WorldWideScience

Sample records for nuclear transport factors

  1. Human and social factors in the transportation of nuclear wastes

    International Nuclear Information System (INIS)

    Freudenburg, W.R.

    1991-01-01

    The main body of this report is a broad-based examination of human and social factors in the transportation of nuclear wastes. It deals with pair interested problems that, while familiar to the social science community, appear to have received little attention from the risk assessment community to data: The human and social attenuation of risk estimates, and the organizational amplification of risks. Second, given the special opportunities for learning that are presented by the recent Alaska oil spill, in particular, the Appendix to this report examines the issue of organizational foresight in the context of the Exxon oil spill

  2. Nuclear transport

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    During january and february 2003, a unique event concerning nuclear transport was reported and rated 1 on the INES scale. This event concerns the absence of a maintenance operation on a shipping cask. This shipping cask was used for several years for nuclear transport inside La-hague site before being re-assigned to transport on public thoroughfare. The re-assignment of the cask should have been preceded and conditioned by a maintenance operation whose purpose is to check the efficiency of its radiation shield. During this period 2 on-site inspections concerning the transport of nuclear materials were performed. (A.C.)

  3. Nuclear transport

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    During September and October 2001, 1 event has been reported and classified at the first level of the INES scale. This incident concerns the violation of the European regulation that imposes to any driver of radioactive matter of being the holder of a certificate asserting that he attended a special training. During this period, 13 in-site inspections have been made in places related to nuclear transport. (A.C.)

  4. Nuclear transport

    International Nuclear Information System (INIS)

    Anon.

    2001-01-01

    Here is given the decree (2001/1199) of the 10. of december 2001 relative to the passing of safety rules concerning the maritime transport of spent fuels, plutonium and high-level radioactive wastes contained in packages. (O.M.)

  5. Factors influencing the design and assessment of elastomer seals for nuclear fuel transport flasks

    International Nuclear Information System (INIS)

    Chivers, T.C.; George, A.F.

    1984-06-01

    Elastomeric seals offer considerable advantages in the achievement of high integrity sealing. This report discusses the factors limiting the performance of elastomers under fault conditions, with particular attention to Nuclear Fuel Transport Flask seals. There is emphasis on seal compression and its optimisation, so that it is high enough to ensure adequate surface roughness infilling, and low enough to avoid damaging tensile stresses. The assessment of seal performance is discussed, and includes consideration of pressure actuation and extrusion, permeation losses and rig testing. It is concluded that to reach a satisfactory design requires considerable information on different aspects of elastomeric performance. (author)

  6. Transportation of nuclear fuel

    International Nuclear Information System (INIS)

    Prowse, D.R.

    1979-01-01

    Shipment of used fuel from nuclear reactors to a central fuel management facility is discussed with particular emphasis on the assessment of the risk to the public due to these shipments. The methods of transporting used fuel in large shipping containers is reviewed. In terms of an accident scenario, it is demonstrated that the primary risk of transport of used fuel is due to injury and death in common road accidents. The radiological nature of the used fuel cargo is, for all practical purposes, an insignificant factor in the total risk to the public. (author)

  7. Interaction of Sp1 zinc finger with transport factor in the nuclear localization of transcription factor Sp1

    International Nuclear Information System (INIS)

    Ito, Tatsuo; Kitamura, Haruka; Uwatoko, Chisana; Azumano, Makiko; Itoh, Kohji; Kuwahara, Jun

    2010-01-01

    Research highlights: → Sp1 zinc fingers themselves interact with importin α. → Sp1 zinc finger domains play an essential role as a nuclear localization signal. → Sp1 can be transported into the nucleus in an importin-dependent manner. -- Abstract: Transcription factor Sp1 is localized in the nucleus and regulates the expression of many cellular genes, but the nuclear transport mechanism of Sp1 is not well understood. In this study, we revealed that GST-fused Sp1 protein bound to endogenous importin α in HeLa cells via the Sp1 zinc finger domains, which comprise the DNA binding domain of Sp1. It was found that the Sp1 zinc finger domains directly interacted with a wide range of importin α including the armadillo (arm) repeat domain and the C-terminal acidic domain. Furthermore, it turned out that all three zinc fingers of Sp1 are essential for binding to importin α. Taken together, these results suggest that the Sp1 zinc finger domains play an essential role as a NLS and Sp1 can be transported into the nucleus in an importin-dependent manner even though it possesses no classical NLSs.

  8. Transport Nuclear Liability Insurance

    International Nuclear Information System (INIS)

    Folens, M.

    2006-01-01

    Although transport of nuclear substances represents only a very small part of the global transport of dangerous goods, it takes place every day all over the world and it is part of our daily life. Transport of nuclear material takes also place at every stage of the nuclear fuel cycle; radioactive materials are carried out all over the world by all major modes of transport: sea, air, road and rail. Despite the large number of nuclear transports, they are not considered as posing a serious risk. A major nuclear incident is almost always associated with the operating of fixed installations such as nuclear power plants; just think about Three Mile Island and Chernobyl. This perception is strengthened by the absence so far of serious accidents in the nuclear transport sector and this finding is in fact proof of the very safe conditions of nuclear transport. But accidents can never be excluded entirely and in some cases damages could be as large as those caused by fixed installations. This means that protection of the interests of possible victims should also be covered in a correct way. That is why the special nuclear liability regime has also been developed to cover damage caused by a nuclear transport accident. As stated by Patrick Reyners, the prime motivation for originally adopting a special nuclear regime was the harmonisation of national legislation and that nowhere more than in the field of international transport operations is such harmonisation felt desirable . The international legal regime has been developed along two tracks, one based on the mode of transport and the other based on the notion of dangerous goods. The linkage between those two tracks is of permanent concern and the mode of transport is the key element to determine which international instrument should be applicable. The purpose of this paper is to briefly introduce the financial security provided by the insurance industry to cover the international nuclear liability regime for nuclear

  9. Nuclear materials transportation

    International Nuclear Information System (INIS)

    Ushakov, B.A.

    1986-01-01

    Various methods of nuclear materials transportation at different stages of the fuel cycle (U 3 O 8 , UF 6 production enrichment, fuel element manufacturing, storage) are considered. The advantages and drawbacks of railway, automobile, maritime and air transport are analyzed. Some types of containers are characterized

  10. Nuclear materials transport worldwide

    International Nuclear Information System (INIS)

    Stellpflug, J.

    1987-01-01

    This Greenpeace report shows: nuclear materials transport is an extremely hazardous business. There is no safe protection against accidents, kidnapping, or sabotage. Any moment of a day, at any place, a nuclear transport accident may bring the world to disaster, releasing plutonium or radioactive fission products to the environment. Such an event is not less probable than the MCA at Chernobyl. The author of the book in hand follows the secret track of radioactive materials around the world, from uranium mines to the nuclear power plants, from reprocessing facilities to the waste repositories. He explores the routes of transport and the risks involved, he gives the names of transport firms and discloses incidents and carelessness, tells about damaged waste drums and plutonium that 'disappeared'. He also tells about worldwide, organised resistance to such nuclear transports, explaining the Greenpeace missions on the open sea, or the 'day X' operation at the Gorleben site, informing the reader about protests and actions for a world freed from the threat of nuclear energy. (orig./HP) [de

  11. Nuclear transport - The regulatory dimension

    International Nuclear Information System (INIS)

    Green, L.

    2002-01-01

    The benefits that the peaceful applications of nuclear energy have brought to society are due in no small part to industry's capacity to transport radioactive materials safely, efficiently and reliably. The nuclear transport industry has a vital role in realising a fundamental objective of the International Atomic Energy Agency (IAEA) as stated in its statute to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world. The context in which transports currently take place is complex, and rapidly changing. In many respects transport is being viewed as an integral market issue and not a subsidiary concern. The availability of carriers drives routing decisions and changes in material flows necessitate new approaches to packaging and transport scenarios. Pressures on the transport sector are not without serious consequences; they can cause delays and in some cases cancellation of planned movements. Complex routings and the necessary use of chartered carriers can push up costs and work against cost efficiency. Since the events of 11 September 2001 the security of nuclear transports has contributed an added dimension to how transports take place. Transports of radioactive material have an outstanding safety record, indeed the transport of such materials could be regarded as a model for the transport of other classes of dangerous goods. This safety record is achieved by two inter-related factors. It is due primarily to well founded regulations developed by such key intergovernmental organisations as the IAEA, with the essential contributions of the member states who participate in the implementation of regulations and the review process. It is due also to the professionalism of those in the industry. There is a necessary synergy between the two - between the regulators whose task it is to make and to enforce the rules for safe, efficient and reliable transport and those whose job it is to transport within the rules. It

  12. Transportation of nuclear materials

    International Nuclear Information System (INIS)

    Brobst, W.A.

    1977-01-01

    Twenty years of almost accident-free transport of nuclear materials is pointed to as evidence of a fundamentally correct approach to the problems involved. The increased volume and new technical problems in the future will require extension of these good practices in both regulations and packaging. The general principles of safety in the transport of radioactive materials are discussed first, followed by the transport of spent fuel and of radioactive waste. The security and physical protection of nuclear shipments is then treated. In discussing future problems, the question of public understanding and acceptance is taken first, thereafter transport safeguards and the technical bases for the safety regulations. There is also said to be a need for a new technology for spent fuel casks, while a re-examination of the IAEA transport standards for radiation doses is recommended. The IAEA regulations regarding quality assurance are said to be incomplete, and more information is required on correlations between engineering analysis, scale model testing and full scale crash testing. Transport stresses on contents need to be considered while administrative controls have been neglected. (JIW)

  13. Transport of nuclear materials

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    During november and december 2001, 2 events concerning nuclear transport were reported and classified on the first grade (grade 1) of the INES scale. The first event concerns a hole in a transport cask of contaminated tools. The hole seems to have been made by the fork of a handling equipment. The second event concerns the loss of a parcel containing a technetium generator, this generator represented an activity of about 141 G Becquerel of 99 Mo the day it left the premises of CIS-bio in Saclay. (A.C.)

  14. Comparative assessment of spent nuclear fuel transportation routes using risk factors and a geographic information system

    International Nuclear Information System (INIS)

    Toth, D.M.

    1996-01-01

    The assessment of potential alternative routes was simplified through the use of six comparative risk factors evaluated using detailed, route-specific data. The route and environmental attributes varied strongly with location and were developed from national, state, and local sources. The six comparative factors were risk measures of incident-free transportation radiation exposure, radiological accident population exposure, nonradiological accidents, contamination of environmental sensitive areas, environmental justice for minority populations, and environmental justice for low-income populations. An assessment of four real North-Central Florida routes provided a sample implementation of the analysis tools and risk factors. The assessment routes, consisting of common beginning and end locations, included an interstate highway, a rural highway, a mostly urban highway, and a combination interstate highway with rural bypass. This route comparative assessment study predicted that the interstate highway, despite a higher population density, greater traffic volume, and greater number of vehicular fatality accidents, would present the lowest cumulative risk. On the contrary, the rural highway route, characterized as having the lowest population density, minimal vehicle traffic volume, and the lowest percentages of minority and low-income populations, displayed the highest cumulative risk measure. Factors contributing to the high risk for the rural highway route included greater route length, higher vehicular fatality accident rates per vehicle mile traveled, and the close proximity to environmentally sensitive areas. This route comparative assessment study predicted that the interstate highway, despite a higher population density, greater traffic volume, and greater number of vehicular fatality accidents, would present the lowest cumulative risk. On the contrary, the rural highway route, characterized as having the lowest population density, minimal vehicle traffic volume

  15. Management of the process of nuclear transport

    International Nuclear Information System (INIS)

    Requejo, P.

    2015-01-01

    Since 1996 ETSA is the only Spanish logistics operator specialized on servicing the nuclear and radioactive industry. Nowadays ETSA has some technological systems specifically designed for the management of nuclear transports. These tools have been the result of the analysis of multiple factors involved in nuclear shipments, of ETSAs wide experience as a logistics operator and the search for continuous improvement. (Author)

  16. GROUND TRANSPORTATION OF NUCLEAR PROPULSION STAGES

    Energy Technology Data Exchange (ETDEWEB)

    Marjon, P. L.

    1963-08-15

    The results of studies on transportation problems associated with the development and testing of nuclear rocket powered space vehicles at the static test size are presented. Factors involved in selecting a transport mode are discussed. Radiation shutdown considerations and a conceptual transporter capable of handling test articles of foreseeable size are examined. (D.C.W.)

  17. 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.)

  18. Management of the process of nuclear transport; Gestion del proceso de transporte nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Requejo, P.

    2015-07-01

    Since 1996 ETSA is the only Spanish logistics operator specialized on servicing the nuclear and radioactive industry. Nowadays ETSA has some technological systems specifically designed for the management of nuclear transports. These tools have been the result of the analysis of multiple factors involved in nuclear shipments, of ETSAs wide experience as a logistics operator and the search for continuous improvement. (Author)

  19. Fasting Induces Nuclear Factor E2-Related Factor 2 and ATP-Binding Cassette Transporters via Protein Kinase A and Sirtuin-1 in Mouse and Human

    Science.gov (United States)

    Kulkarni, Supriya R.; Donepudi, Ajay C.; Xu, Jialin; Wei, Wei; Cheng, Qiuqiong C.; Driscoll, Maureen V.; Johnson, Delinda A.; Johnson, Jeffrey A.; Li, Xiaoling

    2014-01-01

    Abstract Aims: The purpose of this study was to determine whether 3′-5′-cyclic adenosine monophosphate (cAMP)-protein kinase A (PKA) and Sirtuin-1 (SIRT1) dependent mechanisms modulate ATP-binding Cassette (ABC) transport protein expression. ABC transport proteins (ABCC2–4) are essential for chemical elimination from hepatocytes and biliary excretion. Nuclear factor-E2 related-factor 2 (NRF2) is a transcription factor that mediates ABCC induction in response to chemical inducers and liver injury. However, a role for NRF2 in the regulation of transporter expression in nonchemical models of liver perturbation is largely undescribed. Results: Here we show that fasting increased NRF2 target gene expression through NRF2- and SIRT1–dependent mechanisms. In intact mouse liver, fasting induces NRF2 target gene expression by at least 1.5 to 5-fold. In mouse and human hepatocytes, treatment with 8-Bromoadenosine-cAMP, a cAMP analogue, increased NRF2 target gene expression and antioxidant response element activity, which was decreased by the PKA inhibitor, H-89. Moreover, fasting induced NRF2 target gene expression was decreased in liver and hepatocytes of SIRT1 liver-specific null mice and NRF2-null mice. Lastly, NRF2 and SIRT1 were recruited to MAREs and Antioxidant Response Elements (AREs) in the human ABCC2 promoter. Innovation: Oxidative stress mediated NRF2 activation is well described, yet the influence of basic metabolic processes on NRF2 activation is just emerging. Conclusion: The current data point toward a novel role of nutrient status in regulation of NRF2 activity and the antioxidant response, and indicates that cAMP/PKA and SIRT1 are upstream regulators for fasting-induced activation of the NRF2-ARE pathway. Antioxid. Redox Signal. 20, 15–30. PMID:23725046

  20. Transport Properties in Nuclear Pasta

    Science.gov (United States)

    Caplan, Matthew; Horowitz, Charles; Berry, Donald; da Silva Schneider, Andre

    2016-09-01

    At the base of the inner crust of neutron stars, where matter is near the nuclear saturation density, nuclear matter arranges itself into exotic shapes such as cylinders and slabs, called `nuclear pasta.' Lepton scattering from these structures may govern the transport properties of the inner crust; electron scattering from protons in the pasta determines the thermal and electrical conductivity, as well as the shear viscosity of the inner crust. These properties may vary in pasta structures which form at various densities, temperatures, and proton fractions. In this talk, we report on our calculations of lepton transport in nuclear pasta and the implication for neutron star observables.

  1. Nuclear materials transport in France

    International Nuclear Information System (INIS)

    Korycanek, J.

    1990-01-01

    About 1.5 million tons of uranium ore, 8000 tons of uranium concentrate, 1000 tons of UF 6 , 340 spent fuel containers, and 30 000 m 3 of nuclear wastes are transported annually by trucks, trains and ships in France. Annual costs of this transportation amount to 500-600 million FRF, and about 200 employees are engaged in this activity. Transportation of spent fuel to the La Hague and Marcoule fuel reprocessing plants, and the transport of plutonium are dealt with in detail. (Z.M.). 5 figs., 1 ref

  2. 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

  3. Factors affecting nuclear development

    International Nuclear Information System (INIS)

    Stevens, G.H.; Girouard, P.

    1995-01-01

    Among the factors affecting nuclear development, some depend more or less on public authorities, but many are out of public authorities control (foreign policies, market and deregulation, socials and environmental impacts, public opinion). As far as possible, the following study tries to identify those factors. (D.L.). 2 photos

  4. Perspective on transporting nuclear materials

    International Nuclear Information System (INIS)

    Wymer, R.G.

    1975-01-01

    An evaluation is made of the material flow to be expected up to the year 2000 to and from the various steps in the nuclear cycle. These include the reactors, reprocessing plants, enrichment plants, U mills, U conversion plants, and fuel fabrication plants. A somewhat more-detailed discussion is given of the safety engineering that goes into the design of containers and packages and the selection of the mode of transportation. The relationship of shipping to siting and transportation accidents is considered briefly

  5. 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.)

  6. Transport insurance of unirradiated nuclear fuels

    International Nuclear Information System (INIS)

    Matto, H.

    1985-01-01

    Special conditions must be taken into account in transport insurance for nuclear materials even if the nuclear risk involved is negligible, as in shipments of unirradiated nuclear fuels. The shipwreck of the 'Mont Louis' has raised a number of open points which must be solved pragmatically within the framework of transport insurance. Some proposals are outlined in the article. (orig.) [de

  7. 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

  8. Transport and nuclear waste disposal

    International Nuclear Information System (INIS)

    Wild, E.

    1999-01-01

    The author assesses both past and future of nuclear waste disposal in Germany. The failure of the disposal concept is, he believes, mainly the fault of the Federal Government. On the basis of the Nuclear Energy Act, the government is obliged to ensure that ultimate-storage sites are established and operated. Up to the present, however, the government has failed - apart from the episode in Asse and Morsleben and espite existing feasible proposals in Konrad and Gorleben - to achieve this objective. This negative development is particularly evident from the projects which have had to be prematurely abandoned. The costs of such 'investment follies' meanwhile amount to several billion DM. At least 92% of the capacity in the intermediate-storage sites are at present unused. Following the closure of the ultimate-storage site in Morsleben, action must be taken to change over to long-term intermediate-storage of operational waste. The government has extensive intermediate-storage capacity at the intermediate-storage site Nord in Greifswald. There, the wate originally planned for storage in Morsleben could be intermediately stored at ERAM-rates. Nuclear waste transportation, too, could long ago have been resumed, in the author's view. For the purpose of improving the transport organisation, a new company was founded which represents exclusively the interests of the reprocessing firms at the nuclear power stations. The author's conclusion: The EVU have done their homework properly and implemented all necessary measures in order to be able to resume transport of fuel elements as soon as possible. The generating station operators favour a solution based upon agreement with the Federal Government. The EVU have already declared their willingness - in the event of unanimous agreement - to set up intermediate-storage sites near the power stations. The ponds in the generating stations, however, are unsuitable for use as intermediate-storage areas. If intermediate-storage areas for

  9. 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)

  10. Activity transport in nuclear reactors

    International Nuclear Information System (INIS)

    Narasimhan, S.V.

    2000-01-01

    The chemistry of the primary coolant is such that the general material loss is immeasurably low. However, the generation of radioactive corrosion products in the coolant, their transportation and distribution to different out of core surfaces occur irrevocably through the life cycle of the reactor. This phenomena leading to the build up of radiation field, which is unique to the nuclear reactor systems, is the only major problem of any significance. Minimization of this phenomenon can be done by many ways. The processes involved in the mechanism of activity transport are quite complex and are not at all thoroughly understood. The codes that have been developed so far use many empirical coefficients for some of the rate processes, which are either partially justified by simulated experimental studies or supported theoretically. In a multi-metal system like that of the reactor, the corrosion rates or release rates need not be similar especially in reactors like PHWRs. The mechanisms involved in the formation of protective oxide coating are quite complex to model in a simplified manner. The paper brings out some these features involved in the activity transport modeling and analyses the need for extensive field related experimental work to substantiate the model. (author)

  11. Transport description of damped nuclear reactions

    International Nuclear Information System (INIS)

    Randrup, J.

    1984-01-01

    This lecture series is concerned with the transport description of damped nuclear reactions. Part 1 is an elementary introduction to the general transport theory of nuclear dynamics. It can be read without any special knowledge of the field, although basic quantum mechanics is required for the formal derivation of the general expressions for the transport coefficients. The results can also be used in a wider context than the present one. Part 2 gives the student an up-to-date orientation about recent progress in the understanding of the angular-momentum variables in damped reactions. The emphasis is here on the qualitative understanding of the physics rather than the, at times somewhat tedious, formal derivations. More detailed presentations are due to be published soon. By necessity entire topics have been omitted. For example, no discussion is given of the calculation of the form factors, and the several instructive applications of the theory to transport of mass and change are not covered at all. For these topics they refer to the literature. It is hoped that the present notes provide a sufficient basis to make the literature on the subject accessible to the student

  12. Tritium transport around nuclear facilities

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.; Sweet, C.W.

    1981-01-01

    The transport and cycling of tritium around nuclear facilities is reviewed with special emphasis on studies at the Savannah River Laboratory, Aiken, South Carolina. These studies have shown that the rate of deposition from the atmosphere, the site of deposition, and the subsequent cycling are strongly influenced by the compound with which the tritium is associated. Tritiated hydrogen is largely deposited in the soil, while tritiated water is deposited in the greatest quantity in the vegetation. Tritiated hydrogen is converted in the soil to tritiated water that leaves the soil slowly, through drainage and transpiration. Tritiated water deposited directly to the vegetation leaves the vegetation more rapidly after exposure. Only a small part of the tritium entering the vegetation becomes bound in organic molecules. However, it appears tht the existence of soil organic compounds with tritium concentrations greater than the equilibrium concentration in the associated water can be explained by direct metabolism of tritiated hydrogen in vegetation

  13. Tritium transport around nuclear faciliteis

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.; Sweet, C.W.

    1982-01-01

    The transport and cycling of tritium around nuclear facilities is reviewed with special emphasis on studies at the Savannah River Laboratory, Aiken, South Carolina. These studies have shown that the rate of deposition from the atmosphere, the site of deposition, and the subsequent cycling are strongly influenced by the compound with which the tritium is associated. Tritiated hydrogen is largely deposited in the soil, while tritiated water is deposited in the greatest quantity in the vegetation. Tritiated hydrogen is converted in the soil to tritiated water that leaves the soil slowly, through drainage and transpiration. Tritiated water deposited directly to the vegetation leaves the vegetation more rapidly after exposure. Only a small part of the tritium entering the vegetation becomes bound in organic molecules. However, it appears that the existence of soil organic compounds with tritium concentrations greater than the equilibrium concentration in the associated water can be explained by direct metabolism of tritiated hydrogen in vegetation. (J.P.N.)

  14. 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

  15. Transport device for nuclear fuel powder

    International Nuclear Information System (INIS)

    Adelmann, M.

    1987-01-01

    The transport device for nuclear fuel powder, which does not disintegrate during transport, has a transport pipe which starts with its entry end from the floor or a closed container and opens with its outlet end at the top into a closed separation container connect via a powder filter to a suction pump. By alternate regular opening and closing of a first control valve for transport gas fitted to a transport pipe to a supply duct and a second control valve for transport gas fitted to the container to an additional supply duct, alternating plugs of nuclear fuel powder and transport gas cushions are formed and are transported to the outlet end of the transport pipe. (orig./HP) [de

  16. Release of radioactive materials from nuclear power plants. Report No. 2. Dispersion mechanisms, transport paths, and concentration factors for radionuclides in the cooling water recipient

    International Nuclear Information System (INIS)

    Rygg, B.

    The discharge of radioactive materials in the cooling water from a nuclear power plant may involve consequences for the interests involved in the recipient and its organisms. Of special interest is the transport of radionuclides in water, sediments, and organisms to man. The most important elements are H, Na, P, Cr, Mn, Fe, Co, Zn, Sr, Mo, Ru, I, Cs, and Ce. Metals with high affinity for organic material will be sorbed to sediments rich in organic material, while other elements will be enriched in algaes and arrive in the sediment through decay or excrement. Elements in particulate form will normally precipitate. Ions will generally not be enriched in sediments. Marine organisms may take up nuclides directly from the water and from food. The concentration factor is dependent on the chemical properties of the element and the physiology of the organism. The occurrence of elements in water and organisms in the Oslofjord district is poorly known and tables have therefore been derived from literature data to indicate the concentration factors to be expected

  17. 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

  18. Transport packages for nuclear material and waste

    International Nuclear Information System (INIS)

    1997-01-01

    The regulations and responsibilities concerning the transport packages of nuclear materials and waste are given in the guide. The approval procedure, control of manufacturing, commissioning of the packaging and the control of use are specified. (13 refs.)

  19. The maritime transport of nuclear substances

    International Nuclear Information System (INIS)

    Los Santos, A. de; Corretjer, L.

    1976-01-01

    In view of the fact that the regulation of maritime transport of nuclear materials comes under both maritime and nuclear law has raised problems which it was attempted to solve by specific standards. As regards the prevention of nuclear hazards, these standards are based on the recommendations of competent international organizations, while concerning compensation of nuclear damage, a Convention which has just come into force lays down that nuclear law has priority over maritime law. Despite the progress made, a study of the situation in this field shows that it can be further improved. (N.E.A.) [fr

  20. 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.)

  1. Power peaking nuclear reliability factors

    International Nuclear Information System (INIS)

    Hassan, H.A.; Pegram, J.W.; Mays, C.W.; Romano, J.J.; Woods, J.J.; Warren, H.D.

    1977-11-01

    The Calculational Nuclear Reliability Factor (CNRF) assigned to the limiting power density calculated in reactor design has been determined. The CNRF is presented as a function of the relative power density of the fuel assembly and its radial local. In addition, the Measurement Nuclear Reliability Factor (MNRF) for the measured peak hot pellet power in the core has been evaluated. This MNRF is also presented as a function of the relative power density and radial local within the fuel assembly

  2. Transport of nuclear substances in Canada

    Energy Technology Data Exchange (ETDEWEB)

    Faille, S. [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

    2015-07-01

    CNSC Regulates all Nuclear-related facilities and activities including Uranium mines and mill;, uranium fuel fabrication and processing; nuclear power plants; nuclear substance processing; industrial and medical applications; nuclear research and education; transport; export/import control; security and safeguards and waste management facilities. Our mandate is to protect the health, safety and security of Canadians and the environment, and implement Canada's International commitments on the peaceful use of nuclear energy and disseminate objective scientific, technical and regulatory information to the public. Based on the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material, 1996 Edition, Revised and currently being revised to reflect the 2012 edition of the IAEA Regulations.

  3. Transport of nuclear substances in Canada

    International Nuclear Information System (INIS)

    Faille, S.

    2015-01-01

    CNSC Regulates all Nuclear-related facilities and activities including Uranium mines and mill;, uranium fuel fabrication and processing; nuclear power plants; nuclear substance processing; industrial and medical applications; nuclear research and education; transport; export/import control; security and safeguards and waste management facilities. Our mandate is to protect the health, safety and security of Canadians and the environment, and implement Canada's International commitments on the peaceful use of nuclear energy and disseminate objective scientific, technical and regulatory information to the public. Based on the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material, 1996 Edition, Revised and currently being revised to reflect the 2012 edition of the IAEA Regulations.

  4. Legal aspects of transport of nuclear materials

    International Nuclear Information System (INIS)

    Jacobsson, Mans.

    The Paris Convention and the Brussels Supplementary Convention are briefly discussed and other conventions in the field of civil liability for nuclear damage are mentioned: the Vienna Convention, the Nuclear Ships Convention and the 1971 Convention relating to civil liability in the field of maritime carriage of nuclear material. Legislation on civil liability in the Nordic countries, which is based on the Paris Convention and the Supplementary Convention is discussed, notably the principle of channelling of liability and exceptions from that principle due to rules of liability in older transport conventions and certain problems due to the limited geographical scope of the Paris Convention and the Supplementary Convention. Insurance problems arising in connection with transport of nuclear materials are surveyed and an outline is given of the administrative provisions concerning transport (based on the IAEA transport regulations) which govern transport of radioactive materials by different means: road, rail, sea and air. Finally, the 1968 Treaty on the Non-Proliferation of Nuclear Weapons is discussed. (NEA) [fr

  5. 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

  6. CTCN: Colloid transport code -- nuclear

    International Nuclear Information System (INIS)

    Jain, R.

    1993-01-01

    This report describes the CTCN computer code, designed to solve the equations of transient colloidal transport of radionuclides in porous and fractured media. This Fortran 77 package solves systems of coupled nonlinear differential-algebraic equations with a wide range of boundary conditions. The package uses the Method of Lines technique with a special section which forms finite-difference discretizations in up to four spatial dimensions to automatically convert the system into a set of ordinary differential equations. The CTCN code then solves these equations using a robust, efficient ODE solver. Thus CTCN can be used to solve population balance equations along with the usual transport equations to model colloid transport processes or as a general problem solver to treat up to four-dimensional differential-algebraic systems

  7. Nuclear transportation: The global vision

    International Nuclear Information System (INIS)

    Lowry, D.; Blowers, A.

    1996-01-01

    The movement of nuclear materials - spent fuel, plutonium and uranium and radioactive wastes - has become an issue of international political significance. It has generated considerable attention from a developing network of NGOs focussing on movements between France and Japan. The paper discusses the conflicts and their implications for six basic principles of radioactive waste management

  8. Overview of nuclear materials transportation

    International Nuclear Information System (INIS)

    Grella, A.W.

    1986-01-01

    This presentation is an overview of transportation as it relates to one specific type of material, low specific activity (LSA) material. It is the predominant type of material that fits into the low-level waste category. An attempt is made to discuss how LSA is regulated, setting forth the requirements. First the general scheme of regulations are reviewed. In addition future changes in the regulations which will affect transportation of LSA materials and, which quite likely, will have an impact on R and D needs in this area are presented

  9. The Next Nuclear Gamble. Transportation and storage of nuclear waste

    International Nuclear Information System (INIS)

    Resnikoff, M.

    1985-01-01

    The Next Nuclear Gamble examines risks, costs, and alternatives in handling irradiated nuclear fuel. The debate over nuclear power and the disposal of its high-level radioactive waste is now nearly four decades old. Ever larger quantities of commercial radioactive fuel continue to accumulate in reactor storage pools throughout the country and no permanent storage solution has yet been designated. As an interim solution, the government and utilities prefer that radioactive wastes be transported to temporary storage facilities and subsequently to a permanent depository. If this temporary and centralized storage system is implemented, however, the number of nuclear waste shipments on the highway will increase one hundredfold over the next fifteen years. The question directly addressed is whether nuclear transport is safe or represents the American public's domestic nuclear gamble. This Council on Economic Priorities study, directed by Marvin Resnikoff, shows on the basis of hundreds of government and industry reports, interviews and surveys, and original research, that transportation of nuclear materials as currently practiced is unsafe

  10. GLONASS satellite monitoring of nuclear transports

    International Nuclear Information System (INIS)

    Davydov, Yu.L.

    2012-01-01

    In 2011 Rosatom has made the decision to create the industry-wide automated system for monitoring of transports of radioactive substances (RS) and wastes (RAW), as well as hazardous loads by rail and automobile, based upon the same hardware as used by the GLONASS satellite navigation system - the so-called ASBT-GLONASS system. The new system will use the same technical infrastructure as the existing operational Automated System for Safe Transport of Nuclear Materials of Categories I and II (ASBT). The ASBT structure includes a network of control centres fitted with automation and communication hardware. In addition, ASBT includes technical complexes installed upon transport vehicles intended for nuclear material transport. In order to identify transport vehicle location, the GLONASS/GPS (GALS-P-ASBT) satellite navigational receiver device is used, it is developed especially for ASBT systems taking in account information security requirements. By now the basic software and hardware complex ASBT-GLONASS has been created (equipment to be carried on-board the transport vehicle loaded with RS and RAW, as well as the transport control stations) that supports transport monitoring and transmission of an emergency signal to control stations of companies which deal with RS and RAW transportation [ru

  11. Uncontrolled transport of nuclear materials

    International Nuclear Information System (INIS)

    Wassermann, U.

    1985-01-01

    An account is given of international transport of plutonium, uranium oxides, uranium hexafluoride, enriched uranium and irradiated fuel for reprocessing. Referring to the sinking of the 'Mont Louis', it is stated that the International Maritime Organization has been asked by the National Union of Seamen and 'Greenpeace' to bar shipment of radioactive material until stricter international safety regulations are introduced. (U.K.)

  12. Next nuclear gamble: transportation and storage of nuclear waste

    International Nuclear Information System (INIS)

    Resnikoff, M.

    1983-01-01

    Accidents during transport of nuclear waste are more threatening - though less likely - than a reactor meltdown because transportation accidents could occur in the middle of a populous city, affecting more people and property than a plant accident, according to the Council on Economic Priorities, a non-profit public service research organization. Transportation, as presently practiced, is unsafe. Shipping containers, called casks, are poorly designed and constructed, CEP says. The problem needs attention because the number of casks filled with nuclear waste on the nation's highways could increase a hundred times during the next 15 years under the Nuclear Waste Policy Act of 1982, which calls for storage areas. Recommendations, both technical and regulatory, for reducing the risks are presented

  13. Problems relating to international transport of nuclear fuels

    International Nuclear Information System (INIS)

    Timm, U.E.

    1985-01-01

    Owing to the tremendous geographic distances between uranium deposits of interest, to the various degrees of sophistication of nuclear industry in industrialized countries and to the close international cooperation in the field of nuclear energy, safe international transports, physical protection and transport handling play an important role. It is suggested to better coordinate the activities of nuclear power plant operators, the nuclear industry and specialized transport companies with respect to all national and international issues of nuclear fuel transports. (DG) [de

  14. Institutional issues affecting transportation of nuclear materials

    International Nuclear Information System (INIS)

    Reese, R.T.; Luna, R.E.

    1980-01-01

    The institutional issues affecting transportation of nuclear materials in the United States represent significant barriers to meeting future needs in the transport of radioactive waste materials to their ultimate repository. While technological problems which must be overcome to perform such movements seem to be within the state-of-the-art, the timely resolution of these institutional issues seems less assured. However, the definition of these issues, as attempted in this paper, together with systematic analysis of cause and possible solutions are the essential elements of the Transportation Technology Center's Institutional Issues Program

  15. Energetics of Transport through the Nuclear Pore Complex.

    Directory of Open Access Journals (Sweden)

    Ali Ghavami

    Full Text Available Molecular transport across the nuclear envelope in eukaryotic cells is solely controlled by the nuclear pore complex (NPC. The NPC provides two types of nucleocytoplasmic transport: passive diffusion of small molecules and active chaperon-mediated translocation of large molecules. It has been shown that the interaction between intrinsically disordered proteins that line the central channel of the NPC and the transporting cargoes is the determining factor, but the exact mechanism of transport is yet unknown. Here, we use coarse-grained molecular dynamics simulations to quantify the energy barrier that has to be overcome for molecules to pass through the NPC. We focus on two aspects of transport. First, the passive transport of model cargo molecules with different sizes is studied and the size selectivity feature of the NPC is investigated. Our results show that the transport probability of cargoes is significantly reduced when they are larger than ∼5 nm in diameter. Secondly, we show that incorporating hydrophobic binding spots on the surface of the cargo effectively decreases the energy barrier of the pore. Finally, a simple transport model is proposed which characterizes the energy barrier of the NPC as a function of diameter and hydrophobicity of the transporting particles.

  16. Factorization of Transport Coefficients in Macroporous Media

    DEFF Research Database (Denmark)

    Shapiro, Alexander; Stenby, Erling Halfdan

    2000-01-01

    We prove the fundamental theorem about factorization of the phenomenological coefficients for transport in macroporous media. By factorization we mean the representation of the transport coefficients as products of geometric parameters of the porous medium and the parameters characteristic...

  17. Update of Nuclear Waste Policy Act transportation activities

    International Nuclear Information System (INIS)

    Callaghan, E.F.

    1987-01-01

    As directed by the Nuclear Waste Policy Act of 1982 (NWPA), the Department of Energy (DOE) is developing a nationwide system for transporting spent nuclear fuel and high-level radioactive waste from commercial power plants to deep geologic repositories for disposal. Plans for the transportation system will consider the following factors: the President's 1985 decision to co-locate some defense high-level waste with commercial waste in a repository, the NWPA requirement that the private sector be used to the fullest extent possible in developing and operating the system, and the possible approval by Congress of the DOE's proposal for a Monitored Retrievable Storage (MRS) facility, submitted in March 1987. (The MRS, if approved, would provide for the consolidation, packaging, and perhaps the temporary storage of spent fuel from reactors.) The ''Transportation Business Plan'', published in January 1986, reflects these considerations. The transportation system, when operational, will consist of two elements: (1) the cask system, which includes the transportation casks, the vehicular conveyances, tie-downs, and associated equipment for handling the casks; and (2) the transportation support system which is comprised of facilities, equipment, and services to support waste transportation. Development of the transportation system incorporates the following work elements: operational planning, support systems development, cash system development, systems analysis, and institutional activities. This paper focusses on the technical aspects of the system

  18. Transport of proximity nuclear radioactive materials

    International Nuclear Information System (INIS)

    2010-01-01

    This brief publication gives an overview of the international and national regulatory framework for the transport of radioactive substances, outlines progress orientations identified by the French Nuclear Safety Authority (ASN), indicates the parcel classification and shipment radiological criteria, and how to declare events occurring during the transport of radioactive substances, which number to phone in case of a radiological incident. Finally, the role of the ASN and its field of activity in matters of control are briefly presented with a table of its office addresses in France

  19. Transport description of damped nuclear reactions

    International Nuclear Information System (INIS)

    Randrup, J.

    1983-04-01

    Part I is an elementary introduction to the general transport theory of nuclear dynamics. It can be read without any special knowledge of the field, although basic quantum mechanics is required for the formal derivation of the general expression for the transport coefficients. The results can also be used in a wider context than the present one. Part II gives the student an up-to-date orientation about recent progress in the understanding of the angular-momentum variables in damped reactions. The emphasis is here on the qualitative understanding of the physics rather than the, at times somewhat tedious, formal derivations

  20. Liability for international nuclear transport: an overview

    International Nuclear Information System (INIS)

    Brown, O.F.; Horbach, N.

    2000-01-01

    Many elements can bear on liability for nuclear damage during transport. For example, liability may depend upon a number of facts that may be categorized as follows: shipment, origin or destination of the shipment, deviation from the planed route, temporary storage incidental to carriage; content of shipment, type of nuclear material involved, whether its origin is civilian or defence-related; sites of accident, number and type of territories damaged (i.e. potential conventions involved), applicable territorial limits, exclusive economic zone, high seas, etc.; nature of damages, personal injury, property damage, damage to the means of carriage, indirect damage, preventive measures, environmental cleanup or retrieval at seas, res communis, transboundary damages etc.; victims involved, nationality and domiciles of victims; jurisdiction, flag (for ships) or national registration (for aircraft) of the transporting vessel, courts of one or more states may have (or assert) jurisdiction to hear claims, and may have to determine what law to apply to a particular accident; applicable law, the applicability laws and/or international nuclear liability conventions; the extent to which any applicable convention has been implemented or modified by domestic legislation, conflicts with the 1982 Law of the Sea Convention or other applicable international agreements, and finally, also written agreements between installation operators and carriers can define applicable law as well as responsibilities. Harmonizing nuclear liability protection and applying it to additional international shipments would be facilitated by more countries being in treaty relations with each other as soon as possible. Adherence to an international convention by more countries (including China, Russia, the United States, etc.) would promote the open flow of services and advanced technology, and better facilitate international transport. The conventions protect the public, harmonize legislation in the

  1. The changing nature of nuclear transport

    International Nuclear Information System (INIS)

    Brobst, W.A.

    1976-01-01

    The IAEA's efforts in transport safety have been proven through 25 years of nearly accident-free transport, with no evidence of death or injury from the nuclear characteristics of those shipments. Much testing has been done over the last five years to verify the technical bases for the IAEA Regulations. Rather than being complacent with the past, we should instead see ourselves at a turning point for the solution of problems coming up in the next few years. The number of shipments will increase drastically and this will result in changes of risk levels. A number of critical problems will be discussed: (1) lack of public acceptance of nuclear shipment safety; (2) transport safeguards; (3) incompleteness in the IAEA package damage tests; (4) need for innovative technology for spent fuel casks; (5) reduction of radiation dose to the public; (6) quality assurance; (7) engineering analyses versus scale-model and full-scale testing; and (8) transport controls. A recommendation is made to the IAEA to set up immediately a study group to define these problems, list alternatives and options, and recommend corrective actions. (author)

  2. Current trends in nuclear material transportation

    International Nuclear Information System (INIS)

    Ravenscroft, Norman; Oshinowo, Franchone

    1997-01-01

    The business of radioactive material transportation has evolved considerably in the past 40 years. Current practices reflect extensive international experience in handling radioactive cargo within a mature and tested regulatory framework. Nevertheless, new developments continue to have an impact on how shipments of nuclear material are planned and carried out. Entities involved in the transport of radioactive materials must keep abreast of these developments and work together to find innovative solutions to ensure that safe, smooth transport activities may continue. Several recent trends in the regulatory environment and political atmosphere require attention. There are four key trends that we'll be examining today: 1) the reduction in the pool of available commercial carriers; 2) routing restrictions; 3) package validation issues; and 4) increasing political sensitivities. Careful planning and cooperative measures are necessary to alleviate problems in each of these areas. (author)

  3. Thermal analysis of transportation packaging for nuclear spent fuel

    International Nuclear Information System (INIS)

    Akamatsu, Hiroshi; Taniuchi, Hiroaki

    1989-01-01

    Safety analysis of transportation packaging for nuclear spent fuel comprises structural, thermal, containment, shielding and criticality factors, and the safety of a packaging is verified by these analyses. In thermal analysis, the temperature of each part of the packaging is calculated under normal and accident test conditions. As an example of thermal analysis, the temperature distribution of a packaging being subjected to a normal test was calculated by the TRUMP code and compared with measured data. (author)

  4. Nuclear transport of heat shock proteins in stressed cells

    International Nuclear Information System (INIS)

    Chughtai, Zahoor Saeed

    2001-01-01

    Nuclear import of proteins that are too large to passively enter the nucleus requires soluble factors, energy , and a nuclear localization signal (NLS). Nuclear protein transport can be regulated, and different forms of stress affect nucleocytoplasmic trafficking. As such, import of proteins containing a classical NLS is inhibited in starving yeast cells. In contrast, the heat shock protein hsp70 Ssa4p concentrates in nuclei upon starvation. Nuclear concentration of Ssa4p in starving cells is reversible, and transfer of nutrient-depleted cells to fresh medium induces Ssa4p nuclear export. This export reaction represents an active process that is sensitive to oxidative stress. Upon starvation, the N-terminal domain of Ssa4p mediates Ssa4p nuclear accumulation, and a short hydrophobic sequence, termed Star (for starvation), is sufficient to localize the reporter proteins green fluorescent protein or β-gaIactosidase to nuclei. To determine whether nuclear accumulation of Star-β-galactosidase depends on a specific nuclear carrier, I have analyzed its distribution in mutant yeast strains that carry a deletion of a single β-importin gene. With this assay I have identified Nmd5p as a β-importin required to concentrate Star-β-galactosidase in nuclei of stationary phase cells. (author)

  5. Nuclear transport of heat shock proteins in stressed cells

    Energy Technology Data Exchange (ETDEWEB)

    Chughtai, Zahoor Saeed

    2001-07-01

    Nuclear import of proteins that are too large to passively enter the nucleus requires soluble factors, energy , and a nuclear localization signal (NLS). Nuclear protein transport can be regulated, and different forms of stress affect nucleocytoplasmic trafficking. As such, import of proteins containing a classical NLS is inhibited in starving yeast cells. In contrast, the heat shock protein hsp70 Ssa4p concentrates in nuclei upon starvation. Nuclear concentration of Ssa4p in starving cells is reversible, and transfer of nutrient-depleted cells to fresh medium induces Ssa4p nuclear export. This export reaction represents an active process that is sensitive to oxidative stress. Upon starvation, the N-terminal domain of Ssa4p mediates Ssa4p nuclear accumulation, and a short hydrophobic sequence, termed Star (for starvation), is sufficient to localize the reporter proteins green fluorescent protein or {beta}-gaIactosidase to nuclei. To determine whether nuclear accumulation of Star-{beta}-galactosidase depends on a specific nuclear carrier, I have analyzed its distribution in mutant yeast strains that carry a deletion of a single {beta}-importin gene. With this assay I have identified Nmd5p as a {beta}-importin required to concentrate Star-{beta}-galactosidase in nuclei of stationary phase cells. (author)

  6. Equipment transporter for nuclear steam generator

    International Nuclear Information System (INIS)

    Hayes, L.R.

    1987-01-01

    A transporter is described for use in a steam generator of a nuclear power installation. The generator is essentially a heat exchanger having a vertically extended shell. Across the lower portion extends a horizontal tube sheet having an upper surface which supports a bundle of vertically extending tubes forming a limited annular space with the inside of the shell wall and the upper surface. An opening of limited dimensions through the shell wall gains manual access to the limited annular space. The transporter has means for locating and removing solid debris from the upper surface of the tube sheet in the annular space and has a means for assembly and disassembly of the transporter so that it may be manually passed through the shell opening to and from a position on the upper surface of the tube sheet in the annular space. The transporter includes: a body; at least three wheels mounted on the body for engaging the upper surface of the tube sheet; a first motor mounted on the body drivingly connected to the wheels for moving the transporter along the upper surface of the tube sheet in the annular space; a remotely operated means on the body for locating solid debris on the upper surface of the tube sheet; and means for securing and removing solid debris on the upper surface of the tube sheet located by the means for locating

  7. Transverse-momentum spectra and nuclear modification factor using Boltzmann Transport Equation with flow in Pb+Pb collisions at √(s{sub NN}) = 2.76 TeV

    Energy Technology Data Exchange (ETDEWEB)

    Tripathy, Sushanta; Khuntia, Arvind; Tiwari, Swatantra Kumar; Sahoo, Raghunath [Indian Institute of Technology Indore, Discipline of Physics, School of Basic Sciences, Indore (India)

    2017-05-15

    In the continuation of our previous work, the transverse-momentum (p{sub T}) spectra and nuclear modification factor (R{sub AA}) are derived using the relaxation time approximation of Boltzmann Transport Equation (BTE). The initial p{sub T}-distribution used to describe p + p collisions has been studied with the perturbative-Quantum Chromodynamics (pQCD) inspired power-law distribution, Hagedorn's empirical formula and with the Tsallis non-extensive statistical distribution. The non-extensive Tsallis distribution is observed to describe the complete range of the transverse-momentum spectra. The Boltzmann-Gibbs Blast Wave (BGBW) distribution is used as the equilibrium distribution in the present formalism, to describe the p{sub T}-distribution and nuclear modification factor in nucleus-nucleus collisions. The experimental data for Pb+Pb collisions at √(s{sub NN}) = 2.76 TeV at the Large Hadron Collider at CERN have been analyzed for pions, kaons, protons, K{sup *0} and φ. It is observed that the present formalism while explaining the transverse-momentum spectra up to 5 GeV/c, explains the nuclear modification factor very well up to 8 GeV/c in p{sub T} for all these particles except for protons. R{sub AA} is found to be independent of the degree of non-extensivity, q{sub pp} after p{sub T} ∝ 8 GeV/c. (orig.)

  8. Loss of hepatocyte-nuclear-factor-4alpha affects colonic ion transport and causes chronic inflammation resembling inflammatory bowel disease in mice.

    Directory of Open Access Journals (Sweden)

    Mathieu Darsigny

    Full Text Available BACKGROUND: Hnf4alpha, an epithelial specific transcriptional regulator, is decreased in inflammatory bowel disease and protects against chemically-induced colitis in mice. However, the precise role of this factor in maintaining normal inflammatory homeostasis of the intestine remains unclear. The aim of this study was to evaluate the sole role of epithelial Hnf4alpha in the maintenance of gut inflammatory homeostasis in mice. METHODOLOGY/PRINCIPAL FINDINGS: We show here that specific epithelial deletion of Hnf4alpha in mice causes spontaneous chronic intestinal inflammation leading to focal areas of crypt dropout, increased cytokines and chemokines secretion, immune cell infiltrates and crypt hyperplasia. A gene profiling analysis in diseased Hnf4alpha null colon confirms profound genetic changes in cell death and proliferative behaviour related to cancer. Among the genes involved in the immune protection through epithelial barrier function, we identify the ion transporter claudin-15 to be down-modulated early in the colon of Hnf4alpha mutants. This coincides with a significant decrease of mucosal ion transport but not of barrier permeability in young animals prior to the manifestation of the disease. We confirm that claudin-15 is a direct Hnf4alpha gene target in the intestinal epithelial context and is down-modulated in mouse experimental colitis and inflammatory bowel disease. CONCLUSION: Our results highlight the critical role of Hnf4alpha to maintain intestinal inflammatory homeostasis during mouse adult life and uncover a novel function for Hnf4alpha in the regulation of claudin-15 expression. This establishes Hnf4alpha as a mediator of ion epithelial transport, an important process for the maintenance of gut inflammatory homeostasis.

  9. Organizational factors in nuclear safety

    International Nuclear Information System (INIS)

    Wilpert, Bernhard

    2000-01-01

    The overall picture of factors which contributed to the event presents a panorama of a NPP where organizational and managerial characteristics were intricately intertwined and emerged as crucial for a general deterioration of the plant's capabilities to continually correct its deficiencies and optimize its operations. In the following author shall attempt to first cover various important efforts to modeling organizational factors relevant to safety. The second part of my presentation will offer an attempt towards an integrative model. The third part concludes with an agenda for research and practice. Most of the twelve different approaches above attempt to consider safety relevant organizational factors by way of pragmatic classifications. Together with their sub-categories we can count close to 160 different factors on various levels of abstraction. This is tantamount to say that most approaches lack systematic theoretical underpinnings. Thus then arises the question whether we need to develop a generic model, which promises to encompass these three major approaches altogether. Practical issues emerge particularly in the domain of organizational development, i.e. the goal oriented efforts to change the structures and the functioning of nuclear operations in such a way that the desired outputs in terms safety and reliability result in a sustained fashion. Again, these practical concerns are intimately related to developments and advances in theory and methodology. Only a close cooperation among scientists from various disciplines and of practitioners holds the promise of adequately understanding and use of organizational factors in future improving the safety record of nuclear industry worldwide. (S.Y.)

  10. Nuclear transport in Entamoeba histolytica: knowledge gap and therapeutic potential.

    Science.gov (United States)

    Gwairgi, Marina A; Ghildyal, Reena

    2018-03-22

    Entamoeba histolytica is the protozoan parasite that causes human amoebiasis. It is one of the leading parasitic disease burdens in tropical regions and developing countries, with spread to developed countries through migrants from and travellers to endemic regions. Understanding E. histolytica's invasion mechanisms requires an understanding of how it interacts with external cell components and how it engulfs and kills cells (phagocytosis). Recent research suggests that optimal phagocytosis requires signalling events from the cell surface to the nucleus via the cytoplasm, and the induction of several factors that are transported to the plasma membrane. Current research in other protozoans suggests the presence of proteins with nuclear localization signals, nuclear export signals and Ran proteins; however, there is limited literature on their functionality and their functional similarity to higher eukaryotes. Based on learnings from the development of antivirals, nuclear transport elements in E. histolytica may present viable, specific, therapeutic targets. In this review, we aim to summarize our limited knowledge of the eukaryotic nuclear transport mechanisms that are conserved and may function in E. histolytica.

  11. Nevada commercial spent nuclear fuel transportation experience

    International Nuclear Information System (INIS)

    1991-09-01

    The purpose of this report is to present an historic overview of commercial reactor spent nuclear fuel (SNF) shipments that have occurred in the state of Nevada, and to review the accident and incident experience for this type of shipments. Results show that between 1964 and 1990, 309 truck shipments covering approximately 40,000 miles moved through Nevada; this level of activity places Nevada tenth among the states in the number of truck shipments of SNF. For the same period, 15 rail shipments moving through the State covered approximately 6,500 miles, making Nevada 20th among the states in terms of number of rail shipments. None of these shipments had an accident or an incident associated with them. Because the data for Nevada are so limited, national data on SNF transportation and the safety of truck and rail transportation in general were also assessed

  12. Questions raised on transport of nuclear material

    International Nuclear Information System (INIS)

    Lubinska, A.

    1984-01-01

    Public opinion is demanding safer rules for the shipment of radioactive materials since the recent collision and sinking of a French freighter carrying uranium hexafluoride. At issue is the secrecy of the cargo, the delay in releasing information to the public and salvage crews, and the use of unmarked trucks. The nuclear industry points out that no recent incidents have led to the loss of human life, but there is concern among European Community members that a number of countries have yet to ratify international conventions and agreements on hazardous materials transport, that none of these agreements are mandatory, and that none address the transfrontier movement of waste materials

  13. Transportation of hazardous and nuclear materials

    International Nuclear Information System (INIS)

    Boryczka, M.; Shaver, D.

    1989-01-01

    Transportation of hazardous and radioactive materials is a vital part of the nation's economy. In recent years public concern over the relative safety of transporting hazardous materials has risen sharply. The United States has a long history of transporting hazardous and radioactive material; rocket propellants, commercial spent fuel, low-level and high-level radioactive waste has been shipped for years. While the track record for shipping these materials is excellent, the knowledge that hazardous materials are passing through communities raises the ire of citizens and local governments. Public outcry over shipments containing hazardous cargo has been especially prominent when shippers have attempted to transport rocket propellants or spent nuclear fuel. Studies of recent shipments have provided insight into the difficulties of shipping in a politically charged environment, the major issues of concern to citizens, and some of the more successful methods of dealing with public concerns. This paper focuses on lessons learned from these studies which include interviews with shippers, carriers, and regulators

  14. Transport of nuclear material (Part II)

    International Nuclear Information System (INIS)

    Staake, Theo; Schmidt, Thomas

    1983-01-01

    Providing a complete back-end service for MTR reactors is one of the fundamental and traditional tasks of TRANSNUKLEAR GmbH (TN). TN's services in this field cover everything from supplying the ideal transport cask, providing technical assistance during the loading operation, obtaining the necessary package approval and transport licenses, providing the required insurance cover, carrying out the transport, right thru to settling the reprocessing contract. Up until 1976, TN carried out transports of MTR fuel elements to the European reprocessing plants at Mol in Belgium and Marcoule in France. In all, some 1000 fuel elements were transported in this p e ri od. However, following the decision by these plants not to reprocess these elements anymore, subsequent transports had to be made to the US-DOE reprocessing plants. TN pooled together the interests of all her MTR customers and signed a reprocessing contract with the US-DOE, which ensured a complete back-end service for these reactors well into the future. In close cooperation with our associated company, Transnuclear Inc. in New York and Washington, a new transport concept was developed, which proved itself to be both economic and reliable. Up to now, a total of about 2050 MTR fuel elements have been transported by TN-Germany to the USA in 65 separate shipments. The total number of shipments performed by the TN group is 165 shipments. All shipments were carried out routinely without any incident. In March this year, the US-DOE made use of a clause in the contract, in which 90 days' notice was given of a change in reprocessing plant. Whereas previously all elements had been taken to the Savannah River Plant (SRP) in South Carolina, in future all elements have to go to the Idaho Chemical Processing Plant (ICPP) near Idaho Falls. This change presented TN with the not inconsiderable problem of finding a suitable transport route. Due to the large number of influencing factors, the TN-group carried out a special

  15. Regulation on the transport of nuclear fuel materials by vehicles

    International Nuclear Information System (INIS)

    1984-01-01

    The regulations applying to the transport of nuclear fuel materials by vehicles, mentioned in the law for the regulations of nuclear source materials, nuclear fuel materials and reactors. The transport is for outside of the factories and the site of enterprises by such modes of transport as rail, trucks, etc. Covered are the following: definitions of terms, places of fuel materials handling, loading methods, limitations on mix loading with other cargo, radiation dose rates concerning the containers and the vehicles, transport indexes, signs and indications, limitations on train linkage during transport by rail, security guards, transport of empty containers, etc. together with ordinary rail cargo and so on. (Mori, K.)

