nuclear fuel element

    Science.gov (United States)

    Zocher, Roy W.

    1991-01-01

    A nuclear fuel element and a method of manufacturing the element. The fuel element is comprised of a metal primary container and a fuel pellet which is located inside it and which is often fragmented. The primary container is subjected to elevated pressure and temperature to deform the container such that the container conforms to the fuel pellet, that is, such that the container is in substantial contact with the surface of the pellet. This conformance eliminates clearances which permit rubbing together of fuel pellet fragments and rubbing of fuel pellet fragments against the container, thus reducing the amount of dust inside the fuel container and the amount of dust which may escape in the event of container breach. Also, as a result of the inventive method, fuel pellet fragments tend to adhere to one another to form a coherent non-fragmented mass; this reduces the tendency of a fragment to pierce the container in the event of impact.

  4. The nuclear fuel cycle

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    This chapter explains the distinction between fissile and fertile materials, examines briefly the processes involved in fuel manufacture and management, describes the alternative nuclear fuel cycles and considers their advantages and disadvantages. Fuel management is usually divided into three stages; the front end stage of production and fabrication, the back end stage which deals with the fuel after it is removed from the reactor (including reprocessing and waste treatment) and the stage in between when the fuel is actually in the reactor. These stages are illustrated and explained in detail. The plutonium fuel cycle and thorium-uranium-233 fuel cycle are explained. The differences between fuels for thermal reactors and fast reactors are explained. (U.K.)

  5. Nuclear Fuel Management Optimization

    Energy Technology Data Exchange (ETDEWEB)

    Karve, A.A.; Keller, P.M.; Turinsky, P.J.; Maldonado, G.I.

    2001-06-17

    The nuclear fuel management design optimization problem has grown more challenging and important with the passage of time. In this paper, we summarize our research on this design optimization problem. A suite of computer codes that aid in making nuclear fuel management decisions has been developed. These codes utilize stochastic optimization techniques to search the decision space for determining the family of near-optimum decisions in the suboptimization problem being solved.

  6. A common high standard for nuclear power plant exports: overview and analysis of the Nuclear Power Plant Exporters' Principles of Conduct

    International Nuclear Information System (INIS)

    Perkovich, George; Radzinsky, Brian

    2012-01-01

    At this time, there is no overarching global framework to regulate the development of the nuclear power industry. Laws concerning the export of nuclear technology vary across jurisdictions, and politically-binding arrangements such as the Nuclear Suppliers Group (NSG) help ensure that weapons-usable or dual-use technologies are not exported, but no single international regime or agreement manages the gamut of potential risks that may arise from the export of civilian nuclear power plants. Accordingly in 2008, the Carnegie Endowment for International Peace convened internationally-recognised experts in nuclear energy to begin a dialogue with nuclear power plant vendors about defining common criteria for the socially responsible export of nuclear power plants. The goal was to articulate a comprehensive set of principles and best practices that would raise the overall standard of practice for exports of nuclear power plants while enjoying widespread support and adherence. The outcome of this process is the Nuclear Power Plant Exporters' Principles of Conduct - an export-oriented code of conduct for nuclear power plant vendors. The Principles of Conduct help ensure that the participating companies will proceed with the sale of a new nuclear power plant only after a careful assessment of the legal, political, and technical contexts surrounding potential customers. It comprises six 'principles' that each address a major area of concern involved in the export of a nuclear power plant: safety, physical security, environmental protection and spent fuel management, systems of compensation for nuclear damage, non-proliferation and safeguards, and business ethics. The Principles of Conduct entail vendor responsibilities to apply specific standards or engage in certain practices before signing contracts and during the marketing and construction phases of a nuclear power plant export project. Conformity with the Principles of Conduct is voluntary and not-legally binding, but the

  7. 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

  8. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Butterfield, C.E.; Waite, E.

    1982-01-01

    A nuclear reactor fuel element comprising a column of vibration compacted fuel which is retained in consolidated condition by a thimble shaped plug. The plug is wedged into gripping engagement with the wall of the sheath by a wedge. The wedge material has a lower coefficient of expansion than the sheath material so that at reactor operating temperature the retainer can relax sufficient to accommodate thermal expansion of the column of fuel. (author)

  9. 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

  10. Nuclear Fuel Cycle Objectives

    International Nuclear Information System (INIS)

    2013-01-01

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

  11. 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

  12. 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

  13. Nuclear fuel pin scanner

    Science.gov (United States)

    Bramblett, Richard L.; Preskitt, Charles A.

    1987-03-03

    Systems and methods for inspection of nuclear fuel pins to determine fiss loading and uniformity. The system includes infeed mechanisms which stockpile, identify and install nuclear fuel pins into an irradiator. The irradiator provides extended activation times using an approximately cylindrical arrangement of numerous fuel pins. The fuel pins can be arranged in a magazine which is rotated about a longitudinal axis of rotation. A source of activating radiation is positioned equidistant from the fuel pins along the longitudinal axis of rotation. The source of activating radiation is preferably oscillated along the axis to uniformly activate the fuel pins. A detector is provided downstream of the irradiator. The detector uses a plurality of detector elements arranged in an axial array. Each detector element inspects a segment of the fuel pin. The activated fuel pin being inspected in the detector is oscillated repeatedly over a distance equal to the spacing between adjacent detector elements, thereby multiplying the effective time available for detecting radiation emissions from the activated fuel pin.

  14. 10 CFR Appendix O to Part 110 - Illustrative List of Fuel Element Fabrication Plant Equipment and Components Under NRC's Export...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Illustrative List of Fuel Element Fabrication Plant... Appendix O to Part 110—Illustrative List of Fuel Element Fabrication Plant Equipment and Components Under NRC's Export Licensing Authority Note: Nuclear fuel elements are manufactured from source or special...

  15. 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)

  16. Overview of nuclear export policies of major foreign supplier nations

    International Nuclear Information System (INIS)

    1977-01-01

    The United States faces increased competition from foreign nuclear suppliers, including West Germany, France, the United Kingdom, Canada, and possibly, in the near future, Japan. This general overview shows the differences and similarities in foreign nuclear supplier export requirements. It is based on summaries furnished by the Department of State covering the nuclear export policies and procedures of the major foreign supplier nations

  17. Prospects for Australian involvement in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Chandra, S.; Hallenstein, C.

    1988-05-01

    A review of recent overseas developments in the nuclear industry by The Northern Territory Department of Mines and Energy suggests that there are market prospects in all stages of the fuel cycle. Australia could secure those markets through aggressive marketing and competitive prices. This report gives a profile of the nuclear fuel cycle and nuclear fuel cycle technologies, and describes the prospects of Australian involvement in the nuclear fuel cycle. It concludes that the nuclear fuel cycle industry has the potential to earn around $10 billion per year in export income. It recommend that the Federal Government: (1) re-examines its position on the Slayter recommendation (1984) that Australia should develop new uranium mines and further stages of the nuclear fuel cycle, and (2) gives it's in-principle agreement to the Northern Territory to seek expressions of interest from the nuclear industry for the establishment of an integrated nuclear fuel cycle industry in the Northern Territory

  18. Nuclear Fuel Cycle; (USA)

    Energy Technology Data Exchange (ETDEWEB)

    Cason, D.L.; Hicks, S.C. (eds.)

    1991-01-01

    Nuclear Fuel Cycle (NFC) announces on a monthly basis the current worldwide information available from the open literature on all aspects of the fuel cycle except in-reactor properties and performance of fuels. More information related to radioactive waste and to the transport and storage of spent fuel is included in the current awareness publication, Radioactive Waste Management. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are other US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Technology Data Exchange, the International Atomic Energy Agency's International Nuclear Information System, or government-to-government agreements. The digests in NFC on nuclear fuel back to 1948 are available for online searching and retrieval in EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

  19. 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

  20. 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

  1. Nuclear fuel assembly repair

    International Nuclear Information System (INIS)

    Bassler, E.A.; Stavsky, R.

    1986-01-01

    In response to utility needs to recover investment in nuclear fuel assemblies, Westinghouse Electric Corporation has developed tools and equipment to repair damaged fuel assemblies in an economical and safe manner, to enable utilities to reinsert these assemblies in the core. There are two possible repair techniques - bottom nozzle reconstitution and top nozzle reconstitution. Both techniques have been approved through formal design review; prototype tools have been built and successfully tested. The tools are modular in nature, easily transportable, and designed to fit the spent fuel pool at a reactor site. (author)

  2. Nuclear fuel assembly

    International Nuclear Information System (INIS)

    Domoto, Noboru; Masuda, Hiroyuki

    1989-01-01

    In a nuclear fuel assembly loaded with a plurality of fuel rods, the inside of a fuel rod disposed at a high neutron flux region is divided into an inner region and an outer region, and more burnable poisons are mixed in the inner region than in the outer region. Alternatively, the central portion of a pellet disposed in a high neutron flux region is made hollow, in which burnable poisons are charged. This can prevent neutron infinite multiplication factor from decreasing extremely at the initial burning stage. Further, the burnable poisons are not rapidly burnt completely and local peaking coefficient can be controlled. Accordingly, in a case of suppressing a predetermined excess reactivity by using a fuel rod incorporated with the burnable poison, the fuel economy can be improved more and the reactor core controllability can also be improved as compared with the usual case. (T.M.)

  3. Nuclear export criteria and controls in the United States

    International Nuclear Information System (INIS)

    Shapar, H.K.

    1979-01-01

    The paper describes the export licensing procedure and the modifications made to it under the 1978 Nuclear Non-Proliferation Act (NNPA) to achieve greater control over exports of nuclear material and facilities. Export licences from the Nuclear Regulatory Commission are now required for certain items connected with nuclear plant construction and the procedure for obtaining the views of the Executive Branch have been formalised. The President is enabled to override the denial of an export licence by the NRC. Amongst the new criteria on the export licensing procedure added to the 1954 Atomic Energy Act, the NNPA provides that the IAEA Safeguards under the Non-Proliferation Treaty are applicable to exported nuclear material or facilities, together with adequate physical protection measures. (NEA) [fr

  4. Encapsulating spent nuclear fuel

    International Nuclear Information System (INIS)

    Fleischer, L.R.; Gunasekaran, M.

    1979-01-01

    A system is described for encapsulating spent nuclear fuel discharged from nuclear reactors in the form of rods or multi-rod assemblies. The rods are completely and contiguously enclosed in concrete in which metallic fibres are incorporated to increase thermal conductivity and polymers to decrease fluid permeability. This technique provides the advantage of acceptable long-term stability for storage over the conventional underwater storage method. Examples are given of suitable concrete compositions. (UK)

  5. The politics of fading dreams: Britain and the nuclear export business

    International Nuclear Information System (INIS)

    Boardman, R.; Grieve, M.

    1983-01-01

    The subject is discussed as follows: introduction to a chapter focused on the politics of Britain's foreign nuclear trade; export goals and the nuclear programme (discussion of Magnox, AGR, SGHWR and PWR); the pursuit of exports; nuclear exports and proliferation (reprocessing; fast reactors; plutonium; INFCE); public opinion, nuclear power and exports (interest groups); conclusions (Britain's nuclear exports and non-proliferation). (U.K.)

  6. Nuclear fuel transport flasks

    International Nuclear Information System (INIS)

    Burgess, M.H.; Fry, C.J.

    1984-01-01

    A nuclear fuel transport flask has a surrounding structure carrying inwardly directed heat transfer fins additional to the normal outwardly directed heat transfer fins on the main body of the flask. The additional fins can be interleaved with the main fins, and the structure carrying the additional fins can either be a shroud or an open framework. (author)

  7. 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

  8. Integral nuclear fuel element assembly

    International Nuclear Information System (INIS)

    Schluderberg, D. C.

    1985-01-01

    An integral nuclear fuel element assembly utilizes longitudinally finned fuel pins. The continuous or interrupted fins of the fuel pins are brazed to fins of juxtaposed fuel pins or directly to the juxtaposed fuel pins or both. The integrally brazed fuel assembly is designed to satisfy the thermal and hydraulic requirements of a fuel assembly lattice having moderator to fuel atom ratios required to achieve high conversion and breeding ratios

  9. 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

  10. Analysis and prediction of leucine-rich nuclear export signals

    DEFF Research Database (Denmark)

    La Cour, T.; Kiemer, Lars; Mølgaard, Anne

    2004-01-01

    We present a thorough analysis of nuclear export signals and a prediction server, which we have made publicly available. The machine learning prediction method is a significant improvement over the generally used consensus patterns. Nuclear export signals (NESs) are extremely important regulators...

  11. Political implications of US nuclear-export-policy development

    International Nuclear Information System (INIS)

    Johnson-Freese, J.S.

    1981-01-01

    There has been a great deal of international debate regarding how effective strict export controls on nuclear-energy supplies are toward a non-proliferation goal. With the Carter Administration, the debate was heightened by a new, more-vigorous US nuclear-export policy, much of which was codified by the Nuclear Non-Proliferation Act of 1978 (NNPA). Because of the US position in both the international non-proliferation regime and nuclear export market, the NNPA has had far-reaching consequences. The thesis of this paper is that a nuclear-export policy that fails to consider its short-term ramifications, as the NNPA has been accused of, will be self-defeating. If the US wants a viable worldwide nuclear non-proliferation policy, it must first direct its efforts toward building a domestic non-proliferation consensus, and then worldwide, rather than first setting a highly controversial policy and expecting other nations to fall into line. This work provides a comprehensive case study of US nuclear-export policy between the years 1976 to 1980 in support of the thesis. Further, the behavior and impact of the interest groups which seem to shape US nuclear-export policies is examined, and recommendations made regarding the role of groups in nuclear policy-making and implementation. Finally, recommendations are made regarding non-proliferation policy for the future, as it relates to nuclear exports

  12. nuclear fuel design criteria

    International Nuclear Information System (INIS)

    Can, S.

    1997-01-01

    Nuclear fuel design is strictly dependent on reactor type and experiences obtained from performance of nuclear fuels. The objectives of the design are reliability, and economy. Nuclear fuel design requires an interdisciplinary work which has to cover, at least nuclear design, thermalhydraulic design, mechanical design, and material properties.The procedure of design, as describe in the quality assurance, consist of a number of steps. The most important parts are: Design description or inputs, preliminary design, detailed design and design output, and design verification. The first step covers objectives and requirements, as defined by the customer and by the regulatory authority for product performance,environmental factors, safety, etc. The second describes assumptions and alternatives, safety, economy and engineering analyses. The third covers technical specifications, design drawings, selection of QA program category, etc. The most important form of design verification is design review by qualified independent internal or external reviewers. The scope of the review depends on the specific character of the design work. Personnel involved in verification and review do not assume prime responsibility for detecting errors. Responsibility for the design remains with the personnel involved in the design work

  13. Study on international publicity and export strategy establishment of nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ji Bok; Choi, C.O.; Park, K. B.; Chang, M. H.; Kim, K. K.; Yang, M. S.; Jung, I. H.; Kim, K. P.; Wu, J. S.; Jang, C. I.; Han, B. O.; Sim, J. H.; Chung, M.; Chung, J.K

    1999-05-01

    The objective of this study is to devise a proper measure for international publicity and technology export strategy. Analysed and summaries in detail are other countries nuclear policy trend and the current technology development status of Korea Standard Nuclear Plant that we developed on our own technology, design and construction technology for research reactor, System-integrated Modular Advanced Reactor of which design is in progress, Direct use of Spent PWR Fuel in CANDU Reactors, and Radioisotopes. Based on that, the measures are proposed for the export industrialization of nuclear technology and establishment of the export basis. Also the international nuclear cooperation and publicity strategy are suggested to support the technology export basis. By surveying the world nuclear status, the direction for the international cooperation and publicity is settled and the specific publicity strategy is proposed for the cooperation with IAEA and multi-countries and the establishment of the nuclear technology export basis. As part of this project, the panel on major technologies such as Korea Standard Nuclear Plant, HANARO, and System-integrated Modular Advanced Reactor was displayed successfully at the IAEA meeting, which contribute much to the publicity of our nuclear technology to the international nuclear society. (author)

  14. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E. D.

    1984-01-01

    An array of rods is assembled to form a fuel element for a pressurized water reactor, the rods comprising zirconium alloy sheathed nuclear fuel pellets and containing helium. The helium gas pressure is selected for each rod so that it differs substantially from the helium gas pressure in its closest neighbors. In a preferred arrangement the rods are arranged in a square lattice and the helium gas pressure alternates between a relatively high value and a relatively low value so that each rod has as its closest neighbors up to four rods containing helium gas at the other pressure value

  15. Nuclear reactor fuel elements

    Energy Technology Data Exchange (ETDEWEB)

    Hindle, E. D.

    1984-10-16

    An array of rods is assembled to form a fuel element for a pressurized water reactor, the rods comprising zirconium alloy sheathed nuclear fuel pellets and containing helium. The helium gas pressure is selected for each rod so that it differs substantially from the helium gas pressure in its closest neighbors. In a preferred arrangement the rods are arranged in a square lattice and the helium gas pressure alternates between a relatively high value and a relatively low value so that each rod has as its closest neighbors up to four rods containing helium gas at the other pressure value.

  16. Nuclear fuel subassembly

    International Nuclear Information System (INIS)

    Cayol, A.; Chalony, A.; Clottes, G.; Praizey, J.P.; Skok, J.; Venobre, H.

    1976-01-01

    A nuclear fuel sub-assembly is described which comprises a bundle of fuel pins provided with helical spacers and located within a shroud for the coolant. The sub-channels at the periphery of the bundle are restricted in order that the rate of flow matches the heat transfer surfaces in all sub-channels. For this purpose the spacers of the outer pins project radially by an extent smaller than the spacers of the inner pins. In addition longitudinal ribs may be provided in the outer sub-channels

  17. Nuclear fuel assembly

    International Nuclear Information System (INIS)

    1975-01-01

    The nuclear fuel assembly described includes a cluster of fuel elements supported at a distance from each other so that their axes are parallel in order to establish secondary channels between them reserved for the coolant. Several ducts for an auxiliary cooling fluid are arranged in the cluster. The wall of each duct is pierced with coolant ejection holes which are placed circumferentially to a pre-determined pattern established according to the position of the duct in the cluster and by the axial distance of the ejection hole along the duct. This assembly is intended for reactors cooled by light or heavy water [fr

  18. Fabrication of nuclear fuel

    International Nuclear Information System (INIS)

    Ion, S.E.; Watson, R.H.; Loch, E.P.

    1989-01-01

    Commercial nuclear fuel fabrication is focused on providing quality products. Throughout manufacturing attention is placed on the precise control of processes, procedures and tooling to reduce product variability. This paper describes the processes used to manufacture fuel for the advanced gas cooled reactor, light water reactor, fast breeder reactor and Magnox reactor systems at the BNFL, Springfields, and Westinghouse Columbia, USA, facilities. It covers the chemical purification and conversion stages of fuel production before describing the fabrication of both oxide and metallic fuel and gives a general overview of the technology used. Although the principles of fuel fabrication in terms of providing a cladding designed to be the primary envelope to encase the fuel are similar for each system, there are detailed differences in manufacturing route and cladding type which arise from differing reactor requirements. These, together with developments made in response to customer needs, are reviewed and the need to maintain a high purity reliable product with low variability at all stages in manufacture is emphasized throughout. (author)

  19. Nuclear fuel brokerage

    International Nuclear Information System (INIS)

    Hoffman, J.; Schreiber, K.

    1985-01-01

    Making available nuclear fuels on the spot market, especially uranium in various compounds and processing stages, has become an important service rendered nuclear power plant operators. A secondary market has grown, both for natural uranium and for separative work, the conditions and transactions of which require a comprehensive overview of what is going on, especially also in connection with possibilities to terminate in a profitable manner existing contracts. This situation has favored the activity of brokers with excellent knowledge of the market, who are able to handle the complicated terms and conditions in an optimum way. (orig.) [de

  20. Nuclear fuel pin

    International Nuclear Information System (INIS)

    Hartley, Kenneth; Moulding, T.L.J.; Rostron, Norman.

    1979-01-01

    Fuel pin for use in fast breeder nuclear reactors containing fissile and fertile areas of which the fissile and fertile materials do not mix. The fissile material takes the shape of large and small diameter microspheres (the small diameter microspheres can pass through the interstices between the large microspheres). The barrier layers being composed of microspheres with a diameter situated between those of the large and small microspheres ensure that the materials do not mix [fr

  1. Nuclear reactor fuel assembly

    International Nuclear Information System (INIS)

    1975-01-01

    A description is given of a nuclear reactor fuel assembly comprising a cluster of fuel elements supported by transversal grids so that their axes are parallel to and at a distance from each other, in order to establish interstices for the axial flow of a coolant. At least one of the interstices is occupied by an axial duct reserved for an auxiliary cooling fluid and is fitted with side holes through which the auxiliary cooling fluid is sprayed into the cluster. Deflectors extend as from a transversal grid in a position opposite the holes to deflect the cooling fluid jet towards those parts of the fuel elements that are not accessible to the auxiliary coolant. This assembly is intended for reactors cooled by light or heavy water [fr

  2. The nuclear importation and exportation - The Brazilian situation

    International Nuclear Information System (INIS)

    Coimbra, G.L.

    1985-01-01

    The panorama of Brazilian economy emphasizing the measurements adopted by Brazilian government referring to importation and exportation policy is presented. The Brazilian Nuclear Program knows the nuclear trade gives good economic perspective. In the context of importation and exportation policy the laws concerned to nuclear trade transactions, taxes, national organizations responsible by the external trade policy and their attributions are presented. (M.C.K.) [pt

  3. Nuclear fuel handling apparatus

    International Nuclear Information System (INIS)

    Andrea, C.; Dupen, C.F.G.; Noyes, R.C.

    1977-01-01

    A fuel handling machine for a liquid metal cooled nuclear reactor in which a retractable handling tube and gripper are lowered into the reactor to withdraw a spent fuel assembly into the handling tube. The handling tube containing the fuel assembly immersed in liquid sodium is then withdrawn completely from the reactor into the outer barrel of the handling machine. The machine is then used to transport the spent fuel assembly directly to a remotely located decay tank. The fuel handling machine includes a decay heat removal system which continuously removes heat from the interior of the handling tube and which is capable of operating at its full cooling capacity at all times. The handling tube is supported in the machine from an articulated joint which enables it to readily align itself with the correct position in the core. An emergency sodium supply is carried directly by the machine to provide make up in the event of a loss of sodium from the handling tube during transport to the decay tank. 5 claims, 32 drawing figures

  4. 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

  5. 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.)

  6. Physical protection of export/import and transportation of nuclear material in the Slovak Republic

    International Nuclear Information System (INIS)

    Vaclav, J

    2002-01-01

    Full text: The paper contains short overview about average amount of nuclear materials transported on the territory of the Slovak Republic in a year, and the physical protection of these nuclear materials. There are several types of transportation and export/import of nuclear materials in the SR: fresh fuel import; import of other unirradiated nuclear materials (e.g. depleted uranium, natural uranium); export of unirradiated nuclear materials (e.g. natural uranium); internal transportation of fresh fuel; internal transportation of other unirradiated nuclear materials; internal transportation of spent fuel. The main objective of the nuclear regulatory authority SR is to supervise observation of the national legislation as follows: the act no. 130 / 1998 on peaceful use of nuclear energy; UJD SR's regulation no. 186/1999 which details the physical protection of the nuclear facilities, nuclear materials, and radioactive waste (following requirements of INFCIRC 225 / Rev. 4); UJD SR's regulation no. 284 / 1999 which details conditions of nuclear material and radioactive wastes transportation. (author)

  7. Nuclear fuel element

    International Nuclear Information System (INIS)

    Armijo, J.S.

    1977-01-01

    A nuclear fuel element for use in the core of a nuclear reactor is disclosed which has a composite cladding having a substrate, a metal barrier metallurgically bonded to the inside surface of the substrate and an inner layer metallurgically bonded to the inside surface of the metal barrier. In this composite cladding, the inner layer and the metal barrier shield the substrate from any impurities or fission products from the nuclear fuel material held within the composite cladding. The metal barrier forms about 1 to about 4 percent of the thickness of the cladding and is comprised of a metal selected from the group consisting of niobium, aluminum, copper, nickel, stainless steel, and iron. The inner layer and then the metal barrier serve as reaction sites for volatile impurities and fission products and protect the substrate from contact and reaction with such impurities and fission products. The substrate and the inner layer of the composite cladding are selected from conventional cladding materials and preferably are a zirconium alloy. Also in a preferred embodiment the substrate and the inner layer are comprised of the same material, preferably a zirconium alloy. 19 claims, 2 figures

  8. A Study on Improvement of Export Control law's understanding for nuclear control items' exporters in Rep. of Korea

    International Nuclear Information System (INIS)

    Lim, Dong Hyuk; Choi, Sun Do; Yang, Seung Hyo

    2011-01-01

    According to export of UAE commercial reactor and JRTR(Jordan Research and Training Reactor) in 2009, Korea's international prestige has enhanced and it has been more important for researcher in charge of export control to understand and carry out duties on export control by obeying Nuclear Suppliers Group(NSG) Guidelines. Currently, the NSG tries to prevent the proliferation of nuclear weapons by harmonising export control systems of participating countries in relation to trade with nuclear commodities and nuclear-related dual-use materials, equipment, software and technology. In addition, through the implementation of two sets of Guidelines for nuclear exports and nuclear-related exports, the NSG aims to ensure that nuclear trade for peaceful purposes does not contribute to the proliferation of nuclear weapons or other nuclear explosive devices, and that international trade and cooperation in the nuclear field is not hindered unjustly in the process. However, there is still not a little confusion of export businesses owing to lack of understanding of nuclear items in Korea. Therefore, by correctly understanding export control systems, permits and licenses, ITT and persistingly communicating with export businesses, Researchers in charge of export control are able to eliminate confusion of production businesses regarding export and establish a export control culture

  9. Regional Seminars to Address Current Nuclear Export Control Issues

    International Nuclear Information System (INIS)

    Killinger, Mark H.

    2002-01-01

    The control of nuclear-related exports, a critical component of the nonproliferation regime, is facing several opportunities and challenges. As countries sign and ratify the International Atomic Energy Agency's (IAEA) safeguards Additional Protocol (AP), they will begin to report far more export information, including exports of a list of items similar to the Nuclear Supplier Group's Trigger List that existed when the AP was developed in the mid-1990s. This positive development contrasts with challenges such as globalization, transshipments, and tracking of end-uses. Pacific Northwest National Laboratory is proposing that the US Department of Energy (DOE) develop regional seminars that address these types of issues related to export/import controls. The DOE seminars would be designed to supplement regional seminars sponsored by the IAEA and member states on topics related to the Additional Protocol (referred to as 'IAEA seminars'). The topic of nuclear export/import controls is not thoroughly addressed in the IAEA seminars. The proposed DOE seminars would therefore have two objectives: familiarizing countries with the export/import provisions of the Additional Protocol, and addressing challenges such as those noted above. The seminars would be directed particularly at countries that have not ratified the AP, and at regions where export-related problems are particularly prevalent. The intent is to encourage governments to implement more effective nuclear export control systems that meet the challenges of the 21st century.

  10. Nuclear fuel assembly and process

    International Nuclear Information System (INIS)

    Grubb, W.T.

    1978-01-01

    Rupture of boiling water reactor nuclear fuel cladding resulting from embrittlement caused by fission product cadmium is prevented by adding the stoichiometrically equivalent amount of gold, silver or palladium to the fuel

  11. Legal problems concerning the export of nuclear power plants

    International Nuclear Information System (INIS)

    Pierer, Heinrich von.

    1977-01-01

    The legal problems raised by the export of nuclear power plants may be divided into three main categories: nuclear operator's liability for nuclear damage, the consequences for the supplier of the licensing requirements in the national laws of the buyer country and finally, the constraints of applying non-proliferation safeguards on export of nuclear equipment. As regards the third party liability regime in particular, the difficulties lie essentially in the insufficiency of the definition of the nuclear operator and the lack of harmonization in, or even the absence of national laws in this field. (NEA) [fr

  12. Nuclear power for the oil-exporting countries

    International Nuclear Information System (INIS)

    Stauffer, T.R.

    1983-01-01

    The focus of this paper is the economic rationale for nuclear power in the oil-exporting countries, with the collateral objective of defining the size of the potential market in terms of the exporting countries' economic opportunities and energy needs. Headings are: status of nuclear power in Iran and Egypt; rationale for using nuclear power (gas value; gas balance; financial and fiscal parameters; opportunity cost of capital; taxation burdens; rate making formulae; conservation ethos); applications (nuclear - oil competition; process heat and desalination; nuclear reactors and development assistance); conclusion. (U.K.)

  13. Export and import provisions for nuclear materials and power plants, from the legal point of view

    International Nuclear Information System (INIS)

    Shapar, H.K.

    1975-01-01

    This paper provides a general review of the legal bases for and the administrative procedures involved in the export and import licensing of nuclear power reactors, fuels, and other nuclear materials by the United States. The basic statutory provisions and requirements are briefly described, and the requirement of an agreement for cooperation reviewed. The regulations of the Nuclear Regulatory Commission are covered in greater detail as they apply to the export and import of power reactors, nuclear fuels, source materials and byproduct materials. The intra-governmental procedures for review of an application for an export license are described in detail. Problems encountered in the administration of the law and regulations are described and the methods of resolving them are noted. The paper concludes with a brief account of three current topics, 1) the preparation of an environmental impact statement for export programs, 2) the situation with respect to the export licensing of component parts of reactors by the U.S. Department of Commerce, and 3) the shipment of plutonium by air. (orig.) [de

  14. Nuclear power and nuclear weapons: export policy and proliferation resistance

    International Nuclear Information System (INIS)

    Lodgaard, S.

    1979-01-01

    After briefly summing up the present extent of proliferation, and potential proliferation, the international nuclear markets, both the open and the grey, are considered. In the open market political pressure has led to cessation of the export of 'sensitive' plant. The grey market is very difficult to regulate and, while a reduction is possible, its elimination is improbable. The extent of IAEA safeguards is briefly presented. Revision of bilateral nuclear cooperation agreements by USA is in progress, the object being further to restrict possible proliferation, and Canada and Australia are adopting similar policies. The consequences of differences in safeguard requirements may be to ensure a supply of uranium which is not subject to strict safeguards. The influence of the INFCE study project is also discussed at some length. The non-aligned countries have pointed out that the new export policies of the supplying countries have undermined Article IV of the NPT and are also not in line with the basis of North-South cooperation, which is based on advanced tecknology transfer. It is concluded that it is time that such unilaterally restrictive policies were reevaluated and a basis prepared for agreement on mutually acceptable limitations. (JIW)

  15. Swelling-resistant nuclear fuel

    Science.gov (United States)

    Arsenlis, Athanasios [Hayward, CA; Satcher, Jr., Joe; Kucheyev, Sergei O [Oakland, CA

    2011-12-27

    A nuclear fuel according to one embodiment includes an assembly of nuclear fuel particles; and continuous open channels defined between at least some of the nuclear fuel particles, wherein the channels are characterized as allowing fission gasses produced in an interior of the assembly to escape from the interior of the assembly to an exterior thereof without causing significant swelling of the assembly. Additional embodiments, including methods, are also presented.

  16. Mechanisms of Nuclear Export in Cancer and Resistance to Chemotherapy

    Directory of Open Access Journals (Sweden)

    Mohamed El-Tanani

    2016-03-01

    Full Text Available Tumour suppressor proteins, such as p53, BRCA1, and ABC, play key roles in preventing the development of a malignant phenotype, but those that function as transcriptional regulators need to enter the nucleus in order to function. The export of proteins between the nucleus and cytoplasm is complex. It occurs through nuclear pores and exported proteins need a nuclear export signal (NES to bind to nuclear exportin proteins, including CRM1 (Chromosomal Region Maintenance protein 1, and the energy for this process is provided by the RanGTP/RanGDP gradient. Due to the loss of DNA repair and cell cycle checkpoints, drug resistance is a major problem in cancer treatment, and often an initially successful treatment will fail due to the development of resistance. An important mechanism underlying resistance is nuclear export, and a number of strategies that can prevent nuclear export may reverse resistance. Examples include inhibitors of CRM1, antibodies to the nuclear export signal, and alteration of nuclear pore structure. Each of these are considered in this review.

  17. Accident tolerant composite nuclear fuels

    Directory of Open Access Journals (Sweden)

    Szpunar Barbara

    2017-01-01

    Full Text Available Investigated accident tolerant nuclear fuels are fuels with enhanced thermal conductivity, which can withstand the loss of coolant for a longer time by allowing faster dissipation of heat, thus lowering the centerline temperature and preventing the melting of the fuel. Traditional nuclear fuels have a very low thermal conductivity and can be significantly enhanced if transformed into a composite with a very high thermal conductivity components. In this study, we analyze the thermal properties of various composites of mixed oxides and thoria fuels to improve thermal conductivity for the next generation safer nuclear reactors.

  18. Nuclear export of RNA: Different sizes, shapes and functions.

    Science.gov (United States)

    Williams, Tobias; Ngo, Linh H; Wickramasinghe, Vihandha O

    2018-03-01

    Export of protein-coding and non-coding RNA molecules from the nucleus to the cytoplasm is critical for gene expression. This necessitates the continuous transport of RNA species of different size, shape and function through nuclear pore complexes via export receptors and adaptor proteins. Here, we provide an overview of the major RNA export pathways in humans, highlighting the similarities and differences between each. Its importance is underscored by the growing appreciation that deregulation of RNA export pathways is associated with human diseases like cancer. Crown Copyright © 2017. Published by Elsevier Ltd. All rights reserved.

  19. Nuclear fuel assembly

    International Nuclear Information System (INIS)

    Hoshi, Masaya; Makihara, Yoshiaki.

    1985-01-01

    Purpose: To limit a bypass flow by inhibiting or restricting the lateral flow of coolants between lower nozzle legs of a nuclear fuel assembly, so that the flow speed of a jet stream flowing through the gaps between buffle plates into the reactor core is not increased. Constitution: The lower nozzle of a fuel assembly comprises an upper plate, an enclosure and legs, in which flow apertures are perforated in the enclosure, the area for the flow apertures and the slit are set to less than predetermined values, and the flow apertures are arranged so that they are situated within the gaps between the lower end of the buffle plate and the lower reactor core plate. As the result, since the jet stream from the gaps between the buffle plates can be so decreased as the effect thereof on the fuel rods is negligible, measurement for the size of the gap between the buffle plates upon periodical inspection is no more necessary, thereby enabling to shorten the time of the periodical inspection and reduce the exposure dose. (Kamimura, M.)

  20. 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

  1. 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

  2. French nuclear industry exportations: companies and organisations, achievements and projects

    International Nuclear Information System (INIS)

    Faudon, V.; Pailler, S.; Miniere, D.; Pouget-Abadie, X.; Journes, F.; Ouali, F.; Brochard, D.; Choho, T.; Lagarde, D.; Anglaret, P.; Kottman, G.; Mockly, D.; Ouzounian, G.; Cordier, P.Y.; Prenez, J.C.; Arpino, J.M.; Jaouen, C.; Jolly, B.

    2013-01-01

    This document gathers a series of short articles in which the following players: French Nuclear Safety Authority (ASN), Electricity of France (EdF), French Alternative Energies and Atomic Energy Commission (CEA), AREVA, ALSTOM, the Association of French Nuclear Industry Exporters (AIFEN), the National Radioactive Waste Management Agency (ANDRA) and the French Society of Nuclear Energy (SFEN) present their competencies in their respective fields and their strategies and commercial offers for exports. 2 articles are dedicated to the achievements of the French nuclear industry in China and another details the cooperation between SFEN and its foreign counterparts. Another article briefly presents the EPR and ATMEA reactors. (A.C.)

  3. Nuclear export of proteins and drug resistance in cancer.

    Science.gov (United States)

    Turner, Joel G; Dawson, Jana; Sullivan, Daniel M

    2012-04-15

    The intracellular location of a protein is crucial to its normal functioning in a cell. Cancer cells utilize the normal processes of nuclear-cytoplasmic transport through the nuclear pore complex of a cell to effectively evade anti-neoplastic mechanisms. CRM1-mediated export is increased in various cancers. Proteins that are exported in cancer include tumor-suppressive proteins such as retinoblastoma, APC, p53, BRAC1, FOXO proteins, INI1/hSNF5, galectin-3, Bok, nucleophosmin, RASSF2, Merlin, p21(CIP), p27(KIP1), N-WASP/FAK, estradiol receptor and Tob, drug targets topoisomerase I and IIα and BCR-ABL, and the molecular chaperone protein Hsp90. Here, we review in detail the current processes and known structures involved in the export of a protein through the nuclear pore complex. We also discuss the export receptor molecule CRM1 and its binding to the leucine-rich nuclear export signal of the cargo protein and the formation of a nuclear export trimer with RanGTP. The therapeutic potential of various CRM1 inhibitors will be addressed, including leptomycin B, ratjadone, KOS-2464, and specific small molecule inhibitors of CRM1, N-azolylacrylate analogs, FOXO export inhibitors, valtrate, acetoxychavicol acetate, CBS9106, and SINE inhibitors. We will also discuss examples of how drug resistance may be reversed by targeting the exported proteins topoisomerase IIα, BCR-ABL, and galectin-3. As effective and less toxic CRM1 export inhibitors become available, they may be used as both single agents and in combination with current chemotherapeutic drugs. We believe that the future development of low-toxicity, small-molecule CRM1 inhibitors may provide a new approach to treating cancer. Copyright © 2011 Elsevier Inc. All rights reserved.

  4. Safety and exportation of nuclear power stations

    International Nuclear Information System (INIS)

    Coudray, M.; Perrais, J.P.

    1976-01-01

    Safety problems arising from exportation are especially handled through the French exportation of PWR stations. Regulations differ widely from one country to another. However, very large use of American regulations is made and frequently there is a tendency to harden such or such clause in the quotation. Industry must be ready to give satisfaction to such demands of customers. Sometimes also, it is a mere duplication of French stations which is above all looked for. In that case, it is the problem of using French regulations abroad which arises. Desirable changes in examination proceedings are analyzed together with a French regulation effort aiming to make easier the promotion of their use abroad. Finally, safety may be a factor of success for exportation attempts. It is shown how useless some outbiddings may be, but also how, on the contrary, speeding up of research and development effort towards specific safety problems in case of exportation, is to be promoted [fr

  5. The export receptor Crm1 forms a dimer to promote nuclear export of HIV RNA.

    Science.gov (United States)

    Booth, David S; Cheng, Yifan; Frankel, Alan D

    2014-12-08

    The HIV Rev protein routes viral RNAs containing the Rev Response Element (RRE) through the Crm1 nuclear export pathway to the cytoplasm where viral proteins are expressed and genomic RNA is delivered to assembling virions. The RRE assembles a Rev oligomer that displays nuclear export sequences (NESs) for recognition by the Crm1-Ran(GTP) nuclear receptor complex. Here we provide the first view of an assembled HIV-host nuclear export complex using single-particle electron microscopy. Unexpectedly, Crm1 forms a dimer with an extensive interface that enhances association with Rev-RRE and poises NES binding sites to interact with a Rev oligomer. The interface between Crm1 monomers explains differences between Crm1 orthologs that alter nuclear export and determine cellular tropism for viral replication. The arrangement of the export complex identifies a novel binding surface to possibly target an HIV inhibitor and may point to a broader role for Crm1 dimerization in regulating host gene expression.

  6. Four decades of living with the genie: United States nuclear export policy

    International Nuclear Information System (INIS)

    Kramish, A.

    1983-01-01

    The subject is discussed as follows: general introduction (examples of complex nature of nuclear trade); non-proliferation policy - the beginnings (early US action to control dealings with other countries); the Nuclear Non-Proliferation Act of 1978 (formulation of US policy on nuclear trade; INFCE (International Nuclear Fuel Cycle Evaluation)); the Symington and Glenn Amendments (US legislation to control trade with other countries); the Export-Import Bank Act (US legislation for the same purpose as above); the Non-Proliferation Treaty; the Reagan Policy (US present policy to support IAEA safeguards and Non-Proliferation Treaty); future prospects. (U.K.)

  7. Burnable absorber coated nuclear fuel

    International Nuclear Information System (INIS)

    Chubb, W.; Radford, K.C.; Parks, B.H.

    1984-01-01

    A nuclear fuel body which is at least partially covered by a burnable neutron absorber layer is provided with a hydrophobic overcoat generally covering the burnable absorber layer and bonded directly to it. In a method for providing a UO 2 fuel pellet with a zirconium diboride burnable poison layer, the fuel body is provided with an intermediate niobium layer. (author)

  8. 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.)

  9. Nuclear Fuel elements

    International Nuclear Information System (INIS)

    Hirakawa, Hiromasa.

    1979-01-01

    Purpose: To reduce the stress gradient resulted in the fuel can in fuel rods adapted to control the axial power distribution by the combination of fuel pellets having different linear power densities. Constitution: In a fuel rod comprising a first fuel pellet of a relatively low linear power density and a second fuel pellet of a relatively high linear power density, the second fuel pellet is cut at its both end faces by an amount corresponding to the heat expansion of the pellet due to the difference in the linear power density to the adjacent first fuel pellet. Thus, the second fuel pellet takes a smaller space than the first fuel pellet in the fuel can. This can reduce the stress produced in the portion of the fuel can corresponding to the boundary between the adjacent fuel pellets. (Kawakami, Y.)

  10. Thorium in nuclear fuel

    International Nuclear Information System (INIS)

    Stankevicius, Alejandro

    2012-01-01

    We revise the advantages and possible problems on the use of thorium as a nuclear fuel instead of uranium. The following aspects are considered: 1) In the world there are three times more thorium than uranium 2) In spite that thorium in his natural form it is not a fisil, under neutron irradiation, is possible to transform it to uranium 233, a fisil of a high quality. 3) His ceramic oxides properties are superior to uranium or plutonium oxides. 4) During the irradiation the U 233 due to n,2n reaction produce small quantities of U 232 and his decay daughters' bismuth 212 and thallium 208 witch are strong gamma source. In turn thorium 228 and uranium 232 became, in time anti-proliferate due to there radiation intensity. 5) As it is described in here and experiments done in several countries reactors PHWR can be adapted to the use of thorium as a fuel element 6) As a problem we should mentioned that the different steps in the process must be done under strong radiation shielding and using only automatized equipment s (author)

  11. Comparison of alcogas aviation fuel with export aviation gasoline

    Science.gov (United States)

    Gage, V R; Sparrow, S W; Harper, D R

    1921-01-01

    Mixtures of gasoline and alcohol when used in internal combustion engines designed for gasoline have been found to possess the advantage of alcohol in withstanding high compression without "knock" while retaining advantages of gasoline with regard to starting characteristics. Test of such fuels for maximum power-producing ability and fuel economy at various rates of consumption are thus of practical importance, with especial reference to high-compression engine development. This report discusses the results of tests which compares the performance of alcogas with x gasoline (export grade) as a standard.

  12. British Nuclear Fuels (Warrington)

    International Nuclear Information System (INIS)

    Hoyle, D.; Cryer, B.; Bellotti, D.

    1992-01-01

    This adjournment debate is about British Nuclear Fuels plc and the 750 redundancies due to take place by the mid-1990s at BNFL, Risley. The debate was instigated by the Member of Parliament for Warrington, the constituency in which BNFL, Risley is situated. Other members pointed out that other industries, such as the textile industry are also suffering job losses due to the recession. However the MP for Warrington argued that the recent restructuring of BNFL restricted the financial flexibility of BNFL so that the benefits of contracts won for THORP at Sellafield could not help BNFL, Risley. The debate became more generally about training, apprentices and employment opportunities. The Parliamentary Under-Secretary of State for Energy explained the position as he saw it and said BNFL may be able to offer more help to its apprentices. Long- term employment prospects at BNFL are dependent on the future of the nuclear industry in general. The debate lasted about half an hour and is reported verbatim. (U.K)

  13. Analysis and prediction of leucine-rich nuclear export signals

    DEFF Research Database (Denmark)

    La Cour, T.; Kiemer, Lars; Mølgaard, Anne

    2004-01-01

    We present a thorough analysis of nuclear export signals and a prediction server, which we have made publicly available. The machine learning prediction method is a significant improvement over the generally used consensus patterns. Nuclear export signals (NESs) are extremely important regulators...... this analysis is that the most important properties of NESs are accessibility and flexibility allowing relevant proteins to interact with the signal. Furthermore, we show that not only the known hydrophobic residues are important in defining a nuclear export signals. We employ both neural networks and hidden...... of the subcellular location of proteins. This regulation has an impact on transcription and other nuclear processes, which are fundamental to the viability of the cell. NESs are studied in relation to cancer, the cell cycle, cell differentiation and other important aspects of molecular biology. Our conclusion from...

  14. Upgrading nuclear-fuel management

    International Nuclear Information System (INIS)

    Spetz, S.W.

    1978-01-01

    Because of the unavailability of nuclear-fuel reprocessing, more efficient methods must be found in using fresh uranium-fuel supplies in LWRs. The lumped-burnable-poison shuffle and multibatch-shuffle schemes are proposed by one reactor supplier as viable means of obtaining this practical and economical objective. Another means of attaining better fuel efficiency might be by increasing the number of fuel assemblies, with a higher uranium-enrichment percentage. Thus, refueling might be made at 18-month intervals

  15. 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.)

  16. Advanced Nuclear Fuel Cycle Options

    Energy Technology Data Exchange (ETDEWEB)

    Roald Wigeland; Temitope Taiwo; Michael Todosow; William Halsey; Jess Gehin

    2010-06-01

    A systematic evaluation has been conducted of the potential for advanced nuclear fuel cycle strategies and options to address the issues ascribed to the use of nuclear power. Issues included nuclear waste management, proliferation risk, safety, security, economics and affordability, and sustainability. The two basic strategies, once-through and recycle, and the range of possibilities within each strategy, are considered for all aspects of the fuel cycle including options for nuclear material irradiation, separations if needed, and disposal. Options range from incremental changes to today’s implementation to revolutionary concepts that would require the development of advanced nuclear technologies.

  17. Nuclear fuels; Les combustibles nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    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{sub 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{sub 2} ceramics by ab initio calculations, cladding and assembly materials, pellet-cladding interaction, advanced UO{sub 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

  18. Export financing of nuclear power plants - banks experience

    International Nuclear Information System (INIS)

    Loeber

    1976-01-01

    Export financing of a nuclear power plant to be exported from Germany, is, in principle, provided by German commercial banks and KfW (Kreditanstalt fuer Wiederaufbau). As a rule, 50 per cent of the financing of maturities falling due under the export portion of the loan will be taken over by a banking syndicate of approximately 25 member banks, and the remaining 50 per cent would be provided by KfW. KfW and the commercial banks must grant their loans at the respective money market conditions. The banks' and KfW's loans will normally be disbursed pro rata delivery. (HP) [de

  19. 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

  20. The fabrication of nuclear fuel

    International Nuclear Information System (INIS)

    D'Amore, Mead

    1987-01-01

    The chronology of fuel product and core management development over the past 25 years in the USA is explained. Nuclear fuel for Westinghouse reactors is made by converting enriched uranium hexafluoride (UF 6 ) into uranium dioxide (UO 2 ) powder. The powder is pressed into pellets which are loaded into zircalloy fuel tubes (typically over 14 million pellets in 50,952 rods). The fuel rods are arranged in fuel assemblies which are shipped to the reactor site (typically 193 fuel assemblies are needed for one 1000MWe reactor). Each stage of the fuel fabrication cycle (cladding manufacture, chemical conversion UF 6 - UO 2 , pellet production, fuel rod fabrication, grid assembly, skeleton assembly, fuel assembly) is described, with particular reference to the Westinghouse process and plant. (UK)

  1. 77 FR 27113 - Export and Import of Nuclear Equipment and Material; Export of International Atomic Energy Agency...

    Science.gov (United States)

    2012-05-09

    ... / Wednesday, May 9, 2012 / Rules and Regulations#0;#0; ] NUCLEAR REGULATORY COMMISSION 10 CFR Part 110 RIN 3150-AJ04 Export and Import of Nuclear Equipment and Material; Export of International Atomic Energy Agency Safeguards Samples AGENCY: Nuclear Regulatory Commission. ACTION: Final rule. SUMMARY: The U.S...

  2. Nuclear Imprisonment: Viral Strategies to Arrest Host mRNA Nuclear Export

    Science.gov (United States)

    Kuss, Sharon K.; Mata, Miguel A.; Zhang, Liang; Fontoura, Beatriz M. A.

    2013-01-01

    Viruses possess many strategies to impair host cellular responses to infection. Nuclear export of host messenger RNAs (mRNA) that encode antiviral factors is critical for antiviral protein production and control of viral infections. Several viruses have evolved sophisticated strategies to inhibit nuclear export of host mRNAs, including targeting mRNA export factors and nucleoporins to compromise their roles in nucleo-cytoplasmic trafficking of cellular mRNA. Here, we present a review of research focused on suppression of host mRNA nuclear export by viruses, including influenza A virus and vesicular stomatitis virus, and the impact of this viral suppression on host antiviral responses. PMID:23872491

  3. 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.)

  4. Quality assurance of nuclear fuel

    International Nuclear Information System (INIS)

    1994-01-01

    The guide presents the quality assurance requirements to be completed with in the procurement, design, manufacture, transport, handling and operation of the nuclear fuel. The guide also applies to the procurement of the control rods and the 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 organizations whose activities affect fuel quality, the safety of fuel transport, storage and operation. (2 refs.)

  5. An evaluation of Kazakhstan nuclear export control system

    International Nuclear Information System (INIS)

    Yeligbayeva, G.; Masenov, Ch.

    2002-01-01

    A system to control the export nuclear materials and technologies is a natural part of creating a self-sustaining government. The government of Kazakhstan has made a great deal of progress in building such a system. Control of export and import of nuclear materials and technologies and dual-use materials, related to nuclear activity, became one of the important part of mechanism of Non-Proliferation conditions realization in Kazakhstan. The system of export control has developed well over the 10 years. Kazakhstan is in the midst of a long process of building a functional export control system consistent with World standards. The state system of export control currently exists in Kazakhstan on the legislative base, and is based on efficient cooperation of the KAEC with a number of competent state bodies (Ministry of Economy, Ministry of Foreign Affairs, State Customs Committee) each of them has its own specific functions, duties and rights. The export is carried out using licenses, issued by the Ministry of Economy of the RK, according to applications of certain standard which are previously agreed with the KAEC under decision of the RK Government. The KAEC, acting on the base of export control principles and observance of international obligations on non-proliferation matter, makes decisions, only after thorough evaluation of ways of export and reliability of an end-user of the commodity, to agree the application for a license. The most fully developed aspect is the licensing process. General politics of export regulation in Kazakhstan are based on normative acts and rules, which are wholly appropriate (complementary) to the managing principles of nuclear export. There exists a full legal basis for the licensing system. But the process is going, some provisions is changing: in 2000 Kazakhstan corrected the export control law and approved the national control list very similar with EU control list, in 2002 the rules of the process of licensing the export and import

  6. Principles and trends of nuclear exports from the U.S.A

    International Nuclear Information System (INIS)

    Patermann, C.

    1977-01-01

    The 'Atoms for Peace' Program marked the beginning of worldwide utilization of nuclear energy for peaceful purposes and of an unparalleled cooperation beyond all national frontiers, even across the Iron Curtain. The United States was the sponsor, and has remained the prime mover, of the expanding development of nuclear power and its associated areas, such as radiation protection and legal problems. The efforts taken to prevent the abuse of nuclear fuels for non-peaceful purposes crystallized around the IAEA's Non-Proliferation Program and the corresponding safeguards agreements concluded with the Agency, to which even some countries subordinated themselves with specific projects which are not signatories to the NPT. Until approximately two years ago, the United States was satisfied if countries receiving nuclear exports expressed their willingness to agree to international safeguards controls. However, as a consequence of various nuclear exports from other industrialized countries, such as the Federal Republic and France, a trend became apparent in the U.S. which led to interventions against these nuclear exports. In 1976, finally, this attitude brought about a re-orientation of U.S. nuclear policy, both within the United States and vis-a-vis third countries. (orig.) [de

  7. 40 CFR 80.1430 - Requirements for exporters of renewable fuels.

    Science.gov (United States)

    2010-07-01

    ... renewable fuels. 80.1430 Section 80.1430 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) REGULATION OF FUELS AND FUEL ADDITIVES Renewable Fuel Standard § 80.1430 Requirements for exporters of renewable fuels. (a) Any party that owns any amount of renewable fuel, whether in...

  8. 40 CFR 80.1130 - Requirements for exporters of renewable fuels.

    Science.gov (United States)

    2010-07-01

    ... renewable fuels. 80.1130 Section 80.1130 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) REGULATION OF FUELS AND FUEL ADDITIVES Renewable Fuel Standard § 80.1130 Requirements for exporters of renewable fuels. (a) Any party that owns any amount of renewable fuel (in its...

  9. Nuclear fuel string assembly

    International Nuclear Information System (INIS)

    Ip, A.K.; Koyanagi, K.; Tarasuk, W.R.

    1976-01-01

    A method of fabricating rodded fuels suitable for use in pressure tube type reactors and in pressure vessel type reactors is described. Fuel rods are secured as an inner and an outer sub-assembly, each rod attached between mounting rings secured to the rod ends. The two sub-assemblies are telescoped together and positioned by spaced thimbles located between them to provide precise positioning while permittng differential axial movement between the sub-assemblies. Such sub-assemblies are particularly suited for mounting as bundle strings. The method provides particular advantages in the assembly of annular-section fuel pins, which includes booster fuel containing enriched fuel material. (LL)

  10. 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

  11. 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)

  12. 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

  13. Nuclear fuel assembly

    International Nuclear Information System (INIS)

    Betten, P.R.

    1976-01-01

    Under the invention the fuel assembly is particularly suitable for liquid metal cooled fast neutron breeder reactors. Hence, according to the invention a fuel assembly cladding includes inward corrugations with respect to the remainder of the cladding according to a recurring pattern determined by the pitch of the metal wire helically wound round the fuel rods of the assembly. The parts of the cladding pressed inwards correspond to the areas in which the wire encircling the peripheral fuel rods is generally located apart from the cladding, thereby reducing the play between the cladding and the peripheral fuel rods situated in these areas. The reduction in the play in turn improves the coolant flow in the internal secondary channels of the fuel assembly to the detriment of the flow in the peripheral secondary channels and thereby establishes a better coolant fluid temperature profile [fr

  14. 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.

  15. Nuclear fuel cycle. V. 2

    International Nuclear Information System (INIS)

    1984-01-01

    Nuclear fuel cycle information in some countries that develop, supply or use nuclear energy is presented. Data about Argentina, Australia, Belgium, Netherlands, Italy, Denmarmark, Norway, Sweden, Switzerland, Finland, Spain and India are included. The information is presented in a tree-like graphic way. (C.S.A.) [pt

  16. Nuclear fuel cycle. V. 1

    International Nuclear Information System (INIS)

    1983-01-01

    Nuclear fuel cycle information in the main countries that develop, supply or use nuclear energy is presented. Data about Japan, FRG, United Kingdom, France and Canada are included. The information is presented in a tree-like graphic way. (C.S.A.) [pt

  17. 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.

  18. Nuclear fuel financing

    International Nuclear Information System (INIS)

    Lurf, G.

    1975-01-01

    Fuel financing is only at its beginning. A logical way of developing financing model is a step by step method starting with the financing of pre-payments. The second step will be financing of natural uranium and enrichment services to the point where the finished fuel elements are delivered to the reactor operator. The third step should be the financing of fuel elements during the time the elements are inserted in the reactor. (orig.) [de

  19. NUCLEAR REACTOR FUEL SYSTEMS

    Science.gov (United States)

    Thamer, B.J.; Bidwell, R.M.; Hammond, R.P.

    1959-09-15

    Homogeneous reactor fuel solutions are reported which provide automatic recombination of radiolytic gases and exhibit large thermal expansion characteristics, thereby providing stability at high temperatures and enabling reactor operation without the necessity of apparatus to recombine gases formed by the radiolytic dissociation of water in the fuel and without the necessity of liquid fuel handling outside the reactor vessel except for recovery processes. The fuels consist of phosphoric acid and water solutions of enriched uranium, wherein the uranium is in either the hexavalent or tetravalent state.

  20. US Nuclear Non-Proliferation Policy: impact on exports and nuclear industry could not be determined

    International Nuclear Information System (INIS)

    Staats, E.B.

    1980-01-01

    The Nuclear Non-Proliferation Act of 1978 established new measures to prevent the diversion to weapons use of peaceful nuclear exports. It also created a policy to confirm US reliability as a nuclear supplier. GAO did not identify any export sales lost as a result of the Act, but did find indications that nonprofileration policies can influence export sales. Based on avavailable data, GAO could not determine the impact of the Act on the competitiveness of US nuclear exports. However, US companies are at some disadvantage because importers perceive that implementation of the Act may result in delayed export licenses. The United States dominated the nuclear export market through the early 1970s. However, foreign competitors, some aided by US technology transfers, emerged to monopolize home markets and complete for third-country business. Further, the market has been depressed since 1974 and prospects for US nuclear power plant exports have dimmed greatly. However, US companies continue to view exports as important to sustain production capacity

  1. The nuclear export policy of the Reagan administration

    International Nuclear Information System (INIS)

    Pilat, J.F.; Donnelly, W.H.

    1983-01-01

    tThe Reagan Administration maintains the Carter Administration's objective of non-proliferation of nuclear weapons as being fundamental to US nuclear export policy. However, it sees the USA as having another important role to play in influencing the use of nuclear power and the trading of related goods and technologies in other countries. While the Administration believes its policies will prove beneficial to the USA, there is concern that trade considerations are being given priority over preventing the proliferation of nuclear weapons. (author)

  2. Spent Nuclear Fuel Project Safety Management Plan

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1996-02-01

    The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities

  3. Nuclear export and armament. New threats and peace perspectives

    International Nuclear Information System (INIS)

    Kubbig, B.W.; Mueller, H.

    1993-02-01

    The authors give a condensed analysis of safety and politico-economic dimensions regarding the further proliferation of nuclear weapons and carrier systems with which nuclear blasting charges can be transported. From the content: - Proliferation and non-proliferation: technology, economy and (international) law in a political historic survey. - Missile defense: appropriate technological answer to the political proliferation problem? -export strategies: USA and FRG in comparison, interest and policy of the European Community. - Components for an extensive proliferation strategy. (orig./HP) [de

  4. Nuclear fuel manufacture and technology

    International Nuclear Information System (INIS)

    Nuclear power accounts for approximately 17% of the world's total electrical energy production. Over 30 countries operate in excess of 430 nuclear power plants with a combined generating capacity of more than 340 000 MWe. BNFL is a leading force in the international nuclear industry, supplying products and services across the complete fuel cycle business spectrum. These services and products include fuel and intermediate products manufacture, reprocessing, transport, waste management and decommissioning. This paper describes the processes involved in taking uranium ore as a raw material through to the production of advanced fuels and focuses on the manufacture and technology for both uranium oxide (UO 2 ) and mixed oxide (MOX) fuels. As a light water reactor (LWR) fuel fabricator, BNFL is able to manufacture MOX or UO 2 fuel utilizing recycled uranium. This paper discusses the technology involved in the use of plutonium or uranium oxide recovered from reprocessing and other advanced fuel technical issues. Improved production methods and the application of advanced engineering permits the next generation of fuel fabrication plants to capitalize on advances in technology. The long-term research and development (R and D) commitments by BNFL are outlined in this paper, indicating the levels of investment needed in R and D to accommodate a high technology company in an international market. (author)

  5. Nuclear fuel element end fitting

    International Nuclear Information System (INIS)

    Jabsen, F.S.

    1979-01-01

    A typical embodiment of the invention has an array of sockets that are welded to the intersections of the plates that form the upper and lower end fittings of a nuclear reactor fuel element. The sockets, which are generally cylindrical in shape, are oriented in directions that enable the longitudinal axes of the sockets to align with the longitudinal axes of the fuel rods that are received in the respective sockets. Detents impressed in the surfaces of the sockets engage mating grooves that are formed in the ends of the fuel rods to provide for the structural integrity of the fuel element

  6. Nuclear reactor fuel element

    International Nuclear Information System (INIS)

    Steinke, A.

    1985-01-01

    The grid-shaped spacer for PWR fuel elements consists of flat, upright metal bars at right angles to the fuel rods. In one corner of a grid mesh it has a spring with two end parts for the fuel rod. The cut-outs for the end parts start from an end edge of the metal bar parallel to the fuel rods. The transverse metal bar is one of four outer metal bars. Both end parts of the spring have an extension parallel to this outer metal arm, which grips a grid mesh adjacent to this grid mesh at the side in one corner of the spacer and forms an end part of a spring for the fuel rod there on the inside of the outer metal bar. (HP) [de

  7. 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

  8. Rack for nuclear fuel elements

    International Nuclear Information System (INIS)

    Rubinstein, H.J.; Gordon, C.B.; Robison, A.; Clark, P.M.

    1977-01-01

    Disclosed is a rack for storing spent nuclear fuel elements in which a plurality of aligned rows of upright enclosures of generally square cross-sectional areas contain vertically disposed spent fuel elements. Each fuel element is supported at the lower end thereof by a respective support that rests on the floor of the spent fuel pool for a nuclear power plant. An open rack frame is employed as an upright support for the enclosures containing the spent fuel elements. Legs at the lower corners of the frame rest on the floor of the pool to support the frame. In one exemplary embodiment, the support for the fuel element is in the form of a base on which a fuel element rests and the base is supported by legs. In another exemplary embodiment, each fuel element is supported on the pool floor by a self-adjusting support in the form of a base on which a fuel element rests and the base rests on a ball or swivel joint for self-alignment. The lower four corners of the frame are supported by legs adjustable in height for leveling the frame. Each adjustable frame leg is in the form of a base resting on the pool floor and the base supports a threaded post. The threaded post adjustably engages a threaded column on which rests the lower end of the frame. 16 claims, 14 figures

  9. Nuclear fuel rods

    International Nuclear Information System (INIS)

    Wada, Toyoji.

    1979-01-01

    Purpose: To remove failures caused from combination of fuel-cladding interactions, hydrogen absorptions, stress corrosions or the likes by setting the quantity ratio of uranium or uranium and plutonium relative to oxygen to a specific range in fuel pellets and forming a specific size of a through hole at the center of the pellets. Constitution: In a fuel rods of a structure wherein fuel pellets prepared by compacting and sintering uranium dioxide, or oxide mixture consisting of oxides of plutonium and uranium are sealed with a zirconium metal can, the ratio of uranium or uranium and plutonium to oxygen is specified as 1 : 2.01 - 1 : 2.05 in the can and a passing hole of a size in the range of 15 - 30% of the outer diameter of the fuel pellet is formed at the center of the pellet. This increases the oxygen partial pressure in the fuel rod, oxidizes and forms a protection layer on the inner surface of the can to control the hydrogen absorption and stress corrosion. Locallized stress due to fuel cladding interaction (PCMI) can also be moderated. (Horiuchi, T.)

  10. 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

  11. Study on status of nuclear export/import implementation in KAERI

    International Nuclear Information System (INIS)

    Kim, H. J.; Lee, B. D.; Lee, S. H.; Park, H. J.; So, D. S.

    2004-01-01

    As Korea is the member of ZC(Zangger Committee) and NSG(Nuclear Suppliers Group), domestic legislation reflected their guideline of nuclear export. The paper investigate the status of implementation procedures of nuclear export and import in KAERI based on domestic and international law. In addition, the paper analyzes on problem of export/import implementation system and also extract the efficient implementation system of nuclear export and import

  12. Transport of irradiated nuclear fuel

    International Nuclear Information System (INIS)

    1980-01-01

    In response to public interest in the transport by rail through London of containers of irradiated fuel elements on their way from nuclear power stations to Windscale, the Central Electricity Generating Board and British Rail held three information meetings in London in January 1980. One meeting was for representatives of London Borough Councils and Members of Parliament with a known interest in the subject, and the others were for press, radio and television journalists. This booklet contains the main points made by the principal speakers from the CEGB and BR. (The points covered include: brief description of the fuel cycle; effect of the fission process in producing plutonium and fission products in the fuel element; fuel transport; the fuel flasks; protection against accidents; experience of transporting fuel). (U.K.)

  13. Nuclear reactor fuel element

    International Nuclear Information System (INIS)

    1987-01-01

    A fuel element of a PWR has a deflector projection outside on the intermediate strip of the spacer to avoid hooking up during fuelling and fuel removal, which is placed in the direction of the diagonals of the corner grid mesh between the two outer bars on the intermediate strip and is oblique to the two ends of the intermediate strip in the longitudinal direction of the bars. (orig./HP) [de

  14. Nuclear fuel assembly

    International Nuclear Information System (INIS)

    Helmersson, S.

    1982-05-01

    The fuel assembly has a square-shaped cross section and it is put together of four quadratic assemblies each having seventeen positions for fuel rods, which are situated in a lattice formed by a pattern of triangles and squares. Nine of the positions correspond to the junction of a square lattice which has four squares, whereas eight rods are outside the quadratic past. (G.B.)

  15. Upgrading the safety assessment of exported nuclear power plants

    International Nuclear Information System (INIS)

    Rosen, M.

    1978-01-01

    An examination of the safety aspects of exported nuclear power plants demonstrates that additional and somewhat special considerations exist for these plants, and thus that some new approaches may be required to insure their safety. In view of the generally small regulatory staffs of importing countries, suggestions are given for measures which should be taken by the various organizations involved in the export and import of nuclear power facilities to raise the level of the very essential safety assessment. These include the upgrading of the 'export edition' of the traditionally supplied safety documentation by use of a Supplementary Information Report, written specifically for the needs of a smaller and/or less technically qualified staff, which highlights the differences that exist between the facility to be constructed and the supposedly similar reference plant of the supplier country; by improvement of supporting safety documentation to allow for adequate understanding of significant safety parameters; and by attention to the needs of smaller countries in the critical Operating Regulations (Technical Specifications for Operation). Consideration is also given to upgrading the regulatory effort and to the obligations of principal organizations involved with exported nuclear plants, including national and international, for insuring the importing countries' technical readiness and the adequacy of the regulatory effort. Special attention is directed towards the project contract as a means of implementing programmes to achieve these goals. (author)

  16. Nuclear Import and Export of the Thyroid Hormone Receptor.

    Science.gov (United States)

    Zhang, Jibo; Roggero, Vincent R; Allison, Lizabeth A

    2018-01-01

    The thyroid hormone receptors, TRα1 and TRβ1, are members of the nuclear receptor superfamily that forms one of the most abundant classes of transcription factors in multicellular organisms. Although primarily localized to the nucleus, TRα1 and TRβ1 shuttle rapidly between the nucleus and cytoplasm. The fine balance between nuclear import and export of TRs has emerged as a critical control point for modulating thyroid hormone-responsive gene expression. Mutagenesis studies have defined two nuclear localization signal (NLS) motifs that direct nuclear import of TRα1: NLS-1 in the hinge domain and NLS-2 in the N-terminal A/B domain. Three nuclear export signal (NES) motifs reside in the ligand-binding domain. A combined approach of shRNA-mediated knockdown and coimmunoprecipitation assays revealed that nuclear entry of TRα1 is facilitated by importin 7, likely through interactions with NLS-2, and importin β1 and the adapter importin α1 interacting with both NLS-1 and NLS-2. Interestingly, TRβ1 lacks NLS-2 and nuclear import depends solely on the importin α1/β1 heterodimer. Heterokaryon and fluorescence recovery after photobleaching shuttling assays identified multiple exportins that play a role in nuclear export of TRα1, including CRM1 (exportin 1), and exportins 4, 5, and 7. Even single amino acid changes in TRs dramatically alter their intracellular distribution patterns. We conclude that mutations within NLS and NES motifs affect nuclear shuttling activity, and propose that TR mislocalization contributes to the development of some types of cancer and Resistance to Thyroid Hormone syndrome. © 2018 Elsevier Inc. All rights reserved.

  17. Nuclear export signal-interacting protein forms complexes with lamin A/C-Nups to mediate the CRM1-independent nuclear export of large hepatitis delta antigen.

    Science.gov (United States)

    Huang, Cheng; Jiang, Jia-Yin; Chang, Shin C; Tsay, Yeou-Guang; Chen, Mei-Ru; Chang, Ming-Fu

    2013-02-01

    Nuclear export is an important process that not only regulates the functions of cellular factors but also facilitates the assembly of viral nucleoprotein complexes. Chromosome region maintenance 1 (CRM1) that mediates the transport of proteins bearing the classical leucine-rich nuclear export signal (NES) is the best-characterized nuclear export receptor. Recently, several CRM1-independent nuclear export pathways were also identified. The nuclear export of the large form of hepatitis delta antigen (HDAg-L), a nucleocapsid protein of hepatitis delta virus (HDV), which contains a CRM1-independent proline-rich NES, is mediated by the host NES-interacting protein (NESI). The mechanism of the NESI protein in mediating nuclear export is still unknown. In this study, NESI was characterized as a highly glycosylated membrane protein. It interacted and colocalized well in the nuclear envelope with lamin A/C and nucleoporins. Importantly, HDAg-L could be coimmunoprecipitated with lamin A/C and nucleoporins. In addition, binding of the cargo HDAg-L to the C terminus of NESI was detected for the wild-type protein but not for the nuclear export-defective HDAg-L carrying a P205A mutation [HDAg-L(P205A)]. Knockdown of lamin A/C effectively reduced the nuclear export of HDAg-L and the assembly of HDV. These data indicate that by forming complexes with lamin A/C and nucleoporins, NESI facilitates the CRM1-independent nuclear export of HDAg-L.

  18. Inspection of nuclear fuel transport in Spain

    International Nuclear Information System (INIS)

    Lobo Mendez, J.

    1977-01-01

    The experience acquired in inspecting nuclear fuel shipments carried out in Spain will serve as a basis for establishing the regulations wich must be adhered to for future transports, as the transport of nuclear fuels in Spain will increase considerably within the next years as a result of the Spanish nuclear program. The experience acquired in nuclear fuel transport inspection is described. (author) [es

  19. Government experience in nuclear power plant export financing

    International Nuclear Information System (INIS)

    Kalbitz, K.

    1976-01-01

    Because the long-term funds at the disposal of the commercial banks were insufficient to make available the amounts required for the exportation of nuclear power plants, it was necessary to make available long-term funds of the mortgage banks. On account of the strict regulations governing the lending operations of such banks, it was, however, necessary to introduce a Federal guarantee which covers 100% of the contract value in each case. On balance, however, the Federal Government does not take over any additional risks, because recourse may be taken to the commercial banks, which are liable for all additional payments under the credit arrangement having arisen from the improvement of the guarantee in favour of the mortgage banks. This has resulted in a considerable improvement of the export financing system which, of course, is for benefit of other major export projects too. (HP) [de

  20. Nuclear Export Control Policy in Korea - Present and future

    International Nuclear Information System (INIS)

    Kim, Jongsook

    2008-01-01

    The International community has been facing with the continued challenges for possession and proliferation of WMD over the past years. In addition, it is known that the terrorist groups are interested in acquiring WMD. The black market of WMD related materials and technologies show also the one of seriousness of our challenges. A number of international treaties, agreements and initiatives to control the proliferation of weapons of N, B, C and their delivery system have been existed to deal with these challenges, but their missions are challenged greatly in recent a series of nuclear issues by Iran and North Korea. The paper reviews the current international export control status and Korea export control system and policy. It also addresses some agenda to be done as future export control policy in Korea

  1. Nuclear fuel assembly

    International Nuclear Information System (INIS)

    Takeda, Tadashi; Sato, Kenji; Goto, Masakazu.

    1984-01-01

    Purpose: To facilitate identification of a fuel assembly upon fuel exchange in BWR type reactors. Constitution: Fluorescent material is coated or metal plating is applied to the impressed portion of a upper tie plate handle of a fuel assembly, and the fluorescent material or the metal plating surface is covered with a protective membrane made of transparent material. This enables to distinguish the impressed surface from a distant place and chemical reaction between the impressed surface and the reactor water can be prevented. Furthermore, since the protective membrane is formed such that it protrudes toward the upper side relative to the impressed surface, there is no risk of depositions of claddings thereover. (Moriyama, K.)

  2. Nuclear fuel elements design, fabrication and performance

    CERN Document Server

    Frost, Brian R T

    1982-01-01

    Nuclear Fuel Elements: Design, Fabrication and Performance is concerned with the design, fabrication, and performance of nuclear fuel elements, with emphasis on fast reactor fuel elements. Topics range from fuel types and the irradiation behavior of fuels to cladding and duct materials, fuel element design and modeling, fuel element performance testing and qualification, and the performance of water reactor fuels. Fast reactor fuel elements, research and test reactor fuel elements, and unconventional fuel elements are also covered. This volume consists of 12 chapters and begins with an overvie

  3. Nuclear fuel rod

    International Nuclear Information System (INIS)

    Ross, W.T.; Williamson, H.E.

    1977-01-01

    In order to improve the efficiency of Zr or Zr alloy getters in the fuel cans of a fuel element, the formation of Zr oxide layers must be prevented. Therefore, a compound body acting as a bimetal is to be inserted which consists of a metallic substrate (Ni, Ni alloys, ferro-alloys, steel, Ti, Ti alloys) and a coating (Zr, Zr alloys). The substrate has a much higher thermal expansion coefficient than the coating, so that the surface of the coating layer formed is constantly torn apart at normal operating temperatures of the reactor. The invention is described in great detail. (HP) [de

  4. 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)

  5. Regulating nuclear fuel waste

    International Nuclear Information System (INIS)

    1995-01-01

    When Parliament passed the Atomic Energy Control Act in 1946, it erected the framework for nuclear safety in Canada. Under the Act, the government created the Atomic Energy Control Board and gave it the authority to make and enforce regulations governing every aspect of nuclear power production and use in this country. The Act gives the Control Board the flexibility to amend its regulations to adapt to changes in technology, health and safety standards, co-operative agreements with provincial agencies and policy regarding trade in nuclear materials. This flexibility has allowed the Control Board to successfully regulate the nuclear industry for more than 40 years. Its mission statement 'to ensure that the use of nuclear energy in Canada does not pose undue risk to health, safety, security and the environment' concisely states the Control Board's primary objective. The Atomic Energy Control Board regulates all aspects of nuclear energy in Canada to ensure there is no undue risk to health, safety, security or the environment. It does this through a multi-stage licensing process

  6. Fuel Fabrication and Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-02-02

    The uranium from the enrichment plant is still in the form of UF6. UF6 is not suitable for use in a reactor due to its highly corrosive chemistry as well as its phase diagram. UF6 is converted into UO2 fuel pellets, which are in turn placed in fuel rods and assemblies. Reactor designs are variable in moderators, coolants, fuel, performance etc.The dream of energy ‘too-cheap to meter’ is no more, and now the nuclear power industry is pushing ahead with advanced reactor designs.