  16. Aircraft transporting container for nuclear fuel

    International Nuclear Information System (INIS)

    Kurakami, Jun-ichi; Kubo, Minoru.

    1991-01-01

    The present invention concerns an air craft transporting container for nuclear fuels. A sealing container that seals a nuclear fuel container and constitutes a sealed boundary for the transporting container is incorporated in an inner container. Shock absorbers are filled for absorbing impact shock energy in the gap between the inner container and the sealing container. The inner container is incorporated with wooden impact shock absorbers being filled so that it is situated in a substantially central portion of an external container. Partitioning cylinders are disposed coaxially in the cylindrical layer filled with wooden impact shock absorbers at an intermediate portion between the outer and the inner containers. Further, a plurality of longitudinally intersecting partitioning disks are disposed each at a predetermined distance in right and left cylindrical wooden impact shock absorbing layers which are in contact with the end face of the inner container. Accordingly, the impact shock energy can be absorbed by the wooden impact shock absorbers efficiently by a plurality of the partitioning disks and the partitioning cylinders. (I.N.)

  17. The eyes, ears and collective voice for nuclear transport

    International Nuclear Information System (INIS)

    Green, L.

    2000-01-01

    Transport is a vital part of the nuclear industry and the safety record of radioactive materials transport across the world is excellent. This record is due primarily to well-founded regulations developed by such intergovernmental organisations as the International Atomic Energy Agency and the International Maritime Organisation. It is due, also, to the professionalism of those in the industry. Attitudes to nuclear transport are important. They have the potential, if not heeded, and not responded to sensitively and convincingly to make life very much more difficult for those committed to the safe, reliable and efficient transport of nuclear materials. What is required is a balanced situation, which takes account both of the public's attitudes and industry's need for an efficient operation. The voices of the nuclear transport industry and those who value the industry need to be heard. The World Nuclear Transport Institute was established to provide the nuclear transport industry with the collective eyes, ears and voice in the key intergovernmental organisations which are so important to it. The nuclear transport industry has a safety record which could be regarded as a model for the transport of dangerous goods of all kinds. The industry is situated within a comprehensive and strict regime of national and international standards and regulations. That is the message to be disseminated, and that is the commitment of the World Nuclear Transport Institute as it works to protect and to promote the safe, efficient and reliable transport of radioactive materials. (author)

  18. 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.

  19. Rules specific to nuclear incidence occurring in installations or during transport of nuclear substances

    International Nuclear Information System (INIS)

    Rocamora, P.

    1976-01-01

    International nuclear third party liability conventions deal in depth with the liability system governing the transport of nuclear substances. Without appropriate legislation, international transport would be likely to meet very serious legal difficulties. The rule of nuclear conventions apply the same system to transport as to nuclear installations and mainly enable a determination of the operator liable. They also allow the person responsible for transport to assume liability therefor in place of the operator who whould normally have been liable. These nuclear conventions do not affect application of international transport conventions and this provision has been the cause of serious difficulties regarding maritime transport. This resulted in the adoption in 1971 in Brussels of a convention relating to civil liability in the field of maritime carriage of nuclear material. The purpose of this convention is to establish in the field of maritime transport, the priority of the system of absolute, exclusive and limited liability in the nuclear conventions. (NEA) [fr

  20. Spatiotemporal Regulation of Nuclear Transport Machinery and Microtubule Organization

    Science.gov (United States)

    Okada, Naoyuki; Sato, Masamitsu

    2015-01-01

    Spindle microtubules capture and segregate chromosomes and, therefore, their assembly is an essential event in mitosis. To carry out their mission, many key players for microtubule formation need to be strictly orchestrated. Particularly, proteins that assemble the spindle need to be translocated at appropriate sites during mitosis. A small GTPase (hydrolase enzyme of guanosine triphosphate), Ran, controls this translocation. Ran plays many roles in many cellular events: nucleocytoplasmic shuttling through the nuclear envelope, assembly of the mitotic spindle, and reorganization of the nuclear envelope at the mitotic exit. Although these events are seemingly distinct, recent studies demonstrate that the mechanisms underlying these phenomena are substantially the same as explained by molecular interplay of the master regulator Ran, the transport factor importin, and its cargo proteins. Our review focuses on how the transport machinery regulates mitotic progression of cells. We summarize translocation mechanisms governed by Ran and its regulatory proteins, and particularly focus on Ran-GTP targets in fission yeast that promote spindle formation. We also discuss the coordination of the spatial and temporal regulation of proteins from the viewpoint of transport machinery. We propose that the transport machinery is an essential key that couples the spatial and temporal events in cells. PMID:26308057

  1. Liability and insurance aspects of international transport of nuclear materials

    International Nuclear Information System (INIS)

    van Gijn, S.H.

    1985-01-01

    The Paris and Vienna Conventions do not affect the application of any international transport agreement already in force. However, in certain circumstances both the nuclear operator and the carrier may be held liable for nuclear damage which arises during international transports of nuclear materials. The ensuing cumulation of liabilities under the Nuclear and Transport Conventions may cause serious problems in obtaining adequate insurance cover for such transports. The 1971 Brussels Convention seeks to solve this problem by exonerating any person who might be held liable for nuclear damage under an international maritime convention or national law. Similar difficulties are encountered in the case of transports of nuclear materials between states which have and states which have not ratified the Paris and Vienna Conventions. (NEA) [fr

  2. Lessons learned in communicating nuclear transportation issues - a case study

    International Nuclear Information System (INIS)

    Reilly, B.; Austin, P.

    1992-01-01

    Successful communication requires several key elements. They include a non-intimidating forum for exchanging information, two-way communication, advance preparation to identify what each party wants to learn, and feedback. There is no single approach that guarantees success. Factors such as technical complexity of the issue, level of support by the public, and trust and confidence among the parties all play a role in determining the most workable approach for any particular situation. This paper illustrates lessons learned by the US Department of Energy (DOE) in communicating nuclear waste disposal and transportation issues to the public

  3. Force Triggers YAP Nuclear Entry by Regulating Transport across Nuclear Pores.

    Science.gov (United States)

    Elosegui-Artola, Alberto; Andreu, Ion; Beedle, Amy E M; Lezamiz, Ainhoa; Uroz, Marina; Kosmalska, Anita J; Oria, Roger; Kechagia, Jenny Z; Rico-Lastres, Palma; Le Roux, Anabel-Lise; Shanahan, Catherine M; Trepat, Xavier; Navajas, Daniel; Garcia-Manyes, Sergi; Roca-Cusachs, Pere

    2017-11-30

    YAP is a mechanosensitive transcriptional activator with a critical role in cancer, regeneration, and organ size control. Here, we show that force applied to the nucleus directly drives YAP nuclear translocation by decreasing the mechanical restriction of nuclear pores to molecular transport. Exposure to a stiff environment leads cells to establish a mechanical connection between the nucleus and the cytoskeleton, allowing forces exerted through focal adhesions to reach the nucleus. Force transmission then leads to nuclear flattening, which stretches nuclear pores, reduces their mechanical resistance to molecular transport, and increases YAP nuclear import. The restriction to transport is further regulated by the mechanical stability of the transported protein, which determines both active nuclear transport of YAP and passive transport of small proteins. Our results unveil a mechanosensing mechanism mediated directly by nuclear pores, demonstrated for YAP but with potential general applicability in transcriptional regulation. Copyright © 2017 Elsevier Inc. All rights reserved.

  4. Energetics of Transport through the Nuclear Pore Complex

    NARCIS (Netherlands)

    Ghavami, Ali; van der Giessen, Erik; Onck, Patrick R

    2016-01-01

    Molecular transport across the nuclear envelope in eukaryotic cells is solely controlled by the nuclear pore complex (NPC). The NPC provides two types of nucleocytoplasmic transport: passive diffusion of small molecules and active chaperon-mediated translocation of large molecules. It has been shown

  5. Ordinance concerning the filing of transport of nuclear fuel materials

    International Nuclear Information System (INIS)

    1987-01-01

    This Order provides provisions concerning nuclear fuel substances requiring notification (nuclear fuel substance, material contaminated with nuclear fuel substances, fissionable substances, etc.), procedure for notification (to prefectural public safety commission), certificate of transpot (issued via public safety commission), instructions (speed of vehicle for transporting nuclear fuel substances, parking of vehicle, place for loading and unloading of nuclear fuel substances, method for loading and unloading, report to police, measures for disaster prevention during transport, etc.), communication among members of public safety commission (for smooth transport), notification of alteration of data in transport certificate (application to be submitted to public safety commission), application of reissue of transport certificate, return of transport certificate, inspection concerning transport (to be performed by police), submission of report (to be submitted by refining facilities manager, processing facilities manager, nuclear reactor manager, master of foreign nuclear powered ship, reprocessing facilities manager, waste disposal facilities manager; concerning stolen or missing nuclear fuel substances, traffic accident, unusual leakage of nuclear fuel substances, etc.). (Nogami, K.)

  6. Nuclear liability in the course of transport - some insurance aspects

    International Nuclear Information System (INIS)

    Andersson, G.

    1993-01-01

    This presentation deals with some legal and practical problems in the transport liability field, problems the author has met over the years as an insurer of nuclear risks. The intention is not to give a presentation of the nuclear liability rules as such, which should be familiar to the reader, neither to give an overall survey of the insurance procedures as regards transport of nuclear substances. It will just point out a few questions that are typical for this kind of business and that might be of interest for those who in one way or another might be involved in the insurance of nuclear transports

  7. Experience of air transport of nuclear fuel material in Japan

    International Nuclear Information System (INIS)

    Yamashita, T.; Toguri, D.; Kawasaki, M.

    2004-01-01

    Certified Reference Materials (hereafter called as to CRMs), which are indispensable for Quality Assurance and Material Accountability in nuclear fuel plants, are being provided by overseas suppliers to Japanese nuclear entities as Type A package (non-fissile) through air transport. However, after the criticality accident at JCO in Japan, special law defining nuclear disaster countermeasures (hereafter called as to the LAW) has been newly enforced in June 2000. Thereafter, nuclear fuel materials must meet not only to the existing transport regulations but also to the LAW for its transport

  8. Public and media acceptance of nuclear materials transport

    International Nuclear Information System (INIS)

    Lindeman, E.

    1999-01-01

    Transport is absolutely essential to the continued existence of a nuclear industry that includes large-scale power generation, sophisticated research, and medicine. Indeed, transport of nuclear materials is hardly a new business. What is new is the public's awareness and distrust of this transport - a distrust fuelled by the well-funded and skilled manipulation of the nuclear industry's detractors. The nuclear industry itself has only recently begun to acknowledge the importance and the implications of transport. This paper looks at the public and media response to the European-Japanese and the US Department of Energy's transport campaigns and quotes from several telling newspaper articles. It emphasizes the need for the nuclear industry to continue to be vigilant in its efforts to reach the public, media and governments with good science, openness and well-communicated facts. (author)

  9. Transport of radioactive waste from nuclear facilities

    International Nuclear Information System (INIS)

    Keese, H.

    1976-01-01

    A transport system for spent fuel elements and radioactive waste is reported on. The construction of appropriate transport containers, safety regulations, as well as future developments in transport systems and transport containers are discussed in detail. The volume of the spent fuel elements to be moved and the number of transport containers needed is gone into, too. (HR/LN) [de

  10. Japan's regulatory and safety issues regarding nuclear materials transport

    International Nuclear Information System (INIS)

    Saito, T.; Yamanaka, T.

    2004-01-01

    This paper focuses on the regulatory and safety issues on nuclear materials transport which the Government of Japan (GOJ) faces and needs to well handle. Background information about the status of nuclear power plants (NPP) and nuclear fuel cycle (NFC) facilities in Japan will promote a better understanding of what this paper addresses

  11. The climatogenetic factors and the transport network

    Directory of Open Access Journals (Sweden)

    Vasile MAXIM

    2010-03-01

    Full Text Available The article analyses the climatogenic factors and how they influence the transport system (network of the Republic of Moldova. The following climatogenetic factors were analysed: dynamic, physical-geographic, etc. as well as some specific climatic elements as the temperature of the air, cloud amount, humidity, direction and speed of the wind. As a conclusion it can be mentioned that when tracing the terrestrial transport system it is necessary to take into consideration the climatic factors which directly influence this field of human activity.

  12. Nuclear transports. Unpopular as never before?; Nukleartransporte. Ungeliebter denn je?

    Energy Technology Data Exchange (ETDEWEB)

    Feldmann, Ulrike

    2014-11-15

    Since many years there are initiatives in cities with large German seaports to prevent nuclear transports through the cities and transshipment at these harbours. Through the reactor accident in Fukushima and the Federal Government's decision 2011 to opt out, initiatives against nuclear transports seem to have gotten fresh wind in their sails. This is indicated by initiatives in Bremen and Hamburg. Though, to protect health and material goods from hazards and harmful ionising radiation, transportation of radioactive material is regulated by nuclear law as well as traffic law, enactments, guidelines, standards and recommendations, nationally and internationally. These regulations have contributed to the fact that nuclear material has been transported worldwide routinely without harm for the past five decades with an average of roughly 20 million nuclear material transports per year. These attempts disregard that about 95 % of all nuclear transports is not caused by the nuclear energy industry. We should stop demonising nuclear transports and rather acknowledge that they are necessary part of our everyday life.

  13. Transportation of nuclear material in France: regulatory and technical aspects

    International Nuclear Information System (INIS)

    Flory, D.; Renard, C.

    1995-01-01

    Legislative and regulatory documentation define responsibilities in the field of security and physical protection for transportation of nuclear material. Any transportation activity has to conform to an advance authorization regime delivered by the Ministry of Industry. Responsibility for physical protection of nuclear material rests with the carrier under control of the public authority. Penalties reinforce this administrative regime. Operational responsibility for management and control of transport operations has been entrusted by the ministry to the operational transport unit (Echelon Operationnel des Transports - EOT) of IPSN (Institute for Nuclear Protection and Safety). To guarantee en efficient protection of transport operations, the various following means are provided for: -specialized transport means; - devices for real time tracking of road vehicles; - administrative authorization and declaration procedures; -intervention capacities in case of sabotage... This set of technical means and administrative measures is completed by the existence of a body of inspectors who may control every step of the operations. (authors). 3 tabs

  14. Nitric oxide modulates sodium vitamin C transporter 2 (SVCT-2) protein expression via protein kinase G (PKG) and nuclear factor-κB (NF-κB).

    Science.gov (United States)

    Portugal, Camila Cabral; da Encarnação, Thaísa Godinho; Socodato, Renato; Moreira, Sarah Rodrigues; Brudzewsky, Dan; Ambrósio, António Francisco; Paes-de-Carvalho, Roberto

    2012-02-03

    Ascorbate is an important antioxidant, which also displays important functions in neuronal tissues, including the retina. The retina is responsible for the initial steps of visual processing, which is further refined in cerebral high-order centers. The retina is also a prototypical model for studying physiologic aspects of cells that comprise the nervous system. Of major importance also is the cellular messenger nitric oxide (NO). Previous studies have demonstrated the significance of NO for both survival and proliferation of cultured embryonic retinal cells. Cultured retinal cells express a high-affinity ascorbate transporter, and the release of ascorbate is delicately regulated by ionotropic glutamate receptors. Therefore, we proposed whether there is interplay between the ascorbate transport system and NO signaling pathway in retinal cells. Here we show compelling evidence that ascorbate uptake is tightly controlled by NO and its downstream signaling pathway in culture. NO also modulates the expression of SVCT-2, an effect mediated by cGMP and PKG. Kinetic studies suggest that NO increases the transport capacity for ascorbate, but not the affinity of SVCT-2 for its substrate. Interestingly, NO utilizes the NF-κB pathway, in a PKG-dependent manner, to modulate both SVCT-2 expression and ascorbate uptake. These results demonstrate that NO exerts a fine-tuned control of the availability of ascorbate to cultured retinal cells and strongly reinforces ascorbate as an important bioactive molecule in neuronal tissues.

  15. 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

  16. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Swain, A.D.

    1981-01-01

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants. (orig.) [de

  17. Human factors in nuclear power plant operations

    International Nuclear Information System (INIS)

    Swain, A.D.

    1980-08-01

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants

  18. The new context for transport of radioactive and nuclear material

    International Nuclear Information System (INIS)

    Anne, C.; Galtier, J.

    2002-01-01

    The transportation of radioactive and nuclear materials involves all modes of transportation with a predominance for road and for air. It is but a minute fraction dangerous good transportation. Around 10 millions of radioactive packages are shipped annually all over the world of which ninety percent total corresponds to shipments of radioisotopes. In spite of the small volume transported, experience, evolution of transport means and technologies, the trend to constantly improve security and safety and public acceptance have modified the transport environment. During the last few years, new evolutions have applied to the transport of radioactive and nuclear materials in various fields and especially: - Safety - Security - Logistics means - Public acceptance - Quality Assurance. We propose to examine the evolution of these different fields and their impact on transportation methods and means. (authors)

  19. Estimated consequences from severe spent nuclear fuel transportation accidents

    International Nuclear Information System (INIS)

    Arnish, J.J.; Monette, F.; LePoire, D.; Biwer, B.M.

    1996-01-01

    The RISKIND software package is used to estimate radiological consequences of severe accident scenarios involving the transportation of spent nuclear fuel. Radiological risks are estimated for both a collective population and a maximally exposed individual based on representative truck and rail cask designs described in the U.S. Nuclear Regulatory Commission (NRC) modal study. The estimate of collective population risk considers all possible environmental pathways, including acute and long-term exposures, and is presented in terms of the 50-y committed effective dose equivalent. Radiological risks to a maximally exposed individual from acute exposure are estimated and presented in terms of the first year and 50-y committed effective dose equivalent. Consequences are estimated for accidents occurring in rural and urban population areas. The modeled pathways include inhalation during initial passing of the radioactive cloud, external exposure from a reduction of the cask shielding, long-term external exposure. from ground deposition, and ingestion from contaminated food (rural only). The major pathways and contributing radionuclides are identified, and the effects of possible mitigative actions are discussed. The cask accident responses and the radionuclide release fractions are modeled as described in the NRC modal study. Estimates of severe accident probabilities are presented for both truck and rail modes of transport. The assumptions made in this study tend to be conservative; however, a set of multiplicative factors are identified that can be applied to estimate more realistic conditions

  20. Parvoviral nuclear import: bypassing the host nuclear-transport machinery.

    Science.gov (United States)

    Cohen, Sarah; Behzad, Ali R; Carroll, Jeffrey B; Panté, Nelly

    2006-11-01

    The parvovirus Minute virus of mice (MVM) is a small DNA virus that replicates in the nucleus of its host cells. However, very little is known about the mechanisms underlying parvovirus' nuclear import. Recently, it was found that microinjection of MVM into the cytoplasm of Xenopus oocytes causes damage to the nuclear envelope (NE), suggesting that the nuclear-import mechanism of MVM involves disruption of the NE and import through the resulting breaks. Here, fluorescence microscopy and electron microscopy were used to examine the effect of MVM on host-cell nuclear structure during infection of mouse fibroblast cells. It was found that MVM caused dramatic changes in nuclear shape and morphology, alterations of nuclear lamin immunostaining and breaks in the NE of infected cells. Thus, it seems that the unusual nuclear-import mechanism observed in Xenopus oocytes is in fact used by MVM during infection of host cells.

  1. 30 years of experience in safe transportation of nuclear materials

    International Nuclear Information System (INIS)

    Kaneko, K.

    2004-01-01

    In April 2003, Nuclear Fuel Transport Co., Ltd. (NFT) marked the 30 th anniversary of its founding. NFT was established in 1973 and in 1978, commenced SF transport to the reprocessing plant in Tokai-mura. And then, after making preparations to transport nuclear materials to the various facilities at the Nuclear Fuel Cycle Center in Rokkasho-mura, NFT successfully started transportation of LLW (low level waste) to Rokksho-mura's LLW disposal center in 1992, domestic land transportation of HLW returned from overseas to the HLW storage center in 1995, domestic land transportation of natural hexafluoride delivered from overseas to the uranium enrichment plant in 1996, and transportation of SF to the reprocessing plant in 2000. NFT has realized an annual SF transportation capacity of 300 MTU and is currently making great company wide efforts to meet the Rokkasho Reprocessing Plant's future SF annual reprocessing capacity of 800MTU. At the end of FY2003, NFT had successfully transported 560 casks (about 1,730 MTU) of SF in more than 200 voyages in total, about 160,000 drums of LLW in around 100 voyages in total. This paper introduces the record of safe transport and its experience over the past 30 years and prospect for future transport business

  2. 30 years of experience in safe transportation of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Kaneko, K. [Nuclear Fuel Transport Co., Ltd., Tokyo (Japan)

    2004-07-01

    In April 2003, Nuclear Fuel Transport Co., Ltd. (NFT) marked the 30{sup th} anniversary of its founding. NFT was established in 1973 and in 1978, commenced SF transport to the reprocessing plant in Tokai-mura. And then, after making preparations to transport nuclear materials to the various facilities at the Nuclear Fuel Cycle Center in Rokkasho-mura, NFT successfully started transportation of LLW (low level waste) to Rokksho-mura's LLW disposal center in 1992, domestic land transportation of HLW returned from overseas to the HLW storage center in 1995, domestic land transportation of natural hexafluoride delivered from overseas to the uranium enrichment plant in 1996, and transportation of SF to the reprocessing plant in 2000. NFT has realized an annual SF transportation capacity of 300 MTU and is currently making great company wide efforts to meet the Rokkasho Reprocessing Plant's future SF annual reprocessing capacity of 800MTU. At the end of FY2003, NFT had successfully transported 560 casks (about 1,730 MTU) of SF in more than 200 voyages in total, about 160,000 drums of LLW in around 100 voyages in total. This paper introduces the record of safe transport and its experience over the past 30 years and prospect for future transport business.

  3. The new context for transport of radioactive nuclear material

    International Nuclear Information System (INIS)

    Anne, Catherine; Galtier, Jerome

    2001-01-01

    The transportation of radioactive and nuclear materials, involves all modes of transportation (road, air, sea, rail) with predominance for road and for air (air for radioisotopes). In this paper we examine the impact of new evolutions in the fields of safety, security, logistics means, public acceptance and quality assurance

  4. Radiological environmental impacts from transportation of nuclear materials

    International Nuclear Information System (INIS)

    Shuai Zhengqing

    1994-01-01

    The author describes radiological impacts from transportation of nuclear materials. RADTRAN 4.0 supplied by IAEA was adopted to evaluate radiological consequence of incident-free transportation as well as the radiological risks from vehicular accidents occurring during transportation. The results of calculation show that the collective effective dose equivalent of incident-free transportation to the public and transportation workers is 7.94 x 10 -4 man·Sv. The calculated data suggest that the environmental impacts under normal and assumed accidental conditions are acceptable

  5. The Nuclear Energy Factor In Indian Politics

    Directory of Open Access Journals (Sweden)

    A. A. Boyko

    2017-01-01

    Full Text Available Nuclear energy is a key branch of the world power system. The nuclear energy development is viewed by India as one of the ways to resolve the problem of the energy supply. In 2008 the country gained more opportunities for developing nuclear power sector and solving the national power deficit problem after NSG lifted restrictions on nuclear trade. This resulted in foreign companies emerging on the Indian nuclear market. In 2011 after the major emergency at Fukushima Daiichi Nuclear Power Plant in Japan India faced numerous anti-nuclear protests backed by NGOs, including those with foreign funding, and political parties. The article deals with the question of the political role this anti-nuclear opposition plays in India. According to some researchers the protests are organized by the competitors in order to compromise the business of a Russian company Rosatom in India. However, such demonstrations are spread throughout the country and directed against the competitors of Rosatom as well. The article comes to conclusion that the protests are just a reflection of the political fights in India where nuclear energy is a significant political factor.

  6. Human Factor on Gravelines Nuclear Power Plants

    International Nuclear Information System (INIS)

    Duboc, Gerard

    1998-01-01

    In a first part, the documents describes the commitments by EDF nuclear power plan operations to demands made by the Safety Authority regarding actions in the field of human factors (concerns expressed by the Authority, in-depth analysis, positions on different points raised by the Authority). In a second part, it presents the various actions undertaken in the Gravelines nuclear power station regarding human factors: creation of an 'operator club' (mission and objectives, methods and means, first meetings, tracking file), development of risk analysis strategy, setting up of a human factor engineering mission and example of action in case of a significant event

  7. Human factor problem in nuclear power generation

    International Nuclear Information System (INIS)

    Yoshino, Kenji; Fujimoto, Junzo

    1999-01-01

    Since a nuclear power plant accident at Threemile Island in U.S.A. occurred in March, 1979, twenty years have passed. After the accident, the human factor problem became focussed in nuclear power, to succeed its research at present. For direct reason of human error, most of factors at individual level or work operation level are often listed at their center. Then, it is natural that studies on design of a machine or apparatus suitable for various human functions and abilities and on improvement of relationship between 'human being and machine' and 'human being and working environment' are important in future. Here was, as first, described on outlines of the human factor problem in a nuclear power plant developed at a chance of past important accident, and then was described on educational training for its countermeasure. At last, some concrete researching results obtained by human factor research were introduced. (G.K.)

  8. Angular-momentum transport in nuclear collisions

    International Nuclear Information System (INIS)

    Wolschin, G.; Ayik, S.; Noerenberg, W.

    1978-01-01

    Among the various relaxation processes that can be observed in heavy-ion collisions, the dissipation of relative angular momentum into intrinsic angular momentum of the fragments attracts increasing attention. Here we present a transport theoretical description of angular-momentum and mass transport that allows for a transparent interpretation of the data. (orig.) [de

  9. Transport perturbation theory in nuclear reactor analysis

    International Nuclear Information System (INIS)

    Nishigori, Takeo; Takeda, Toshikazu; Selvi, S.

    1985-01-01

    Perturbation theory is formulated on the basis of transport theory to obtain a formula for the reactivity changes due to possible variations of cross sections. Useful applications to cell homogenization are presented for the whole core calculation in transport and in diffusion theories. (author)

  10. Irradiated nuclear fuel transport from Japan to Europe

    International Nuclear Information System (INIS)

    Kavanagh, M.T.; Shimoyama, S.

    1976-01-01

    Irradiated nuclear fuel has been transported from Japan to Europe since 1969, although U.K. experience goes back almost two decades. Both magnox and oxide fuel have been transported, and the technical requirements associated with each type of fuel are outlined. The specialized ships used by British Nuclear Fuels Limited (BNFL) for this transport are described, as well as the ships being developed for future use in the Japan trade. The ship requirements are related to the regulatory position both in the United Kingdom and internationally, and the Japanese regulatory requirements are described. Finally, specific operational experience of a Japanese reactor operator is described

  11. Ordinance concerning the filing of transport of nuclear fuel materials

    International Nuclear Information System (INIS)

    1979-01-01

    The ordinance is defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the order for execution of the law. Any person who reports the transport of nuclear fuel materials shall file four copies of a notification according to the form attached to the public safety commission of the prefecture in charge of the dispatching place. When the transportation extends over the area in charge of another public safety commission, the commission which has received the notice shall report without delay date and route of the transport, kind and quantity of nuclear fuel materials and other necessary matters to the commission concerned and hear from the latter opinions on the items informed. The designation by the ordinance includes speed of the vehicle loaded with nuclear fuel materials, disposition of an accompanying car, arrangement of the line of the loaded vehicle and accompanying and other escorting cars, location of the parking, place of unloading and temporary storage, etc. Reports concerning troubles and measures taken shall be filed in ten days to the public safety commission which has received the notification, when accidents occur on the way, such as: theft or loss of nuclear fuel materials; traffic accident; irregular leaking of nuclear fuel materials and personal trouble by the transport. (Okada, K.)

  12. The French nuclear safety authority's experience with radioactive transport inspection

    International Nuclear Information System (INIS)

    Jacob, E.; Aguilar, J.

    2004-01-01

    About 300,000 radioactive material packages are transported annually in France. Most consist of radioisotopes for medical, pharmaceutical or industrial use. On the other hand, the nuclear industry deals with the transport of fuel cycle materials (uranium, fuel assemblies, etc.) and waste from power plants, reprocessing plants and research centers. France is also a transit country for shipments such as spent fuel packages from Switzerland or Germany, which are bound for Sellafield in Great Britain. The French nuclear safety authority (DGSNR: Directorate General for Nuclear Safety and Radioprotection) has been responsible since 1997 for the safety of radioactive material transport. This paper presents DGNSR's experience with transport inspection: a feedback of key points based on 300 inspections achieved during the past five years is given

  13. Institutional support to the nuclear power based on transportable installations

    International Nuclear Information System (INIS)

    Kuznetsov, V.P.; Cherepnin, Y.S.

    2010-01-01

    Existing nuclear power uses large-power nuclear plants (more than 1,000 MWe) and enriched uranium fuel ( 2 35 U ). Each plant is treated as an exclusive costly project. As a result, large NPPs are operated predominantly in highly developed big countries. In many countries, construction of large power units is not reasonable because of the economic conditions and national specifics. This calls for the use of small- and medium-power nuclear plants (SMPNP), especially transportable nuclear installations (TNI). TNI feature small power (up to 100 MWe); serial production, and transportability. Small- and medium-power nuclear plants could serve to produce electricity and heat; perform water desalination; provide temporary and emergency energy supply. The authors discuss some findings of the studies carried out on the various aspects of the TNI life, as well as the legal and institutional support to their development, construction and operation. The studies have been performed in the framework of the INPRO Action Plan

  14. Transportation capabilities study of DOE-owned spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Clark, G.L.; Johnson, R.A.; Smith, R.W. [Packaging Technology, Inc., Tacoma, WA (United States); Abbott, D.G.; Tyacke, M.J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1994-10-01

    This study evaluates current capabilities for transporting spent nuclear fuel owned by the US Department of Energy. Currently licensed irradiated fuel shipping packages that have the potential for shipping the spent nuclear fuel are identified and then matched against the various spent nuclear fuel types. Also included are the results of a limited investigation into other certified packages and new packages currently under development. This study is intended to support top-level planning for the disposition of the Department of Energy`s spent nuclear fuel inventory.

  15. Probabilistic Risk Assessment on Maritime Spent Nuclear Fuel Transportation

    Energy Technology Data Exchange (ETDEWEB)

    Christian, Robby; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    Spent nuclear fuel (SNF) management has been an indispensable issue in South Korea. Before a long term SNF solution is implemented, there exists the need to distribute the spent fuel pool storage loads. Transportation of SNF assemblies from populated pools to vacant ones may preferably be done through the maritime mode since all nuclear power plants in South Korea are located at coastal sites. To determine its feasibility, it is necessary to assess risks of the maritime SNF transportation. This work proposes a methodology to assess the risk arising from ship collisions during the transportation of SNF by sea. Its scope is limited to the damage probability of SNF packages given a collision event. The effect of transport parameters' variation to the package damage probability was investigated to obtain insights into possible ways to minimize risks. A reference vessel and transport cask are given in a case study to illustrate the methodology's application.

  16. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Pack, R.W.

    1978-01-01

    The Electric Power Research Institute has started research in human factors in nuclear power plants. One project, completed in March 1977, reviewed human factors problems in operating power plants and produced a report evaluating those problems. A second project developed computer programs for evaluating operator performance on training simulators. A third project is developing and evaluating control-room design approaches. A fourth project is reviewing human factors problems associated with power-plant maintainability and instrumentation and control technician activities. Human factors engineering is an interdisciplinary specialty concerned with influencing the design of equipment systems, facilities, and operational environments to promote safe, efficient, and reliable operator performance. The Electric Power Research Institute (EPRI) has undertaken four projects studying the application of human factors engineering principles to nuclear power plants. (author)

  17. Transportation risks in the US nuclear fuel cycle

    International Nuclear Information System (INIS)

    Rhoads, R.E.; Andrews, W.B.

    1980-01-01

    Estimated risks associated with accidental releases of materials transported for each step of the nuclear fuel cycle are presented. The risk estimates include both immediate and latent fatilities caused by releases of these materials in transportation accidents. Studies of the risk of transporting yellowcake, fresh nuclear and low level wastes from the front end of the fuel cycle have not been completed. Existing information does permit estimates of the risks to be made. The estimates presented result from the very low hazards associated with release of these materials. These estimates are consistent with the results of other studies. The results show that risks from all the fuel cycle transportation steps are low. The results also indicate that the total transportation risks associated with the nuclear fuel cycle are distributed about evenly between the fuel supply end and waste management end of the cycle. Risks in the front end of the cycle result primarily from the chemical toxicity of the materials transported. The results of the risk analysis studies for transportation of nuclear fuel cycle materials are compared with the results for the three studies that have been completed for non-nuclear systems. The risk analysis methodology used in these studies identifies the complete spectrum of potential accident consequences and estimates the probability of events producing that level of consequence. The maximum number of fatalities predicted for each material is presented. A variety of risk measures have been used because of the inherent difficulties in making risk comparisons. Examination of a number of risk measures can provide additional insights and help guard against conclusions that are dependent on the way the risk information has been developed and displayed. The results indicate that the risks from transporting these materials are all relatively low in comparison to other risks in society

  18. Colloid transport code-nuclear user's manual

    International Nuclear Information System (INIS)

    Jain, R.

    1992-01-01

    This report describes the CTCN computer code, designed to solve the equations of transient colloidal transport of radionuclides in porous and fractured media. This Fortran 77 package solves systems of coupled nonlinear differential equations with a wide range of boundary conditions. The package uses the Method of Lines technique with a special section which forms finite-difference discretizations in up to four spatial dimensions to automatically convert the system into a set of ordinary differential equations. The CTCN code then solves these equations using a robust, efficient ODE solver. Thus CTCN can be used to solve population balance equations along with the usual transport equations to model colloid transport processes or as a general problem solver to treat up to four-dimensional differential systems

  19. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Hennig, J.; Bohr, E.

    1976-04-01

    This annotated bibliography is a first attempt to give a survey of the kind of literature which is relevant for the ergonomic working conditions in nuclear power plants. Such a survey seems to be useful in view of the fact that the 'factor human being' comes recently more and more to the fore in nuclear power plants. In this context, the necessity is often pointed out to systematically include our knowledge of the performance capacity and limits of human beings when designing the working conditions for the personnel of nuclear power plants. For this reason, the bibliography is so much intended for the ergonomics experts as for the experts of nuclear engineering. (orig./LN) [de

  20. Conservation laws and nuclear transport models

    International Nuclear Information System (INIS)

    Gale, C.; Das Gupta, S.

    1990-01-01

    We discuss the consequences of energy and angular momentum conservation for nucleon-nucleon scattering in a nuclear environment during high-energy heavy-ion collisions. We describe algorithms that ensure stricter enforcement of such conservation laws within popular microscopic models of intermediate-energy heavy-ion collisions. We find that the net effects on global observables are small

  1. The human factor in the nuclear industry

    International Nuclear Information System (INIS)

    Colas, Armand

    1998-01-01

    After having evoked the progressive reduction and stabilization of significant incidents occurring every year in French nuclear power plants, and the challenges faced by nuclear energy (loss of public confidence, loss of competitiveness), and then outlined the importance of safety to overcome these challenges, the author comments EDF's approach to the human factor. He first highlights the importance of information and communication towards the population. He briefly discusses the meaning of human factors for the nuclear industry, sometimes perceived as the contribution people to the company's safety and performance. He comments the evolution observed in the perception of human error in different industrial or technical environments and situations, and outlines what is at stake to reduce the production of faults and organize a 'hunt for latent defects'

  2. Human factors methods in DOE nuclear facilities

    International Nuclear Information System (INIS)

    Bennett, C.T.; Banks, W.W.; Waters, R.J.

    1993-01-01

    The US Department of Energy (DOE) is in the process of developing a series of guidelines for the use of human factors standards, procedures, and methods to be used in nuclear facilities. This paper discusses the philosophy and process being used to develop a DOE human factors methods handbook to be used during the design cycle. The following sections will discuss: (1) basic justification for the project; (2) human factors design objectives and goals; and (3) role of human factors engineering (HFE) in the design cycle

  3. COPI-mediated retrograde trafficking from the Golgi to the ER regulates EGFR nuclear transport

    International Nuclear Information System (INIS)

    Wang, Ying-Nai; Wang, Hongmei; Yamaguchi, Hirohito; Lee, Hong-Jen; Lee, Heng-Huan; Hung, Mien-Chie

    2010-01-01

    Research highlights: → ARF1 activation is involved in the EGFR transport to the ER and the nucleus. → Assembly of γ-COP coatomer mediates EGFR transport to the ER and the nucleus. → Golgi-to-ER retrograde trafficking regulates nuclear transport of EGFR. -- Abstract: Emerging evidence indicates that cell surface receptors, such as the entire epidermal growth factor receptor (EGFR) family, have been shown to localize in the nucleus. A retrograde route from the Golgi to the endoplasmic reticulum (ER) is postulated to be involved in the EGFR trafficking to the nucleus; however, the molecular mechanism in this proposed model remains unexplored. Here, we demonstrate that membrane-embedded vesicular trafficking is involved in the nuclear transport of EGFR. Confocal immunofluorescence reveals that in response to EGF, a portion of EGFR redistributes to the Golgi and the ER, where its NH 2 -terminus resides within the lumen of Golgi/ER and COOH-terminus is exposed to the cytoplasm. Blockage of the Golgi-to-ER retrograde trafficking by brefeldin A or dominant mutants of the small GTPase ADP-ribosylation factor, which both resulted in the disassembly of the coat protein complex I (COPI) coat to the Golgi, inhibit EGFR transport to the ER and the nucleus. We further find that EGF-dependent nuclear transport of EGFR is regulated by retrograde trafficking from the Golgi to the ER involving an association of EGFR with γ-COP, one of the subunits of the COPI coatomer. Our findings experimentally provide a comprehensive pathway that nuclear transport of EGFR is regulated by COPI-mediated vesicular trafficking from the Golgi to the ER, and may serve as a general mechanism in regulating the nuclear transport of other cell surface receptors.

  4. Multipurpose containers for the transport of nuclear material: The example of transport flask CF6

    International Nuclear Information System (INIS)

    Gualdrini, G.F.; Borgia, M.G.

    1989-03-01

    The present paper summarizes the design and licensing activity carried out in the frame work of an ENEA working group which was set up with the aim of developing transport flasks for radioactive and non radioactive dangerous materials. In particular the nuclear design of the multipurpose transport flask CF6 is described. The paper was presented at the seminar on 'Nuclear wastes and transport of radioactive materials' held in Bologna on June 4th and 5th 1987 under the aegis of the Department of Physics of the University of Bologna. (author)

  5. Risk management of onsite transportation of nuclear waste

    International Nuclear Information System (INIS)

    Field, J.G.; Wang, O.S.; Mercado, J.E.

    1993-01-01

    The United States Department of Energy (DOE) Hanford Site recently has undergone a significant change in mission. The focus of operations has shifted from plutonium production to environmental restoration. This transition has caused a substantial increase in quantities of nuclear waste and other hazardous materials packaged and transported onsite. In response to the escalating transportation activity, Westinghouse Hanford Company (Westinghouse Hanford), the Hanford Site operations and engineering contractor, is proposing an integrated risk assessment methodology and risk management strategy to enhance the safety of onsite packaging and transportation operations involving nuclear waste. The proposed methodology consists of three integral parts: risk assessment, risk acceptance criteria, and risk minimization. The purpose of the methodology is to ensure that the risk for each ongoing transportation activity is acceptable and to minimize the overall risk for current and future onsite operations. (authors). 2 figs., 6 refs

  6. Risk management of onsite transportation of nuclear waste

    International Nuclear Information System (INIS)

    Field, J.G.; Wang, O.S.; Mercado, J.E.

    1993-03-01

    The United States Department of Energy (DOE) Hanford Site recently has undergone a significant change in mission. The focus of operations has shifted from plutonium production to environmental restoration. This transition has caused a substantial increase in quantities of nuclear waste and other hazardous materials packaged and transported onsite. In response to the escalating transportation activity, Westinghouse Hanford Company (Westinghouse Hanford), the Hanford Site operations and engineering contractor, is proposing an integrated risk assessment methodology and risk management strategy to enhance the safety of onsite packaging and transportation operations involving nuclear waste. The proposed methodology consists of three integral parts: risk assessment, risk acceptance criteria, and risk minimization. The purpose of the methodology is to ensure that the risk for each ongoing transportation activity is acceptable and to minimize the overall risk for current and future onsite operations

  7. Transportation cost of nuclear off-peak power for hydrogen production based on water electrolysis

    International Nuclear Information System (INIS)

    Shimizu, Saburo; Ueno, Shuichi

    2004-01-01

    The paper describes transportation cost of the nuclear off-peak power for a hydrogen production based on water electrolysis in Japan. The power could be obtainable by substituting hydropower and/or fossil fueled power supplying peak and middle demands with nuclear power. The transportation cost of the off-peak power was evaluated to be 1.42 yen/kWh when an electrolyser receives the off-peak power from a 6kV distribution wire. Marked reduction of the cost was caused by the increase of the capacity factor. (author)

  8. Fuel transporting device in nuclear reactor

    International Nuclear Information System (INIS)

    Inoue, Tatsumi.

    1975-01-01

    Object: To obtain a support structure of an excellent quakeproof property for a fuel transporting device provided for the transportation of fuel between a reactor building and an auxiliary building in a pressure tube reactor or the like. Structure: The structure comprises an oblique transfer chute loosely penetrating the reactor building, reactor container and auxiliary building, a transfer chute support outer cylinder surrounding the transfer chute and having one end coupled to the transfer chute and other end coupled to the container, flexible seal members respectively provided on the reactor building side and on the auxiliary building side and surrounding the transfer chute and a slidable support supported on the side of the auxiliary building such that it can be in frictional contact with the outer periphery of the transfer chute. With this construction, the relative displacements of various parts caused by an earthquake or the like can be absorbed by the support outer cylinder, flexible seals and slidable support. (Ikeda, J.)

  9. Uranium, a factor limiting nuclear energy?

    International Nuclear Information System (INIS)

    Ohnemus, J.

    2006-01-01

    Nuclear power has been back as a topic of public debate since early this year. A special subject under discussion is the extension of nuclear power plant life. Hardly had it been on the agenda, when interested parties announced that this step was impossible because uranium reserves were no longer sufficient. A variety of terms are being used in this discussion without their meaning being taken into account: stocks, resources, and reserves. To clarify the situation, this article outlines important aspects of short and long term uranium supplies, and analyzes their meaning. Here are some of the most important issues under consideration: - For what period of time is there really enough uranium? - Is uranium becoming the limiting factor in the use of nuclear power? - Is uranium really a 'sustainable' energy resource? - Will higher prices extend the range? - What is the influence of the price of uranium on the cost of electricity generation? Among other results, it is found that comprehensive sources of low-price uranium and nuclear fuels are, or can be made, available worldwide. Consequently, the 'range' is beyond the time frames currently mentioned, also as a function of technological factors, i.e. reaching several hundred years. It is also important to note that nuclear power - ensures greater independence of volatile imported sources, - guarantees reliably low electricity prices, - has a huge potential of environmental protection, and - is a clean source of energy. (orig.)

  10. Uranium, a factor limiting nuclear energy?

    International Nuclear Information System (INIS)

    2006-01-01

    Nuclear power has been back as a topic of public debate since early this year. A special subject under discussion is the extension of nuclear power plant life. Hardly had it been on the agenda, when interested parties announced that this step was impossible because uranium reserves were no longer sufficient. A variety of terms are being used in this discussion without their meaning being taken into account: stocks, resources, and reserves. To clarify the situation, this article outlines important aspects of short and long term uranium supplies, and analyzes their meaning. Here are some of the most important issues under consideration: - For what period of time is there really enough uranium? - Is uranium becoming the limiting factor in the use of nuclear power? - Is uranium really a 'sustainable' energy resource? - Will higher prices extend the range? - What is the influence of the price of uranium on the cost of electricity generation? Among other results, it is found that comprehensive sources of low-price uranium and nuclear fuels are, or can be made, available worldwide. Consequently, the 'range' is beyond the time frames currently mentioned, also as a function of technological factors, i.e. reaching several hundred years. It is also important to note that nuclear power - ensures greater independence of volatile imported sources, - guarantees reliably low electricity prices, - has a huge potential of environmental protection, and - is a clean source of energy. (orig./GL)

  11. Activity transport in nuclear generating stations

    International Nuclear Information System (INIS)

    Mitchell, A.B.

    1975-01-01

    The objective of this paper is to give a basic understanding of the operational limitations caused by radiation fields in the present design of CANDU-PHW reactors. A simple model of activity transport is described, and the significance of various radioisotopes identified. The impact which radiation fields have at the Divisional, Station Manager and Operation levels, is outlined in the context of typical work situations. (author)

  12. The permission of transport of irradiated nuclear fuel elements

    International Nuclear Information System (INIS)

    Klomberg, T.J.M.

    2000-01-01

    In July and October 2000 the Dutch government granted permits for the transportation of irradiated nuclear fuel elements. The environmental organization Greenpeace objected against the permit, but that was rejected by the Dutch Council of State. A brief overview is given of the judgements and the state-of-the-art with respect to the transportation of the elements from Dutch reactors and storage facilities in Petten, Dodewaard and Borssele to Cogema in La Hague, France and BNFL in Sellafield, England

  13. Factores que condicionan el rendimiento del transporte

    Directory of Open Access Journals (Sweden)

    Mediavilla, A.

    1963-09-01

    Full Text Available The efficiency of motor transport depends on the rational and precise coordination of the various factors which affect movement by motor vehicles, namely: Correct space and time planning. Speed, by using suitable material and exploiting effectively the power and the capacity of the drivers. Continuity of performance, due to a systematic and efficient maintenance service and intelligent traffic control. Flexibility to introduce modifications in the existing schedules, without interrupting the flow of traffic. By applying effectively the above principles it will be possible to organise transport in the best possible manner. Briefly the above requirements can be summarised thus: «to place, rapidly and regularly, at the preappointed places, all the necessary material for the execution of a particular project».El rendimiento del transporte efectuado por vehículos automóviles, depende de la coordinación racional y armónica de los principios que rigen los movimientos motorizados: Ordenación en tiempo y espacio. Rapidez, mediante el uso del adecuado material y el aprovechamiento de su potencia y de la capacidad de los conductores. Continuidad, merced a un entretenimiento constante y eficaz y a tina inteligente regulación del tráfico. Flexibilidad para introducir, en los movimientos, las modificaciones que se estimen convenientes, sin interrumpir los desplazamientos. Con la aplicación acertada de estos principios se logrará cumplir, en condiciones óptimas, la misión del transporte, la cual puede ser definida como: «situar, con rapidez y regularidad en los lugares prefijados, todos los elementos precisos para el normal desarrollo y ejecución de un plan».

  14. Costs for insurance of civil responsibility for nuclear damage during transportation of nuclear materials

    International Nuclear Information System (INIS)

    Amelina, M.E.; Arsent'ev, S.V.; Molchanov, A.S.

    2009-01-01

    The article considers the method of calculation of rates for insurance of civil responsibility for nuclear damage during transportation of nuclear materials, which can minimize the insurer's costs for this type of insurance in situation when there is no statistics available and it is not possible to calculate the insurance rate by the traditional means using the probability theory

  15. Human error prediction and countermeasures based on CREAM in spent nuclear fuel (SNF) transportation

    International Nuclear Information System (INIS)

    Kim, Jae San

    2007-02-01

    Since the 1980s, in order to secure the storage capacity of spent nuclear fuel (SNF) at NPPs, SNF assemblies have been transported on-site from one unit to another unit nearby. However in the future the amount of the spent fuel will approach capacity in the areas used, and some of these SNFs will have to be transported to an off-site spent fuel repository. Most SNF materials used at NPPs will be transported by general cargo ships from abroad, and these SNFs will be stored in an interim storage facility. In the process of transporting SNF, human interactions will involve inspecting and preparing the cask and spent fuel, loading the cask onto the vehicle or ship, transferring the cask as well as storage or monitoring the cask. The transportation of SNF involves a number of activities that depend on reliable human performance. In the case of the transport of a cask, human errors may include spent fuel bundle misidentification or cask transport accidents among others. Reviews of accident events when transporting the Radioactive Material (RAM) throughout the world indicate that human error is the major causes for more than 65% of significant events. For the safety of SNF transportation, it is very important to predict human error and to deduce a method that minimizes the human error. This study examines the human factor effects on the safety of transporting spent nuclear fuel (SNF). It predicts and identifies the possible human errors in the SNF transport process (loading, transfer and storage of the SNF). After evaluating the human error mode in each transport process, countermeasures to minimize the human error are deduced. The human errors in SNF transportation were analyzed using Hollnagel's Cognitive Reliability and Error Analysis Method (CREAM). After determining the important factors for each process, countermeasures to minimize human error are provided in three parts: System design, Operational environment, and Human ability

  16. Review of EPRI Nuclear Human Factors Program

    International Nuclear Information System (INIS)

    Hanes, L.F.; O'Brien, J.F.

    1996-01-01

    The Electric Power Research Institute (EPRI) Human Factors Program, which is part of the EPRI Nuclear Power Group, was established in 1975. Over the years, the Program has changed emphasis based on the shifting priorities and needs of the commercial nuclear power industry. The Program has produced many important products that provide significant safety and economic benefits for EPRI member utilities. This presentation will provide a brief history of the Program and products. Current projects and products that have been released recently will be mentioned

  17. Human and organizational factors in nuclear safety

    International Nuclear Information System (INIS)

    Garcia, A.; Barrientos, M.; Gil, B.

    2015-01-01

    Nuclear installations are socio technical systems where human and organizational factors, in both utilities and regulators, have a significant impact on safety. Three Mile Island (TMI) accident, original of several initiatives in the human factors field, nevertheless became a lost opportunity to timely acquire lessons related to the upper tiers of the system. Nowadays, Spanish nuclear installations have integrated in their processes specialists and activities in human and organizational factors, promoted by the licensees After many years of hard work, Spanish installations have achieved a better position to face new challenges, such as those posed by Fukushima. With this experience, only technology-centered action plan would not be acceptable, turning this accident in yet another lost opportunity. (Author)

  18. Fuel containing vessel for transporting nuclear fuel

    International Nuclear Information System (INIS)

    Yoshizawa, Hiroyasu; Shimizu, Fukuzo; Tanaka, Nobuyuki.

    1996-01-01

    A shock absorbing mechanism is disposed on an inner bottom of a vessel main body. The shock absorbing mechanism comprises a shock absorbing member disposed on the upper surface of a bottom wall, an annular metal plate disposed on the upper surface of the shock absorbing member and an annular spacer disposed on the upper surface of the metal plate. The shock absorbing member is made of a material such as of wood, lead, metal honeycomb or a metal mesh, which plastically deforms when applied with load higher than a predetermined level, and is formed in a square block-like form covering the upper surface of the bottom wall. The spacer is made of a thin soft material such as tetrafluoroethylene, and is formed in such a shape as capable of preventing direct contact of the lower end of the cylindrical member in a lower tie plate of nuclear fuels with the metal portion. This can ensure integrity of nuclear fuels even when they fall from a high place upon an assumed dropping accident. (I.N.)

  19. Nuclear Waste Policy Act transportation planning

    International Nuclear Information System (INIS)

    Klein, K.A.

    1984-01-01

    The importance and magnitude of effort to put in place a safe, publicly acceptable transportation system for radioactive wastes are discussed. The importance of working openly, documenting efforts in a way that is objective and can be understood by the general public, and being particularly sensitive and responsive to public concerns is recognized. Key elements of current planning have been described, but numerous details remain to be worked out. These details will be worked out, proposed in programs plans, and made publicly available. The author looks forward to ideas and comments for improving these plans and their implementation

  20. Vulnerability Analysis Considerations for the Transportation of Special Nuclear Material

    International Nuclear Information System (INIS)

    Nicholson, Lary G.; Purvis, James W.

    1999-01-01

    The vulnerability analysis methodology developed for fixed nuclear material sites has proven to be extremely effective in assessing associated transportation issues. The basic methods and techniques used are directly applicable to conducting a transportation vulnerability analysis. The purpose of this paper is to illustrate that the same physical protection elements (detection, delay, and response) are present, although the response force plays a dominant role in preventing the theft or sabotage of material. Transportation systems are continuously exposed to the general public whereas the fixed site location by its very nature restricts general public access

  1. Radioactive materials and nuclear fuel transport requirements in Poland in the light of international regulations

    International Nuclear Information System (INIS)

    Musialowicz, T.

    1977-01-01

    National regulations for the transport of radioactive materials and nuclear fuel in Poland are discussed. Basic transport requirements and regulations, transport experience including transport accidents and emergency service are described. The comparison with international regulations is given

  2. Nuclear critical safety analysis for UX-30 transport of freight package

    International Nuclear Information System (INIS)

    Quan Yanhui; Zhou Qi; Yin Shenggui

    2014-01-01

    The nuclear critical safety analysis and evaluation for UX-30 transport freight package in the natural condition and accident condition were carried out with MONK-9A code and MCNP code. Firstly, the critical benchmark experiment data of public in international were selected, and the deflection and subcritical limiting value with MONK-9A code and MCNP code in calculating same material form were validated and confirmed. Secondly, the neutron efficiency multiplication factors in the natural condition and accident condition were calculated and analyzed, and the safety in transport process was evaluated by taking conservative suppose of nuclear critical safety. The calculation results show that the max value of k eff for UX-30 transport freight package is less than the subcritical limiting value, and the UX-30 transport freight package is in the state of subcritical safety. Moreover, the critical safety index (CSI) for UX-30 package can define zero based on the definition of critical safety index. (authors)

  3. Demonstration of a transportable storage system for spent nuclear fuel

    International Nuclear Information System (INIS)

    Shetler, J.R.; Miller, K.R.; Jones, R.E.