  7. Fuel Fabrication and Nuclear Reactors

    International Nuclear Information System (INIS)

    Karpius, Peter Joseph

    2017-01-01

    The uranium from the enrichment plant is still in the form of UF 6 . UF 6 is not suitable for use in a reactor due to its highly corrosive chemistry as well as its phase diagram. UF 6 is converted into UO 2 fuel pellets, which are in turn placed in fuel rods and assemblies. Reactor designs are variable in moderators, coolants, fuel, performance etc.The dream of energy ''too-cheap to meter'' is no more, and now the nuclear power industry is pushing ahead with advanced reactor designs.

  8. Nuclear fuel cycle studies

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    For the metal-matrix encapsulation of radioactive waste, brittle-fracture, leach-rate, and migration studies are being conducted. For fuel reprocessing, annular and centrifugal contactors are being tested and modeled. For the LWBR proof-of-breeding project, the full-scale shear and the prototype dissolver were procured and tested. 5 figures

  9. Contracting for nuclear fuels

    International Nuclear Information System (INIS)

    Schuessler, C.M.

    1981-10-01

    This paper deals with uranium sales contracts, i.e. with contractual arrangements in the first steps of the fuel cycle, which cover uranium production and conversion. The various types of contract are described and, where appropriate, their underlying business philosophy and their main terms and conditions. Finally, the specific common features of such contracts are reviewed. (NEA) [fr

  10. Fuel assemblies for nuclear reactors

    International Nuclear Information System (INIS)

    Leonard, B.H. Jr.

    1975-01-01

    A description is given of a fuel assembly for a nuclear reactor comprising a plurality of elongated plate-like fuel bearing elements of the same length and width, paired longer than they are wide and assembly spacer members having means defining opposed spaced notches for receiving the side edges of said elongated plate-like fuel bearing elements, and means for securing said plate-like fuel bearing elements to said paired assembly spacer members with the side edges of said plate-like elements engaged in opposite notches in said paired assembly spacer elements so as to secure said fuel bearing elements in side by side spaced relation in a staggered arrangement transversely so as to conform to a diamond shaped profile in which opposite sides are parallel and opposite angles are substantially 60 0 and substantially 120 0

  11. Experience with the export of nuclear plants

    International Nuclear Information System (INIS)

    Huettl, A.

    1991-01-01

    Licensing and regulatory aspects represent an important issue during the definition and implementation phase of a nuclear power project. Strict adherence to the principles 'licensability in country of origin' and 'reference plant as built' may prove to be counterproductive on account of the differences in licensing infrastructure in vendor's and buyer's countries and of the difficulty in striking a balance between proven and up-to-date designs. In order to repeat good experience in safety, consistency of the applicable rules and regulations is important when performing the necessary adaptations to local requirements. The use of an internationally accepted body of rules such as NUSS as a yardstick for safety evaluation helps to identify special requirements in vendor's country, thus minimizing distortions in evaluation of competing bids. Benefitting from ongoing efforts to improve transparency and mutual understanding of the national safety approaches through bodies and missions like INSAG, WANO, OSART, a graded approach for implementing safety review during construction and operation is suggested, matching it to the scope of a national program of NPP construction. Together with efficient project control this will minimize the demands on resources - both human and financial - required for a successful launch of a nuclear power plant. (orig.)

  12. Nuclear reactor fuel element

    International Nuclear Information System (INIS)

    D'Eye, R.W.M.; Shennan, J.V.; Ford, L.H.

    1977-01-01

    Fuel element with particles from ceramic fissionable material (e.g. uranium carbide), each one being coated with pyrolitically deposited carbon and all of them being connected at their points of contact by means of an individual crossbar. The crossbar consists of silicon carbide produced by reaction of silicon metal powder with the carbon under the influence of heat. Previously the silicon metal powder together with the particles was kneaded in a solvent and a binder (e.g. epoxy resin in methyl ethyl ketone plus setting agent) to from a pulp. The reaction temperature lies at 1750 0 C. The reaction itself may take place in a nitrogen atmosphere. There will be produced a fuel element with a high overall thermal conductivity. (DG) [de

  13. 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)

  14. Import and export of small quantities of nuclear materials

    International Nuclear Information System (INIS)

    Grenier, M.

    1986-06-01

    Administrative procedures for import export of nuclear materials are specific for each country. In France regulations are reviewed for small quantities, lower threshold, in some cases, allows a simplified procedure, however thresholds are not the same in the different texts (and for one of them, concerning proliferation, is zero). It is obvious that regulations are necessary even for small quantities but national and international threshold should be harmonized [fr

  15. Fire resistant nuclear fuel cask

    Science.gov (United States)

    Heckman, Richard C.; Moss, Marvin

    1979-01-01

    The disclosure is directed to a fire resistant nuclear fuel cask employing reversibly thermally expansible bands between adjacent cooling fins such that normal outward flow of heat is not interfered with, but abnormal inward flow of heat is impeded or blocked.

  16. Disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    1979-12-01

    This report addresses the topic of the mined geologic disposal of spent nuclear fuel from Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). Although some fuel processing options are identified, most of the information in this report relates to the isolation of spent fuel in the form it is removed from the reactor. The characteristics of the waste management system and research which relate to spent fuel isolation are discussed. The differences between spent fuel and processed HLW which impact the waste isolation system are defined and evaluated for the nature and extent of that impact. What is known and what needs to be determined about spent fuel as a waste form to design a viable waste isolation system is presented. Other waste forms and programs such as geologic exploration, site characterization and licensing which are generic to all waste forms are also discussed. R and D is being carried out to establish the technical information to develop the methods used for disposal of spent fuel. All evidence to date indicates that there is no reason, based on safety considerations, that spent fuel should not be disposed of as a waste

  17. Disposal of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    This report addresses the topic of the mined geologic disposal of spent nuclear fuel from Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). Although some fuel processing options are identified, most of the information in this report relates to the isolation of spent fuel in the form it is removed from the reactor. The characteristics of the waste management system and research which relate to spent fuel isolation are discussed. The differences between spent fuel and processed HLW which impact the waste isolation system are defined and evaluated for the nature and extent of that impact. What is known and what needs to be determined about spent fuel as a waste form to design a viable waste isolation system is presented. Other waste forms and programs such as geologic exploration, site characterization and licensing which are generic to all waste forms are also discussed. R and D is being carried out to establish the technical information to develop the methods used for disposal of spent fuel. All evidence to date indicates that there is no reason, based on safety considerations, that spent fuel should not be disposed of as a waste.

  18. World nuclear fuel cycle requirements 1991

    International Nuclear Information System (INIS)

    1991-01-01

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

  19. World nuclear fuel cycle requirements 1991

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-10

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

  20. 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.

  1. Nuclear reactor fuel element

    International Nuclear Information System (INIS)

    Lippert, H.J.

    1985-01-01

    The fuel element box for a BWR is situated with a corner bolt on the inside in one corner of its top on the top side of the top plate. This corner bolt is screwed down with a bolt with a corner part which is provided with leaf springs outside on two sides, where the bolt has a smaller diameter and an expansion shank. The bolt is held captive to the bolt head on the top and the holder on the bottom of the corner part. The holder is a locknut. If the expansion forces are too great, the bolt can only break at the expansion shank. (HP) [de

  2. Uranium - the nuclear fuel

    International Nuclear Information System (INIS)

    Smith, E.E.N.

    1976-01-01

    A brief history is presented of Canadian uranium exploration, production, and sales. Statistics show that Canada is a good customer for its own uranium due to a rapidly expanding nuclear power program. Due to an average 10 year lag between commencement of exploration and production, and with current producers sold out through 1985, it is imperative that exploration efforts be increased. (E.C.B.)

  3. Nuclear Imprisonment: Viral Strategies to Arrest Host mRNA Nuclear Export

    Directory of Open Access Journals (Sweden)

    Beatriz M. A. Fontoura

    2013-07-01

    Full Text Available Viruses possess many strategies to impair host cellular responses to infection. Nuclear export of host messenger RNAs (mRNA that encode antiviral factors is critical for antiviral protein production and control of viral infections. Several viruses have evolved sophisticated strategies to inhibit nuclear export of host mRNAs, including targeting mRNA export factors and nucleoporins to compromise their roles in nucleo-cytoplasmic trafficking of cellular mRNA. Here, we present a review of research focused on suppression of host mRNA nuclear export by viruses, including influenza A virus and vesicular stomatitis virus, and the impact of this viral suppression on host antiviral responses.

  4. NUCLEAR REACTOR FUEL ELEMENT ASSEMBLY

    Science.gov (United States)

    Stengel, F.G.

    1963-12-24

    A method of fabricating nuclear reactor fuel element assemblies having a plurality of longitudinally extending flat fuel elements in spaced parallel relation to each other to form channels is presented. One side of a flat side plate is held contiguous to the ends of the elements and a welding means is passed along the other side of the platertransverse to the direction of the longitudinal extension of the elements. The setting and speed of travel of the welding means is set to cause penetration of the side plate with welds at bridge the gap in each channel between adjacent fuel elements with a weld-through bubble of predetermined size. The fabrication of a high strength, dependable fuel element is provided, and the reduction of distortion and high production costs are facilitated by this method. (AEC)

  5. 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

  6. Compositions and methods for treating nuclear fuel

    Science.gov (United States)

    Soderquist, Chuck Z; Johnsen, Amanda M; McNamara, Bruce K; Hanson, Brady D; Smith, Steven C; Peper, Shane M

    2013-08-13

    Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

  7. Analysis of World Nuclear Market and Strategy of Korean NPP's Competitiveness Improvement for Exportation

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jae Young; Jeong, Yong Hoon [KAIST, Daejeon (Korea, Republic of); Roh, Seungkook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Chang, Soon Heung [Handong Global University, Pohang (Korea, Republic of)

    2016-10-15

    China, India and USA (nuclear adopted countries) are planning tremendous number of NPPs to meet their increasing electricity demand and Saudi Arabia, Vietnam (nuclear adopting countries) are also planning to include nuclear power in their energy mix as a long-term plan. Korea has exported 4 units of APR1400 to the UAE in December, 2009. Korea became sixth NPP supplier country and our economic feasibility and safety features were started to evaluate worldwide. Nuclear industries became a new driver of Korea’s export and nuclear industries in Korea are now expecting another NPP export to Middle-eastern countries, including UAE and Saudi Arabia, based on the first-mover’s advantage at the UAE. In 2000s, five countries (Japan, USA, France, Russia and Korea), which are able to build NPP, focused on NPP export more than domestic construction. Global trend of world nuclear market changed rapidly, especially after NPP export to the UAE. By the global trend, hegemony of nuclear market migrated from supplier country to buyer country. Nuclear companies started cooperating rather than competing. Financing to developing countries become more important. In general, one of the considerable combinations is Korea-Japan-USA alliance. Korea is in charge of EPC, Japan supports financing and deficient technology (with USA partner), and Japan-USA handles fuel supply and back-end fuel cycle based on new agreed terms of ROK-US Nuclear Cooperation Agreement. This combination was judged to best way to collaborate with global companies. Paying attention to many delayed (or potentially delayed) constructions from Russia, intercepting the construction work will be available in case of contracted countries. Korea can emphasize the short construction time, high responsiveness and mild/equal diplomatic position to the target countries.

  8. Analysis of World Nuclear Market and Strategy of Korean NPP's Competitiveness Improvement for Exportation

    International Nuclear Information System (INIS)

    Choi, Jae Young; Jeong, Yong Hoon; Roh, Seungkook; Chang, Soon Heung

    2016-01-01

    China, India and USA (nuclear adopted countries) are planning tremendous number of NPPs to meet their increasing electricity demand and Saudi Arabia, Vietnam (nuclear adopting countries) are also planning to include nuclear power in their energy mix as a long-term plan. Korea has exported 4 units of APR1400 to the UAE in December, 2009. Korea became sixth NPP supplier country and our economic feasibility and safety features were started to evaluate worldwide. Nuclear industries became a new driver of Korea’s export and nuclear industries in Korea are now expecting another NPP export to Middle-eastern countries, including UAE and Saudi Arabia, based on the first-mover’s advantage at the UAE. In 2000s, five countries (Japan, USA, France, Russia and Korea), which are able to build NPP, focused on NPP export more than domestic construction. Global trend of world nuclear market changed rapidly, especially after NPP export to the UAE. By the global trend, hegemony of nuclear market migrated from supplier country to buyer country. Nuclear companies started cooperating rather than competing. Financing to developing countries become more important. In general, one of the considerable combinations is Korea-Japan-USA alliance. Korea is in charge of EPC, Japan supports financing and deficient technology (with USA partner), and Japan-USA handles fuel supply and back-end fuel cycle based on new agreed terms of ROK-US Nuclear Cooperation Agreement. This combination was judged to best way to collaborate with global companies. Paying attention to many delayed (or potentially delayed) constructions from Russia, intercepting the construction work will be available in case of contracted countries. Korea can emphasize the short construction time, high responsiveness and mild/equal diplomatic position to the target countries

  9. The new US nuclear non-proliferation and export policy

    International Nuclear Information System (INIS)

    Welck, S. von.

    1981-01-01

    The future American nuclear non-proliferation and export policy will be determined chiefly by three elements: (1) Adherence to the former objective of nuclear non-proliferation. (2) A large and varied assortment of old and new tools for implementing this goal. (3) Much more differentiation in applying these tools in the light of the reliability, with respect to non-proliferation policy, of the respective partner. Consequently, it would make little sense for the new Administration to force upon allied industrialized countries, whose nuclear technologies are at the same level as that of the United States, restrictive rules on reprocessing and breeder technology. The new measures designed to curb proliferation are especially meant to destroy motivations that could cause states to own nuclear explosives. This also applies to the removal of economic motivations. (orig.) [de

  10. Regulation of p53 tetramerization and nuclear export by ARC.

    Science.gov (United States)

    Foo, Roger S-Y; Nam, Young-Jae; Ostreicher, Marc Jason; Metzl, Mark D; Whelan, Russell S; Peng, Chang-Fu; Ashton, Anthony W; Fu, Weimin; Mani, Kartik; Chin, Suet-Feung; Provenzano, Elena; Ellis, Ian; Figg, Nichola; Pinder, Sarah; Bennett, Martin R; Caldas, Carlos; Kitsis, Richard N

    2007-12-26

    Inactivation of the transcription factor p53 is central to carcinogenesis. Yet only approximately one-half of cancers have p53 loss-of-function mutations. Here, we demonstrate a mechanism for p53 inactivation by apoptosis repressor with caspase recruitment domain (ARC), a protein induced in multiple cancer cells. The direct binding in the nucleus of ARC to the p53 tetramerization domain inhibits p53 tetramerization. This exposes a nuclear export signal in p53, triggering Crm1-dependent relocation of p53 to the cytoplasm. Knockdown of endogenous ARC in breast cancer cells results in spontaneous tetramerization of endogenous p53, accumulation of p53 in the nucleus, and activation of endogenous p53 target genes. In primary human breast cancers with nuclear ARC, p53 is almost always WT. Conversely, nearly all breast cancers with mutant p53 lack nuclear ARC. We conclude that nuclear ARC is induced in cancer cells and negatively regulates p53.

  11. Ceramics as nuclear reactor fuels

    International Nuclear Information System (INIS)

    Reeve, K.D.

    1975-01-01

    Ceramics are widely accepted as nuclear reactor fuel materials, for both metal clad ceramic and all-ceramic fuel designs. Metal clad UO 2 is used commercially in large tonnages in five different power reactor designs. UO 2 pellets are made by familiar ceramic techniques but in a reactor they undergo complex thermal and chemical changes which must be thoroughly understood. Metal clad uranium-plutonium dioxide is used in present day fast breeder reactors, but may eventually be replaced by uranium-plutonium carbide or nitride. All-ceramic fuels, which are necessary for reactors operating above about 750 0 C, must incorporate one or more fission product retentive ceramic coatings. BeO-coated BeO matrix dispersion fuels and silicate glaze coated UO 2 -SiO 2 have been studied for specialised applications, but the only commercial high temperature fuel is based on graphite in which small fuel particles, each coated with vapour deposited carbon and silicon carbide, are dispersed. Ceramists have much to contribute to many aspects of fuel science and technology. (author)

  12. Fuel assemblies for nuclear reactor

    International Nuclear Information System (INIS)

    Nishi, Akihito.

    1987-01-01

    Purpose: To control power-up rate at the initial burning stage of new fuel assemblies due to fuel exchange in a pressure tube type power reactor. Constitution: Burnable poisons are disposed to a most portion of fuel pellets in a fuel assembly to such a low concentration as the burn-up rate changes with time at the initial stage of the burning. The most portion means substantially more than one-half part of the pellets and gadolinia is used as burn-up poisons to be dispersed and the concentration is set to less than about 0.2 %. Upon elapse of about 15 days after the charging, the burnable poisons are eliminated and the infinite multiplication factors are about at 1.2 to attain a predetermined power state. Since the power-up rate of the nuclear reactor fuel assembly is about 0.1 % power/hour and the power-up rate of the fuel assembly around the exchanged channel is lower than that, it can be lowered sufficiently than the limit for the power-up rate practiced upon reactor start-up thereby enabling to replace fuels during power operation. (Horiuchi, T.)

  13. 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

  14. 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.)

  15. Nuclear export of cutaneous HPV8 E7 oncoprotein is mediated by a leucine-rich nuclear export signal via a CRM1 pathway

    International Nuclear Information System (INIS)

    Onder, Zeynep; Chang, Vivian; Moroianu, Junona

    2015-01-01

    We recently determined that the nuclear import of cutaneous beta genus HPV8 E7 oncoprotein it is mediated by its zinc-binding domain via direct hydrophobic interactions with the FG nucleoporins Nup62 and Nup153 (Onder and Moroianu, 2014). Here we investigated the nuclear export of HPV8 E7 oncoprotein using confocal microscopy after transfections of HeLa cells with EGFP–8cE7 and mutant plasmids and treatment with Ratjadone A nuclear export inhibitor. We determined that HPV8 E7 contains a leucine-rich nuclear export signal (NES), 76 IRTFQELLF 84 , within its zinc-binding domain that mediates its nuclear export via a CRM1 pathway. We found that HPV8 E7 interacts with CRM1 and that the hydrophobic amino acid residues I76, F79 and L82 of the NES are essential for this interaction and for nuclear export of HPV8 E7 oncoprotein. - Highlights: • HPV8 E7 has a leucine-rich NES within its zinc-binding domain that mediates its nuclear export. • CRM1 nuclear export receptor interacts with HPV8 E7 and mediates its export. • Identification of the critical hydrophobic amino acids of the NES of HPV8 E7

  16. Nuclear export of cutaneous HPV8 E7 oncoprotein is mediated by a leucine-rich nuclear export signal via a CRM1 pathway

    Energy Technology Data Exchange (ETDEWEB)

    Onder, Zeynep; Chang, Vivian; Moroianu, Junona, E-mail: moroianu@bc.edu

    2015-01-01

    We recently determined that the nuclear import of cutaneous beta genus HPV8 E7 oncoprotein it is mediated by its zinc-binding domain via direct hydrophobic interactions with the FG nucleoporins Nup62 and Nup153 (Onder and Moroianu, 2014). Here we investigated the nuclear export of HPV8 E7 oncoprotein using confocal microscopy after transfections of HeLa cells with EGFP–8cE7 and mutant plasmids and treatment with Ratjadone A nuclear export inhibitor. We determined that HPV8 E7 contains a leucine-rich nuclear export signal (NES), {sub 76}IRTFQELLF{sub 84}, within its zinc-binding domain that mediates its nuclear export via a CRM1 pathway. We found that HPV8 E7 interacts with CRM1 and that the hydrophobic amino acid residues I76, F79 and L82 of the NES are essential for this interaction and for nuclear export of HPV8 E7 oncoprotein. - Highlights: • HPV8 E7 has a leucine-rich NES within its zinc-binding domain that mediates its nuclear export. • CRM1 nuclear export receptor interacts with HPV8 E7 and mediates its export. • Identification of the critical hydrophobic amino acids of the NES of HPV8 E7.

  17. Proliferation Resistant Nuclear Reactor Fuel

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-02-18

    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

  18. Nuclear fuel microsphere gamma analyzer

    International Nuclear Information System (INIS)

    Valentine, K.H.; Long, E.L. Jr.; Willey, M.G.

    1977-01-01

    A gamma analyzer system is provided for the analysis of nuclear fuel microspheres and other radioactive particles. The system consists of an analysis turntable with means for loading, in sequence, a plurality of stations within the turntable; a gamma ray detector for determining the spectrum of a sample in one section; means for analyzing the spectrum; and a receiver turntable to collect the analyzed material in stations according to the spectrum analysis. Accordingly, particles may be sorted according to their quality; e.g., fuel particles with fractured coatings may be separated from those that are not fractured, or according to other properties. 4 claims, 3 figures

  19. O. Nuclear energy in a food exporting country

    International Nuclear Information System (INIS)

    1976-01-01

    This report attempts to estimate the affect on agricultural exports from New Zealand which might result from the operation of nuclear power. By far the most serious of these would result from an accidental release of radioactive material, and the likely affects of such releases are considered both in the first year after an accident and in the future. Previous assessments of this type have concentrated attention on property damage and on the health hazards which might result to consumers of contaminated food in the first year or two after a release. In this report the emphasis is on exported foods to which different criteria might apply, and some very approximate estimates are made of long-term implications. To a large extent these can be described only as speculations, but they have some value as a guide. No analgous report has been found in the open literature from other countries, and this particularly includes Denmark which has much in common with New Zealand in this regard. The possible effect of routine operation of nuclear power on food exports is also briefly considered

  20. Coal and nuclear electricity fuels

    International Nuclear Information System (INIS)

    Rahnama, F.

    1982-06-01

    Comparative economic analysis is used to contrast the economic advantages of nuclear and coal-fired electric generating stations for Canadian regions. A simplified cash flow method is used with present value techniques to yield a single levelized total unit energy cost over the lifetime of a generating station. Sensitivity analysis illustrates the effects of significant changes in some of the cost data. The analysis indicates that in Quebec, Ontario, Manitoba and British Columbia nuclear energy is less costly than coal for electric power generation. In the base case scenario the nuclear advantage is 24 percent in Quebec, 29 percent in Ontario, 34 percent in Manitoba, and 16 percent in British Columbia. Total unit energy cost is sensitive to variations in both capital and fuel costs for both nuclear and coal-fuelled power stations, but are not very sensitive to operating and maintenance costs

  1. Nuclear Fuels: Present and Future

    Directory of Open Access Journals (Sweden)

    Donald R. Olander

    2009-02-01

    Full Text Available The important new developments in nuclear fuels and their problems are reviewed and compared with the status of present light-water reactor fuels. The limitations of these fuels and the reactors they power are reviewed with respect to important recent concerns, namely provision of outlet coolant temperatures high enough for use in H2 production, destruction of plutonium to eliminate proliferation concerns, and burning of the minor actinides to reduce the waste repository heat load and long-term radiation hazard. In addition to current oxide-based fuel-rod designs, the hydride fuel with liquid metal thermal bonding of the fuel-cladding gap is covered. Finally, two of the most promising Generation IV reactor concepts, the Very High Temperature Reactor and the Sodium Fast Reactor, and the accompanying reprocessing technologies, aqueous-based UREX and pyrometallurgical, are summarized. In all of the topics covered, the thermodynamics involved in the material's behavior under irradiation and in the reprocessing schemes are emphasized.

  2. Interfaces in ceramic nuclear fuels

    International Nuclear Information System (INIS)

    Reeve, K.D.

    Internal interfaces in all-ceramic dispersion fuels (such as these for HTGRs) are discussed for two classes: BeO-based dispersions, and coated particles for graphite-based fuels. The following points are made: (1) The strength of a two-phase dispersion is controlled by the weaker dispersed phase bonded to the matrix. (2) Differential expansion between two phases can be controlled by an intermediate buffer zone of low density. (3) A thin ceramic coating should be in compression. (4) Chemical reaction between coating and substrate and mass transfer in service should be minimized. The problems of the nuclear fuel designer are to develop coatings for fission product retention, and to produce radiation-resistant interfaces. 44 references, 18 figures

  3. Electrochemical reprocessing of nuclear fuels

    International Nuclear Information System (INIS)

    Brambilla, G.; Sartorelli, A.

    1980-01-01

    A method is described for the reprocessing of irradiated nuclear fuel which is particularly suitable for use with fuel from fast reactors and has the advantage of being a dry process in which there is no danger of radiation damage to a solvent medium as in a wet process. It comprises the steps of dissolving the fuel in a salt melt under such conditions that uranium and plutonium therein are converted to sulphate form. The plutonium sulphate may then be thermally decomposed to PuO 2 and removed. The salt melt is then subjected to electrolysis conditions to achieve cathodic deposition of UO 2 (and possibly PuO 2 ). The salt melt can then be recycled or conditioned for final disposal. (author)

  4. The implications of nuclear export policies and trade on the current and future development in Spain

    International Nuclear Information System (INIS)

    Sanchez, J.L.

    1978-01-01

    This paper deals with the status of the Spanish nuclear programme. The 1964 Act on nuclear energy authorizes the Spanish Government to conclude bilateral agreements enabling Spain to benefit from the transfer of advanced technologies. In this context, Spain signed an agreement with the U.S. on 20 March 1974 and another agreement with IAEA and the U.S. in June 1974. The paper also envisages the consequences of the U.S. 1978 Non-Proliferation Act on Spain's nuclear activities: need to renegotiate the present agreements, loss of confidence in view of the new conditions imposed (restrictions in export licences) and practical implementation for the three Spanish installations which use enriched fuel of American origin. (NEA) [fr

  5. Nuclear fuel production at BNFL plants

    International Nuclear Information System (INIS)

    Petritskij, E.P.

    1994-01-01

    The structure of nuclear fuel production at BNFL plants is described, as well as basic technological processes of UO 2 powder production including IDR process for automatic fabrication of fuel elements and fuel assemblies. Physical and chemical properties of UO 2 powder, fuel pellet sintering parameters, data on in-reactor operation of nuclear fuels fabricated from pellets of controlled porosity with CONPOR additives, are presented. 8 refs.; 2 figs.; 3 tabs

  6. External cost assessment for nuclear fuel cycle

    International Nuclear Information System (INIS)

    Park, Byung Heung; Ko, Won Il

    2015-01-01

    Nuclear power is currently the second largest power supply method in Korea and the number of nuclear power plants are planned to be increased as well. However, clear management policy for spent fuels generated from nuclear power plants has not yet been established. The back-end fuel cycle, associated with nuclear material flow after nuclear reactors is a collection of technologies designed for the spent fuel management and the spent fuel management policy is closely related with the selection of a nuclear fuel cycle. Cost is an important consideration in selection of a nuclear fuel cycle and should be determined by adding external cost to private cost. Unlike the private cost, which is a direct cost, studies on the external cost are focused on nuclear reactors and not at the nuclear fuel cycle. In this research, external cost indicators applicable to nuclear fuel cycle were derived and quantified. OT (once through), DUPIC (Direct Use of PWR SF in CANDU), PWR-MOX (PWR PUREX reprocessing), and Pyro-SFR (SFR recycling with pyroprocessing) were selected as nuclear fuel cycles which could be considered for estimating external cost in Korea. Energy supply security cost, accident risk cost, and acceptance cost were defined as external cost according to precedent and estimated after analyzing approaches which have been adopted for estimating external costs on nuclear power generation

  7. Nuclear localization signal regulates porcine circovirus type 2 capsid protein nuclear export through phosphorylation.

    Science.gov (United States)

    Hou, Qiang; Hou, Shaohua; Chen, Qing; Jia, Hong; Xin, Ting; Jiang, Yitong; Guo, Xiaoyu; Zhu, Hongfei

    2018-02-15

    The open reading frame 2 (ORF2) of Porcine circovirus type 2 (PCV2) encodes the major Capsid (Cap) protein, which self-assembles into virus-like particle (VLP) of similar morphology to the PCV2 virion and accumulates in the nucleus through the N-terminal arginine-rich nuclear localization signal (NLS). In this study, PCV2 Cap protein and its derivates were expressed via the baculovirus expression system, and the cellular localization of the recombinant proteins were investigated using anti-Cap mAb by imaging flow cytometry. Analysis of subcellular localization of Cap protein and its variants demonstrated that NLS mediated Cap protein nuclear export as well as nuclear import, and a phosphorylation site (S17) was identified by liquid chromatography-tandem mass spectrometry (LC-MS/MS) in the NLS domain to regulate Cap protein nuclear export. Phosphorylation of NLS regulating the PCV2 Cap protein nuclear export was also demonstrated in PK15 cells by fluorescence microscopy. Moreover, the influence of Rep and Rep' protein on Cap protein subcellular localization was investigated in PK15 cells. Phosphorylation of NLS regulating Cap protein nuclear export provides more detailed knowledge of the PCV2 viral life cycle. Copyright © 2018 Elsevier B.V. All rights reserved.

  8. ALD coating of nuclear fuel actinides materials

    Science.gov (United States)

    Yacout, A. M.; Pellin, Michael J.; Yun, Di; Billone, Mike

    2017-09-05

    The invention provides a method of forming a nuclear fuel pellet of a uranium containing fuel alternative to UO.sub.2, with the steps of obtaining a fuel form in a powdered state; coating the fuel form in a powdered state with at least one layer of a material; and sintering the powdered fuel form into a fuel pellet. Also provided is a sintered nuclear fuel pellet of a uranium containing fuel alternative to UO.sub.2, wherein the pellet is made from particles of fuel, wherein the particles of fuel are particles of a uranium containing moiety, and wherein the fuel particles are coated with at least one layer between about 1 nm to about 4 nm thick of a material using atomic layer deposition, and wherein the at least one layer of the material substantially surrounds each interfacial grain barrier after the powdered fuel form has been sintered.

  9. A second CRM1-dependent nuclear export signal in the influenza A virus NS2 protein contributes to the nuclear export of viral ribonucleoproteins.

    Science.gov (United States)

    Huang, Shengping; Chen, Jingjing; Chen, Quanjiao; Wang, Huadong; Yao, Yanfeng; Chen, Jianjun; Chen, Ze

    2013-01-01

    Influenza A virus NS2 protein, also called nuclear export protein (NEP), is crucial for the nuclear export of viral ribonucleoproteins. However, the molecular mechanisms of NEP mediation in this process remain incompletely understood. A leucine-rich nuclear export signal (NES2) in NEP, located at the predicted N2 helix of the N-terminal domain, was identified in the present study. NES2 was demonstrated to be a transferable NES, with its nuclear export activity depending on the nuclear export receptor chromosome region maintenance 1 (CRM1)-mediated pathway. The interaction between NEP and CRM1 is coordinately regulated by both the previously reported NES (NES1) and now the new NES2. Deletion of the NES1 enhances the interaction between NEP and CRM1, and deletion of the NES1 and NES2 motifs completely abolishes this interaction. Moreover, NES2 interacts with CRM1 in the mammalian two-hybrid system. Mutant viruses containing NES2 alterations generated by reversed genetics exhibit reduced viral growth and delay in the nuclear export of viral ribonucleoproteins (vRNPs). The NES2 motif is highly conserved in the influenza A and B viruses. The results demonstrate that leucine-rich NES2 is involved in the nuclear export of vRNPs and contributes to the understanding of nucleocytoplasmic transport of influenza virus vRNPs.

  10. Nuclear power, nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    1991-01-01

    The following topics are discussed in 5 chapters: nuclear power, nuclear fuel cycle, radioactive waste management, special events, highlights of the IAEA's work. In the field of nuclear power, the status of nuclear energy generation at the end of 1990 is presented, as well as power plant performance, nuclear power costs, power plant aging and life extension, advanced reactor systems, quality management and quality assurance, automation and human action in nuclear power plant operation and finally the trends of nuclear power to 2010. The following aspects concerning nuclear fuel cycle are discussed: uranium exploration, resources, supply and demand, refining and conversion, enrichment, reactor fuel technology, spent fuel management, economics of the nuclear fuel cycle and trends for the near future. In the field of radioactive waste management, problems concerning treatment and conditioning of radioactive waste, radioactive waste disposal, decontamination and decommissioning and trends for the near future are discussed. Refs, figs and tabs

  11. Nuclear fuel cycle activities with an utility

    International Nuclear Information System (INIS)

    Schwarz, E.

    1977-01-01

    The lecture will deal with the following topics: Fuel requirements: establishing fuel requirements - first core - reloads. Calculation of required uranium and separation work: reload planning - long term - short term - during refuelling; exactness of calculations: contracts: 1) Uranium and conversion; 2) Enrichment services; 3) Fuel elements; 4) Ownership; 5) Accidential loss of material; 6) Flexibility in time and amounts; 7) Specifications, surcharges; 8) Terms of payment; 9) Fuel containers, ownership, retransport; fuel reserves: 1) Natural uranium (concentrates or reserves in the ground); 2) Enriched uranium; 3) Fuel elements; 4) Cost of reserves; 5) Exchange in case of need. Handling of contracts: 1) Schedule for deliveries; Notes for deliveries; 3) Fuel accounting and balance; 4) Formalities (export and import licenses, customs etc.). Fuel cost: 1) Prices; 2) Fuel cost calculations for comparison of bids and cost forecast. (orig.) [de

  12. 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

  13. 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)

  14. Critical review of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Kuster, N.

    1996-01-01

    Transmutation of long-lived radionuclides is considered as an alternative to the in-depth disposal of spent nuclear fuel, in particular, on the final stage of the nuclear fuel cycle. The majority of conclusions is the result of the common work of the Karlsruhe FZK and the Commissariat on nuclear energy of France (CEA)

  15. Salzburg - International conference on nuclear power and its fuel cycle

    International Nuclear Information System (INIS)

    1977-01-01

    The city of Salzburg, on the banks of the Salzach River, is dominated by the Hohensalzburg Castle, the fortress of the Archbishops that ruled the region. The Old Town is architecturally of a single style, the baroque. Its picturesque streets with their wrought iron signs and the spacious squares with sculptured fountains have charmed countless visitors. Salzburg is also a popular site for international meetings. The Festspielhaus and the Kongresshaus will be the venue of the International Conference on Nuclear Power and Its Fuel Cycle. Some 2000 participants are expected to attend and 348 papers are scheduled for this major conference sponsored by the International Atomic Energy Agency. The Plenary Sessions will be held in the auditorium of the Festspielhaus, and the technical sessions and round-table discussions in the Kongresshaus. The Conference will open on 2 May with the first of five plenary sessions on world energy supply and demand and the future of nuclear power. Other topics to be covered include: supply of nuclear fuel and fuel cycle services, radioactivity management, nuclear safety, nuclear power and public opinion, safeguarding of nuclear materials, and nuclear power prospects in developing countries. Eight round-table discussions will take place during the Conference. These discussions will centre on the role of nuclear power in future energy supply, transfer of nuclear technology to developing countries, management of radioactivity and radioactive wastes, standardized safety reviews of exported nuclear power plants, and the need for integrated nuclear fuel cycle planning at the national and international levels. Special evening lectures by eminent nuclear scientists are also being planned. In addition, tours and group excursions for those attending the Conference are being organized. The Proceedings of the Conference will be published in eight volumes by the IAEA. (author)

  16. 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.)

  17. Fuel optimization of Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Liao Zejun; Li Zhuoqun; Kong Deping; Xue Xincai; Wang Shiwei

    2010-01-01

    Based on the design practice of the fuel replacement of Qin Shan nuclear power plant, this document effectively analyzes the shortcomings of current replacement design of Qin Shan. To address these shortcomings, this document successfully implements the 300 MW fuel optimization program from fuel replacement. fuel improvement and experimentation ,and achieves great economic results. (authors)

  18. Transport and reprocessing of irradiated nuclear fuel

    International Nuclear Information System (INIS)

    Lenail, B.

    1981-01-01

    This contribution deals with transport and packaging of oxide fuel from and to the Cogema reprocessing plant at La Hague (France). After a general discussion of nuclear fuel and the fuel cycle, the main aspects of transport and reprocessing of oxide fuel are analysed. (Auth.)

  19. Nuclear fuel pellet loading machine

    International Nuclear Information System (INIS)

    Kee, R.W.; Denero, J.V.