    1993-01-01

    The purpose of this paper is to discuss the joint demonstration project between the Sacramento Municipal Utility District (SMUD) and the US Department of Energy (DOE) regarding the use of a transportable storage system for the long-term storage and subsequent transport of spent nuclear fuel. SMUD's Rancho Seco nuclear generating station was shut down permanently in June 1989. After the shutdown, SMUD began planning the decommissioning process, including the disposition of the spent nuclear fuel. Concurrently, Congress had directed the Secretary of Energy to develop a plan for the use of dual-purpose casks. Licensing and demonstrating a dual-purpose cask, or transportable storage system, would be a step toward achieving Congress's goal of demonstrating a technology that can be used to minimize the handling of spent nuclear fuel from the time the fuel is permanently removed from the reactor through to its ultimate disposal at a DOE facility. For SMUD, using a transportable storage system at the Rancho Seco Independent Spent-Fuel Storage Installation supports the goal of abandoning Rancho Seco's spent-fuel pool as decommissioning proceeds

  4. Studies and research concerning BNFP. Nuclear spent fuel transportation studies

    International Nuclear Information System (INIS)

    Anderson, R.T.; Maier, J.B.

    1979-11-01

    Currently, there are a number of institutional problems associated with the shipment of spent fuel assemblies from commercial nuclear power plants: new and conflicting regulations, embargoing of certain routes, imposition of transport safeguards, physical security in-transit, and a lack of definition of when and where the fuel will be moved. This report presents a summary of these types and kinds of problems. It represents the results of evaluations performed relative to fuel receipt at the Barnwell Nuclear Fuel Plant. Case studies were made which address existing reactor sites with near-term spent fuel transportation needs. Shipment by either highway, rail, water, or intermodal water-rail was considered. The report identifies the impact of new regulations and uncertainty caused by indeterminate regulatory policy and lack of action on spent fuel acceptance and storage. This stagnant situation has made it impossible for industry to determine realistic transportation scenarios for business planning and financial risk analysis. A current lack of private investment in nuclear transportation equipment is expected to further prolong the problems associated with nuclear spent fuel and waste disposition. These problems are expected to intensify in the 1980's and in certain cases will make continuing reactor plant operation difficult or impossible

  5. QUANTUM TRANSPORT-THEORY OF NUCLEAR-MATTER

    NARCIS (Netherlands)

    BOTERMANS, W; MALFLIET, R

    1990-01-01

    Quantum kinetic equations are derived using the Keldysh Green's function formalism to describe non-equilibrium processes in nuclear matter and nucleus-nucleus collisions. A general transport equation is proposed which includes energy spreading effects. We discuss a number of specific kinetic

  6. Assembly for transport and storage of radioactive nuclear fuel elements

    International Nuclear Information System (INIS)

    Myers, G.

    1978-01-01

    The invention concerns the self-control of coolant deficiencies on the transport of spent fuel elements from nuclear reactors. It guarantees that drying out of the fuel elements is prevented in case of a change of volume of the fluid contained in storage tanks and accumulators and serving as coolant and shielding medium. (TK) [de

  7. Program strategy document for the Nuclear Materials Transportation Technology Center

    International Nuclear Information System (INIS)

    Jefferson, R.M.

    1979-07-01

    A multiyear program plan is presented which describes the program of the Nuclear Materials Transportation Technology Center (TIC) at Sandia Laboratories. The work element plans, along with their corresponding work breakdown structures, are presented for TTC activities in the areas of Technology and Information Center, Systems Development, Technology, and Institutional Issues for the years from 1979 to 1985

  8. Uranium - a factor limiting nuclear energy?

    International Nuclear Information System (INIS)

    Ohnemus, J.

    2006-01-01

    Nuclear power has been back as a topic of public debate since early this year. A special subject under discussion is the extension of nuclear power plant life. Hardly had it been on the agenda, when interested parties announced that this st ep was impossible because uranium reserves were no longer sufficient. A variety of terms are being used in this discussion without their meaning being taken int o account: stocks, resources, and reserves. To clarify the situation, this artic le outlines important aspects of short and long term uranium supplies, and analy zes their meaning. Here are some of the most important issues under consideration: - For what period of time is there really enough uranium? - Is uranium becoming the limiting factor in the use of nuclear power? - Is uranium really a 'sustainable' energy resource? - Will higher prices extend the range? - What is the in fluence of the price of uranium on the cost of electricity generation? Among oth er results, it is found that comprehensive sources of low-price uranium and nucl ear fuels are, or can be made, available worldwide. Consequently, the 'range' is beyond the time frames currently mentioned, also as a function of technological factors, i.e. reaching several hundred years. It is also important to note that nuclear power - ensures greater independence of volatile imported sources, - guarantees reliably low electricity prices, - has a huge potential of environmental protection, and - is a clean source of energy. (orig.)

  9. Homogeneity of blended nuclear fuel powders after pneumatic transport

    International Nuclear Information System (INIS)

    Smeltzer, E.E.; Skriba, M.C.; Lyon, W.L.

    1982-01-01

    A study of the pneumatic transport of fine (approx. 1μm) cohesive nuclear fuel powders was conducted for the U.S. Department of Energy to demonstrate the feasibility of this method of transport and to develop a design data base for use in a large scale nuclear fuel production facility. As part of this program, a considerable effort was directed at following the homogeneity of blended powders. Since different reactors require different enrichments, blending and subsequent transport are critical parts of the fabrication sequence. The various materials used represented analogs of a wide range of powders and blends that could be expected in a commercial mixed oxide fabrication facility. All UO 2 powders used were depleted and a co-precipitated master mix of (U, Th)O 2 was made specifically for this program, using thorium as an analog for plutonium. In order to determine the effect of pneumatic transport on a blended powder, samples were taken from a feeder vessel before each test, and from a receiver vessel and a few line sections after each transfer test. The average difference between the before and after degree of non-homogeneity was < 1%, for the 21 tests considered. This shows that overall, the pneumatic transport of blended, fine nuclear fuel powders is possible, with only minor unblending occurring

  10. Transport of large particles released in a nuclear accident

    International Nuclear Information System (INIS)

    Poellaenen, R.; Toivonen, H.; Lahtinen, J.; Ilander, T.

    1995-10-01

    Highly radioactive particulate material may be released in a nuclear accident or sometimes during normal operation of a nuclear power plant. However, consequence analyses related to radioactive releases are often performed neglecting the particle nature of the release. The properties of the particles have an important role in the radiological hazard. A particle deposited on the skin may cause a large and highly non-uniform skin beta dose. Skin dose limits may be exceeded although the overall activity concentration in air is below the level of countermeasures. For sheltering purposes it is crucial to find out the transport range, i.e. the travel distance of the particles. A method for estimating the transport range of large particles (aerodynamic diameter d a > 20 μm) in simplified meteorological conditions is presented. A user-friendly computer code, known as TROP, is developed for fast range calculations in a nuclear emergency. (orig.) (23 refs., 13 figs.)

  11. Radiation transport methods for nuclear log assessment - an overview

    International Nuclear Information System (INIS)

    Badruzzaman, A.

    1996-01-01

    Methods of radiation transport have been applied to well-logging problems with nuclear sources since the early 1960s. Nuclear sondes are used in identifying rock compositions and fluid properties in reservoirs to predict the porosity and oil saturation. Early computational effort in nuclear logging used diffusion techniques. As computers became more powerful, deterministic transport methods and, finally, Monte Carlo methods were applied to solve these problems in three dimensions. Recently, the application has been extended to problems with a new generation of devices, including spectroscopic sondes that measure such quantities as the carbon/oxygen ratio to predict oil saturation and logging-while-drilling (LWD) sondes that take neutron and gamma measurements as they rotate in the borehole. These measurements present conditions that will be difficult to calibrate in the laboratory

  12. Transport of large particles released in a nuclear accident

    Energy Technology Data Exchange (ETDEWEB)

    Poellaenen, R; Toivonen, H; Lahtinen, J; Ilander, T

    1995-10-01

    Highly radioactive particulate material may be released in a nuclear accident or sometimes during normal operation of a nuclear power plant. However, consequence analyses related to radioactive releases are often performed neglecting the particle nature of the release. The properties of the particles have an important role in the radiological hazard. A particle deposited on the skin may cause a large and highly non-uniform skin beta dose. Skin dose limits may be exceeded although the overall activity concentration in air is below the level of countermeasures. For sheltering purposes it is crucial to find out the transport range, i.e. the travel distance of the particles. A method for estimating the transport range of large particles (aerodynamic diameter d{sub a} > 20 {mu}m) in simplified meteorological conditions is presented. A user-friendly computer code, known as TROP, is developed for fast range calculations in a nuclear emergency. (orig.) (23 refs., 13 figs.).

  13. Transport of nuclear material under the 1971 Brussels Convention

    International Nuclear Information System (INIS)

    Lagorce, M.

    1975-01-01

    The legal regime in force before entry into force of the 1971 Brussels Convention relating to civil liability for the maritime carriage of nuclear material created serious difficulties for maritime carriers, regarding both the financial risks entailed and restrictions on enjoyment of the rights granted by civil liability conventions. The 1971 Convention exonerates from liability any person likely to be held liable for nuclear damage under maritime law, provided another person is liable under the nuclear conventions or an equivalent national law. A problem remaining is that of compensation of nuclear damage to the means of transport for countries not having opted for re-inclusion of such damage in the nuclear law regime; this does not apply however to countries having ratified the Convention to date. A feature of the latter is that it establishes as extensively as possible the priority of nuclear law over maritime law. Furthermore the new regime continues to preserve efficiently the interests of victims of nuclear incidents. It is therefore to be hoped that insurers will no longer hesitate to cover international maritime carriage of nuclear material [fr

  14. Human factors in nuclear safety oversight

    International Nuclear Information System (INIS)

    Taylor, K.

    1989-01-01

    The mission of the nuclear safety oversight function at the Savannah River Plant is to enhance the process and nuclear safety of site facilities. One of the major goals surrounding this mission is the reduction of human error. It is for this reason that several human factors engineers are assigned to the Operations assessment Group of the Facility Safety Evaluation Section (FSES). The initial task of the human factors contingent was the design and implementation of a site wide root cause analysis program. The intent of this system is to determine the most prevalent sources of human error in facility operations and to assist in determining where the limited human factors resources should be focused. In this paper the strategy used to educate the organization about the field of human factors is described. Creating an awareness of the importance of human factors engineering in all facets of design, operation, and maintenance is considered to be an important step in reducing the rate of human error

  15. NMTC/JAM, Simulates High Energy Nuclear Reactions and Nuclear-Meson Transport Processes

    International Nuclear Information System (INIS)

    Furihata, Shiori

    2002-01-01

    1 - Description of program or function: NMTC/JAM is an upgraded version of the code system NMTC/JAERI97. NMTC/JAERI97 simulates high energy nuclear reactions and nucleon-meson transport processes. It implements an intra-nuclear cascade model taking account of the in-medium nuclear effects and the pre-equilibrium calculation model based on the exciton one. For treating the nucleon transport process, the nucleon-nucleus cross sections are revised to those derived by the systematics of Pearlstein. Moreover, the level density parameter derived by Ignatyuk is included as a new option for particle evaporation calculation. A geometry package based on the Combinatorial Geometry with multi-array system and the importance sampling technique is implemented in the code. Tally function is also employed for obtaining such physical quantities as neutron energy spectra, heat deposition and nuclide yield without editing a history file. The code can simulate both the primary spallation reaction and the secondary particle transport in the intermediate energy region from 20 MeV to 3.5 GeV by the use of the Monte Carlo technique. The code has been employed in combination with the neutron-photon transport codes available to the energy region below 20 MeV for neutronics calculation of accelerator-based subcritical reactors, analyses of thick target spallation experimented and so on. 2 - Methods: High energy nuclear reactions induced by incident high energy protons, neutrons and pions are simulated with the Monte Carlo Method by the intra-nuclear nucleon-nucleon reaction probabilities based on an intra-nuclear nucleon cascade model followed by the particle evaporation including high energy fission process. Jet-Aa Microscopic transport model (JAM) is employed to simulate high energy nuclear reactions in the energy range of GeV. All reaction channels are taken into account in the JAM calculation. An intra-nuclear cascade model (ISOBAR code) taking account of the in-medium nuclear effects

  16. Transport of nuclear materials: a major stake for the reprocessing-conditioning-recycling strategy

    International Nuclear Information System (INIS)

    Gautrot, J.J.

    1998-01-01

    As the international reference in terms of fuel cycle services, the COGEMA Group has developed a wide range of industrialized products answering to its clients needs. But, as deregulation and competition are now expanding, utilities has to be perfectly aware of the cost level of their strategic choices, and to keep these costs down. This point is especially valid in the back-end of the fuel cycle. Several leading nuclear countries around the world have chosen the reprocessing-recycling option because it ensures a economically mastered vision. In that respect, transportation reliability is consequently a basic requirement. It ensures a balanced and continuous flows of materials. Transportation system must be reliable in terms of schedule, safety or industrial aspects (i.e. dedicated packaging for road, rail, sea or air transports, maintenance aspects...). Any serious flaw in one of these three points could lead to delays, thus lessening the economic advantage for utilities. But, one must not loose sight that transportation of nuclear materials is tied to extra-technical issues, such as environmental or regulatory factors, which are fundamental for a consistent understanding of this business. The COGEMA Group, through its subsidiary Transnucleaire, possesses a dedicated transport system, widely praised for its constant commitment in terms of safety, quality and operating. This papers presents the overall back-end transportation framework and details the transport organisations as well as the main achievements of Transnucleaire when it comes to sea, road or rail back-end transports. (authors)

  17. Three distinct domains contribute to nuclear transport of murine Foxp3.

    Directory of Open Access Journals (Sweden)

    Wayne W Hancock

    2009-11-01

    Full Text Available Foxp3, a 47-kDa transcription factor, is necessary for the function of CD4+CD25+ regulatory T cells (Tregs, with an essential role in the control of self-reactive T cells and in preventing autoimmunity. Activation of Tregs by TCR engagement results in upregulation of Foxp3 expression, followed by its rapid nuclear transport and binding to chromatin. Here, we identify three distinct Foxp3 domains that contribute to nuclear transport. The first domain (Domain 1 comprises the C-terminal 12 amino acids. The second domain (Domain 2 is located immediately N-terminal to the forkhead domain (FHD, recently reported to be a binding site for the runt-related transcription factor 1/acute myeloid leukemia 1 (Runx1/AML1. The third domain (Domain 3 is located within the N-terminal first 51 amino acids. Unlike the known nuclear localization signals (NLSs, none of these three regions are rich in basic residues and do not bear any similarity to known monopartite or bipartite NLSs that have one or more clusters of basic amino acids. The basic arginine-lysine-lysine-arginine (RKKR sequence, located 12-aa from the C-terminal end of Foxp3 was previously reported to be a nuclear localization signal (NLS for several proteins, including for a GFP-Foxp3 hybrid. Evidence is provided here that in the full-length native Foxp3 RKKR does not function as an NLS. The data reported in this study indicates that Foxp3 achieves nuclear transport by binding to other nuclear factors and co-transporting with them to the nucleus.

  18. Geologic factors in nuclear waste disposal

    International Nuclear Information System (INIS)

    Towse, D.

    1978-07-01

    The study of geosciences and their relation to nuclear waste disposal and management entails analyzing the hydrology, chemistry, and geometry of the nuclear waste migration process. Hydrologic effects are determined by analyzing the porosity and permeability (natural and induced) of rock as well as pressures and gradients, dispersion, and aquifer length of the system. Chemistry parameters include radionuclide retardation factors and waste dissolution rate. Geometric parameters (i.e., parameters with dimension) evaluated include repository layer thickness, fracture zone area, tunnel length, and aquifer length. The above parameters act as natural barriers or controls to nuclear waste migration, and are evaluated in three potential geologic media: salt, shale, and crystalline rock deposits. Parametric values are assigned that correspond to many existing situations. These values, in addition to other important inputs, are lumped as a hydrology input into a computer simulation program used to model and calculate nuclear waste migration from the repository to the biosphere, and potential individual and population dose and radiation effects. These results are preliminary and show trends only; they do not represent an actual risk analysis

  19. Transportation of radioactive wastes from nuclear fuel cycles

    International Nuclear Information System (INIS)

    1979-09-01

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

  20. Minaret, a deterministic neutron transport solver for nuclear core calculations

    International Nuclear Information System (INIS)

    Moller, J-Y.; Lautard, J-J.

    2011-01-01

    We present here MINARET a deterministic transport solver for nuclear core calculations to solve the steady state Boltzmann equation. The code follows the multi-group formalism to discretize the energy variable. It uses discrete ordinate method to deal with the angular variable and a DGFEM to solve spatially the Boltzmann equation. The mesh is unstructured in 2D and semi-unstructured in 3D (cylindrical). Curved triangles can be used to fit the exact geometry. For the curved elements, two different sets of basis functions can be used. Transport solver is accelerated with a DSA method. Diffusion and SPN calculations are made possible by skipping the transport sweep in the source iteration. The transport calculations are parallelized with respect to the angular directions. Numerical results are presented for simple geometries and for the C5G7 Benchmark, JHR reactor and the ESFR (in 2D and 3D). Straight and curved finite element results are compared. (author)

  1. Pair production from nuclear collisions and cosmic ray transport

    International Nuclear Information System (INIS)

    Norbury, John W

    2006-01-01

    Modern cosmic ray transport codes, that are capable of use for a variety of applications, need to include all significant atomic, nuclear and particle reactions at a variety of energies. Lepton pair production from nucleus-nucleus collisions has not been included in transport codes to date. Using the methods of Baur, Bertulani and Baron, the present report provides estimates of electron-positron pair production cross sections for nuclei and energies relevant to cosmic ray transport. It is shown that the cross sections are large compared to other typical processes such as single neutron removal due to strong or electromagnetic interactions. Therefore, lepton pair production may need to be included in some transport code applications involving MeV electrons. (brief report)

  2. Minaret, a deterministic neutron transport solver for nuclear core calculations

    Energy Technology Data Exchange (ETDEWEB)

    Moller, J-Y.; Lautard, J-J., E-mail: jean-yves.moller@cea.fr, E-mail: jean-jacques.lautard@cea.fr [CEA - Centre de Saclay , Gif sur Yvette (France)

    2011-07-01

    We present here MINARET a deterministic transport solver for nuclear core calculations to solve the steady state Boltzmann equation. The code follows the multi-group formalism to discretize the energy variable. It uses discrete ordinate method to deal with the angular variable and a DGFEM to solve spatially the Boltzmann equation. The mesh is unstructured in 2D and semi-unstructured in 3D (cylindrical). Curved triangles can be used to fit the exact geometry. For the curved elements, two different sets of basis functions can be used. Transport solver is accelerated with a DSA method. Diffusion and SPN calculations are made possible by skipping the transport sweep in the source iteration. The transport calculations are parallelized with respect to the angular directions. Numerical results are presented for simple geometries and for the C5G7 Benchmark, JHR reactor and the ESFR (in 2D and 3D). Straight and curved finite element results are compared. (author)

  3. Intercontinental nuclear transport from the private international law perspective

    International Nuclear Information System (INIS)

    Magnus, U.

    2000-01-01

    The aim of this paper is to give a survey on choice of law rules which apply outside the nuclear liability conventions in case of damage caused by international nuclear transports. We found a remarkable variety of solutions. Some of the solutions make it difficult or even impossible to predict in advance which substantive law in a hypothetical case would apply. These difficulties are increased by the fact that more often than not, a victim can choose where to sue and thereby also influence the final outcome of a case. As far as private international law rules apply - and as mentioned the non-ratification of the nuclear liability conventions by many nuclear states forces us to fall back on the choice of law rules in many cases - the applicable law and the hypothetical level of compensation therefore often remain uncertain when judged at the time of organisation of the nuclear transport. However, at this time the question of undertaking risks and of insurability must be decided. (author)

  4. Transportation of nuclear materials: the nuclear focus of the 80's

    International Nuclear Information System (INIS)

    Meyers, S.; Hardin, E.C. Jr.; Jefferson, R.M.

    1980-01-01

    The transport of radioactive material has been carried out since the inception of the nuclear age (over 30 years) with an unparralled safety record. Despite these achievements, there is a need to strive for improvements, to develop safer and more efficient transportation systems, moreover to perform these tasks in a highly visible manner so that public concern can be allayed. But, in the same vein that the past record is not of itself sufficient, neither is public participation the solution to all the issues surrounding the transportation of radioactive materials. The solutions to the problems facing the nuclear transport industry involve many disciplines, much of which rest on a foundation of sound technology. This conference is built around a core of papers on the developing technology of nuclear transportation: on systems, their design and development, their manufacturing processes, their operation and the methodologies of quality assurance in each of these activities. The role of IAEA in the collecting of data to compile information on the flow of radioactive materials, the mode of transport and the corresponding accident/incident experience, as well as its role in initiating a program to develop a worldwide uniform methodology to address the risks of transporting radioactive materials are covered in this symposium

  5. Human Factors in Nuclear Reactor Accidents

    International Nuclear Information System (INIS)

    Mustafa, M.E.

    2016-01-01

    While many people would blame nature for the disaster of the “Fukushima Daiichi” accident, experts considered this accident to be also a human-induced disaster. This confirmed the importance of human errors which have been getting a growing interest in the nuclear field after the Three Mile Island accident. Personnel play an important role in design, operation, maintenance, planning, and management. The interface between machine and man is known as a human factor. In the present work, the human factors that have to be considered were discussed. The effect of the control room configuration and equipment design effect on the human behavior was also discussed. Precise reviewing of person’s qualifications and experience was focused. Insufficient training has been a major cause of human error in the nuclear field. The effective training issues were introduced. Avoiding complicated operational processes and non responsive management systems was stressed. Distinguishing between the procedures for normal and emergency operations was emphasised. It was stated that human error during maintenance and testing activities could cause a serious accident. This is because safety systems do not cover much more risk probabilities in the maintenance and testing activities like they do in the normal operation. In nuclear industry, the need for a classification and identification of human errors has been well recognised. As a result of this, human reliability must be assessed. These errors are analyzed by a probabilistic safety assessment which deals with errors in reading, listening and implementing procedures but not with cognitive errors. Much efforts must be accomplished to consider cognitive errors in the probabilistic safety assessment. The ways of collecting human factor data were surveyed. The methods for identifying safe designs, helping decision makers to predict how proposed or current policies will affect safety, and comprehensive understanding of the relationship

  6. Risk assessment for transportation of radioactive materials and nuclear explosives

    International Nuclear Information System (INIS)

    Clauss, D.B.; Wilson, R.K.; Hartman, W.F.

    1991-01-01

    Sandia National Laboratories has the lead technical role for probabilistic risk assessments of transportation of nuclear weapons, components, and special nuclear material in support of the US Department of Energy. The emphasis of the risk assessments is on evaluating the probability of inadvertent disposal of radioactive material and the consequences of such a release. This paper will provide an overview of the methodology being developed for the risk assessment and will discuss the interpretation and use of the results. The advantages and disadvantages of using risk assessment as an alternative to performance-based criteria for packaging will be described. 2 refs., 1 fig

  7. Nuclear-electrolytic hydrogen as a transportation fuel

    International Nuclear Information System (INIS)

    DeLuchi, M.A.

    1989-01-01

    Hydrogen is a very attractive transportation fuel in three important ways: it is the least polluting fuel that can be used in an internal combustion engine, it produces no greenhouse gases, and it is potentially available anywhere there is water and a clean source of power. The prospect of a clean, widely available transportation fuel has motivated much of the research on hydrogen fuels. This paper is a state-of-the art review of the production, storage, performance, environmental impacts, safety, and cost of nuclear-electrolytic hydrogen for highway vehicles

  8. Analysis of the transportation logistics for spent nuclear fuel in Korea

    International Nuclear Information System (INIS)

    Lee, Hyo Jik; Ko, Won Il; Seo, Ki Seok

    2010-01-01

    As a part of the back-end fuel cycle, transportation of spent nuclear fuel (SNF) from nuclear power plants (NPP s ) to a fuel storage facility is very important in establishing a nuclear fuel cycle. In Korea, the accumulated amount of SNF in the NPP pools is troublesome since the temporary storage facilities at these NPP pools are expected to be full of SNF within ten years. Therefore, Korea cannot help but plan for the construction of an interim storage facility to solve this problem in the near future. Especially, a decision on several factors, such as where the interim storage facility should be located, how many casks a transport ship can carry at a time and how many casks are initially required, affect the configuration of the transportation system. In order to analyze the various possible candidate scenarios, we assumed four cases for the interim storage facility location, three cases for the load capacity that a transport ship can carry and two cases for the total amount of casks used for transportation. First, this study considered the currently accumulated amount of SNF in Korea, and the amount of SNF generated from NPP s until all NPP s are shut down. Then, how much SNF per year must be transported from theNPP s to an interim storage facility was calculated during an assumed transportation period. Second, 24 candidate transportation scenarios were constructed by a combination of the decision factors. To construct viable yearly transportation schedules for the selected 24 scenarios, we created a spreadsheet program named TranScenario, which was developed by using MS EXCEL. TranScenario can help schedulers input shipping routes and allocate transportation casks. Also,TranScenario provides information on the cask distribution in the NPP s and in the interim storage facility automatically, by displaying it in real time according to the shipping routes, cask types and cask numbers that the user generates. Once a yearly transportation schedule is established

  9. The transport of fuel assemblies. New containers for transport the used nuclear material in Juzbado factory

    International Nuclear Information System (INIS)

    2005-01-01

    Juzbado Manufacturing Facility is designed to be versatile and flexible. It is manufactured different kind of fuel assemblies PWR, BWR and VVER, beginning by the uranium oxide coming from the conversion facilities. The transport of these products (radioactive material fissile) requires the availability of different kind of packages; our models variety is similar to the big manufacturers. It is required a depth knowledge of the licensing process, approvals, manufacturing and handling instruction to be confident. Moreover, the recently changes on the Transport Regulations and the demands for the approval by the Competent Authorities have required the renovation of most of the package designs for the transport of radioactive material fissile worldwide. ENUSA assumed time ago this renovation and it is nowadays in the pick moment of this process. If we also consider the complexity on the management of multimodal international transportations, the Logistic task for the transport of nuclear material associated to the Juzbado factory results in a real changeling area. (Author)

  10. Spent Nuclear Fuel Transportation Risk Assessment Methodology for Homeland Security

    International Nuclear Information System (INIS)

    Teagarden, Grant A.; Canavan, Kenneth T.; Nickell, Robert E.

    2006-01-01

    In response to increased interest in risk-informed decision making regarding terrorism, EPRI was selected by U.S. DHS and ASME to develop and demonstrate a nuclear sector specific methodology for owner / operators to utilize in performing a Risk Analysis and Management for Critical Asset Protection (RAMCAP) assessment for the transportation of spent nuclear fuel (SNF). The objective is to characterize SNF transportation risk for risk management opportunities and to provide consistent information for DHS decision making. The method uses a characterization of risk as a function of Consequence, Vulnerability, and Threat. Worst reasonable case scenarios characterize risk for a benchmark set of threats and consequence types. A trial application was successfully performed and implementation is underway by one utility. (authors)

  11. Transport code and nuclear data in intermediate energy region

    Energy Technology Data Exchange (ETDEWEB)

    Hasegawa, Akira; Odama, Naomitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Maekawa, F.; Ueki, K.; Kosaka, K.; Oyama, Y.

    1998-11-01

    We briefly reviewed the problems of intermediate energy nuclear data file and transport codes in connection with processing of the data. This is a summary of our group in the task force on JENDL High Energy File Integral Evaluation (JHEFIE). In this article we stress the necessity of the production of intermediate evaluated nuclear data file up to 3 GeV for the application of accelerator driven transmutation (ADT) system. And also we state the necessity of having our own transport code system to calculate the radiation fields using these evaluated files from the strategic points of view to keep our development of the ADT technology completely free from other conditions outside of our own such as imported codes and data with poor maintenance or unknown accuracy. (author)

  12. Transport code and nuclear data in intermediate energy region

    International Nuclear Information System (INIS)

    Hasegawa, Akira; Odama, Naomitsu; Maekawa, F.; Ueki, K.; Kosaka, K.; Oyama, Y.

    1998-01-01

    We briefly reviewed the problems of intermediate energy nuclear data file and transport codes in connection with processing of the data. This is a summary of our group in the task force on JENDL High Energy File Integral Evaluation (JHEFIE). In this article we stress the necessity of the production of intermediate evaluated nuclear data file up to 3 GeV for the application of accelerator driven transmutation (ADT) system. And also we state the necessity of having our own transport code system to calculate the radiation fields using these evaluated files from the strategic points of view to keep our development of the ADT technology completely free from other conditions outside of our own such as imported codes and data with poor maintenance or unknown accuracy. (author)

  13. Biomechanics of the transport barrier in the nuclear pore complex.

    Science.gov (United States)

    Stanley, George J; Fassati, Ariberto; Hoogenboom, Bart W

    2017-08-01

    The nuclear pore complex (NPC) is the selective gateway through which all molecules must pass when entering or exiting the nucleus. It is a cog in the gene expression pathway, an entrance to the nucleus exploited by viruses, and a highly-tuned nanoscale filter. The NPC is a large proteinaceous assembly with a central lumen occluded by natively disordered proteins, known as FG-nucleoporins (or FG-nups). These FG-nups, along with a family of soluble proteins known as nuclear transport receptors (NTRs), form the selective transport barrier. Although much is known about the transport cycle and the necessity of NTRs for chaperoning cargo molecules through the NPC, the mechanism by which NTRs and NTR•cargo complexes translocate the selective transport barrier is not well understood. How can disordered FG-nups and soluble NTRs form a transport barrier that is selective, ATP-free, and fast? In this work, we review various mechanical approaches - both experimental and theoretical/computational - employed to better understand the morphology of the FG-nups, and their role in nucleocytoplasmic transport. Recent experiments on FG-nups tethered to planar surfaces, coupled with quantitative modelling work suggests that FG-nup morphologies are the result of a finely balanced system with significant contributions from FG-nup cohesiveness and entropic repulsion, and from NTR•FG-nup binding avidity; whilst AFM experiments on intact NPCs suggest that the FG-nups are sufficiently cohesive to form condensates in the centre of the NPC lumen, which may transiently dissolve to facilitate the transport of larger cargoes. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. Recent developments in the regulation of nuclear transportation

    International Nuclear Information System (INIS)

    Grella, A.W.

    1978-01-01

    In the past four years, almost all nations and international or intergovernmental transport organizations have effected transitions from the 1967 to 1973 IAEA standards as their basis for regulatory requirements for the safe transport of radioactive materials. One major exception to this transition is the USA itself, where this transition has not yet taken place. Major amendments to revise 49 CFR Parts 100-199 of the Department of Transportation regulations and 10 CFR Part 71 of the Nuclear Regulatory Commission regulations are required to effect this transition. The notices of proposed rulemaking to effect this transition in the USA are expected to be published by DOT and NRC concurrently sometime in 1978. Final amendments can be expected later, after the public comment period on the notices and considerations of those comments. This paper summarizes the status of current thinking on US adoption of the 1973 IAEA standards, as well as the status of adoption of those standards by international intergovernmental organizations, such as the Intergovernmental Maritime Consultative Organization, International Civil Aviation Organization, etc. A number of the differences between the expected US regulations and other regulations based on the 1973 IAEA standards are explained. This paper also discusses a number of other events or matters which have been taking place in the US in the past four years which have or may have an effect on transport of nuclear materials and its regulation, including air transport of plutonium, rail transport of spent fuel and other regulations by state or political subdivisions. The paper also discusses changes to US regulations accomplished in the past four years, which are not related to 1973 IAEA standards, as well as some other possible areas where regulatory proposals might be anticipated, such as control of radiation exposures to certain transport workers and other matters

  15. Dynamics of miRNA biogenesis and nuclear transport

    Directory of Open Access Journals (Sweden)

    Kotipalli Aneesh

    2016-12-01

    Full Text Available MicroRNAs (miRNAs are short noncoding RNA sequences ~22 nucleotides in length that play an important role in gene regulation-transcription and translation. The processing of these miRNAs takes place in both the nucleus and the cytoplasm while the final maturation occurs in the cytoplasm. Some mature miRNAs with nuclear localisation signals (NLS are transported back to the nucleus and some remain in the cytoplasm. The functional roles of these miRNAs are seen in both the nucleus and the cytoplasm. In the nucleus, miRNAs regulate gene expression by binding to the targeted promoter sequences and affect either the transcriptional gene silencing (TGS or transcriptional gene activation (TGA. In the cytoplasm, targeted mRNAs are translationally repressed or cleaved based on the complementarity between the two sequences at the seed region of miRNA and mRNA. The selective transport of mature miRNAs to the nucleus follows the classical nuclear import mechanism. The classical nuclear import mechanism is a highly regulated process, involving exportins and importins. The nuclear pore complex (NPC regulates all these transport events like a gate keeper. The half-life of miRNAs is rather low, so within a short time miRNAs perform their function. Temporal studies of miRNA biogenesis are, therefore, useful. We have carried out simulation studies for important miRNA biogenesis steps and also classical nuclear import mechanism using ordinary differential equation (ODE solver in the Octave software.

  16. Experience of air transport of nuclear fuel material as type A package

    International Nuclear Information System (INIS)

    Kawasaki, Masashi; Kageyama, Tomio; Suzuki, Toru

    2004-01-01

    Special law on nuclear disaster countermeasures (hereafter called as to nuclear disaster countermeasures low) that is domestic law for dealing with measures for nuclear disaster, was enforced in June, 2000. Therefore, nuclear enterprise was obliged to report accidents as required by nuclear disaster countermeasures law, besides meeting the technical requirement of existent transport regulation. For overseas procurement of plutonium reference materials that are needed for material accountability, A Type package must be transported by air. Therefore, concept of air transport of nuclear fuel materials according to the nuclear disaster countermeasures law was discussed, and the manual including measures against accident in air transport was prepared for the oversea procurement. In this presentation, the concept of air transport of A Type package containing nuclear fuel materials according to the nuclear disaster countermeasures law, and the experience of a transportation of plutonium solution from France are shown. (author)

  17. Transportation research activities in support of nuclear waste management programs

    International Nuclear Information System (INIS)

    Allen, G.C. Jr.; Cashwell, J.W.; Jefferson, R.M.

    1983-01-01

    Transportation Technology Center has been conducting a wide range of technical research activities to assure the ability to transport radioactive materials in a safe, reliable manner. These activities include tasks in basic, analysis methodology and system research areas. Recently, the requirements of defense waste shipments have served as a focal point for development tasks with the expectation that they would serve as a precursor for commercial activities. The passage of the Nuclear Waste Policy Act has placed additional responsibility on the Department of Energy for concerns involving the shipments of civilian materials. The development of additional research responsibilities is expected to proceed concurrently with the evolution of the transportation mission plan for civilian spent fuel and high-level wastes

  18. Transportation research activities in support of nuclear waste management programs

    International Nuclear Information System (INIS)

    Allen, G.C.; Luna, R.E.; Jefferson, R.M.; Wowak, W.E.

    1983-01-01

    The Transportation Technology Center has been conducting a wide range of technical and non-technical research activities to assure the ability to transport radioactive materials in a safe, reliable, and publicly acceptable manner. These activities include tasks in Information and Intergovernmental issues, Safety Assessment and Environmental Analysis and Technology Development. Until recently, the requirements of defense waste shipments have served as a focal point for development tasks with the expectation that they would serve as a precursor for commercial activities. The passage of the Nuclear Waste Policy Act has placed additional responsibility on DOE for concerns involving the shipments of civilian materials. The development of additional research responsibilities is expected to proceed concurrently with the evolution of the transportation mission plan for civilian spent fuel and high-level wastes

  19. Nuclear materials transportation workshops: USDOE outreach to local governments

    International Nuclear Information System (INIS)

    1987-01-01

    To provide direct outreach to local governments, the Transportation Management Division of the United States Department of Energy asked the Urban Consortium and its Energy Task Force to assemble representatives for two workshops focusing on the transport of nuclear materials. The first session, for jurisdictions east of the Mississippi River, was held in New Orleans on May 5--6, 1988; the second was conducted on June 6--7, 1988 in Denver for jurisdictions to the west. Twenty local government professionals with management or operational responsibility for hazardous materials transportation within their jurisdictions were selected to attend each workshop. The discussions identified five major areas of concern to local government professionals; coordination; training; information resources; marking and placarding; and responder resources. Integrated federal, state, and local levels of government emerged as a priority coordination issue along with the need for expanded availability of training and training resources for first-reponders

  20. Transport of nuclear used fuel and waste materials

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

  1. Regression analysis of nuclear plant capacity factors

    International Nuclear Information System (INIS)

    Stocks, K.J.; Faulkner, J.I.

    1980-07-01

    Operating data on all commercial nuclear power plants of the PWR, HWR, BWR and GCR types in the Western World are analysed statistically to determine whether the explanatory variables size, year of operation, vintage and reactor supplier are significant in accounting for the variation in capacity factor. The results are compared with a number of previous studies which analysed only United States reactors. The possibility of specification errors affecting the results is also examined. Although, in general, the variables considered are statistically significant, they explain only a small portion of the variation in the capacity factor. The equations thus obtained should certainly not be used to predict the lifetime performance of future large reactors

  2. Organizational factors and nuclear power plant safety

    International Nuclear Information System (INIS)

    Haber, S.B.

    1995-01-01

    There are many organizations in our society that depend on human performance to avoid incidents involving significant adverse consequences. As our culture and technology have become more sophisticated, the management of risk on a broad basis has become more and more critical. The safe operation of military facilities, chemical plants, airlines, and mass transit, to name a few, are substantially dependent on the performance of the organizations that operate those facilities. The nuclear power industry has, within the past 15 years, increased the attention given to the influence of human performance in the safe operation of nuclear power plants (NPP). While NPPs have been designed through engineering disciplines to intercept and mitigate events that could cause adverse consequences, it has been clear from various safety-related incidents that human performance also plays a dominant role in preventing accidents. Initial efforts following the 1979 Three Mile Island incident focused primarily on ergonomic factors (e.g., the best design of control rooms for maximum performance). Greater attention was subsequently directed towards cognitive processes involved in the use of NPP decision support systems and decision making in general, personnel functions such as selection systems, and the influence of work scheduling and planning on employees' performance. Although each of these approaches has contributed to increasing the safety of NPPS, during the last few years, there has been a growing awareness that particular attention must be paid to how organizational processes affect NPP personnel performance, and thus, plant safety. The direct importance of organizational factors on safety performance in the NPP has been well-documented in the reports on the Three Mile Island and Chernobyl accidents as well as numerous other events, especially as evaluated by the U.S. Nuclear Regulatory Commission (NRC)

  3. Surface sensitivity of nuclear-knock-out form factors

    International Nuclear Information System (INIS)

    Fratamico, G.

    1984-01-01

    A numerical calculation has been performed to investigate the sensitivity of nuclear-knock-out form factors to nuclear-surface behaviour of bound-state wave functions. The result of our investigation suggests that one can extract the bound-state behaviour at the surface from experimental information on nuclear-knock-out form factors

  4. Transport Properties of the Nuclear Pasta Phase with Quantum Molecular Dynamics

    Science.gov (United States)

    Nandi, Rana; Schramm, Stefan

    2018-01-01

    We study the transport properties of nuclear pasta for a wide range of density, temperature, and proton fractions, relevant for different astrophysical scenarios adopting a quantum molecular dynamics model. In particular, we estimate the values of shear viscosity as well as electrical and thermal conductivities by calculating the static structure factor S(q) using simulation data. In the density and temperature range where the pasta phase appears, the static structure factor shows irregular behavior. The presence of a slab phase greatly enhances the peak in S(q). However, the effect of irregularities in S(q) on the transport coefficients is not very dramatic. The values of all three transport coefficients are found to have the same orders of magnitude as found in theoretical calculations for the inner crust matter of neutron stars without the pasta phase; therefore, the values are in contrast to earlier speculations that a pasta layer might be highly resistive, both thermally and electrically.

  5. Development of human factors engineering guide for nuclear power project

    International Nuclear Information System (INIS)

    Wu Dangshi; Sheng Jufang

    1997-01-01

    'THE PRACTICAL GUIDE FOR APPLICATION OF HUMAN FACTORS ENGINEERING TO NUCLEAR POWER PROJECT (First Draft, in Chinese)', which was developed under a research program sponsored by National Nuclear Safety Administration (NNSA) is described briefly. It is hoped that more conscious, more systematical and more comprehensive application of Human Factors Engineering to the nuclear power projects from the preliminary feasibility studies up to the commercial operation will benefit the safe, efficient and economical operations of nuclear power plants in China

  6. Human factors in nuclear power plant operation

    International Nuclear Information System (INIS)

    Sabri, Z.A.; Husseiny, A.A.

    1980-01-01

    An extensive effort is being devoted to developing a comprehensive human factor program that encompasses establishment of a data base for human error prediction using past operation experience in commercial nuclear power plants. Some of the main results of such an effort are reported including data retrieval and classification systems which have been developed to assist in estimation of operator error rates. Also, statistical methods are developed to relate operator error data to reactor type, age, and specific technical design features. Results reported in this paper are based on an analysis of LER's covering a six-year period for LWR's. Developments presently include a computer data management program, statistical model, and detailed error taxonomy

  7. Assessing numerical methods used in nuclear aerosol transport models

    International Nuclear Information System (INIS)

    McDonald, B.H.

    1987-01-01

    Several computer codes are in use for predicting the behaviour of nuclear aerosols released into containment during postulated accidents in water-cooled reactors. Each of these codes uses numerical methods to discretize and integrate the equations that govern the aerosol transport process. Computers perform only algebraic operations and generate only numbers. It is in the numerical methods that sense can be made of these numbers and where they can be related to the actual solution of the equations. In this report, the numerical methods most commonly used in the aerosol transport codes are examined as special cases of a general solution procedure, the Method of Weighted Residuals. It would appear that the numerical methods used in the codes are all capable of producing reasonable answers to the mathematical problem when used with skill and care. 27 refs

  8. Policy issues of transporting spent nuclear fuel by rail

    International Nuclear Information System (INIS)

    Spraggins, H.B.

    1994-01-01

    The topic of this paper is safe and economical transportation of spent nuclear fuel by rail. The cost of safe movement given the liability consequences in the event of a rail accident involving such material is the core issue. Underlying this issue is the ability to access the risk probability of such an accident. The paper delineates how the rail industry and certain governmental agencies perceive and assess such important operational, safety, and economic issues. It also covers benefits and drawbacks of dedicated and regular train movement of such materials

  9. Transportable nuclear power plant TEC-M with two reactor plants of improved safety

    International Nuclear Information System (INIS)

    Ogloblin, B.G.; Sazonov, A.G.; Svishchev, A.M.; Gromov, B.F.; Zelensky, V.N.; Komkova, O.I.; Sidorov, V.I.; Tolstopyatov, V.P.; Toshinsky, G.I.

    1993-01-01

    Liquid metals are the best to meet the requirements of inherently safety nuclear power plants among the coolants used. A great experience has been gained in lead coolant power plant development and operation as applied to transportable power set-ups. Low chemical activity of this coolant with respect to air-water interaction is a determining factor for this coolant. The transportable nuclear power plant is described. It is intended to generate electric power for populated areas placed a long distance from the main electric power supply sources where it is difficult or not economical to deliver the conventional types of fuel. There are several remote areas in Siberia, Kamchatka in need of this type of power plant

  10. 25 CFR 170.900 - What is the purpose of the provisions relating to transportation of hazardous and nuclear waste?

    Science.gov (United States)

    2010-04-01

    ... transportation of hazardous and nuclear waste? 170.900 Section 170.900 Indians BUREAU OF INDIAN AFFAIRS... and Nuclear Waste Transportation § 170.900 What is the purpose of the provisions relating to transportation of hazardous and nuclear waste? Sections 170.900 through 170.907 on transportation of nuclear and...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  12. Nuclear safety regulation on nuclear safety equipment activities in relation to human and organizational factors

    International Nuclear Information System (INIS)

    Li Tianshu

    2013-01-01

    Based on years of knowledge in nuclear safety supervision and experience of investigating and dealing with violation events in repair welding of DFHM, this paper analyzes major faults in manufacturing and maintaining activities of nuclear safety equipment in relation to human and organizational factors. It could be deducted that human and organizational factors has definitely become key features in the development of nuclear energy and technology. Some feasible measures to reinforce supervision on nuclear safety equipment activities have also been proposed. (author)

  13. Transport in biosphere of radionuclides released from finally disposed nuclear waste - background information for transport and dose model

    International Nuclear Information System (INIS)

    Hulmi, R.; Savolainen, I.

    1981-07-01

    An outline is made about the biosphere transport and dose models employed in the estimation of doses due to releases from finally disposed nuclear waste. The models often divide into two parts; the first one describes the transport of radionuclides in those parts of biosphere where the time scale is large (e.g. soil, sea and sea sediment), the second part of the model describes the transport of nuclides in the systems where the time scale is small (e.g. food chains, plants and animals). The description of biosphere conditions includes remarkable uncertainty due to the complexity of the biosphere and its ecosystems. Therefore studies of scenario type are recommended: some values of parametres describing the conditions are assumed, and the consequences are estimated by using these values. The effect of uncertainty in various factors on the uncertainty of final results should be investigated with the employment of alternative scenarios and parametric sensitivity studies. In addition to the ordinary results, intermediate results should be presented. A proposal for the structure of a transport and dose program based on dynamic linear compartment model is presented and mathematical solution alternatives are studied also

  14. Nuclear thermal propulsion transportation systems for lunar/Mars exploration

    International Nuclear Information System (INIS)

    Clark, J.S.; Borowski, S.K.; Mcilwain, M.C.; Pellaccio, D.G.

    1992-09-01

    Nuclear thermal propulsion technology development is underway at NASA and DoE for Space Exploration Initiative (SEI) missions to Mars, with initial near-earth flights to validate flight readiness. Several reactor concepts are being considered for these missions, and important selection criteria will be evaluated before final selection of a system. These criteria include: safety and reliability, technical risk, cost, and performance, in that order. Of the concepts evaluated to date, the Nuclear Engine for Rocket Vehicle Applications (NERVA) derivative (NDR) is the only concept that has demonstrated full power, life, and performance in actual reactor tests. Other concepts will require significant design work and must demonstrate proof-of-concept. Technical risk, and hence, development cost should therefore be lowest for the concept, and the NDR concept is currently being considered for the initial SEI missions. As lighter weight, higher performance systems are developed and validated, including appropriate safety and astronaut-rating requirements, they will be considered to support future SEI application. A space transportation system using a modular nuclear thermal rocket (NTR) system for lunar and Mars missions is expected to result in significant life cycle cost savings. Finally, several key issues remain for NTR's, including public acceptance and operational issues. Nonetheless, NTR's are believed to be the next generation of space propulsion systems - the key to space exploration

  15. Elastic Network Model of a Nuclear Transport Complex

    Science.gov (United States)

    Ryan, Patrick; Liu, Wing K.; Lee, Dockjin; Seo, Sangjae; Kim, Young-Jin; Kim, Moon K.

    2010-05-01

    The structure of Kap95p was obtained from the Protein Data Bank (www.pdb.org) and analyzed RanGTP plays an important role in both nuclear protein import and export cycles. In the nucleus, RanGTP releases macromolecular cargoes from importins and conversely facilitates cargo binding to exportins. Although the crystal structure of the nuclear import complex formed by importin Kap95p and RanGTP was recently identified, its molecular mechanism still remains unclear. To understand the relationship between structure and function of a nuclear transport complex, a structure-based mechanical model of Kap95p:RanGTP complex is introduced. In this model, a protein structure is simply modeled as an elastic network in which a set of coarse-grained point masses are connected by linear springs representing biochemical interactions at atomic level. Harmonic normal mode analysis (NMA) and anharmonic elastic network interpolation (ENI) are performed to predict the modes of vibrations and a feasible pathway between locked and unlocked conformations of Kap95p, respectively. Simulation results imply that the binding of RanGTP to Kap95p induces the release of the cargo in the nucleus as well as prevents any new cargo from attaching to the Kap95p:RanGTP complex.

  16. Factors of Transport (and Logistic Development

    Directory of Open Access Journals (Sweden)

    Igor Trupac

    2003-03-01

    Full Text Available The characteristic of the present time is the crucia~ significant,and rapid transformation of the common conditions oftrade, transport, and information interchange. However, thestrategic role in this process belongs to the communication andinformation systems. The development of communication andinformation technology systems is incredibly fast, so that referenceis made to the world of advanced communications.The trend found in business life is very complicated. We arestriving both towards collectivisation as well as individualisationat the same time, since thus the world of competitivenessand co-operation is created.In this world the transport and communication and informationnetwork is expected to become fully integrated in the industrialproduction and service-providing system, so as to providethe foundation for a dynamic adjustment to the market requirements.It is clear that the transport infrastructure and cross-borderdevelopment stand for the predominant developmental impulseto the general and physical development of particular areasand of the Slovenian country as a whole. In the pre-accessionperiod of Slovenia to the EU (the accession of Slovenia tothe EU could only occur in 2003-2004, at the earliest, it is necessary,in both fields, to accelerate the activities that will provideco-operation on equal footing. Taking into consideration allthe increasingly open borders (associated members, full members,the economic development will have a favourable impacton the improved competitiveness and co-operation among regionsand states, which will result in an increase in the flow ofgoods, capital and services, and in particular in an improvedmobility of the population.

  17. Safeguards systems concepts for nuclear material transportation. Final report

    International Nuclear Information System (INIS)

    Baldonado, O.C.; Kevany, M.; Rodney, D.; Pitts, D.; Mazur, M.

    1977-09-01

    The report describes the development of system concepts for the safeguarding of special strategic nuclear materials (SNM) against malevolent adversary action during the interfacility transport of the SNM. The methodology used includes techniques for defining, classifying, and analyzing adversary action sequences; defining safeguards system components; assessing the vulnerability of various safeguards systems and their component parts to the potential adversary action sequences, and conceptualizing system design requirements. The method of analysis is based primarily on a comparison of adversary actions with safeguards measures, to estimate vulnerability. Because of the paucity of the data available for assessing vulnerability, the Delphi approach was used to generate data: values were estimated in a structured exercise by a panel of experts in the safeguards and terrorist fields. It is concluded that the probability of successful attack against a truck/escort convoy manned by well-trained, well-armed personnel is low enough to discourage all but the strongest adversaries. Secrecy of operations and careful screening of personnel are very important. No reliance should be placed on current capabilities of local law enforcement agencies. The recommendation of the study is the use of road transport in the near future and air transport at a later time when the number of shipments reaches a level to justify it, and when present safety problems are resolved

  18. A Review on Sabotage against Transportation of Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Choi, Sungyeol; Lim, Jihwan

    2016-01-01

    This report assesses the risk of routine transportation including cask response to an impact or fire accidents. In addition, we have still found the non-negligible difference among the studies for scenarios, approaches, and data. In order to evaluate attack cases on the same basis and reflect more realistic situations, at this moment, it is worthwhile to thoroughly review and analyze the existing studies and to suggest further development directions. In Section 2, we compare scenarios of terror attacks against spent fuel storage and transportation. Section 3 compares target scenarios, capabilities, and limitations of assessment methods. In addition, we collect and compare modeling data used for previous studies to analyze gaps and uncertainties in the existing studies. According to the long term management strategy for spent fuels in Korea, they will be transported from the spent fuel pools in each nuclear power plant to the central interim storage facility. The government should not be the only ones contributing to this dialogue. This dialogue that needs to happen should work both ways, with the government presenting their information and statistics and the public relaying their concerns for the government to review

  19. A Review on Sabotage against Transportation of Spent Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Sungyeol; Lim, Jihwan [UNIST, Ulsan (Korea, Republic of)

    2016-10-15

    This report assesses the risk of routine transportation including cask response to an impact or fire accidents. In addition, we have still found the non-negligible difference among the studies for scenarios, approaches, and data. In order to evaluate attack cases on the same basis and reflect more realistic situations, at this moment, it is worthwhile to thoroughly review and analyze the existing studies and to suggest further development directions. In Section 2, we compare scenarios of terror attacks against spent fuel storage and transportation. Section 3 compares target scenarios, capabilities, and limitations of assessment methods. In addition, we collect and compare modeling data used for previous studies to analyze gaps and uncertainties in the existing studies. According to the long term management strategy for spent fuels in Korea, they will be transported from the spent fuel pools in each nuclear power plant to the central interim storage facility. The government should not be the only ones contributing to this dialogue. This dialogue that needs to happen should work both ways, with the government presenting their information and statistics and the public relaying their concerns for the government to review.

  20. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Bohr, E.; Hennig, J.; Preuss, W.; Thau, G.

    1977-01-01

    This report describes the results of a study on the functions of operating and maintenance personnel in nuclear power plants. Since an effective power plant design must take into systematic account the possibilities and limitations of the human element, the basic aim of the study was to identify what the human operators are required to do and how they achieve it. Information was acquired by direct observation and by interviews as well as by evaluation of written documents (e.g. incident reports, procedures manuals, work regulations) and of working conditions (e.g. equipment and workplace design). A literature search and evaluation carried out within the scope of this study has been published as a separate document. The main part of the report is devoted to discussions and conclusions on selected areas of potential improvements. The topics include control room design, factors of the physical environment including radiation, problems of maintainability, design of written documents, problems in communicating information, design and control of tasks, placement and training. A separate section deals with problems of recording human errors. (orig.) [de

  1. Analysis of NEPA/CEQ requirements with respect to nuclear materials transportation

    International Nuclear Information System (INIS)

    Ross, K.E.L.; Welles, B.W.; Pellettieri, M.W.

    1983-01-01

    This paper examines the responsibility of federal agencies concerned with nuclear materials transportation decisions that come within the scope of the National Environmental Policy Act of 1969 (NEPA) and the requirements established by the Council on Environmental Quality (CEQ). Two of the case histories presented in this paper focus on actions taken by the Nuclear Regulatory Commission (NRC) and the Department of Transportation (DOT). A third case history, in which the limits of environmental impact are judicially redefined, presents an analysis of NEPA application in an NRC licensing action. The decision by the US Supreme Court (April 19, 1983) disallowed psychological stress as a factor to be required in environmental analysis of federal actions. The review by the Supreme Court of environmental impact considerations required under NEPA is clearly transferable to federal actions involving transportation of nuclear materials. Of interest in these examples is the application of NEPA requirements for worst-case analysis and the employment of the rule of reason by a federal agency to determine the limits of its NEPA obligations

  2. The concept of and factors affecting transport accessibility of seaports

    Directory of Open Access Journals (Sweden)

    Janusz Dąbrowski

    2012-03-01

    Full Text Available Transport accessibility of seaports is a frequently studied area in economic research. In practice, port operators and authorities use it to promote their services and compete in the market. Up to this day, theoretical basis of seaports transport accessibility has not been properly described. The article attempts to systematize and expend the knowledge in this field. New definitions of transport availability from wider and narrower perspectives were suggested; different types of accessibility and their mutual relations were explained. These ideas were complemented by introducing classification of factors affecting transport accessibility of seaports.

  3. Factors in public perception of nuclear energy

    International Nuclear Information System (INIS)

    Hore-Lacy, I.