    1975-01-01

    An apparatus for loading nuclear fuel pellets on trays for transfer in a system is described. A conveyor supplies pellets from a source to a loading station. When the pellets reach a predetermined position at the loading station, a manual or automatically operated arm pushes the pellets into slots on a tray and this process is repeated until pellet sensing switches detect that the tray is full. Thereupon, the tray is lowered onto a belt or other type conveyor and transferred to other apparatus in the system, such as a furnace for sintering, and in some cases, reduction of UO 2 . 2 to UO 2 . The pellets are retained on the tray and subsequently loaded directly into fuel rods to be used in the reactor core. (auth)

  20. IRAK2 directs stimulus-dependent nuclear export of inflammatory mRNAs.

    Science.gov (United States)

    Zhou, Hao; Bulek, Katarzyna; Li, Xiao; Herjan, Tomasz; Yu, Minjia; Qian, Wen; Wang, Han; Zhou, Gao; Chen, Xing; Yang, Hui; Hong, Lingzi; Zhao, Junjie; Qin, Luke; Fukuda, Koichi; Flotho, Annette; Gao, Ji; Dongre, Ashok; Carman, Julie A; Kang, Zizhen; Su, Bing; Kern, Timothy S; Smith, Jonathan D; Hamilton, Thomas A; Melchior, Frauke; Fox, Paul L; Li, Xiaoxia

    2017-10-09

    Expression of inflammatory genes is determined in part by post-transcriptional regulation of mRNA metabolism but how stimulus- and transcript-dependent nuclear export influence is poorly understood. Here, we report a novel pathway in which LPS/TLR4 engagement promotes nuclear localization of IRAK2 to facilitate nuclear export of a specific subset of inflammation-related mRNAs for translation in murine macrophages. IRAK2 kinase activity is required for LPS-induced RanBP2-mediated IRAK2 sumoylation and subsequent nuclear translocation. Array analysis showed that an SRSF1-binding motif is enriched in mRNAs dependent on IRAK2 for nuclear export. Nuclear IRAK2 phosphorylates SRSF1 to reduce its binding to target mRNAs, which promotes the RNA binding of the nuclear export adaptor ALYREF and nuclear export receptor Nxf1 loading for the export of the mRNAs. In summary, LPS activates a nuclear function of IRAK2 that facilitates the assembly of nuclear export machinery to export selected inflammatory mRNAs to the cytoplasm for translation.

  1. Radioecology of nuclear fuel cycles

    International Nuclear Information System (INIS)

    Schreckhise, R.G.; Cadwell, L.L.; Emery, R.M.

    1981-01-01

    This study provides information to help assess the environmental impacts and certain potential human hazards associated with nuclear fuel cycles. A data base is being developed to define and quantify biological transport routes which will permit credible predictions and assessment of routine and potential large-scale releases of radionuclides and other toxic materials. Information obtained from existing storage and disposal sites will provide a meaningful radioecological perspective with which to improve the effectiveness of waste management practices. This paper focuses on terrestrial and aquatic radioecology of waste management areas and biotic transport parameters

  2. Getter for nuclear fuel elements

    International Nuclear Information System (INIS)

    Ross, W.T.; Williamson, H.E.

    1976-01-01

    A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has disposed therein an improved getter capable of gettering reactive gases including a source of hydrogen. The getter comprises a composite with a substrate having thereon a coating capable of gettering reactive gases. The substrate has a greater coefficient of thermal expansion than does the coating, and over a period of time at reactor operating temperatures any protective film on the coating is fractured at various places and fresh portions of the coating are exposed to getter reactive gases. With further passage of time at reactor operating temperatures a fracture of the protective film on the coating will grow into a crack in the coating exposing further portions of the coating capable of gettering reactive gases. 13 claims, 5 drawing figures

  3. Getter for nuclear fuel elements

    International Nuclear Information System (INIS)

    Ross, W.T.; Williamson, H.E.

    1976-01-01

    A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has disposed therein an improved getter capable of gettering reactive gases including a source of hydrogen. The getter comprises a composite with a substrate having thereon a coating capable of gettering reactive gases. The substrate has a greater coefficient of thermal expansion than does the coating, and over a period of time at reactor operating temperatures any protective film on the coating is fractured at various places and fresh portions of the coating are exposed to getter reactive gases. With further passage of time at reactor operating temperatures a fracture of the protective film on the coating will grow into a crack in the coating exposing further portions of the coating capable of gettering reactive gases

  4. 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

  5. MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION

    Directory of Open Access Journals (Sweden)

    Miroslav Cech

    2016-12-01

    Full Text Available This paper describes materials made of zirconium-based alloys used for nuclear fuel cladding fabrication. It is focused on corrosion problems their theoretical description and modeling in nuclear engineering.

  6. Assessing mRNA nuclear export in mammalian cells by microinjection.

    Science.gov (United States)

    Lee, Eliza S; Palazzo, Alexander F

    2017-08-15

    The nuclear export of mRNAs is an important yet little understood part of eukaryotic gene expression. One of the easiest methods for monitoring mRNA export in mammalian tissue culture cells is through the microinjection of DNA plasmids into the nucleus and monitoring the distribution of the transcribed product over time. Here we describe how to setup a microscope equipped with a micromanipulator used in cell microinjections, and we explain how to perform a nuclear mRNA export assay and obtain the nuclear export rate for any given mRNA. Copyright © 2017 Elsevier Inc. All rights reserved.

  7. 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

  8. OECD - HRP 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.

  9. 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.

  10. OECD - HRP Summer School on Nuclear Fuel

    International Nuclear Information System (INIS)

    2000-01-01

    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

  11. Nuclear export policy and regulation for non-proliferation: Federal Republic of Germany

    International Nuclear Information System (INIS)

    Boulanger, Werner.

    1978-01-01

    The nuclear export policy of the Federal Republic of Germany complies with the principle of non-proliferation of nuclear weapons. Already in 1967 the Federal Government stated in a Peace Note that no export was authorised to countries (outside Euratom) which did not comply with the IAEA Safeguards. In the bilateral agreement the Federal Republic signed with Brasil in 1975, emphasis was put on international safeguards and the control exercised on exported materials to avoid any diversion for military purposes. (NEA) [fr

  12. 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

  13. Export regulation

    International Nuclear Information System (INIS)

    Gates, D.J.

    1978-01-01

    Australia is a major uranium supplier. Uranium is exported under conditions laid down to avoid any nuclear proliferation. On 24 May 1977 the Prime Minister had stated the main elements of Australian policy: the strengthening of the system of international safeguards and the selection of importing countries. (Non-nuclear weapon states must be Contracting Parties to the NPT. Nuclear weapon states must undertake not to use Australian uranium for this purpose). Australia retains property of the uranium up to the UF 6 stage (uranium hexafluoride) in the fuel cycle; it reserves the right to stop any export if the importing country no longer complies with AIEA Safeguards. Any transfer to a third country, any irradiated fuel reprocessing, requires Australia's prior agreement. Finally, importing countries must satisfy physical protection conditions. (NEA) [fr

  14. Inhibition of CRM1-mediated nuclear export of influenza A nucleoprotein and nuclear export protein as a novel target for antiviral drug development.

    Science.gov (United States)

    Chutiwitoonchai, Nopporn; Mano, Takafumi; Kakisaka, Michinori; Sato, Hirotaka; Kondoh, Yasumitsu; Osada, Hiroyuki; Kotani, Osamu; Yokoyama, Masaru; Sato, Hironori; Aida, Yoko

    2017-07-01

    An anti-influenza compound, DP2392-E10 based on inhibition of the nuclear export function of the viral nucleoprotein-nuclear export signal 3 (NP-NES3) domain was successfully identified by our previous high-throughput screening system. Here, we demonstrated that DP2392-E10 exerts its antiviral effect by inhibiting replication of a broad range of influenza A subtypes. In regard to the molecular mechanism, we revealed that DP2392-E10 inhibits nuclear export of both viral NP and nuclear export protein (NEP). More specifically, in vitro pull-down assays revealed that DP2392-E10 directly binds cellular CRM1, which mediates nuclear export of NP and NEP. In silico docking suggested that DP2392-E10 binds at a region close to the HEAT9 and HEAT10 domains of CRM1. Together, these results indicate that the CRM1-mediated nuclear export function of influenza virus represents a new potential target for antiviral drug development, and also provide a core structure for a novel class of inhibitors that target this function. Copyright © 2017 Elsevier Inc. All rights reserved.

  15. Development of a nuclear fuel cycle transparency framework

    International Nuclear Information System (INIS)

    Love, Tracia L.

    2005-01-01

    Nuclear fuel cycle transparency can be defined as a confidence building approach among political entities to ensure civilian nuclear facilities are not being used for the development of nuclear weapons. Transparency concepts facilitate the transfer of nuclear technology, as the current international political climate indicates a need for increased methods of assuring non-proliferation. This research develops a system which will augment current non-proliferation assessment activities undertaken by U.S. and international regulatory agencies. It will support the export of nuclear technologies, as well as the design and construction of Gen. IV energy systems. Additionally, the framework developed by this research will provide feedback to cooperating parties, thus ensuring full transparency of a nuclear fuel cycle. As fuel handling activities become increasingly automated, proliferation or diversion potential of nuclear material still needs to be assessed. However, with increased automation, there exists a vast amount of process data to be monitored. By designing a system that monitors process data continuously, and compares this data to declared process information and plant designs, a faster and more efficient assessment of proliferation risk can be made. Figure 1 provides an illustration of the transparency framework that has been developed. As shown in the figure, real-time process data is collected at the fuel cycle facility; a reactor, a fabrication plant, or a recycle facility, etc. Data is sent to the monitoring organization and is assessed for proliferation risk. Analysis and recommendations are made to cooperating parties, and feedback is provided to the facility. The analysis of proliferation risk is based on the following factors: (1) Material attractiveness: the quantification of factors relevant to the proliferation risk of a certain material (e.g., highly enriched Pu-239 is more attractive than that of lower enrichment) (2) The static (baseline) risk: the

  16. 10 CFR 110.26 - General license for the export of nuclear reactor components.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false General license for the export of nuclear reactor components. 110.26 Section 110.26 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF... Denmark Finland France Germany Greece Indonesia Ireland Italy Japan Latvia Lithuania Luxembourg...

  17. Nuclear fuel powder transfer device

    International Nuclear Information System (INIS)

    Komono, Akira

    1998-01-01

    A pair of parallel rails are laid between a receiving portion to a molding portion of a nuclear fuel powder transfer device. The rails are disposed to the upper portion of a plurality of parallel support columns at the same height. A powder container is disposed while being tilted in the inside of the vessel main body of a transfer device, and rotational shafts equipped with wheels are secured to right and left external walls. A nuclear powder to be mixed, together with additives, is supplied to the powder container of the transfer device. The transfer device engaged with the rails on the receiving side is transferred toward the molding portion. The wheels are rotated along the rails, and the rotational shafts, the vessel main body and the powder container are rotated. The nuclear powder in the tilted powder container disposed is rotated right and left and up and down by the rotation, and the powder is mixed satisfactory when it reaches the molding portion. (I.N.)

  18. A study on establishing export system of nuclear related equipments to the IAEA

    Energy Technology Data Exchange (ETDEWEB)

    Song, Ki Dong; Lee, Man Ki; Moon, Ki Hwan; Kim, Seung Soo; Lim, Chae Young; Kim, Hwa Sup; Min, Tae Sik [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-04-01

    In spite of the advanced status in the international nuclear society, exports of domestic nuclear industries to procurement market of the international organizations has been negligible. This study briefly explained the role and the structure of the IAEA. Then, this study surveyed the size of procurement market, major procurement items, and procurement process. This study also gave an export example to the IAEA from Korea Atomic Energy Research Institute for the ease of understanding the procurement process. Based on these surveys and analysis, this study established the goal and strategy for exports of nuclear equipments to the IAEA. Besides, this study surveyed domestic nuclear industries that have potential to export their products to the IAEA. Then, Korea Atomic Energy Research Institute, by a cooperation with Korea Atomic Industrial Forum Inc., held workshop on 'export of nuclear equipments to IAEA' in May 2001 for them. 4 refs., 1 fig., 10 tabs. (Author)

  19. Monitoring arrangement for vented nuclear fuel elements

    Science.gov (United States)

    Campana, Robert J.

    1981-01-01

    In a nuclear fuel reactor core, fuel elements are arranged in a closely packed hexagonal configuration, each fuel element having diametrically opposed vents permitting 180.degree. rotation of the fuel elements to counteract bowing. A grid plate engages the fuel elements and forms passages for communicating sets of three, four or six individual vents with respective monitor lines in order to communicate vented radioactive gases from the fuel elements to suitable monitor means in a manner readily permitting detection of leakage in individual fuel elements.

  20. 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

  1. Nuclide inventory for nuclear fuel waste management

    International Nuclear Information System (INIS)

    Mehta, K.

    1982-09-01

    To assist research projects in the Canadian Nuclear Fuel Waste Management Prgram, a compilation has been made of all the nuclides that are likely to be present in a nuclear fuel waste disposal vault and that are potentially hazardous to man during the post-closure phase. The compilation includes radiologically toxic and chemically toxic nuclides

  2. Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel

    International Nuclear Information System (INIS)

    Mecartnery, Martha; Graeve, Olivia; Patel, Maulik

    2017-01-01

    The goal of this research is to help develop new fuels for higher efficiency, longer lifetimes (higher burn-up) and increased accident tolerance in future nuclear reactors. Multiphase nanocrystalline ceramics will be used in the design of simulated advanced inert matrix nuclear fuel to provide for enhanced plasticity, better radiation tolerance, and improved thermal conductivity

  3. Spent Nuclear Fuel (SNF) Project Execution Plan

    Energy Technology Data Exchange (ETDEWEB)

    LEROY, P.G.

    2000-11-03

    The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities.

  4. Spent Nuclear Fuel (SNF) Project Execution Plan

    International Nuclear Information System (INIS)

    LEROY, P.G.

    2000-01-01

    The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities

  5. Multiphase Nanocrystalline Ceramic Concept for Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Mecartnery, Martha [Univ. of California, Irvine, CA (United States); Graeve, Olivia [Univ. of California, San Diego, CA (United States); Patel, Maulik [Univ. of Liverpool (United Kingdom)

    2017-05-25

    The goal of this research is to help develop new fuels for higher efficiency, longer lifetimes (higher burn-up) and increased accident tolerance in future nuclear reactors. Multiphase nanocrystalline ceramics will be used in the design of simulated advanced inert matrix nuclear fuel to provide for enhanced plasticity, better radiation tolerance, and improved thermal conductivity

  6. 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

  7. 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.

  8. Decision support for selecting exportable nuclear technology using the analytic hierarchy process. A Korean case

    International Nuclear Information System (INIS)

    Lee, Deok Joo; Hwang, Jooho

    2010-01-01

    The Korean government plans to increase strategically focused R and D investment in some promising nuclear technology areas to create export opportunities of technology in a global nuclear market. The purpose of this paper is to present a decision support process for selecting promising nuclear technology with the perspective of exportability by using the AHP based on extensive data gathered from nuclear experts in Korea. In this study, the decision criteria for evaluating the export competitiveness of nuclear technologies were determined, and a hierarchical structure for the decision-making process was systematically developed. Subsequently relative weights of decision criteria were derived using AHP methodology and the export competitiveness of nuclear technology alternatives was quantified to prioritize them. We discuss the implications of our results with a viewpoint toward national nuclear technology policy. (author)

  9. 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

  10. A comparative study on export control systems of nuclear technology in ROK and USA

    International Nuclear Information System (INIS)

    Tae, Jae Woong; Shin, Dong Hoon

    2013-01-01

    Perfect removal of transferred technology is impossible because it is impossible to find all copies of technologies such as files and documents. International community concerns about Terrorists' acquirement of nuclear technologies related to nuclear reactors, enrichment and reprocessing Facilities and heavy water production facilities, which can be used for production of nuclear weapons. Non-state actors as well as concerning countries have tried to possess nuclear technology for developing nuclear weapons. Non-state actors' activities threaten global nuclear security. Korea exported four nuclear power plants to UAE and a research reactor to Jordan. Non-state actors may try to procure nuclear equipment and technology from Korean nuclear industries. Therefore, the export control system should be enhanced for national nuclear security and safety. In this study, the export control system of Korea and the United States were compared concerning to nuclear technology. In summary, controlled activities related to nuclear technology are treated more variously and more diverse activities are controlled in the United States than In Korea. Catch-all control will lose its effectiveness without this. Related to the control of ITT (Intangible Technology Transfer), Korea and the United States are trying to amend the export control regulation. Both of them are trying to control intangible technology transfers effectively. Revised Foreign Trade Act in Korea is expected to introduce a more rigorous system of nuclear technology controls. It focuses on nationality rather than residence. The revised law may face into other problems such as dual nationals like as the United States. However, this satisfies legislative requirements for control of a deemed export. The revised law will enter into force in 2014. Accurate meanings of technology and export will be defined soon in the enforcement decree and the public notice before 2014. However, it is hard to revise the definition of export

  11. The safety of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1993-01-01

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

  12. Storage and handling of nuclear fuel

    International Nuclear Information System (INIS)

    2006-01-01

    This Guide defines the safety requirements and the control procedure for the storage and handling of fresh and spent fuel of a nuclear power plant. The control procedure applies to all those structures and components of the storage and handling systems that may affect fuel safety. The Guide does not deal with the control of any process-related technical systems (e.g. cooling and purification systems), including their structures and components, connected with fuel storage. With regard to the storage of spent fuel, this Guide only deals with storage in a water pool. Guide YVL6.1 describes the regulatory control of nuclear fuel by the Radiation and Nuclear Safety Authority, Finland (STUK) in general. The detailed requirements for fuel control are given in Guide YVL6.3. The regulatory control of nuclear power plants by STUK on the whole is discussed in Guide YVL1.1

  13. Nuclear fuels for very high temperature applications

    International Nuclear Information System (INIS)

    Lundberg, L.B.; Hobbins, R.R.

    1992-01-01

    The success of the development of nuclear thermal propulsion devices and thermionic space nuclear power generation systems depends on the successful utilization of nuclear fuel materials at temperatures in the range 2000 to 3500 K. Problems associated with the utilization of uranium bearing fuel materials at these very high temperatures while maintaining them in the solid state for the required operating times are addressed. The critical issues addressed include evaporation, melting, reactor neutron spectrum, high temperature chemical stability, fabrication, fission induced swelling, fission product release, high temperature creep, thermal shock resistance, and fuel density, both mass and fissile atom. Candidate fuel materials for this temperature range are based on UO 2 or uranium carbides. Evaporation suppression, such as a sealed cladding, is required for either fuel base. Nuclear performance data needed for design are sparse for all candidate fuel forms in this temperature range, especially at the higher temperatures

  14. FERC perspectives on nuclear fuel accounting issues

    International Nuclear Information System (INIS)

    McDanal, M.W.

    1986-01-01

    The purpose of the presentation is to discuss the treatment of nuclear fuel and problems that have evolved in industry practices in accounting for fuel. For some time, revisions to the Uniform System of Accounts have been considered with regard to the nuclear fuel accounts. A number of controversial issues have been encountered on audits, including treatment of nuclear fuel enrichment charges, costs associated with delays in enrichment services, the treatment and recognition of fuel inventories in excess of current or projected needs, and investments in and advances to mining and milling companies for future deliveries of nuclear fuel materials. In an effort to remedy the problems and to adapt the Federal Energy Regulatory Commission's accounting to more easily provide for or point out classifications for each problem area, staff is reevaluating the need for contemplated amendments to the Uniform System of Accounts

  15. The nuclear export protein of H5N1 influenza A viruses recruits Matrix 1 (M1) protein to the viral ribonucleoprotein to mediate nuclear export.

    Science.gov (United States)

    Brunotte, Linda; Flies, Joe; Bolte, Hardin; Reuther, Peter; Vreede, Frank; Schwemmle, Martin

    2014-07-18

    In influenza A virus-infected cells, replication and transcription of the viral genome occurs in the nucleus. To be packaged into viral particles at the plasma membrane, encapsidated viral genomes must be exported from the nucleus. Intriguingly, the nuclear export protein (NEP) is involved in both processes. Although NEP stimulates viral RNA synthesis by binding to the viral polymerase, its function during nuclear export implicates interaction with viral ribonucleoprotein (vRNP)-associated M1. The observation that both interactions are mediated by the C-terminal moiety of NEP raised the question whether these two features of NEP are linked functionally. Here we provide evidence that the interaction between M1 and the vRNP depends on the NEP C terminus and its polymerase activity-enhancing property for the nuclear export of vRNPs. This suggests that these features of NEP are linked functionally. Furthermore, our data suggest that the N-terminal domain of NEP interferes with the stability of the vRNP-M1-NEP nuclear export complex, probably mediated by its highly flexible intramolecular interaction with the NEP C terminus. On the basis of our data, we propose a new model for the assembly of the nuclear export complex of Influenza A vRNPs. © 2014 by The American Society for Biochemistry and Molecular Biology, Inc.

  16. Fuel assemblies for use in nuclear reactors

    International Nuclear Information System (INIS)

    Schluderberg, D.C.

    1981-01-01

    A fuel assembly for use in pressurized water cooled nuclear fast breeder reactors is described in which moderator to fuel ratios, conducive to a high Pu-U-D 2 O reactor breeding ratio, are obtained whilst at the same time ensuring accurate spacing of fuel pins without the parasitic losses associated with the use of spacer grids. (U.K.)

  17. Nuclear fuel pellet manufacturing method

    International Nuclear Information System (INIS)

    Matsuda, Tetsushi.

    1995-01-01

    An uranium oxide powder is compression-molded to form a compressed powder product, and the compressed powder product is sintered to form a ceramic nuclear fuel pellet. In this case, the uranium oxide powder to be supplied to a press hole for compression molding is exposed to an atmosphere of one of vapors of benzene, hexane, acetone, acetic acid, ethanol or water, or an atmosphere of a vapor mixture of several kinds of them. Thereafter, uranium oxide powder is compression molded in the same vapor atmosphere. Since the vapor atmosphere is used as an aid for a molding adjuvant or a substitute thereof, lowering of pellet density due to residual molding adjuvant can be prevented. In addition, the vapor atmosphere is penetrated uniformly between the uranium oxide powder to suppress density fluctuation of the compressed powder material thereby enabling to unify the shrinking rate. (I.N.)

  18. Murine Leukemia Virus Uses TREX Components for Efficient Nuclear Export of Unspliced Viral Transcripts

    Directory of Open Access Journals (Sweden)

    Toshie Sakuma

    2014-03-01

    Full Text Available Previously we reported that nuclear export of both unspliced and spliced murine leukemia virus (MLV transcripts depends on the nuclear export factor (NXF1 pathway. Although the mRNA export complex TREX, which contains Aly/REF, UAP56, and the THO complex, is involved in the NXF1-mediated nuclear export of cellular mRNAs, its contribution to the export of MLV mRNA transcripts remains poorly understood. Here, we studied the involvement of TREX components in the export of MLV transcripts. Depletion of UAP56, but not Aly/REF, reduced the level of both unspliced and spliced viral transcripts in the cytoplasm. Interestingly, depletion of THO components, including THOC5 and THOC7, affected only unspliced viral transcripts in the cytoplasm. Moreover, the RNA immunoprecipitation assay showed that only the unspliced viral transcript interacted with THOC5. These results imply that MLV requires UAP56, THOC5 and THOC7, in addition to NXF1, for nuclear export of viral transcripts. Given that naturally intronless mRNAs, but not bulk mRNAs, require THOC5 for nuclear export, it is plausible that THOC5 plays a key role in the export of unspliced MLV transcripts.

  19. Overview of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Knief, R.A.

    1978-01-01

    The nuclear fuel cycle is substantially more complicated than the energy production cycles of conventional fuels because of the very low abundance of uranium 235, the presence of radioactivity, the potential for producing fissile nuclides from irradiation, and the risk that fissile materials will be used for nuclear weapons. These factors add enrichment, recycling, spent fuel storage, and safeguards to the cycle, besides making the conventional steps of exploration, mining, processing, use, waste disposal, and transportation more difficult

  20. NUFCOS - nuclear fuel cycle optimization system

    International Nuclear Information System (INIS)

    Kaikkonen, H.; Salo, J.-P.; Vieno, T.; Vira, J.

    1979-05-01

    NUFCOS is a multigoal nuclear fuel cycle optimization code with an arbitrary number of decision objectives. The multigoal decision-making is based on the evolving techniques of fuzzy optimization. After a short description of the fuel cycle model and the calculation methods this report gives the input instructions in the case of three optimization criteria: minimization of fuel cycle costs, economical risk and nuclear weapons proliferation risk. (author)

  1. Financial aspects of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Lurf, G.

    1975-01-01

    A nuclear power plant has a forward supply of several years as a consequence of the long processing time of the uranium from mining to delivery of fabricated fuel elements and of the long insertion time in the reactor. This leads to a considerable capital requirement although the specific fuel costs for nuclear fuel are considerably lower then for a conventional power plant and present only 15% of the total generating costs. (orig./RW) [de

  2. Russian exports of emission permits under the Kyoto Protocol: The interplay with non-competitive fuel markets

    International Nuclear Information System (INIS)

    Hagem, Cathrine; Maestad, Ottar

    2006-01-01

    The paper analyses optimal strategies for a country that has market power in an international market for emission permits at the same time as a domestic fuel producer participates in a non-competitive fuel export market. In particular, the effects of coordinating fuel and permit exports are explored. We show that such coordination may either increase or reduce the optimal mark-up on permits, depending on the degree of substitution between alternative fuels. When the fuel market is oligopolistic, coordination of permit and fuel exports may lead to a strategic disadvantage in the fuel market, which makes such coordination unprofitable. However, illustrative numerical simulations suggest that Russia will benefit from coordinating its permit exports with its oil and gas exports during the Kyoto commitment period. (author)

  3. A study on the establishment of national nuclear foreign policy with reference to nuclear export control system, strategy toward IAEA, and NPT review conferences

    International Nuclear Information System (INIS)

    Choi, Young Myung; Nam, Jang Soo; Lee, Han Myung

    1990-02-01

    The objectives of this study are follows: suggestion for i) our future nuclear development directions, ii) establishment of national export control system, iii) establishment of strategy toward IAEA, and suggestion of our standpoints toward the 4th NPT review conference. This study proposes the following; 1) It is desirable that nuclear power generation strategy is propelled under the premise of economics and proven technology. And international cooperation in connection with the nuclear fuel cycle should be reinforced. 2) It is recommened that nuclear export control system should be government-led. 3) Our country needs to make efforts in increasing the number of Korean staff in the IAEA, and to establish permanent mission which is wholly responsible for the IAEA affairs, and to construct a system which deals with nuclear foregin activities. 4) It is desirable that the basic position of our country toward the 4th NPT review conference should be : i) to urge parties to the NPT to conclude safeguards agreement with IAEA as early as possible, ii) to request nuclear suppliers to mitigate their nuclear technology for peaceful uses to nuclear developing countries, and iii) to urge nuclear weapon states to make further efforts for nuclear disarmament. (author)

  4. 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

  5. Simulated nuclear reactor fuel assembly

    International Nuclear Information System (INIS)

    Berta, V.T.

    1993-01-01

    An apparatus for electrically simulating a nuclear reactor fuel assembly. It includes a heater assembly having a top end and a bottom end and a plurality of concentric heater tubes having electrical circuitry connected to a power source, and radially spaced from each other. An outer target tube and an inner target tube is concentric with the heater tubes and with each other, and the outer target tube surrounds and is radially spaced from the heater tubes. The inner target tube is surrounded by and radially spaced from the heater tubes and outer target tube. The top of the assembly is generally open to allow for the electrical power connection to the heater tubes, and the bottom of the assembly includes means for completing the electrical circuitry in the heater tubes to provide electrical resistance heating to simulate the power profile in a nuclear reactor. The embedded conductor elements in each heater tube is split into two halves for a substantial portion of its length and provided with electrical isolation such that each half of the conductor is joined at one end and is not joined at the other end

  6. RanBP3 influences interactions between CRM1 and its nuclear protein export substrates

    OpenAIRE

    Englmeier, Ludwig; Fornerod, Maarten; Bischoff, F. Ralf; Petosa, Carlo; Mattaj, Iain W.; Kutay, Ulrike

    2001-01-01

    We investigated the role of RanBP3, a nuclear member of the Ran-binding protein 1 family, in CRM1-mediated protein export in higher eukaryotes. RanBP3 interacts directly with CRM1 and also forms a trimeric complex with CRM1 and RanGTP. However, RanBP3 does not bind to CRM1 like an export substrate. Instead, it can stabilize CRM1–export substrate interaction. Nuclear RanBP3 stimulates CRM1-dependent protein export in permeabilized cells. These data indicate that RanBP3 functions by a novel mec...

  7. Integration of renewable energies and nuclear power into North African Energy Systems: An analysis of energy import and export effects

    International Nuclear Information System (INIS)

    Supersberger, Nikolaus; Fuehrer, Laura

    2011-01-01

    The North African countries Morocco, Algeria, Tunisia, Libya and Egypt have been and are currently experiencing rapid growth in energy demand. This development confronts their political leaders with the question of how to expand or diversify their countries' generation capacities. In this context, renewable energies and nuclear power constitute options that have rarely been exploited so far in the region. This article analyzes the drawbacks and benefits of both alternatives, with a special focus on import and export dynamics. When attempting to make the strategic decision between renewables and atomic power, North African regional specifics and circumstances have to be taken into account. Hence, in a first step, the article characterizes the energy systems of the North African countries and presents scenarios for their future development. In a second step, it scrutinizes the energy challenges these states face in terms of domestic concerns and foreign affairs. Finally, a case study of Algeria is used to demonstrate how renewable energies, but not nuclear power, are able to respond to North African energy challenges. - Research highlights: → Using nuclear power would require fuel imports over the entire operation time. → Hence, energy exporters (Algeria, Libya) would become dependent on fuel imports. → Renewable energies can make North African countries less fuel import dependent. → Nuclear technologies would have to be imported over the whole life cycle of plants. → Domestic production for renewables technologies could be established after a first phase of technology imports.

  8. Nuclear export of cutaneous HPV8 E7 oncoprotein is mediated by a leucine-rich nuclear export signal via a CRM1 pathway.

    Science.gov (United States)

    Onder, Zeynep; Chang, Vivian; Moroianu, Junona

    2015-01-01

    We recently determined that the nuclear import of cutaneous beta genus HPV8 E7 oncoprotein it is mediated by its zinc-binding domain via direct hydrophobic interactions with the FG nucleoporins Nup62 and Nup153 (Onder and Moroianu, 2014). Here we investigated the nuclear export of HPV8 E7 oncoprotein using confocal microscopy after transfections of HeLa cells with EGFP-8cE7 and mutant plasmids and treatment with Ratjadone A nuclear export inhibitor. We determined that HPV8 E7 contains a leucine-rich nuclear export signal (NES), 76IRTFQELLF84, within its zinc-binding domain that mediates its nuclear export via a CRM1 pathway. We found that HPV8 E7 interacts with CRM1 and that the hydrophobic amino acid residues I76, F79 and L82 of the NES are essential for this interaction and for nuclear export of HPV8 E7 oncoprotein. Copyright © 2014 Elsevier Inc. All rights reserved.

  9. Nuclear safety aspects of exported replicate nuclear power plants and associated problems

    International Nuclear Information System (INIS)

    Kern, H.G.

    1978-01-01

    The standardization of the export nuclear power plant is being pursued with the concept of replication. This concept entails using another exported Nuclear Power Plant (NPP) as the base design and adapting it to a new site. The general ground rule applied to this concept is upgrading the design where necessary and duplicating the design where it is superior. Such continuous improvement will result in a standard export NPP that incorporates design features which will make it essentially acceptable for any suitable site. The advantages of replication are, therefore, boundless. However, the replication mode requires superior design control by the engineer to assure that only improvements alter the base design. With this concept, the replicating engineer is essentially assigned the responsiblity of safeguarding the standard export plant design. He is delegated the task of filtering the design such that only the conservative aspects prevail. Tight control of design changes via properly administered procedures is necessary to assure that no unforeseen compromises are made in designs which have already achieved optimization. Techniques to accomplish successful replication include, among others, the use of PCNs, system cognizant engineers, design verfication review, and the participation of all engineering disciplines in the development of the project schedule. (author)

  10. Fuel assembly for a nuclear reactor

    International Nuclear Information System (INIS)

    Gjertsen, R.K.; Tower, S.N.; Huckestein, E.A.

    1982-01-01

    A fuel assembly for a nuclear reactor comprises a 5x5 array of guide tubes in a generally 20x20 array of fuel elements, the guide tubes being arranged to accommodate either control rods or water displacer rods. The fuel assembly has top and bottom Inconel (Registered Trade Mark) grids and intermediate Zircaloy grids in engagement with the guide tubes and supporting the fuel elements and guide tubes while allowing flow of reactor coolant through the assembly. (author)

  11. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

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

    1984-04-01

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

  12. Fuel element shipping shim for nuclear reactor

    International Nuclear Information System (INIS)

    Gehri, A.

    1975-01-01

    A shim is described for use in the transportation of nuclear reactor fuel assemblies. It comprises a member preferably made of low density polyethylene designed to have three-point contact with the fuel rods of a fuel assembly and being of sufficient flexibility to effectively function as a shock absorber. The shim is designed to self-lock in place when associated with the fuel rods. (Official Gazette)

  13. Development of nuclear fuel cycle technologies

    International Nuclear Information System (INIS)

    Suzuoki, Akira; Matsumoto, Takashi; Suzuki, Kazumichi; Kawamura, Fumio

    1995-01-01

    In the long term plan for atomic energy that the Atomic Energy Commission decided the other day, the necessity of the technical development for establishing full scale fuel cycle for future was emphasized. Hitachi Ltd. has engaged in technical development and facility construction in the fields of uranium enrichment, MOX fuel fabrication, spent fuel reprocessing and so on. In uranium enrichment, it took part in the development of centrifuge process centering around Power Reactor and Nuclear Fuel Development Corporation (PNC), and took its share in the construction of the Rokkasho uranium enrichment plant of Japan Nuclear Fuel Service Co., Ltd. Also it cooperates with Laser Enrichment Technology Research Association. In Mox fuel fabrication, it took part in the construction of the facilities for Monju plutonium fuel production of PNC, for pellet production, fabrication and assembling processes. In spent fuel reprocessing, it cooperated with the technical development of maintenance and repair of Tokai reprocessing plant of PNC, and the construction of spent fuel stores in Rokkasho reprocessing plant is advanced. The centrifuge process and the atomic laser process of uranium enrichment are explained. The high reliability of spent fuel reprocessing plants and the advancement of spent fuel reprocessing process are reported. Hitachi Ltd. Intends to exert efforts for the technical development to establish nuclear fuel cycle which increases the importance hereafter. (K.I.)

  14. Korea nuclear exports: Why did the Koreans win the UAE tender? Will Korea achieve its goal of exporting 80 nuclear reactors by 2030?

    International Nuclear Information System (INIS)

    Berthelemy, Michel; Leveque, Francois

    2011-01-01

    The success of Korea in winning, in December 2009, a USD 18.6 billion nuclear tender in the United Arab Emirates (UAE) has led to a growing interest in the organization and strengths of the Korean nuclear industry. In this paper, we present the main economic and political factors that explain the success of the Korean consortium. In particular, thanks to an active national program of Nuclear Power Plant (NPP) construction, Korea has developed distinct competitive advantages in terms of low cost, high credibility and high performance. At the same time, due to the important barriers to enter into the nuclear export market in the UAE, Korea has had to sacrifice its profit margin and has benefited from a strong political support from its government through export financing. More importantly, Korea's success is also due to its alliance with Westinghouse and the support of the US diplomacy. Subsequently, we show that while Korea has recently experienced setbacks in nuclear tenders, it will most certainly try to win in the short run a second nuclear tender with another aggressive price. In the longer run, Korea could take a growing share of the international market for NPPs. However, the extent to which Korea can achieve its long term export target will depend upon its capacity to finance nuclear export through export credits and upon the development of its alliance with Westinghouse. It is important to note that this paper was written before the Fukushima nuclear disaster. The scale of the human and environmental consequences of this accident are still unknown, and will undoubtedly have short and long term consequences on nuclear safety requirements and public attitude toward nuclear energy, which will most certainly impact the outlooks for nuclear new-builds. (authors)

  15. National Policy on Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Soedyartomo, S.

    1996-01-01

    National policy on nuclear fuel cycle is aimed at attaining the expected condition, i.e. being able to support optimality the national energy policy and other related Government policies taking into account current domestic nuclear fuel cycle condition and the trend of international nuclear fuel cycle development, the national strength, weakness, thread and opportunity in the field of energy. This policy has to be followed by the strategy to accomplish covering the optimization of domestic efforts, cooperation with other countries, and or purchasing licences. These policy and strategy have to be broken down into various nuclear fuel cycle programmes covering basically assesment of the whole cycle, performing research and development of the whole cycle without enrichment and reprocessing being able for weapon, as well as programmes for industrialization of the fuel cycle stepwisery commencing with the middle part of the cycle and ending with the edge of the back-end of the cycle

  16. The Bacterial Flagellar Type III Export Gate Complex Is a Dual Fuel Engine That Can Use Both H+ and Na+ for Flagellar Protein Export.