    1999-01-01

    Public communication about nuclear energy needs to relate to the cultural undercurrents which determine how people perceive the environment. The paper discusses some of these and suggests ways of responding to them. It also outlines major ethical considerations relevant to uranium mining and nuclear energy and communication about both and shows that competent discourse about values is fundamental

  4. Public opinion factors regarding nuclear power

    International Nuclear Information System (INIS)

    Benson, B.

    1991-01-01

    This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry's practices are aligned with public opinion, a more favorable regulatory climate is possible

  5. Public opinion factors regarding nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-12-31

    This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry`s practices are aligned with public opinion, a more favorable regulatory climate is possible.

  6. Public opinion factors regarding nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-01-01

    This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry's practices are aligned with public opinion, a more favorable regulatory climate is possible.

  7. Human reliability and risk management in the transportation of spent nuclear fuel

    International Nuclear Information System (INIS)

    Tuler, S.; Kasperson, R.E.; Ratick, S.

    1989-01-01

    This paper summarizes work on human factor contributions to risks from spent nuclear fuel transportation. Human participation may have significant effects on the levels and types of risks by enabling or initiating incidents and exacerbating adverse consequences. Human errors are defined to be the result of mismatches between perceived system state and actual system state. In complex transportation systems such mismatches may be distributed in time (e.g., during different stages of design, implementation, operation, maintenance) and location (e.g., human error, its identification, and its recovery may be geographically and institutionally separate). Risk management programs may decrease the probability of undesirable events or attenuate the consequences of mismatches. This paper presents a methodology to identify the scope and types of human-task mismatches and to identify potential management options for their prevention, mitigation, or recovery. A review of transportation accident databases, in conjunction with human error models, is used to develop a taxonomy of human errors during design for the pre-identification of potential mismatches or after incidents have occurred to evaluate their causes. Risk management options to improve human reliability are identified by a matrix that relates the multiple stages of a spent nuclear fuel transportation system to management options (e.g., training, data analysis, regulation). The paper concludes with examples to illustrate how the methodology may be applied. (author)

  8. Considerations in the selection of transport modes for spent nuclear fuel shipments

    International Nuclear Information System (INIS)

    Daling, P.M.; McNair, G.W.; Andrews, W.B.

    1985-07-01

    This paper discusses the factors associated with selecting a particular transport mode for spent fuel shipments. These factors include transportation costs, economics of potential transportation accidents, risk/safety of spent fuel transportation, routing alternatives, shipping cask handling capabilities, and shipping cask availability. Data needed to estimate transportation costs and risks are presented and discussed. The remaining factors are discussed qualitatively and can be used as guidance for selecting a particular transport mode. 15 refs., 3 tabs

  9. 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)

  10. Spent nuclear fuel transportation: public issues and answers

    International Nuclear Information System (INIS)

    Hoffman, W.D.

    1986-01-01

    The court-ordered shipping of 750 spent nuclear fuel assemblies from West Valley, New York back to their utility owners has generated considerable public and media interest. This paper discusses the specific concerns of the general public over the West Valley shipments, the issues raised by opposition groups, the interest of public officials and emergency preparedness teams as well as the media coverage generated. An analysis is performed on the effectiveness of the West Valley and utility public information programs utilized in addressing these issues, concerns and interests. Emphasis is placed on communications which work to facilitate the shipments and generate fuel transport acceptance. Information programs are discussed which increase preparedness for nuclear shipments by emergency response teams and build public confidence in their safety. The paper also examines communications which could have further enhanced the shipping campaign to date. Finally, plans are discussed for media preparation with interview training and press conferences. Emphasis is placed on materials provided for the media which have served to generate more favorable print and air time

  11. Spent nuclear fuel transportation: Public issues and answers

    International Nuclear Information System (INIS)

    Hoffman, W.D.

    1986-01-01

    The court-ordered shipping of 750 spent nuclear fuel assemblies from West Valley, New York back to their utility owners has generated considerable public and media interest. This paper discusses the specific concerns of the general public over the West Valley shipments, the issues raised by opposition groups, the interests of public officials and emergency preparedness teams as well as the media coverage generated. An analysis is performed on the effectiveness of the West Valley and utility public information programs utilized in addressing these issues, concerns and interests. Emphasis is placed on communications which work to facilitate the shipments and generate fuel transport acceptance. Information programs are discussed which increase preparedness for nuclear shipments by emergency response teams and build public confidence in their safety. The paper also examines communications which could have further enhanced the shipping campaigns to date. Finally, plans are discussed for media preparation with interview training and press conferences. Emphasis is placed on materials provided for the media which has served to generate more favorable print and air time

  12. Ergonomics in nuclear and human factors engineering

    International Nuclear Information System (INIS)

    Muench, E.; Schultheiss, G.F.

    1988-01-01

    The work situation including man-machine-relationships in nuclear power plants is described. The overview gives only a compact summary of some important ergonomic parameters, i.e. human body dimension, human load, human characteristics and human knowledge. (DG)

  13. Source to sink transport and regulation by environmental factors

    Directory of Open Access Journals (Sweden)

    Remi eLemoine

    2013-07-01

    Full Text Available Source-to-sink transport of sugar is one of the major determinants of plant growth and relies on the efficient and controlled distribution of sucrose (and some other sugars such as raffinose and polyols across plant organs through the phloem. However, sugar transport through the phloem can be affected by many environmental factors that alter source/sink relationships. In this paper, we summarize current knowledge about the phloem transport mechanisms and review the effects of several abiotic (water and salt stress, mineral deficiency, CO2, light, temperature, air and soil pollutants and biotic (mutualistic and pathogenic microbes, viruses, aphids and parasitic plants factors. Concerning abiotic constraints, alteration of the distribution of sugar among sinks is often reported, with some sinks as roots favoured in case of mineral deficiency. Many of these constraints impair the transport function of the phloem but the exact mechanisms are far from being completely known. Phloem integrity can be disrupted (e.g. by callose deposition and under certain conditions, phloem transport is affected, earlier than photosynthesis. Photosynthesis inhibition could result from the increase in sugar concentration due to phloem transport decrease. Biotic interactions (aphids, fungi, viruses… also affect crop plant productivity. Recent breakthroughs have identified some of the sugar transporters involved in these interactions on the host and pathogen sides. The different data are discussed in relation to the phloem transport pathways. When possible, the link with current knowledge on the pathways at the molecular level will be highlighted.

  14. The VENUS-7 benchmarks. Results from state-of-the-art transport codes and nuclear data

    International Nuclear Information System (INIS)

    Zwermann, Winfried; Pautz, Andreas; Timm, Wolf

    2010-01-01

    For the validation of both nuclear data and computational methods, comparisons with experimental data are necessary. Most advantageous are assemblies where not only the multiplication factors or critical parameters were measured, but also additional quantities like reactivity differences or pin-wise fission rate distributions have been assessed. Currently there is a comprehensive activity to evaluate such measure-ments and incorporate them in the International Handbook of Evaluated Reactor Physics Benchmark Experiments. A large number of such experiments was performed at the VENUS zero power reactor at SCK/CEN in Belgium in the sixties and seventies. The VENUS-7 series was specified as an international benchmark within the OECD/NEA Working Party on Scientific Issues of Reactor Systems (WPRS), and results obtained with various codes and nuclear data evaluations were summarized. In the present paper, results of high-accuracy transport codes with full spatial resolution with up-to-date nuclear data libraries from the JEFF and ENDF/B evaluations are presented. The comparisons of the results, both code-to-code and with the measured data are augmented by uncertainty and sensitivity analyses with respect to nuclear data uncertainties. For the multiplication factors, these are performed with the TSUNAMI-3D code from the SCALE system. In addition, uncertainties in the reactivity differences are analyzed with the TSAR code which is available from the current SCALE-6 version. (orig.)

  15. Role of zinc finger structure in nuclear localization of transcription factor Sp1

    International Nuclear Information System (INIS)

    Ito, Tatsuo; Azumano, Makiko; Uwatoko, Chisana; Itoh, Kohji; Kuwahara, Jun

    2009-01-01

    Transcription factor Sp1 is localized in the nucleus and regulates gene expression. Our previous study demonstrated that the carboxyl terminal region of Sp1 containing 3-zinc finger region as DNA binding domain can also serve as nuclear localization signal (NLS). However, the nuclear transport mechanism of Sp1 has not been well understood. In this study, we performed a gene expression study on mutant Sp1 genes causing a set of amino acid substitutions in zinc finger domains to elucidate nuclear import activity. Nuclear localization of the GFP-fused mutant Sp1 proteins bearing concomitant substitutions in the first and third zinc fingers was highly inhibited. These mutant Sp1 proteins had also lost the binding ability as to the GC box sequence. The results suggest that the overall tertiary structure formed by the three zinc fingers is essential for nuclear localization of Sp1 as well as dispersed basic amino acids within the zinc fingers region.

  16. Proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel: Appendix B, foreign research reactor spent nuclear fuel characteristics and transportation casks. Volume 2

    International Nuclear Information System (INIS)

    1995-03-01

    This is Appendix B of a draft Environmental Impact Statement (EIS) on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. It discusses relevant characterization and other information of foreign research reactor spent nuclear fuel that could be managed under the proposed action. It also discusses regulations for the transport of radioactive materials and the design of spent fuel casks

  17. A Fuzzy Modeling Approach to Road Transport with Application to a Case of Spent Nuclear Fuel Transport

    International Nuclear Information System (INIS)

    Marseguerra, Marzio; Zio, Enrico; Bianchi, Mauro

    2004-01-01

    In this paper, we propose a general fuzzy inference approach to building a model of hazardous road transport that relates given traffic, weather, and vehicle-speed conditions to the accident rate. The development of the model is discussed in detail, and its validation is provided with reference to literature data regarding the transport of spent nuclear fuel to its final confinement repository

  18. Regulatory Framework for the Safe and Secure Transport of Nuclear Material in Japan

    International Nuclear Information System (INIS)

    Konnai, A.; Shibasaki, N.; Ikoma, Y.; Kato, M.; Yamauchi, T.; Iwasa, T.

    2016-01-01

    Regulations for nuclear material transport in Japan are based on international regulations. Safety and security regulations, however, have sometime different aspects which have caused a conflict of operations. This paper aims to introduce framework of safety and security regulations for nuclear material transport in Japan, and shows some issues in cooperation of these regulations. (author)

  19. 10 CFR 70.20a - General license to possess special nuclear material for transport.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF... transport. (a) A general license is issued to any person to possess formula quantities of strategic special...

  20. Human factor as nuclear safety element

    International Nuclear Information System (INIS)

    Valeca, S.C.; Preda, M.; Valeca, M.; Ana, E. M.; Popescu, D.

    2008-01-01

    National nuclear power system is based on western technology, it covers almost 20% from national need and could be briefly described by: - Safety and economic performances of Cernavoda NPP Unit 1; - Reduced influence on environment, population and workers; - Excellent ranking (place 4) among CANDU units from all over the world. Also, the national nuclear power system plays a major role in Romanian power policy accomplishment: - Energy safety and independence assurance; - Decrease of production of greenhouse effect gases; - Preserve the stability and adequacy of energy cost. 'Nuclear Safety' concept covers all the activities resulting from nuclear fuel cycle. By taking into account the international experience, the related activities are estimated to last around 70 years in Romania: - 10 years for site description and selection, design, manufacturing and commissioning activities; - 40 years for Nuclear Power Plant operation, maintenance and modernization activities; - 20 years for preservation and decommissioning activities. The above mentioned activities requires human resources, qualified and specialized in the following areas: - research and development; - equipment design, manufacturing and operation; - components construction and assembly, operation and maintenance. (authors)

  1. Regulations concerning the transport of nuclear fuel materials outside the works or the enterprise

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and the ordinance for its execution, and to enforce the law. Basic terms are defined, such as vehicle transport, simplified transport, nuclear fuel transport goods, exclusive loading, worker, cumulative dose and exposure radiation dose. Nuclear fuel transport goods are classified into types of L, A, BM and BU according to their radioactivities. Radiation dose rate shall not exceed 0.5 milli-rem an hour on the surface of the type L, and 200 milli-rem an hour on the surface of the type A. For the type BM, the rate shall not surpass 1,000 milli-rem an hour at the distance of 1 meter from the surface in the special test conditions. The transport goods of fissile materials must not reach criticality on the way, but also shall conform to the stipulated technical standards. The particular things contaminated by nuclear fuel materials can be transported without specifying as nuclear fuel transport goods, and their radiation dose rate shall not go beyond 0.5 milli-rem an hour on the surface. The transport by special measures, the technical standards of simplified transport and measures to be taken in danger in transit are defined, respectively.(Okada, K.)

  2. Regulations concerning the transport of nuclear fuel materials outside the works or the enterprise

    International Nuclear Information System (INIS)

    1979-01-01

    The regulations are defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the order for execution of the law. Basic concepts and terms are explained, such as: vehicle transport; easy transport; nuclear fuel material load, exclusive loading, employee, accumulative dose and exposure dose. Technical standards of vehicle transport are specified in detail on nucler fuel materials as nuclear fuel load, L,A, EM and BU type of load, nuclear fuel load of fission substances, the second and third type of fission load and materials contaminated by nuclear fuel substances to be carried not as nuclear fuel loads. Special exceptional measures to such transport and technical standards of easy transport are also designated. The application for confirmation of the transport shall be filed to the Director General of Science and Technology Agency according to the form attached with documents explaining nuclear fuel materials to be transferred, the vessel of such materials and construction, material and method of production of such a vessel, safety of nuclear materials contained, etc. Measures in dangerous situations shall be taken to fight a fire or prohibit the entrance of persons other than the staff concerned. Reports shall be presented in 10 days to the Director, when theft, loss or irregular leaking of nuclear fuel materials or personal troubles occur on the way. (Okada, K.)

  3. Evaluation of the transport and resuspension of a simulated nuclear waste slurry: Nuclear Waste Treatment Program

    International Nuclear Information System (INIS)

    Carleson, T.E.; Drown, D.C.; Hart, R.E.; Peterson, M.E.

    1987-09-01

    The Department of Chemical Engineering at the University of Idaho conducted research on the transport and resuspension of a simulated high-level nuclear waste slurry. In the United States, the reference process for treating both defense and civilian HLLW is vitrification using the liquid-fed ceramic melter process. The non-Newtonian behavior of the slurry complicates the evaluation of the transport and resuspension characteristics of the slurry. The resuspension of a simulated (nonradioactive) melter feed slurry was evaluated using a slurry designated as WV-205. The simulated slurry was developed for the West Valley Demonstration Project and was used during a pilot-scale ceramic melter (PSCM) experiment conducted at PNL in July 1985 (PSCM-21). This study involved determining the transport characteristics of a fully suspended slurry and the resuspension characteristics of settled solids in a pilot-scale pipe loop. The goal was to predict the transport and resuspension of a full-scale system based on rheological data for a specific slurry. The rheological behavior of the slurry was evaluated using a concentric cylinder rotational viscometer, a capillary tube viscometer, and the pilot-scale pipe loop. The results obtained from the three approaches were compared. 40 refs., 74 figs., 15 tabs

  4. Importance of human factors on nuclear installations safety

    International Nuclear Information System (INIS)

    Caruso, G.J.

    1990-01-01

    Actually, installations safety and, in particular the nuclear installations infer a strong incidence in human factors related to the design and operation of such installations. In general, the experience aims to that the most important accidents have happened as result of the components' failures combination and human failures in the operation of safety systems. Human factors in the nuclear installations may be divided into two areas: economy and human reliability. Human factors treatments for the safety evaluation of the nuclear installations allow to diagnose the weak points of man-machine interaction. (Author) [es

  5. District file of major risks for the Moselle district: B6 - The nuclear risk; B7 - The risk related to radioactive material transport

    International Nuclear Information System (INIS)

    2013-10-01

    A first document addresses the nuclear risk with some generalities (definition, occurrence, consequences for people and for the environment with an indication of exposure thresholds, presentation of individual safety directives), a discussion of the nuclear risk level in the district (history, contamination threats, preventive actions for the Cattenom nuclear plant, existence of a triple barrier for radioactive product containment, other factors aimed at nuclear safety, urban development control, control of nuclear activities, information, rescue organisation, map of concerned communes). The second document addresses the risk related to radioactive material transport with some generalities (definition, occurrence, consequences for persons and goods, individual safety directive in case of road or railway accident), a more detailed analysis of the risk in the district (situation of the radioactive material transport in the district, risk history, human and environmental stakes, preventive actions, radiation protection safety challenges, safety factors, control of transports, rescue organisation)

  6. The human factor in nuclear reactor operation

    International Nuclear Information System (INIS)

    Bertron, L.

    1982-05-01

    The principal operating characteristics of nuclear power plants are summarized. A description of major hazards relating to operator fallibility in normal and abnormal operating conditions is followed by a specific analysis of control room hazards, shift organization and selection and training of management personnel

  7. Japan's regulatory and safety issues regarding nuclear materials transport

    Energy Technology Data Exchange (ETDEWEB)

    Saito, T. [Nuclear and Industrial Safety Agency, Ministry of Economy, Trade and Industry, Government of Japan, Tokyo (Japan); Yamanaka, T. [Japan Nuclear Energy Safety Organization, Government of Japan, Tokyo (Japan)

    2004-07-01

    This paper focuses on the regulatory and safety issues on nuclear materials transport which the Government of Japan (GOJ) faces and needs to well handle. Background information about the status of nuclear power plants (NPP) and nuclear fuel cycle (NFC) facilities in Japan will promote a better understanding of what this paper addresses.

  8. Current status of sea transport of nuclear fuel materials and LLW in Japan

    International Nuclear Information System (INIS)

    Kitagawa, Hiroshi; Akiyama, Hideo

    2000-01-01

    Along with the basic policy of the nuclear fuel cycle of Japan, many fuel cycle facilities have been already constructed in Rokkasho-Mura, Aomori prefecture, such as the uranium enrichment plant, the low level waste disposal center and the receiving pool of the spent nuclear fuels for reprocessing. These facilities belong to the Japan Nuclear Fuel Limited. (JNFL). Domestic sea transport of the spent nuclear fuels (SF) has been carried out since 1977 to the Tokai Reprocessing Plant, and the first sea transport of the SF to the fuel cycle facility in Rokkasho-Mura was done in Oct, 1998 using a new exclusive ship 'Rokuei-Maru'. Sea transport of the low level radioactive wastes (LLW) has been carried out since 1992 to the Rokkasho LLW Disposal Center, and about 130,000 LLW drams were transported from the nuclear power plant sites. These sea transport have demonstrated the safety of the transport of the nuclear fuel cycle materials. It is hoped that the safe sea transport of the nuclear fuel materials will contribute to the more progress of the nuclear fuel cycle activities of Japan. (author)

  9. Site Specific Analyses of a Spent Nuclear Fuel Transportation Accident

    International Nuclear Information System (INIS)

    Biwer, B. M.; Chen, S. Y.

    2003-01-01

    The number of spent nuclear fuel (SNF) shipments is expected to increase significantly during the time period that the United States' inventory of SNF is sent to a final disposal site. Prior work estimated that the highest accident risks of a SNF shipping campaign to the proposed geologic repository at Yucca Mountain were in the corridor states, such as Illinois. The largest potential human health impacts would be expected to occur in areas with high population densities such as urban settings. Thus, our current study examined the human health impacts from the most plausible severe SNF transportation accidents in the Chicago metropolitan area. The RISKIND 2.0 program was used to model site-specific data for an area where the largest impacts might occur. The results have shown that the radiological human health consequences of a severe SNF rail transportation accident on average might be similar to one year of exposure to natural background radiation for those persons living a nd working in the most affected areas downwind of the actual accident location. For maximally exposed individuals, an exposure similar to about two years of exposure to natural background radiation was estimated. In addition to the accident probabilities being very low (approximately 1 chance in 10,000 or less during the entire shipping campaign), the actual human health impacts are expected to be lower if any of the accidents considered did occur, because the results are dependent on the specific location and weather conditions, such as wind speed and direction, that were selected to maximize the results. Also, comparison of the results of longer duration accident scenarios against U.S. Environmental Protection Agency guidelines was made to demonstrate the usefulness of this site-specific analysis for emergency planning purposes

  10. Study of a conceptual nuclear-energy center at Green River, Utah: site-specific transportation

    International Nuclear Information System (INIS)

    1981-10-01

    The objective of the following report is to assess the adequacy of the local and regional transportation network for handling traffic, logistics, and the transport of major power plant components to the Utah Nuclear Energy Center (UNEC) Horse Bench site. The discussion is divided into four parts: (1) system requirements; (2) description of the existing transportation network; (3) evaluation; (4) summary and conclusions

  11. Nuclear safety and human factors: the French factory of expertise

    International Nuclear Information System (INIS)

    Rolina, G.

    2009-01-01

    The French regulation of the nuclear safety is based on the maintaining of a deep technical dialogue between the nuclear safety authority, the I.R.S.N. (Institute of radiation protection and nuclear safety) and the nuclear operators. This type of risk management is called 'french coking' by the Anglo-Saxons, followers of stricter regulatory approach, more readable by the civil society. This technical dialogue is not without quality, especially in the field of human and organizational factors where it allows to improve the know how situation that stays incomplete. (N.C.)

  12. U.S. Nuclear Regulatory Commission human factors program plan

    International Nuclear Information System (INIS)

    1986-04-01

    The purpose of the U.S. Nuclear Regulatory Commission (NRC) Human Factors Program Plan is to ensure that proper consideration is given to human factors in the design and operation of nuclear facilities. This revised plan addresses human factors issues related to the operation of nuclear power plants (NPPs). The three issues of concern are (1) the activities planned to provide the technical bases to resolve the remaining tasks related to human factors as described in NUREG-0660, The NRC Action Plan Developed as a Result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the need to address the additional human factors efforts that were identified during implementation of the Action Plan; and (3) the actual fulfillment of those developmental activities specified in Revision 1 of this plan. The plan represents a systematic approach for addressing high priority human factors concerns important to NPP safety in FY 1986 through 1987

  13. Human factors aspects of advanced instrumentation in the nuclear industry

    International Nuclear Information System (INIS)

    Carter, R.J.

    1989-01-01

    An important consideration in regards to the use of advanced instrumentation in the nuclear industry is the interface between the instrumentation system and the human. A survey, oriented towards identifying the human factors aspects of digital instrumentation, was conducted at a number of United States (US) and Canadian nuclear vendors and utilities. Human factors issues, subsumed under the categories of computer-generated displays, controls, organizational support, training, and related topics were identified. 20 refs., 2 tabs

  14. Key factors of low carbon development strategy for sustainable transport

    Science.gov (United States)

    Thaveewatanaseth, K.; Limjirakan, S.

    2018-02-01

    Cities become more vulnerable to climate change impacts causing by urbanization, economic growth, increasing of energy consumption and carbon dioxide (CO2) emissions. People who live in the cities have already been affected from the impacts in terms of socioeconomic and environmental aspects. Sustainable transport plays the key role in CO2 mitigation and contributes positive impacts on sustainable development for the cities. Several studies in megacities both in developed and developing countries support that mass transit system is an important transportation mode in CO2 mitigation and sustainable transport development. This paper aims to study key factors of low carbon development strategy for sustainable transport. The Bangkok Mass Rapid Transit System (MRT) located in Bangkok was the study area. Data collection was using semi-structured in-depth interview protocol with thirty respondents consisting of six groups i.e. governmental agencies, the MRT operators, consulting companies, international organizations, non-profit organizations, and experts. The research findings highlighted the major factors and supplemental elements composing of institution and technical capacity, institutional framework, policy setting and process, and plan of implementation that would support more effective strategic process for low carbon development strategy (LCDS) for sustainable transport. The study would highly recommend on readiness of institution and technical capacities, stakeholder mapping, high-level decision- makers participation, and a clear direction of the governmental policies that are strongly needed in achieving the sustainable transport.

  15. Leukemia-Associated Nup214 Fusion Proteins Disturb the XPO1-Mediated Nuclear-Cytoplasmic Transport Pathway and Thereby the NF-κB Signaling Pathway.

    Science.gov (United States)

    Saito, Shoko; Cigdem, Sadik; Okuwaki, Mitsuru; Nagata, Kyosuke

    2016-07-01

    Nuclear-cytoplasmic transport through nuclear pore complexes is mediated by nuclear transport receptors. Previous reports have suggested that aberrant nuclear-cytoplasmic transport due to mutations or overexpression of nuclear pore complexes and nuclear transport receptors is closely linked to diseases. Nup214, a component of nuclear pore complexes, has been found as chimeric fusion proteins in leukemia. Among various Nup214 fusion proteins, SET-Nup214 and DEK-Nup214 have been shown to be engaged in tumorigenesis, but their oncogenic mechanisms remain unclear. In this study, we examined the functions of the Nup214 fusion proteins by focusing on their effects on nuclear-cytoplasmic transport. We found that SET-Nup214 and DEK-Nup214 interact with exportin-1 (XPO1)/CRM1 and nuclear RNA export factor 1 (NXF1)/TAP, which mediate leucine-rich nuclear export signal (NES)-dependent protein export and mRNA export, respectively. SET-Nup214 and DEK-Nup214 decreased the XPO1-mediated nuclear export of NES proteins such as cyclin B and proteins involved in the NF-κB signaling pathway by tethering XPO1 onto nuclear dots where Nup214 fusion proteins are localized. We also demonstrated that SET-Nup214 and DEK-Nup214 expression inhibited NF-κB-mediated transcription by abnormal tethering of the complex containing p65 and its inhibitor, IκB, in the nucleus. These results suggest that SET-Nup214 and DEK-Nup214 perturb the regulation of gene expression through alteration of the nuclear-cytoplasmic transport system. Copyright © 2016, American Society for Microbiology. All Rights Reserved.

  16. Availability improvement factors at Taipower's nuclear power plant system

    International Nuclear Information System (INIS)

    Chen, J.H.

    1985-01-01

    Sufficient electricity to meet the needs of a growing industrial economy, is one of the most important factors in the total economic development of a nation. Currently, nuclear power is considered one of the most economical and available sources of energy. To keep pace with Taiwan's rapid economic development, while also observing our government's policy of diversifying the requirements for imported forms of energy, Taiwan Power Company has embarked upon an ambitious of nuclear power plant construction. This paper discusses the improvement of Taiwan's nuclear power plants. At the present time, Taipower has completed three nuclear power plants. Two of these are located in northern Taiwan, along the East China Sea, while the third is on the southern tip of Taiwan, bordering the South China Sea. These three plants, each with two nuclear generating units, comprise a total nuclear generating capacity of 5144 MWe

  17. Factors influencing chemical durability of nuclear waste glasses

    International Nuclear Information System (INIS)

    Feng, Xiangdong; Bates, J.K.

    1993-01-01

    A short summary is given of our studies on the major factors that affect the chemical durability of nuclear waste glasses. These factors include glass composition, solution composition, SA/V (ratio of glass surface area to the volume of solution), radiation, and colloidal formation. These investigations have enabled us to gain a better understanding of the chemical durability of nuclear waste glasses and to accumulate.a data base for modeling the long-term durability of waste glass, which will be used in the risk assessment of nuclear waste disposal. This knowledge gained also enhances our ability to formulate optimal waste glass compositions

  18. Critical Design Factors for Sector Transport Maintenance in DEMO

    Energy Technology Data Exchange (ETDEWEB)

    Utoh, H.; Someya, Y.; Tobita, K.; Asakura, N.; Hoshino, K.; Nakamura, M., E-mail: uto.hiroyasu@jaea.go.jp [Japan Atomic Energy Agency, Rokkasho (Japan)

    2012-09-15

    Full text: Maintenance is a critical issue for fusion DEMO reactor because the design conditions and requirements of DEMO maintenance scheme are different from that of ITER remote handling. The sector transport maintenance scheme has advantages to maintain blankets and divertors without the use of sophisticated remote handling devices including sensitive devices to radiation in the reactor. SlimCS designed in JAEA adopts the sector transport maintenance scheme in which every sector is pulled out horizontally through a port between TF coils. A critical design issue for the horizontal sector transport maintenance scheme is how to support an enormous turnover force of the toroidal field (TF) coils. We propose following two options; first option is the horizontal transport maintenance scheme in which every sector is pulled out through four horizontal ports connected with the corridor. Second option is the vertical sector transport maintenance scheme with small vertical maintenance ports (total: 6 ports). The new horizontal sector transport limited in the number of maintenance ports is a more realistic maintenance scheme, and the key engineering issue is the transferring mechanism of sector in the vacuum vessel. In the maintenance scenario, the key design factors are the cool down time in reactor and the cooling method in maintenance scheme for keeping components under operation temperature. By one-dimensional heat conduction analysis, the sector should be transported to hot cell within 40 hours in the case the cool down time is one month. In the horizontal sector transport maintenance, the maintenance time including removal of cooling piping, drain of cooling water and sector transport to hot cell is about 32 hours. Furthermore, the tritium release in the sector transport can be suppressed because the components temperature drops by forced-air cooling system. This paper mainly focuses on a sector transport maintenance scheme from the aspects of high plant availability

  19. Human factor analysis and preventive countermeasures in nuclear power plant

    International Nuclear Information System (INIS)

    Li Ye

    2010-01-01

    Based on the human error analysis theory and the characteristics of maintenance in a nuclear power plant, human factors of maintenance in NPP are divided into three different areas: human, technology, and organization. Which is defined as individual factors, including psychological factors, physiological characteristics, health status, level of knowledge and interpersonal skills; The technical factors including technology, equipment, tools, working order, etc.; The organizational factors including management, information exchange, education, working environment, team building and leadership management,etc The analysis found that organizational factors can directly or indirectly affect the behavior of staff and technical factors, is the most basic human error factor. Based on this nuclear power plant to reduce human error and measures the response. (authors)

  20. Negative transcriptional regulation of mitochondrial transcription factor A (TFAM) by nuclear TFAM

    International Nuclear Information System (INIS)

    Lee, Eun Jin; Kang, Young Cheol; Park, Wook-Ha; Jeong, Jae Hoon; Pak, Youngmi Kim

    2014-01-01

    Highlights: • TFAM localizes in nuclei and mitochondria of neuronal cells. • Nuclear TFAM does not bind the Tfam promoter. • Nuclear TFAM reduced the Tfam promoter activity via suppressing NRF-1 activity. • A novel self-negative feedback regulation of Tfam gene expression is explored. • FAM may play different roles depending on its subcellular localizations. - Abstract: The nuclear DNA-encoded mitochondrial transcription factor A (TFAM) is synthesized in cytoplasm and transported into mitochondria. TFAM enhances both transcription and replication of mitochondrial DNA. It is unclear, however, whether TFAM plays a role in regulating nuclear gene expression. Here, we demonstrated that TFAM was localized to the nucleus and mitochondria by immunostaining, subcellular fractionation, and TFAM-green fluorescent protein hybrid protein studies. In HT22 hippocampal neuronal cells, human TFAM (hTFAM) overexpression suppressed human Tfam promoter-mediated luciferase activity in a dose-dependent manner. The mitochondria targeting sequence-deficient hTFAM also repressed Tfam promoter activity to the same degree as hTFAM. It indicated that nuclear hTFAM suppressed Tfam expression without modulating mitochondrial activity. The repression required for nuclear respiratory factor-1 (NRF-1), but hTFAM did not bind to the NRF-1 binding site of its promoter. TFAM was co-immunoprecipitated with NRF-1. Taken together, we suggest that nuclear TFAM down-regulate its own gene expression as a NRF-1 repressor, showing that TFAM may play different roles depending on its subcellular localizations

  1. Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip; Marincel, Michelle K.

    2008-03-01

    This report summarizes the results of three detailed studies of the physical protection systems for the protection of nuclear materials transport in Japan, with an emphasis on the transportation of mixed oxide fuel materials1. The Japanese infrastructure for transporting nuclear fuel materials is addressed in the first section. The second section of this report presents a summary of baseline data from the open literature on the threats of sabotage and theft during the transport of nuclear fuel materials in Japan. The third section summarizes a review of current International Atomic Energy Agency, Japanese and United States guidelines and regulations concerning the physical protection for the transportation of nuclear fuel materials.

  2. b-jet tagged nuclear modification factors in heavy ion collisions with CMS

    CERN Document Server

    Jung, Kurt

    2014-01-01

    The energy loss of jets in heavy-ion collisions is expected to depend on the flavor of the fragmenting parton. Thus, measurements of jet quenching as a function of flavor place powerful constraints on the thermodynamical and transport properties of the hot and dense medium. Measurements of the nuclear modification factors of the heavy-flavor-tagged jets in both PbPb and pPb collisions can quantify such energy loss effects. Specifically, pPb measurements provide crucial insights into the behavior of the cold nuclear matter effect, which is required to fully understand the hot and dense medium effects on jets in PbPb collisions. In this talk, we present the b-jet spectra and the first measurement of the nuclear modification factors as a function of transverse momentum and pseudorapidity, using the high statistics pp, pPb and PbPb data taken in 2011 and 2013.

  3. Research of human factor in nuclear power plants

    International Nuclear Information System (INIS)

    Nopp, I.

    1983-01-01

    The question is discussed of the study of the human factor with regard to the reliability of nuclear power plant operation. The reliability of the human factor is the result of the functional fitness, motivation, working conditions and working regime of personnel. (J.B.)

  4. Economic benefits of power factor correction at a nuclear facility

    International Nuclear Information System (INIS)

    Boger, R.M.; Dalos, W.; Juguilon, M.E.

    1986-01-01

    The economic benefits of correcting poor power factor at an operating nuclear facility are shown. A project approach for achieving rapid return of investment without disrupting plant availability is described. Examples of technical problems associated with using capacitors for power factor correction are presented

  5. Nuclear energy - stabilising factor in the world economy

    International Nuclear Information System (INIS)

    Legassov, V.; Feoktistov, L.; Kouzmine, I.

    1986-01-01

    One of the most important factors for international stability is the development of the economy, reducing the risk of local armed conflicts which could escalate into world-wide nuclear war. Economic progress which plays such a vital part is in turn heavily dependent on energy supplies. The article takes a brief look at the role of nuclear power in this context. (B.M.S.)

  6. Physical protection in the transport of nuclear materials (Legal aspects of the domestic system)

    International Nuclear Information System (INIS)

    Novais, F.J.G.

    1978-04-01

    A study of the physical protection system is made. Emphasis is given to some considerations in the nuclear material transport area, mainly the details of the domestic system, from a juridic pont of view. (Author) [pt

  7. Multiple nucleon transfer in damped nuclear collisions. [Lectures, mass charge, and linear and angular momentum transport

    Energy Technology Data Exchange (ETDEWEB)

    Randrup, J.

    1979-07-01

    This lecture discusses a theory for the transport of mass, charge, linear, and angular momentum and energy in damped nuclear collisions, as induced by multiple transfer of individual nucleons. 11 references.

  8. Transfer factors for nuclear emergency preparedness

    Energy Technology Data Exchange (ETDEWEB)

    Kostiainen, E.; Haenninen, R. [Radiation and Nuclear Safety Authority (STUK) (Finland); Rosen, K.; Haak, E.; Eriksson, Aa. [Swedish Univ. of Agricultural Science (Sweden); Nielsen, S.P.; Keith-Roach, M. [Risoe National Lab. (Denmark); Salbu, B. [Agricultural Univ. of Norway (Norway)

    2002-12-01

    This report by the NKS/BOK-1.4 project subgroup describes transfer factors for radiocaesium and radiostrontium for the fallout year and the years after the fallout. The intention has been to collect information on tools to assess the order of magnitude of radioactive contamination of agricultural products in an emergency situation in Nordic environment. The report describes transfer paths from fallout to plant, from soil to plant and to animal products. The transfer factors of radionuclides (Sr, Cs, I) given in the report are intended to be used for making rough estimates of the contamination of agricultural products soon after the heaviness and composition of the deposition (Bq m{sup -2}) is known. (au)

  9. Transfer factors for nuclear emergency preparedness

    International Nuclear Information System (INIS)

    Kostiainen, E.; Haenninen, R.; Rosen, K.; Haak, E.; Eriksson, Aa.; Nielsen, S.P.; Keith-Roach, M.; Salbu, B.

    2002-12-01

    This report by the NKS/BOK-1.4 project subgroup describes transfer factors for radiocaesium and radiostrontium for the fallout year and the years after the fallout. The intention has been to collect information on tools to assess the order of magnitude of radioactive contamination of agricultural products in an emergency situation in Nordic environment. The report describes transfer paths from fallout to plant, from soil to plant and to animal products. The transfer factors of radionuclides (Sr, Cs, I) given in the report are intended to be used for making rough estimates of the contamination of agricultural products soon after the heaviness and composition of the deposition (Bq m -2 ) is known. (au)

  10. Human factors engineering in nuclear plant rehabilitations

    International Nuclear Information System (INIS)

    Bernston, K.; Remisz, M.; Malcolm, S.

    2001-01-01

    There are several unique considerations when creating and maintaining a human factors program for a plant refurbishment. These consideration arise from a variety of sources, including budget and time constraints on life extension projects, working to existing plant protocols and current acceptable HFE practices, and issues relating to function and task analysis. This results in a need to streamline and carefully time HFE practices from project start up to completion. In order to perform this task adequately, a comprehensive Human Factors Engineering Program Plan should be designed and tailored to the project. Systems of planning and prioritization are essential, and the required HFE designer training needs to be established. HFE specialists need to be aware of the existing plant constraints, and he prepared to work within them when providing support. The current paper discusses these aspects in the context of major refurbishment work at CANDU stations. (author)

  11. Key Factors for Nuclear Being Economic after Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Roh, Myung Sub; Park, Seo Yeon [KEPCO International Nuclear Graduate School, Ulju (Korea, Republic of)

    2012-05-15

    It is hard to overstate the importance of electricity to the standard of living and the quality of life in a country. Electricity demand grows with population and with the changing nature, level and composition of economic and social activity. Civilization, industrialization and urbanization are, of course, key factors. It, historically, has shown that each major nuclear accident has caused a re-examination of the risk of nuclear power leading to more stringent safety requirement and higher costs. The Fukushima accident and its likely impact on future nuclear power development are difficult to foresee. The accident was a tragedy for the people affected and seriously undermined public confidence in the safety of nuclear power. A number of countries announced reviews of their programs, some took steps toward phasing out nuclear power entirely, and others reemphasized their expansion plans. The Korean nuclear community is carry out many ambitious projects for last three decades continuously and facing the another challenges relating to the future nuclear power economics and difficulty in financing new investment. In order to meet the above economic objective, it is strongly recommended that great emphasis should be placed on maintaining the nuclear economics without jeopardizing safety such as design simplification, standardization, shortening of construction period, increased availability, etc

  12. Key Factors for Nuclear Being Economic after Fukushima

    International Nuclear Information System (INIS)

    Roh, Myung Sub; Park, Seo Yeon

    2012-01-01

    It is hard to overstate the importance of electricity to the standard of living and the quality of life in a country. Electricity demand grows with population and with the changing nature, level and composition of economic and social activity. Civilization, industrialization and urbanization are, of course, key factors. It, historically, has shown that each major nuclear accident has caused a re-examination of the risk of nuclear power leading to more stringent safety requirement and higher costs. The Fukushima accident and its likely impact on future nuclear power development are difficult to foresee. The accident was a tragedy for the people affected and seriously undermined public confidence in the safety of nuclear power. A number of countries announced reviews of their programs, some took steps toward phasing out nuclear power entirely, and others reemphasized their expansion plans. The Korean nuclear community is carry out many ambitious projects for last three decades continuously and facing the another challenges relating to the future nuclear power economics and difficulty in financing new investment. In order to meet the above economic objective, it is strongly recommended that great emphasis should be placed on maintaining the nuclear economics without jeopardizing safety such as design simplification, standardization, shortening of construction period, increased availability, etc

  13. Overview of factors affecting the leachability of nuclear waste forms

    International Nuclear Information System (INIS)

    Stone, J.A.

    1980-01-01

    An overview of various factors that affect the leachability of nuclear waste forms is presented. The factors affect primarily the leaching system (temperature, for example), the leachant (pH, for example), or the solid being leached (surface condition, for example). A qualitative understanding exists of the major factors affecting leaching, but further studies are needed to establish leaching mechanisms and develop predictive models. 67 refs

  14. A regulatory perspective on human factors in nuclear power

    International Nuclear Information System (INIS)

    Whitfield, D.

    1987-01-01

    This paper sets out the approaches being taken by the United Kingdom Nuclear Installations Inspectorate (NII) to monitoring the application of human factors principles and practice in the UK industry. The role of NII is outlined, the development of human factors concerns is reviewed, the assessment of the Sizewell 'B' safety case is presented as a particular example, and pertinent future developments in the human factors discipline are proposed. (author)

  15. Development of nuclear spent fuel Maritime transportation scenario

    International Nuclear Information System (INIS)

    Yoo, Min; Kang, Hyun Gook

    2014-01-01

    Spent fuel transportation of South Korea is to be conducted through near sea because it is able to ship a large amount of the spent fuel far from the public comparing to overland transportation. The maritime transportation is expected to be increased and its risk has to be assessed. For the risk assessment, this study utilizes the probabilistic safety assessment (PSA) method and the notions of the combined event. Risk assessment of maritime transportation of spent fuel is not well developed in comparison with overland transportation. For the assessment, first, the transportation scenario should be developed and categorized. Categories are assorted into the locations, release aspects and exposure aspects. This study deals with accident that happens on voyage and concentrated on ship-ship collision. The collision accident scenario is generated with event tree analysis. The scenario will be exploited for the maritime transportation risk model which includes consequence and accident probability

  16. Development of nuclear spent fuel Maritime transportation scenario

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Min; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

    2014-08-15

    Spent fuel transportation of South Korea is to be conducted through near sea because it is able to ship a large amount of the spent fuel far from the public comparing to overland transportation. The maritime transportation is expected to be increased and its risk has to be assessed. For the risk assessment, this study utilizes the probabilistic safety assessment (PSA) method and the notions of the combined event. Risk assessment of maritime transportation of spent fuel is not well developed in comparison with overland transportation. For the assessment, first, the transportation scenario should be developed and categorized. Categories are assorted into the locations, release aspects and exposure aspects. This study deals with accident that happens on voyage and concentrated on ship-ship collision. The collision accident scenario is generated with event tree analysis. The scenario will be exploited for the maritime transportation risk model which includes consequence and accident probability.

  17. Goal system for comparative assessments of nuclear fuel transport under security aspects

    International Nuclear Information System (INIS)

    Behrendt, V.; Schwieren, G.

    1983-01-01

    Due to the great hazard potential of nuclear fuel transports the possibility always exists during transportation that either a single perpetrator or a group of perpetrators will try to get possession of the nuclear fuel. One can assume that at the end of such illegal actions there will be a politically (or otherwise) motivated extortion. Thinking about security one has to face things like sabotage, attacks from inside or outside the system, robbery and/or dispersion of the transported goods. In respect to the security of nuclear transports we carried out an investigation for the German Ministry of the Interior in order to review the different levels of security of different transport systems. This paper deals with the methodological approach, especially with the goal system and the way we executed the investigation

  18. Human factor engineering applied to nuclear power plant design

    International Nuclear Information System (INIS)

    Manrique, A.; Valdivia, J.C.; Jimenez, A.

    2001-01-01

    For the design and construction of new nuclear power plants as well as for maintenance and operation of the existing ones new man-machine interface designs and modifications are been produced. For these new designs Human Factor Engineering must be applied the same as for any other traditional engineering discipline. Advantages of implementing adequate Human Factor Engineering techniques in the design of nuclear reactors have become not only a fact recognized by the majority of engineers and operators but also an explicit requirement regulated and mandatory for the new designs of the so called advanced reactors. Additionally, the big saving achieved by a nuclear power plant having an operating methodology which significantly decreases the risk of operating errors makes it necessary and almost vital its implementation. The first step for this is preparing a plan to incorporate all the Human Factor Engineering principles and developing an integral design of the Instrumentation and Control and Man-machine interface systems. (author)

  19. The significance of human factors in nuclear activities

    International Nuclear Information System (INIS)

    Weil, L.; Berg, H.P.

    1999-01-01

    Human factors is an aspect increasingly investigated in the last few years in efforts and programmes for enhancing the operational safety of nuclear systems. Methodology has been elaborated for analysis and evaluation of human reliability, or development of instruments supporting the decisions to be taken by the operators at the man-control room interface of nuclear installations, as well as initial approaches to introduce organisational factors which may influence the man-machine function allocation, and thus are an element of the safety culture concept. The significance of human factors in nuclear activities, as well as activities at the national and international level for optimisation of the man-machine interface and the man-organisation interface are discussed. (orig./CB) [de

  20. Human factors in the Canadian nuclear industry: future needs

    International Nuclear Information System (INIS)

    Harrison, F.

    2008-01-01

    Currently the industry is facing refurbishment and new builds. At present most licensees in Canada do not have sufficient numbers of Human Factors staff. As a result, the activities of the CNSC are too often focused on providing guidance regarding the application of Human Factors, in addition to reviewing work submitted by the licensee. Greater efficiencies for both the licensee and the CNSC could be realized if licensee staff had greater Human Factors expertise. Strategies for developing Human Factors expertise should be explored through cooperative partnerships with universities, which could be encouraged to include Human Factors courses specific to nuclear. (author)

  1. Human factor in the problem of Russian nuclear industry safety

    International Nuclear Information System (INIS)

    Abramova, V.

    2002-01-01

    The approach to human factor definition, considered in the paper, consists of recognition of as many as possible factors for developing a complete list of factors, which have influence on mistakes or successful work of NPP personnel. Safety culture is considered as the main factor. The enhancement in nuclear power industry includes an optimization of organizational structures and development of personnel safety attitudes. The organizational factors, as possible root causes for human errors, need to be identified, assessed and improved. The organizational activities taken in Russia are presented

  2. Spatial dose and microdose distribution in tissues. Ionization, nuclear reactions, multiple scattering simulation of beam transport

    International Nuclear Information System (INIS)

    Jacquot, C.

    1976-01-01

    Computer simulation and nuclear emulsion and gelatin techniques enabled to give the total elastic and inelastic cross sections and to forecast the spatial microdose distributions in cells, nuclei and molecules. For this purpose, the transport of a beam into tissues having a given composition is calculated, the nuclear reactions are generated and the energy depositions in standard planes perpendicular to the beam are recorded

  3. US Nuclear Regulatory Commission human-factors program plan

    International Nuclear Information System (INIS)

    1983-08-01

    The purpose of the NRC Human Factors Program Plan is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This initial plan addresses nuclear power plants (NPP) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, The NRC Action Plan Developed as a Result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements, and (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-83 through FY-85 time frame

  4. Correction factors for photon spectrometry in nuclear parameters study

    International Nuclear Information System (INIS)

    Patrao, Karla Cristina de Souza

    2004-10-01

    The goal of this work was the determination, using metrologic severity, the factors of correction for coincidences XX, Xγ and γγ and the factors of transference of efficiency for use in gamma spectrometry. On this way, it was carried through by determination of nuclear parameters of a nuclide used in medicine diagnostic ( 201 Tl) and the standardization of two environmental samples, of regular and irregular geometry, proceeding from the residual (ashes and slag) from the nuclear industry. The results shows that this adopted methodology is valid, and it allows its application for many different nuclides, including complex decay schema nuclides, using only photons spectrometry techniques on semiconductor detectors. (author)

  5. Nuclear modification factor using Tsallis non-extensive statistics

    Energy Technology Data Exchange (ETDEWEB)

    Tripathy, Sushanta; Garg, Prakhar; Kumar, Prateek; Sahoo, Raghunath [Indian Institute of Technology Indore, Discipline of Physics, School of Basic Sciences, Simrol (India); Bhattacharyya, Trambak; Cleymans, Jean [University of Cape Town, UCT-CERN Research Centre and Department of Physics, Rondebosch (South Africa)

    2016-09-15

    The nuclear modification factor is derived using Tsallis non-extensive statistics in relaxation time approximation. The variation of the nuclear modification factor with transverse momentum for different values of the non-extensive parameter, q, is also observed. The experimental data from RHIC and LHC are analysed in the framework of Tsallis non-extensive statistics in a relaxation time approximation. It is shown that the proposed approach explains the R{sub AA} of all particles over a wide range of transverse momentum but does not seem to describe the rise in R{sub AA} at very high transverse momenta. (orig.)

  6. Further activities of safety culture toward nuclear transportation industry

    International Nuclear Information System (INIS)

    Machida, Y.; Shimakura, D.

    2004-01-01

    On September 30, 1999, a criticality accident occurred at the uranium processing facility of the JCO Co. Ltd. (hereinafter referred to as ''JCO'') Tokai plant, located in Tokaimura, Ibaraki Prefecture. This was an unprecedented accident in Japan's history of peaceful use of nuclear power, resulting in three workers exposed to severe radiation, two of whom died, and the evacuation and enforced indoor confinement of local residents. Nuclear power suppliers must take personal responsibility for ensuring safety. In this connection, the electric power industry, heavy electric machinery manufacturers, fuel fabricators, and nuclear power research organizations gathered together to establish the Nuclear Safety Network (NSnet) in December 1999, based on the resolve to share and improve the level of the safety culture across the entire nuclear power industry and to assure that such an accident never occurs again. NSnet serves as a link between nuclear power enterprises, research organizations, and other bodies, based on the principles of equality and reciprocity. A variety of activities are pursued, such as diffusing a safety culture, implementing mutual evaluation among members, and exchanging safety-related information. Aiming to share and improve the safety culture throughout the entire nuclear power industry, NSnet thoroughly implements the principle of safety first, while at the same time making efforts to restore trust in nuclear power

  7. Further activities of safety culture toward nuclear transportation industry

    Energy Technology Data Exchange (ETDEWEB)

    Machida, Y.; Shimakura, D. [NSnet, Tokyo (Japan)

    2004-07-01

    On September 30, 1999, a criticality accident occurred at the uranium processing facility of the JCO Co. Ltd. (hereinafter referred to as ''JCO'') Tokai plant, located in Tokaimura, Ibaraki Prefecture. This was an unprecedented accident in Japan's history of peaceful use of nuclear power, resulting in three workers exposed to severe radiation, two of whom died, and the evacuation and enforced indoor confinement of local residents. Nuclear power suppliers must take personal responsibility for ensuring safety. In this connection, the electric power industry, heavy electric machinery manufacturers, fuel fabricators, and nuclear power research organizations gathered together to establish the Nuclear Safety Network (NSnet) in December 1999, based on the resolve to share and improve the level of the safety culture across the entire nuclear power industry and to assure that such an accident never occurs again. NSnet serves as a link between nuclear power enterprises, research organizations, and other bodies, based on the principles of equality and reciprocity. A variety of activities are pursued, such as diffusing a safety culture, implementing mutual evaluation among members, and exchanging safety-related information. Aiming to share and improve the safety culture throughout the entire nuclear power industry, NSnet thoroughly implements the principle of safety first, while at the same time making efforts to restore trust in nuclear power.

  8. Quality- a Factor of Management in Road Transport of Goods

    Directory of Open Access Journals (Sweden)

    Livij Jakomin

    2012-10-01

    Full Text Available Providing services on a quality level is an important factorof management in the trade rivalry for the control over the market.The factors affecting quality comprise technical factors andoperational and organisational ones. The technical factors includethe choice, the due care and maintenance of the vehicle.The operational and organisational factors are the quality offer,performing the transport service, the response in case of action,and the information efficiency.The necessity to control the total quality management is theresponsibility of the management. All staff members must participatein the improvement of quality management in their particularworking environment. Improved quality managementprovides for a higher safety of business operation and jobs, resultingin enhanced social security, which is gaining importancein mutual relations.

  9. Economic Conditions and Factors Affecting New Nuclear Power Deployment

    Energy Technology Data Exchange (ETDEWEB)

    Harrison, Thomas J [ORNL

    2014-10-01

    This report documents work performed in support of the US Department of Energy Office of Nuclear Energy’s Advanced Small Modular Reactor (AdvSMR) program. The report presents information and results from economic analyses to describe current electricity market conditions and those key factors that may impact the deployment of AdvSMRs or any other new nuclear power plants. Thus, this report serves as a reference document for DOE as it moves forward with its plans to develop advanced reactors, including AdvSMRs. For the purpose of this analysis, information on electricity markets and nuclear power plant operating costs will be combined to examine the current state of the nuclear industry and the process required to successfully move forward with new nuclear power in general and AdvSMRs in particular. The current electricity market is generally unfavorable to new nuclear construction, especially in deregulated markets with heavy competition from natural gas and subsidized renewables. The successful and profitable operation of a nuclear power plant (or any power plant) requires the rate at which the electricity is sold to be sufficiently greater than the cost to operate. The wholesale rates in most US markets have settled into values that provide profits for most operating nuclear power plants but are too low to support the added cost of capital recovery for new nuclear construction. There is a strong geographic dependence on the wholesale rate, with some markets currently able to support new nuclear construction. However, there is also a strong geographic dependence on pronuclear public opinion; the areas where power prices are high tend to have unfavorable views on the construction of new nuclear power plants. The use of government-backed incentives, such as subsidies, can help provide a margin to help justify construction projects that otherwise may not seem viable. Similarly, low interest rates for the project will also add a positive margin to the economic

  10. Factors which could limit the nuclear fuel cycle development

    International Nuclear Information System (INIS)

    Pecqueur, M.; Barre, B.

    1977-01-01

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

  11. Human factor in the process of nuclear power development

    International Nuclear Information System (INIS)

    Enenkl, V.

    The building up of nuclear power requires the training not only of personnel but of the whole population as well. Professional workers in nuclear power facilities production and personnel operating the equipment of nuclear power plants must be on a high technical and managerial level. The important quality of such personnel is their reliability and responsibility. The human factor influences the level, quality and thereby also the service-life of the machines and equipment and their operation. The improvement of the quality of work in nuclear power production depends on upgrading the scientific and technical level of workers and personnel, their training, in-service education and the raising of the social standing. (B.H.)

  12. Novel nuclear-encoded proteins interacting with a plastid sigma factor, Sig1, in Arabidopsis thaliana.

    Science.gov (United States)

    Morikawa, Kazuya; Shiina, Takashi; Murakami, Shinya; Toyoshima, Yoshinori

    2002-03-13

    Sigma factor binding proteins are involved in modifying the promoter preferences of the RNA polymerase in bacteria. We found the nuclear encoded protein (SibI) that is transported into chloroplasts and interacts specifically with the region 4 of Sig1 in Arabidopsis. SibI and its homologue, T3K9.5 are novel proteins, which are not homologous to any protein of known function. The expression of sibI was tissue specific, light dependent, and developmentally timed. We suggest the transcriptional regulation by sigma factor binding proteins to function in the plastids of higher plant.

  13. Spent nuclear fuel transport: Problem state and analysis of modern approaches

    International Nuclear Information System (INIS)

    Nosovs'kij, A.V.; Yatsenko, M.V.

    2018-01-01

    The paper presents the review of international and national experience related to transport of spent nuclear fuel (SNF) and trends in the development of transport containers. The analysis covers the vectors for the future improvement of packaging and the regulatory framework on SNF transport in Ukraine and other countries. The tasks for future research were identified. The results of this research will be used during the operation of the CSNSF.

  14. Executive summary of safeguards systems concepts for nuclear material transportation. Final report

    International Nuclear Information System (INIS)

    Baldonado, O.C.; Kevany, M.; Rodney, D.; Pitts, D.; Mazur, M.

    1977-09-01

    The U.S. Nuclear Regulatory Commission contracted with System Development Corporation to develop integrated system concepts for the safeguard of special strategic nuclear materials (SSNM), which include plutonium, uranium 233 and uranium 235 of at least 20 percent enrichment, against malevolent action during interfacility transport. This executive summary outlines the conduct and findings of the project. The study was divided into three major subtasks: (1) The development of adversary action sequences; (2) The assessment of the vulnerability of the transport of nuclear materials to adversary action; (3) The development of conceptual safeguards system design requirements to reduce vulnerabilities

  15. Supporting system in emergency response plan for nuclear material transport accidents

    International Nuclear Information System (INIS)

    Nakagome, Y.; Aoki, S.

    1993-01-01

    As aiming to provide the detailed information concerning nuclear material transport accidents and to supply it to the concerned organizations by an online computer, the Emergency Response Supporting System has been constructed in the Nuclear Safety Technology Center, Japan. The system consists of four subsystems and four data bases. By inputting initial information such as name of package and date of accident, one can obtain the appropriate initial response procedures and related information for the accident immediately. The system must be useful for protecting the public safety from nuclear material transport accidents. But, it is not expected that the system shall be used in future. (J.P.N.)

  16. Transportation of irradiated fuel elements

    International Nuclear Information System (INIS)

    1980-01-01

    A critique is presented of current methods of transporting spent nuclear fuel and the inadequacies of the associated contingency plans, with particular reference to the transportation of irradiated fuel through London. Anti-nuclear and pro-nuclear arguments are presented on a number of factors, including tests on flasks, levels of radiation exposure, routine transport arrangements and contingency arrangements. (U.K.)

  17. Overview of transportation in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Rhoads, R.E.

    1977-05-01

    This document presents a review of current transportation regulations, a description of transportation systems currently in use, a discussion of systems that are anticipated to be developed in the future and a projection of shipments and shipping distances through the year 2000

  18. Comprehensive transportation risk assessment system based on unit-consequence factors

    International Nuclear Information System (INIS)

    Biwer, B.M.; Monette, F.A.; LePoire, D.J.; Chen, S.Y.

    1994-01-01

    The U.S. Department of Energy (DOE) Environmental Restoration and Waste Management Programmatic Environmental Impact Statement requires a comprehensive transportation risk analysis of radioactive waste shipments for large shipping campaigns. Thousands of unique shipments involving truck and rail transport must be analyzed; a comprehensive risk analysis is impossible with currently available methods. Argonne National Laboratory developed a modular transportation model that can handle the demands imposed by such an analysis. The modular design of the model facilitates the simple addition/updating of transportation routes and waste inventories, as required, and reduces the overhead associated with file maintenance and quality assurance. The model incorporates unit-consequences factors generated with the RADTRAN 4 transportation risk analysis code that are combined with an easy-to-use, menu-driven interface on IBM-compatible computers running under DOS. User selection of multiple origin/destination site pairs for the shipment of multiple radioactive waste inventories is permitted from pop-up lists. Over 800 predefined routes are available among more than 30 DOE sites and waste inventories that include high-level waste, spent nuclear fuel, transuranic waste, low-level waste, low-level mixed waste, and greater-than-Class C waste

  19. Planned reliability in the transport and installation of large nuclear components

    International Nuclear Information System (INIS)

    Bieler, L.

    1988-01-01

    The transport and installation of heavy and bulky large components require detailed planning of all jobs and activities, trained and experienced personnel and corresponding technical equipment for reliable and quality-assured implementation. The correct approach to the planning and implementation of such transports and installations has been confirmed by years of successful performance of these jobs e.g. in reactor pressure vessels and steam generators for nuclear power plants. Large components for nuclear power plants are truly extreme examples but will be all the better suited for demonstrating the problems inherent in transport and installation. (orig.) [de

  20. Storage, handling and internal transport of radioactive materials (fuel elements excepted) in nuclear power plants

    International Nuclear Information System (INIS)

    1983-06-01

    The rule applies to storage and handling as well as to transport within the plant and to the exchange of - solid radioactive wastes, - liquid radioactive wastes, except for those covered by the rule KTA 3603, - radioactive components and parts which are planned to be mounted and dismounted until shutdown of the plant, - radioactive-contaminated tools and appliances, - radioactive preparations. The rule is to be applied within the fenced-in sites of stationary nuclear power plants with LWR or HTR including their transport load halls, as fas as these are situated so as to be approachable from the nuclear power station by local transport systems. (orig./HP) [de

  1. Sea transport of used nuclear fuel and radiactive disposals to a Swedish central store

    International Nuclear Information System (INIS)

    1977-10-01

    Sea transport of used nuclear fuel and radioactive disposals to a Swedish central store. A vessel for transporting used nuclear fuel and radioactive disposals from the power stations at Ringhals, Barsebaeck, Simpevarp and Forsmark to a central store has been projected. Safety aspects, technical and economical aspects have been taken into consideration with regard to the actual volume of goods to be transported. Three different types of vessels are presented and a specification is given for the main alternative. A safety study of the main alternative is shown, regarding collision safety, fire risks and fire extinguishing equipment. (author)

  2. Human factors engineering plan for reviewing nuclear plant modernization programs

    International Nuclear Information System (INIS)

    O'Hara, John; Higgins, James

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation

  3. Human factors engineering plan for reviewing nuclear plant modernization programs

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, John; Higgins, James [Brookhaven National Laboratory, Upton, NY (United States)

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation.

  4. Single HIV-1 Imaging Reveals Progression of Infection through CA-Dependent Steps of Docking at the Nuclear Pore, Uncoating, and Nuclear Transport.

    Science.gov (United States)

    Francis, Ashwanth C; Melikyan, Gregory B

    2018-04-11

    The HIV-1 core consists of capsid proteins (CA) surrounding viral genomic RNA. After virus-cell fusion, the core enters the cytoplasm and the capsid shell is lost through uncoating. CA loss precedes nuclear import and HIV integration into the host genome, but the timing and location of uncoating remain unclear. By visualizing single HIV-1 infection, we find that CA is required for core docking at the nuclear envelope (NE), whereas early uncoating in the cytoplasm promotes proteasomal degradation of viral complexes. Only docked cores exhibiting accelerated loss of CA at the NE enter the nucleus. Interestingly, a CA mutation (N74D) altering virus engagement of host factors involved in nuclear transport does not alter the uncoating site at the NE but reduces the nuclear penetration depth. Thus, CA protects HIV-1 complexes from degradation, mediates docking at the nuclear pore before uncoating, and determines the depth of nuclear penetration en route to integration. Copyright © 2018 Elsevier Inc. All rights reserved.

  5. Informational system to assist decision making at spent nuclear fuel transportation from VVER-440, VVER-1000 and RBMK-1000 nuclear power plants

    International Nuclear Information System (INIS)

    Kuryndin, A.V.; Kirkin, A.M.; Stroganov, A.A.

    2012-01-01

    The developed informational system provides an automated estimations of nuclear and radiation safety parameters during spent nuclear fuel transportation from WWER-440 and WWER-1000 and RBMK-1000 nuclear power plants to the nuclear fuel cycle facilities, and allows us to determine the optimum cask loading from the dose rates distribution outside of protection point of view [ru

  6. High Fill-Factor Transport Experiments on the HCX

    International Nuclear Information System (INIS)

    Prost, L R; Seidl, P A; Lund, S M

    2004-01-01

    Heavy-ion induction linacs have application as drivers for high energy density physics studies and ultimately as drivers for inertial fusion energy. Experiments on the High-Current Experiment (HCX) at LBNL explore heavy-ion beam transport at high fill factors (i.e., the ratio of the maximum transverse extent of the beam to the physical aperture). The fill factor has a large impact on the cost of multi-beam induction accelerators, the 80% fill factor compared with 60% would reduce the cost of an HIF driver by about 1/3. With a coasting low-emittance 1 MeV K + beam, transport through ten electrostatic quadrupoles was achieved at high beam fill factor (80%) without observed emittance growth and with little beam loss ((le) 1%), even though the initial beam distribution is neither ideal nor in thermal equilibrium, see Figure. While 10 quadrupoles are too few for settling questions of emittance evolution in a long system, they are very relevant for studying the rapid initial evolution of the emittance and beam profile that is expected in the front end of an accelerator. Studies at higher fill factors are planned, so that the failure mode can be established. Good envelope control was achieved, suggesting that, in a longer lattice of similar design, rematching only every ten lattice periods (at 80% fill factor) will be sufficient. Agreement was reached between an improved envelope model and the data. Improvements to the model are: realistic quadrupole fringe fields based on 3D field calculations; quadrupole E z from the 3D lattice structure and corresponding radial focusing force; and corrections due to the grounded slit plates of the intercepting diagnostics that short out the self-field of the beam near those plates. We also find that understanding and controlling the time dependence of the envelope parameters is critical to achieving high fill factors, notably because of the injector and matching section dynamics

  7. Transport and repair of contaminated nuclear components - liabilities and insurance

    International Nuclear Information System (INIS)

    Brunego, C.; Deprimoz, J.; Engelhard, M.

    1983-01-01

    The nuclear park has been constructed fairly recently and has not yet required large-scale maintenance efforts; however account should now be taken of the fact that periodic checks of nuclear power plants will imply systematic transfers of irradiated or contaminated materials outside the plants. In this context, the paper reviews the nuclear third party liability regime under the Paris Convention and the Euratom directives on radiation protection. It then describes the cover offered by insurance pools in several European countries. (NEA) [fr

  8. Nanoscale stiffness topography reveals structure and mechanics of the transport barrier in intact nuclear pore complexes

    Science.gov (United States)

    Bestembayeva, Aizhan; Kramer, Armin; Labokha, Aksana A.; Osmanović, Dino; Liashkovich, Ivan; Orlova, Elena V.; Ford, Ian J.; Charras, Guillaume; Fassati, Ariberto; Hoogenboom, Bart W.

    2015-01-01

    The nuclear pore complex (NPC) is the gate for transport between the cell nucleus and the cytoplasm. Small molecules cross the NPC by passive diffusion, but molecules larger than ∼5 nm must bind to nuclear transport receptors to overcome a selective barrier within the NPC. Although the structure and shape of the cytoplasmic ring of the NPC are relatively well characterized, the selective barrier is situated deep within the central channel of the NPC and depends critically on unstructured nuclear pore proteins, and is therefore not well understood. Here, we show that stiffness topography with sharp atomic force microscopy tips can generate nanoscale cross-sections of the NPC. The cross-sections reveal two distinct structures, a cytoplasmic ring and a central plug structure, which are consistent with the three-dimensional NPC structure derived from electron microscopy. The central plug persists after reactivation of the transport cycle and resultant cargo release, indicating that the plug is an intrinsic part of the NPC barrier. Added nuclear transport receptors accumulate on the intact transport barrier and lead to a homogenization of the barrier stiffness. The observed nanomechanical properties in the NPC indicate the presence of a cohesive barrier to transport and are quantitatively consistent with the presence of a central condensate of nuclear pore proteins in the NPC channel.

  9. A review of tsp as one of the transportation security aspects of nuclear materials

    International Nuclear Information System (INIS)

    Wiryono

    2013-01-01

    A review has done for the Transportation Safety Plan (TSP) as one of the aspects of safety in the transport of nuclear materials. The review is necessary to harmonize national regulations with international practice. International practice of using TSP as one of the security requirements in addition to the Radiation Protection Program as a requirement of safety in the transport of nuclear materials. TSP is intended to ensure sound implementation of the transport of nuclear materials. TSP evaluation process can be done with a prescriptive approach, performance, and combinations. TSP contains information about administrative requirements, delivery security and response planning. TSP can be used to ensure the security of the implementation of the transport of nuclear materials effectively and efficiently. BAPETEN should require the applicant to submit the TSP as one document security requirements prior approval transporting nuclear materials. BAPETEN need to define the approach to the formulation and evaluation of TSP. BAPETEN need to set up an evaluation and inspection procedures for the implementation of TSP. (author)

  10. Personality Factors and Nuclear Power Plant Operators: Initial License Success

    Science.gov (United States)

    DeVita-Cochrane, Cynthia

    Commercial nuclear power utilities are under pressure to effectively recruit and retain licensed reactor operators in light of poor candidate training completion rates and recent candidate failures on the Nuclear Regulatory Commission (NRC) license exam. One candidate failure can cost a utility over $400,000, making the successful licensing of new operators a critical path to operational excellence. This study was designed to discover if the NEO-PI-3, a 5-factor measure of personality, could improve selection in nuclear utilities by identifying personality factors that predict license candidate success. Two large U.S. commercial nuclear power corporations provided potential participant contact information and candidate results on the 2014 NRC exam from their nuclear power units nation-wide. License candidates who participated (n = 75) completed the NEO-PI-3 personality test and results were compared to 3 outcomes on the NRC exam: written exam, simulated operating exam, and overall exam result. Significant correlations were found between several personality factors and both written and operating exam outcomes on the NRC exam. Further, a regression analysis indicated that personality factors, particularly Conscientiousness, predicted simulated operating exam scores. The results of this study may be used to support the use of the NEO-PI-3 to improve operator selection as an addition to the current selection protocol. Positive social change implications from this study include support for the use of a personality measure by utilities to improve their return-on-investment in candidates and by individual candidates to avoid career failures. The results of this study may also positively impact the public by supporting the safe and reliable operation of commercial nuclear power utilities in the United States.

  11. EDF, a utility and its own needs in the field of transport of nuclear materials

    International Nuclear Information System (INIS)

    Gouin, P.; Mignot, E.; Hoang, L.P.

    1989-01-01

    As one of the most important producers of nuclear electricity in the world, EDF is concerned by all the aspects of the transport of nuclear materials and more particularly by those related to the nuclear fuel cycle. EDF is not itself a specialist in this field and most of the transports along the nuclear fuel cycle is done for their own account by their usual partners such as COGEMA or TRANSNUCLEAIRE. Since the beginning of the French nuclear program, they have generally used for these transports casks that already exist on the market and which were well suited to their needs. Nevertheless, new and specific needs appeared during the progress of their nuclear program and have lead them to: study and build new casks or packages, use existing casks for new purposes, develop a device for the measurement of fuel assemblies burn up, develop a software to optimize the evacuation of irradiated fuel for reprocessing. The purpose of this paper is to describe these realization but as a preliminary, they will present briefly the importance of the transport of nuclear materials for EDF

  12. A report on human factors in nuclear safety

    International Nuclear Information System (INIS)

    1983-03-01

    Following the Three Mile Island incident of 1979, studies were undertaken by the Atomic Energy Control Board (AECB), in-house and through outside consultants, to address the role of human factors in the regulatory process. This report by the Advisory Committee on Nuclear Safety (ACNS) comments briefly on these studies and offers suggestions which would promote a more formal treatment of human factors by the AECB

  13. Factor of radioactive waste on nuclear power program

    International Nuclear Information System (INIS)

    Syed Abdul Malik Syed Zain

    2009-01-01

    Global warming phenomena and rising oil prices have brought the excitement of open space use of nuclear power. Arguments in favor of this technology range in terms of more environmentally friendly, energy diversification and cost efficiency has prompted the government to widen the choice of nuclear power be considered as a serious alternative. Despite the attractive factors to the use of these powers, there are also factors that stem from the continued development of nuclear power. These include the factor of safety, security, security of fuel supply, and public attention is often associated with radioactive waste management. This article attempts to debate specific to radioactive waste management factors that impact on public acceptance of a country's nuclear power program, especially in Malaysia. Starting from the absence of radioactive waste management policy to model uncertainty of the landfill and complications in selecting a repository site shows the basic infrastructure is still lacking. In addition, previous experience handling thorium waste has not reached a final settlement after several years of implementation. It reinforced the perception about the level of public confidence in the competence and attitude of local workers who are not very encouraging to pursue this advanced.

  14. on skin keratinocytes by nuclear factor-kappa B

    African Journals Online (AJOL)

    DR. NJ TONUKARI

    2012-06-21

    Jun 21, 2012 ... Effects of advanced glycation end-products (AGEs) on ... AGE levels, nuclear factor-kappa B (NF-κB) localization and cell viability were measured in vivo. ..... and related alteration in NF-κB activity, we treated normal cells by ...

  15. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    International Nuclear Information System (INIS)

    Yuan, Y.C.; Chen, S.Y.; LePoire, D.J.

    1993-02-01

    This report presents the technical details of RISIUND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, semiinteractive program that can be run on an IBM or equivalent personal computer. The program language is FORTRAN-77. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incidentfree models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionudide inventory and dose conversion factors

  16. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Yuan, Y.C. [Square Y, Orchard Park, NY (United States); Chen, S.Y.; LePoire, D.J. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Rothman, R. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

    1993-02-01

    This report presents the technical details of RISIUND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, semiinteractive program that can be run on an IBM or equivalent personal computer. The program language is FORTRAN-77. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incidentfree models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionudide inventory and dose conversion factors.

  17. New safety and security requirements for the transport of nuclear and other radioactive materials in Hungary

    International Nuclear Information System (INIS)

    Katona, T.; Horvath, K.; Safar, J.

    2016-01-01

    In addition to the promulgation of mode-specific regulations of international transport of dangerous goods, some Hungarian governmental and ministerial decrees impose further conditions upon the transport of nuclear and other radioactive materials. One of these ministerial decrees on the transport, carriage and packaging of radioactive materials is under revision and it will require • approval of emergency response plan (including security and safety contingency plan); • report on transport incidents and accidents for classifying them in accordance with the INES scale; • the competent authority to request experts’ support for the approval of package designs, radioactive material designs and shipments. Regarding the security of the transport of nuclear and other radioactive materials a new Hungarian governmental decree and a related guidance are about to be published which will supply additional requirements in the field of the transport security especially concerning radioactive materials, implementing - among others - IAEA recommendations of the NSS No9 and No14. The main and relevant features of the Hungarian nuclear regulatory system and the details of both new decrees regarding the safety and security issues of transport of nuclear and other radioactive materials will be discussed. (author)

  18. Legal Framework and Best Practice for Improving Transport Security of Radioactive and Nuclear Materials in Croatia

    International Nuclear Information System (INIS)

    Ilijas, B.; Medakovic, S.

    2012-01-01

    Security of transporting radioactive and nuclear materials always poses a demanding task to the holder of the authorization or beneficiary, and especially transporter. Very strict and precise legal framework must be done for this purpose, yet it has not be too complicated to create a great problems in practice. The best balance between efficiency and simplicity should be achieved. In Croatia on power is 'The Dangerous Goods Transport Act' which stipulates the conditions for the carriage of dangerous goods in individual transport modes, obligations of persons participating in the carriage, requirements for packaging and vehicles, conditions for the appointment of safety advisers and safety adviser's rights and duties, competence and conditions for the implementation of training programs for persons participating in transport, competence of the state authorities related to such carriage and supervision of the implementation of the Act. Besides this Act, which regulates the issue in more general way, in preparation is a new 'Ordinance on Physical Security Measures for Radioactive Sources, Nuclear Material and Nuclear Facilities'. The intention of this Ordinance, in the part dealing with transport, is to bring specific approach, in accordance with IAEA guides, forwarding the most of obligations to the holder of the authorization or beneficiary and transporter, leaving state regulatory bodies mostly supervising role. In practice this can create some problems in the beginning, but with rising security awareness and after some experience collected, this can be the best way to achieve satisfactory security, yet not slowing down and complicating regular jobs with radioactive and nuclear materials.(author).

  19. Study on CPPNM Interpretation of the Physical Protection Regulatory Aspects for International Transport of Nuclear Material

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woo-jin; Yang, Seong-hyo; Hyung, Sang-chul [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2015-05-15

    Nuclear energy has been regulated by various international agreements or treaties due to the potential dangers. In case of export or import of nuclear material, it is important to comply with international norms and domestic laws related to nonproliferation and physical protection of nuclear material. Because, if non-compliant, it can be taken nuclear sanctions from the international community, and thus the domestic nuclear activities can be under a negative impact. Recently, international interests in nuclear security have been increased, it has become very sensitive to whether or not to join, and to comply with international treaties during international transportation of nuclear materials. Currently it is not discussed yet how to present and interpret the relevant provisions in CPPNM. However, it is necessary to prepare for the dispute among the parties that we don't know when it happens.

  20. Risk of transporting spent nuclear fuel by train

    International Nuclear Information System (INIS)

    Elder, H.K.

    1981-12-01

    This paper presents results of a study which analyzes the risk of transporting spent fuel by train. The risk assessment methodology consists of 4 basic steps: (1) a description of the system being analyzed; (2) identification of sequences of events that could lead to a release of material during transportation; (3) evaluation of the probability and consequences of each release sequence; and (4) assessment of the risk and evaluation of the results. The conclusion reached was that considering the substantial benefits derived from the fuel, the current spent fuel transportation system poses reasonably low risks

  1. Transportation: the vital tendons of the nuclear industry

    International Nuclear Information System (INIS)

    Jefferson, R.M.

    1979-01-01

    Of the 100 million packages of hazardous materials shipped each year, about 2 million contain radioactive materials; of these, only about 350,000 pertain to the fuel cycle and to radioactive wastes. A brief description is given of the philosophy responsible for the safe transportation of radioactive materials for the past 30 years. The range of problems facing the industry in the transportation of radioactive materials is discussed. DOE established a Transportation Technology Center at Sandia Laboratories in order to meet these problems

  2. Regulations for safe transport of spent fuels from nuclear power plants in CMEA member countries. Part III

    International Nuclear Information System (INIS)

    Zizka, B.

    1978-11-01

    The regulations for safe transport of spent fuel from nuclear power plants in the CMEA member countries consist of general provisions, technical requirements for spent fuel transport, transport conditions, procedures for submitting reports on transport, regulations for transport and protection of radioactive material to be transported, procedures for customs clearance, technical and organizational measures for the prevention of hypothetical accidents and the elimination of their consequences. The bodies responsible for spent fuel transport in the CMEA member countries are listed. (J.B.)

  3. Transport of Spent Nuclear Fuels, High and Intermediate Level Wastes: A Continuous Challenge

    International Nuclear Information System (INIS)

    Otton, C.; Blachet, L.

    2009-01-01

    For more than 45 years TN International has been involved in the radioactive materials transportation field. Since the beginning the used nuclear fuel transportation has been its core business. During all these years TN International, now part of AREVA, has been able to anticipate and fulfil the needs for new transport or storage casks design to fit the nuclear industry evolutions. A whole fleet of casks able to transport all the materials of the nuclear fuel cycle has been developed. In this presentation we will focus on the casks for the spent fuel, high level waste and intermediate level waste transportation. Answering to the constant evolution of the nuclear industry transport needs is a challenge that TN International faces routinely. Concerning the spent nuclear fuel transportation, TN International has developed in the early 80's a fleet of TN12 type casks fitted with several types of baskets able to safely transport all the spent fuel from the nuclear power plant or the research laboratories to AREVA La Hague plant. The current challenge is the design of a new transport cask generation taking into account the needs of the industry for the next 30 years. The replacement of the TN12 cask generation is to be scheduled as the regulations have changed and the fuel characteristics have evolved. The new generation of casks will take into account all the technical evolutions made during the TN12 thirty years of use. MOX spent fuel has now its dedicated cask: the TN112 which certificate of approval has been obtained in July 2008. This cask is able to transport 12 MOX spent fuel elements with a short cooling time. The first loading of the cask has been performed in 2008 in the EDF nuclear power plant of Saint-Laurent-des-Eaux. Concerning the high level waste such as the La Hague vitrified residues a whole fleet of casks has been developed such as the TN 28 VT dedicated to transport, the TN81 and TN85 dedicated to transport and storage. These casks have permitted the

  4. A Transportation Risk Assessment Tool for Analyzing the Transport of Spent Nuclear Fuel and High-Level Radioactive Waste to the Proposed Yucca Mountain Repository

    International Nuclear Information System (INIS)

    Best, Ralph; Winnard, T.; Ross, S.; Best, R.

    2001-01-01

    The Yucca Mountain Transportation Database was developed as a data management tool for assembling and integrating data from multiple sources to compile the potential transportation impacts presented in the Draft Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada (DEIS). The database uses the results from existing models and codes such as RADTRAN, RISKIND, INTERLINE, and HIGHWAY to estimate transportation-related impacts of transporting spent nuclear fuel and high-level radioactive waste from commercial reactors and U. S. Department of Energy (DOE) facilities to Yucca Mountain. The source tables in the database are compendiums of information from many diverse sources including: radionuclide quantities for each waste type; route and route characteristics for rail, legal-weight truck, heavy haul. truck, and barge transport options; state-specific accident and fatality rates for routes selected for analysis; packaging and shipment data by waste type; unit risk factors; the complex behavior of the packaged waste forms in severe transport accidents; and the effects of exposure to radiation or the isotopic specific effects of radionclides should they be released in severe transportation accidents. The database works together with the codes RADTRAN (Neuhauser, et al, 1994) and RISKlND (Yuan, et al, 1995) to calculate incident-free dose and accident risk. For the incident-free transportation scenario, the database uses RADTRAN and RISKIND-generated data to calculate doses to offlink populations, onlink populations, people at stops, crews, inspectors, workers at intermodal transfer stations, guards at overnight stops, and escorts, as well as non-radioactive pollution health effects. For accident scenarios, the database uses RADTRAN-generated data to calculate dose risks based on ingestion, inhalation, resuspension, immersion (cloudshine), and groundshine as

  5. Legal, institutional, and political issues in transportation of nuclear materials at the back end of the LWR nuclear fuel cycle

    International Nuclear Information System (INIS)

    Lippek, H.E.; Schuller, C.R.

    1979-03-01

    A study was conducted to identify major legal and institutional problems and issues in the transportation of spent fuel and associated processing wastes at the back end of the LWR nuclear fuel cycle. (Most of the discussion centers on the transportation of spent fuel, since this activity will involve virtually all of the legal and institutional problems likely to be encountered in moving waste materials, as well.) Actions or approaches that might be pursued to resolve the problems identified in the analysis are suggested. Two scenarios for the industrial-scale transportation of spent fuel and radioactive wastes, taken together, high-light most of the major problems and issues of a legal and institutional nature that are likely to arise: (1) utilizing the Allied General Nuclear Services (AGNS) facility at Barnwell, SC, as a temporary storage facility for spent fuel; and (2) utilizing AGNS for full-scale commercial reprocessing of spent LWR fuel

  6. Legal, institutional, and political issues in transportation of nuclear materials at the back end of the LWR nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Lippek, H.E.; Schuller, C.R.

    1979-03-01

    A study was conducted to identify major legal and institutional problems and issues in the transportation of spent fuel and associated processing wastes at the back end of the LWR nuclear fuel cycle. (Most of the discussion centers on the transportation of spent fuel, since this activity will involve virtually all of the legal and institutional problems likely to be encountered in moving waste materials, as well.) Actions or approaches that might be pursued to resolve the problems identified in the analysis are suggested. Two scenarios for the industrial-scale transportation of spent fuel and radioactive wastes, taken together, high-light most of the major problems and issues of a legal and institutional nature that are likely to arise: (1) utilizing the Allied General Nuclear Services (AGNS) facility at Barnwell, SC, as a temporary storage facility for spent fuel; and (2) utilizing AGNS for full-scale commercial reprocessing of spent LWR fuel.

  7. Transport of nuclear materials as an international project

    International Nuclear Information System (INIS)

    Bartejsova, Eva

    2010-01-01

    The following companies are involved in this project: CEZ a.s., ALTA a.s., ALTA 32 s.r.o., DMS s.r.o., TVEL (RF), and NUKLON (RF). Transport containers are TK-S5 (for Temelin) and TK-S55 (for Dukovany) types. Details of fuel supplies for the 2 Czech NPPs are described and the fresh fuel element transport procedure is highlighted. (P.A.)

  8. Below Grade Assessment of Spent Nuclear Fuel Cask Transport Route

    International Nuclear Information System (INIS)

    CHENAULT, D.M.

    1999-01-01

    The report provides an assessment of the route for the SNF Fuel transport system from the K Basins to the CVDF and to the CSB. Results include the identification of any underground structures or utilities traveled over by the transport, the overburden depths for all locations identified, evaluation of the loading conditions, and determination of the effects of the loads on the structures and utilities

  9. Probabilistic risk assessment on maritime spent nuclear fuel transportation (Part II: Ship collision probability)

    International Nuclear Information System (INIS)

    Christian, Robby; Kang, Hyun Gook

    2017-01-01

    This paper proposes a methodology to assess and reduce risks of maritime spent nuclear fuel transportation with a probabilistic approach. Event trees detailing the progression of collisions leading to transport casks’ damage were constructed. Parallel and crossing collision probabilities were formulated based on the Poisson distribution. Automatic Identification System (AIS) data were processed with the Hough Transform algorithm to estimate possible intersections between the shipment route and the marine traffic. Monte Carlo simulations were done to compute collision probabilities and impact energies at each intersection. Possible safety improvement measures through a proper selection of operational transport parameters were investigated. These parameters include shipment routes, ship's cruise velocity, number of transport casks carried in a shipment, the casks’ stowage configuration and loading order on board the ship. A shipment case study is presented. Waters with high collision probabilities were identified. Effective range of cruising velocity to reduce collision risks were discovered. The number of casks in a shipment and their stowage method which gave low cask damage frequencies were obtained. The proposed methodology was successful in quantifying ship collision and cask damage frequency. It was effective in assisting decision making processes to minimize risks in maritime spent nuclear fuel transportation. - Highlights: • Proposes a probabilistic framework on the safety of spent nuclear fuel transportation by sea. • Developed a marine traffic simulation model using Generalized Hough Transform (GHT) algorithm. • A transportation case study on South Korean waters is presented. • Single-vessel risk reduction method is outlined by optimizing transport parameters.

  10. US Nuclear Regulatory Commission Human Factors Program Plan. Revision 1

    International Nuclear Information System (INIS)

    1984-09-01

    The purpose of the NRC Human Factors Program Plan (NUREG-0985) is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This revised plan addresses nuclear power plants (NPPs) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, THE NRC Action Plan developed as a result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention; (3) conduct of developmental activities specified in NUREG-0985 during FY-83; and (4) the impact of Section 306 of the Nuclear Waste Policy Act of 1982, PL 97-425. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-84 through FY-86 time frame

  11. Quality management in the nuclear industry: the human factor

    International Nuclear Information System (INIS)

    1990-01-01

    In the nuclear industry it is vital to understand the 'human factor' with regard to plant performance and plant safety. A proper management system ensures that personnel perform their duties correctly. 'Quality Management in the Nuclear Industry: the Human Factor', was a conference organized by the Institution of Mechanical Engineers in October 1990. The conference covered a wide range of topics on an international level including: standards, licensing and regulatory procedures; selection assessment and training of personnel; feedback from experience of good practice and of deviations; management and support of personnel performance; modelling and evaluation of human factors. The papers presented at the conference are contained in this volume. All twenty papers are indexed separately. (author)

  12. Nuclear materials transport worldwide. Greenpeace report 2. Der weltweite Atomtransport. Greenpeace Report 2

    Energy Technology Data Exchange (ETDEWEB)

    Stellpflug, J.

    1987-01-01

    This Greenpeace report shows: nuclear materials transport is an extremely hazardous business. There is no safe protection against accidents, kidnapping, or sabotage. Any moment of a day, at any place, a nuclear transport accident may bring the world to disaster, releasing plutonium or radioactive fission products to the environment. Such an event is not less probable than the MCA at Chernobyl. The author of the book in hand follows the secret track of radioactive materials around the world, from uranium mines to the nuclear power plants, from reprocessing facilities to the waste repositories. He explores the routes of transport and the risks involved, he gives the names of transport firms and discloses incidents and carelessness, tells about damaged waste drums and plutonium that 'disappeared'. He also tells about worldwide, organised resistance to such nuclear transports, explaining the Greenpeace missions on the open sea, or the 'day X' operation at the Gorleben site, informing the reader about protests and actions for a world freed from the threat of nuclear energy.

  13. Notification determining technical details concerning measures for transportation of nuclear fuel materials

    International Nuclear Information System (INIS)

    1977-01-01

    These provisions are established on the basis of and to enforce ''The regulation for installation and operation of reactor'', ''The regulation concerning the fabricating business of nuclear fuel'' and ''The regulations concerning the reprocessing business of spent fuel''. The terms used hereinafter are according to those used in such regulations. The limit of radioactivity concentration of things contaminated by the nuclear fuel materials which are not required to be enclosed in vessels is defined in the lists attached. In the applications for the approval of the measures concerning the transport of things remarkably difficult to be enclosed in vessels, the name and the address of the applicant, the kind, quantity, form and constitution of the thing contaminated by the nuclear fuel materials to be transported, the date and route of the transport and the measures for the prevention of injuries during the transport must be written. The limit of quantity of nuclear fuel materials classifying the performance of vessels is defined respectively in the lists attached. The radiation dose rates provided for by the Director General of the Science and Technology Agency concerning transported things and transporting apparatuses are 200 millirem per hour on the surfaces of such things and containers. The nuclear fission materials specified, for which the measures for the prevention of criticality are especially required, include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, and the chemical compounds of such substances, and the nuclear fuel materials containing one or two and more of such substances, excluding the nuclear fuel materials with less than 15 grams of such uranium and plutonium. (Okada, K.)

  14. Regional, national and international security requirements for the transport of nuclear cargo by sea

    International Nuclear Information System (INIS)

    Booker, P.A.; Barnwell, I.

    2004-01-01

    Since the beginning of the nuclear age in the 1940's, the world has focused on the immense possibilities of nuclear power with both its destructive and productive capabilities. The civil nuclear industry in the UK, as in most nuclear weapons states, grew from the military facilities built in the post war years under the political climate of the Cold War. In the early years of the industry, civil and defence nuclear facilities were inextricably linked both in public perceptions and the regulatory infrastructure under which they operated. The nuclear arms race and the spread of communism overshadowed people's perceptions of there being two separate uses of nuclear material. This was a double edged sword which initially allowed the industry to develop largely unhindered by public concerns but latterly meant the industry could not break away from its roots and to many is still perceived as a dangerous and destructive force. Regulatory frameworks governing all aspects of the industry have developed both nationally and internationally driven by valid public concerns, political agendas and an international consensus that the unregulated use of nuclear material has catastrophic possibilities on an international scale. With the internationalisation of the civil nuclear industry and the costs associated with developing facilities to fully support each stage of the fuel cycle, from enrichment, fuel manufacturing, reprocessing and waste remediation, it became inevitable that a transport infrastructure would develop to make best use of the facilities. Regulations, both national and international are implicit in ensuring the security of nuclear material in transit. Due to the physical size of many of the irradiated fuel packages and implications of the changes to transport safety regulations, international transports of nuclear material, other than within mainland Europe, is predominantly carried out by sea

  15. Regional, national and international security requirements for the transport of nuclear cargo by sea

    Energy Technology Data Exchange (ETDEWEB)

    Booker, P.A.; Barnwell, I. [Marine Operations, BNFL International Transport and British Nuclear Group Security (United Kingdom)

    2004-07-01

    Since the beginning of the nuclear age in the 1940's, the world has focused on the immense possibilities of nuclear power with both its destructive and productive capabilities. The civil nuclear industry in the UK, as in most nuclear weapons states, grew from the military facilities built in the post war years under the political climate of the Cold War. In the early years of the industry, civil and defence nuclear facilities were inextricably linked both in public perceptions and the regulatory infrastructure under which they operated. The nuclear arms race and the spread of communism overshadowed people's perceptions of there being two separate uses of nuclear material. This was a double edged sword which initially allowed the industry to develop largely unhindered by public concerns but latterly meant the industry could not break away from its roots and to many is still perceived as a dangerous and destructive force. Regulatory frameworks governing all aspects of the industry have developed both nationally and internationally driven by valid public concerns, political agendas and an international consensus that the unregulated use of nuclear material has catastrophic possibilities on an international scale. With the internationalisation of the civil nuclear industry and the costs associated with developing facilities to fully support each stage of the fuel cycle, from enrichment, fuel manufacturing, reprocessing and waste remediation, it became inevitable that a transport infrastructure would develop to make best use of the facilities. Regulations, both national and international are implicit in ensuring the security of nuclear material in transit. Due to the physical size of many of the irradiated fuel packages and implications of the changes to transport safety regulations, international transports of nuclear material, other than within mainland Europe, is predominantly carried out by sea.

  16. Specific transport and storage solutions: Waste management facing current and future stakes of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Deniau, Helene; Gagner, Laurent; Gendreau, Francoise; Presta, Anne

    2006-01-01

    With major projects ongoing or being planned, and also with the daily management of radioactive waste from nuclear facilities, the role of transport and/or storage packaging has been often overlooked. Indeed, the packaging development process and transport solutions implemented are a key part of the waste management challenge: protection of people and environment. During over four decades, the AREVA Group has developed a complete and coherent system for the transport of waste produced by nuclear industries. The transport solutions integrate the factors to consider, as industrial transportation needs, various waste forms, associated hazards and current regulations. Thus, COGEMA LOGISTICS has designed, licensed and manufactured a large number of different transport, storage and dual purpose cask models for residues and all kinds of radioactive wastes. The present paper proposes to illustrate how a company acting both as a cask designer and a carrier is key to the waste management issue and how it can support the waste management policy of nuclear producers through their operational choices. We will focus on the COGEMA LOGISTICS technical solutions implemented to guarantee safe and secure transportation and storage solutions. We will describe different aspects of the cask design process, insisting on how it enables to fulfill both customer needs and regulation requirements. We will also mention the associated services developed by the AREVA Business Unit Logistics (COGEMA LOGISTICS, TRANSNUCLEAR, MAINCO, and LEMARECHAL CELESTIN) in order to manage transportation of liquid and solid waste towards interim or final storage sites. The paper has the following contents: About radioactive waste; - Radioactive waste classification; - High level activity waste and long-lived intermediate level waste; - Long-lived low level waste; - Short-lived low- and intermediate level waste; - Very low level waste; - The radioactive waste in nuclear fuel cycle; - Packaging design and

  17. Factors influencing the transport accessibility level - seniors point of view

    Energy Technology Data Exchange (ETDEWEB)

    Zakowska, L.; Pulawska-Obiedowska, S.

    2016-07-01

    The growing group of European older inhabitants, namely senior citizens (aged + 65) belong to the most vulnerable group to social exclusion. Transport accessibility is a concept, that can lead to enhancing life quality of seniors, which is shown based on the case study of Cracow, Poland as a European city. 100 seniors, that are living in different areas (urban, suburban), were asked for define different aspects that may influence their travel behaviour. Respondents were indicating their individual concerns connected with travelling, the existing barriers and expected solutions.The goal of the paper is to present the main outcomes of the conducted surveys, in order to present the concept of transport accessibility in the context of the most important factors influencing seniors life quality. The accessibility conditions and barriers, which can affect mobility possibilities and different activities of senior citizens in urban areas, are indicated in the paper. The identification of the crucial aspects of accessibility play an important role in development of sustainable transport system together with sustainable urban design, that will be friendly for all citizens in aging society. (Author)

  18. Heavy Quark and Quarkonium Transport in High Energy Nuclear Collisions

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, Kai [Physics Department, Tsinghua University and Collaborative Innovation Center of Quantum Matter, Beijing 100084 (China); Institute for Theoretical Physics, Johann Wolfgang Goethe-University, Max-von-Laue-Str. 1, D-60438 Frankfurt am Main (Germany); Frankfurt Institute for Advanced Studies, Ruth-Moufang-Str. 1, D-60438 Frankfurt am Main (Germany); Dai, Wei [Physics Department, Tsinghua University and Collaborative Innovation Center of Quantum Matter, Beijing 100084 (China); Xu, Nu [Nuclear Science Division, Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Key Laboratory of Quark and Lepton Physics (MOE) and Institute of Particle Physics, Central China Normal University, Wuhan 430079 (China); Zhuang, Pengfei [Physics Department, Tsinghua University and Collaborative Innovation Center of Quantum Matter, Beijing 100084 (China)

    2016-12-15

    The strong interaction between heavy quarks and the quark gluon plasma makes the open and hidden charm hadrons be sensitive probes of the deconfinement phase transition in high energy nuclear collisions. Both the cold and hot nuclear matter effects change with the colliding energy and significantly influence the heavy quark and charmonium yield and their transverse momentum distributions. The ratio of averaged quarkonium transverse momentum square and the elliptic flow reveal the nature of the QCD medium created in heavy ion collisions at SPS, RHIC and LHC energies.

  19. Heavy Quark and Quarkonium Transport in High Energy Nuclear Collisions

    International Nuclear Information System (INIS)

    Zhou, Kai; Dai, Wei; Xu, Nu; Zhuang, Pengfei

    2016-01-01

    The strong interaction between heavy quarks and the quark gluon plasma makes the open and hidden charm hadrons be sensitive probes of the deconfinement phase transition in high energy nuclear collisions. Both the cold and hot nuclear matter effects change with the colliding energy and significantly influence the heavy quark and charmonium yield and their transverse momentum distributions. The ratio of averaged quarkonium transverse momentum square and the elliptic flow reveal the nature of the QCD medium created in heavy ion collisions at SPS, RHIC and LHC energies.

  20. Transportation ALARA analysis for a nuclear waste management system

    International Nuclear Information System (INIS)

    McNair, G. W.; Schneider, K.; Smith, R.I.; Ross, W.; Faletti, D.

    1988-01-01

    In planning for implementation of a safe and cost-effective transportation system, the Department of Energy (DOE) commissioned the Pacific Northwest Laboratory (PNL) to develop estimates of the radiation doses, both public and occupational, that would result from operation of a system postulated using current designs and practices. From that evaluation, PNL identified activities/operations that result in relatively high doses, proposed conceptual alternatives that would effectively reduce such exposures, and evaluated the cost-effectiveness of such alternatives. This study contains an analysis of routine operations and estimates of the public and worker radiation doses that would occur in a postulated generic reference spent fuel transportation system using both truck and rail modes. Total risks are not estimated (i.e., consideration of nonradiological or accident risks that will be the subject of future studies in the transportation systems study plan 9TSSP) are not included). The system encompasses spent fuel loading at the reactor, transportation of the fuel to and from a receiving and handling facility and unloading of the fuel at a repository. The analysis provides cost/dose trade-offs of the postulated reference system as well as selected potential alternatives to the transportation system

  1. Nuclear Factor-kappaB in Autoimmunity: Man and Mouse.

    Science.gov (United States)

    Miraghazadeh, Bahar; Cook, Matthew C

    2018-01-01

    NF-κB (nuclear factor-kappa B) is a transcription complex crucial for host defense mediated by innate and adaptive immunity, where canonical NF-κB signaling, mediated by nuclear translocation of RelA, c-Rel, and p50, is important for immune cell activation, differentiation, and survival. Non-canonical signaling mediated by nuclear translocation of p52 and RelB contributes to lymphocyte maturation and survival and is also crucial for lymphoid organogenesis. We outline NF-κB signaling and regulation, then summarize important molecular contributions of NF-κB to mechanisms of self-tolerance. We relate these mechanisms to autoimmune phenotypes described in what is now a substantial catalog of immune defects conferred by mutations in NF-κB pathways in mouse models. Finally, we describe Mendelian autoimmune syndromes arising from human NF-κB mutations, and speculate on implications for understanding sporadic autoimmune disease.

  2. The transports of nuclear fuel cycle: An essential activity, safely managed

    International Nuclear Information System (INIS)

    Lenail, B.; Savornin, B.; Curtis, H.W.

    1989-01-01

    Transports associated with the nuclear fuel cycle normally use public means of transport by rail, road, sea and air and it might therefore be expected that they would be the Achilles heel of the cycle from a safety point of view. In fact, despite a few minor accidents, no radioactive releases resulting in a significant exposure of the public or the environment have occurred. On the other hand, during the last quarter, the news media have reported major spillages of crude oil and chemicals of high toxicity which have jeopardized the environment, the explosion of gas tankers with dozens of fatalities, and even the sinking of a nuclear submarine. All reports show that the radiation exposure to the public resulting from transports is negligible, i.e., far below 1% of that due to the whole nuclear industry. Similarly, the radiation exposure of transport workers has been lower than anticipated over several decades. The demonstrations and attacks by opponents of the nuclear industry against transports have been limited and have been used as an attempt to freeze the activity of different plants or disposal sites, and to focus public attention on the nuclear issue, rather than to question the fuel cycle transports themselves or the safety principles ruling them. When looking for explanations of such a favorable situation, which they should endeavour to perpetuate, without being surprised if any incident occurs, one finds two major reasons: First, the awareness by the fuel cycle operators, of the vital importance of a safe and reliable implementation of the necessary transports. Secondly, the results of assessments of safety conducted by international organizations and most countries, which have resulted in detailed international recommendations, as well as uniform national and modal regulations, thus establishing the necessary link between the basic rules for radioprotection and the needs of the Transport Industry

  3. Storage, transportation and disposal system for used nuclear fuel assemblies

    Science.gov (United States)

    Scaglione, John M.; Wagner, John C.

    2017-01-10

    An integrated storage, transportation and disposal system for used fuel assemblies is provided. The system includes a plurality of sealed canisters and a cask sized to receive the sealed canisters in side by side relationship. The plurality of sealed canisters include an internal basket structure to receive a plurality of used fuel assemblies. The internal basket structure includes a plurality of radiation-absorbing panels and a plurality of hemispherical ribs generally perpendicular to the canister sidewall. The sealed canisters are received within the cask for storage and transportation and are removed from the cask for disposal at a designated repository. The system of the present invention allows the handling of sealed canisters separately or collectively, while allowing storage and transportation of high burnup fuel and damaged fuel to the designated repository.

  4. Safety transport of radioactive waste in the nuclear power area

    Directory of Open Access Journals (Sweden)

    Tureková Ivana

    2017-01-01

    Full Text Available Radioactive wastes require strict rules for manipulation with them due to the hazards for the human health and environment, not excluding the hazards during their internal transport. The article deals with the transport of packing unit inside of the company and it proposes the possible alternatives so that meet the limit conditions and reduce the manipulation time with the radioactive material in the packing unit. The packing unite isolates fixated liquid waste from the environment while it also serves as protection. There are also important external radiation characteristics of package unit, which consist of measurable values of the scratch contamination surface and dose power on the surface of package unit. Thus, the paper is aimed to point out the necessity of the logistics during manipulation with the package unit in the process of internal transport so that the dose power of exposed employees would achieve the lowest possible level and meet the strict limits in a full extent.

  5. Colloid transport code-nuclear user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Jain, R. [New Mexico Univ., Albuquerque, NM (United States)

    1992-04-03

    This report describes the CTCN computer code, designed to solve the equations of transient colloidal transport of radionuclides in porous and fractured media. This Fortran 77 package solves systems of coupled nonlinear differential equations with a wide range of boundary conditions. The package uses the Method of Lines technique with a special section which forms finite-difference discretizations in up to four spatial dimensions to automatically convert the system into a set of ordinary differential equations. The CTCN code then solves these equations using a robust, efficient ODE solver. Thus CTCN can be used to solve population balance equations along with the usual transport equations to model colloid transport processes or as a general problem solver to treat up to four-dimensional differential systems.

  6. The Transportable Nuclear Plant for Multi Purpose Applications

    International Nuclear Information System (INIS)

    Pahladsingh, R.R.

    2002-01-01

    The DOE (Department of Energy - USA) has started the Generation IV initiative for the new generation of nuclear reactors that have to be much better developed for safety, economy and public acceptance. The SGR (Simplified Gas-cooled Reactor) is being proposed as a Generation IV modular nuclear reactor, using graphite pebbles as fuel, whereby an attempt has been made to meet all the DOE requirements [1,2] to be used for future nuclear reactors. Deregulation and liberalization are changing the global energy-markets. At the same time innovative technologies are introduced in the electricity industry; often as a requirement from the upcoming Digital Society. Energy solutions for the future are more seen as a mix of energy-sources for generation-, transmission- and distribution energy-services. The Internet Energy-web based 'Virtual' enterprises are coming up and will gradually change our society. The focus in this paper is on the changing and emerging global energy-markets and how the nuclear industry can anticipate in the coming Digital Society. (authors)

  7. 77 FR 34194 - Advance Notification to Native American Tribes of Transportation of Certain Types of Nuclear Waste

    Science.gov (United States)

    2012-06-11

    ... Notification to Native American Tribes of Transportation of Certain Types of Nuclear Waste AGENCY: Nuclear... fuel and certain nuclear wastes for any shipment that passes within or across their reservations. The... irradiated reactor fuel and certain nuclear waste passing through or across the boundary of their States...

  8. Human factors guidelines for nuclear power plant applications

    International Nuclear Information System (INIS)

    Ketchel, J.

    1993-01-01

    In 1989, Waters et al. reported to the Human Factors Society on developing human factors criteria for a new reactor plant. They correctly indicated that much of the guidance documentation in human factors engineering has derived from MIL-STD-1472 and its antecedents. Guidelines for human-computer interface have sprung primarily from the Smith and Mosier compendium and its source documents. NUREG-0700, which is currently being updated, was developed by the US Nuclear Regulatory Commission (NRC) as a general evaluation guide for inspecting control rooms. In addition, the Electric Power Research Institute, Institute of Nuclear Power Operations, US Department of Energy, the NRC, and others have published a number of specialized documents on a range of subjects. The number of guidelines and standards has grown in the past few years to an impressive number, including those published by international organizations and professional societies. This paper provides an update on current efforts to provide appropriate guidance for the power industry and, perhaps more importantly, offers a perspective on how users should think about using the available materials and what else is needed. The Electric Power Research Institute (EPRI) continues to be one of the principal participants in providing guidance to the utilities. Human factors guidelines is indeed a timely topic, currently of great interest to EPRI's constituents and to designers of new and upgraded nuclear power plants (NPMs) in the Advanced Light Water Reactor and the Instrumentation and Control Upgrade Initiative programs

  9. Selected risk factors of diabetes mellitus among road transport drivers.

    Science.gov (United States)

    Marcinkiewicz, Andrzej; Szosland, Dorota

    2010-01-01

    Road transport drivers are one of the professional groups whose activities have a strong impact on public safety. In view of the nature of their professional activity, the drivers are at a higher risk of obesity and hypertension, and thus, indirectly, of carbohydrate metabolism disorders such as diabetes mellitus. Medical documentation was a source of data for the reported study. It derived from medical examinations of truck and bus drivers applying for the new category II driving licence or for prolongation of the one they already had. Excessive body weight was recorded in 62.6% of the study population; 45.3% had overweight and 17.4% were diagnosed with obesity. Hypertension was noted in the medical records of 36.7% drivers. The prevalence of abnormal BP values was increasing with age. Overweight was found to be a risk factor for hypertension. Hyperglycaemia was found in 47.5% of the drivers and was also increasing with age. In road transport drivers, the high prevalence of excessive body weight and elevated arterial blood pressure as the risk factors for diabetes indicates a need to undertake multidimensional actions targeted on this particular profession and involving various health care sectors. Prophylactic and detailed pre-placement examinations should be considered, depending on the rate and intensity of the disorders diagnosed. This should be coupled with an introduction of primary and secondary prophylactic activities and monitoring of relevant treatment. A close collaboration with the patient's GP is necessary.

  10. Factors affecting the next generation of nuclear power

    International Nuclear Information System (INIS)

    Remick, F.J.

    1990-01-01

    For both financial, environmental and health reasons, and because of external and internal factors affecting this nation's energy supply, nuclear power will likely play a part in supplying this nation's energy in the coming decades. I believe this to be true for some other parts of the world as well. Even some severe critics of the nuclear power industry and the NRC might agree with me on this point. Increasing concern with the environmental consequences of the burning of fossil fuels has led some former opponents of the use of nuclear power to balance anew the risks and benefits of nuclear power and to modify to some degree their former opposition. A related concern with the adequacy of the energy supply is leading others to modify their positions. According to analyses done by the U.S. Department of Energy, after 1994 the United States will no longer be able to assure all its citizens a reliable supply of electricity. Already, many areas of the country are in need of additional electric capacity. In both Sweden and Switzerland, similar concerns have led to the adoption by many of more compromising positions. Some critics of nuclear power may in the end still reject it as an alternative, but, with the increased pressures on the environment and on our energy supply, nuclear power is an alternative which cannot be rejected without the most serious consideration. This should be, I believe, a point of consensus among us. In sum, there is a future for nuclear power in the sense that there is a use for it

  11. Factors affecting the next generation of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Remick, F J [Nuclear Regulatory Commission, Washington, DC (United States)

    1990-07-01

    For both financial, environmental and health reasons, and because of external and internal factors affecting this nation's energy supply, nuclear power will likely play a part in supplying this nation's energy in the coming decades. I believe this to be true for some other parts of the world as well. Even some severe critics of the nuclear power industry and the NRC might agree with me on this point. Increasing concern with the environmental consequences of the burning of fossil fuels has led some former opponents of the use of nuclear power to balance anew the risks and benefits of nuclear power and to modify to some degree their former opposition. A related concern with the adequacy of the energy supply is leading others to modify their positions. According to analyses done by the U.S. Department of Energy, after 1994 the United States will no longer be able to assure all its citizens a reliable supply of electricity. Already, many areas of the country are in need of additional electric capacity. In both Sweden and Switzerland, similar concerns have led to the adoption by many of more compromising positions. Some critics of nuclear power may in the end still reject it as an alternative, but, with the increased pressures on the environment and on our energy supply, nuclear power is an alternative which cannot be rejected without the most serious consideration. This should be, I believe, a point of consensus among us. In sum, there is a future for nuclear power in the sense that there is a use for it.

  12. Statistical factors affecting the success of nuclear operations

    International Nuclear Information System (INIS)

    Sunder, S.; Stephenson, J.R.; Hochman, D.

    1999-01-01

    In this article, the authors present a statistical analysis to determine the operational, financial, technical, and managerial factors that most significantly affect the success of nuclear operations. The study analyzes data for over 70 nuclear plants and 40 operating companies over a period of five years in order to draw conclusions that they hope will be of interest to utility companies and public utility commissions as they seek ways to improve rates of success in nuclear operations. Some of these conclusions will not be surprising--for example, that older plants have heavier maintenance requirements--but others are less intuitive. For instance, the observation that operators of fewer plants have lower costs suggests that any experience curve benefits associated with managing multiple nuclear facilities is overshadowed by the logistic problems of multiple facilities. After presenting a brief history of nuclear power in America, the authors outline the motivations of the study and the methodology of their analysis. They end the article with the results of the study and discuss some of the managerial implications of these findings

  13. Factors influencing the decommissioning of large-scale nuclear plants

    International Nuclear Information System (INIS)

    Large, J.H.

    1988-01-01

    The decision-making process involving the decommissioning of the UK graphite moderated, gas-cooled nuclear power stations is complex. There are timing, engineering, waste disposal, cost and lost generation capacity factors to consider and the overall decision of when and how to proceed with decommissioning may include political and public tolerance dimensions. For the final stage of decommissioning the nuclear industry could either completely dismantle the reactor island leaving a green-field site or, alternatively, the reactor island could be maintained indefinitely with additional super- and substructure containment. At this time the first of these options, or deferred decommissioning, prevails and with this the nuclear industry has expressed considerable confidence that the technology required will become available with passing time, that acceptable radioactive waste disposal methods and facilities will be available and that the eventual costs of decommissioning will not escalate without restraint. If the deferred decommissioning strategy is wrong and it is not possible to completely dismantle the reactor islands a century into the future, then it may be too late to effect sufficient longer term containment to maintain the reactor hulks in a reliable condition. With respect to the final decommissioning of large-scale nuclear plant, it is concluded that the nuclear industry does not know quite how to do it, when it will be attempted and when it will be completed, and they do not know how much it will eventually cost. (author)

  14. Status and future aspects of nuclear fuel cycle transports in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Blechschmidt, M.; Keese, H.