    Science.gov (United States)

    Minamino, Tohru; Morimoto, Yusuke V; Hara, Noritaka; Aldridge, Phillip D; Namba, Keiichi

    2016-03-01

    The bacterial flagellar type III export apparatus utilizes ATP and proton motive force (PMF) to transport flagellar proteins to the distal end of the growing flagellar structure for self-assembly. The transmembrane export gate complex is a H+-protein antiporter, of which activity is greatly augmented by an associated cytoplasmic ATPase complex. Here, we report that the export gate complex can use sodium motive force (SMF) in addition to PMF across the cytoplasmic membrane to drive protein export. Protein export was considerably reduced in the absence of the ATPase complex and a pH gradient across the membrane, but Na+ increased it dramatically. Phenamil, a blocker of Na+ translocation, inhibited protein export. Overexpression of FlhA increased the intracellular Na+ concentration in the presence of 100 mM NaCl but not in its absence, suggesting that FlhA acts as a Na+ channel. In wild-type cells, however, neither Na+ nor phenamil affected protein export, indicating that the Na+ channel activity of FlhA is suppressed by the ATPase complex. We propose that the export gate by itself is a dual fuel engine that uses both PMF and SMF for protein export and that the ATPase complex switches this dual fuel engine into a PMF-driven export machinery to become much more robust against environmental changes in external pH and Na+ concentration.

  17. 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.)

  18. Regulatory viewpoint on nuclear fuel quality assurance

    International Nuclear Information System (INIS)

    Tripp, L.E.

    1976-01-01

    Considerations of the importance of fuel quality and performance to nuclear safety, ''as low reasonably achievable'' release of radioactive materials in reactor effluents, and past fuel performance problems demonstrate the need for strong regulatory input, review and inspection of nuclear fuel quality assurance programs at all levels. Such a regulatory program is being applied in the United States of America by the US Nuclear Regulatory Commission. Quality assurance requirements are contained within government regulations. Guidance on acceptable methods of implementing portions of the quality assurance program is contained within Regulatory Guides and other NRC documents. Fuel supplier quality assurance program descriptions are reviewed as a part of the reactor licensing process. Inspections of reactor licensee control of their fuel vendors as well as direct inspections of fuel vendor quality assurance programs are conducted on a regularly scheduled basis. (author)

  19. Nuclear fuel elements having a composite cladding

    Science.gov (United States)

    Gordon, Gerald M.; Cowan, II, Robert L.; Davies, John H.

    1983-09-20

    An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel element has a composite cladding of an outer portion forming a substrate having on the inside surface a metal layer selected from the group consisting of copper, nickel, iron and alloys of the foregoing with a gap between the composite cladding and the core of nuclear fuel. The nuclear fuel element comprises a container of the elongated composite cladding, 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, an enclosure integrally secured and sealed at each end of said container and a nuclear fuel material retaining means positioned in the cavity. The metal layer of the composite cladding prevents perforations or failures in the cladding substrate from stress corrosion cracking or from fuel pellet-cladding interaction or both. The substrate of the composite cladding is selected from conventional cladding materials and preferably is a zirconium alloy.

  20. 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

  1. The management strategy of spent nuclear fuel

    International Nuclear Information System (INIS)

    Bandi Parapak; Siti Alimah

    2010-01-01

    The assessment of management strategy of spent nuclear fuel has been carried out. Spent nuclear fuel is one of the by-products of nuclear power plant. The technical operations related to the management of spent fuel discharged from reactors are called the back-end fuel cycle. It can be largely divided into three option s : the once-through cycle, the closed cycle and the so-called ‟wait and see” policy. Whatever strategy is selected for the back-end of the nuclear fuel cycle, Away-from-Reactor (AFR) storage facilities has to be constructed. For the once through cycle, the entire content of spent fuel is considered as waste, and is subject to be disposed of into a deep underground repository. In the closed cycle, however, can be divided into: (1) uranium and plutonium are recovered from spent fuel by reprocessing and recycled to manufacture mixed oxide (MOX) fuel rods, (2) waste transmutation in accelerator-driven subcritical reactors, (3) DUPIC (Direct Use of Spent PWR Fuel In CANDU) concept. In wait and see policy, which means first storing the spent fuel and deciding at a later stage on reprocessing or disposal. (author)

  2. Nuclear fuel transport and particularly spent fuel transport

    International Nuclear Information System (INIS)

    Lenail, B.

    1986-01-01

    Nuclear material transport is an essential activity for COGEMA linking the different steps of the fuel cycle transport systems have to be safe and reliable. Spent fuel transport is more particularly examined in this paper because the development of reprocessing plant. Industrial, techmical and economical aspects are reviewed [fr

  3. CONSTRUCTION OF NUCLEAR FUEL ELEMENTS

    Science.gov (United States)

    Weems, S.J.

    1963-09-24

    >A rib arrangement and an end construction for nuclearfuel elements laid end to end in a coolant tube are described. The rib arrangement is such that each fuel element, when separated from other fuel elements, fits loosely in the coolant tube and so can easily be inserted or withdrawn from the tube. The end construction of the fuel elements is such that the fuel elements when assembled end to end are keyed against relative rotation, and the ribs of each fuel element cooperate with the ribs of the adjacent fuel elements to give the assembled fuel elements a tight fit with the coolant tube. (AEC)

  4. Identification of a putative nuclear export signal motif in human NANOG homeobox domain

    International Nuclear Information System (INIS)

    Park, Sung-Won; Do, Hyun-Jin; Huh, Sun-Hyung; Sung, Boreum; Uhm, Sang-Jun; Song, Hyuk; Kim, Nam-Hyung; Kim, Jae-Hwan

    2012-01-01

    Highlights: ► We found the putative nuclear export signal motif within human NANOG homeodomain. ► Leucine-rich residues are important for human NANOG homeodomain nuclear export. ► CRM1-specific inhibitor LMB blocked the potent human NANOG NES-mediated nuclear export. -- Abstract: NANOG is a homeobox-containing transcription factor that plays an important role in pluripotent stem cells and tumorigenic cells. To understand how nuclear localization of human NANOG is regulated, the NANOG sequence was examined and a leucine-rich nuclear export signal (NES) motif ( 125 MQELSNILNL 134 ) was found in the homeodomain (HD). To functionally validate the putative NES motif, deletion and site-directed mutants were fused to an EGFP expression vector and transfected into COS-7 cells, and the localization of the proteins was examined. While hNANOG HD exclusively localized to the nucleus, a mutant with both NLSs deleted and only the putative NES motif contained (hNANOG HD-ΔNLSs) was predominantly cytoplasmic, as observed by nucleo/cytoplasmic fractionation and Western blot analysis as well as confocal microscopy. Furthermore, site-directed mutagenesis of the putative NES motif in a partial hNANOG HD only containing either one of the two NLS motifs led to localization in the nucleus, suggesting that the NES motif may play a functional role in nuclear export. Furthermore, CRM1-specific nuclear export inhibitor LMB blocked the hNANOG potent NES-mediated export, suggesting that the leucine-rich motif may function in CRM1-mediated nuclear export of hNANOG. Collectively, a NES motif is present in the hNANOG HD and may be functionally involved in CRM1-mediated nuclear export pathway.

  5. Inner nuclear envelope protein SUN1 plays a prominent role in mammalian mRNA export.

    Science.gov (United States)

    Li, Ping; Noegel, Angelika A

    2015-11-16

    Nuclear export of messenger ribonucleoproteins (mRNPs) through the nuclear pore complex (NPC) can be roughly classified into two forms: bulk and specific export, involving an nuclear RNA export factor 1 (NXF1)-dependent pathway and chromosome region maintenance 1 (CRM1)-dependent pathway, respectively. SUN proteins constitute the inner nuclear envelope component of the l I: nker of N: ucleoskeleton and C: ytoskeleton (LINC) complex. Here, we show that mammalian cells require SUN1 for efficient nuclear mRNP export. The results indicate that both SUN1 and SUN2 interact with heterogeneous nuclear ribonucleoprotein (hnRNP) F/H and hnRNP K/J. SUN1 depletion inhibits the mRNP export, with accumulations of both hnRNPs and poly(A)+RNA in the nucleus. Leptomycin B treatment indicates that SUN1 functions in mammalian mRNA export involving the NXF1-dependent pathway. SUN1 mediates mRNA export through its association with mRNP complexes via a direct interaction with NXF1. Additionally, SUN1 associates with the NPC through a direct interaction with Nup153, a nuclear pore component involved in mRNA export. Taken together, our results reveal that the inner nuclear envelope protein SUN1 has additional functions aside from being a central component of the LINC complex and that it is an integral component of the mammalian mRNA export pathway suggesting a model whereby SUN1 recruits NXF1-containing mRNP onto the nuclear envelope and hands it over to Nup153. © The Author(s) 2015. Published by Oxford University Press on behalf of Nucleic Acids Research.

  6. Fuel assembly for a nuclear reactor

    International Nuclear Information System (INIS)

    Gjertsen, R.K.

    1982-01-01

    A fuel assembly in a nuclear reactor comprises a locking mechanism that is capable of locking the fuel assembly to the core plate of a nuclear reactor to prevent inadvertent movement of the fuel assembly. The locking mechanism comprises a ratchet mechanism 108 that allows the fuel assembly to be easily locked to the core plate but prevents unlocking except when the ratchet is disengaged. The ratchet mechanism is coupled to the locking mechanism by a rotatable guide tube for a control rod or water displacer rod. (author)

  7. Annotated Bibliography for Drying Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Rebecca E. Smith

    2011-09-01

    Internationally, the nuclear industry is represented by both commercial utilities and research institutions. Over the past two decades many of these entities have had to relocate inventories of spent nuclear fuel from underwater storage to dry storage. These efforts were primarily prompted by two factors: insufficient storage capacity (potentially precipitated by an open-ended nuclear fuel cycle) or deteriorating quality of existing underwater facilities. The intent of developing this bibliography is to assess what issues associated with fuel drying have been identified, to consider where concerns have been satisfactorily addressed, and to recommend where additional research would offer the most value to the commercial industry and the U. S. Department of Energy.

  8. International Nuclear Fuel Cycle Fact Book

    Energy Technology Data Exchange (ETDEWEB)

    Leigh, I.W.; Patridge, M.D.

    1991-05-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECN/NEA activities reports; not reflect any one single source but frequently represent a consolidation/combination of information.

  9. Globalisation of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Rougeau, J.-P.; Durret, L.-F.

    1995-01-01

    Three main features of the globalisation of the nuclear fuel cycle are identified and discussed. The first is an increase in the scale of the nuclear fuel cycle materials and services markets in the past 20 years. This has been accompanied by a growth in the sophistication of the fuel cycle. Secondly, the nuclear industry is now more vulnerable to outside pressures; it is no longer possible to make strategic decisions on the industry within a country solely on national considerations. Thirdly, there are changes in the decision-making process at the political, regulatory, operational and industrial level which are the consequence of global factors. (UK)

  10. Globalisation of the nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Rougeau, J.-P.; Durret, L.-F.

    1995-12-31

    Three main features of the globalisation of the nuclear fuel cycle are identified and discussed. The first is an increase in the scale of the nuclear fuel cycle materials and services markets in the past 20 years. This has been accompanied by a growth in the sophistication of the fuel cycle. Secondly, the nuclear industry is now more vulnerable to outside pressures; it is no longer possible to make strategic decisions on the industry within a country solely on national considerations. Thirdly, there are changes in the decision-making process at the political, regulatory, operational and industrial level which are the consequence of global factors. (UK).

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

    African Journals Online (AJOL)

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

  12. A subset of FG-nucleoporins is necessary for efficient Msn5-mediated nuclear protein export

    Science.gov (United States)

    Finn, Erin M.; DeRoo, Elise P.; Clement, George W.; Rao, Sheila; Kruse, Sarah E.; Kokanovich, Kate M.; Belanger, Kenneth D.

    2013-01-01

    The transport of proteins between the cytoplasm and nucleus requires interactions between soluble transport receptors (karyopherins) and phenylalanine-glycine (FG) repeat domains on nuclear pore complex proteins (nucleoporins). However, the role of specific FG repeat-containing nucleoporins in nuclear protein export has not been carefully investigated. We have developed a novel kinetic assay to investigate the relative export kinetics mediated by the karyopherin Msn5/Kap142 in yeast containing specific FG-Nup mutations. Using the Msn5 substrate Crz1 as a marker for Msn5-mediated protein export, we observe that deletions of NUP100 or NUP2 result in decreased rates of Crz1 export, while nup60Δ and nup42Δ mutants do not vary significantly from wild type. The decreased Msn5 export rate in nup100Δ was confirmed using Mig1-GFP as a transport substrate. A nup100ΔGLFG mutant shows defects in nuclear export kinetics similar to a nup100Δ deletion. Removal of FG-repeats from Nsp1 also decreases export kinetics, while a loss of Nup1 FXFGs does not. To confirm that our export data reflected functional differences in protein localization, we performed Crz1 transcription activation assays using a CDRE::LacZ reporter gene that is upregulated upon increased transcription activation by Crz1 in vivo. We observe that expression from this reporter increases in nup100ΔGLFG and nsp1ΔFGΔFXFG strains that exhibit decreased Crz1 export kinetics but resembles wild-type levels in nup1ΔFXFG strains that do not exhibit export defects. These data provide evidence that the export of Msn5 is likely mediated by a specific subset of FG-Nups and that the GLFG repeat domain of Nup100 is important for Msn5-mediated nuclear protein export. PMID:23295456

  13. On recycling of nuclear fuel in Japan

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    In Japan, atomic energy has become to accomplish the important role in energy supply. Recently the interest in the protection of global environment heightened, and the anxiety on oil supply has been felt due to the circumstances in Mideast. Therefore, the importance of atomic energy as an energy source for hereafter increased, and the future plan of nuclear fuel recycling in Japan must be promoted on such viewpoint. At present in Japan, the construction of nuclear fuel cycle facilities is in progress in Rokkasho, Aomori Prefecture. The prototype FBR 'Monju' started the general functional test in May, this year. The transport of the plutonium reprocessed in U.K. and France to Japan will be carried out in near future. This report presents the concrete measures of nuclear fuel recycling in Japan from the long term viewpoint up to 2010. The necessity and meaning of nuclear fuel recycling in Japan, the effort related to nuclear nonproliferation, the plan of nuclear fuel recycling for hereafter in Japan, the organization of MOX fuel fabrication in Japan and abroad, the method of utilizing recovered uranium and the reprocessing of spent MOX fuel are described. (K.I.).

  14. World nuclear fuel cycle requirements 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This analysis report presents the projected requirements for uranium concentrate and uranium enrichment services to fuel the nuclear power plants expected to be operating under two nuclear supply scenarios. These two scenarios, the Lower Reference and Upper Reference cases, apply to the United States, Canada, Europe, the Far East, and other countries in the World Outside Centrally Planned Economic Areas (WOCA). A No New Orders scenarios is also presented for the Unites States. This report contains an analysis of the sensitivities of the nuclear fuel cycle projections to different levels and types of projected nuclear capacity, different enrichment tails assays, higher and lower capacity factors, changes in nuclear fuel burnup levels, and other exogenous assumptions. The projections for the United States generally extend through the year 2020, and the WOCA projections, which include the United States, are provided through 2010. The report also presents annual projections of spent nuclear fuel; discharges and inventories of spent fuel. Appendix D includes domestic spent fuel projections through the year 2020 for the Lower and Upper Reference cases and through 2036, the last year in which spent fuel is discharged, for the No New Orders case

  15. 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.)

  16. Thorium fuel cycle: a nuclear strategy and fuel recycle technology

    Energy Technology Data Exchange (ETDEWEB)

    Kasten, P.R.; Dahlberg, R.C.; Wymer, R.G.

    1978-01-01

    Use of thorium fuel cycles in thermal reactors appears to permit a moderate rate of introduction of fast breeder reactors into the nuclear economy and helps maintain a relatively low ratio of FBRs to thermal reactors in the future. To implement the benefits of thorium fuel cycles, however, will require fuel recycle research and development. Fuel recycle technology developed for uranium and plutonium cycles will be beneficial to thorium fuel cycle development; however, significant additional R and D is required to implement either the HEUTH or the DUTH cycles. The metal-clad reactors in general have relatively common generic technology development requirements, although there are significant differences between fast and thermal reactor fuel recycle needs. The thorium fuel recycle R and D requirements of HTGRs are more reactor-specific than of the other reactor types; however, some specific efforts will be required for all the different reactor types.

  17. Radioecology of nuclear fuel cycles

    International Nuclear Information System (INIS)

    Schreckhise, R.G.; Cadwell, L.L.; Emery, R.M.

    1980-01-01

    Sites where radioactive wastes are found are solid waste burial grounds, soils below liquid stoage areas, surface ditches and ponds, and the terrestrial environment around chemical processing facilities that discharge airborne radioactive debris from stacks. This study provides information to help assess the environmental impacts and certain potentiall human hazards associated with nuclear fuel cycles. A data base is being developed to define and quantify biological transport routes which will permit credible predictions and assessment of routine and potential large-scale releases of radionuclides and other toxic materials. These data, used in assessment models, will increase the accuracy of estimating radiation doses to man and other life forms. Information obtained from existing storage and disposal sites will provide a meaningful radioecological perspective with which to improve the effectiveness of waste management practices. Results will provide information to determine if waste management procedures on the Hanford Site have caused ecological perturbations, and if so, to determine the source, nature, and magnitude of such disturbances

  18. 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

  19. 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

  20. The formation of nuclear export control in Azerbaijan

    International Nuclear Information System (INIS)

    Garibov, A.A.

    2003-01-01

    Full text: The controlling process of exporting and importing on Azerbaijan borders is being carried out by two state organizations. 1.Border Guard Department; 2.Azerbaijan State Customs Committee. The officers of these organizations have no enough necessary experience and knowledge dealing with the legal and illegal trafficking. There were not special educational institutions in order to train personals for both of these organizations made newly. So there's difference between the professions of the majority of the employees, that's why some of the employees follow the instructions linking to the normative documents while passing the border. When trafficking nuclear and dual-use items officially the controller and other employees should look through the list of all and know them how to behave and to make official, the characteristic parameters of the materials, and the instruction of monitoring. In order to realize all works pointed, the employees of Border Guard Department and Customs Control Check Points have to attend special courses. The employees of both organizations are frequently changed that's why studying courses are to be organized. The analysis of studying considered that will be realized shows mainly there may be two student groups. Mainly, the Institute of Radiation Problems of ANAS (Azerbaijan National Academy of Sciences) as the expert laboratory takes part in. On the borders of Azerbaijan Republic the dual-use items and equipment having the type of isotope sources being utilized in the technological process are mainly being transported. In the materials presented the results and the solution of the problems dealing with realizing the controlling expert system of nuclear materials in the existing control checkpoints due to the international standards have been given

  1. Nuclear fuel reliability in NPP KRSKO

    International Nuclear Information System (INIS)

    Antolovic, A.; Kurincic, B.

    2001-01-01

    The importance of achieving and maintaining high fuel integrity comes from negative consequences of operation with failed fuel. Failed fuel has a significant effect on operating cost and performance, and increases the radiological consequences to environment. Fuel failures represent a breach in the first barrier (cladding) preventing the release of fission products. Historically NPP Krsko experienced some degradation of fuel cladding integrity. To resolve this problem and to ensure the safe, reliable and cost effective operation of nuclear fuel, NPP Krsko established 'Fuel Integrity Program'. The key elements of the Program are: continuous monitoring and trending of the fuel behaviour through operating cycle, evaluation of key performance indicators (RCS isotopes, operational parameters) to determine whether the fuel defects exist, implementation of appropriate actions to reduce and mitigate the consequences of fuel defects (four action levels), 100% examination of fuel to remove the defective fuel from operation (Ultrasonic (UT), In Mast Sipping (IMS) and visual inspection), evaluating the worldwide experience and fuel performance and, integrating the experience and knowledge into new fuel design (ZIRLO TM cladding, debris filter bottom nozzle, removable top nozzle). Since start of commercial operation fuel integrity has been evaluated considering certain aspects like operation and fuel handling, fuel rod burnup and cycle length, cladding material properties, etc. As a result of successful Fuel Integrity Program NPP Krsko has achieved high performance level in terms of fuel integrity in past four cycles. Also, NPP Krsko calculations show good matching between analytical prediction of number of failed fuel rods from primary coolant activity analysis and inspection results with the Nondestructive Testing (NDT) methods.(author)

  2. Analysis of nuclear export control system and implementing international nonproliferation regime in China

    International Nuclear Information System (INIS)

    Kim, J. S.; Lee, J. S.; Ahn, J. S.; Kim, B. G.; Min, K. S.

    2000-01-01

    China's exporting behaviour of nuclear items had been disconnected from the international non-proliferation regime such as IAEA safeguards and export control related with peaceful use of nuclear energy since 1970s. Especially, China had been one of principle suppliers of nuclear facility and technologies to Pakistan and Iran which had developed nuclear weapon programs. On the other hand, according to the rapid growth of economic scale after China began to open to the world, an active program for nuclear power plant as an electricity source had established. This means that China have surfaced as a big market to Korean nuclear industries. Regarding this, the paper dealt with the nuclear export control matters, i.e. the history of nuclear export control system and analyzed on background of enforcement of U.S.-China Nuclear Cooperation Agreement that had been apolitical issue between U.S. and China. Prospects toward conforming its nuclear export policies, laws and regulations to international standards also analyzed in results

  3. Define rules for the exporter and importer of minerals or ores containing nuclear elements

    International Nuclear Information System (INIS)

    1969-01-01

    The present resolution establishes regulations for the exporter of minerals or ores containing associated nuclear elements, and for the importer of chemical compounds of technical purity grade, containing a quantity of fissile of fertile materials equal to the existent in the exported material

  4. FUEL ELEMENT FOR NUCLEAR REACTORS

    Science.gov (United States)

    Bassett, C.H.

    1961-11-21

    A fuel element is designed which is particularly adapted for reactors of high power density used to generate steam for the production of electricity. The fuel element consists of inner and outer concentric tubes forming an annular chamber within which is contained fissionable fuel pellet segments, wedge members interposed between the fuel segments, and a spring which, acting with wedge members, urges said fuel pellets radially into contact against the inner surface of the outer tube. The wedge members may be a fertile material convertible into fissionable fuel material by absorbing neutrons emitted from the fissionable fuel pellet segments. The costly grinding of cylindrical fuel pellets to close tolerances for snug engagement is reduced because the need to finish the exact size is eliminated. (AEC)

  5. Levelized nuclear fueling cost in Israel

    International Nuclear Information System (INIS)

    Baron, A.I.; Adar, J.

    1982-01-01

    Basic nuclear fuel cycle mode options are discussed as they apply to PWR-type reactors. Forecast fueling costs have been computed and are reported for the two main choices - basic front-end cost supplemented by either a throw- away mode option or a reprocessing mode option. It is concluded that reprocessing could result in total unit fueling costs ranging from a minimum slightly lower, through a maximum about 30% higher than the total unit fueling cost using the throw-away mode option. Moreover, in massive breeder development the total unit fueling cost can extend even below the numerically calculated limit. (H.K.)

  6. Storage and Reprocessing of Spent Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-02-02

    Addressing the problem of waste, especially high-level waste (HLW), is a requirement of the nuclear fuel cycle that cannot be ignored. We explore the two options employed currently, long-term storage and reprocessing.

  7. Solvent extraction in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Chesne, A.

    1980-09-01

    The author reviews the chief aspects of solvent extraction in reprocessing, including choice of the solvent, general description of the Purex process, and extractor technology, while emphasizing the specific character of nuclear fuels

  8. 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)

  9. Concrete encapsulation for spent nuclear fuel storage

    International Nuclear Information System (INIS)

    Fleischer, L.R.; Gunasekaran, M.

    1981-01-01

    Concrete systems, mixtures and methods for encapsulating and storing spent nuclear fuel. Fuel discharged from nuclear reactors in the form of rods or multi-rod assemblies is completely and contiguously enclosed in concrete having incorporated therein metallic fibers to increase thermal conductivity and polymers to decrease fluid permeability. The metallic fibers and the polymers can be distributed in a single concrete layer, or separate contiguous layers can be utilized for the conductivity and impermeability characteristics

  10. Nuclear fuel resources: enough to last?

    International Nuclear Information System (INIS)

    Price, R.; Blaise, J.R.

    2002-01-01

    The need to meet ever-growing energy demands in an environmentally sustainable manner has turned attention to the potential for nuclear energy to play an expanded role in future energy supply mixes. One of the key aspects in defining the sustainability of any energy source is the availability of fuel resources. This article shows that available nuclear energy fuel resources can meet future needs for hundreds, even thousands, of years

  11. Nuclear fuel: modelling the advanced plutonium assembly

    International Nuclear Information System (INIS)

    Kaoua, Th.; Lenain, R.

    2004-01-01

    The benefits of modeling in the nuclear sector are illustrated by the example of the design study for a new plutonium fuel assembly, APA, capable of ensuring maximum consumption of this fuel in pressurized-water reactors. Beyond the physical design of the assembly and its integration into the reactor, this serves for the working out of a complete materials flow and assists in modeling production from the entire inventory of nuclear power stations. (authors)

  12. Fuel element for a nuclear reactor

    International Nuclear Information System (INIS)

    Linning, D.L.

    1977-01-01

    An improvement of the fuel element for a fast nuclear reactor described in patent 15 89 010 is proposed which should avoid possible damage due to swelling of the fuel. While the fuel element according to patent 15 89 010 is made in the form of a tube, here a further metal jacket is inserted in the centre of the fuel rod and the intermediate layer (ceramic uranium compound) is provided on both sides, so that the nuclear fuel is situated in the centre of the annular construction. Ceramic uranium or plutonium compounds (preferably carbide) form the fuel zone in the form of circular pellets, which are surrounded by annular gaps, so that gaseous fission products can escape. (UWI) [de

  13. Nuclear power and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1988-06-01

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

  14. Nuclear fuel for LWR type reactor

    International Nuclear Information System (INIS)

    Gunji, Yasuyoshi.

    1995-01-01

    Coated particulate fuels are used. The coated particulate fuel comprises a sintered nuclear fuel sphere as a center, and respective layers of a low density thermally decomposed carbon layer, a high density thermally decomposed carbon layer, a silicon carbide layer and a high density thermally decomposed carbon layer disposed successively. The nuclear fuel sintered sphere comprises a sintered nuclear fuel of uranium dioxide having a diameter of from 0.3mm to 1.2mm. The low density thermally decomposed carbon layer as the first cladding layer coating the sintered nuclear fuel sphere functions as a buffering layer for the sintered nuclear fuel sphere and the high density thermally decomposed carbon layer as a second cladding layer. In addition, it functions for absorption of swelling and storing of FP gases. The high density thermally decomposed carbon layer as the second cladding layer functions as a layer for holding gaseous FP. In addition, a silicon carbide layer as a third cladding layer functions as a barrier for a solid FP. A high density thermally decomposing carbon layer as a fourth cladding layer functions as a protection layer for the silicon carbide layer. (I.N.)

  15. Nuclear reactor fuel assembly spacer grids

    International Nuclear Information System (INIS)

    Jabsen, F.S.

    1977-01-01

    Designs of nuclear reactor fuel assembly spacer grids for supporting and spacing fuel elements are described which do not utilize resilient grid plate protrusions in the peripheral band but retain the advantages inherent in the combination resilient and rigid protrusion cells. (U.K.)

  16. 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

  17. The nuclear fuel: a limitless resource?

    International Nuclear Information System (INIS)

    Sorin, Francis

    2015-01-01

    This article proposes an overview of the possible resources of nuclear fuel in the future. The author notably addresses the use of thorium as a future fuel (it is abundant but has a low solubility), the exploitation of uranium present in sea water (the quantity is huge but the extraction process is complex and costly), the use of uranium 238 as fuel for fast neutron reactors (99 per cent of the mass of natural uranium is made of this isotope)

  18. Nuclear spent fuel management. Experience and options

    International Nuclear Information System (INIS)

    1986-01-01

    Spent nuclear fuel can be stored safely for long periods at relatively low cost, but some form of permanent disposal will eventually be necessary. This report examines the options for spent fuel management, explores the future prospects for each stage of the back-end of the fuel cycle and provides a thorough review of past experience and the technical status of the alternatives. Current policies and practices in twelve OECD countries are surveyed

  19. Rack for storing spent nuclear fuel elements

    Science.gov (United States)

    Rubinstein, Herbert J.; Clark, Philip M.; Gilcrest, James D.

    1978-06-20

    A rack for storing spent nuclear fuel elements in which a plurality of aligned rows of upright enclosures of generally square cross-sectional areas contain vertically disposed fuel elements. The enclosures are fixed at the lower ends thereof to a base. Pockets are formed between confronting walls of adjacent enclosures for receiving high absorption neutron absorbers, such as Boral, cadmium, borated stainless steel and the like for the closer spacing of spent fuel elements.

  20. Fuel handling system of nuclear reactor plants

    International Nuclear Information System (INIS)

    Faulstich, D.L.

    1991-01-01

    This patent describes a fuel handing system for nuclear reactor plants comprising a reactor vessel having an openable top and removable cover for refueling and containing therein, submerged in coolant water substantially filling the reactor vessel, a fuel core including a multiplicity of fuel bundles formed of groups of sealed tube elements enclosing fissionable fuel assembled into units. It comprises a fuel bundle handing platform moveable over the open top of the reactor vessel; a fuel bundle handing mast extendable downward from the platform with a lower end projecting into the open top reactor vessel to the fuel core submerged in water; a grapple head mounted on the lower end of the mast provided with grappling hook means for attaching to and transporting fuel bundles into and out from the fuel core; and a camera with a prismatic viewing head surrounded by a radioactive resisting quartz cylinder and enclosed within the grapple head which is provided with at least three windows with at least two windows provided with an angled surface for aiming the camera prismatic viewing head in different directions and thereby viewing the fuel bundles of the fuel core from different perspectives, and having a cable connecting the camera with a viewing monitor located above the reactor vessel for observing the fuel bundles of the fuel core and for enabling aiming of the camera prismatic viewing head through the windows by an operator

  1. Identification of a nuclear export signal in the KSHV latent protein LANA2 mediating its export from the nucleus

    International Nuclear Information System (INIS)

    Munoz-Fontela, C.; Collado, M.; Rodriguez, E.; Garcia, M.A.; Alvarez-Barrientos, A.; Arroyo, J.; Nombela, C.; Rivas, C.

    2005-01-01

    LANA2 is a latent protein detected in Kaposi's sarcoma-associated herpesvirus (KSHV)-infected B cells that inhibits p53-dependent transcriptional transactivation and apoptosis and PKR-dependent apoptosis, suggesting an important role in the transforming activity of the virus. It has been reported that LANA2 localizes into the nucleus of both KSHV-infected B cells and transiently transfected HeLa cells. In this study, we show that LANA2 is a nucleocytoplasmic shuttling protein that requires a Rev-type nuclear export signal located in the C-terminus to direct the protein to the cytoplasm, through an association with the export receptor CRM1. In addition, a functional protein kinase B (PKB)/Akt phosphorylation motif partially overlapping with the nuclear export signal was identified. Nuclear exclusion of LANA2 was negatively regulated by the phosphorylation of threonine 564 by Akt. The ability of LANA2 to shuttle between nucleus and cytoplasm has implications for the function of this viral protein

  2. Integrated spent nuclear fuel database system

    International Nuclear Information System (INIS)

    Henline, S.P.; Klingler, K.G.; Schierman, B.H.

    1994-01-01

    The Distributed Information Systems software Unit at the Idaho National Engineering Laboratory has designed and developed an Integrated Spent Nuclear Fuel Database System (ISNFDS), which maintains a computerized inventory of all US Department of Energy (DOE) spent nuclear fuel (SNF). Commercial SNF is not included in the ISNFDS unless it is owned or stored by DOE. The ISNFDS is an integrated, single data source containing accurate, traceable, and consistent data and provides extensive data for each fuel, extensive facility data for every facility, and numerous data reports and queries

  3. Canada's nuclear fuel industry: An overview. Background paper

    International Nuclear Information System (INIS)

    Nixon, A.

    1993-11-01

    Canada was among the first countries to mine and process uranium-bearing ores. Such ores contain trace amounts of radium, which was in great demand for medical treatment and for use by research laboratories in the early part of the century. For the last half century, the same basic processes have been used to extract uranium from its ores and convert it to a form suitable for use in nuclear reactors. The process described here is that currently in use in Canada. Mining can take a variety of forms, from open-pit to deep, hard-rock. Mining is typically the most costly step in the process, particularly for lower-grade ores. The ore is crushed and ground in the mill to the consistency of fine sand from which the uranium is extracted chemically to produce the impure concentrate known as yellowcake. In the next step, the impure uranium concentrate is chemically refined into highly purified, nuclear-grade, uranium trioxide (UO 3 ). Uranium trioxide is then converted, in two separate chemical processes, into uranium dioxide (UO 2 ) which is destined for domestic consumption and uranium hexafluoride (UF 6 ) which is exported. In Canada, fabrication is the final step of the fuel production process. Uranium dioxide powder is compressed and sintered into very dense ceramic pellets which are then sealed in zirconium tubes and assembled into fuel bundles for Candu reactors. This background paper will review the Canadian nuclear fuels industry. 1 fig

  4. The sea transport of irradiated nuclear fuel

    International Nuclear Information System (INIS)

    Miller, M.L.

    1995-01-01

    The paper describes the development of a transport system dedicated to the sea transport of irradiated nuclear fuel. It reviews the background to why shipments were required and the establishment of a specialist shipping company, Pacific Nuclear Transport Limited. A description of the ships, flasks and other equipment utilized is provided, together with details of key procedures implemented to ensure safety and customer satisfaction

  5. Accelerators and alternative nuclear fuel management options

    International Nuclear Information System (INIS)

    Harms, A.A.

    1983-01-01

    The development of special accelerators suggests the po tential for new directions in nuclear energy systems evolution. Such directions point towards a more acceptable form of nuclear energy by reason of the consequent accessibility of enhanced fuel management choices. Essential and specifically directed research and development activity needs to be under taken in order to clarify and resolve a number of technical issues

  6. 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

  7. Waste management and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Molinari, J.

    1982-01-01

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

  8. Long term wet spent nuclear fuel storage

    International Nuclear Information System (INIS)

    1987-04-01

    The meeting showed that there is continuing confidence in the use of wet storage for spent nuclear fuel and that long-term wet storage of fuel clad in zirconium alloys can be readily achieved. The importance of maintaining good water chemistry has been identified. The long-term wet storage behaviour of sensitized stainless steel clad fuel involves, as yet, some uncertainties. However, great reliance will be placed on long-term wet storage of spent fuel into the future. The following topics were treated to some extent: Oxidation of the external surface of fuel clad, rod consolidation, radiation protection, optimum methods of treating spent fuel storage water, physical radiation effects, and the behaviour of spent fuel assemblies of long-term wet storage conditions. A number of papers on national experience are included

  9. Fuel transfer system for a nuclear reactor

    International Nuclear Information System (INIS)

    Katz, L.R.; Marshall, J.R.; Desmarchais, W.E.

    1977-01-01

    Disclosed is a fuel transfer system for moving nuclear reactor fuel assemblies from a new fuel storage pit to a containment area containing the nuclear reactor, and for transferring spent fuel assemblies under water from the reactor to a spent fuel storage area. The system includes an underwater track which extends through a wall dividing the fuel building from the reactor containment and a car on the track serves as the vehicle for moving fuel assemblies between these two areas. The car is driven by a motor and linkage extending from an operating deck to a chain belt drive on the car. A housing pivotally mounted at its center on the car is hydraulically actuated to vertically receive a fuel assembly which then is rotated to a horizontal position to permit movement through the wall between the containment and fuel building areas. Return to the vertical position provides for fuel assembly removal and the reverse process is repeated when transferring an assembly in the opposite direction. Limit switches used in controlling operation of the system are designed to be replaced from the operating deck when necessary by tools designed for this purpose. 5 claims, 8 figures

  10. 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

  11. Questionnaire used and responses obtained by sub-group 1C on the subject of the impact of national policies and constraints on nuclear fuel exploration, marketing and assurance of supply

    International Nuclear Information System (INIS)

    Information on existing national policies and incentives for uranium and thorium exploration, mining, export, import and stockpiling of nuclear fuel and measures which are being adopted to promote nuclear industries is presented

  12. Nuclear Fuels & Materials Spotlight Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    I. J. van Rooyen,; T. M. Lillo; Y. Q. WU; P.A. Demkowicz; L. Scott; D.M. Scates; E. L. Reber; J. H. Jackson; J. A. Smith; D.L. Cottle; B.H. Rabin; M.R. Tonks; S.B. Biner; Y. Zhang; R.L. Williamson; S.R. Novascone; B.W. Spencer; J.D. Hales; D.R. Gaston; C.J. Permann; D. Anders; S.L. Hayes; P.C. Millett; D. Andersson; C. Stanek; R. Ali; S.L. Garrett; J.E. Daw; J.L. Rempe; J. Palmer; B. Tittmann; B. Reinhardt; G. Kohse; P. Ramuhali; H.T. Chien; T. Unruh; B.M. Chase; D.W. Nigg; G. Imel; J. T. Harris

    2014-04-01

    As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • The first identification of silver and palladium migrating through the SiC layer in TRISO fuel • A description of irradiation assisted stress corrosion testing capabilities that support commercial light water reactor life extension • Results of high-temperature safety testing on coated particle fuels irradiated in the ATR • New methods for testing the integrity of irradiated plate-type reactor fuel • Description of a 'Smart Fuel' concept that wirelessly provides real time information about changes in nuclear fuel properties and operating conditions • Development and testing of ultrasonic transducers and real-time flux sensors for use inside reactor cores, and • An example of a capsule irradiation test. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps to spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at INL, and hope that you find this issue informative.