    1977-01-01

    The transport practices in the Federal Republic of Germany for materials of the nuclear fuel cycle are discussed. Particularly containers and modes of transport for UF 6 , fresh and spent fuel elements, plutonium and radwaste are described, with main emphasis on transport to reprocessing and waste storage facilities. In most cases nuclear materials have to be shipped across the borders because at present neither an enrichment nor an industrial reprocessing plant exists in the Federal Republic of Germany. Transports are therefore carried out according to international standards, such as the IAEA recommendations laid down in legal traffic regulations. Control and physical protection are being exercised on the basis of national regulations. The paper summarizes the experience gained in performing quite a number of various shipments and deals with the application of the relevant transport regulations. It also gives a brief outlook on future aspects, such as the increasing transport volume, and transport problems related to decommissioning and the operation of a nuclear fuel cycle center

  15. Nuclear transport factor directs localization of protein synthesis during mitosis

    NARCIS (Netherlands)

    Bogaart, Geert van den; Meinema, Anne C.; Krasnikov, Viktor; Veenhoff, Liesbeth M.; Poolman, Bert

    Export of messenger RNA from the transcription site in the nucleus and mRNA targeting to the translation site in the cytoplasm are key regulatory processes in protein synthesis. In yeast, the mRNA-binding proteins Nab2p and Nab4p/Hrp1p accompany transcripts to their translation site, where the

  16. Human factor engineering applied to nuclear power plant design

    International Nuclear Information System (INIS)

    Manrique, A.; Valdivia, J.C.

    2007-01-01

    Advantages of implementing adequate Human Factor Engineering techniques in the design of nuclear reactors have become not only a fact recognized by the majority of engineers and operators but also an explicit requirement regulated and mandatory for the new designs of the so called advanced reactors. The first step for this is preparing a plan to incorporate all the Human Factor Engineering principles and developing an integral design of the Instrumentation and Control and Man-machine interface systems. Such a plan should state: -) Activities to be performed, and -) Creation of a Human Factor Engineering team adequately qualified. The Human Factor Engineering team is an integral part of the design team and is strongly linked to the engineering organizations but simultaneously has independence to act and is free to evaluate designs and propose changes in order to enhance human behavior. TECNATOM S.A. (a Spanish company) has been a part of the Design and Human Factor Engineering Team and has collaborated in the design of an advanced Nuclear Power Plant, developing methodologies and further implementing those methodologies in the design of the plant systems through the development of the plant systems operational analysis and of the man-machine interface design. The methodologies developed are made up of the following plans: -) Human Factor Engineering implementation in the Man-Machine Interface design; -) Plant System Functional Requirement Analysis; -) Allocation of Functions to man/machine; -) Task Analysis; -) Human-System Interface design; -) Control Room Verification and -) Validation

  17. Nuclear Regulatory Commission Human Factors Program Plan. Revision 2

    International Nuclear Information System (INIS)

    1986-04-01

    This document is the Second Annual Revision to the NRC Human Factors Program Plan. The first edition was published in August 1983. Revision 1 was published in July of 1984. Purpose of the NRC Human Factors Program is to ensure that proper consideration is given to human factors in the design and operation of nuclear power plants. This document describes the plans of the Office of Nuclear Reactor Regulation to address high priority human factors concerns of importance to reactor safety in FY 1986 and FY 1987. Revision 2 of the plan incorporates recent Commission decisions and policies bearing on the human factors aspects of reactor safety regulation. With a few exceptions, the principal changes from prior editions reflect a shift from developing new requirements to staff evaluation of industry progress in resolving human factors issues. The plan addresses seven major program elements: (1) Training, (2) Licensing Examinations, (3) Procedures, (4) Man-Machine Interface, (5) Staffing and Qualifications, (6) Management and Organization, and (7) Human Performance

  18. Major factors influencing craft productivity in nuclear power plant construction

    International Nuclear Information System (INIS)

    Borcherding, J.D.; Sebastian, S.J.

    1980-01-01

    This paper reports on a research study whose objective was to determine the most influential factors adversely affecting craft productivity in nuclear power plant construction from the perspective of the tradesmen employed at the sites. Data were collected through the use of a questionnaire survey and group interview sessions, predominantly with workmen, at six nuclear power plant construction projects. Craftsmen were chosen as the major data base because of their awareness of how their time would actually be spent on the project. Topics considered include the factors influencing craft productivity, material availability, redoing work, crew interfacing, overcrowded work areas, instruction time, inspection delays, craft turnover, craft absenteeism, foreman changes, foreman incompetence, engineering design lead time, comprehensive scheduling of the design function, the responsibility of the utility, value engineering, plant standardization, the effective utilization of the planning and scheduling system, and the labor-management committee

  19. Neutron transport. Physics and calculation of nuclear reactors with applications to pressurized water reactors and fast neutron reactors. 2 ed.

    International Nuclear Information System (INIS)

    Bussac, J.; Reuss, P.

    1985-01-01

    This book presents the main physical bases of neutron theory and nuclear reactor calculation. 1) Interactions of neutrons with matter and basic principles of neutron transport; 2) Neutron transport in homogeneous medium and the neutron field: kinetic behaviour, slowing-down, resonance absorption, diffusion equation, processing methods; 3) Theory of a reactor constituted with homogeneous zones: critical condition, kinetics, separation of variables, calculation and neutron balance of the fundamental mode, one-group and multigroup theories; 4) Study of heterogeneous cell lattices: fast fission factor, resonance absorption, thermal output factor, diffusion coefficient, computer codes; 5) Operation and control of reactors: perturbation theory, reactivity, fuel properties evolution, poisoning by fission products, calculation of a reactor and fuel management; 6) Study of some types of reactors: PWR and fast breeder reactors, the main reactor types of the present French program [fr

  20. C-14 release and transport from a nuclear waste repository in an unsaturated medium

    International Nuclear Information System (INIS)

    Light, W.B.; Zwahlen, E.D.; Pigford, T.H.; Chambre, P.L.; Lee, W.W.L.

    1990-06-01

    The release of 14 C as 14 CO 2 from partly failed spent fuel containers has been analyzed by the flow of gases into and out of the containers. This flow of gases is driven by pressure differences, which are in turn caused by heating by the spent fuel. In this analysis, the timing and size of holes in the containers are assumed to be given. A better means of predicting the time distribution and sizes of penetrations in nuclear waste containers is needed. For the purposes of far-field transport calculations, we have adopted release rates that are shown to be bonding for the large range of hole sizes studied. The transport of released 14 CO 2 has been analyzed by transport in equivalent porous medium. The peak 14 CO 2 concentration in pore gas at 350 m above the repository does not depend on the time of hole occurrence, although the time of penetration obviously affects the arrival and duration of exposure to 14 C. Nor does water saturation have much effect on peak concentration. In this analysis we have used a constant gas Darcy velocity. We performed limited sensitivity analysis on gas Darcy velocity by using values one order of magnitude above and below the published value. This probably gives us bounds on the likely gas Darcy velocity. Our calculations show that essentially all the released 14 C will reach the ground surface in less than one half-life of 14 C. However, the quantities of 14 C reaching the ground surface are so small that even if all containers fail at emplacement and conservative dose factors are used, the resultant inhalation dose to the maximally exposed individual is about 0.1% of natural background radiation. 14 refs., 18 figs., 3 tabs

  1. Insurance of liability for the transport of nuclear materials

    International Nuclear Information System (INIS)

    Deprimoz, J.

    1975-01-01

    The legal principle governing civil liability for damage involving nuclear substances in course of carriage are summarized, and the main aspects of the French nuclear insurance market are analysed. The financial capacity of insurance and the role of the Atomic Pool as an aid in this respect as well as its use as a mechanism for reinsurance are also discussed. As regards the insured party, cases are reviewed where the principle of the sole liability of the operator is inapplicable. Arguments are put forward demonstrating that acknowledgement of a plurality of insured persons would not necessarily lead to an increase of insurance costs. Finally, a review is made of the nature and extent of the damage covered according to whether such damage is caused to persons or property [fr

  2. Intermediate range atmospheric transport and technology assessments: nuclear pollutants

    International Nuclear Information System (INIS)

    Rohwer, P.S.; Hoffman, F.O.; Miller, C.W.

    1981-01-01

    Mathematical models have been used to assess potential impacts of radioactivity releases during all phases of our country's development of nuclear power. Experience to date has shown that in terms of potential dose to man, the most significant releases of radioactivity from nuclear fuel cycle facilities are those to the atmosphere. Our ability to predict atmospheric dispersion will, therefore, ultimately affect our capability to understand and assess the significance of both routine and accidental discharges of radionuclides. Assessment of potential radiological exposures from postulated routine and accidental releases of radionuclides from the fast-breeder reactor will require the use of atmospheric dispersion models, and the design, siting, and licensing of breeder reactor fuel cycle facilities will be influenced by the predictions made by these models

  3. Postulated accident scenarios for the on-site transport of spent nuclear fuel

    International Nuclear Information System (INIS)

    Morandin, G.; Sauve, R.

    2004-01-01

    Once a spent fuel container is loaded with spent fuel it typically travels on-site to a processing building for permanent lid attachment. During on-site transport a lid clamp is utilized to ensure the container lid remains in place. The safe on-site transport of spent nuclear fuel must rely on the structural integrity of the transport container and system of transport. Regard for on-site traffic and safe, efficient travel routes are important and manageable with well thought-out planning. Non-manageable incidences, such as flying debris from tornado force winds or postulated blasts in proximity to the transport container, that may result in high velocity impact and shock loading on the transport system must be considered. This paper consists of simulations that consider these types of postulated accident scenarios using detailed nonlinear finite element techniques

  4. Electrodriven selective transport of Cs+ using chlorinated cobalt dicarbollide in polymer inclusion membrane: a novel approach for cesium removal from simulated nuclear waste solution.

    Science.gov (United States)

    Chaudhury, Sanhita; Bhattacharyya, Arunasis; Goswami, Asok

    2014-11-04

    The work describes a novel and cleaner approach of electrodriven selective transport of Cs from simulated nuclear waste solutions through cellulose tri acetate (CTA)/poly vinyl chloride (PVC) based polymer inclusion membrane. The electrodriven cation transport together with the use of highly Cs+ selective hexachlorinated derivative of cobalt bis dicarbollide, allows to achieve selective separation of Cs+ from high concentration of Na+ and other fission products in nuclear waste solutions. The transport selectivity has been studied using radiotracer technique as well as atomic emission spectroscopic technique. Transport studies using CTA based membrane have been carried out from neutral solution as well as 0.4 M HNO3, while that with PVC based membrane has been carried out from 3 M HNO3. High decontamination factor for Cs+ over Na+ has been obtained in all the cases. Experiment with simulated high level waste solution shows selective transport of Cs+ from most of other fission products also. Significantly fast Cs+ transport rate along with high selectivity is an interesting feature observed in this membrane. The current efficiency for Cs+ transport has been found to be ∼100%. The promising results show the possibility of using this kind of electrodriven membrane transport methods for nuclear waste treatment.

  5. Plasma wake and nuclear forces on fragmented H+ transport

    International Nuclear Information System (INIS)

    Barriga-Carrasco, Manuel D; Deutsch, Claude

    2006-01-01

    The objective of the present work is to study the target electronic and nuclear interactions produced when a H + ion traverses classical plasma matter. Electronic interactions are treated by means of the dielectric formalism while nuclear interactions are dealt within the classical dispersion theory through a Monte Carlo computer code. The interactions through plasma electronic medium among close ions are called wake forces. We checked that these forces screen the Coulomb explosions of the two fragmented protons from the same H + ion decreasing their relative distance in the analysed cases. These forces align the interproton vector along the motion direction. They also tend the two-proton energy loss to the value of two isolated protons when at early times it is rather larger. Nevertheless most parts of these wake effects cannot be corroborated experimentally as they are masked by the projectile collisions with target nuclei in our numerical experiment. These collisions cancel the screening produced by the wake forces, increasing the interproton distance even faster than for bare Coulomb explosion. Also they misalign the interproton vector along the motion direction and contribute moderately to increase the energy loss of the fragmented H + ion. These nuclear collisions effects are more significant in reducing projectile velocity

  6. Transport, acceptance, storage and handling of the itens of nuclear power plants

    International Nuclear Information System (INIS)

    1989-01-01

    The norm aiming to establish the requirements applied to workers or organizations which participate of the activities of transport, acceptance, storage and handling of important itens for safety of nuclear power plants, is presented. The established requirements treat of protection and control necessary to assure that the quality of important itens for safety be it preserved from the end of fabrication until their incorporation to nuclear power plant. (M.C.K.) [pt

  7. A Historical Review of the Safe Transport of Spent Nuclear Fuel, Rev. 1

    Energy Technology Data Exchange (ETDEWEB)

    Connolly, Kevin J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pope, Ronald [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-09-01

    This report is a revision to M3 milestone M3FT-16OR090402028 for the former Nuclear Fuels Storage and Transportation Planning Project (NFST), “Safety Record of SNF Shipments.” The US Department of Energy (DOE) has since established the Office of Integrated Waste Management (IWM), which builds on the work begun by NFST, to develop an integrated waste management system for spent nuclear fuel (SNF), including the developm

  8. Preliminary Report: Bases for Containment Analysis for Transportation of Aluminum-Based Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Vinson, D.W.

    1998-01-01

    Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to SRS under the site FRR/DRR Receipts Program. Shipment of the FRR/DRR assemblies required that the cask with loaded fuel be certified by the US Nuclear Regulatory Commission (for US-owned casks) or the US Department of Transportation (for foreign-owned casks) to comply with the requirements in 10CFR71

  9. Leak-Path Factor Analysis for the Nuclear Materials Storage Facility

    International Nuclear Information System (INIS)

    Shaffer, C.; Leonard, M.

    1999-01-01

    Leak-path factors (LPFs) were calculated for the Nuclear Materials Storage Facility (NMSF) located in the Plutonium Facility, Building 41 at the Los Alamos National Laboratory Technical Area 55. In the unlikely event of an accidental fire powerful enough to fail a container holding actinides, the subsequent release of oxides, modeled as PuO 2 aerosols, from the facility and into the surrounding environment was predicted. A 1-h nondestructive assay (NDA) laboratory fire accident was simulated with the MELCOR severe accident analysis code. Fire-driven air movement along with wind-driven air infiltration transported a portion of these actinides from the building. This fraction is referred to as the leak-path factor. The potential effect of smoke aerosol on the transport of the actinides was investigated to verify the validity of neglecting the smoke as conservative. The input model for the NMSF consisted of a system of control volumes, flow pathways, and surfaces sufficient to model the thermal-hydraulic conditions within the facility and the aerosol transport data necessary to simulate the transport of PuO 2 particles. The thermal-hydraulic, heat-transfer, and aerosol-transport models are solved simultaneously with data being exchanged between models. A MELCOR input model was designed such that it would reproduce the salient features of the fire per the corresponding CFAST calculation. Air infiltration into and out of the facility would be affected strongly by wind-driven differential pressures across the building. Therefore, differential pressures were applied to each side of the building according to guidance found in the ASHRAE handbook using a standard-velocity head equation with a leading multiplier to account for the orientation of the wind with the building. The model for the transport of aerosols considered all applicable transport processes, but the deposition within the building clearly was dominated by gravitational settling

  10. Forecasting of the radioactive material transport demand for the Brazilian Nuclear Program and the security aspects

    International Nuclear Information System (INIS)

    Meldonian, Nelson Leon

    1979-01-01

    In the nuclear fuel cycle, a lot of radioactive materials are produced. These radioactive materials must be transported in order to promote the integration of the fuel cycle units. Considerations about the transport characteristics of radioactive material were made for each section of the fuel cycle. These considerations were based on the experience of several countries and in accordance with the International Atomic Energy Agency regulations. A prediction of transport demands for the Brazilian Nuclear Program until year 2.010 was made. The prediction refers mainly to the quantity of radioactive material produced in each section of the cycle the quantity of vehicles needed for the transport of these materials. Several safety aspects were considered specially, the accidents predictions for years 2.000 and 2.010. The accident probability in Brazilian railroads and highways was compared with that of the USA. (author)

  11. Application of the nuclear gages in dynamic sedimentology for the solid transport study

    International Nuclear Information System (INIS)

    Lamdasni, Y.

    1994-02-01

    The problems caused by the solid particle transport in rivers, dams, harbors, estuaries and in navigation channels have considerable economical consequences. The technical difficulties met when trying to limit or manage these problems are very important because of lack of knowledge. The nuclear gages and the radioactive tracers can be the measurement and monitoring means which, associated to the conventional techniques, permit to develop strongly the knowledge in the solid transport field. This report gives the modes of solid transport and the problems caused by these transports and exposes the physical properties of the fine sediments and their behavior under the hydrodynamic effects. In the same way, it deals with the theory of the nuclear gages, often applied in dynamic sedimentology and gives some examples of their applications. 29 refs., 35 figs., 5 tabs. (F.M.)

  12. Transportation systems to support the Nuclear Waste Policy Act of 1982

    International Nuclear Information System (INIS)

    Wilmot, E.L.; Philpott, R.E.

    1985-01-01

    Late in 1982, the United States Congress enacted legislation for the disposal of spent nuclear fuel and high-level waste. The policy, embodied in Public Law 97-425 and referred to as the Nuclear Waste Policy Act of 1982 (NWPA), mandates that the Department of Energy (DOE) be responsible for the transport of commercial spent fuel and defense high-level waste from their points of origin to facilities constructed under provisions of the NWPA. It is the purpose of this paper to describe the preliminary transportation policies and plans developed by the Office of Civilian Radioactive Waste Management (OCRWM), within the DOE, to respond to the NWPA mandate

  13. Sampling and transport of paraffin waste form from CWDS of nuclear power plant

    International Nuclear Information System (INIS)

    Lee, J. M.; Hwang, J. H.; Kim, C. R.; Park, J. W.

    2000-01-01

    Sampling and transport of paraffin waste form from concentrated waste drying system (CWDS) of domestic nuclear power plant were performed to collect the leaching characteristic data for the disposal of radioactive waste. Transport was performed according to the national regulations and the internal rules of the nuclear power plant. The sample of paraffin waste form was classified as L type package according to the regulation and radiation exposure of operator was measured in the range of 6 to 12 mrem that was less than the estimated amount

  14. Nuclear recycle: One of the key factors ensuring the sustainable development of China's nuclear power

    International Nuclear Information System (INIS)

    Jiang Yunqing

    2002-01-01

    Since early 1970's China has established a complete nuclear fuel cycle system for defense purpose. CNNC and its formers deal mainly with business in nuclear power and nuclear fuel cycle fields. Now COSTIND (CAEA) implements the governmental functions. Based on the features of energy sources, China is steady developing nuclear power as the appropriate supplement to meet demand of electricity in the southeast coastal regions. In the middle of 1980's, considering a number of elements, covering spent fuel arising from PWR dominantly, uranium source availability, development of FBR, radioactive waste management safely and existing good nuclear industry foundation etc., the closed fuel cycle strategy was formulated and announced internationally. In view of complexity of reprocessing technology and the limited spent fuel arising in the early period of nuclear power growing up, a multi-purpose pilot plant will be first set up. The plant involved in spent fuel AFR storage, and HEU/LEU fuel reprocessing separately has been constructed since 1991. At present more than a half of the project job has been completed while the preparation for long-distance transport of spent fuel is actively pushed on. It is expected that a centralized wet storage facility will be finished at the end of next year but the whole plant will be put into active commissioning in 2003. With the extension of the cumulative arising of spent fuel, a large scale reprocessing plant would be established around 2020. Reprocessed uranium will be surely re-enriched in the past manner while reactor-grade plutonium would be fabricated into MOX fuel to supply to FBR program. (author)

  15. Progress in nuclear well logging modeling using deterministic transport codes

    International Nuclear Information System (INIS)

    Kodeli, I.; Aldama, D.L.; Maucec, M.; Trkov, A.

    2002-01-01

    Further studies in continuation of the work presented in 2001 in Portoroz were performed in order to study and improve the performances, precission and domain of application of the deterministic transport codes with respect to the oil well logging analysis. These codes are in particular expected to complement the Monte Carlo solutions, since they can provide a detailed particle flux distribution in the whole geometry in a very reasonable CPU time. Real-time calculation can be envisaged. The performances of deterministic transport methods were compared to those of the Monte Carlo method. IRTMBA generic benchmark was analysed using the codes MCNP-4C and DORT/TORT. Centric as well as excentric casings were considered using 14 MeV point neutron source and NaI scintillation detectors. Neutron and gamma spectra were compared at two detector positions.(author)

  16. Human-factor operating concept for Borssele Nuclear Power Station

    International Nuclear Information System (INIS)

    Wieman, J.L.

    1995-01-01

    The safety level in the operation of a reactor is determined basically by human beings. The Borssele Nuclear Power Station has carried out measures for improving the man-machine interface through training and operating instructions for the shift personnel. The retrofitting of control technology relevant to safety engineering should avoid operating instructions which can cause potential failures. A safety study has shown that the remaining risk following all retrofitting measures remains dependent to the extent of 80% on human factors and that human factors as a whole have a positive effect on reactor safety. (orig.) [de

  17. A human factors data bank for French nuclear power plants

    International Nuclear Information System (INIS)

    Villemeur, A.; Mosneron-Dupin, F.; Bouissou, M.; Meslin, T.

    1986-01-01

    CONFUCIUS is a computerized data bank developed by Electricite de France to study human factors in nuclear power plants. A detailed and homogeneous grouping of described operation and maintenance errors as well as of performance times is possible with CONFUCIUS. It also incorporates a selection of statistical treatment softwares. Readily usable and modifiable, the system can easily evolve. It allows a wide range of applications (safety analysis, event analysis, training, human factors engineering, probabilistic analysis). Data derived from the analysis of significant events reported in power plants and from the analysis of simulator tests are used as inputs into this data bank

  18. Battelle's human factors program for the US Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Shikiar, R.

    1983-10-01

    Battelle has been involved in a programmatic effort of technical assistance to the Division of Human Factors Safety of the NRC. This program involves the efforts of over 75 professionals engaged in over 20 projects. These projects span the areas of human factors engineering, procedures, examinations, training, staffing and qualifications, and utility management and organization. All of these bear, one way or another, on the role of operators in nuclear power plants. This programmatic effort can be viewed as part of an integrative approach to system safety

  19. Nuclear terrorism risk analysis using game theory. Case study of sea transportation of MOX fuel

    International Nuclear Information System (INIS)

    Nakatani, Eri; Tanaka, Satoru; Choi, Jor-Shan

    2010-01-01

    While considerable attention and resources have been directed towards improving nuclear security in Japan in response to the threat of nuclear terrorism, the transport of nuclear material raises concern by the public as indicated in the recent return of MOX fuel from Europe. This concern cannot be adequately addressed by the government through communications with the public because of the confidential nature of such transport. Also, it remains a challenge for adequately assessing the nuclear terrorism risk because many key parameters associated with such assessment cannot be derived from statistical data and reflect actors' intentions unlike assessment on natural disasters. This study proposes an assessment methodology which introduces game theory to deduce the correlations between those key parameters and can be used to analyze the nuclear terrorism risk, both quantitatively and qualitatively for the civilian use of nuclear power. Risk will be calculated by Monte Carlo methods based on probability distributions set for actors' utilities. A case-study of transporting the MOX fuel by sea is also included. (author)

  20. Nuclear elastic scattering effects on fusion product transport in compact tori

    International Nuclear Information System (INIS)

    DeVeaux, J.; Greenspan, E.; Miley, G.H.

    1980-01-01

    This paper seeks to advance previous work including the effects of nuclear elastic scattering (NES) on fusion-product transport. We have found that NES may dominate the slowing-down process for high-temperature, advance-fuel plasmas which burn Cat.D or D- 3 He. A modified version of the Monte Carlo fusion product transport code, MCFRM, was used to evaluate the effects of NES on discrete fusion-product orbits in the FRM

  1. Human factors methods for nuclear control room design. Volume I. Human factors enhancement of existing nuclear control rooms. Final report

    International Nuclear Information System (INIS)

    Seminara, J.L.; Seidenstein, S.; Eckert, S.K.; Smith, D.L.

    1979-11-01

    Human factors engineering is an interdisciplinary specialty concerned with influencing the design of equipment systems, facilities, and operational environments to promote safe, efficient, and reliable operator performance. Human factors approaches were applied in the design of representative nuclear power plant control panels. First, methods for upgrading existing operational control panels were examined. Then, based on detailed human factors analyses of operator information and control requirements, designs of reactor, feedwater, and turbine-generator control panels were developed to improve the operator-control board interface, thereby reducing the potential for operator errors. In addition to examining present-generation concepts, human factors aspects of advanced systems and of hybrid combinations of advanced and conventional designs were investigated. Special attention was given to warning system designs. Also, a survey was conducted among control board designers to (1) develop an overview of design practices in the industry, and (2) establish appropriate measures leading to a more systematic concern for human factors in control board design

  2. Effect of hemodialysis on factors influencing oxygen transport.

    Science.gov (United States)

    Hirszel, P; Maher, J F; Tempel, G E; Mengel, C E

    1975-06-01

    Ten patients underwent 4 study hemodialyses, one with standard dialysis conditions, one with an isophosphate dialysate, one with simultaneous ammonium chloride loading, and other, after pretreatment, with sodium bicarbonate. Measurement of hemoglobin oxygen affinity (P-50), erythrocyte 2,3-DPG, blood-gasses, and serum chemistries revealed biochemically effective hemodialyses and slight changes in oxygen transport parameters. The P-50 (in vivo) values decreased slightly but significantly (p greater than 0.05) with dialysis. When corrected to pH 7.4, eliminating the Bohr effect, P-50 increased (p greater than 0.05). With unmodified dialysis elevated values of 2,3-DPG (in comparison to normal) decreased, a change that did not correlate with delta-p-50, delta-serum phosphate, or delta-serum creatinine. With standard and isophosphate dialyses Po-2 decreased significantly. The decrease correlated with delta-hydrogen ion concentration and did not occur with dialyses designed to maintain pH constant. Thus, hemodialysis influences many factors that affect oxygen transport in different and counterbalancing directions. These changes are not totally explained by alterations in 2,3-DPG, pH or serum phosphate. Maintenance of acidosis or hyperphosphatemia during dialysis is not recommended.

  3. Pre-transport factors affecting the welfare of cattle during road transport for slaughter – a review

    Directory of Open Access Journals (Sweden)

    Veronika Šímová

    2016-01-01

    Full Text Available In terms of animal welfare, transport per se is very important in the course of the transportation process and transport duration is considered as one of the determining factors, however, the phase that precedes the actual transport is also of great importance (and often even more important as to stress induction. This pre-transport phase includes many aspects, such as on-farm handling, rearing conditions, assembly of animals, classifying, weighing, repenning in a new environment, re-grouping, mixing with unfamiliar animals, and handling at loading, which is regarded as the most significant factor affecting animal welfare. Therefore, the present work focuses on the factors that play a role during this phase. Those factors are naturally interconnected and their adverse consecutive effects on animal welfare can hardly be separated.

  4. Key Response Planning Factors for the Aftermath of Nuclear Terrorism

    Energy Technology Data Exchange (ETDEWEB)

    Buddemeier, B R; Dillon, M B

    2009-01-21

    Despite hundreds of above-ground nuclear tests and data gathered from Hiroshima and Nagasaki, the effects of a ground-level, low-yield nuclear detonation in a modern urban environment are still the subject of considerable scientific debate. Extensive review of nuclear weapon effects studies and discussions with nuclear weapon effects experts from various federal agencies, national laboratories, and technical organizations have identified key issues and bounded some of the unknowns required to support response planning for a low-yield, ground-level nuclear detonation in a modern U.S. city. This study, which is focused primarily upon the hazards posed by radioactive fallout, used detailed fallout predictions from the advanced suite of three-dimensional (3-D) meteorology and plume/fallout models developed at Lawrence Livermore National Laboratory (LLNL), including extensive global Key Response Planning Factors for the Aftermath of Nuclear Terrorism geographical and real-time meteorological databases to support model calculations. This 3-D modeling system provides detailed simulations that account for complex meteorology and terrain effects. The results of initial modeling and analysis were presented to federal, state, and local working groups to obtain critical, broad-based review and feedback on strategy and messaging. This effort involved a diverse set of communities, including New York City, National Capitol Regions, Charlotte, Houston, Portland, and Los Angeles. The largest potential for reducing casualties during the post-detonation response phase comes from reducing exposure to fallout radiation. This can be accomplished through early, adequate sheltering followed by informed, delayed evacuation.B The response challenges to a nuclear detonation must be solved through multiple approaches of public education, planning, and rapid response actions. Because the successful response will require extensive coordination of a large number of organizations, supplemented by

  5. Heat resistant materials and their feasibility issues for a space nuclear transportation system

    International Nuclear Information System (INIS)

    Olsen, C.S.

    1991-01-01

    A number of nuclear propulsion concepts based on solid-core nuclear propulsion are being evaluated for a nuclear propulsion transportation system to support the Space Exploration Initiative (SEI) involving the reestablishment of a manned lunar base and the subsequent exploration of Mars. These systems will require high-temperature materials to meet the operating conditions with appropriate reliability and safety built into these systems through the selection and testing of appropriate materials. The application of materials for nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems and the feasibility issues identified for their use will be discussed. Some mechanical property measurements have been obtained, and compatibility tests were conducted to help identify feasibility issues. 3 refs., 1 fig., 4 tabs

  6. Computer codes in nuclear safety, radiation transport and dosimetry

    International Nuclear Information System (INIS)

    Bordy, J.M.; Kodeli, I.; Menard, St.; Bouchet, J.L.; Renard, F.; Martin, E.; Blazy, L.; Voros, S.; Bochud, F.; Laedermann, J.P.; Beaugelin, K.; Makovicka, L.; Quiot, A.; Vermeersch, F.; Roche, H.; Perrin, M.C.; Laye, F.; Bardies, M.; Struelens, L.; Vanhavere, F.; Gschwind, R.; Fernandez, F.; Quesne, B.; Fritsch, P.; Lamart, St.; Crovisier, Ph.; Leservot, A.; Antoni, R.; Huet, Ch.; Thiam, Ch.; Donadille, L.; Monfort, M.; Diop, Ch.; Ricard, M.

    2006-01-01

    The purpose of this conference was to describe the present state of computer codes dedicated to radiation transport or radiation source assessment or dosimetry. The presentations have been parted into 2 sessions: 1) methodology and 2) uses in industrial or medical or research domains. It appears that 2 different calculation strategies are prevailing, both are based on preliminary Monte-Carlo calculations with data storage. First, quick simulations made from a database of particle histories built though a previous Monte-Carlo simulation and secondly, a neuronal approach involving a learning platform generated through a previous Monte-Carlo simulation. This document gathers the slides of the presentations

  7. Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations

    Energy Technology Data Exchange (ETDEWEB)

    Clarno, Kevin T [ORNL; Hamilton, Steven P [ORNL; Philip, Bobby [ORNL; Berrill, Mark A [ORNL; Sampath, Rahul S [ORNL; Allu, Srikanth [ORNL; Pugmire, Dave [ORNL; Dilts, Gary [Los Alamos National Laboratory (LANL); Banfield, James E [ORNL

    2012-02-01

    The Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) is focused on predicting the temperature and strain within a nuclear fuel assembly to evaluate the performance and safety of existing and advanced nuclear fuel bundles within existing and advanced nuclear reactors. AMPFuel was extended to include an integrated nuclear fuel assembly capability for (one-way) coupled radiation transport and nuclear fuel assembly thermo-mechanics. This capability is the initial step toward incorporating an improved predictive nuclear fuel assembly modeling capability to accurately account for source-terms and boundary conditions of traditional (single-pin) nuclear fuel performance simulation, such as the neutron flux distribution, coolant conditions, and assembly mechanical stresses. A novel scheme is introduced for transferring the power distribution from the Scale/Denovo (Denovo) radiation transport code (structured, Cartesian mesh with smeared materials within each cell) to AMPFuel (unstructured, hexagonal mesh with a single material within each cell), allowing the use of a relatively coarse spatial mesh (10 million elements) for the radiation transport and a fine spatial mesh (3.3 billion elements) for thermo-mechanics with very little loss of accuracy. In addition, a new nuclear fuel-specific preconditioner was developed to account for the high aspect ratio of each fuel pin (12 feet axially, but 1 4 inches in diameter) with many individual fuel regions (pellets). With this novel capability, AMPFuel was used to model an entire 17 17 pressurized water reactor fuel assembly with many of the features resolved in three dimensions (for thermo-mechanics and/or neutronics), including the fuel, gap, and cladding of each of the 264 fuel pins; the 25 guide tubes; the top and bottom structural regions; and the upper and lower (neutron) reflector regions. The final, full assembly calculation was executed on Jaguar using 40,000 cores in under 10 hours to model over 162

  8. Studies and research concerning BNFP. Nuclear transportation studies related to use of the Barnwell Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    Anderson, R.T.

    1981-11-01

    It will be necessary to transport radioactive material on a routine basis if the Barnwell Nuclear Fuel Plant (BNFP) is to be utilized. This report examines the current and projected status of transport of high-level nuclear material, with particular application directed toward the operation of the BNFP. The current domestic US status is one of comparative inactivity in the movement of utility spent fuel. Pending the successful disposition of fuel cycle options such as either Away-from-Reactor (AFR) storage or reprocessing, spent fuel transport to the BNFP will be dormant through the mid-1980's. If fuel movement is initiated, the primary areas of concern will be the maze of local, state, and federal regulations on routing, the availability of spent fuel casks, and the logistic concerns of fuel loading and unloading capability at the reactor and the BNFP. The report examines the application of overweight truck (OWT) shipments of spent fuel casks patterned on current European practice. Overweight shipments, whether by truck or intermodal movement (rail or barge combined with truck shipment), can have a significant impact on resolving logistics problems. It seems obvious from our studies that OWT casks will be utilized, along with legal weight truck and rail shipment. Water transport was also examined. It appears that this mode will only be used in the event that highway and rail problems are insuperable

  9. Transferring aviation human factors technology to the nuclear power industry

    International Nuclear Information System (INIS)

    Montemerlo, M.D.

    1981-01-01

    The purpose of this paper is to demonstrate the availability of aviation safety technology and research on problems which are sufficiently similar to those faced by the nuclear power industry that an agressive effort to adapt and transfer that technology and research is warranted. Because of time and space constraints, the scope of this paper is reduced from a discussion of all of aviation safety technology to the human factors of air carrier safety. This area was selected not only because of similarities in the human factors challenges shared by both industries (e.g. selection, training, evaluation, certification, etc.) but because experience in aviation has clearly demonstrated that human error contributes to a substantially greater proportion of accidents and incidents than does equipment failure. The Congress of the United States has placed a great deal of emphasis on investigating and solving human factors problems in aviation. A number of recent examples of this interest and of the resulting actions are described. The opinions of prominent aviation organizations as to the human factors problems most in need of research are presented, along with indications of where technology transfer to the nuclear power industry may be viable. The areas covered include: fatigue, crew size, information transfer, resource management, safety data-bases, the role of automation, voice and data recording systems, crew distractions, the management of safety regulatory agencies, equipment recertification, team training, crew work-load, behavioural factors, human factors of equipment design, medical problems, toxicological factors, the use of simulators for training and certification, determining the causes of human errors, the politics of systems improvement, and importance of both safety and public perception of safety if the industry is to be viable. (author)

  10. Tumour Necrosis Factor-alpha and Nuclear Factor-kappa B Gene Variants in Sepsis.

    Science.gov (United States)

    Acar, Leyla; Atalan, Nazan; Karagedik, E Hande; Ergen, Arzu

    2018-01-20

    The humoral system is activated and various cytokines are released due to infections in tissues and traumatic damage. Nuclear factor-kappa B dimers are encoded by nuclear factor-kappa B genes and regulate transcription of several crucial proteins of inflammation such as tumour necrosis factor-alpha. To investigate the possible effect of polymorphisms on tumour necrosis factor-alpha serum levels with clinical and prognostic parameters of sepsis by determining the nuclear factor-kappa B-1-94 ins/del ATTG and tumour necrosis factor-alpha (-308 G/A) gene polymorphisms and tumour necrosis factor-alpha serum levels. Case-control study. Seventy-two patients with sepsis and 104 healthy controls were included in the study. In order to determine the polymorphisms of nuclear factor-kappa B-1-94 ins/del ATTG and tumour necrosis factor-alpha (-308 G/A), polymerase chain reaction-restriction fragment length polymorphism analysis was performed and serum tumour necrosis factor-alpha levels were determined using an enzyme-linked immunosorbent assay. We observed no significant differences in tumour necrosis factor-alpha serum levels between the study groups. In the patient group, an increase in the tumour necrosis factor-alpha serum levels in patients carrying the tumour necrosis factor-alpha (-308 G/A) A allele compared to those without the A allele was found to be statistically significant. Additionally, an increase in the tumour necrosis factor-alpha serum levels in patients carrying tumour necrosis factor-alpha (-308 G/A) AA genotype compared with patients carrying the AG or GG genotypes was statistically significant. No significant differences were found in these 2 polymorphisms between the patient and control groups (p>0.05). Our results showed the AA genotype and the A allele of the tumour necrosis factor-alpha (-308 G/A) polymorphism may be used as a predictor of elevated tumour necrosis factor-alpha levels in patients with sepsis.

  11. Criticality Calculations of Fresh LEU and MOX Assemblies for Transport and Storage at the Balakovo Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Goluoglu, S.

    2001-01-11

    Transportation of low-enriched uranium (LEU) and mixed-oxide (MOX) assemblies to and within the VVER-1000-type Balakovo Nuclear Power Plant is investigated. Effective multiplication factors for fresh fuel assemblies on the railroad platform, fresh fuel assemblies in the fuel transportation vehicle, and fresh fuel assemblies in the spent fuel storage pool are calculated. If there is no absorber between the units, the configurations with all MOX assemblies result in higher effective multiplication factors than the configurations with all LEU assemblies when the system is dry. When the system is flooded, the configurations with all LEU assemblies result in higher effective multiplication factors. For normal operating conditions, effective multiplication factors for all configurations are below the presumed upper subcritical limit of 0.95. For an accident condition of a fully loaded fuel transportation vehicle that is flooded with low-density water (possibly from a fire suppression system), the presumed upper subcritical limit is exceeded by configurations containing LEU assemblies.

  12. Human Factors Engineering Review Model for advanced nuclear power reactors

    International Nuclear Information System (INIS)

    O'Hara, J.; Higgins, J.; Goodman, C.; Galletti, G.: Eckenrode, R.

    1993-01-01

    One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model's rationale, scope, objectives, development, general characteristics. and application

  13. Human factors considerations for expert systems in the nuclear industry

    International Nuclear Information System (INIS)

    Nelson, W.R.

    1988-01-01

    This paper discusses the general human factors issues relative to the development and implementation of expert systems for the nuclear industry. It summarizes the relevant research that addresses these issues, and identifies those areas that need the most effort for success. Since much of the prominent work for the application of expert systems has focused on computerized aids for decision making in emergencies, this paper draws from this area for its examples. This area tends to highlight the issues because of the safety-critical nature of the application. The same issues, however, are relevant to other applications of expert systems in the nuclear industry as well, even though the consequences of failure may not be as dramatic

  14. Railroad infrastructure adequacy for safe transportation of spent nuclear fuel

    International Nuclear Information System (INIS)

    Fisher, A.C.; Furber, C.P.

    1992-01-01

    The purpose of this paper is to discuss the railroad industry's concerns on the movement of spent nuclear fuel including the magnitude of thermal and mechanical forces in train accidents, emergency response capability, railroad's liability for non-breach-of-cask accidents, and the importance of using dedicated trains to improve public perception of these movements; summarize the current status of the condition of the American railroads' equipment, facilities, track structure, and right-of-way; outline the continuing efforts of the railroad industry to improve customer service and profitability through downsizing and shifting of branch lines to more customer-oriented and efficient short-line carriers; and discuss potential problems of government subsidization of private railroads to enable upgrading of tracks and structures to handle rights-of-way in the future

  15. Process for the transport of heat energy released by a nuclear reactor

    International Nuclear Information System (INIS)

    Nuernberg, H.W.; Wolff, G.

    1978-01-01

    The heat produced in a nuclear reactor is converted into latent chemical binding energy. The heat can be released again below 400 0 C by recombination after transport by decomposition of ethane or propane into ethylene or propylene and hydrogen. (TK) [de

  16. Nuclear elastic scattering effects on fusion product transport in the FRM

    International Nuclear Information System (INIS)

    DeVeaux, J.C.; Greenspan, E.; Miley, G.H.

    1981-01-01

    Large energy transfer (LET) events such as nuclear elastic scatterng (NES) are shown to have significant effects on fusion product transport in the field-reversed mirror. The method used and preliminary results obtained from the study on NES effects on f/sub p/ orbits are described

  17. Dual Liability for Nuclear Damage in Conventions and Finnish Legislation in the Field of Transport

    International Nuclear Information System (INIS)

    Manninen, J.

    1986-01-01

    The exception made in the 1960 Paris Convention on Third Party Liability in the Field of Nuclear Energy to the otherwise absolute channelling of liability in order to avoid conflicts with the then existing international agreements in the field of transport is briefly described. The dual liability created by this provision is studied, as well as the question whether and when the victim might prefer to base his claim on a transport agreement instead of the Paris Convention. The so-called nuclear clauses in the new agreements in the transport field are analysed. The problems caused by the absence of a nuclear clause in the Guatemala City and Montreal Protocols, amending the Warsaw Convention relating to international air carriage are noted. Finally the relationship between nuclear liability legislation and transport legislation in Finland, as well as the cases where a dual liability existed at the time of the ratification of the Paris Convention and the changes which have taken place since then are described. (NEA) [fr

  18. Epidermal growth factor inhibits glycyl sarcosine transport and hPepT1 expression in a human intestinal cell line

    DEFF Research Database (Denmark)

    Nielsen, Carsten Uhd; Amstrup, Jan; Steffansen, Bente

    2001-01-01

    Intestinal oligopeptide transporter, growth factor, immunocytochemistry, laser scanning confocal microscopy......Intestinal oligopeptide transporter, growth factor, immunocytochemistry, laser scanning confocal microscopy...

  19. Decree no 2007-1557 from November 2, 2007, relative to basic nuclear facilities and to the nuclear safety control of nuclear materials transport

    International Nuclear Information System (INIS)

    2007-11-01

    This decree concerns the enforcement of articles 5, 17 and 36 of the law 2006-686 from June 13, 2006, relative to the transparency and safety in the nuclear domain. A consultative commission of basic nuclear facilities is established. The decree presents the general dispositions relative to basic nuclear facilities, the dispositions relative to their creation and operation, to their shutdown and dismantling. It precises the dispositions in the domain of public utility services, administrative procedures and sanctions. It stipulates also the particular dispositions relative to other facilities located in the vicinity of nuclear facilities, relative to the use of pressure systems, and relative to the transport of radioactive materials. (J.S.)

  20. Harmonisation of criticality assessments of packages for the transport of fissile nuclear fuel cycle materials

    International Nuclear Information System (INIS)

    Farrington, L.

    2004-01-01

    The transport of fissile nuclear fuel cycle materials is an international business, and for international shipments the regulations require a package to be certified by each country through or into which the consignment is to be transported. This raises a number of harmonisation issues, which have an important bearing on transport activities. National authorities carry out independent reviews of the criticality safety of packages containing fissile materials but the underlying assumptions used in the calculations can differ, and the outcome is that implementation of the regulations is not uniform. A single design may require multiple criticality analyses to obtain base approval and foreign validations. When several competent authorities are involved, the approval and validation process of package design can often become a time-consuming, expensive and unpredictably lengthy process that can have a significant detrimental effect upon the businesses involved. The characteristics of the fissile nuclear fuel cycle materials transported by the various countries have much in common and so have the designs of the packages to contain them. A greater degree of standardisation should allow criticality safety to be assessed consistently and efficiently with benefits for the nuclear transport industry and the regulatory bodies. (author)

  1. Harmonisation of criticality assessments of packages for the transport of fissile nuclear fuel cycle materials

    International Nuclear Information System (INIS)

    Farrington, L.

    2004-01-01

    The transport of fissile nuclear fuel cycle materials is an international business and for international shipments the regulations require a package to be certified by each country through or into which the consignment is to be transported. This raises a number of harmonisation issues, which have an important bearing on transport activities. National authorities carry out independent reviews of criticality safety of packages containing fissile materials but the underlying assumptions used in the calculations can differ, and the outcome is that implementation of the regulations is not uniform. A single design may require multiple criticality analyses to obtain base approval and foreign validations. When several Competent Authorities are involved, the approval and validation process of package design can often become time consuming, expensive and an unpredictably lengthy process that can have a significant detrimental effect upon the businesses involved. The characteristics of the fissile nuclear fuel cycle materials transported by the various countries have much in common and so have the designs of the packages to contain them. A greater degree of standardisation should allow criticality safety to be assessed consistently and efficiently with benefits for the nuclear transport industry and the regulatory bodies

  2. Transport of radioactive droplet moisture from a source in a nuclear power plant spray pond

    International Nuclear Information System (INIS)

    Elokhin, A.P.

    1995-01-01

    In addition to a change in the microclimate in the region surrounding a nuclear power plant resulting from the emission of vapor form a cooling tower, evaporation of water from the water surface of a cooling pond or a spray pond, in the latter case direct radioactive contamination of the underlying surface around the nuclear power plant can also occur due to discharge of process water (radioactive) into the pond and its transport in the air over a certain distance in the form of droplet moisture. A typical example may be the situation at the Zaporozhe nuclear power plant in 1986 when accidental discharge of process water into the cooling pond occurred. Below we present a solution for the problem of transport of droplet moisture taking into account its evaporation, which may be used to estimate the scale of radioactive contamination of the locality

  3. Order of 26 March 1982 on the protection and control of nuclear materials during transport

    International Nuclear Information System (INIS)

    1982-01-01

    This Order was made in implementation of Act No. 80-572 of 25th July 1980 on protection and control of nuclear materials and in particular, of Decree No. 81-512 of 12th May 1981, which was itself made in pursuance of the Act. In accordance with the Decree, this Order determines the rules applicable to the protection and control of nuclear materials in course of carriage, especially in connection with the supervision of the conditions in which such transport is carried out and the authorities warned in case of an incident, accident or any occurrence whatsoever which is likely to delay or jeopardize execution of the planned transport operation or protection of the nuclear material concerned. (NEA) [fr

  4. Institutional interactions in developing a transportation system under the Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    Denny, S.H.

    1986-01-01

    The Department of Energy (DOE) recognizes that the success of its efforts to develop and operate a system for transporting nuclear waste under the provisions of the Nuclear Waste Policy Act of 1982 (NWPA) depends in large measure on the effectiveness of Departmental interactions with the affected parties. To ensure the necessary network of communication, the DOE is establishing lines of contact with those who are potential participants in the task of developing the policies and procedures for the NWPA transportation system. In addition, a number of measures have been initiated to reinforce broad-based involvement in program development. The Transportation Institutional Plan provides a preliminary road map of DOE's projected interactions over the next decade and is discussed in this paper

  5. Third party liability insurance for international transport of nuclear substances in countries party to the Paris Convention

    International Nuclear Information System (INIS)

    Lacroix, F.

    1977-01-01

    The number of international transports of radioactive materials has been increasing at an accelerating rate for several years. These transports are subject to specific safety rules which must be complied with in order to obtain nuclear third party liability cover. In general nuclear transports are insured under a policy which differs from that for installations. Transport policy criteria have been harmonized to some extent, in particular, in the frame of the OECD Nuclear Energy Agency. Certificates established by the competent national authorities testifying to the existence of insurance must in principle be approved by the countries crossed which are parties to the Paris Convention. (NEA) [fr

  6. Two Differential Binding Mechanisms of FG-Nucleoporins and Nuclear Transport Receptors

    Directory of Open Access Journals (Sweden)

    Piau Siong Tan

    2018-03-01

    Full Text Available Summary: Phenylalanine-glycine-rich nucleoporins (FG-Nups are intrinsically disordered proteins, constituting the selective barrier of the nuclear pore complex (NPC. Previous studies showed that nuclear transport receptors (NTRs were found to interact with FG-Nups by forming an “archetypal-fuzzy” complex through the rapid formation and breakage of interactions with many individual FG motifs. Here, we use single-molecule studies combined with atomistic simulations to show that, in sharp contrast, FG-Nup214 undergoes a coupled reconfiguration-binding mechanism when interacting with the export receptor CRM1. Association and dissociation rate constants are more than an order of magnitude lower than in the archetypal-fuzzy complex between FG-Nup153 and NTRs. Unexpectedly, this behavior appears not to be encoded selectively into CRM1 but rather into the FG-Nup214 sequence. The same distinct binding mechanisms are unperturbed in O-linked β-N-acetylglucosamine-modified FG-Nups. Our results have implications for differential roles of distinctly spatially distributed FG-Nup⋅NTR interactions in the cell. : Archetypal-fuzzy complexes found in most FG-Nucleoporin⋅nuclear transport receptor complexes allow fast yet specific nuclear transport. Tan et al. show that FG-Nup214, located at the periphery of the nuclear pore complex, binds to CRM1⋅RanGTP via a coupled reconfiguration-binding mechanism, which can enable different functionalities e.g., cargo release. Keywords: intrinsically disordered protein, glycosylation, FG-Nup, nuclear transport receptors, binding mechanism, single-molecule FRET, molecular dynamics simulations

  7. For a few dollars more: Public trust and the case for transporting nuclear waste in dedicated trains

    International Nuclear Information System (INIS)

    Glickman, T.S.; Golding, D.

    1991-01-01

    The debate about the use of dedicated trains for shipping spent fuel and high-level nuclear waste has been going on for the past l5 years. The nuclear industry and its regulatory agencies would like to consider the case closed. The recent passage of the Hazardous Materials Transportation Uniform Act of 1990, however, opens the door once more, giving the railroads and other proponents of dedicated trains another chance to present their case. This paper argues that earlier conclusions favoring regular trains over dedicated trains were based on incomplete cost and risk information and neglected other factors which are not technical, but social and institutional in nature. The paper finds that the additional cost of a dedicated system is lower than previously thought and concludes that it is a small price to pay for reduced public opposition and increased levels of trust

  8. Proposal for guidelines for the physical protection of nuclear materials, plants and transports in Denmark

    International Nuclear Information System (INIS)

    1978-03-01

    The guidelines are based on recommendations in the IAEA's ''Physical Protection of Nuclear Material,'' INFCIRC/225/rev.1. In accordance with practice in other countries, the guidelines give more detailed requirements for the protection of reactor plants than those given in the IAEA's present recommendations, which put more emphasis on the protection of nuclear materials. The measures to be taken for nuclear plants, or nuclear transports, are proposed made to fit the potential risk that the more closely defined actions imply. It is suggested that the more detailed rules for the scope of the protection of plants or materials should be laid down by the National Agency on the basis of recommendations made by the Inspectorate of Nuclear Installations, which in turn are based on the safety documentation of the plant/material owners. It is further proposed that the National Agency, again on a recommendation from the Inspectorate, should lay down more detailed guidelines for the reporting of changes in stocks or transports of nuclear materials. (author)

  9. Radionuclide transport through perforations in nuclear waste containers

    International Nuclear Information System (INIS)

    Aidun, C.K.; Bloom, S.G.; Raines, G.E.

    1987-11-01

    Previous analytical models for the steady-state radionuclide release rate through perforations in nuclear waste containers into the surrounding medium are based on a zero wall thickness assumption. In this paper we investigate the effect of the wall thickness on the mass transfer rate through isolated cylindrical holes. We solve the steady-state diffusion equation for the concentration field and derive a model based on the analytical solution. By direct comparison, we show that the zero wall thickness model overpredicts the mass transfer rate by about 1300 percent for a circular hole with 1-cm radius and a wall thickness of 10 cm. As expected, the zero-thickness model becomes even less accurate as the hole radius decreases; it predicts a greater release rate from a large number of small holes than the mass transfer rate from an uncontained waste form cylinder. In contrast, the results predicted by our model remain bounded for isolated holes and never exceed the mass transfer from an uncontained waste form. 6 refs., 9 figs., 3 tabs

  10. Calmodulin-dependent nuclear import of HMG-box family nuclear factors: importance of the role of SRY in sex reversal.

    Science.gov (United States)

    Kaur, Gurpreet; Delluc-Clavieres, Aurelie; Poon, Ivan K H; Forwood, Jade K; Glover, Dominic J; Jans, David A

    2010-08-15

    The HMG (high-mobility group)-box-containing chromatin-remodelling factor SRY (sex-determining region on the Y chromosome) plays a key role in sex determination. Its role in the nucleus is critically dependent on two NLSs (nuclear localization signals) that flank its HMG domain: the C-terminally located 'beta-NLS' that mediates nuclear transport through Impbeta1 (importin beta1) and the N-terminally located 'CaM-NLS' which is known to recognize the calcium-binding protein CaM (calmodulin). In the present study, we examined a number of missense mutations in the SRY CaM-NLS from human XY sex-reversed females for the first time, showing that they result in significantly reduced nuclear localization of GFP (green fluorescent protein)-SRY fusion proteins in transfected cells compared with wild-type. The CaM antagonist CDZ (calmidazolium chloride) was found to significantly reduce wild-type SRY nuclear accumulation, indicating dependence of SRY nuclear import on CaM. Intriguingly, the CaM-NLS mutants were all resistant to CDZ's effects, implying a loss of interaction with CaM, which was confirmed by direct binding experiments. CaM-binding/resultant nuclear accumulation was the only property of SRY found to be impaired by two of the CaM-NLS mutations, implying that inhibition of CaM-dependent nuclear import is the basis of sex reversal in these cases. Importantly, the CaM-NLS is conserved in other HMG-box-domain-containing proteins such as SOX-2, -9, -10 and HMGN1, all of which were found for the first time to rely on CaM for optimal nuclear localization. CaM-dependent nuclear translocation is thus a common mechanism for this family of important transcription factors.

  11. Deterministic and stochastic transport theories for the analysis of complex nuclear systems

    International Nuclear Information System (INIS)

    Giffard, F.X.