  13. Vertical integration in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Mommsen, J.T.

    1977-01-01

    Vertical integration in the nuclear fuel cycle and its contribution to market power of integrated fuel suppliers were studied. The industry subdivision analyzed is the uranium raw materials sector. The hypotheses demonstrated are that (1) this sector of the industry is trending toward vertical integration between production of uranium raw materials and the manufacture of nuclear fuel elements, and (2) this vertical integration confers upon integrated firms a significant market advantage over non-integrated fuel manufacturers. Under microeconomic concepts the rationale for vertical integration is the pursuit of efficiency, and it is beneficial because it increases physical output and decreases price. The Market Advantage Model developed is an arithmetical statement of the relative market power (in terms of price) between non-integrated nuclear fuel manufacturers and integrated raw material/fuel suppliers, based on the concept of the ''squeeze.'' In operation, the model compares net profit and return on sales of nuclear fuel elements between the competitors, under different price and cost circumstances. The model shows that, if integrated and non-integrated competitors sell their final product at identical prices, the non-integrated manufacturer returns a net profit only 17% of the integrated firm. Also, the integrated supplier can price his product 35% below the non-integrated producer's price and still return the same net profit. Vertical integration confers a definite market advantage to the integrated supplier, and the basic source of that advantage is the cost-price differential of the raw material, uranium

  14. 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

  15. Spent nuclear fuel policies in historical perspective: An international comparison

    International Nuclear Information System (INIS)

    Hoegselius, Per

    2009-01-01

    The purpose of this article is to explain why the world's nuclear power countries differ from each other with respect to their spent nuclear fuel (SNF) policies. The emergence and evolution of three principal SNF approaches are analyzed: direct disposal, reprocessing and SNF export. Five broad explanatory factors are identified and discussed in relation to the observed differences in policy outcomes: military ambitions and non-proliferation, technological culture, political culture and civil society, geological conditions, and energy policy. SNF policy outcomes can generally be seen to result from a complex interaction between these broad factors, but it is also possible to discern a number of important patterns. To the extent that the five factors may undergo far-reaching changes in the future, the historical experience of how they have shaped SNF policies also give a hint of possible future directions in SNF policymaking around the world

  16. Advanced Nuclear Fuels Corporation: one year later

    International Nuclear Information System (INIS)

    Bjoernard, T.A.; Sofer, G.A.

    1988-01-01

    About one year ago, after 18 years of business as a wholly owned affiliate of Exxon Corporation, Exxon Nuclear Company was acquired by Siemens/KWU and its name was changed to Advanced Nuclear Fuels Corporation (ANF). This profile describes the status of ANF one year later, principally from the European perspective but with some mention of ANF's worldwide operations to provide a balanced picture. After one year of operation as an affiliate of Siemens/KWU, ANF's role remains as an independent international supplier of nuclear fuel and services to utilities in Europe, the USA and the Far East, but with substantially augmented capabilities resulting from the new affiliation

  17. Morbillivirus nucleoprotein possesses a novel nuclear localization signal and a CRM1-independent nuclear export signal

    International Nuclear Information System (INIS)

    Sato, Hiroki; Masuda, Munemitsu; Miura, Ryuichi; Yoneda, Misako; Kai, Chieko

    2006-01-01

    Morbilliviruses, which belong to the Mononegavirales, replicate its RNA genome in the cytoplasm of the host cell. However, they also form characteristic intranuclear inclusion bodies, consisting of nucleoprotein (N), in infected cells. To analyze the mechanisms of nucleocytoplasmic transport of N protein, we characterized the nuclear localization (NLS) and nuclear export (NES) signals of canine distemper virus (CDV) N protein by deletion mutation and alanine substitution of the protein. The NLS has a novel leucine/isoleucine-rich motif (TGILISIL) at positions 70-77, whereas the NES is composed of a leucine-rich motif (LLRSLTLF) at positions 4-11. The NLS and NES of the N proteins of other morbilliviruses, that is, measles virus (MV) and rinderpest virus (RPV), were also analyzed. The NLS of CDV-N protein is conserved at the same position in MV-N protein, whereas the NES of MV-N protein is located in the C-terminal region. The NES of RPV-N protein is also located at the same position as CDV-N protein, whereas the NLS motif is present not only at the same locus as CDV-N protein but also at other sites. Interestingly, the nuclear export of all these N proteins appears to proceed via a CRM1-independent pathway

  18. Nuclear Fuel Cycle Evaluation and Real Options

    Directory of Open Access Journals (Sweden)

    L. Havlíček

    2008-01-01

    Full Text Available The first part of this paper describes the nuclear fuel cycle. It is divided into three parts. The first part, called Front-End, covers all activities connected with fuel procurement and fabrication. The middle part of the cycle includes fuel reload design activities and the operation of the fuel in the reactor. Back-End comprises all activities ensuring safe separation of spent fuel and radioactive waste from the environment. The individual stages of the fuel cycle are strongly interrelated. Overall economic optimization is very difficult. Generally, NPV is used for an economic evaluation in the nuclear fuel cycle. However the high volatility of uranium prices in the Front-End, and the large uncertainty of both economic and technical parameters in the Back-End, make the use of NPV difficult. The real option method is able to evaluate the value added by flexibility of decision making by a company under conditions of uncertainty. The possibility of applying this method to the nuclear fuel cycle evaluation is studied. 

  19. Fundamental aspects of nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Olander, D.R.

    1976-01-01

    The book presented is designed to function both as a text for first-year graduate courses in nuclear materials and as a reference for workers involved in the materials design and performance aspects of nuclear power plants. The contents are arranged under the following chapter headings: statistical thermodynamics, thermal properties of solids, crystal structures, cohesive energy of solids, chemical equilibrium, point defects in solids, diffusion in solids, dislocations and grain boundaries, equation of state of UO 2 , fuel element thermal performance, fuel chemistry, behavior of solid fission products in oxide fuel elements, swelling due to fission gases, pore migration and fuel restructuring kinetics, fission gas release, mechanical properties of UO 2 , radiation damage, radiation effects in metals, interaction of sodium and stainless steel, modeling of the structural behavior of fuel elements and assemblies

  20. Fundamental aspects of nuclear reactor fuel elements

    Energy Technology Data Exchange (ETDEWEB)

    Olander, D.R.

    1976-01-01

    The book presented is designed to function both as a text for first-year graduate courses in nuclear materials and as a reference for workers involved in the materials design and performance aspects of nuclear power plants. The contents are arranged under the following chapter headings: statistical thermodynamics, thermal properties of solids, crystal structures, cohesive energy of solids, chemical equilibrium, point defects in solids, diffusion in solids, dislocations and grain boundaries, equation of state of UO/sub 2/, fuel element thermal performance, fuel chemistry, behavior of solid fission products in oxide fuel elements, swelling due to fission gases, pore migration and fuel restructuring kinetics, fission gas release, mechanical properties of UO/sub 2/, radiation damage, radiation effects in metals, interaction of sodium and stainless steel, modeling of the structural behavior of fuel elements and assemblies. (DG)

  1. Nuclear fuel cycle facility accident analysis handbook

    Energy Technology Data Exchange (ETDEWEB)

    Ayer, J E; Clark, A T; Loysen, P; Ballinger, M Y; Mishima, J; Owczarski, P C; Gregory, W S; Nichols, B D

    1988-05-01

    The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH.

  2. Nuclear fuel cycle facility accident analysis handbook

    International Nuclear Information System (INIS)

    Ayer, J.E.; Clark, A.T.; Loysen, P.; Ballinger, M.Y.; Mishima, J.; Owczarski, P.C.; Gregory, W.S.; Nichols, B.D.

    1988-05-01

    The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH

  3. Nuclear fuels for material test reactors

    International Nuclear Information System (INIS)

    Ramanathan, L.V.; Durazzo, M.; Freitas, C.T. de

    1982-01-01

    Experimental results related do the development of nuclear fuels for reactors cooled and moderated by water have been presented cylindrical and plate type fuels have been described in which the core consists of U compouns dispersed in an Al matrix and is clad with aluminium. Fabrication details involving rollmilling, swaging or hot pressing have been described. Corrosion and irradiation test results are also discussed. The performance of the different types of fuels indicates that it is possible to locally fabricate fuel plates with U 3 O 8 +Al cores (20% enriched U) for use in operating Brazilian research reactors. (Author) [pt

  4. International nuclear fuel cycle fact book

    International Nuclear Information System (INIS)

    1992-09-01

    The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R ampersand D programs and key personnel on 23 countries, including the US, four multi-national agencies, and 21 nuclear societies. The Fact Book is organized as follows: National summaries-a section for each country which summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies-a section for each of the international agencies which has significant fuel cycle involvement and a listing of nuclear societies. Glossary-a list of abbreviations/acronyms of organizations, facilities, technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter presented from the perspective of the Fact Book user in the United States

  5. Significant incidents in nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    1996-03-01

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

  6. Abundant thorium as an alternative nuclear fuel

    International Nuclear Information System (INIS)

    Baker Schaffer, Marvin

    2013-01-01

    It has long been known that thorium-232 is a fertile radioactive material that can produce energy in nuclear reactors for conversion to electricity. Thorium-232 is well suited to a variety of reactor types including molten fluoride salt designs, heavy water CANDU configurations, and helium-cooled TRISO-fueled systems. Among contentious commercial nuclear power issues are the questions of what to do with long-lived radioactive waste and how to minimize weapon proliferation dangers. The substitution of thorium for uranium as fuel in nuclear reactors has significant potential for minimizing both problems. Thorium is three times more abundant in nature than uranium. Whereas uranium has to be imported, there is enough thorium in the United States alone to provide adequate grid power for many centuries. A well-designed thorium reactor could produce electricity less expensively than a next-generation coal-fired plant or a current-generation uranium-fueled nuclear reactor. Importantly, thorium reactors produce substantially less long-lived radioactive waste than uranium reactors. Thorium-fueled reactors with molten salt configurations and very high temperature thorium-based TRISO-fueled reactors are both recommended for priority Generation IV funding in the 2030 time frame. - Highlights: • Thorium is an abundant nuclear fuel that is well suited to three advanced reactor configurations. • Important thorium reactor configurations include molten salt, CANDU, and TRISO systems. • Thorium has important nuclear waste disposal advantages relative to pressurized water reactors. • Thorium as a nuclear fuel has important advantages relative to weapon non-proliferation

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

    Energy Technology Data Exchange (ETDEWEB)

    Saltiel, David H.; Pregenzer, Arian Leigh

    2005-04-01

    the century and could increase even more quickly. Much of the new demand will come from the rapidly expanding economies in China and India, but much of the developing world stands poised to follow the same path. This growth in demand is paralleled by concerns about global warming and the long-term reliability of carbon-based fuel supplies, concerns which expanded use of nuclear power can help to address. For these reasons and others, many countries in Asia have already clearly signaled that nuclear energy will play a key role for years to come. Numerous proposals have been made in the last two years for reducing the proliferation risk of the civilian nuclear fuel cycle. These range from a ban on export of enrichment and reprocessing technology to countries not already possessing operational capabilities to multinational management of the nuclear fuel cycle and strengthening existing monitoring and security mechanisms. The need for international willingness to enforce nonproliferation commitments and norms has also been emphasized. Some of these proposals could significantly impact the production of nuclear energy. Because the successful strengthening of the nonproliferation regime and the expansion of nuclear energy are so closely related, any successful approach to resolving these issues will require the creative input of experts from both the nuclear energy and nonproliferation communities. Against this backdrop, Sandia National Laboratories organized its 14th International Security Conference (ISC) around the theme: Strengthening the Nuclear Nonproliferation Regime: Focus on the Civilian Nuclear Fuel Cycle. The goal of the conference was to begin a constructive dialogue between the nuclear energy and nuclear nonproliferation communities. The conference was held in Chantilly, Virginia, just outside Washington, D.C. on April 4-6, 2005, and was attended by approximately 125 participants from fifteen countries. The ISC agenda was structured to produce a systematic

  8. Elements of nuclear reactor fueling theory

    International Nuclear Information System (INIS)

    Egan, M.R.

    1984-01-01

    Starting with a review of the simple batch size effect, a more general theory of nuclear fueling is derived to describe the behavior and physical requirements of operating cycle sequences and fueling strategies having practical use in the management of nuclear fuel. The generalized theory, based on linear reactivity modeling, is analytical and represents the effects of multiple-stream, multiple-depletion-batch fueling configurations in systems employing arbitrary, non-integer batch size strategies, and containing fuel with variable energy generation rates. Reactor operating cycles and cycle sequences are represented with realistic structure that includes the effects of variable cycle energy production, cycle lengths, end-of-cycle operating extensions and maneuvering allowances. Results of the analytical theory are first applied to the special case of degenerate equilibrium cycle sequences, yielding several fundamental principles related to the selection of refueling strategy, and which govern fueling decisions normally made by the fuel manager. It is also demonstrated in this application that the simple batch size effect is not valid for non-integer fueling strategies, even in the simplest sequence configurations, and that it systematically underestimates the fueling requirements of degenerate sequences in general

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

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  10. Managing the Nuclear Fuel Cycle, The Big Picture

    International Nuclear Information System (INIS)

    Carlsen, Brett W.

    2010-01-01

    The nuclear industry, at least in the United States, has failed to deliver on its promise of cheap, abundant energy. After pioneering the science and application and becoming a primary exporter of nuclear technologies, domestic use of nuclear power fell out-of-favor with the public and has been relatively stagnant for several decades. Recently, renewed interest has generated optimism and talk of a nuclear renaissance characterized by a new generation of safe, clean nuclear plants in this country. But, as illustrated by recent policy shifts regarding closure of the fuel cycle and geologic disposal of high-level radioactive wastes, significant hurdles have yet to be overcome. Using the principles of system dynamics, this paper will take a holistic look at the nuclear industry and the interactions between the key players to explore both the intended and unintended consequences of efforts to address the issues that have impeded the growth of the industry and also to illustrate aspects which must be effectively addressed if the renaissance of our industry is to be achieved and sustained.

  11. Managing the Nuclear Fuel Cycle, The Big Picture

    Energy Technology Data Exchange (ETDEWEB)

    Brett W Carlsen

    2010-07-01

    The nuclear industry, at least in the United States, has failed to deliver on its promise of cheap, abundant energy. After pioneering the science and application and becoming a primary exporter of nuclear technologies, domestic use of nuclear power fell out-of-favor with the public and has been relatively stagnant for several decades. Recently, renewed interest has generated optimism and talk of a nuclear renaissance characterized by a new generation of safe, clean nuclear plants in this country. But, as illustrated by recent policy shifts regarding closure of the fuel cycle and geologic disposal of high-level radioactive wastes, significant hurdles have yet to be overcome. Using the principles of system dynamics, this paper will take a holistic look at the nuclear industry and the interactions between the key players to explore both the intended and unintended consequences of efforts to address the issues that have impeded the growth of the industry and also to illustrate aspects which must be effectively addressed if the renaissance of our industry is to be achieved and sustained.

  12. Scyl1 Facilitates Nuclear tRNA Export in Mammalian Cells by Acting at the Nuclear Pore Complex

    Science.gov (United States)

    Chafe, Shawn C.

    2010-01-01

    Scyl1 is an evolutionarily conserved N-terminal protein kinase-like domain protein that plays a role in COP1-mediated retrograde protein trafficking in mammalian cells. Furthermore, loss of Scyl1 function has been shown to result in neurodegenerative disorders in mice. Here, we report that Scyl1 is also a cytoplasmic component of the mammalian nuclear tRNA export machinery. Like exportin-t, overexpression of Scyl1 restored export of a nuclear export-defective serine amber suppressor tRNA mutant in COS-7 cells. Scyl1 binds tRNA saturably, and associates with the nuclear pore complex by interacting, in part, with Nup98. Scyl1 copurifies with the nuclear tRNA export receptors exportin-t and exportin-5, the RanGTPase, and the eukaryotic elongation factor eEF-1A, which transports aminoacyl-tRNAs to the ribosomes. Scyl1 interacts directly with exportin-t and RanGTP but not with eEF-1A or RanGDP in vitro. Moreover, exportin-t containing tRNA, Scyl1, and RanGTP form a quaternary complex in vitro. Biochemical characterization also suggests that the nuclear aminoacylation-dependent pathway is primarily responsible for tRNA export in mammalian cells. These findings together suggest that Scyl1 participates in the nuclear aminoacylation-dependent tRNA export pathway and may unload aminoacyl-tRNAs from the nuclear tRNA export receptor at the cytoplasmic side of the nuclear pore complex and channels them to eEF-1A. PMID:20505071

  13. 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.)

  14. Nuclear fuel cycles: Adjusting to new realities

    International Nuclear Information System (INIS)

    Semenov, B.A.; Oi, N.

    1993-01-01

    This article presents a brief overview of developments, and describes a number of international activities being undertaken by the IAEA through its programme covering the nuclear fuel cycle. The activities fall into four areas: uranium resources; reactor fuel performance and technology; spent fuel management; and nuclear fuel cycle evaluation. Additionally, important work is being done through sub-programmes related to structural materials used in the nuclear industry. Throughout the nuclear fuel cycle, facilities have been plagued over the years with problems associated with some types of materials subjected to irradiation. Degradation of their mechanical and physical properties have led to the failure of components and costly downtime of reactors. The corrosion of metals and alloys continues to pose serious difficulties. These and other technical matters are being addressed internationally with the Agency's involvement and support. The Agency has been a center of information on uranium geology, exploration, mining, ore processing, and the analysis of supply and demand for many years. Current work further covers the closure of uranium mining and milling projects from the point of view of safety, environmental protection, economics, and licensing. Emphasis also is placed on supporting technical co-operation projects in countries seeking assistance in developing their peaceful nuclear programmes and fuel-cycle capabilities. An International Working Group on Nuclear Fuel Performance and Technology (IWGFPT), which was established in 1977, continues to guide the IAEA's work in the area of fuel design, fabrication, and performance. It now consists of 25 Member States and three international organizations and acts as a forum for contact between developed and developing countries. The IAEA's Regular Advisory Group on Spent Fuel Management was established in 1984. The Group meets every second year to provide technical advice on the Agency's programme and serves as a

  15. Nuclear reactor seismic fuel assembly grid

    International Nuclear Information System (INIS)

    Anthony, A.J.

    1977-01-01

    The strength of a nuclear reactor fuel assembly is enhanced by increasing the crush strength of the zircaloy spacer grids which locate and support the fuel elements in the fuel assembly. Increased resistance to deformation as a result of laterally directed forces is achieved by increasing the section modulus of the perimeter strip through bending the upper and lower edges thereof inwardly. The perimeter strip is further rigidized by forming, in the central portion thereof, dimples which extend inwardly with respect to the fuel assembly. The integrity of the spacer grid may also be enhanced by providing back-up arches for some or all of the integral fuel element locating springs and the strength of the fuel assembly may be further enhanced by providing, intermediate its ends, a steel seismic grid. 13 claims, 6 figures

  16. Reconstitutable fuel assembly for a nuclear reactor

    International Nuclear Information System (INIS)

    Shallenberger, J.M.; Kmonk, S.; Ferlan, S.J.

    1981-01-01

    A reconstitutable fuel assembly for a nuclear reactor with a mechanical arrangement for connecting control rod guide thimbles to the top and bottom nozzle plates of a fuel assembly. Sleeves enclosing control rod guide thimbles interconnect the top and bottom nozzle plates and the fuel assembly upper and lower spacer grid. Each sleeve is secured to the respective nozzle plate by retaining rings disposed on opposite sides. Should it be necessary to remove a fuel rod from the assembly, the retaining rings in either the top or bottom nozzles may be removed to release the nozzle from the control rod guide thimbles and thus expose either the top or bottom ends of the fuel rods to fuel rod removing mechanisms. (author)

  17. Magnetic signature surveillance of nuclear fuel

    International Nuclear Information System (INIS)

    Bernatowicz, H.; Schoenig, F.C.

    1981-01-01

    Typical nuclear fuel material contains tramp ferromagnetic particles of random size and distribution. Also, selected amounts of paramagnetic or ferromagnetic material can be added at random or at known positions in the fuel material. The fuel material in its non-magnetic container is scanned along its length by magnetic susceptibility detecting apparatus whereby susceptibility changes along its length are obtained and provide a unique signal waveform of the container of fuel material as a signature thereof. The output signature is stored. At subsequent times in its life the container is again scanned and respective signatures obtained which are compared with the initially obtained signature, any differences indicating alteration or tampering with the fuel material. If the fuel material includes a paramagnetic additive by taking two measurements along the container the effects thereof can be cancelled out. (author)

  18. Nuclear fuel supply view in Argentina

    International Nuclear Information System (INIS)

    Cirimello, R.O.

    1997-01-01

    The Argentine Atomic Energy Commission promoted and participated in a unique achievement in the R and D system in Argentina: the integration of science technology and production based on a central core of knowledge for the control and management of the nuclear fuel cycle technology. CONUAR SA, as a fuel manufacturer, FAE SA, the manufacturer of Zircaloy tubes, CNEA and now DIOXITEC SA producer of Uranium Dioxide, have been supply, in the last ten years, the amount of products required for about 1300 Tn of equivalent U content in fuels. The most promising changes for the fuel cycle economy is the Slight Enriched Uranium project which begun in Atucha I reactor. In 1997 seventy five fuel assemblies, equivalent to 900 Candu fuel bundles, will complete its irradiation. (author)

  19. Panorama 2010: Nuclear fuel resources

    International Nuclear Information System (INIS)

    Gabriel, S.; Saniere, A.

    2010-01-01

    The abundance of projects to build nuclear power plants, the desire of new countries to acquire civil atomic power, contracts sometimes deemed fantastically high for the operation of uranium mines, etc. All of these signals indicate a return to nuclear power in a context dominated by the fight against global warming. But can nuclear power make a durable contribution to the effort to meet the ever-increasing demand for energy? (author)

  20. Burnup measuring method for nuclear fuel substances

    International Nuclear Information System (INIS)

    Kobayashi, Iwao.

    1979-01-01

    Purpose: To enable non-destructive measurement for the amounts of fissile nucleides contained in nuclear fuel substances by the use of the difference in neutron spectra. Method: Neutrons generated from a neutron source are irradiated to a nuclear fuel substance, the neutrons generated from the nuclear fission reactions in the nuclear fuel substance are identified as epithermal neutrons and the neutrons from the neutron source as thermal neutrons and only the epithermal neutrons are detected to thereby measure the amounts of fissile neucleides in the nuclear fuel substances. For example, a neutron source is provided movably on one side of fuel assemblies placed in water and a neutron detector is situated on the other side by way of gamma-ray shield made of lead. The neutron detector is covered with a thermal neutron-absorbing substance such as cadmium and boron at the outer circumference so that only the epithermal neutrons can permeate therethrough. A high sensitivity detector for thermal neutron are used for improving the detecting efficiency, and the epithermal neutrons are introduced into hydrogen-containing substances such as paraffins to be detected as thermal neutrons. (Kawakami, Y.)

  1. Density control method for nuclear fuel pellet

    International Nuclear Information System (INIS)

    Wataumi, Kazutoshi.

    1993-01-01

    In a density control for nuclear fuel pellets produced from a raw material powder containing dioxides of uranium or plutonium and oxides of rare earth elements, trimetal octoxides formed from dioxides or the raw material powder not undergoing thermal hysteresis at higher than 1,000degC are added to the raw material powder. Further, trimetal octoxides obtained by calcining a sintering product of the raw material powder is added in addition the trimetal octoxides of the elements. Furthermore, the density of the nuclear fuel pellet is controlled by two kinds of trimetal octoxides obtained by calcining the sintering products of the dioxides, the raw material powder or the nuclear fuel sintering materials at 350 to 800degC. Since trimetal octoxides powder derived from the raw material powder is used as a density increasing additive for the nuclear fuel pellets, it is advantageous in view of stable operation, different from a conventional method of controlling molding condition and sintering condition, and since the trimetal octoxides powder derived from the sintering product is also used, various kinds of density control for nuclear fuel pellets can be conducted. (N.H.)

  2. 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.)

  3. 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

  4. Prevention of nuclear fuel cladding materials corrosion

    International Nuclear Information System (INIS)

    Yang, K.R.; Yang, J.C.; Lee, I.C.; Kang, H.D.; Cho, S.W.; Whang, C.K.

    1983-01-01

    The only way which could be performed by the operator of nuclear power plant to minimizing the degradation of nuclear fuel cladding material is to control the water quality of primary coolant as specified standard conditions which dose not attack the cladding material. If the water quality of reactor coolant does not meet far from the specification, the failure will occure not only cladding material itself but construction material of primary system which contact with the coolant. The corrosion product of system material are circulate through the whole primary system with the coolant and activated by the neutron near the reactor core. The activated corrosion products and fission products which released from fuel rod to the coolant, so called crud, will repeate deposition and redeposition continuously on the fuel rod and construction material surface. As a result we should consider heat transfer problem. In this study following activities were performed; 1. The crud sample was taken from the spent fuel rod surface of Kori unit one and analized for radioactive element and non radioactive chemical species. 2. The failure mode of nuclear fuel cladding material was estimated by the investigation of releasing type of fission products from the fuel rod to the reactor coolant using the iodine isotopes concentration of reactor coolants. 3. A study was carried out on the sipping test results of spent fuel and a discussion was made on the water quality control records through the past three cycle operation period of Kori unit one plant. (Author)

  5. Influenza polymerase encoding mRNAs utilize atypical mRNA nuclear export.

    Science.gov (United States)

    Larsen, Sean; Bui, Steven; Perez, Veronica; Mohammad, Adeba; Medina-Ramirez, Hilario; Newcomb, Laura L

    2014-08-28

    Influenza is a segmented negative strand RNA virus. Each RNA segment is encapsulated by influenza nucleoprotein and bound by the viral RNA dependent RNA polymerase (RdRP) to form viral ribonucleoproteins responsible for RNA synthesis in the nucleus of the host cell. Influenza transcription results in spliced mRNAs (M2 and NS2), intron-containing mRNAs (M1 and NS1), and intron-less mRNAs (HA, NA, NP, PB1, PB2, and PA), all of which undergo nuclear export into the cytoplasm for translation. Most cellular mRNA nuclear export is Nxf1-mediated, while select mRNAs utilize Crm1. Here we inhibited Nxf1 and Crm1 nuclear export prior to infection with influenza A/Udorn/307/1972(H3N2) virus and analyzed influenza intron-less mRNAs using cellular fractionation and reverse transcription-quantitative polymerase chain reaction (RT-qPCR). We examined direct interaction between Nxf1 and influenza intron-less mRNAs using immuno purification of Nxf1 and RT-PCR of associated RNA. Inhibition of Nxf1 resulted in less influenza intron-less mRNA export into the cytoplasm for HA and NA influenza mRNAs in both human embryonic kidney cell line (293 T) and human lung adenocarcinoma epithelial cell line (A549). However, in 293 T cells no change was observed for mRNAs encoding the components of the viral ribonucleoproteins; NP, PA, PB1, and PB2, while in A549 cells, only PA, PB1, and PB2 mRNAs, encoding the RdRP, remained unaffected; NP mRNA was reduced in the cytoplasm. In A549 cells NP, NA, HA, mRNAs were found associated with Nxf1 but PA, PB1, and PB2 mRNAs were not. Crm1 inhibition also resulted in no significant difference in PA, PB1, and PB2 mRNA nuclear export. These results further confirm Nxf1-mediated nuclear export is functional during the influenza life cycle and hijacked for select influenza mRNA nuclear export. We reveal a cell type difference for Nxf1-mediated nuclear export of influenza NP mRNA, a reminder that cell type can influence molecular mechanisms. Importantly, we

  6. Transport of encapsulated nuclear fuels

    International Nuclear Information System (INIS)

    Broman, Ulrika; Dybeck, Peter; Ekendahl, Ann-Mari

    2005-12-01

    The transport system for encapsulated fuel is described, including a preliminary drawing of a transport container. In the report, the encapsulation plant is assumed to be located to Oskarshamn, and the repository to Oskarshamn or Forsmark

  7. MOLTEN FLUORIDE NUCLEAR REACTOR FUEL

    Science.gov (United States)

    Barton, C.J.; Grimes, W.R.

    1960-01-01

    Molten-salt reactor fuel compositions consisting of mixtures of fluoride salts are reported. In its broadest form, the composition contains an alkali fluoride such as sodium fluoride, zirconium tetrafluoride, and a uranium fluoride, the latter being the tetrafluoride or trifluoride or a mixture of the two. An outstanding property of these fuel compositions is a high coeffieient of thermal expansion which provides a negative temperature coefficient of reactivity in reactors in which they are used.

  8. Nuclear fuel sub-assemblies

    International Nuclear Information System (INIS)

    Dodd, J.A.; Butterfield, C.E.; Waite, E.

    1979-01-01

    A fast reactor fuel sub-assembly has honeycomb grids for laterally supporting the fuel pins. The grids are of two series and are arranged alternately along the bundle. The grids of a first series provide a discrete cell for each pin but the grids of the second series have a peripheral group of cells only. The grids of the second series provide intermediate support of the edge pins to restrain bow. (author)

  9. Uranium to Electricity: The Chemistry of the Nuclear Fuel Cycle

    Science.gov (United States)

    Settle, Frank A.

    2009-01-01

    The nuclear fuel cycle consists of a series of industrial processes that produce fuel for the production of electricity in nuclear reactors, use the fuel to generate electricity, and subsequently manage the spent reactor fuel. While the physics and engineering of controlled fission are central to the generation of nuclear power, chemistry…

  10. Costing of spent nuclear fuel storage

    International Nuclear Information System (INIS)

    2009-01-01

    This report deals with economic analysis and cost estimation, based on exploration of relevant issues, including a survey of analytical tools for assessment and updated information on the market and financial issues associated with spent fuel storage. The development of new storage technologies and changes in some of the circumstances affecting the costs of spent fuel storage are also incorporated. This report aims to provide comprehensive information on spent fuel storage costs to engineers and nuclear professionals as well as other stakeholders in the nuclear industry. This report is meant to provide informative guidance on economic aspects involved in selecting a spent fuel storage system, including basic methods of analysis and cost data for project evaluation and comparison of storage options, together with financial and business aspects associated with spent fuel storage. After the review of technical options for spent fuel storage in Section 2, cost categories and components involved in the lifecycle of a storage facility are identified in Section 3 and factors affecting costs of spent fuel storage are then reviewed in the Section 4. Methods for cost estimation and analysis are introduced in Section 5, and other financial and business aspects associated with spent fuel storage are discussed in Section 6.

  11. Drying of mock spent nuclear fuel elements

    Energy Technology Data Exchange (ETDEWEB)

    Crepeau, J.C.; Reese, S.; McIlroy, H.M. Jr. [Univ. of Idaho, Idaho Falls, ID (United States). Dept. of Mechanical Engineering; Lords, R.E. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States)

    1998-03-01

    Spent nuclear fuel elements are stored in underwater cooling pools until the elements can be safely handled and prepared for interim dry storage. The fuel was intended for short-term storage in water before it was to be reprocessed. However, the fuel will no longer be reprocessed, and extended storage in water has caused many of the aluminum-clad elements to degrade, exposing the uranium fuel. In addition, sludge, comprised of corroded aluminum and sediment, has accumulated in and around the fuel plates. The water in the sludge must be removed before the spent fuel elements can be placed in dry storage. Experiments have been performed on mock spent fuel elements with simulated corrosion product applied between the plates. A series of vacuum and heating cycles were used to dry the elements, and a mixture of clay and aluminum oxide was used to simulate corrosion products on the elements. The procedures used in the experiments were determined to be adequate to dry the mock spent fuel elements, and the temperature behavior of the simulated corrosion product within the fuel elements could be used to determine when the element was dry. On plates where areas of wet simulant were found, a sharp frying front was observed that separated the wet and dry parts of the simulated corrosion product. The drying front propagated inward towards the center of the mock fuel elements over time.

  12. Nuclear fuel assembly seismic amplitude limiter

    International Nuclear Information System (INIS)

    Anthony, A.J.

    1977-01-01

    The ability of a nuclear reactor to withstand high seismic loading is enhanced by including, on each fuel assembly, at least one seismic grid which reduces the magnitude of the possible lateral deflection of the individual fuel elements and the entire fuel assembly. The reduction in possible deflection minimizes the possibility of impact of the spacer grids of one fuel assembly on those of an adjacent fuel assembly and reduces the magnitude of forces associated with any such impact thereby minimizing the possibility of fuel assembly damage as a result of high seismic loading. The seismic grid is mounted from the fuel assembly guide tubes, has greater external dimensions when compared to the fuel assembly spacer grids and normally does not support or otherwise contact the fuel elements. The reduction in possible deflection is achieved through reduction of the clearance between adjacent fuel assemblies made possible by the use in the seismic grid of a high strength material characterized by favorable thermal expansion characteristics and minimal irradiation induced expansion

  13. Establishment of China Nuclear Fuel Assembly Database

    International Nuclear Information System (INIS)

    Chen Peng; Jin Yongli; Zhang Yingchao; Lu Huaquan; Chen Jianxin

    2009-01-01

    China Nuclear Fuel Assembly Database (CNFAD) is developed based on Oracle system. It contains the information of fuel assemblies in the stages of its design, fabrication and post irradiation (PIE). The structure of Browser Sever is adopted in the development of the software, which supports the HTTP protocol. It uses Java interface to transfer the codes from server to clients and make the sources of server and clients be utilized reasonably and sufficiently, so it can perform complicated tasks. Data in various stages of the fuel assemblies in Pressure Water Reactor (PWR), such as the design,fabrication, operation, and post irradiation examination, can be stored in this database. Data can be shared by multi users and communicated within long distances. By using CNFAD, the problem of decentralization of fuel data in China nuclear power plants will be solved. (authors)

  14. Transparency associated with the nuclear fuel cycle

    International Nuclear Information System (INIS)

    2009-01-01

    The author first recalls that the French nuclear industry works within the frame defined by international treaties and laws which ensure rigor and transparency. He gives some explanations for the resorting to Russian installations and for reprocessed uranium recycling (among them: supply security for the French nuclear industry, strategy of complete use of uranium energetic potential). Then, he outlines how the French State must further improve transparency and pedagogy about radioactive waste and material management. A technical appendix is provided, describing the fuel cycle (natural uranium extraction, conversion and enrichment, fuel fabrication, irradiation, used fuel processing, reprocessed uranium recycling, plutonium recycling in MOX, waste storage), giving an overview of the international supply context (concurrence and security needs), discussing valorization perspectives for materials which are not used in the current fuel cycle, describing the various aspects of radioactive waste management for the various types of wastes (long life, low or high activity for example), describing the control performed by public authorities and organisations

  15. International Nuclear Fuel Cycle Fact Book

    International Nuclear Information System (INIS)

    Leigh, I.W.; Mitchell, S.J.

    1990-01-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information

  16. Manufacturing method for nuclear fuel pellet

    International Nuclear Information System (INIS)

    Komono, Akira

    1998-01-01

    Upon molding of nuclear fuel pellets, the supply of nuclear fuel powder to a dice is divided to a plurality of stages, and a nuclear fuel powder having higher moldability is supplied to a portion where the density of the powder in the molded product is lower. As a result, the density of the powder of the molded product after molding can be made substantially uniform even in a portion where the molding pressure is low and the density of the powder of the molded product is low. Accordingly, difference of the diameter caused depending on the portion of the pellet after sintering is prevented, so that pellets having substantially uniform diameter can be formed, and the specification of the design can be satisfied. If dice agreed with the aimed diameter is selected based on the degree of shrinkage, a grinding step for making the diameter uniform can be eliminated to attain cost down. (N.H.)

  17. International Nuclear Fuel Cycle Fact Book

    Energy Technology Data Exchange (ETDEWEB)

    Leigh, I.W.

    1992-05-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

  18. International nuclear fuel cycle fact book

    International Nuclear Information System (INIS)

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

    1987-01-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is a consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users

  19. International nuclear fuel cycle fact book

    International Nuclear Information System (INIS)

    Leigh, I.W.

    1988-01-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source or information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users

  20. International nuclear fuel cycle fact book

    Energy Technology Data Exchange (ETDEWEB)

    Leigh, I.W.

    1988-01-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source or information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

  1. International Nuclear Fuel Cycle Fact Book

    Energy Technology Data Exchange (ETDEWEB)

    Leigh, I W; Mitchell, S J

    1990-01-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information.

  2. Intelligent Automated Nuclear Fuel Pellet Inspection System

    International Nuclear Information System (INIS)

    Keyvan, S.

    1999-01-01

    At the present time, nuclear pellet inspection is performed manually using naked eyes for judgment and decisionmaking on accepting or rejecting pellets. This current practice of pellet inspection is tedious and subject to inconsistencies and error. Furthermore, unnecessary re-fabrication of pellets is costly and the presence of low quality pellets in a fuel assembly is unacceptable. To improve the quality control in nuclear fuel fabrication plants, an automated pellet inspection system based on advanced techniques is needed. Such a system addresses the following concerns of the current manual inspection method: (1) the reliability of inspection due to typical human errors, (2) radiation exposure to the workers, and (3) speed of inspection and its economical impact. The goal of this research is to develop an automated nuclear fuel pellet inspection system which is based on pellet video (photographic) images and uses artificial intelligence techniques

  3. International Nuclear Fuel Cycle Fact Book

    International Nuclear Information System (INIS)

    Leigh, I.W.