    2000-01-01

    In the field of reactor and fuel cycle physics, particle transport plays an important role. Neutronic design, operation and evaluation calculations of nuclear systems make use of large and powerful computer codes. However, current limitations in terms of computer resources make it necessary to introduce simplifications and approximations in order to keep calculation time and cost within reasonable limits. Two different types of methods are available in these codes. The first one is the deterministic method, which is applicable in most practical cases but requires approximations. The other method is the Monte Carlo method, which does not make these approximations but which generally requires exceedingly long running times. The main motivation of this work is to investigate the possibility of a combined use of the two methods in such a way as to retain their advantages while avoiding their drawbacks. Our work has mainly focused on the speed-up of 3-D continuous energy Monte Carlo calculations (TRIPOLI-4 code) by means of an optimized biasing scheme derived from importance maps obtained from the deterministic code ERANOS. The application of this method to two different practical shielding-type problems has demonstrated its efficiency: speed-up factors of 100 have been reached. In addition, the method offers the advantage of being easily implemented as it is not very sensitive to the choice of the importance mesh grid. It has also been demonstrated that significant speed-ups can be achieved by this method in the case of coupled neutron-gamma transport problems, provided that the interdependence of the neutron and photon importance maps is taken into account. Complementary studies are necessary to tackle a problem brought out by this work, namely undesirable jumps in the Monte Carlo variance estimates. (author)

  12. Transport and release of fission products during nuclear reactor accident

    International Nuclear Information System (INIS)

    Lee, K.W.; Kuhlman, M.R.; Gieseke, J.A.

    1984-01-01

    This study represents the identification and formulation of a systematic, mechanistic approach to estimating source terms and the implementation of this approach through calculations of fission products release to the environment for a large PWR reactor under a selected set of accident conditions. The development and improvement of calculational procedures is an evolutionary process and in the long term must be verified through experimental studies. It is anticipated that as additional information is obtained the accuracy of predictions can be improved and uncertainties reduced. Transport and deposition of radionuclides were found to be quite dependent on the accident sequences and the corresponding thremal hydraulic conditions. Reduced temperatures led to increased deposition of vapor species, and reduced flow rates to increased aerosol deposition. It is to be recognized that the estimates of release fractions are subject to uncertainties in the data and computer models employed in the calculations and are expected to have been influenced by assumptions regarding plant geometry, thermal hydraulics, deposition mechanisms, and sequence events. The effects of these assumptions will be investigated as this study continues. (Author)

  13. Anomalous solute transport in saturated porous media: Relating transport model parameters to electrical and nuclear magnetic resonance properties

    Science.gov (United States)

    Swanson, Ryan D; Binley, Andrew; Keating, Kristina; France, Samantha; Osterman, Gordon; Day-Lewis, Frederick D.; Singha, Kamini

    2015-01-01

    The advection-dispersion equation (ADE) fails to describe commonly observed non-Fickian solute transport in saturated porous media, necessitating the use of other models such as the dual-domain mass-transfer (DDMT) model. DDMT model parameters are commonly calibrated via curve fitting, providing little insight into the relation between effective parameters and physical properties of the medium. There is a clear need for material characterization techniques that can provide insight into the geometry and connectedness of pore spaces related to transport model parameters. Here, we consider proton nuclear magnetic resonance (NMR), direct-current (DC) resistivity, and complex conductivity (CC) measurements for this purpose, and assess these methods using glass beads as a control and two different samples of the zeolite clinoptilolite, a material that demonstrates non-Fickian transport due to intragranular porosity. We estimate DDMT parameters via calibration of a transport model to column-scale solute tracer tests, and compare NMR, DC resistivity, CC results, which reveal that grain size alone does not control transport properties and measured geophysical parameters; rather, volume and arrangement of the pore space play important roles. NMR cannot provide estimates of more-mobile and less-mobile pore volumes in the absence of tracer tests because these estimates depend critically on the selection of a material-dependent and flow-dependent cutoff time. Increased electrical connectedness from DC resistivity measurements are associated with greater mobile pore space determined from transport model calibration. CC was hypothesized to be related to length scales of mass transfer, but the CC response is unrelated to DDMT.

  14. Factors affecting the cost and competitiveness of nuclear electricity

    International Nuclear Information System (INIS)

    Bertel, E.; Stevens, G.H.

    1996-01-01

    The general context in which are carried out the investment choices of the electric sector has evolved in a significant way during these last years and the changes are to a certain extent irreversible. Economic globalization, deregulation of the electricity market, privatisation of electricity producers, and increasing awareness of environmental issues are modifying the policy-making landscape and the criteria and priorities of decision-makers in the power sector. Competitiveness remains a cornerstone for evaluating and choosing alternative technologies in the process of planning and decision-making for electricity system expansion or power plant replacement. Nevertheless, the production costs analysis inserts factors which were not taking before into account as for instance social impacts, health and environmental effects. These new approaches better reveal the total costs of the different production means. They will certainly lead to different choices than those based on the whole comparison of direct costs supported by producers. The economic studies carried out by the Nuclear Energy Agency of the OECD (NEA) cover all the preceding aspects and give objective information on the competitiveness of nuclear electricity. The nuclear industry has today the necessary means to take up the challenges of the electricity new markets. (O.M.)

  15. Studies on human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Tsukuda, H.; Miyaoka, S.

    1988-01-01

    In order to raise the reliability and safety of nuclear power plants to the highest possible level, improvements to the mechanical system alone are not sufficient. Human factors must be systematically analysed and the causes and mechanisms of human error clarified to allow the development of countermeasures that will reduce error as much as possible. The paper introduces research in two areas, fundamental clarification of human behavioural, physiological and psychological characteristics to aid in the development of preventive measures for reducing error, and studies involving analysis of actual cases of accidents and failures related to man along with development of countermeasures to prevent the recurrence of such cases. The paper especially considers the latter area. The Human Performance Evaluation System (HPES) developed by the Institute of Nuclear Power Operations (INPO) in the USA was applied on a trial basis to 31 recent accidents and failures at Japanese nuclear power plants. The effectiveness of and possible improvement to HPES were considered. Also, cases that were not directly linked to accidents or failures were analysed using a method developed independently in Japan using data collected from a survey of approximately 3,000 power plant personnel. Fundamental research on human behaviour, physiology and psychology are also introduced. (author). 4 figs

  16. Cellular stress stimulates nuclear localization signal (NLS) independent nuclear transport of MRJ

    Science.gov (United States)

    Andrews, Joel F.; Sykora, Landon J.; Barik-Letostak, Tiasha; Menezes, Mitchell E.; Mitra, Aparna; Barik, Sailen; Shevde, Lalita A.; Samant, Rajeev S.

    2012-01-01

    HSP40 family member MRJ (DNAJB6) has been in the spot light for its relevance to Huntington’s, Parkinson’s diseases, limb-girdle muscular dystrophy, placental development, neural stem cells, cell cycle and malignancies such as breast cancer and melanoma. This gene has two spliced variants coding for 2 distinct proteins with significant homology. However, MRJ(L) (large variant) is predominantly localized to the nucleus whereas MRJ(S) (small variant) is predominantly cytoplasmic. Interestingly MRJ(S) translocates to the nucleus in response to heat shock. The classical heat shock proteins respond to crises (stress) by increasing the number of molecules, usually by transcriptional up-regulation. Our studies imply that a quick increase in the molar concentration of MRJ in the nuclear compartment is a novel method by which MRJ responds to stress. We found that MRJ(S) shows NLS (nuclear localization signal) independent nuclear localization in response to heat shock and hypoxia. The specificity of this response is realized due to lack of such response by MRJ(S) when challenged by other stressors, such as some cytokines or UV light. Deletion analysis has allowed us to narrow down on a 20 amino acid stretch at the C-terminal region of MRJ(S) as a potential stress sensing region. Functional studies indicated that constitutive nuclear localization of MRJ(S) promoted attributes of malignancy such as proliferation and invasiveness overall indicating distinct phenotypic characteristics of nuclear MRJ(S). PMID:22504047

  17. Cellular stress stimulates nuclear localization signal (NLS) independent nuclear transport of MRJ

    International Nuclear Information System (INIS)

    Andrews, Joel F.; Sykora, Landon J.; Barik Letostak, Tiasha; Menezes, Mitchell E.; Mitra, Aparna; Barik, Sailen; Shevde, Lalita A.; Samant, Rajeev S.

    2012-01-01

    HSP40 family member MRJ (DNAJB6) has been in the spot light for its relevance to Huntington's, Parkinson's diseases, limb-girdle muscular dystrophy, placental development, neural stem cells, cell cycle and malignancies such as breast cancer and melanoma. This gene has two spliced variants coding for 2 distinct proteins with significant homology. However, MRJ(L) (large variant) is predominantly localized to the nucleus whereas MRJ(S) (small variant) is predominantly cytoplasmic. Interestingly MRJ(S) translocates to the nucleus in response to heat shock. The classical heat shock proteins respond to crises (stress) by increasing the number of molecules, usually by transcriptional up-regulation. Our studies imply that a quick increase in the molar concentration of MRJ in the nuclear compartment is a novel method by which MRJ responds to stress. We found that MRJ(S) shows NLS (nuclear localization signal) independent nuclear localization in response to heat shock and hypoxia. The specificity of this response is realized due to lack of such response by MRJ(S) when challenged by other stressors, such as some cytokines or UV light. Deletion analysis has allowed us to narrow down on a 20 amino acid stretch at the C-terminal region of MRJ(S) as a potential stress sensing region. Functional studies indicated that constitutive nuclear localization of MRJ(S) promoted attributes of malignancy such as proliferation and invasiveness overall indicating distinct phenotypic characteristics of nuclear MRJ(S).

  18. Cellular stress stimulates nuclear localization signal (NLS) independent nuclear transport of MRJ

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, Joel F.; Sykora, Landon J.; Barik Letostak, Tiasha; Menezes, Mitchell E.; Mitra, Aparna [Department of Oncologic Sciences, Mitchell Cancer Institute, University of South Alabama, Mobile, AL (United States); Barik, Sailen [Center for Gene Regulation in Health and Disease, Department of Biological, Geological, and Environmental Sciences, College of Science, Cleveland State University, Cleveland, OH (United States); Shevde, Lalita A. [Department of Oncologic Sciences, Mitchell Cancer Institute, University of South Alabama, Mobile, AL (United States); Samant, Rajeev S., E-mail: rsamant@usouthal.edu [Department of Oncologic Sciences, Mitchell Cancer Institute, University of South Alabama, Mobile, AL (United States)

    2012-06-10

    HSP40 family member MRJ (DNAJB6) has been in the spot light for its relevance to Huntington's, Parkinson's diseases, limb-girdle muscular dystrophy, placental development, neural stem cells, cell cycle and malignancies such as breast cancer and melanoma. This gene has two spliced variants coding for 2 distinct proteins with significant homology. However, MRJ(L) (large variant) is predominantly localized to the nucleus whereas MRJ(S) (small variant) is predominantly cytoplasmic. Interestingly MRJ(S) translocates to the nucleus in response to heat shock. The classical heat shock proteins respond to crises (stress) by increasing the number of molecules, usually by transcriptional up-regulation. Our studies imply that a quick increase in the molar concentration of MRJ in the nuclear compartment is a novel method by which MRJ responds to stress. We found that MRJ(S) shows NLS (nuclear localization signal) independent nuclear localization in response to heat shock and hypoxia. The specificity of this response is realized due to lack of such response by MRJ(S) when challenged by other stressors, such as some cytokines or UV light. Deletion analysis has allowed us to narrow down on a 20 amino acid stretch at the C-terminal region of MRJ(S) as a potential stress sensing region. Functional studies indicated that constitutive nuclear localization of MRJ(S) promoted attributes of malignancy such as proliferation and invasiveness overall indicating distinct phenotypic characteristics of nuclear MRJ(S).

  19. Cellular stress stimulates nuclear localization signal (NLS) independent nuclear transport of MRJ

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, Joel F.; Sykora, Landon J.; Barik Letostak, Tiasha; Menezes, Mitchell E.; Mitra, Aparna [Department of Oncologic Sciences, Mitchell Cancer Institute, University of South Alabama, Mobile, AL (United States); Barik, Sailen [Center for Gene Regulation in Health and Disease, Department of Biological, Geological, and Environmental Sciences, College of Science, Cleveland State University, Cleveland, OH (United States); Shevde, Lalita A. [Department of Oncologic Sciences, Mitchell Cancer Institute, University of South Alabama, Mobile, AL (United States); Samant, Rajeev S., E-mail: rsamant@usouthal.edu [Department of Oncologic Sciences, Mitchell Cancer Institute, University of South Alabama, Mobile, AL (United States)

    2012-06-10

    HSP40 family member MRJ (DNAJB6) has been in the spot light for its relevance to Huntington's, Parkinson's diseases, limb-girdle muscular dystrophy, placental development, neural stem cells, cell cycle and malignancies such as breast cancer and melanoma. This gene has two spliced variants coding for 2 distinct proteins with significant homology. However, MRJ(L) (large variant) is predominantly localized to the nucleus whereas MRJ(S) (small variant) is predominantly cytoplasmic. Interestingly MRJ(S) translocates to the nucleus in response to heat shock. The classical heat shock proteins respond to crises (stress) by increasing the number of molecules, usually by transcriptional up-regulation. Our studies imply that a quick increase in the molar concentration of MRJ in the nuclear compartment is a novel method by which MRJ responds to stress. We found that MRJ(S) shows NLS (nuclear localization signal) independent nuclear localization in response to heat shock and hypoxia. The specificity of this response is realized due to lack of such response by MRJ(S) when challenged by other stressors, such as some cytokines or UV light. Deletion analysis has allowed us to narrow down on a 20 amino acid stretch at the C-terminal region of MRJ(S) as a potential stress sensing region. Functional studies indicated that constitutive nuclear localization of MRJ(S) promoted attributes of malignancy such as proliferation and invasiveness overall indicating distinct phenotypic characteristics of nuclear MRJ(S).

  20. Transport properties of nuclear wastes in geologic media

    International Nuclear Information System (INIS)

    Seitz, M.G.; Rickert, P.; Fried, S.; Friedman, A.M.; Steindler, M.

    1977-01-01

    Laboratory experiments were performed with Cs, Pu, Np, and Am to examine the migratory characteristics of long-lived radionuclides that could be mobilized by groundwaters infiltrating a nuclear waste repository and the surrounding geologic body. In column infiltration experiments, the positions of peak concentrations of Cs in chalk or shale columns, Pu and Am in limestone, sandstone, or tuff and neptunium in a limestone column did not move when the columns were infiltrated with water. However, fractions of all of the nuclides were seen downstream from the peaks, indicating a large dispersion in the relative migration rates of the trace elements in the lithic materials studied. Static absorption experiments showed that plutonium and americium are strongly absorbed from solution by common rocks and that their migration relative to groundwater flow is thereby retarded. Reaction rates of these dissolved elements with rocks were found to vary considerably in different rock-element systems. Following a sorption step in batch experiments with granulated basalt and Am bearing water, Pu and Am were desorbed from rock and repartitioned between rock and solution to an extent comparable to their distribution during absorption. In contrast, when tablets of various rocks were allowed to dry between absorption and desorption tests, Pu and Am were not generally desorbed from the tablets.In batch experiments with Pu and Am-bearing water and granulated basalt of several different particle sizes, the partitioning of Am and Pu did not correlate with the calculated area of the fracture surfaces nor did the partitioning remain constant (as did the measured surface area). Partitioning is concluded to be a bulk phenomenon with complete penetration of 30 to 40 mesh and smaller particles. 9 tables, 4 figs

  1. GTP-dependent binding and nuclear transport of RNA polymerase II by Npa3 protein

    DEFF Research Database (Denmark)

    Staresincic, Lidija; Walker, Jane; Dirac-Svejstrup, A Barbara

    2011-01-01

    in yeast extracts. Indeed, Npa3 depletion in vivo affects nuclear localization of RNAPII; the polymerase accumulates in the cytoplasm. Npa3 is a member of the GPN-LOOP family of GTPases. Npa3 mutants that either cannot bind GTP or that bind but cannot hydrolyze it are inviable and unable to support nuclear...... transport of RNAPII. Surprisingly, we were unable to detect interactions between Npa3 and proteins in the classical importin a/ß pathway for nuclear import. Interestingly, Npa3-RNAPII binding is significantly increased by the addition of GTP or its slowly hydrolyzable analogue guanosine 5'-3-O......-(thio)triphosphate (GTP¿S). Moreover, the Npa3 mutant that binds GTP, but cannot hydrolyze it, binds RNAPII even in the absence of added GTP, whereas the mutant that cannot bind GTP is unable to bind the polymerase. Together, our data suggest that Npa3 defines an unconventional pathway for nuclear import of RNAPII, which...

  2. Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.

    Energy Technology Data Exchange (ETDEWEB)

    OHara,J.; Higgins, J.; Brown, W.; Fink, R.

    2008-02-14

    This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and Training, Normal Operations Management, Disturbance and Emergency Management, Maintenance and Change Management, Plant Design and Construction, and HFE Methods and Tools. The issues where then prioritized into four categories using a 'Phenomena Identification and Ranking Table' methodology based on evaluations provided by 14 independent subject matter experts. The subject matter experts were knowledgeable in a variety of disciplines. Vendors, utilities, research organizations and regulators all participated. Twenty issues were categorized into the top priority category. This Brookhaven National Laboratory (BNL) technical report provides the detailed methodology, issue analysis, and results. A summary of the results of this study can be found in NUREG/CR-6947. The research performed for this project has identified a large number of human-performance issues for new control stations and new nuclear power plant designs. The information gathered in this project can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas through regulatory research. Addressing human-performance issues will provide the technical basis from which regulatory review guidance can be developed to meet these challenges. The availability of this review guidance will help set clear expectations for how the NRC staff will evaluate new designs, reduce regulatory uncertainty, and provide a well-defined path to new nuclear power plant

  3. Public Opinion shifts to the favour of nuclear energy due to steam generator transport

    International Nuclear Information System (INIS)

    Lengar, I.; Nemec, T.

    2000-01-01

    In late August and early September of 1999, nuclear energy topics occupied a central place in the Slovenian media because of the transport of two new steam generators to the Krsko nuclear power plant, and also due to the protest action of an Austrian Green peace group. Before these events, the public opinion in Slovenia was not in favour or nuclear energy ;and Green peace had a good reputation. In September it has lost much credibility because of their clumsy :action of protest, and in just one month this caused a shift of public opinion in Slovenia towards support of Slovenian's only nuclear power plant. The Green peace protest action occurred during the transport of the two new steam generators to Krsko. By replacement of the old steam generators the operation of the Krsko NPP will be extended until 2023. The transport envoy travelled during the first half of September '99 across a considerable part of Slovene territory, passing by the capital of Ljubljana. (authors)

  4. Existing experimental criticality data applicable to nuclear-fuel-transportation systems

    International Nuclear Information System (INIS)

    Bierman, S.R.

    1983-02-01

    Analytical techniques are generally relied upon in making criticality evaluations involving nuclear material outside reactors. For these evaluations to be accepted the calculations must be validated by comparison with experimental data for a known set of conditions having physical and neutronic characteristics similar to those conditions being evaluated analytically. The purpose of this report is to identify those existing experimental data that are suitable for use in verifying criticality calculations on nuclear fuel transportation systems. In addition, near term needs for additional data in this area are identified. Of the considerable amount of criticality data currently existing, that are applicable to non-reactor systems, those particularly suitable for use in support of nuclear material transportation systems have been identified and catalogued into the following groups: (1) critical assemblies of fuel rods in water; (2) critical assemblies of fuel rods in water containing soluble neutron absorbers; (3) critical assemblies containing solid neutron absorber; (4) critical assemblies of fuel rods in water with heavy metal reflectors; and (5) critical assemblies of fuel rods in water with irregular features. A listing of the current near term needs for additional data in each of the groups has been developed for future use in planning criticality research in support of nuclear fuel transportation systems. The criticality experiments needed to provide these data are briefly described and identified according to priority and relative cost of performing the experiments

  5. Working Group 7.1 on environmental transport, US-USSR Joint Coordinating Committee on Civilian Nuclear Reactor Safety

    International Nuclear Information System (INIS)

    Anspaugh, L.R.; Hendrickson, S.M.

    1991-01-01

    This report contains brief summaries of the status of projects of the Environmental Transport Group of the US-USSR Joint Coordinating Committee of Civilian Nuclear Reactor Safety. Projects reported on include: Management and Administration; Atmospheric Transport; Resuspension; External Dose; Terrestrial Food Chains; Aquatic Food Chains; Hydrological Transport; and Intercalibration

  6. Transportation of failed or damaged foreign research reactor spent nuclear fuel

    International Nuclear Information System (INIS)

    Messick, C.E.; Mustin, T.P.; Massey, C.D.

    1998-01-01

    Since resuming the Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program in 1996, the Program has had to deal with difficult issues associated with the transportation of failed or damaged spent fuel. In several instances, problems with failed or damaged fuel have prevented the acceptance of the fuel at considerable cost to both the Department of Energy (DOE) and research reactor operators. In response to the problems faced by the Acceptance Program, DOE has undertaken significant steps to better define the spent fuel acceptance criteria. DOE has worked closely with the U.S. Nuclear Regulatory Commission to address failed or damaged research reactor spent fuel and to identify cask certificate issues which must be resolved by cask owners and foreign regulatory authorities. The specific issues associated with the transport of Materials Testing Reactor (MTR)-type FRR SNF will be discussed. The information presented will include U.S. Nuclear Regulatory Commission regulatory issues, cask certificate issues, technical constraints, and lessons learned. Specific information will also be provided on the latest efforts to revise DOE's Appendix B, Transport Package (Cask) Acceptance Criteria. The information presented in this paper will be important to foreign research reactor operators, shippers, and cask vendors, so that appropriate amendments to the Certificate of Compliance for spent fuel casks can be submitted in a timely manner to facilitate the safe and scheduled transport of FRR SNF

  7. Transportation of failed or damaged foreign research reactor spent nuclear fuel

    International Nuclear Information System (INIS)

    Messick, Charles E.; Mustin, Tracy P.; Massey, Charles D.

    1999-01-01

    Since initiating the Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program in 1996, the Program has had to deal with difficult issues associated with the transportation of failed or damaged spent fuel. In several instances, problems with failed or damaged fuel have prevented the acceptance of the fuel at considerable cost to both the Department of Energy and research reactor operators. In response to the problems faced by the Acceptance Program, DOE has undertaken significant steps to better define the spent fuel acceptance criteria. DOE has worked closely with the U.S. Nuclear Regulatory Commission to address failed or damaged research reactor spent fuel causing a degradation of the fuel assembly exposing fuel meat and to identify cask certificate issues which must be resolved by cask owners and foreign regulatory authorities. The specific issues and implementation challenges associated with the transport of MTR type FRR SNF will be discussed. The information presented will include U.S. Nuclear Regulatory Commission regulatory issues, cask certificate issues, technical constraints, implementation status, and lessons learned. Specific information will also be provided on the latest efforts to revise DOE's Appendix B, Transport Package (Cask) Acceptance Criteria. The information presented in this paper will be of interest to foreign research reactor operators, shippers, and cask vendors in evaluating the condition of their fuel to ensure it can be transported in accordance with appropriate cask certificate requirements. (author)

  8. Analytical benchmarks for nuclear engineering applications. Case studies in neutron transport theory

    International Nuclear Information System (INIS)

    2008-01-01

    The developers of computer codes involving neutron transport theory for nuclear engineering applications seldom apply analytical benchmarking strategies to ensure the quality of their programs. A major reason for this is the lack of analytical benchmarks and their documentation in the literature. The few such benchmarks that do exist are difficult to locate, as they are scattered throughout the neutron transport and radiative transfer literature. The motivation for this benchmark compendium, therefore, is to gather several analytical benchmarks appropriate for nuclear engineering applications under one cover. We consider the following three subject areas: neutron slowing down and thermalization without spatial dependence, one-dimensional neutron transport in infinite and finite media, and multidimensional neutron transport in a half-space and an infinite medium. Each benchmark is briefly described, followed by a detailed derivation of the analytical solution representation. Finally, a demonstration of the evaluation of the solution representation includes qualified numerical benchmark results. All accompanying computer codes are suitable for the PC computational environment and can serve as educational tools for courses in nuclear engineering. While this benchmark compilation does not contain all possible benchmarks, by any means, it does include some of the most prominent ones and should serve as a valuable reference. (author)

  9. Needle-to-incubator transport time: Logistic factors influencing transport time for blood culture specimens

    NARCIS (Netherlands)

    J.J. Kerremans (Jos); A.K. van der Bij (Akke); W.H.F. Goessens (Wil); H.A. Verbrugh (Henri); M.C. Vos (Margreet)

    2009-01-01

    textabstractThe maximum recommended transport time for blood cultures is 4 h [L. S. Garcia (ed.), 2007 Update: Clinical Microbiology Procedures Handbook, 2nd ed., 2007]. In a previous study, we found that the average transport time was 10 h. In this cohort study, we measured transport times for

  10. Safety demonstration analyses at JAERI for severe accident during overland transport of fresh nuclear fuel

    International Nuclear Information System (INIS)

    Nomura, Yasushi; Kitao, Kohichi; Karasawa, Kiyonori; Yamada, Kenji; Takahashi, Satoshi; Watanabe, Kohji; Okuno, Hiroshi; Miyoshi, Yoshinori

    2005-01-01

    It is expected in the near future that more and more fresh nuclear fuel will be transported in a variety of transport packages to cope with increasing demand from nuclear fuel cycle facilities. Accordingly, safety demonstration analyses are planned and conducted at JAERI under contract with the Ministry of Economy, Trade and Industry of Japan. These analyses are conducted in a four year plan from 2001 to 2004 to verify integrity of packaging against leakage of radioactive material in the case of a severe accident postulated to occur during transportation, for the purpose of gaining acceptance of such nuclear fuel activities. In order to create the accident scenarios, actual transportation routes were surveyed, accident or incident records were tracked, international radioactive material transport regulations such as IAEA rules were investigated and thus, accident conditions leading to mechanical damages and thermal failure were determined to characterize the scenarios. As a result, the worst-case conditions of run-off-the-road accidents were set up to define the impact against a concrete or asphalt surface. For fire accident scenarios to be set up, collisions were assumed to occur with an oil tanker carrying lots of inflammable material in open air, or with a commonly used two-ton-truck inside a tunnel without ventilation. Then the cask models were determined for these safety demonstration analyses to represent those commonly used for fresh nuclear fuel transported throughout Japan. Following the postulated accident scenarios, the mechanical damages were analyzed by using the general-purpose finite element code LS-DYNA with three-dimensional elements. It was found that leak tightness of the package be maintained even in the severe impact scenario. Then the thermal safety was analyzed by using the general-purpose finite element code ABAOUS with three-dimensional elements to describe cask geometry. As a result of the thermal analyses, the integrity of the containment

  11. Training on Transport Security of Nuclear/Radioactive Materials for Key Audiences

    Energy Technology Data Exchange (ETDEWEB)

    Pope, Ronald; Liu, Yung; Shuler, J.M.

    2016-01-01

    Beginning in 2013, the U.S. Department of Energy (DOE) Packaging Certification Program (PCP), Office of Packaging and Transportation, Office of Environmental Management has sponsored a series of three training courses on Security of Nuclear and Other Radioactive Materials during Transport. These courses were developed and hosted by Argonne National Laboratory staff with guest lecturers from both the U.S. and international organizations and agencies including the U.S. Nuclear Regulatory Commission (NRC), Federal Bureau of Investigation (FBI), the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), DOE national laboratories, the International Atomic Energy Agency (IAEA), the World Nuclear Transport Institute (WNTI), and the World Institute for Nuclear Security (WINS). Each of the three courses held to date were one-week in length. The courses delved in detail into the regulatory requirements for transport security, focusing on international and U.S.-domestic requirements and guidance documents. Lectures, in-class discussions and small group exercises, including tabletop (TTX) and field exercises were designed to enhance the learning objectives for the participants. For example, the field exercise used the ARG-US radio frequency identification (RFID) remote surveillance system developed by Argonne for DOE/PCP to track and monitor packages in a mock shipment, following in-class exercises of developing a transport security plan (TSP) for the mock shipment, performing a readiness review and identifying needed corrective actions. Participants were able to follow the mock shipment on the webpage in real time in the ARG-US Command Center at Argonne including “staged” incidents that were designed to illustrate the importance of control, command, communication and coordination in ensuring transport security. Great lessons were learned based on feedback from the participant’s course evaluations with the series of the courses. Since the

  12. Improved single particle potential for transport model simulations of nuclear reactions induced by rare isotope beams

    International Nuclear Information System (INIS)

    Xu Chang; Li Baoan

    2010-01-01

    Taking into account more accurately the isospin dependence of nucleon-nucleon interactions in the in-medium many-body force term of the Gogny effective interaction, new expressions for the single-nucleon potential and the symmetry energy are derived. Effects of both the spin (isospin) and the density dependence of nuclear effective interactions on the symmetry potential and the symmetry energy are examined. It is shown that they both play a crucial role in determining the symmetry potential and the symmetry energy at suprasaturation densities. The improved single-nucleon potential will be useful for more accurate simulation of nuclear reactions induced by rare-isotope beams within transport models.

  13. Impact of nuclear 'pasta' on neutrino transport in collapsing stellar cores

    International Nuclear Information System (INIS)

    Sonoda, Hidetaka; Watanabe, Gentaro; Sato, Katsuhiko; Takiwaki, Tomoya; Yasuoka, Kenji; Ebisuzaki, Toshikazu

    2007-01-01

    Nuclear 'pasta', nonspherical nuclei in dense matter, is predicted to occur in collapsing supernova cores. We show how pasta phases affect the neutrino transport cross section via weak neutral current using several nuclear models. This is the first calculation of the neutrino opacity of the phases with rod-like and slab-like nuclei taking account of finite temperature effects, which are well described by the quantum molecular dynamics. We also show that pasta phases can occupy 10-20% of the mass of supernova cores in the later stage of the collapse

  14. Nuclear Liability and Insurance Protection for Nuclear Transport Accidents Involving Non-Contracting EU States: An assessment

    International Nuclear Information System (INIS)

    Horbach, N. L. J. T.

    2006-01-01

    This paper provides an analysis of the possible complications and consequences with respect to nuclear liability and insurance protection applicable in respect of transport activities resulting in damage suffered and/or accidents occurring in EU States that are not party to the Paris Convention. It looks at the different legal aspects (jurisdiction, applicable law, liability amounts, reciprocity) should the revised Vienna and Paris Convention become applicable in comparison with the unrevised Conventions. Within Europe, a large number of States are party to the 1960 Paris Convention and the 1963 Brussels Supplementary Convention, providing liability and insurance protection, in general, up to a limit of 300 million SDRs (or even higher). In principle, such protection is confined to nuclear incidents occurring and nuclear damage suffered in the territory of Contracting Parties, including, as recommended, the high seas, unless the legislation of the Installation State determines otherwise (Article 2). The geographical scope of application of the Paris Convention would thus vary according to the law of the Installation State. However, some EU States never became party to the Paris Convention, and are not bound by its the liability principles (notably, channelling of liability), such as Austria, Luxembourg and Ireland. Transport accidents involving these countries might therefore result in liability claims outside the treaty liability regime against operators, suppliers, carriers or persons involved and for types of damages different from those currently covered by the Paris Convention (e.g., environmental damage). It is uncertain to what extent liability insurance of the installation operators would provide adequate protection and whether related damage claims can be enforceable. In addition, a number of newly entered EU States are party to the Vienna Convention, which, although bound by liability principles basically similar to those of the Paris Convention, will

  15. A preliminary analysis of the risk of transporting nuclear waste to potential candidate commercial repository sites

    International Nuclear Information System (INIS)

    Madsen, M.M.

    1984-01-01

    In accordance with the provisions of the Nuclear Waste Policy Act of 1982, environmental assessments for potential candidate sites are required to provide a basis for selection of the first site for disposal of commercial radioactive waste in deep geologic repositories. A preliminary analysis of the impacts of transportation for each of the five potential sites will be described. Transportation was assumed to be entirely by truck or entirely by rail in order to obtain bounding impacts. This paper presents both radiological and nonradiological risks for the once-through fuel cycle

  16. The transport of radioactive materials, paying special attention to nuclear fuels

    International Nuclear Information System (INIS)

    Blechschmidt, M.

    1977-06-01

    The transport of radioactive materials, particularly within the nuclear fuel cycle, is of increasing importance, and is more than ever a matter of public debate. This report provides information concerning the necessary physical, technical and administrative precautions which must be taken to ensure protection of the environment. The international standard of requirements for the packing of the materials is emphasized, as in many cases, transports cross national borders. The relatively comprehensive list of references can be used for the study of details. (orig.) [de

  17. Shielding requirements for the transport of nuclear warhead components under decommissioning

    International Nuclear Information System (INIS)

    Hansen, L.F.

    1994-09-01

    The requirements to carry out accurate shielding calculations involved with the safe off-site transportation of packages containing nuclear warhead components, special assemblies and radioactive materials are discussed. The need for (a) detailed information on the geometry and material composition of the packaging and radioactive load, (b) accurate representation of the differential energy spectra (dN/dE) for the neutron and gamma spectra emitted by the radioactive materials enclosed in the packaging, (c) well-tested neutron and photon cross section libraries, (d) and accurate three-dimensional Monte Carlo transport codes are illustrated. A brief discussion of the need for reliable dose measurements is presented

  18. Thermodynamics of competitive molecular channel transport: application to artificial nuclear pores.

    Directory of Open Access Journals (Sweden)

    Wolfgang R Bauer

    Full Text Available In an analytical model channel transport is analyzed as a function of key parameters, determining efficiency and selectivity of particle transport in a competitive molecular environment. These key parameters are the concentration of particles, solvent-channel exchange dynamics, as well as particle-in-channel- and interparticle interaction. These parameters are explicitly related to translocation dynamics and channel occupation probability. Slowing down the exchange dynamics at the channel ends, or elevating the particle concentration reduces the in-channel binding strength necessary to maintain maximum transport. Optimized in-channel interaction may even shift from binding to repulsion. A simple equation gives the interrelation of access dynamics and concentration at this transition point. The model is readily transferred to competitive transport of different species, each of them having their individual in-channel affinity. Combinations of channel affinities are determined which differentially favor selectivity of certain species on the cost of others. Selectivity for a species increases if its in-channel binding enhances the species' translocation probability when compared to that of the other species. Selectivity increases particularly for a wide binding site, long channels, and fast access dynamics. Recent experiments on competitive transport of in-channel binding and inert molecules through artificial nuclear pores serve as a paradigm for our model. It explains qualitatively and quantitatively how binding molecules are favored for transport at the cost of the transport of inert molecules.

  19. Thermodynamics of competitive molecular channel transport: application to artificial nuclear pores.

    Science.gov (United States)

    Bauer, Wolfgang R; Nadler, Walter

    2010-12-13

    In an analytical model channel transport is analyzed as a function of key parameters, determining efficiency and selectivity of particle transport in a competitive molecular environment. These key parameters are the concentration of particles, solvent-channel exchange dynamics, as well as particle-in-channel- and interparticle interaction. These parameters are explicitly related to translocation dynamics and channel occupation probability. Slowing down the exchange dynamics at the channel ends, or elevating the particle concentration reduces the in-channel binding strength necessary to maintain maximum transport. Optimized in-channel interaction may even shift from binding to repulsion. A simple equation gives the interrelation of access dynamics and concentration at this transition point. The model is readily transferred to competitive transport of different species, each of them having their individual in-channel affinity. Combinations of channel affinities are determined which differentially favor selectivity of certain species on the cost of others. Selectivity for a species increases if its in-channel binding enhances the species' translocation probability when compared to that of the other species. Selectivity increases particularly for a wide binding site, long channels, and fast access dynamics. Recent experiments on competitive transport of in-channel binding and inert molecules through artificial nuclear pores serve as a paradigm for our model. It explains qualitatively and quantitatively how binding molecules are favored for transport at the cost of the transport of inert molecules.

  20. Probabilistic Risk Assessment of Cask Drop Accident during On-site Spent Nuclear Fuel Transportation

    Energy Technology Data Exchange (ETDEWEB)

    Ham, Jae Hyun; Christian, Robby; Momani, Belal Al; Kang, Hyun Gook [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    There are two ways to transfer the SNF from a site to other site, one is land transportation and the other is maritime transportation. Maritime transportation might be used because this way uses more safe route which is far from populated area. The whole transportation process can be divided in two parts: transferring the SNF between SNP and wharf in-Nuclear Power Plant (NPP) site by truck, and transferring the SNF from the wharf to the other wharf by ship. In this research, on-site SNF transportation between SNP and wharf was considered. Two kinds of single accident can occur during this type of SNF transportation, impact and fire, caused by internal events and external events. In this research, PRA of cask drop accident during onsite SNF transportation was done, risk to a person (mSv/person) from a case with specific conditions was calculated. In every 11 FEM simulation drop cases, FDR is 1 even the fuel assemblies are located inside of the cask. It is a quite larger value for all cases than the results with similar drop condition from the reports which covers the PRA on cask storage system. Because different from previous reports, subsequent impact was considered. Like in figure 8, accelerations which are used to calculate the FDR has extremely higher values in subsequent impact than the first impact for all SNF assemblies.

  1. THE TIME FACTOR IN MARITIME TRANSPORT AND PORT LOGISTICS ACTIVITIES

    Directory of Open Access Journals (Sweden)

    Florin NICOLAE

    2016-06-01

    Full Text Available Execution of the carriage contract requires compliance to all the conditions in it, by all those involved in the transport. Main obligations incumbent upon the vessel, and obviously, to other transporters, who must provide transportation according to deadlines and safety. Contract compliance is certifying transport participants about their seriousness and an appropriate market quotation. Therefore, present work pragmatically sets schematics reference time associated implementation of the carriage contract. Also, are demonstrated relationships established between maritime transport “players” and sequence of activities related to the operation of the vessel in port. The authors propose a set of concepts and terms whose utility is established to solve practical problems in this area of activity.

  2. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Yuan, Y.C. [Square Y Consultants, Orchard Park, NY (US); Chen, S.Y.; Biwer, B.M.; LePoire, D.J. [Argonne National Lab., IL (US)

    1995-11-01

    This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the Windows{trademark} environment. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incident-free models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionuclide inventory and dose conversion factors. In addition, the flexibility of the models allows them to be used for assessing any accidental release involving radioactive materials. The RISKIND code allows for user-specified accident scenarios as well as receptor locations under various exposure conditions, thereby facilitating the estimation of radiological consequences and health risks for individuals. Median (50% probability) and typical worst-case (less than 5% probability of being exceeded) doses and health consequences from potential accidental releases can be calculated by constructing a cumulative dose/probability distribution curve for a complete matrix of site joint-wind-frequency data. These consequence results, together with the estimated probability of the entire spectrum of potential accidents, form a comprehensive, probabilistic risk assessment of a spent nuclear fuel transportation accident.

  3. RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

    International Nuclear Information System (INIS)

    Yuan, Y.C.; Chen, S.Y.; Biwer, B.M.; LePoire, D.J.

    1995-11-01

    This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the Windows trademark environment. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incident-free models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionuclide inventory and dose conversion factors. In addition, the flexibility of the models allows them to be used for assessing any accidental release involving radioactive materials. The RISKIND code allows for user-specified accident scenarios as well as receptor locations under various exposure conditions, thereby facilitating the estimation of radiological consequences and health risks for individuals. Median (50% probability) and typical worst-case (less than 5% probability of being exceeded) doses and health consequences from potential accidental releases can be calculated by constructing a cumulative dose/probability distribution curve for a complete matrix of site joint-wind-frequency data. These consequence results, together with the estimated probability of the entire spectrum of potential accidents, form a comprehensive, probabilistic risk assessment of a spent nuclear fuel transportation accident

  4. Rules common to nuclear incidents occurring in installations or during transport of nuclear substances

    International Nuclear Information System (INIS)

    Lagorce, M.

    1976-01-01

    As concerns the peaceful applications of nuclear power, the traditional third party liability regulations were found to be inadequate to cover the specific aspects of the nuclear risk, and this was likely to hinder the progress of this new activity. This was why the countries involved opted for the elaboration of a special liability regime by adopting the Paris Convention of 29th July 1960, the Convention Supplementary to the Paris Convention of the 31st January 1963 and the Vienna Convention of 21st May 1963. The Paris and Vienna Conventions set up a regime characterized by the nuclear operator's absolute and exclusive liability, the limitation of such liability in amount and in time the uniquity of jurisdictional competence, the obligation to provide financial security for compensation of damage. The purpose of the Brussels Supplementary Convention is to increase the amount of compensation for damage by additional funds supplied partly by the State involved and partly by a collective contribution from the various countries Parties to the Convention, thus setting up a mechanism of international solidarity. (NEA) [fr

  5. 48 CFR 247.372 - DD Form 1654, Evaluation of Transportation Cost Factors.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false DD Form 1654, Evaluation... Transportation in Supply Contracts 247.372 DD Form 1654, Evaluation of Transportation Cost Factors. Contracting personnel may use the DD Form 1654 to furnish information to the transportation office for development of...

  6. Energy Coupling Factor-Type ABC Transporters for Vitamin Uptake in Prokaryotes

    NARCIS (Netherlands)

    Erkens, Guus B.; Dosz-Majsnerowska, Maria; ter Beek, Josy; Slotboom, Dirk Jan

    2012-01-01

    Energy coupling factor (ECF) transporters are a subgroup of ATP-binding cassette (ABC) transporters involved in the uptake of vitamins and micronutrients in prokaryotes. In contrast to classical ABC importers, ECF transporters do not make use of water-soluble substrate binding proteins or domains

  7. A physical model describing the interaction of nuclear transport receptors with FG nucleoporin domain assemblies.

    Science.gov (United States)

    Zahn, Raphael; Osmanović, Dino; Ehret, Severin; Araya Callis, Carolina; Frey, Steffen; Stewart, Murray; You, Changjiang; Görlich, Dirk; Hoogenboom, Bart W; Richter, Ralf P

    2016-04-08

    The permeability barrier of nuclear pore complexes (NPCs) controls bulk nucleocytoplasmic exchange. It consists of nucleoporin domains rich in phenylalanine-glycine motifs (FG domains). As a bottom-up nanoscale model for the permeability barrier, we have used planar films produced with three different end-grafted FG domains, and quantitatively analyzed the binding of two different nuclear transport receptors (NTRs), NTF2 and Importin β, together with the concomitant film thickness changes. NTR binding caused only moderate changes in film thickness; the binding isotherms showed negative cooperativity and could all be mapped onto a single master curve. This universal NTR binding behavior - a key element for the transport selectivity of the NPC - was quantitatively reproduced by a physical model that treats FG domains as regular, flexible polymers, and NTRs as spherical colloids with a homogeneous surface, ignoring the detailed arrangement of interaction sites along FG domains and on the NTR surface.

  8. Nuclear fuel particles in the environment - characteristics, atmospheric transport and skin doses

    International Nuclear Information System (INIS)

    Poellaenen, R.

    2002-05-01

    In the present thesis, nuclear fuel particles are studied from the perspective of their characteristics, atmospheric transport and possible skin doses. These particles, often referred to as 'hot' particles, can be released into the environment, as has happened in past years, through human activities, incidents and accidents, such as the Chernobyl nuclear power plant accident in 1986. Nuclear fuel particles with a diameter of tens of micrometers, referred to here as large particles, may be hundreds of kilobecquerels in activity and even an individual particle may present a quantifiable health hazard. The detection of individual nuclear fuel particles in the environment, their isolation for subsequent analysis and their characterisation are complicated and require well-designed sampling and tailored analytical methods. In the present study, the need to develop particle analysis methods is highlighted. It is shown that complementary analytical techniques are necessary for proper characterisation of the particles. Methods routinely used for homogeneous samples may produce erroneous results if they are carelessly applied to radioactive particles. Large nuclear fuel particles are transported differently in the atmosphere compared with small particles or gaseous species. Thus, the trajectories of gaseous species are not necessarily appropriate for calculating the areas that may receive large particle fallout. A simplified model and a more advanced model based on the data on real weather conditions were applied in the case of the Chernobyl accident to calculate the transport of the particles of different sizes. The models were appropriate in characterising general transport properties but were not able to properly predict the transport of the particles with an aerodynamic diameter of tens of micrometers, detected at distances of hundreds of kilometres from the source, using only the current knowledge of the source term. Either the effective release height has been higher

  9. Nuclear fuel particles in the environment - characteristics, atmospheric transport and skin doses

    Energy Technology Data Exchange (ETDEWEB)

    Poellaenen, R

    2002-05-01

    In the present thesis, nuclear fuel particles are studied from the perspective of their characteristics, atmospheric transport and possible skin doses. These particles, often referred to as 'hot' particles, can be released into the environment, as has happened in past years, through human activities, incidents and accidents, such as the Chernobyl nuclear power plant accident in 1986. Nuclear fuel particles with a diameter of tens of micrometers, referred to here as large particles, may be hundreds of kilobecquerels in activity and even an individual particle may present a quantifiable health hazard. The detection of individual nuclear fuel particles in the environment, their isolation for subsequent analysis and their characterisation are complicated and require well-designed sampling and tailored analytical methods. In the present study, the need to develop particle analysis methods is highlighted. It is shown that complementary analytical techniques are necessary for proper characterisation of the particles. Methods routinely used for homogeneous samples may produce erroneous results if they are carelessly applied to radioactive particles. Large nuclear fuel particles are transported differently in the atmosphere compared with small particles or gaseous species. Thus, the trajectories of gaseous species are not necessarily appropriate for calculating the areas that may receive large particle fallout. A simplified model and a more advanced model based on the data on real weather conditions were applied in the case of the Chernobyl accident to calculate the transport of the particles of different sizes. The models were appropriate in characterising general transport properties but were not able to properly predict the transport of the particles with an aerodynamic diameter of tens of micrometers, detected at distances of hundreds of kilometres from the source, using only the current knowledge of the source term. Either the effective release height has

  10. Spent nuclear fuel and high level radioactive waste transportation. White paper

    International Nuclear Information System (INIS)

    1985-06-01

    The High-Level Radioactive Waste Committee of the Western Interstate Energy Board has been involved in a year-long cooperative project with the US Department of Energy (DOE) to develop an information base on the transportation of spent nuclear fuel and high-level radioactive waste (HLW) so that western states can be constructive and informed participants in the repository program under the Nuclear Waste Policy Act (NWPA). The historical safety record of transportation of HLW and spent fuel is excellent; no release of these radioactive materials has ever occurred during transportation. Projected shipments under the NWPA will, however, greatly exceed current shipments in the US. For example, over the past five years, 119 metric tons of civilian spent fuel have been shipped in this country, while shipments to the first and second repository are each expected to peak at 3000 metric tons per year. The Committee believes that the successful development and operation of a national HLW/spent fuel transportation system can best be accomplished through an open process based on the common sense approach of taking all reasonable measures to minimize public risk and performing whatever actions are reasonably required to promote public acceptance. Therefore, the Committee recommends that the Department of Energy further the goals of the NWPA by developing a Comprehensive Transportation Plan which adopts a systematic, comprehensive, and integrated approach to resolving all spent fuel and HLW transportation issues in a timely manner. The suggested scope of such a plan is discussed in this White paper. Many of the suggested elements of such a plan are similar to those being developed by the Department of energy for inclusion in the Department's Transportation Institutional Plan

  11. Influence factors on etching rate of PET nuclear pore membrane

    International Nuclear Information System (INIS)

    Zuo Zhenzhong; Wu Zhendong; Liang Haiying; Ju Wei; Chen Dongfeng; Fu Yuanyong; Qu Guopu

    2014-01-01

    Background: The nuclear pore membrane is a kind of liquid filtration material manufactured by irradiation and chemical etching. Various conditions in etch process have a great influence on etch rate. Purpose: The influence factors of concentration and temperature of etch solution and the irradiation energy of heavy ions on etch rate was studied. Methods: Four layers of PET (polyethylene terephthalate) films were stacked together and were irradiated with 140-MeV 32 S ions at room temperature under vacuum conditions. Utilizing conductivity measurement technique, the electrical current changes through the u:radiated PET film were monitored during etching, from which the breakthrough time and therefore the track etching rate was calculated. Results: The results show that there is an exponential correlation between etch rate and temperature, and a linear correlation between etch rate and concentration. The track etching rate increases linearly with energy loss rate. Empirical formula for the bulk etching rate as a function of etchant concentration and temperature was also established via fitting of measurements. Conclusion: It is concluded that by using 1.6-MeV·u -1 32 S ions, PET nuclear pore membrane with cylindrical pore shape can be prepared at 85℃ with etchant concentration of l mol·L -1 . (authors)

  12. Integrated management platform of nuclear fuel storage and transportation based on RFID

    International Nuclear Information System (INIS)

    Song Yafeng; Ma Yanqin; Chen Liyu; Jiang Yong; Wu Jianlei; Yang Haibo; Zhang Haiyan

    2012-01-01

    This paper describes integrated system model to improve work efficiency and optimize control measures of nuclear fuel storage and transportation, RFID and information integration technology is introduced, traditional management processes are innovated in data acquisition and monitoring fields as well, system solutions and design model are given by emphasizing on the following key technologies: cascade protection of information system, security protocol of RFID information, algorithm of collision. (authors)

  13. Automation of the helium jet transport system for nuclear recoil products

    International Nuclear Information System (INIS)

    Bellido, Luis F.; Pedrosa, Paulo S.

    1996-09-01

    A computer code and an interface hardware to automate the acquisition data and the sample changer in a helium jet transport system of recoil nucleus was developed for an IBM or compatible personal microcomputer. The software works with a Spectrum-ACE/ADCAM ORTEC's multichannel analysers and the interface card uses the 03EFh port to command the sample changer. This system allows to measure, by gamma spectrometry, radionuclides with half-lives of order of seconds produced from nuclear reactions. (author)

  14. The contribution of transport to the overall risk of nuclear energy

    International Nuclear Information System (INIS)

    Huebenthal, K.

    1985-01-01

    The overall risk of nuclear energy is minute as compared with other natural and civilization-effected risks. The contribution of the transport of radioactive materials to this overall risk is not significant. The paper touches the following subjects: Project Safety Studies of Waste Management (PSE), System Studies Alternative Waste Disposal Technologies (PAE), Motor Columbus and the Federal Gazette 10/2160 of October 1984. Collective doses of the population are given for the fuel cycle with various waste management technologies. (DG) [de

  15. Collective effects on transport coefficients of relativistic nuclear matter. Pt. 2

    International Nuclear Information System (INIS)

    Mornas, L.

    1993-04-01

    The transport coefficients (thermal conductivity, shear and bulk viscosities) of symmetric nuclear matter and neutron matter are calculated in the Walecka model with a Boltzmann-Uehling-Uhlenbeck collision term by means of a Chapman-Enskog expansion in first order. The order of magnitude of the influence of collective effects induced by the presence of the mean σ and ω fields on these coefficients is evaluated. (orig.). 9 figs

  16. A mathematical model for cost of maritime transport. Application to competitiveness of nuclear vessels

    International Nuclear Information System (INIS)

    Dorval, C.

    1966-05-01

    In studying the competitiveness of a nuclear merchant vessel, economic assessments in terms of figures were discarded in favor of a simplified model, which gives a clearer idea of the mechanism of the comparison between alternative vessels and the particular influence of each parameter. An expression is formulated for the unit cost per ton carried over a given distance as a function of the variables (speed and deadweight tonnage) and is used to determine the optima for conventional and nuclear vessels. To represent the freight market involved in the optimization studies, and thus in the competitiveness computation, two cases are taken into account: the tonnage to be carried annually is limited, and the tonnage to be carried annually is not limited. In both cases the optima are calculated and compared for a conventional and a nuclear vessel. Competitiveness curves are plotted as a function of the ratios of nuclear and conventional fuel costs and nuclear and conventional marginal power costs. These curves express the limiting values of the above two ratios for which the transport costs of the nuclear and conventional vessels are equal. The competitiveness curves vary considerably according to the hypothesis adopted for the freight market and the limit of tonnage carried annually. (author) [fr

  17. Advanced Intermediate Heat Transport Loop Design Configurations for Hydrogen Production Using High Temperature Nuclear Reactors

    International Nuclear Information System (INIS)

    Chang Oh; Cliff Davis; Rober Barner; Paul Pickard

    2005-01-01

    The US Department of Energy is investigating the use of high-temperature nuclear reactors to produce hydrogen using either thermochemical cycles or high-temperature electrolysis. Although the hydrogen production processes are in an early stage of development, coupling either of these processes to the high-temperature reactor requires both efficient heat transfer and adequate separation of the facilities to assure that off-normal events in the production facility do not impact the nuclear power plant. An intermediate heat transport loop will be required to separate the operations and safety functions of the nuclear and hydrogen plants. A next generation high-temperature reactor could be envisioned as a single-purpose facility that produces hydrogen or a dual-purpose facility that produces hydrogen and electricity. Early plants, such as the proposed Next Generation Nuclear Plant (NGNP), may be dual-purpose facilities that demonstrate both hydrogen and efficient electrical generation. Later plants could be single-purpose facilities. At this stage of development, both single- and dual-purpose facilities need to be understood. A number of possible configurations for a system that transfers heat between the nuclear reactor and the hydrogen and/or electrical generation plants were identified. These configurations included both direct and indirect cycles for the production of electricity. Both helium and liquid salts were considered as the working fluid in the intermediate heat transport loop. Methods were developed to perform thermal-hydraulic evaluations and cycle-efficiency evaluations of the different configurations and coolants. The thermal-hydraulic evaluations estimated the sizes of various components in the intermediate heat transport loop for the different configurations. The relative sizes of components provide a relative indication of the capital cost associated with the various configurations. Estimates of the overall cycle efficiency of the various

  18. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  19. Scaling of nuclear modification factors for hadrons and light nuclei

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, C.S. [Chinese Academy of Sciences, Shanghai Institute of Applied Physics, Shanghai (China); University of Chinese Academy of Sciences, Beijing (China); Ma, Y.G. [Chinese Academy of Sciences, Shanghai Institute of Applied Physics, Shanghai (China); ShanghaiTech University, Shanghai (China); Zhang, S. [Chinese Academy of Sciences, Shanghai Institute of Applied Physics, Shanghai (China)

    2016-12-15

    The number of constituent quarks (NCQ) scaling for hadrons and the number of constituent nucleons (NCN) scaling for light nuclei are proposed for nuclear modification factors (R{sub cp}) of hadrons and light nuclei, respectively, according to the experimental investigations in relativistic heavy-ion collisions. Based on the coalescence mechanism the scalings are performed for pions and protons at the quark level, and for light nuclei d(anti d) and {sup 3}He at the nucleonic level, respectively, formed in Au+Au and Pb+Pb collisions, and a nice scaling behaviour emerges. The NCQ or NCN scaling law of R{sub cp} can be, respectively, taken as a probe for the quark or nucleon coalescence mechanism for the formation of hadron or light nuclei in relativistic heavy-ion collisions. (orig.)

  20. Safety demonstration analyses for severe accident of fresh nuclear fuel transport packages at JAERI

    International Nuclear Information System (INIS)

    Yamada, K.; Watanabe, K.; Nomura, Y.; Okuno, H.; Miyoshi, Y.