    1992-05-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information

  4. NESbase version 1.0: a database of nuclear export signals

    DEFF Research Database (Denmark)

    la Cour, T.; Gupta, Ramneek; Rapacki, Krzysztof

    2003-01-01

    Protein export from the nucleus is often mediated by a Leucine-rich Nuclear Export Signal (NES). NESbase is a database of experimentally validated Leucine-rich NESs curated from literature. These signals are not annotated in databases such as SWISS-PROT, PIR or PROSITE. Each NESbase entry contains...... information of whether NES was shown to be necessary and/or sufficient for export, and whether the export was shown to be mediated by the export receptor CRM1. The compiled information was used to make a sequence logo of the Leucine-rich NESs, displaying the conservation of amino acids within a window of 25...... residues. Surprisingly, only 36% of the sequences used for the logo fit the widely accepted NES consensus L-x( 2,3) -[ LIVFM] x( 2,3) - L-x-[ LI]. The database is available online at http: / / www. cbs. dtu. dk/ databases/ NESbase/....

  5. Spent nuclear fuel project integrated schedule plan

    International Nuclear Information System (INIS)

    Squires, K.G.

    1995-01-01

    The Spent Nuclear Fuel Integrated Schedule Plan establishes the organizational responsibilities, rules for developing, maintain and status of the SNF integrated schedule, and an implementation plan for the integrated schedule. The mission of the SNFP on the Hanford site is to provide safe, economic, environmentally sound management of Hanford SNF in a manner which stages it to final disposition. This particularly involves K Basin fuel

  6. Prospects for the French nuclear fuel management

    International Nuclear Information System (INIS)

    Presta, M.; Guiheux, J.M.

    1990-01-01

    In France, the present share of nuclear electricity generation is about 70 percent. In order to reduce fuel costs, EDF, the French utility, is dedicated to improve the management of the reloads for the 50 reactors it has to manage. Several decisions are now on the way. They affect the adjustment of the reloads to the situation of electricity consumption, the development of higher burn-up fuels and 1/4 reloads, and the recycling of reprocessing materials. It results that some new features in the management of the fuel cycle have been developed. That is why, COGEMA and other French fuel cycle companies have prepared some new processes to bring new solutions to the utility needs. First, new flexibilities have been created in the enrichment and fabrication management system in order to procure assemblies to EDF according to its needs with both right enrichment levels and fuel capabilities. Second, the recycling of reprocessing materials has been largely studied and large industrial facilities are now either operating or planned: they deal with conversions in UREP plants, enrichment of reprocessed uranium in EURODIF or by laser process, fabrication for REPU fuels by FRAGEMA or for MOX fuels by COMMOX. COGEMA relies on its experience acquired during the large French nuclear program development that let the company to adapt flexibly to the various EDF fuel management improvements. With this background, COGEMA offers services to foreign customers as well. With all these new features, the French nuclear system is now on a good way to ensure a good transition from the phase of building and development to a phase of sophisticated management and optimized use of French nuclear industrial facilities in the next 20 years. (author). 3 figs

  7. Nuclear reactor fuel replacement system

    International Nuclear Information System (INIS)

    Kayano, Hiroyuki; Joge, Toshio.

    1976-01-01

    Object: To permit the direction in which a fuel replacement unit is moving to be monitored by the operator. Structure: When a fuel replacement unit approaches an intermediate goal position preset in the path of movement, renewal of data display on a goal position indicator is made every time the goal position is changed. With this renewal, the prevailing direction of movement of the fuel replacement unit can be monitored by the operator. When the control of movement is initiated, the co-ordinates of the intermediate goal point A are displayed on a goal position indicator. When the replacement unit reaches point A, the co-ordinates of the next intermediate point B are displayed, and upon reaching point B the co-ordinates of the (last) goal point C are displayed. (Nakamura, S.)

  8. Storing the world's spent nuclear fuel

    International Nuclear Information System (INIS)

    Barkenbus, J.N.; Weinberg, A.M.; Alonso, M.

    1985-01-01

    Given the world's prodigious future energy requirements and the inevitable depletion of oil and gas, it would be foolhardy consciously to seek limitations on the growth of nuclear power. Indeed, the authors continue to believe that the global nuclear power enterprise, as measured by installed reactor capacity, can become much larger in the future without increasing proliferation risks. To accomplish this objective will require renewed dedication to the non-proliferation regime, and it will require some new initiatives. Foremost among these would be the establishment of a spent fuel take-back service, in which one or a few states would retrieve spent nuclear fuel from nations generating it. The centralized retrieval of spent fuel would remove accessible plutonium from the control of national leaders in non-nuclear-weapons states, thereby eliminating the temptation to use this material for weapons. The Soviets already implement a retrieval policy with the spent fuel generated by East European allies. The authors believe that it is time for the US to reopen the issue of spent-fuel retrieval, and thus to strengthen its non-proliferation policies and the nonproliferation regime in general. 7 references

  9. 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

  10. Nuclear fuel elements made from nanophase materials

    Science.gov (United States)

    Heubeck, Norman B.

    1998-01-01

    A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000.degree. F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics.

  11. Long island to Limerick, nuclear fuel transfer

    International Nuclear Information System (INIS)

    Jones, Bill

    1999-01-01

    The issue described is: how to move 33 shipments of radioactive nuclear fuel - 200 tons of enriched uranium pellets - on rail cars through the heart of Philadelphia, without upsetting politicians, the media and anti-nuclear activists, after a similar plan to move the fuel through New York City had been rejected in a political disaster. The answer to this is: Strategic Communications Planning. At PECO Energy's department of Corporate and Public Affairs, the research is quite clear that in risk management situations like this, the side that gets out front with the most credible information inevitably wins. That is exactly what was set out to do

  12. Nuclear fuel waste disposal in Canada

    International Nuclear Information System (INIS)

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

    1990-05-01

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

  13. World nuclear fuel market. Seventeenth annual meeting

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The papers presented at the seventeenth World Nuclear Fuels Market meeting are cataloged individually. This volume includes information on the following areas of interest: historical and current aspects of the uranium and plutonium market with respect to supply and demand, pricing, spot market purchasing, and other market phenomena; impact of reprocessing and recycling uranium, plutonium, and mixed oxide fuels; role of individual countries in the market: Hungary, Germany, the Soviet Union, Czechoslovakia, France, and the US; the impact of public opinion and radioactive waste management on the nuclear industry, and a debate regarding long term versus short term contracting by electric utilities for uranium and enrichment services

  14. Financing of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Wyart, P.

    1975-01-01

    Fuels account for only a modest share of the cost of nuclear energy: approximatively one-fourth whereas the capital financing charges exceed one-half. But it is necessary to take account of the combined effect of the magnitude of the needs in coming years and of the resulting acceleration due to the coming on stream of increasingly numerous nuclear power plants and to take account of the characteristics of the fuel cycle which is especially long because of technical requirements and the necessity to establish safety stocks [fr

  15. Country nuclear fuel cycle profile: Spain

    International Nuclear Information System (INIS)

    2005-01-01

    Spain has nine nuclear power plants in operation at seven sites. At the end of 2002 the capacity of the plants totalled 7.9 GW(e). In 2002 their electricity production amounted to 60.28 TW·h, equivalent to 26% of national electricity production. The country currently has no plans to add further nuclear generating capacity. Spain has not yet decided about its nuclear fuel cycle policy. ENUSA Industrias Avanzadas, S.A. provides products and services related to the front end of the nuclear fuel cycle. ENUSA had been exploiting an open pit uranium mine at Saelices el Chico (Salamanca). Owing to the low market price of uranium, the mine cannot be exploited economically and mining activities were stopped at the end of 2000. At the mine site ENUSA has the Quercus plant which began producing uranium concentrates in 1993. In 2001 and 2002 the plant worked at a low production level treating mine water. At the end of 2002 ENUSA terminated the plant's production activities. There is no domestic conversion. In 2002 ENUSA managed and supplied 1325 t U in conversion services to Spanish nuclear power plants. There is no domestic enrichment. In 2002 ENUSA managed and supplied 799 t SWU in enrichment services to Spanish nuclear power plants. ENUSA operates a fuel fabrication facility for BWR, PWR and WWER reactors at Juzbado (Salamanca). The design capacity of this facility is 400 t U/a of fuel elements. The Fifth Radioactive Waste Plan governs the policy regarding spent fuel management. The spent fuel is stored in each nuclear power plant pool. In addition, a temporary storage facility was started up at the Trillo nuclear power plant in 2002 which houses spent fuel from the plant in dual purpose casks. After 2010 it is envisaged that a centralized temporary storage facility will exist. No decision will be taken prior to 2010 with respect to the final disposal of spent fuel. Until then it will be necessary to undertake two lines of research, one that considers a deep geological

  16. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

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

    1983-05-01

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

  17. Nuclear fuel rod end plug weld inspection

    International Nuclear Information System (INIS)

    Parker, M. A.; Patrick, S. S.; Rice, G. F.

    1985-01-01

    Apparatus and method for testing TIG (tungsten inert gas) welds of end plugs on a sealed nuclear reactor fuel rod. An X-ray fluorescent spectrograph testing unit detects tungsten inclusion weld defects in the top end plug's seal weld. Separate ultrasonic weld inspection system testing units test the top end plug's seal and girth welds and test the bottom end plug's girth weld for penetration, porosity and wall thinning defects. The nuclear fuel rod is automatically moved into and out from each testing unit and is automatically transported between the testing units by rod handling devices. A controller supervises the operation of the testing units and the rod handling devices

  18. Reference Neutron Radiographs of Nuclear Reactor Fuel

    DEFF Research Database (Denmark)

    Domanus, Joseph Czeslaw

    1986-01-01

    Reference neutron radiographs of nuclear reactor fuel were produced by the Euraton Neutron Radiography Working Group and published in 1984 by the Reidel Publishing Company. In this collection a classification is given of the various neutron radiographic findings, that can occur in different parts...... of pelletized, annular and vibro-conpacted nuclear fuel pins. Those parts of the pins are shown where changes of appearance differ from those for the parts as fabricated. Also radiographs of those as fabricated parts are included. The collection contains 158 neutron radiographs, reproduced on photographic paper...... (twice enlarged) and on duplicating film (original size)....

  19. Nuclear fuel performance evaluation. Final report

    International Nuclear Information System (INIS)

    Boerresen, S.; Pomeroy, D.L.; Rolstad, E.; Sauar, T.O.

    1977-06-01

    An evaluation has been made of the ability of Scandpower's empirical fuel performance model POSHO (''Power Shock'') to predict the probability of fuel pin failures resulting from pellet-clad interaction in commercial nuclear power plants. POSHO provides an analytical method to calculate the failure probabilities associated with power level maneuvers for different fuel assembly designs. Application of the method provides a basis for risk-benefit decisions concerning operational procedures, fuel designs and fuel management strategies. One boiling water reactor (BWR) and one pressurized water reactor (PWR) were selected for study to compare model predictions with actual failures, as determined from post irradiation examination of the fuel and activity release data. The fuel duty cycles were reconstructed from operating records and nodal power histories were created by using Scandpower's FMS computer programs. Nodal power histories, coupled with the relative pin power distribution in each node, were processed by the fuel failure prediction model, which tracks the interaction power level for each pin group in each node and calculates the power shocks and the probability for pellet-clad interaction cracks. The results of these calculations are processed statistically to give the expected number of cracks, the number of failed fuel pins in each assembly and the total number of failed assemblies in the core. Fuel performance in the BWR, Quad Cities Unit Two, was calculated by the model in approximate agreement with the observed performance. Fuel performance in the PWR, Maine Yankee, was calculated in approximate agreement for two of the three fuel designs. The high failure rate in the third design, Type B fuel, was not calculated by the POSHO pellet-clad interaction model

  20. Nuclear fuel technology - Administrative criteria related to nuclear criticality safety

    International Nuclear Information System (INIS)

    2004-01-01

    An effective nuclear criticality-safety programme includes cooperation among management, supervision, and the nuclear criticality-safety staff and, for each employee, relies upon conformance with operating procedures. Although the extent and complexity of safety-related activities may vary greatly with the size and type of operation with fissile material, certain safety elements are common. This International Standard represents a codification of such elements related to nuclear criticality safety. General guidance for nuclear criticality safety may be found in ISO 1709. The responsibilities of management, supervision, and the nuclear criticality-safety staff are addressed. The Objectives and characteristics of operating and emergency procedures are included in this International Standard. ISO 14943 was prepared by Technical Committee ISO/TC 85, Nuclear energy, Subcommittee SC 5, Nuclear fuel technology

  1. Shipping container for nuclear fuels

    International Nuclear Information System (INIS)

    Housholder, W.R.; Greer, N.L.

    1976-01-01

    A container for nuclear materials is described wherein a specially and uniquely constructed pressure vessel and gamma shield assembly for holding the nuclear materials is provided in a housing, and wherein a positioning means extends between the housing and the assembly for spacing the same, insulation in the housing essentially filling the space between the assembly and housing, the insulation comprising beads, globules or the like of water encapsulated in plastic and which, in one important embodiment, contains neutron absorbing matter

  2. Kraftwerk Union (KWU) nuclear fuel service

    International Nuclear Information System (INIS)

    Knaab, H.; Knecht, K.; Garzarolli, F.

    1977-01-01

    Activities started with the commissioning of the first German nuclear power stations have led to the present form of the nuclear fuel customer service. In the meantime, based on these tasks numerous test and working methods were developed and applied which are now available to operators of nuclear power station. The paper describes the most important methods and instruments and surveys the nuclear fuel service tasks carriedout to date. Past experience has shown that detailed knowledge of design, fabrication as well as the possibility to compose observations with investigations of engineering and hot cell laboratories are prerequisites for successful service performance. The expected trend towards increasing frequency of service activities in the next few years must be taken into account by a continuous expansion in the number of the qualified personnel. It will become necessary for the coordination of the work at an increasing number of reactor plants to conclude long-term service agreements with the customer. (orig.) [de

  3. Nuclear fuel storage apparatus for seismic areas

    International Nuclear Information System (INIS)

    Anthony, A.J.

    1981-01-01

    An earthquake resistant apparatus is claimed for storing nuclear fuel within a water-filled pool wherein a structural grid which supports the fuel is in turn supported by cables from an upper elevation. The grid is located below the water level and spaced from the walls of the pool an amount, preferably at least equal to the anticipated earthquake displacement. The grid is located below the water level a sufficient depth for radiation shielding during fuel handling and storage, and tension members are preferably ten times the design earthquake displacement. A horizontal baffle is located around the periphery of the pool at an elevation above the grid

  4. Nuclear fuel assembly identification using computer vision

    International Nuclear Information System (INIS)

    Moffett, S.D.

    1985-01-01

    This report describes an improved method of remotely identifying irradiated nuclear fuel assemblies. The method uses existing in-cell TV cameras to input an image of the notch-coded top of the fuel assemblies into a computer vision system, which then produces the identifying number for that assembly. This system replaces systems that use either a mechanical mechanism to feel the notches or use human operators to locate notches visually. The system was developed for identifying fuel assemblies from the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor, but could be used for other reactor assembly identification, as appropriate

  5. Characteristics of spent nuclear fuel

    International Nuclear Information System (INIS)

    Notz, K.J.

    1988-04-01

    The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the spent fuels and other wastes that will, or may, eventually be disposed of in a geological repository. The two major sources of these materials are commercial light-water reactor (LWR) spent fuel and immobilized high-level waste (HLW). Other wastes that may require long-term isolation include non-LWR spent fuels and miscellaneous sources such as activated metals. This report deals with spent fuels, but for completeness, the other sources are described briefly. Detailed characterizations are required for all of these potential repository wastes. These characteristics include physical, chemical, and radiological properties. The latter must take into account decay as a function of time. In addition, the present inventories and projected quantities of the various wastes are needed. This information has been assembled in a Characteristics Data Base which provides data in four formats: hard copy standard reports, menu-driven personal computer (PC) data bases, program-level PC data bases, and mainframe computer files. 5 refs., 3 figs., 4 tabs

  6. Locking support for nuclear fuel assemblies

    Science.gov (United States)

    Ledin, Eric

    1980-01-01

    A locking device for supporting and locking a nuclear fuel assembly within a cylindrical bore formed by a support plate, the locking device including a support and locking sleeve having upwardly extending fingers forming wedge shaped contact portions arranged for interaction between an annular tapered surface on the fuel assembly and the support plate bore as well as downwardly extending fingers having wedge shaped contact portions arranged for interaction between an annularly tapered surface on the support plate bore and the fuel assembly whereby the sleeve tends to support and lock the fuel assembly in place within the bore by its own weight while facilitating removal and/or replacement of the fuel assembly.

  7. Nuclear fuel fabrication - developing indigenous capability

    International Nuclear Information System (INIS)

    Gupta, U.C.; Jayaraj, R.N.; Meena, R.; Sastry, V.S.; Radhakrishna, C.; Rao, S.M.; Sinha, K.K.

    1997-01-01

    Nuclear Fuel Complex (NFC), established in early 70's for production of fuel for PHWRs and BWRs in India, has made several improvements in different areas of fuel manufacturing. Starting with wire-wrap type of fuel bundles, NFC had switched over to split spacer type fuel bundle production in mid 80's. On the upstream side slurry extraction was introduced to prepare the pure uranyl nitrate solution directly from the MDU cake. Applying a thin layer of graphite to the inside of the tube was another modification. The Complex has developed cost effective and innovative techniques for these processes, especially for resistance welding of appendages on the fuel elements which has been a unique feature of the Indian PHWR fuel assemblies. Initially, the fuel fabrication plants were set-up with imported process equipment for most of the pelletisation and assembly operations. Gradually with design and development of indigenous equipment both for production and quality control, NFC has demonstrated total self reliance in fuel production by getting these special purpose machines manufactured indigenously. With the expertise gained in different areas of process development and equipment manufacturing, today NFC is in a position to offer know-how and process equipment at very attractive prices. The paper discusses some of the new processes that are developed/introduced in this field and describes different features of a few PLC based automatic equipment developed. Salient features of innovative techniques being adopted in the area Of UO 2 powder production are also briefly indicated. (author)

  8. Computer-assisted nuclear fuel manufacture

    International Nuclear Information System (INIS)

    Maloney, J.P.; Schaumann, S.M.; Stone, E.

    1976-01-01

    At the ERDA Savannah River Plant, a process monitor, which incorporates an online digital computer, assists in manufacturing fuel elements used to produce nuclides such as plutonium, tritium, and californium in the plant's nuclear reactors. Also, inventory functions assist in safeguarding fissile material and protecting against accidental nuclear criticality. Terminals at strategic locations throughout the process area enable production operators to send and receive instructions and information on each manufacturing step

  9. Options contracts in the nuclear fuel industry

    International Nuclear Information System (INIS)

    Fuller, D.M.

    1995-01-01

    This article discusses options trading in the nuclear fuels industry. Although there now exists no formal options market in the nuclear industry, flexibilities, or embedded options, are actually quite common in the long-term supply contracts. The value of these flexibilities can be estimated by applying the methods used to evaluate options. The method used is the Black-Scholes Model, and it is applied to a number of examples

  10. International trade in nuclear fuel cycle services

    International Nuclear Information System (INIS)

    May, D.

    1989-01-01

    This paper analyses and discusses general trends in international trade in nuclear fuel cycle services with particular emphasis on the development of trading patterns between Europe, North America and the Far East. The paper also examines the role of collaborative ventures in the development of the nuclear industry. Barriers to international trade, the effect of government regulations and restrictions and the impact of non-proliferation issues are discussed. (author)

  11. 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)

  12. 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)

  13. 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)

  14. Nuclear Fuels & Materials Spotlight Volume 5

    Energy Technology Data Exchange (ETDEWEB)

    Petti, David Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-10-01

    As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • Evaluation and modeling of light water reactor accident tolerant fuel concepts • Status and results of recent TRISO-coated particle fuel irradiations, post-irradiation examinations, high-temperature safety testing to demonstrate the accident performance of this fuel system, and advanced microscopy to improve the understanding of fission product transport in this fuel system. • Improvements in and applications of meso and engineering scale modeling of light water reactor fuel behavior under a range of operating conditions and postulated accidents (e.g., power ramping, loss of coolant accident, and reactivity initiated accidents) using the MARMOT and BISON codes. • Novel measurements of the properties of nuclear (actinide) materials under extreme conditions, (e.g. high pressure, low/high temperatures, high magnetic field) to improve the scientific understanding of these materials. • Modeling reactor pressure vessel behavior using the GRIZZLY code. • New methods using sound to sense temperature inside a reactor core. • Improved experimental capabilities to study the response of fusion reactor materials to a tritium plasma. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at Idaho National Laboratory, and hope that you find this issue informative.

  15. Romania, producer and consumer of nuclear fuel

    International Nuclear Information System (INIS)

    Iuhas, Tiberius

    1998-01-01

    A historical sketch of the activity of Romanian Rare Metals Enterprises is presented stressing the valorization of rare metals like: - radioactive metals, uranium and thorium; - dispersed rare metals, molybdenum, monazite; - heavy and refractory metals, titanium and zirconium; rare earths, lanthanides and yttrics. The beginning and developing of research in the nuclear field is in closed relation to the existence on the domestic territory of important uranium ores the mining of which begun early in 1954. The exploitation of Baita-Bihor orebody was followed by that at Ciudanovita, Natra and Dobrei ores in Caras-Severin county. Concomitantly with the ore mining, geological research was developed covering vast areas of country's surface and using advanced investigation tools suitable for increasing depths. The next step in the nuclear fuel program was made by building a uranium concentrate (as ammonium or sodium diuranate) plant. Two purification units for processing the uranium concentrate to sintered uranium dioxide powder were completed and commissioned at Feldioara in 1986. The quality of the uranium dioxide product meets the quality standards requirements for CANDU type nuclear fuel as certified in 1994. Currently, part of the fuel load of Cernavoda reactor is fuel element clusters produced by Nuclear Fuel Plant at Pitesti of sintered powder processed at Feldioara. A list of strategic objectives of the Uranium National Company is presented among which: - maintaining the uranium mining and milling activities in close relation with the fuel requirements of Cernavoda NPP; continuing geological research in promising zones, to find new uranium orebodies, easy to mill cost effectively; decreasing the environmental impact in the geological research areas, in mining and transport affected areas and in the processing plants. The fuel demand of current operation of Cernavoda NPP Unit 1 as well as of future Unit 2 after commissioning are and will be satisfied by the

  16. Australia and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Alder, K; Australian Atomic Energy Commission, Lucas Heights; Reynolds, J.; Western Mining Corporation, Western Australia

    2010-01-01

    The nuclear electricity industry based on uranium fuel is now well established in 31 countries. Nuclear's ability to provide large scale base load power at costs competitive with available and politically favoured alternatives is causing it to be increasingly selected for new capacity. The World Nuclear Association data shows that current new construction together with that planned and proposed as of December 2009, will bring world nuclear electricity generating capacity from the present 373 000 MW to 876 000 MWm an increase of 112 per cent. By comparison Australia's total generating capacity (mainly from coal) is 47 000 MW, or one eighth of existing world nuclear capacity. Nuclear growth can be expected to increase further, due to continuing world-wide energy supply security issues and politically driven climate change concerns. Australia has been mining uranium for 60 eventful years, much influenced by government policy changes. Australia's un-mined resources are now the largest in the world and it is already a major supplier to the nuclear fueld cycle, in a growing market. This situation offers long term opportunities for Australia to benefit more fully and at the same time contribute to global security by further participation in the uranium-based nuclear electricity industry fuel cycle

  17. Logistics of nuclear fuel production for nuclear submarines

    International Nuclear Information System (INIS)

    Guimaraes, Leonam dos Santos

    2000-01-01

    The future acquisition of nuclear attack submarines by Brazilian Navy along next century will imply new requirements on Naval Logistic Support System. These needs will impact all the six logistic functions. Among them, fuel supply could be considered as the one which requires the most important capacitating effort, including not only technological development of processes but also the development of a national industrial basis for effective production of nuclear fuel. This paper presents the technical aspects of the processes involved and an annual production dimensioning for an squadron composed by four units. (author)

  18. Nuclear fuel waste policy in Canada

    International Nuclear Information System (INIS)

    Brown, P.A.; Letourneau, C.

    1999-01-01

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

  19. Nuclear fuel element end fitting

    International Nuclear Information System (INIS)

    Jabsen, F.S.

    1980-01-01

    An invention is described whereby end fittings are formed from lattices of mutually perpendicular plates. At the plate intersections, sockets are secured to the end fittings in a manner that permits the longitudinal axes of each of the sockets to align with the respective lines of intersection of the plates. The sockets all protrude above one of the surfaces of the end fitting. Further, a detent is formed in the proturding sides of each of the sockets. Annular grooves are formed in each of the ends of the fuel rods that are to be mounted between the end fittings. The socket detents protrude into the respective annular grooves, thus engaging the grooves and retaining the fuel rods and end fittings in one integral structure. (auth)

  20. Method of cleaning nuclear fuels

    International Nuclear Information System (INIS)

    Yanai, Ryoichi; Terai, Kenji.

    1983-01-01

    Purpose: To remove cladding without increasing the volume of a cleaning apparatus. Constitution: A discharge port is provided to a cleaning vessel for containing fuels and a filter is connected to the discharge port by way of a pressure-reduction valve and a water feeder. Further, a communication port is provided to the bottom of the cleaning vessel and a pressurizer equipped with an electrical heater connected to the communication port by way of an air valve and a communication pipeway. Then, after filling water within the vessel, the pressurizer and the communication pipe and closing the pressure-reduction valve, water is heated by a heater. Subsequently, by closing the air valve and opening the pressure-reduction valve, water in the vessel violently boils under a reduction pressure to strip claddings from the surface of fuel rods and release the same into the water due to impact shocks resulted from the generation of gas bubbles. (Sekiya, J.)

  1. 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

  2. Nuclear Energy and Synthetic Liquid Transportation Fuels

    Science.gov (United States)

    McDonald, Richard

    2012-10-01

    This talk will propose a plan to combine nuclear reactors with the Fischer-Tropsch (F-T) process to produce synthetic carbon-neutral liquid transportation fuels from sea water. These fuels can be formed from the hydrogen and carbon dioxide in sea water and will burn to water and carbon dioxide in a cycle powered by nuclear reactors. The F-T process was developed nearly 100 years ago as a method of synthesizing liquid fuels from coal. This process presently provides commercial liquid fuels in South Africa, Malaysia, and Qatar, mainly using natural gas as a feedstock. Nuclear energy can be used to separate water into hydrogen and oxygen as well as to extract carbon dioxide from sea water using ion exchange technology. The carbon dioxide and hydrogen react to form synthesis gas, the mixture needed at the beginning of the F-T process. Following further refining, the products, typically diesel and Jet-A, can use existing infrastructure and can power conventional engines with little or no modification. We can then use these carbon-neutral liquid fuels conveniently long into the future with few adverse environmental impacts.

  3. British Nuclear Fuels - a dirty business

    International Nuclear Information System (INIS)

    Bunyard, P.

    1983-01-01

    The radioactive discharges from British Nuclear Fuels Sellafield, Cumbria, reprocessing plant to the sea are discussed. Statements that have been made by various individuals and groups about the contamination of the sea, the coast and places inland, and the biological effects of plutonium and americium, are discussed in detail. Particular stress is placed on statements about increased incidence of cancers. (U.K.)

  4. Inspecting fuel pellets for nuclear reactor

    International Nuclear Information System (INIS)

    Wilks, R.S.; Sternheim, E.; Breakey, G.A.; Sturges, R.H.; Taleff, A.; Castner, R.P.

    1982-01-01

    An improved method of controlling the inspection, sorting and classifying of nuclear reactor fuel pellets, including a mechanical handling system and a computer controlled data processing system, is described. Having investigated the diameter, length, surface flaws and weights of the pellets, they are sorted accordingly and the relevant data are stored. (U.K.)

  5. Manufacturing process for improved nuclear fuel tablets

    International Nuclear Information System (INIS)

    Flipot, A.J.; Smolders, A.

    1976-01-01

    A process is described for manufacturing improved nuclear fuel pellets, including compacting ceramic powder in the compaction chamber of a pelletizing machine with only the lower punch moving on compaction, wherein the walls of the compaction chamber are widened on at least part of their height in the direction of a diameter increase toward the die-bearing table. 3 claims, 6 drawing figures

  6. Spent nuclear fuel project product specification

    International Nuclear Information System (INIS)

    PAJUNEN, A.L.

    1999-01-01

    This document establishes the limits and controls for the significant parameters that could potentially affect the safety and/or quality of the Spent Nuclear Fuel (SNF) packaged for processing, transport, and storage. The product specifications in this document cover the SNF packaged in Multi-Canister Overpacks to be transported throughout the SNF Project

  7. Nuclear Fuel Cycle System Analysis (II)

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-04-15

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

  8. Transport and storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Lung, M.; Lenail, B.

    1987-01-01

    From a safety standpoint, spent fuel is clearly not ideal for permanent disposal and reprocessing is the best method of preparing wastes for long-term storage in a repository. Furthermore, the future may demonstrate that some fission products recovered in reprocessing have economic applications. Many countries have in fact reached the point at which the recycling of plutonium and uranium from spent fuel is economical in LWR's. Even in countries where this is not yet evident, (i.e., the United States), the French example shows that the day will come when spent fuel will be retrieved for reprocessing and recycle. It is highly questionable whether spent fuel will ever be considered and treated as waste in the same sense as fission products and processed as such, i.e., packaged in a waste form for permanent disposal. Even when recycled fuel material can no longer be reused in LWR's because of poor reactivity, it will be usable in FBR's. Based on the considerable experience gained by SGN and Cogema, this paper has provided practical discussion and illustrations of spent fuel transport and storage of a very important step in the nuclear fuel management process. The best of spent fuel storage depends on technical, economic and policy considerations. Each design has a role to play and we hope that the above discussion will help clarify certain issues

  9. Method for inspecting nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Jabsen, F.S.

    1979-01-01

    A technique for disassembling a nuclear reactor fuel element without destroying the individual fuel pins and other structural components from which the element is assembled is described. A traveling bridge and trolley span a water-filled spent fuel storage pool and support a strongback. The strongback is under water and provides a working surface on which the spent fuel element is placed for inspection and for the manipulation that is associated with disassembly and assembly. To remove, in a non-destructive manner, the grids that hold the fuel pins in the proper relative positions within the element, bars are inserted through apertures in the grids with the aid of special tools. These bars are rotated to flex the adjacent grid walls and, in this way relax the physical engagement between protruding portions of the grid walls and the associated fuel pins. With the grid structure so flexed to relax the physical grip on the individual fuel pins, these pins can be withdrawn for inspection or replacement as necessary without imposing a need to destroy fuel element components

  10. Hormone-dependent nuclear export of estradiol receptor and DNA synthesis in breast cancer cells

    Science.gov (United States)

    Lombardi, Maria; Castoria, Gabriella; Migliaccio, Antimo; Barone, Maria Vittoria; Di Stasio, Rosina; Ciociola, Alessandra; Bottero, Daniela; Yamaguchi, Hiroshi; Appella, Ettore; Auricchio, Ferdinando

    2008-01-01

    In breast cancer cells, cytoplasmic localization of the estradiol receptor α (ERα) regulates estradiol-dependent S phase entry. We identified a nuclear export sequence (NES) in ERα and show that its export is dependent on both estradiol-mediated phosphatidylinositol-3-kinase (PI3K)/AKT activation and chromosome region maintenance 1 (CRM1). A Tat peptide containing the ERα NES disrupts ERα–CRM1 interaction and prevents nuclear export of ERα- and estradiol-induced DNA synthesis. NES-ERα mutants do not exit the nucleus and inhibit estradiol-induced S phase entry; ERα-dependent transcription is normal. ERα is associated with Forkhead proteins in the nucleus, and estradiol stimulates nuclear exit of both proteins. ERα knockdown or ERα NES mutations prevent ERα and Forkhead nuclear export. A mutant of forkhead in rhabdomyosarcoma (FKHR), which cannot be phosphorylated by estradiol-activated AKT, does not associate with ERα and is trapped in the nucleus, blocking S phase entry. In conclusion, estradiol-induced AKT-dependent phosphorylation of FKHR drives its association with ERα, thereby triggering complex export from the nucleus necessary for initiation of DNA synthesis and S phase entry. PMID:18644889

  11. Three-Dimensional Mapping of mRNA Export through the Nuclear Pore Complex

    Directory of Open Access Journals (Sweden)

    Steven J. Schnell

    2014-11-01

    Full Text Available The locations of transcription and translation of mRNA in eukaryotic cells are spatially separated by the nuclear envelope (NE. Plenty of nuclear pore complexes (NPCs embedded in the NE function as the major gateway for the export of transcribed mRNAs from the nucleus to the cytoplasm. Whereas the NPC, perhaps one of the largest protein complexes, provides a relatively large channel for macromolecules to selectively pass through it in inherently three-dimensional (3D movements, this channel is nonetheless below the diffraction limit of conventional light microscopy. A full understanding of the mRNA export mechanism urgently requires real-time mapping of the 3D dynamics of mRNA in the NPC of live cells with innovative imaging techniques breaking the diffraction limit of conventional light microscopy. Recently, super-resolution fluorescence microscopy and single-particle tracking (SPT techniques have been applied to the study of nuclear export of mRNA in live cells. In this review, we emphasize the necessity of 3D mapping techniques in the study of mRNA export, briefly summarize the feasibility of current 3D imaging approaches, and highlight the new features of mRNA nuclear export elucidated with a newly developed 3D imaging approach combining SPT-based super-resolution imaging and 2D-to-3D deconvolution algorithms.

  12. Fuel handling grapple for nuclear reactor plants

    International Nuclear Information System (INIS)

    Rousar, D.L.

    1992-01-01

    This patent describes a fuel handling system for nuclear reactor plants. It comprises: a reactor vessel having an openable top and removable cover and containing therein, submerged in water substantially filling the reactor vessel, a fuel core including a multiplicity of fuel bundles formed of groups of sealed tube elements enclosing fissionable fuel assembled into units, the fuel handling system consisting essentially of the combination of: a fuel bundle handling platform movable over the open top of the reactor vessel; a fuel bundle handling mast extendable downward from the platform with a lower end projecting into the open top reactor vessel to the fuel core submerged in water; a grapple head mounted on the lower end of the mast provided with grapple means comprising complementary hooks which pivot inward toward each other to securely grasp a bail handle of a nuclear reactor fuel bundle and pivot backward away from each other to release a bail handle; the grapple means having a hollow cylindrical support shaft fixed within the grapple head with hollow cylindrical sleeves rotatably mounted and fixed in longitudinal axial position on the support shaft and each sleeve having complementary hooks secured thereto whereby each hook pivots with the rotation of the sleeve secured thereto; and the hollow cylindrical support shaft being provided with complementary orifices on opposite sides of its hollow cylindrical and intermediate to the sleeves mounted thereon whereby the orifices on both sides of the hollow cylindrical support shaft are vertically aligned providing a direct in-line optical viewing path downward there-through and a remote operator positioned above the grapple means can observe from overhead the area immediately below the grapple hooks

  13. Summary of nuclear fuel reprocessing activities around the world

    International Nuclear Information System (INIS)

    Mellinger, P.J.; Harmon, K.M.; Lakey, L.T.

    1984-11-01

    This review of international practices for nuclear fuel reprocessing was prepared to provide a nontechnical summary of the current status of nuclear fuel reprocessing activities around the world. The sources of information are widely varied

  14. Spent Nuclear Fuel Alternative Technology Decision Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, C.B.

    1999-11-29

    The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology.

  15. Spent Nuclear Fuel Alternative Technology Decision Analysis

    International Nuclear Information System (INIS)

    Shedrow, C.B.

    1999-01-01

    The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology

  16. Nuclear Fuel Cycle Options Catalog FY15 Improvements and Additions

    International Nuclear Information System (INIS)

    Price, Laura L.; Barela, Amanda Crystal; Schetnan, Richard Reed; Walkow, Walter M.

    2015-01-01

    The United States Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Program sponsors nuclear fuel cycle research and development. As part of its Fuel Cycle Options campaign, the DOE has established the Nuclear Fuel Cycle Options Catalog. The catalog is intended for use by the Fuel Cycle Technologies Program in planning its research and development activities and disseminating information regarding nuclear energy to interested parties. The purpose of this report is to document the improvements and additions that have been made to the Nuclear Fuel Cycle Options Catalog in the 2015 fiscal year.

  17. Nuclear Fuel Cycle Options Catalog: FY16 Improvements and Additions

    Energy Technology Data Exchange (ETDEWEB)

    Price, Laura L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Barela, Amanda Crystal [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walkow, Walter M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-08-31

    The United States Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Program sponsors nuclear fuel cycle research and development. As part of its Fuel Cycle Options campaign, the DOE has established the Nuclear Fuel Cycle Options Catalog. The catalog is intended for use by the Fuel Cycle Technologies Program in planning its research and development activities and disseminating information regarding nuclear energy to interested parties. The purpose of this report is to document the improvements and additions that have been made to the Nuclear Fuel Cycle Options Catalog in the 2016 fiscal year.

  18. Nuclear Fuel Cycle Options Catalog FY15 Improvements and Additions.

    Energy Technology Data Exchange (ETDEWEB)

    Price, Laura L. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Barela, Amanda Crystal [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Walkow, Walter M. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-11-01

    The United States Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Program sponsors nuclear fuel cycle research and development. As part of its Fuel Cycle Options campaign, the DOE has established the Nuclear Fuel Cycle Options Catalog. The catalog is intended for use by the Fuel Cycle Technologies Program in planning its research and development activities and disseminating information regarding nuclear energy to interested parties. The purpose of this report is to document the improvements and additions that have been made to the Nuclear Fuel Cycle Options Catalog in the 2015 fiscal year.

  19. Innovative nuclear fuels: results and strategy

    International Nuclear Information System (INIS)

    Stan, Marius

    2009-01-01

    To facilitate the discovery and design of innovative nuclear fuels, multi-scale models and simulations are used to predict irradiation effects on the thermal conductivity, oxygen diffusivity, and thermal expansion of oxide fuels. The multi-scale approach is illustrated using results on ceramic fuels with a focus on predictions of point defect concentrations, stoichiometry, and phase stability. The high performance computer simulations include coupled heat transport, diffusion, and thermal expansion, gas bubble formation and temperature evolution in a fuel element consisting of UO2 fuel and metallic cladding. The second part of the talk is dedicated to a discussion of an international strategy for developing advanced, innovative nuclear fuels. Four initiative are proposed to accelerate the discovery and design of new materials: (a) Develop an international pool of experts, (b) Create Institutes for Materials Discovery and Design, (c) Create an International Knowledge base for experimental data, models (mathematical expressions), and simulations (codes) and (d) Organize international workshops and conference sessions. The paper ends with a discussion of existing and emerging international collaborations.

  20. Assessment of nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    1975-09-01

    The status of technology and the regulatory situation are summarized; the level of Federal support believed to be necessary to ensure that the nuclear option plays its role in the National Energy Plan is estimated. The assessment is based on a review of the open literature (no proprietary information), preliminary economic calculations, and experience of the Du Pont staff in the design, construction, and operation of nuclear facilities at Hanford and Savannah River. Because of the limited time available for the review, the conclusions and recommendations are preliminary, but they should provide an appropriate point of departure for planning purposes. A summary of recommendations and conclusions is provided at the beginning of the report, a current status of the applicable technology is given in Appendix B, and a glossary of terms is provided at the end of the report

  1. Communications received from Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1994-04-01

    The Director General has received notes verbales to the export of nuclear material, equipment and technology from the following Permanent Missions to the International Atomic Energy Agency: notes verbales dated 1 March 1994 from the Permanent Missions of Australia, Austria, Belgium, Bulgaria, Canada, the Czech Republic, Denmark, Finland, France, Germany, Hungary, Italy, Japan, the Netherlands, Poland, Portugal, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, the United States of America; and a note verbale dated 12 March 1994 from the Permanent Mission of Romania. The purpose of these notes verbales is to provide further information on these Governments' nuclear export policies and practices

  2. Fluid pressure method for recovering fuel pellets from nuclear fuel elements

    International Nuclear Information System (INIS)

    John, C.D. Jr.

    1979-01-01

    A method is described for removing fuel pellets from a nuclear fuel element without damaging the fuel pellets or fuel element sheath so that both may be reused. The method comprises holding the fuel element while a high pressure stream internally pressurizes the fuel element to expand the fuel element sheath away from the fuel pellets therein so that the fuel pellets may be easily removed

  3. Dual function of the nuclear export signal of the Borna disease virus nucleoprotein in nuclear export activity and binding to viral phosphoprotein.

    Science.gov (United States)

    Yanai, Mako; Sakai, Madoka; Makino, Akiko; Tomonaga, Keizo

    2017-07-11

    Borna disease virus (BoDV), which has a negative-sense, single-stranded RNA genome, causes persistent infection in the cell nucleus. The nuclear export signal (NES) of the viral nucleoprotein (N) consisting of leucine at positions 128 and 131 and isoleucine at positions 133 and 136 overlaps with one of two predicted binding sites for the viral phosphoprotein (P). A previous study demonstrated that higher expression of BoDV-P inhibits nuclear export of N; however, the function of N NES in the interaction with P remains unclear. We examined the subcellular localization, viral polymerase activity, and P-binding ability of BoDV-N NES mutants. We also characterized a recombinant BoDV (rBoDV) harboring an NES mutation of N. BoDV-N with four alanine-substitutions in the leucine and isoleucine residues of the NES impaired its cytoplasmic localization and abolished polymerase activity and P-binding ability. Although an alanine-substitution at position 131 markedly enhanced viral polymerase activity as determined by a minigenome assay, rBoDV harboring this mutation showed expression of viral RNAs and proteins relative to that of wild-type rBoDV. Our results demonstrate that BoDV-N NES has a dual function in BoDV replication, i.e., nuclear export of N and an interaction with P, affecting viral polymerase activity in the nucleus.

  4. Fuel cycle analysis of once-through nuclear systems

    International Nuclear Information System (INIS)

    Kim, T.K.; Taiwo, T.A.

    2010-01-01

    Once-through fuel cycle systems are commercially used for the generation of nuclear power, with little exception. The bulk of these once-through systems have been water-cooled reactors (light-water and heavy water reactors, LWRs and HWRs). Some gas-cooled reactors are used in the United Kingdom. The commercial power systems that are exceptions use limited recycle (currently one recycle) of transuranic elements, primarily plutonium, as done in Europe and nearing deployment in Japan. For most of these once-through fuel cycles, the ultimate storage of the used (spent) nuclear fuel (UNF, SNF) will be in a geologic repository. Besides the commercial nuclear plants, new once-through concepts are being proposed for various objectives under international advanced nuclear fuel cycle studies and by industrial and venture capital groups. Some of the objectives for these systems include: (1) Long life core for remote use or foreign export and to support proliferation risk reduction goals - In these systems the intent is to achieve very long core-life with no refueling and limited or no access to the fuel. Most of these systems are fast spectrum systems and have been designed with the intent to improve plant economics, minimize nuclear waste, enhance system safety, and reduce proliferation risk. Some of these designs are being developed under Generation IV International Forum activities and have generally not used fuel blankets and have limited the fissile content of the fuel to less than 20% for the purpose on meeting international nonproliferation objectives. In general, the systems attempt to use transuranic elements (TRU) produced in current commercial nuclear power plants as this is seen as a way to minimize the amount of the problematic radio-nuclides that have to be stored in a repository. In this case, however, the reprocessing of the commercial LWR UNF to produce the initial fuel will be necessary. For this reason, some of the systems plan to use low enriched uranium

  5. Fuel cycle analysis of once-through nuclear systems.

    Energy Technology Data Exchange (ETDEWEB)

    Kim, T. K.; Taiwo, T. A.; Nuclear Engineering Division

    2010-08-10

    Once-through fuel cycle systems are commercially used for the generation of nuclear power, with little exception. The bulk of these once-through systems have been water-cooled reactors (light-water and heavy water reactors, LWRs and HWRs). Some gas-cooled reactors are used in the United Kingdom. The commercial power systems that are exceptions use limited recycle (currently one recycle) of transuranic elements, primarily plutonium, as done in Europe and nearing deployment in Japan. For most of these once-through fuel cycles, the ultimate storage of the used (spent) nuclear fuel (UNF, SNF) will be in a geologic repository. Besides the commercial nuclear plants, new once-through concepts are being proposed for various objectives under international advanced nuclear fuel cycle studies and by industrial and venture capital groups. Some of the objectives for these systems include: (1) Long life core for remote use or foreign export and to support proliferation risk reduction goals - In these systems the intent is to achieve very long core-life with no refueling and limited or no access to the fuel. Most of these systems are fast spectrum systems and have been designed with the intent to improve plant economics, minimize nuclear waste, enhance system safety, and reduce proliferation risk. Some of these designs are being developed under Generation IV International Forum activities and have generally not used fuel blankets and have limited the fissile content of the fuel to less than 20% for the purpose on meeting international nonproliferation objectives. In general, the systems attempt to use transuranic elements (TRU) produced in current commercial nuclear power plants as this is seen as a way to minimize the amount of the problematic radio-nuclides that have to be stored in a repository. In this case, however, the reprocessing of the commercial LWR UNF to produce the initial fuel will be necessary. For this reason, some of the systems plan to use low enriched uranium

  6. Nuclear fuel bundle disassembly and assembly tool

    International Nuclear Information System (INIS)

    Yates, J.; Long, J.W.

    1975-01-01

    A nuclear power reactor fuel bundle is described which has a plurality of tubular fuel rods disposed in parallel array between two transverse tie plates. It is secured against disassembly by one or more locking forks which engage slots in tie rods which position the transverse plates. Springs mounted on the fuel and tie rods are compressed when the bundle is assembled thereby maintaining a continual pressure against the locking forks. Force applied in opposition to the springs permits withdrawal of the locking forks so that one tie plate may be removed, giving access to the fuel rods. An assembly and disassembly tool facilitates removal of the locking forks when the bundle is to be disassembled and the placing of the forks during assembly of the bundle. (U.S.)

  7. Supply Security in Future Nuclear Fuel Markets

    International Nuclear Information System (INIS)

    Seward, Amy M.; Wood, Thomas W.; Gitau, Ernest T.; Ford, Benjamin E.

    2013-01-01

    Previous PNNL work has shown the existing nuclear fuel markets to provide a high degree of supply security, including the ability to respond to supply disruptions that occur for technical and non-technical reasons. It is in the context of new reactor designs - that is, reactors likely to be licensed and market ready over the next several decades - that fuel supply security is most relevant. Whereas the fuel design and fabrication technology for existing reactors are well known, the construction of a new set of reactors could stress the ability of the existing market to provide adequate supply redundancy. This study shows this is unlikely to occur for at least thirty years, as most reactors likely to be built in the next three decades will be evolutions of current designs, with similar fuel designs to existing reactors.

  8. Supply Security in Future Nuclear Fuel Markets

    Energy Technology Data Exchange (ETDEWEB)

    Seward, Amy M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wood, Thomas W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gitau, Ernest T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ford, Benjamin E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-11-18

    Previous PNNL work has shown the existing nuclear fuel markets to provide a high degree of supply security, including the ability to respond to supply disruptions that occur for technical and non-technical reasons. It is in the context of new reactor designs – that is, reactors likely to be licensed and market ready over the next several decades – that fuel supply security is most relevant. Whereas the fuel design and fabrication technology for existing reactors are well known, the construction of a new set of reactors could stress the ability of the existing market to provide adequate supply redundancy. This study shows this is unlikely to occur for at least thirty years, as most reactors likely to be built in the next three decades will be evolutions of current designs, with similar fuel designs to existing reactors.

  9. Fuel assembly for a nuclear reactor

    International Nuclear Information System (INIS)

    Anthony, A.J.; Hutchinson, J.J.

    1978-01-01

    A nuclear reactor fuel assembly in which the end fittings may be easily removed after the assembly has been irradiated so that defective fuel rods may be replaced or special fuel or burnable poison rods inserted therein. The fuel assembly is of the type wherein structural support is provided by several vertically extending hollow structural members attached at opposite ends to upper and lower end fittings. The upper and lower end fittings each comprise an end plate and means extending therefrom for alignment and support of the assembly within the reactor core. Threaded joints between the hollow structural members and the means for alignment form the connections between the hollow structural members and the upper and lower end fittings

  10. Spent nuclear fuel project product specification

    International Nuclear Information System (INIS)

    Pajunen, A.L.

    1998-01-01

    Product specifications are limits and controls established for each significant parameter that potentially affects safety and/or quality of the Spent Nuclear Fuel (SNF) packaged for transport to dry storage. The product specifications in this document cover the spent fuel packaged in MultiCanister Overpacks (MCOs) to be transported throughout the SNF Project. The SNF includes N Reactor fuel and single-pass reactor fuel. The FRS removes the SNF from the storage canisters, cleans it, and places it into baskets. The MCO loading system places the baskets into MCO/Cask assembly packages. These packages are then transferred to the Cold Vacuum Drying (CVD) Facility. After drying at the CVD Facility, the MCO cask packages are transferred to the Canister Storage Building (CSB), where the MCOs are removed from the casks, staged, inspected, sealed (by welding), and stored until a suitable permanent disposal option is implemented. The key criteria necessary to achieve these goals are documented in this specification

  11. 77 FR 19278 - Informational Meeting on Nuclear Fuel Cycle Options

    Science.gov (United States)

    2012-03-30

    ... criteria or the pros and cons of any particular fuel cycle option. Opportunity for providing input on the... Informational Meeting on Nuclear Fuel Cycle Options AGENCY: Office of Fuel Cycle Technologies, Office of Nuclear Energy, Department of Energy. ACTION: Notice of meeting. SUMMARY: The Office of Fuel Cycle Technologies...

  12. Nuclear-fuel-cycle education: Module 10. Environmental consideration

    International Nuclear Information System (INIS)

    Wethington, J.A.; Razvi, J.; Grier, C.; Myrick, T.

    1981-12-01

    This educational module is devoted to the environmental considerations of the nuclear fuel cycle. Eight chapters cover: National Environmental Policy Act; environmental impact statements; environmental survey of the uranium fuel cycle; the Barnwell Nuclear Fuel Reprocessing Plant; transport mechanisms; radiological hazards in uranium mining and milling operations; radiological hazards of uranium mill tailings; and the use of recycle plutonium in mixed oxide fuel

  13. Securing the nuclear fuel cycle: What next?

    International Nuclear Information System (INIS)

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

    2006-01-01

    The greatest challenge to the international nuclear non-proliferation regime is posed by nuclear energy's dual nature for both peaceful and military purposes. Uranium enrichment and spent nuclear fuel (SNF) reprocessing (here after called s ensitive nuclear technologies ) are critical from the non-proliferation viewpoint because they may be used to produce weapons-grade nuclear materials: highly enriched uranium and separated plutonium. Alongside measures to limit the spread of sensitive nuclear technologies, multilateral approaches to the nuclear fuel cycle (NFC) started to be discussed. Spiralling prices for hydrocarbons and prospects of their imminent extinction are encouraging more and more countries to look at nuclear energy as an alternative means to ensure their sustainable development. To this end, it's becoming increasingly important to link the objective need for an expanded use of nuclear energy with strengthening nuclear non-proliferation by, in particular, preventing the spread of sensitive nuclear technologies and securing access for interested countries to NFC products and services. With this in mind, at the IAEA General Conference in 2003, IAEA Director General Mohamed ElBaradei called for establishing an international experts group on multilateral nuclear approaches. The proposal was supported, and in February 2005 the international experts, headed by Bruno Pellaud, issued a report (published by the IAEA as INFCIRC-640; see www.iaea.org) with recommendations on different multilateral approaches. The recommendations can be generalized as follows: reinforcement of existing market mechanisms; involvement of governments and the IAEA in the assurance of supply, including the establishment of low-enriched uranium (LEU) stocks as reserves; conversion of existing national uranium enrichment and SNF reprocessing enterprises into multilateral ones under international management and control, and setting up new multilateral enterprises on regional and

  14. GLOBAL PROSPECTS OF SYNTHETIC DIESEL FUEL PRODUCED FROM HYDROCARBON RESOURCES IN OIL&GAS EXPORTING COUNTRIES

    Directory of Open Access Journals (Sweden)

    Tomislav Kurevija

    2007-12-01

    Full Text Available Production of synthetic diesel fuel through Fischer-Tropsch process is a well known technology which dates from II World War, when Germany was producing transport fuel from coal. This process has been further improved in the South Africa due to period of international isolation. Today, with high crude oil market cost and increased demand of energy from China and India, as well as global ecological awareness and need to improve air quality in urban surroundings, many projects are being planned regarding production of synthetic diesel fuel, known as GTL (Gas To Liquid. Most of the future GTL plants are planned in oil exporting countries, such are Qatar and Nigeria, where natural gas as by-product of oil production is being flared, losing in that way precious energy and profit. In that way, otherwise flared natural gas, will be transformed into synthetic diesel fuel which can be directly used in all modern diesel engines. Furthermore, fossil fuel transportation and distribution technology grid can be used without any significant changes. According to lower emissions of harmful gasses during combustion than fossil diesel, this fuel could in the future play a significant part of EU efforts to reach 23% of alternative fuel share till 2020., which are now mostly relied on biodiesel, LPG (liquefied petroleum gas and CNG (compressed natural gas.

  15. Regional nuclear fuel cycle centers study project

    International Nuclear Information System (INIS)

    Bennett, L.; Catlin, R.G.; Meckoni, V.

    1977-01-01

    The concept of regional fuel cycle centers (RFCC) has attracted wide interest. The concept was endorsed by many countries in discussions at the General Conference of the International Atomic Energy Agency and at the General Assembly of the United Nations. Accordingly, in 1975, the IAEA initiated a detailed study of the RFCC concept. The Agency study has concentrated on what is referred to as the ''back-end'' of the fuel cycle because that is the portion which is currently problematic. The study covers transport, storage, processing and recycle activities starting from the time the spent fuel leaves the reactor storage pools and through all steps until the recycled fuel is in finished fuel elements and shipped to the reactor. A detailed evaluation of the specific features of large regional fuel cycle centers established on a multinational basis vis-a-vis smaller dispersed fuel cycle facilities set up on a national basis has been carried out. The methodology for assessment of alternative strategies for fuel storage, reprocessing, and recycling of plutonium has been developed, characteristic data on material flows and cost factors have been generated, and an analytic system has been developed to carry out such evaluations including appropriate sensitivity analysis. Studies in related areas on institutional and legal, organizational, environmental, materials control and other essential aspects have also been made. The material developed during the course of this Study would enable any group of interested Member States to examine and work out alternative strategies pertinent to their present and projected nuclear fuel cycle needs, as well as evolve institutional, legal and other appropriate frameworks or agreements for the establishment of fuel cycle centers on a multinational cooperative basis

  16. Spent Nuclear Fuel Project operational staffing plan

    International Nuclear Information System (INIS)

    Debban, B.L.

    1996-03-01

    Using the Spent Nuclear Fuel (SNF) Project's current process flow concepts and knowledge from cognizant engineering and operational personnel, an initial assessment of the SNF Project radiological exposure and resource requirements was completed. A small project team completed a step by step analysis of fuel movement in the K Basins to the new interim storage location, the Canister Storage Building (CSB). This analysis looked at fuel retrieval, conditioning of the fuel, and transportation of the fuel. This plan describes the staffing structure for fuel processing, fuel movement, and the maintenance and operation (M ampersand O) staffing requirements of the facilities. This initial draft does not identify the support function resources required for M ampersand O, i.e., administrative and engineering (technical support). These will be included in future revisions to the plan. This plan looks at the resource requirements for the SNF subprojects, specifically, the operations of the facilities, balances resources where applicable, rotates crews where applicable, and attempts to use individuals in multi-task assignments. This plan does not apply to the construction phase of planned projects that affect staffing levels of K Basins

  17. Development of nuclear fuel for integrated reactor

    Energy Technology Data Exchange (ETDEWEB)

    Song, Kee Nam; Kim, H. K.; Kang, H. S.; Yoon, K. H.; Chun, T. H.; In, W. K.; Oh, D. S.; Kim, D. W.; Woo, Y. M

    1999-04-01

    The spacer grid assembly which provides both lateral and vertical support for the fuel rods and also provides a flow channel between the fuel rods to afford the heat transfer from the fuel pellet into the coolant in a reactor, is one of the major structural components of nuclear fuel for LWR. Therefore, the spacer grid assembly is a highly ranked component when the improvement of hardware is pursued for promoting fuel performance. Main objective of this project is to develop the inherent spacer grid assembly and to research relevant technologies on the spacer grid assembly. And, the UO{sub 2}-based SMART fuel is preliminarily designed for the 330MWt class SMART, which is planned to produce heat as well as electricity. Results from this project are listed as follows. 1. Three kinds of spacer grid candidates have been invented and applied for domestic and US patents. In addition, the demo SG(3x3 array) were fabricated, which the mechanical/structural test was carried out with. 2. The mechanical/structural technologies related to the spacer grid development are studied and relevant test requirements were established. 3. Preliminary design data of the UO{sub 2}-based SMART fuel have been produced. The structural characteristics of several components such as the top/bottom end piece and the holddown spring assembly were analysed by consulting the numerical method.

  18. Antineutrino Monitoring of Spent Nuclear Fuel

    Science.gov (United States)

    Brdar, Vedran; Huber, Patrick; Kopp, Joachim

    2017-11-01

    Military and civilian applications of nuclear energy have left a significant amount of spent nuclear fuel over the past 70 years. Currently, in many countries worldwide, the use of nuclear energy is on the rise. Therefore, the management of highly radioactive nuclear waste is a pressing issue. In this paper, we explore antineutrino detectors as a tool for monitoring and safeguarding nuclear-waste material. We compute the flux and spectrum of antineutrinos emitted by spent nuclear fuel elements as a function of time, and we illustrate the usefulness of antineutrino detectors in several benchmark scenarios. In particular, we demonstrate how a measurement of the antineutrino flux can help to reverify the contents of a dry storage cask in case the monitoring chain by conventional means gets disrupted. We then comment on the usefulness of antineutrino detectors at long-term storage facilities such as Yucca mountain. Finally, we put forward antineutrino detection as a tool in locating underground "hot spots" in contaminated areas such as the Hanford site in Washington state.

  19. Nuclear power generation and fuel cycle report 1996

    International Nuclear Information System (INIS)

    1996-10-01

    This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included

  20. Nuclear power generation and fuel cycle report 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included.

  1. High-Resolution Imaging Reveals New Features of Nuclear Export of mRNA through the Nuclear Pore Complexes

    Directory of Open Access Journals (Sweden)

    Joseph M. Kelich

    2014-08-01

    Full Text Available The nuclear envelope (NE of eukaryotic cells provides a physical barrier for messenger RNA (mRNA and the associated proteins (mRNPs traveling from sites of transcription in the nucleus to locations of translation processing in the cytoplasm. Nuclear pore complexes (NPCs embedded in the NE serve as a dominant gateway for nuclear export of mRNA. However, the fundamental characterization of export dynamics of mRNPs through the NPC has been hindered by several technical limits. First, the size of NPC that is barely below the diffraction limit of conventional light microscopy requires a super-resolution microscopy imaging approach. Next, the fast transit of mRNPs through the NPC further demands a high temporal resolution by the imaging approach. Finally, the inherent three-dimensional (3D movements of mRNPs through the NPC demand the method to provide a 3D mapping of both transport kinetics and transport pathways of mRNPs. This review will highlight the recently developed super-resolution imaging techniques advanced from 1D to 3D for nuclear export of mRNPs and summarize the new features in the dynamic nuclear export process of mRNPs revealed from these technical advances.

  2. Nuclear Sanctions: Section 102(b) of the Arms Export Control Act and its Application to India and Pakistan

    National Research Council Canada - National Science Library

    Grimmett, Jeanne J

    2001-01-01

    Section 102(b) of the Arms Export Control Act (AECA) requires the President to impose sanctions on any country that he has determined is a "non-nuclear-weapon state" and has received or detonated a "nuclear explosive device...

  3. 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)

  4. Environmental management in Framatome nuclear fuel

    International Nuclear Information System (INIS)

    Thiebaut, B.; Ferre, A.

    1999-01-01

    Environmental preservation is both a national regulatory requirement and a condition for economic and social development. The various industrial sites belonging to the Framatome Nuclear Fuel Organisation, whose activities range from the processing and transformation of Zirconium alloy products to the fabrication of fuel assemblies, have always demonstrated that protection of the environment was their prime concern by implementing low pollution level processes and reducing and/or recycling industrial waste and effluents. As early as January 1996, a directive issued by the Framatome Group defined its environmental policy and responsibilities in the matter. Within the Framatome Nuclear Fuel Organization, this directive has been applied by implementation of: low level pollution processes; better performance of recycling of effluents, by-products and waste; environmental information policy. In all its plants, the Framatome Nuclear Fuel Organization has decided to pursue and to step up its environmental protection policy by: officializing its action through compliance with ISO standard 14001 and certification of all its industrial sites by 2001 at the latest; launching new actions and extra investment programs. In this context, FBFC has applied for a modification of the decrees concerning the dumping of liquid and gas effluents at the Romans factory. (authors)

  5. KLF4 Nuclear Export Requires ERK Activation and Initiates Exit from Naive Pluripotency.

    Science.gov (United States)

    Dhaliwal, Navroop K; Miri, Kamelia; Davidson, Scott; Tamim El Jarkass, Hala; Mitchell, Jennifer A

    2018-04-10

    Cooperative action of a transcription factor complex containing OCT4, SOX2, NANOG, and KLF4 maintains the naive pluripotent state; however, less is known about the mechanisms that disrupt this complex, initiating exit from pluripotency. We show that, as embryonic stem cells (ESCs) exit pluripotency, KLF4 protein is exported from the nucleus causing rapid decline in Nanog and Klf4 transcription; as a result, KLF4 is the first pluripotency transcription factor removed from transcription-associated complexes during differentiation. KLF4 nuclear export requires ERK activation, and phosphorylation of KLF4 by ERK initiates interaction of KLF4 with nuclear export factor XPO1, leading to KLF4 export. Mutation of the ERK phosphorylation site in KLF4 (S132) blocks KLF4 nuclear export, the decline in Nanog, Klf4, and Sox2 mRNA, and differentiation. These findings demonstrate that relocalization of KLF4 to the cytoplasm is a critical first step in exit from the naive pluripotent state and initiation of ESC differentiation. Copyright © 2018 The Authors. Published by Elsevier Inc. All rights reserved.

  6. Upgrading safety documentation for exported nuclear power plants

    International Nuclear Information System (INIS)

    Rosen, M.

    1978-01-01

    In view of the generally small regulatory staffs of importing countries, suggestions are given for upgrading the ''export edition'' of the traditionally supplied safety documentation by use of a Supplementary Information Report, written specifically for the needs of a smaller and/or less technically qualified staff, which would highlight the differences that exist between the facility to be constructed and the supposedly similar reference plant of the supplier country; by improvement of supporting safety documentation to allow for adequate understanding of significant safety parameters; and by attention to the needs of smaller countries in the critical operating regulations (Technical Specifications for Operation). (author)

  7. Review of the IAEA nuclear fuel cycle and material section activities connected with nuclear fuel including WWER fuel

    International Nuclear Information System (INIS)

    Sokolov, F.

    2001-01-01

    Program activities on Nuclear Fuel Cycle and Materials cover the areas of: 1) raw materials (B.1.01); 2) fuel performance and technology (B.1.02); 3) pent fuel (B.1.03); 4) fuel cycle issues and information system (B.1.04); 5) support to technical cooperation activities (B.1.05). The IAEA activities in fuel performance and technology in 2001 include organization of the fuel experts meetings and completion of the Co-ordinate Research Projects (CRP). The special attention is given to the advanced post-irradiation examination techniques for water reactor fuel and fuel behavior under transients and LOCA conditions. An international research program on modeling of activity transfer in primary circuit of NPP is finalized in 2001. A new CRP on fuel modeling at extended burnup (FUMEX II) has planed to be carried out during the period 2002-2006. In the area of spent fuel management the implementation of burnup credit (BUC) in spent fuel management systems has motivated to be used in criticality safety applications, based on economic consideration. An overview of spent fuel storage policy accounting new fuel features as higher enrichment and final burnup, usage of MOX fuel and prolongation of the term of spent fuel storage is also given

  8. Nuclear Export of Pre-Ribosomal Subunits Requires Dbp5, but Not as an RNA-Helicase as for mRNA Export.

    Science.gov (United States)

    Neumann, Bettina; Wu, Haijia; Hackmann, Alexandra; Krebber, Heike

    2016-01-01

    The DEAD-box RNA-helicase Dbp5/Rat8 is known for its function in nuclear mRNA export, where it displaces the export receptor Mex67 from the mRNA at the cytoplasmic side of the nuclear pore complex (NPC). Here we show that Dbp5 is also required for the nuclear export of both pre-ribosomal subunits. Yeast temperature-sensitive dbp5 mutants accumulate both ribosomal particles in their nuclei. Furthermore, Dbp5 genetically and physically interacts with known ribosomal transport factors such as Nmd3. Similar to mRNA export we show that also for ribosomal transport Dbp5 is required at the cytoplasmic side of the NPC. However, unlike its role in mRNA export, Dbp5 does not seem to undergo its ATPase cycle for this function, as ATPase-deficient dbp5 mutants that selectively inhibit mRNA export do not affect ribosomal transport. Furthermore, mutants of GLE1, the ATPase stimulating factor of Dbp5, show no major ribosomal export defects. Consequently, while Dbp5 uses its ATPase cycle to displace the export receptor Mex67 from the translocated mRNAs, Mex67 remains bound to ribosomal subunits upon transit to the cytoplasm, where it is detectable on translating ribosomes. Therefore, we propose a model, in which Dbp5 supports ribosomal transport by capturing ribosomal subunits upon their cytoplasmic appearance at the NPC, possibly by binding export factors such as Mex67. Thus, our findings reveal that although different ribonucleoparticles, mRNAs and pre-ribosomal subunits, use shared export factors, they utilize different transport mechanisms.

  9. Nuclear export controls and the CTBT: Where we've been and challenges ahead - Views of an engineer

    International Nuclear Information System (INIS)

    Lundy, A.S.

    1998-01-01

    The paper discusses the following topics: the importance of export controls; the uniqueness of nuclear weapons and their export control requirements; ''dual-use'' controls; and recent developments in nonproliferation beyond export control. Also discussed are some non-obvious challenges which include computer modeling and visualization, and fissile material availability and instant nukes. The author concludes by asking the Nuclear Suppliers Group to consider whether there are ways to make its controls more effective

  10. Nuclear export controls and the CTBT: Where we`ve been and challenges ahead -- Views of an engineer

    Energy Technology Data Exchange (ETDEWEB)

    Lundy, A.S.

    1998-09-01

    The paper discusses the following topics: the importance of export controls; the uniqueness of nuclear weapons and their export control requirements; ``dual-use`` controls; and recent developments in nonproliferation beyond export control. Also discussed are some non-obvious challenges which include computer modeling and visualization, and fissile material availability and instant nukes. The author concludes by asking the Nuclear Suppliers Group to consider whether there are ways to make its controls more effective.

  11. The industrial nuclear fuel cycle in Argentina

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  12. Applications of superconductivity to nuclear fuel cycle

    International Nuclear Information System (INIS)

    Sasao, Nobuyuki; Kubota, Jun

    1988-01-01

    As the application of superconductivity in nuclear fuel cycle, the plasma process of uranium enrichment, the magnetic separation techniques for fuel reprocessing, waste treatment and so on, and the application of liquid metal MHD to FBRs are explained. Besides, the investigation of rare earth which is the main elements of oxide superconductive materials in the aspect of resources, and the examination of the possibility of actinide superconductive materials including uranium which is a nuclear fuel material are carried out. Through these studies, it was found that by the adoption of superconductivity, that which receives the economical and technical favors most is nuclear power. Nuclearfuel creates rare earth by nuclear fission reaction when it burns in a reactor, and there is the possibility that it becomes the creation of valuable resources for Japan where natural resources are short. The uranium enrichment by the isotope separation using plasma electromagnetic effect was examined in USA, but stopped. Magnetic separation utilizes the gradient of a magnetic field to separate superfine particles, and many applications are conceivable. In the case of liquid metal MHD, the electric conductivity is very high, accordingly the flow velocity and fluid temperature may be relatively low. The development of a superconductive electromagnetic pump for a FBR is discussed. (Kako, I.)

  13. Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

    International Nuclear Information System (INIS)

    1994-04-01

    The Director General has received notes verbales dated 27 August 1993 and 28 October 1993 from the Permanent Missions of Finland and Spain to the International Atomic Energy relating to the export of nuclear material, equipment and technology. The purpose of these notes verbales is to provide further information on those Governments' nuclear export policies and practices

  14. Selective nuclear export of specific classes of mRNA from mammalian nuclei is promoted by GANP.

    Science.gov (United States)

    Wickramasinghe, Vihandha O; Andrews, Robert; Ellis, Peter; Langford, Cordelia; Gurdon, John B; Stewart, Murray; Venkitaraman, Ashok R; Laskey, Ronald A

    2014-04-01

    The nuclear phase of the gene expression pathway culminates in the export of mature messenger RNAs (mRNAs) to the cytoplasm through nuclear pore complexes. GANP (germinal- centre associated nuclear protein) promotes the transfer of mRNAs bound to the transport factor NXF1 to nuclear pore complexes. Here, we demonstrate that GANP, subunit of the TRanscription-EXport-2 (TREX-2) mRNA export complex, promotes selective nuclear export of a specific subset of mRNAs whose transport depends on NXF1. Genome-wide gene expression profiling showed that half of the transcripts whose nuclear export was impaired following NXF1 depletion also showed reduced export when GANP was depleted. GANP-dependent transcripts were highly expressed, yet short-lived, and were highly enriched in those encoding central components of the gene expression machinery such as RNA synthesis and processing factors. After injection into Xenopus oocyte nuclei, representative GANP-dependent transcripts showed faster nuclear export kinetics than representative transcripts that were not influenced by GANP depletion. We propose that GANP promotes the nuclear export of specific classes of mRNAs that may facilitate rapid changes in gene expression.

  15. Inhibition of the Nuclear Export Receptor XPO1 as a Therapeutic Target for Platinum-Resistant Ovarian Cancer

    DEFF Research Database (Denmark)

    Chen, Ying; Camacho, Sandra Catalina; Silvers, Thomas R

    2017-01-01

    Purpose: The high fatality-to-case ratio of ovarian cancer is directly related to platinum resistance. Exportin-1 (XPO1) is a nuclear exporter that mediates nuclear export of multiple tumor suppressors. We investigated possible clinicopathologic correlations of XPO1 expression levels and evaluate...

  16. Selective nuclear export of specific classes of mRNA from mammalian nuclei is promoted by GANP

    Science.gov (United States)

    Wickramasinghe, Vihandha O.; Andrews, Robert; Ellis, Peter; Langford, Cordelia; Gurdon, John B.; Stewart, Murray; Venkitaraman, Ashok R.; Laskey, Ronald A.

    2014-01-01

    The nuclear phase of the gene expression pathway culminates in the export of mature messenger RNAs (mRNAs) to the cytoplasm through nuclear pore complexes. GANP (germinal- centre associated nuclear protein) promotes the transfer of mRNAs bound to the transport factor NXF1 to nuclear pore complexes. Here, we demonstrate that GANP, subunit of the TRanscription-EXport-2 (TREX-2) mRNA export complex, promotes selective nuclear export of a specific subset of mRNAs whose transport depends on NXF1. Genome-wide gene expression profiling showed that half of the transcripts whose nuclear export was impaired following NXF1 depletion also showed reduced export when GANP was depleted. GANP-dependent transcripts were highly expressed, yet short-lived, and were highly enriched in those encoding central components of the gene expression machinery such as RNA synthesis and processing factors. After injection into Xenopus oocyte nuclei, representative GANP-dependent transcripts showed faster nuclear export kinetics than representative transcripts that were not influenced by GANP depletion. We propose that GANP promotes the nuclear export of specific classes of mRNAs that may facilitate rapid changes in gene expression. PMID:24510098

  17. Assembly mechanism for nuclear fuel bundles

    International Nuclear Information System (INIS)

    Long, J.W.; Flora, B.S.; Ford, K.L.

    1980-01-01

    The invention relates to a nuclear power reactor fuel bundle of the type wherein several rods are mounted in parallel array between two tie plates which secure the fuel rods in place and are maintained in assembled position by means of a number of tie rods secured to both of the end plates. Improved apparatus is provided for attaching the tie rods to the upper tie plate by the use of locking lugs fixed to rotatable sleeves which engage the upper tie plate. (auth)

  18. Classification of spent nuclear fuel (SNF)

    International Nuclear Information System (INIS)

    1990-03-01

    This report is one of a series of eight prepared by E. R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high-priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. This document discusses the classification of spent nuclear fuels

  19. Transporting spent nuclear fuel: an overview

    International Nuclear Information System (INIS)

    1986-03-01

    Although high-level radioactive waste from both commercial and defense activities will be shipped to the repository, this booklet focuses on various aspects of transporting commercial spent fuel, which accounts for the majority of the material to be shipped. The booklet is intended to give the reader a basic understanding of the following: the reasons for transportation of spent nuclear fuel, the methods by which it is shipped, the safety and security precautions taken for its transportation, emergency response procedures in the event of an accident, and the DOE program to develop a system uniquely appropriate to NWPA transportation requirements

  20. Multi-layer coated nuclear fuel particles

    International Nuclear Information System (INIS)

    Suzuki, Nobuyuki.

    1984-01-01

    Purpose: To obtain coated fuel particles with low breaking rate. Constitution: In a multi-layer coated nuclear fuel particles having a silicon carbide coating layer as the layer for confining solid fission products, a silicon carbide layer with a density lower than that of the above-mentioned silicon carbide layer is disposed to the inside and/or outside of the later layer. The density is set to less than 3.18 g/cm 2 . Disposition of the lower density silicon carbide layer can moderate the tensile stresses or compression forces exerted to the high density silicon carbide layer thereby enabling to decrease the possibility of failure. (Kamimura, M.)