    2004-01-01

    It is expected in the near future that more and more fresh nuclear fuel will be transported in a variety of transport packages to cope with increasing demand from nuclear fuel cycle facilities. Accordingly, safety demonstration analyses of these methods are planned and conducted at JAERI under contract with the Ministry of Economy, Trade and Industry of Japan. These analyses are conducted part of a four year plan from 2001 to 2004 to verify integrity of packaging against leakage of radioactive material in the case of a severe accident envisioned to occur during transportation, for the purpose of gaining public acceptance of such nuclear fuel activities. In order to create the accident scenarios, actual transportation routes were surveyed, accident or incident records were tracked, international radioactive material transport regulations such as IAEA rules were investigated and, thus, accident conditions leading to mechanical damage and thermal failure were selected for inclusion in the scenario. As a result, the worst-case conditions of run-off-the-road accidents were incorporated, where there is impact against a concrete or asphalt surface. Fire accidents were assumed to occur after collision with a tank truck carrying lots of inflammable material or destruction by fire after collision inside a tunnel. The impact analyses were performed by using three-dimensional elements according to the general purpose impact analysis code LS-DYNA. Leak-tightness of the package was maintained even in the severe impact accident scenario. In addition, the thermal analyses were performed by using two-dimensional elements according to the general purpose finite element method computer code ABAQUS. As a result of these analyses, the integrity of the inside packaging component was found to be sufficient to maintain a leak-tight state, confirming its safety

  1. Transport of spent nuclear fuel from the High Flux Beam Reactor

    International Nuclear Information System (INIS)

    Holland, Michael; Carelli, Joseph; Shelton, Thomas

    1997-01-01

    The shipment of more than 1000 elements of spent nuclear fuel (SNF) from the Department of Energy's Brookhaven National Laboratory (BNL) High Flux Beam Reactor (HFBR) to the Department's Savannah River Site (SRS) for long term interim storage required overcoming several significant obstacles. The project management team was comprised of DOE, BNL and NAC International personnel. This achievement involved coordinating the efforts of numerous government and contractor organizations such as the U.S. Coast Guard, the U.S. Nuclear Regulatory Commission, state and local governments, marine and motor carriers, and carrier inspectors. Unique experience was gained during development and execution of the project in the following areas: dry transfer of SNF to shipping casks; inter-modal transfers; logistics; cask licensing by the Nuclear Regulatory Commission (NRC); compliance with environmental regulations; transportation plan development, and stakeholder outreach and coordination

  2. Radiological health risks from accidents during transportation of spent nuclear fuels

    International Nuclear Information System (INIS)

    Chen, S.Y.; Yuan, Y.C.

    1988-01-01

    Potential radiological health risks from severe accident scenarios during the transportation of spent nuclear fuels are estimated. These extremely low probability, but potentially credible, scenarios are characterized by the U.S. Nuclear Regulatory Commission's Modal Study in terms of the maximum credible structural responses and/or the maximum credible cask temperature responses. In some accident scenarios, the spent nuclear fuel casks are assumed to be breached, resulting in the release of radioactivity to the atmosphere. Models have been developed to estimate radiological health consequences, including potential short-term exposures and health effects to individuals and potential long-term environmental dose commitments and health effects to the population. The population risks are calculated using state-level data, and the resulting overall health risks are compared for several levels of cleanup effort to determine the relative effects on long-term risks to the population in the event of an accident. 4 refs., 3 figs., 3 tabs

  3. Evaluation of groundwater flow and transport at the Shoal underground nuclear test: An interim report

    Energy Technology Data Exchange (ETDEWEB)

    Pohll, G.; Chapman, J.; Hassan, A.; Papelis, C.; Andricevic, R.; Shirley, C.

    1998-07-01

    Since 1962, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive materials in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site, but a limited number of experiments were conducted in other locations. One of these is the subject of this report, the Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada. The Shoal test consisted of a 12-kiloton-yield nuclear detonation which occurred on October 26, 1963. Project Shoal was part of studies to enhance seismic detection of underground nuclear tests, in particular, in active earthquake areas. Characterization of groundwater contamination at the Project Shoal Area is being conducted by the US Department of Energy (DOE) under the Federal Facility Agreement and Consent Order (FFACO) with the State of Nevada Department of Environmental Protection and the US Department of Defense (DOD). This order prescribes a Corrective Action Strategy (Appendix VI), which, as applied to underground nuclear tests, involves preparing a Corrective Action Investigation Plan (CAIP), Corrective Action Decision Document (CADD), Corrective Action Plan, and Closure Report. The scope of the CAIP is flow and transport modeling to establish contaminant boundaries that are protective of human health and the environment. This interim report describes the current status of the flow and transport modeling for the PSA.

  4. Evaluation of groundwater flow and transport at the Shoal underground nuclear test: An interim report

    International Nuclear Information System (INIS)

    Pohll, G.; Chapman, J.; Hassan, A.; Papelis, C.; Andricevic, R.; Shirley, C.

    1998-07-01

    Since 1962, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive materials in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site, but a limited number of experiments were conducted in other locations. One of these is the subject of this report, the Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada. The Shoal test consisted of a 12-kiloton-yield nuclear detonation which occurred on October 26, 1963. Project Shoal was part of studies to enhance seismic detection of underground nuclear tests, in particular, in active earthquake areas. Characterization of groundwater contamination at the Project Shoal Area is being conducted by the US Department of Energy (DOE) under the Federal Facility Agreement and Consent Order (FFACO) with the State of Nevada Department of Environmental Protection and the US Department of Defense (DOD). This order prescribes a Corrective Action Strategy (Appendix VI), which, as applied to underground nuclear tests, involves preparing a Corrective Action Investigation Plan (CAIP), Corrective Action Decision Document (CADD), Corrective Action Plan, and Closure Report. The scope of the CAIP is flow and transport modeling to establish contaminant boundaries that are protective of human health and the environment. This interim report describes the current status of the flow and transport modeling for the PSA

  5. Factors determining the UK's back-end nuclear fuel cycle strategy and future nuclear systems

    International Nuclear Information System (INIS)

    Dunn, M.J.; Ainsworth, Z.E.

    2002-01-01

    Nuclear generating capacity in the UK is static with no units currently under construction. The AGRs and the UK's only PWR, Sizewell B, are operated by British Energy Generation Ltd (BEGL) and British Energy Generation (UK) Ltd (BEG(UK)L), who are subsidiaries of British Energy plc (BE) which was privatised in July 1996. Ownership of the Magnox stations, which were excluded from this privatisation, has now been transferred to BNFL.Government policy on spent fuel management in the UK is that it is for the owners of the spent fuel to decide on the appropriate spent fuel management options, based on their own commercial judgement, subject to meeting the necessary regulatory requirements. The main factors which have predominantly determined UK utility decisions on spent fuel management, to date, have been based on the technical considerations of the spent fuel characteristics, economic attractiveness of the options and at reactor site spent fuel storage capacities. To date, reprocessing has been the dominant form of spent fuel treatment in the UK. Spent fuel storage facilities consist of a mixture of at-reactor stores and large, centralised ponds associated with the reprocessing activities which take place at the Sellafield site. BEGL and BEG(UK)L have contracts for the lifetime arisings of AGR fuel which allow for all AGR spent fuel to be sent to Sellafield for reprocessing or long-term storage. The prompt reprocessing of all Magnox fuel will continue, and spent PWR fuel will continue to be stored at the reactor site in the short to medium term. It is likely that a combination of factors, which are discussed later in this paper, will continue to affect back-end nuclear fuel cycle strategy and future nuclear systems. (author)

  6. Factors influencing the control strategy of hybrid drive of urban public transport buses

    International Nuclear Information System (INIS)

    Barta, Dalibor; Mruzek, Martin

    2015-01-01

    The efficiency of each drives is dependent on many factors. Hybrid drives and specially the drives of urban public transport may be affected by other factors given by transport infrastructure or operational conditions. These factors condition the suitable configuration of the individual elements of hybrid drive and the establishment of good control strategy of such drive. The study of influencing factors of the control strategy is the aim of this paper. (full text)

  7. Assessment of hydrologic transport of radionuclides from the Rulison Underground Nuclear Test Site, Colorado

    International Nuclear Information System (INIS)

    Earman, S.; Chapman, J.; Andricevic, R.

    1996-09-01

    The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Rulison site in west-central Colorado was the location of an underground detonation of a 40-kiloton nuclear device in 1969. The test took place 2,568 m below ground surface in the Mesaverde Formation. Though located below the regional water table, none of the bedrock formations at the site yielded water during hydraulic tests, indicating extremely low permeability conditions. The scenario evaluated was the migration of radionuclides from the blast-created cavity through the Mesaverde Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity and the correlation scale of hydraulic conductivity, with transport of strontium and cesium also sensitive to the sorption coefficient

  8. Revised estimates of the radiological impact of the transport of irradiated nuclear fuels within the UK

    International Nuclear Information System (INIS)

    Macdonald, H.F.

    1987-10-01

    This report presents revised estimates of individual and collective doses associated with irradiated fuel movements from CEGB and SSEB nuclear power stations within the UK. In particular, earlier estimates of transport doses have been updated to take account of recent changes in the patterns of rail traffic. This results in a reduction in the estimated maximum individual doses to members of the public living near marshalling yards where flasks stop en route and also to rail workers incidentally exposed at these locations. The maximum levels of individual dose associated with irradiated fuel transport within the UK are in general low compared with those due to natural background radiation. Further, the associated collective doses are small compared with other sources of dose arising in the nuclear fuel cycle and represent -4 % of the natural background radiation dose to the UK population. In absolute terms the maximum contributions to the annual transport collective doses from Magnox, AGR and projected PWR fuel movements are estimated to be 18, 9 and 0.7 man mSv · a -1 respectively. These results neglect any reduction in doses due to the effects of shielding by buildings or natural obstacles such as railway cuttings or tunnels. Inclusion of these effects has been estimated to reduce the annual transport collective doses to 13, 6 and 0.45 man mSv · a -1 for Magnox, AGR and PWR fuels respectively. (U.K.)

  9. Heat, mass, and momentum transport model for hydrogen diffusion flames in nuclear reactor containments

    International Nuclear Information System (INIS)

    Travis, J.R.

    1985-01-01

    It is now possible to analyze the time-dependent, fully three-dimensional behavior of hydrogen diffusion flames in nuclear reactor containments. This analysis involves coupling the full Navier-Stokes equations with multi-species transport to the global chemical kinetics of hydrogen combustion. A transport equation for the subgrid scale turbulent kinetic energy density is solved to produce the time and space dependent turbulent transport coefficients. The heat transfer coefficient governing the exchange of heat between fluid computational cells adjacent to wall cells is calculated by a modified Reynolds analogy formulation. The analysis of a MARK-III containment indicates very complex flow patterns that greatly influence fluid and wall temperatures and heat fluxes. 18 refs., 24 figs

  10. Method to develop data supporting consequence analyses of transporting nuclear materials in the United States

    International Nuclear Information System (INIS)

    Reese, R.T.; Sandoval, R.P.

    1980-01-01

    The Transportation System Safety Evaluation (TSSE) program at Sandia National Laboratories' Transportation Technology Center was initiated to provide the necessary information on source terms for nuclear materials subjected to extreme environments. The techniques for derivation of source terms for the fuel alone has been described as well as the outline for package response. An additional facet of this problem is the development of analytical methods to describe the transport of the released radionuclides from the fuel rods to possible release points. This work is also covered in the TSSE program. Not all the work required will be performed or funded by Sandia; rather existing work will be sought out and ongoing work will be utilized in an attempt to unify the presentation of data and thus increase its usefulness

  11. NFκBP65 transcription factor modulates resistance to doxorubicin through ABC transporters in breast cancer.

    Science.gov (United States)

    Velaei, Kobra; Samadi, Nasser; Soltani, Sina; Barazvan, Balal; Soleimani Rad, Jafar

    2017-07-01

    Shedding light on chemoresistance biology of breast cancer could contribute to enhance the clinical outcome. Intrinsic or acquired resistance to chemotherapy is a major problem in breast cancer treatment. The NFκB pathway by siRNAP65 and JSH-23 as a translocational inhibitor of NFκBP65 in the doxorubicin-resistant MCF-7 (MCF-7/Dox) and MCF-7 cells was blocked. Then, the ABC transporter expression and function were assessed by real-time qRT-PCR and flow cytometry, respectively. Induction of apoptosis was evaluated after inhibition of the NFΚB pathway as well. Our study underlined the upregulation of NFκBP65 and anti-apoptotic Bcl-2 and downregulation of pro-apoptotic Bax in the MCF-7/Dox cells compared with control MCF-7 cells. Here, we showed that interplay between nuclear factor kappa B P65 (NFkBP65) as a transcriptional regulator and ABC transporters in the MCF-7/Dox cancer cells. We found that inhibition of the elevated expression of NFκBP65 in the resistant breast cancer, whether translocational inhibition or silencing by siRNA, decreased the expression and function of MDR1 and MRP1 efflux pumps. Furthermore, the blockade of NFκBP65 promoted apoptosis via modulating Bcl-2 and BAX expression. After inhibition of the NFκBP65 signaling pathway, elevated baseline expression of survival Bcl-2 gene in the resistant breast cells significantly decreased. Suppression of the NFκB pathway has a profound dual impact on promoting the intrinsic apoptotic pathway and reducing ABC transporter function and expression, which are some of the chemoresistance features. It was speculated that the NFκB pathway directly acts on doxorubicin-induced MDR1 and MRP1 expression in MCF-7/Dox cells.

  12. Land and Water Use, CO2 Emissions, and Worker Radiological Exposure Factors for the Nuclear Fuel Cycle

    Energy Technology Data Exchange (ETDEWEB)

    Brett W Carlsen; Brent W Dixon; Urairisa Pathanapirom; Eric Schneider; Bethany L. Smith; Timothy M. AUlt; Allen G. Croff; Steven L. Krahn

    2013-08-01

    The Department of Energy Office of Nuclear Energy’s Fuel Cycle Technologies program is preparing to evaluate several proposed nuclear fuel cycle options to help guide and prioritize Fuel Cycle Technology research and development. Metrics are being developed to assess performance against nine evaluation criteria that will be used to assess relevant impacts resulting from all phases of the fuel cycle. This report focuses on four specific environmental metrics. • land use • water use • CO2 emissions • radiological Dose to workers Impacts associated with the processes in the front-end of the nuclear fuel cycle, mining through enrichment and deconversion of DUF6 are summarized from FCRD-FCO-2012-000124, Revision 1. Impact estimates are developed within this report for the remaining phases of the nuclear fuel cycle. These phases include fuel fabrication, reactor construction and operations, fuel reprocessing, and storage, transport, and disposal of associated used fuel and radioactive wastes. Impact estimates for each of the phases of the nuclear fuel cycle are given as impact factors normalized per unit process throughput or output. These impact factors can then be re-scaled against the appropriate mass flows to provide estimates for a wide range of potential fuel cycles. A companion report, FCRD-FCO-2013-000213, applies the impact factors to estimate and provide a comparative evaluation of 40 fuel cycles under consideration relative to these four environmental metrics.

  13. Assessment of hydrologic transport of radionuclides from the Rio Blanco underground nuclear test site, Colorado

    International Nuclear Information System (INIS)

    Chapman, J.; Earman, S.; Andricevic, R.

    1996-10-01

    DOE is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations used for nuclear testing. Evaluation of radionuclide transport by groundwater is part of preliminary risk analysis. These evaluations allow prioritization of test areas in terms of risk, provide a basis for discussions with regulators and the public about future work, and provide a framework for assessing site characterization data needs. The Rio Blanco site in Colorado was the location of the simultaneous detonation of three 30-kiloton nuclear devices. The devices were located 1780, 1899, and 2039 below ground surface in the Fort Union and Mesaverde formations. Although all the bedrock formations at the site are thought to contain water, those below the Green River Formation (below 1000 in depth) are also gas-bearing, and have very low permeabilities. The transport scenario evaluated was the migration of radionuclides from the blast-created cavity through the Fort Union Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. This modeling was performed to investigate how the uncertainty in various physical parameters affect radionuclide transport at the site, and to serve as a starting point for discussion regarding further investigation; it was not intended to be a definitive simulation of migration pathways or radionuclide concentration values. Given the sparse data, the modeling results may differ significantly from reality. Confidence in transport predictions can be increased by obtaining more site data, including the amount of radionuclides which would have been available for transport (i.e., not trapped in melt glass or vented during gas flow testing), and the hydraulic properties of the formation. 38 refs., 6 figs., 1 tab

  14. Environmental Baseline File National Transportation

    International Nuclear Information System (INIS)

    Harris, M.

    1999-01-01

    This Environmental Baseline File summarizes and consolidates information related to the national-level transportation of commercial spent nuclear fuel. Topics addressed include: shipments of commercial spent nuclear fuel based on mostly truck and mostly rail shipping scenarios; transportation routing for commercial spent nuclear fuel sites and DOE sites; radionuclide inventories for various shipping container capacities; transportation routing; populations along transportation routes; urbanized area population densities; the impacts of historical, reasonably foreseeable, and general transportation; state-level food transfer factors; Federal Guidance Report No. 11 and 12 radionuclide dose conversion factors; and national average atmospheric conditions

  15. Some factors affecting radiative heat transport in PWR cores

    International Nuclear Information System (INIS)

    Hall, A.N.

    1989-04-01

    This report discusses radiative heat transport in Pressurized Water Reactor cores, using simple models to illustrate basic features of the transport process. Heat transport by conduction and convection is ignored in order to focus attention on the restrictions on radiative heat transport imposed by the geometry of the heat emitting and absorbing structures. The importance of the spacing of the emitting and absorbing structures is emphasised. Steady state temperature distributions are found for models of cores which are uniformly heated by fission product decay. In all of the models, a steady state temperature distribution can only be obtained if the central core temperature is in excess of the melting point of UO 2 . It has recently been reported that the MIMAS computer code, which takes into account radiative heat transport, has been used to model the heat-up of the Three Mile Island-2 reactor core, and the computations indicate that the core could not have reached the melting point of UO 2 at any time or any place. We discuss this result in the light of the calculations presented in this paper. It appears that the predicted stabilisation of the core temperatures at ∼ 2200 0 C may be a consequence of the artificially large spacing between the radial rings employed in the MIMAS code, rather than a result of physical significance. (author)

  16. Factors relevant to the sealing of nuclear facilities

    International Nuclear Information System (INIS)

    1991-05-01

    This report reviews and summaries the factors to be considered in the design, construction and surveillance of confinement structures for damaged nuclear facilities. General engineering, design and environmental considerations are included, both from the standpoint of the mitigation of near-term effects by virtue of interim confinement, and from the standpoint of the acceptability of the structure for long-term confinement. Factors which influence optimization of the design and the construction sequence are reviewed, including the nature of the accident, natural conditions of the site, and thermal and radiation effects. Safety criteria are presented from the standpoint of regulatory requirements, radiological consequences, and monitoring/surveillance requirements for both interim and long-term confinement. Methodologies related to concrete fabrication technology and other construction techniques appropriate for building confinement structures are discussed. Long-term considerations relative to the future of the site for in-place storage/disposal of the waste, and possible future reuse of the site are also included

  17. Study on the factors affecting the quality of public bus transportation service in Bali Province using factor analysis

    Science.gov (United States)

    Susilawati, M.; Nilakusmawati, D. P. E.

    2017-06-01

    The volume of mobility flows are increasing day by day and the condition of the number of people using private transport modes contribute to traffic congestion. With the limited capacity of the road, one of the alternatives solution to reduce congestion is to optimize the use of public transport. The purposes of this study are to determine the factors that influence user’s satisfaction on the quality of public bus transportation service and determine variables that became identifier on the dominant factor affecting user’s satisfaction. The study was conducted for the public bus transportation between districts in the province of Bali, which is among the eight regencies and one municipality, using a questionnaire as a data collection instrument. Service variables determinant of user’s satisfaction in this study, described in 25 questions, which were analyzed using factor analysis. The results showed there were six factors that explain the satisfaction of users of public transport in Bali, with a total diversity of data that can be parsed by 61.436%. These factors are: Safety and comfort, Responsiveness, Capacity, Tangible, Safety, Reliability. The dominant factor affecting public transport user satisfaction is the safety and comfort, with the most influential variable is feeling concerned about the personal safety of users when on the bus.

  18. Transport of radioactive materials on public roads - with regard to the authorizations granted to the Nuclear Center

    International Nuclear Information System (INIS)

    Berger, H.U.

    1992-10-01

    This report shall be a help for scientific and technical personal of the nuclear research center in the choice of the modalities of the transport of radioactive materials on public roads in accordance to regulations and authorizations. Not only the atomic law, the radiation protection ordinance and the ordinance on dangerous goods on roads, which are binding in any case, are regarded in this report but also as the scope and the impositions of the transport authorization of the nuclear research center as the internal instructions of the nuclear research center. With regard to the transport of nuclear fuel material only the cases of transport exempted of authorization and transport of such kinds waste containing nuclear fuel material treated where the waste has a density at most of 15g/cm 3 or where the package contains at most 15g of nuclear fuel material. The reader is guided by dialogue (pretty much as a book for' programmed learning') to the solution of his special problem of transport. In order to narrow down the size of this report, all technical or administrative details are treated in 11 brochures, which are published as technical supplements of this report. These supplements are available on request. (orig.) [de

  19. Characterization of germ cell-specific expression of the orphan nuclear receptor, germ cell nuclear factor.

    Science.gov (United States)

    Katz, D; Niederberger, C; Slaughter, G R; Cooney, A J

    1997-10-01

    Nuclear receptors, such as those for androgens, estrogens, and progesterones, control many reproductive processes. Proteins with structures similar to these receptors, but for which ligands have not yet been identified, have been termed orphan nuclear receptors. One of these orphans, germ cell nuclear factor (GCNF), has been shown to be germ cell specific in the adult and, therefore, may also participate in the regulation of reproductive functions. In this paper, we examine more closely the expression patterns of GCNF in germ cells to begin to define spatio-temporal domains of its activity. In situ hybridization showed that GCNF messenger RNA (mRNA) is lacking in the testis of hypogonadal mutant mice, which lack developed spermatids, but is present in the wild-type testis. Thus, GCNF is, indeed, germ cell specific in the adult male. Quantitation of the specific in situ hybridization signal in wild-type testis reveals that GCNF mRNA is most abundant in stage VII round spermatids. Similarly, Northern analysis and specific in situ hybridization show that GCNF expression first occurs in testis of 20-day-old mice, when round spermatids first emerge. Therefore, in the male, GCNF expression occurs postmeiotically and may participate in the morphological changes of the maturing spermatids. In contrast, female expression of GCNF is shown in growing oocytes that have not completed the first meiotic division. Thus, GCNF in the female is expressed before the completion of meiosis. Finally, the nature of the two different mRNAs that hybridize to the GCNF complementary DNA was studied. Although both messages contain the DNA binding domain, only the larger message is recognized by a probe from the extreme 3' untranslated region. In situ hybridization with these differential probes demonstrates that both messages are present in growing oocytes. In addition, the coding region and portions of the 3' untranslated region of the GCNF complementary DNA are conserved in the rat.

  20. Chemical factors affecting fission product transport in severe LMFBR accidents

    International Nuclear Information System (INIS)

    Wichner, R.P.; Jolley, R.L.; Gat, U.; Rodgers, B.R.

    1984-10-01

    This study was performed as a part of a larger evaluation effort on LMFBR accident, source-term estimation. Purpose was to provide basic chemical information regarding fission product, sodium coolant, and structural material interactions required to perform estimation of fission product transport under LMFBR accident conditions. Emphasis was placed on conditions within the reactor vessel; containment vessel conditions are discussed only briefly

  1. Cytokinin response factors regulate PIN-FORMED auxin transporters

    Czech Academy of Sciences Publication Activity Database

    Šimášková, M.; O'Brien, J.A.; Khan, M.; Van Noorden, G.; Ötvös, K.; Vieten, A.; De Clercq, E.; Van Haperen, J.M.A.; Cuesta, C.; Hoyerová, Klára; Vanneste, S.; Marhavý, P.; Wabnik, K.; Van Breusegem, F.; Nowack, M.; Murphy, A.; Friml, J.; Weijers, D.; Beeckman, T.; Benková, E.

    2015-01-01

    Roč. 6, NOV (2015), s. 8717 ISSN 2041-1723 Institutional support: RVO:61389030 Keywords : ARABIDOPSIS -THALIANA * ROOT-MERISTEM * TRANSCRIPTION FACTORS Subject RIV: ED - Physiology Impact factor: 11.329, year: 2015

  2. Transportation Energy Futures Series: Effects of the Built Environment on Transportation: Energy Use, Greenhouse Gas Emissions, and Other Factors

    Energy Technology Data Exchange (ETDEWEB)

    Porter, C. D.; Brown, A.; Dunphy, R. T.; Vimmerstedt, L.

    2013-03-01

    Planning initiatives in many regions and communities aim to reduce transportation energy use, decrease emissions, and achieve related environmental benefits by changing land use. This report reviews and summarizes findings from existing literature on the relationship between the built environment and transportation energy use and greenhouse gas emissions, identifying results trends as well as potential future actions. The indirect influence of federal transportation and housing policies, as well as the direct impact of municipal regulation on land use are examined for their effect on transportation patterns and energy use. Special attention is given to the 'four D' factors of density, diversity, design and accessibility. The report concludes that policy-driven changes to the built environment could reduce transportation energy and GHG emissions from less than 1% to as much as 10% by 2050, the equivalent of 16%-18% of present-day urban light-duty-vehicle travel. This is one of a series of reports produced as a result of the Transportation Energy Futures (TEF) project, a Department of Energy-sponsored multi-agency project initiated to pinpoint underexplored strategies for abating GHGs and reducing petroleum dependence related to transportation.

  3. Transportation Energy Futures Series. Effects of the Built Environment on Transportation. Energy Use, Greenhouse Gas Emissions, and Other Factors

    Energy Technology Data Exchange (ETDEWEB)

    Porter, C. D. [National Renewable Energy Lab. (NREL) and Cambridge Systematics, Inc., Golden, CO (United States); Brown, A. [National Renewable Energy Lab. (NREL) and Cambridge Systematics, Inc., Golden, CO (United States); Dunphy, R. T. [National Renewable Energy Lab. (NREL) and Cambridge Systematics, Inc., Golden, CO (United States); Vimmerstedt, L. [National Renewable Energy Lab. (NREL) and Cambridge Systematics, Inc., Golden, CO (United States)

    2013-03-15

    Planning initiatives in many regions and communities aim to reduce transportation energy use, decrease emissions, and achieve related environmental benefits by changing land use. This report reviews and summarizes findings from existing literature on the relationship between the built environment and transportation energy use and greenhouse gas emissions, identifying results trends as well as potential future actions. The indirect influence of federal transportation and housing policies, as well as the direct impact of municipal regulation on land use are examined for their effect on transportation patterns and energy use. Special attention is given to the 'four D' factors of density, diversity, design and accessibility. The report concludes that policy-driven changes to the built environment could reduce transportation energy and GHG emissions from less than 1% to as much as 10% by 2050, the equivalent of 16%-18% of present-day urban light-duty-vehicle travel. This is one of a series of reports produced as a result of the Transportation Energy Futures (TEF) project, a Department of Energy-sponsored multi-agency project initiated to pinpoint underexplored strategies for abating GHGs and reducing petroleum dependence related to transportation.

  4. Experiences in certification of packages for transportation of fresh nuclear fuel in the context of new safety requirements established by IAEA regulations (IAEA-96 regulations, ST-1) for air transportation of nuclear materials (requirements to C-type packages)

    Energy Technology Data Exchange (ETDEWEB)

    Dudai, V.I.; Kovtun, A.D.; Matveev, V.Z.; Morenko, A.I.; Nilulin, V.M.; Shapovalov, V.I.; Yakushev, V.A.; Bobrovsky, V.S.; Rozhkov, V.V.; Agapov, A.M.; Kolesnikov, A.S. [Russian Federal Nuclear Centre - All-Russian Research Inst. of Experimental Physics, Sarov (Russian Federation)]|[JSC ' ' MSZ' ' , Electrostal (Russian Federation)]|[JSC ' ' NPCC' ' , Novosibirsk (Russian Federation)]|[Minatom of Russia, Moscow (Russian Federation)]|[Gosatomnadzor of Russia, Moscow (Russian Federation)

    2004-07-01

    Every year in Russia, a large amount of domestic and international transportation of fresh nuclear fuel (FNF) used in Russian and foreign energy and research atomic reactors and referred to fissile materials based on IAEA Regulations is performed. Here, bulk transportation is performed by air, and it concerns international transportation in particular. According to national ''Main Regulations for Safe Transport and physical Protection of Nuclear Materials (OPBZ- 83)'' and ''Regulations for the Safe Transport of Radioactive Materials'' of the International Atomic Energy Agency (IAEA Regulations), nuclear and radiation security under normal (accident free) and accident conditions of transport must be completely provided by the package design. In this context, high requirements to fissile packages exposed to heat and mechanical loads in transport accidents are imposed. A long-standing experience in accident free transportation of FM has shown that such approach to provide nuclear and radiation security pays for itself completely. Nevertheless, once in 10 years the International Atomic Energy Agency on every revision of the ''Regulations for the Safe Transport of Radioactive Materials'' places more stringent requirements upon the FM and transportation thereof, resulting from the objectively increasing risk associated with constant rise in volume and density of transportation, and also strained social and economical situation in a number of regions in the world. In the new edition of the IAEA Regulations (ST-1), published in 1996 and brought into force in 2001 (IAEA-96 Regulations), the requirements to FM packages conveyed by aircraft were radically changed. These requirements are completely presented in new Russian ''Regulations for the Safe Transport of Radioactive Materials'' (PBTRM- 2004) which will be brought into force in the time ahead.

  5. The contribution of human factors to risks from radioactive material transport

    International Nuclear Information System (INIS)

    Blenkin, J.J.; Ridsdale, E.; Wilkinson, H.L.

    1998-01-01

    The use of probabilistic risk assessment to assess the safety of radioactive material transport operations is well accepted. However, quantitative risk assessment of radioactive material transport operations have generally not explicitly considered human factors in estimating risks. Given the high profile of human factors as the root cause of many serious transport incidents omission of an explicit consideration of human factors in a risk assessment could lead to assessments losing credibility. In addition, scrutiny of radioactive material transport incident databases reveals a large number of operational incidents and minor accidents that would have been avoided if more attention had been paid to human factors aspects, and provides examples of instances where improvements have been achieved. This paper examines the areas of radioactive material transport risk assessments (both qualitative and quantitative) which could be strengthened by further examination of the impact of human errors. It is concluded that a more complete and detailed understanding of the effects of human factors on the risks from radioactive material transport operations has been obtained. Quality assurance has a key part to play in ensuring that packages are correctly manufactured and prepared for transport. Risk assessments of radioactive material transport operations can be strengthened by concentrating on the key human factors effects. (authors)

  6. Beznau nuclear power plant: comments of the Federal Department of Transport, Communications and Energy on the reproaches of Greenpeace

    International Nuclear Information System (INIS)

    Ogi, A.

    1995-01-01

    Answer of the chairman of the EVED (Federal Department of Transport, Communications and Energy) to the open letter in which Greenpeace Switzerland made massive accusations against the nuclear power plant Beznau and the HSK (Federal Nuclear Safety Inspectorate). All the charges are rebutted in this answer

  7. Bim nuclear translocation and inactivation by viral interferon regulatory factor.

    Directory of Open Access Journals (Sweden)

    Young Bong Choi

    2010-08-01

    Full Text Available Viral replication efficiency is in large part governed by the ability of viruses to counteract pro-apoptotic signals induced by infection of the host cell. Human herpesvirus 8 (HHV-8 uses several strategies to block the host's innate antiviral defenses via interference with interferon and apoptotic signaling. Contributors include the four viral interferon regulatory factors (vIRFs 1-4, which function in dominant negative fashion to block cellular IRF activities in addition to targeting IRF signaling-induced proteins such as p53 and inhibiting other inducers of apoptosis such as TGFbeta receptor-activated Smad transcription factors. Here we identify direct targeting by vIRF-1 of BH3-only pro-apoptotic Bcl-2 family member Bim, a key negative regulator of HHV-8 replication, to effect its inactivation via nuclear translocation. vIRF-1-mediated relocalization of Bim was identified in transfected cells, by both immunofluorescence assay and western analysis of fractionated cell extracts. Also, co-localization of vIRF-1 and Bim was detected in nuclei of lytically infected endothelial cells. In vitro co-precipitation assays using purified vIRF-1 and Bim revealed direct interaction between the proteins, and Bim-binding residues of vIRF-1 were mapped by deletion and point mutagenesis. Generation and experimental utilization of Bim-refractory vIRF-1 variants revealed the importance of vIRF-1:Bim interaction, specifically, in pro-replication and anti-apoptotic activity of vIRF-1. Furthermore, blocking of the interaction with cell-permeable peptide corresponding to the Bim-binding region of vIRF-1 confirmed the relevance of vIRF-1:Bim association to vIRF-1 pro-replication activity. To our knowledge, this is the first report of an IRF protein that interacts with a Bcl-2 family member and of nuclear sequestration of Bim or any other member of the family as a means of inactivation. The data presented reveal a novel mechanism utilized by a virus to control

  8. A TRANSPORTATION RISK ASSESSMENT TOOL FOR ANALYZING THE TRANSPORT OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE TO THE PROPOSED YUCCA MOUNTAIN REPOSITORY

    International Nuclear Information System (INIS)

    2001-01-01

    The Yucca Mountain Draft Environmental Impact Statement (DEIS) analysis addressed the potential for transporting spent nuclear fuel and high-level radioactive waste from 77 origins for 34 types of spent fuel and high-level radioactive waste, 49,914 legal weight truck shipments, and 10,911 rail shipments. The analysis evaluated transportation over 59,250 unique shipment links for travel outside Nevada (shipment segments in urban, suburban or rural zones by state), and 22,611 links in Nevada. In addition, the analysis modeled the behavior of 41 isotopes, 1091 source terms, and used 8850 food transfer factors (distinct factors by isotope for each state). The analysis also used mode-specific accident rates for legal weight truck, rail, and heavy haul truck by state, and barge by waterway. This complex mix of data and information required an innovative approach to assess the transportation impacts. The approach employed a Microsoft(reg s ign) Access database tool that incorporated data from many sources, including unit risk factors calculated using the RADTRAN IV transportation risk assessment computer program. Using Microsoft(reg s ign) Access, the analysts organized data (such as state-specific accident and fatality rates) into tables and developed queries to obtain the overall transportation impacts. Queries are instructions to the database describing how to use data contained in the database tables. While a query might be applied to thousands of table entries, there is only one sequence of queries that is used to calculate a particular transportation impact. For example, the incident-free dose to off-link populations in a state is calculated by a query that uses route segment lengths for each route in a state that could be used by shipments, populations for each segment, number of shipments on each segment, and an incident-free unit risk factor calculated using RADTRAN IV. In addition to providing a method for using large volumes of data in the calculations, the

  9. Recommended nuclear criticality safety experiments in support of the safe transportation of fissile material

    International Nuclear Information System (INIS)

    Tollefson, D.A.; Elliott, E.P.; Dyer, H.R.; Thompson, S.A.

    1993-01-01

    Validation of computer codes and nuclear data (cross-section) libraries using benchmark quality critical (or certain subcritical) experiments is an essential part of a nuclear criticality safety evaluation. The validation results establish the credibility of the calculational tools for use in evaluating a particular application. Validation of the calculational tools is addressed in several American National Standards Institute/American Nuclear Society (ANSI/ANS) standards, with ANSI/ANS-8.1 being the most relevant. Documentation of the validation is a required part of all safety analyses involving significant quantities of fissile materials. In the case of transportation of fissile materials, the safety analysis report for packaging (SARP) must contain a thorough discussion of benchmark experiments, detailing how the experiments relate to the significant packaging and contents materials (fissile, moderating, neutron absorbing) within the package. The experiments recommended in this paper are needed to address certain areas related to transportation of unirradiated fissile materials in drum-type containers (packagings) for which current data are inadequate or are lacking

  10. Plasticity of an ultrafast interaction between nucleoporins and nuclear transport receptors.

    Science.gov (United States)

    Milles, Sigrid; Mercadante, Davide; Aramburu, Iker Valle; Jensen, Malene Ringkjøbing; Banterle, Niccolò; Koehler, Christine; Tyagi, Swati; Clarke, Jane; Shammas, Sarah L; Blackledge, Martin; Gräter, Frauke; Lemke, Edward A

    2015-10-22

    The mechanisms by which intrinsically disordered proteins engage in rapid and highly selective binding is a subject of considerable interest and represents a central paradigm to nuclear pore complex (NPC) function, where nuclear transport receptors (NTRs) move through the NPC by binding disordered phenylalanine-glycine-rich nucleoporins (FG-Nups). Combining single-molecule fluorescence, molecular simulations, and nuclear magnetic resonance, we show that a rapidly fluctuating FG-Nup populates an ensemble of conformations that are prone to bind NTRs with near diffusion-limited on rates, as shown by stopped-flow kinetic measurements. This is achieved using multiple, minimalistic, low-affinity binding motifs that are in rapid exchange when engaging with the NTR, allowing the FG-Nup to maintain an unexpectedly high plasticity in its bound state. We propose that these exceptional physical characteristics enable a rapid and specific transport mechanism in the physiological context, a notion supported by single molecule in-cell assays on intact NPCs. Copyright © 2015 The Authors. Published by Elsevier Inc. All rights reserved.

  11. Analysis of the risk of transporting spent nuclear fuel by train

    Energy Technology Data Exchange (ETDEWEB)

    Elder, H.K.

    1981-09-01

    This report uses risk analyses to analyze the safety of transporting spent nuclear fuel for commercial rail shipping systems. The rail systems analyzed are those expected to be used in the United States when the total electricity-generating capacity by nuclear reactors is 100 GW in the late 1980s. Risk as used in this report is the product of the probability of a release of material to the environment and the consequences resulting from the release. The analysis includes risks in terms of expected fatalities from release of radioactive materials due to transportation accidents involving PWR spent fuel shipped in rail casks. The expected total risk from such shipments is 1.3 x 10/sup -4/ fatalities per year. Risk spectrums are developed for shipments of spent fuel that are 180 days and 4 years out-of-reactor. The risk from transporting spent fuel by train is much less (by 2 to 4 orders of magnitude) than the risk to society from other man-caused events such as dam failure.

  12. Characterization of a baculovirus nuclear localization signal domain in the late expression factor 3 protein

    International Nuclear Information System (INIS)

    Au, Victoria; Yu Mei; Carstens, Eric B.

    2009-01-01

    The baculovirus Autographa californica multicapsid nucleopolyhedrovirus (AcMNPV) single-stranded DNA binding protein LEF-3 is a multi-functional protein that is required to transport the helicase protein P143 into the nucleus of infected cells where they function to replicate viral DNA. The N-terminal 56 amino acid region of LEF-3 is required for nuclear transport. In this report, we analyzed the effect of site-specific mutagenesis of LEF-3 on its intracellular distribution. Fluorescence microscopy of expression plasmid-transfected cells demonstrated that the residues 28 to 32 formed the core nuclear localization signal, but other adjacent positively-charged residues augmented these sequences. Comparison with other group I Alphabaculoviruses suggested that this core region functionally duplicated residues including 18 and 19. This was demonstrated by the loss of nuclear localization when the equivalent residues (18 to 20) in Choristoneura fumiferana nucleopolyhedrovirus (CfMNPV) LEF-3 were mutated. The AcMNPV LEF-3 nuclear localization domain was also shown to drive nuclear transport in mammalian cells indicating that the protein nuclear import systems in insect and mammalian cells are conserved. We also demonstrated by mutagenesis that two conserved cysteine residues located at 82 and 106 were not essential for nuclear localization or for interaction with P143. However, by using a modified construct of P143 that localized on its own to the nucleus, we demonstrated that a functional nuclear localization domain on LEF-3 was required for interaction between LEF-3 and P143

  13. A nuclear free southeast Asia - the China factor

    International Nuclear Information System (INIS)

    Malik, J.M.

    1989-01-01

    It is estimated that the principal nuclear threat to Southeast Asia comes from nuclear weapons stored by the two superpowers in their respective bases and their targeting of each other's bases. Calls for the creation of a nuclear weapons free zone in Southeast Asia (SEANFZ) poses a number of problems to China because of the perceived negative impact of such zones on Chinese security interests, force deployment and strategic doctrine. Hence, it is argued that China is unlikely to support a nuclear free zone treaty which only embraces the Asean states because it would lead to unilateral disarmament on the part of pro-western countries while leaving Indochinese states and the Soviet Union. However, if the proposed SEANFZ treaty resembles the South Pacific Nuclear Free Zone treaty, which allow the transit of nuclear-armed vessels, China could be expected to support it. ills

  14. Factors affecting nuclear research reactor utilization across countries

    International Nuclear Information System (INIS)

    Hien, P.D.

    2000-01-01

    In view of the worldwide declining trend of research reactor utilization and the fact that many reactors in developing countries are under-utilised, a question naturally arises as to whether the investment in a research reactor is justifiable. Statistical analyses were applied to reveal relationships between the status of reactor utilization and socio-economic conditions among countries, that may provide a guidance for reactor planning and cost benefit assessment. The reactor power has significant regression relationships with size indicators such as GNP, electricity consumption and R and D expenditure. Concerning the effectiveness of investment in research reactors, the number of reactor operation days per year only weakly correlates with electricity consumption and R and D expenditure, implying that there are controlling factors specific of each group of countries. In the case of less developed countries, the low customer demands on reactor operation may be associated with the failure in achieving quality assurance for the reactor products and services, inadequate investment in the infrastructure for reactor exploitation, the shortage of R and D funding and well trained manpower and the lack of measures to get the scientific community involved in the application of nuclear techniques. (author)

  15. The human factors specialist in nuclear control centre design

    International Nuclear Information System (INIS)

    Wilson, R.B.; Beattie, J.D.

    The main focus at Ontario Hydro for man-machine interface design is in the design of control centres. Because the control of a nuclear generating unit is highly centralized there is an increasing need for effective information display and control layout. Control panel design innovations such as the use of CRT displays and the extended use of computerized control in the Darlington station have made it possible for Ontario Hydro to continue to have one first operator for each generating unit. The human factors specialist involved in control panel design must deal with people who know much more about the specific systems being controlled, and must become a generalist in all these systems as well. Designers have to use conceptual techniques such as task analysis, systems design, panel mock-ups, anthropometric data, and personal judgement based on experience as they design panels. They must find a balance between becoming locked into existing technology and methods, slavishly following the latest technological trends, and forgetting that real people will be using what they design

  16. System of large transport containers for waste from dismantling light water and gas-cooled nuclear reactors. Volume 2

    International Nuclear Information System (INIS)

    Price, M.S.T.

    1986-09-01

    This report deals with the operational, radiological and economic aspects of transport as well as conceptual designs of large containers for the transport of radioactive decommissioning wastes from nuclear power plants within the member states of the European Economic Community. The means of transport, the costs and radiological detriment are considered, and conceptual designs of containers are described. Recommendations are made for further studies. (U.K.)

  17. The human factor in the operation of nuclear powered submarines

    International Nuclear Information System (INIS)

    Dambier, M.

    1982-05-01

    The conditions characterizing the operation of nuclear powered submarines are described and the precautionary measures suitable to reduce the incidence of human errors and their consequences are explained

  18. Calculation of health risks from spent-nuclear-fuel transportation accidents

    International Nuclear Information System (INIS)

    Chen, S.Y.; Yuan, Y.C.

    1987-01-01

    Models developed to analyze potential radiological health risks from various accident scenarios during transportation of spent nuclear fuels are described. The models are designed both for detailed route-specific risk analyses and for use in conducting overall risk analyses for route selection and related decision-making activities. The radiological risks calculated include individual dose commitments, collective dose commitments, and long-term (100-year) environmental dose commitments to a population following release of radioactivity. To facilitate route-specific analysis, a state-level database was developed and incorporated into the model. Route-specific analysis is demonstrated by the calculation of radiological risks resulting from various accident scenarios, as postulated by the recent US Nuclear Regulatory Commission Modal Study, for four representative states selected from various regions of the United States. 10 refs., 3 figs., 3 tabs

  19. Spent Nuclear Fuel Transportation: An Examination of Potential Lessons Learned From Prior Shipping Campaigns

    International Nuclear Information System (INIS)

    M. Keister; K, McBride

    2006-01-01

    The Nuclear Waste Policy Act of 1982 (NWPA), as amended, assigned the Department of Energy (DOE) responsibility for developing and managing a Federal system for the disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for accepting, transporting, and disposing of SNF and HLW at the Yucca Mountain repository (if licensed) in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence. OCRWM faces a near-term challenge--to develop and demonstrate a transportation system that will sustain safe and efficient shipments of SNF and HLW to a repository. To better inform and improve its current planning, OCRWM has extensively reviewed plans and other documents related to past high-visibility shipping campaigns of SNF and other radioactive materials within the United States. This report summarizes the results of this review and, where appropriate, lessons learned. The objective of this lessons learned study was to identify successful, best-in-class trends and commonalities from past shipping campaigns, which OCRWM could consider when planning for the development and operation of a repository transportation system. Note: this paper is for analytical and discussion purposes only, and is not an endorsement of, or commitment by, OCRWM to follow any of the comments or trends. If OCRWM elects to make such commitments at a future time, they will be appropriately documented in formal programmatic policy statements, plans and procedures. Reviewers examined an extensive study completed in 2003 by DOE's National Transportation Program (NTP), Office of Environmental Management (EM), as well as plans and documents related to SNF shipments since issuance of the NTP report. OCRWM examined specific planning, business, institutional and operating practices that have been identified by DOE, its transportation contractors

  20. Assessment of hydrologic transport of radionuclides from the Gnome underground nuclear test site, New Mexico

    International Nuclear Information System (INIS)

    Earman, S.; Chapman, J.; Pohlmann, K.; Andricevic, R.

    1996-09-01

    The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary site risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Gnome site in southeastern New Mexico was the location of an underground detonation of a 3.5-kiloton nuclear device in 1961, and a hydrologic tracer test using radionuclides in 1963. The tracer test involved the injection of tritium, 90 Sr, and 137 Cs directly into the Culebra Dolomite, a nine to ten-meter-thick aquifer located approximately 150 in below land surface. The Gnome nuclear test was carried out in the Salado Formation, a thick salt deposit located 200 in below the Culebra. Because salt behaves plastically, the cavity created by the explosion is expected to close, and although there is no evidence that migration has actually occurred, it is assumed that radionuclides from the cavity are released into the overlying Culebra Dolomite during this closure process. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides may be present in concentrations exceeding drinking water regulations outside the drilling exclusion boundary established by DOE. Calculated mean tritium concentrations peak at values exceeding the U.S. Environmental Protection Agency drinking water standard of 20,000 pCi/L at distances of up to almost eight kilometers west of the nuclear test

  1. Stochastic modelling of fusion-product transport and thermalization with nuclear elastic scattering

    International Nuclear Information System (INIS)

    Deveaux, J.C.

    1983-01-01

    Monte Carlo methods are developed to model fusion-product (fp) transport and thermalization with both Rutherford scattering and nuclear elastic scattering (NES) in high-temperature (T/sub i/, T/sub e-/ > 50 keV), advanced-fuel (e.g. Cat-D, D- 3 He) plasmas. A discrete-event model is used to superimpose NES collisions on a Rutherford scattering model that contains the Spitzer coefficients of drag, velocity diffusion (VD), and pith-angle scattering (PAS). The effects of NES on fp transport and thermalization are investigated for advanced-fuel, Field-Reversed Mirror (FRM) plasmas that have a significant Hamiltonian-canonical angular momentum (H-Ptheta) space loss cone which scales with the characteristic size (S identical with R/sub HV//3p/sub i/) and applied vacuum magnetic field (B 0 )

  2. Monitoring and diagnostic system of fission product transport and release in nuclear power plants

    International Nuclear Information System (INIS)

    Kodaira, H.; Kondo, S.; Togo, Y.

    1983-01-01

    A monitoring and diagnostic system (MADS) of fission product (FP) transport and release in nuclear power plants (NPPs) is proposed and the conceptual design for MADS is studied. A MADS can be described in the most general way as a computer-based information processing system which takes in plant data, processes it and displays the results to the NPP's operating crew. A major concern for MADS is, however, not to evaluate general plant dynamics, but to monitor the distribution of whole radioactive materials such as FP, and to diagnose the plant state in the view of FP transport during the NPP's lifetime. Several functions demanded of MADS are: (a) during normal operation, to certify the fuel integrity and the effectiveness of the purification systems, (b) in an unusual event, to identify the event and to monitor the amount of FP release with accuracy, and (c) in case of a rare occurrence, to estimate the maximum potential release

  3. Risk comparisons for the transportation of spent fuel from nuclear reactors

    International Nuclear Information System (INIS)

    Hull, A.P.; Lessard, E.T.

    1985-04-01

    In summary, on the basis of calculated estimates, tests and accident statistics, the transport of spent nuclear fuel by whatever means has been shown to represent an infinitesimally small risk to the public, wherever they may be located enroute. This conclusion is based on three points (1) the probability of an accident involving spent fuel is small, (2) the probability that this hypothetical accident releases radioactive materials is even smaller and (3) the public-health consequences of such a release are trivial. It hardly seems to warrant the extensive assessment that it has received. If the risk to the public is of concern, this attention and analysis might have been more profitably spent on the improvement of the safety of the transport of a wide variety of other hazardous substances, which at present are given little if any prior scrutiny

  4. Process of Judging Significant Modifications for Different Transportation Systems compared to the Approach for Nuclear Installations

    Directory of Open Access Journals (Sweden)

    Nicolas Petrek

    2015-12-01

    Full Text Available The implementation of the CSM regulation by the European Commission in 2009 which harmonizes the risk assessment process and introduces a rather new concept of judging changes within the European railway industry. This circumstance has risen the question how other technology sectors handle the aspect of modifications and alterations. The paper discusses the approaches for judging the significance of modifications within the three transport sectors of European railways, aviation and maritime transportation and the procedure which is used in the area of nuclear safety. We will outline the similarities and differences between these four methods and discuss the underlying reasons. Finally, we will take into account the role of the European legislator and the fundamental idea of a harmonization of the different approaches.

  5. Systems engineering approach to U.S. Department of Energy's commercial nuclear waste transportation program

    International Nuclear Information System (INIS)

    Pardue, W.M.

    1987-01-01

    The U.S Department of Energy (DOE) has been given the responsibility of developing a program to transport commercially produced spent nuclear fuel and high-level radioactive wastes to disposal sites or storage facilities safely and cost-effectively. To accomplish this task it is desirable to plan, perform, and document all technical activities based on systems engineering principles. This paper presents an overview of the systems engineering approach being developed by Battelle for consideration by DOE, specifically the early identification of the required technical activities and approaches to technical management and decision making. The program should support the development of an integrated, well-documented transportation system acceptable to regulatory agencies and the public

  6. The transportation of British nuclear weapons by road. Hiroshima is waiting to happen in the UK

    International Nuclear Information System (INIS)

    Harris, E.J.

    1993-01-01

    This leaflet describes the transportation of nuclear weapons on United Kingdom roads. The author seeks to question the safety and desirability of such activities, and points out the potential hazards to humans and the environment should convoy accidents occur. Correspondence is included between the author and various Government sources to illustrate the difficulty of obtaining full, accurate information on the design and safety of weapons transportation vehicles and the reasons and frequency of weapons convoys. The author contrasts these difficulties with the free available government information in the United States of America because of the Freedom of Information Act. Readers are urged to contribute to monitoring the routes and occurrence of UK weapons convoys to assist in data collection. (UK)

  7. Legal and governmental infrastructure for nuclear, radiation, radioactive waste and transport safety. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    This publication establishes requirements for legal and governmental responsibilities in respect of the safety of nuclear facilities, the safe use of sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material. Thus, it covers development of the legal framework for establishing a regulatory body and other actions to achieve effective regulatory control of facilities and activities. Other responsibilities are also covered, such as those for developing the necessary support for safety, involvement in securing third party liability and emergency preparedness

  8. Legal and governmental infrastructure for nuclear, radiation, radioactive waste and transport safety. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    This publication establishes requirements for legal and governmental responsibilities in respect of the safety of nuclear facilities, the safe use of sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material. Thus, it covers development of the legal framework for establishing a regulatory body and other actions to achieve effective regulatory control of facilities and activities. Other responsibilities are also covered, such as those for developing the necessary support for safety, involvement in securing third party liability and emergency preparedness

  9. The role of nuclear techniques in the long-term prediction of radionuclide transport

    International Nuclear Information System (INIS)

    Airey, P.L.; Duerden, P.

    1985-01-01

    Problems associated with the long-term prediction of the migration of radionuclides, and the role of natural analogues in reducing the inherent uncertainties are discussed. Particular reference is made to the evaluation of uranium ore bodies in the Alligator Rivers region, Northern Territory, as analogues of high-level radioactive waste repositories. A range of nuclear techniques has been used to identify the role of colloids, of alpha recoil and of mineralogy in transport. Specific mention is made of a method being developed which enables models of the migration of solute through fractured rock to be assessed via a combination of alpha track, fission track and PIXE/PIGME techniques

  10. Legal and Institutional Issues of Transportable Nuclear Power Plants: A Preliminary Study

    International Nuclear Information System (INIS)

    2013-01-01

    jointly the international and national actions required for ensuring the sustainability of nuclear energy through innovations in technology and/or institutional arrangements. A transportable nuclear power plant (TNPP) is a factory manufactured, transportable and relocatable nuclear power plant which, when fuelled, is capable of producing final energy products such as electricity and heat. Introducing a TNPP may require fewer financial and human resources from the host State. However, the deployment of such reactors will face new legal issues in the international context which need to be resolved to enable the deployment of such reactors in countries other than the country of origin. The objective of this report is to study the legal and institutional issues for the deployment of TNPPs, to reveal challenges that might be faced in their deployment, and to outline pathways for resolution of the identified issues and challenges in the short and long terms. It is addressed to senior legal, regulatory and technical officers in Member States planning to embark on a nuclear power programme or to expand an existing one by considering the introduction of a TNPP

  11. Constraining nuclear data via cosmological observations: Neutrino energy transport and big bang nucleosynthesis

    Directory of Open Access Journals (Sweden)

    Paris Mark

    2017-01-01

    Full Text Available We introduce a new computational capability that moves toward a self-consistent calculation of neutrino transport and nuclear reactions for big bang nucleosynthesis (BBN. Such a self-consistent approach is needed to be able to extract detailed information about nuclear reactions and physics beyond the standard model from precision cosmological observations of primordial nuclides and the cosmic microwave background radiation. We calculate the evolution of the early universe through the epochs of weak decoupling, weak freeze-out and big bang nucleosynthesis (BBN by simultaneously coupling a full strong, electromagnetic, and weak nuclear reaction network with a multi-energy group Boltzmann neutrino energy transport scheme. The modular structure of our approach allows the dissection of the relative contributions of each process responsible for evolving the dynamics of the early universe. Such an approach allows a detailed account of the evolution of the active neutrino energy distribution functions alongside and self-consistently with the nuclear reactions and entropy/heat generation and 'ow between the neutrino and photon/electron/positron/baryon plasma components. Our calculations reveal nonlinear feedback in the time evolution of neutrino distribution functions and plasma thermodynamic conditions. We discuss the time development of neutrino spectral distortions and concomitant entropy production and extraction from the plasma. These e↑ects result in changes in the computed values of the BBN deuterium and helium-4 yields that are on the order of a half-percent relative to a baseline standard BBN calculation with no neutrino transport. This is an order of magnitude larger e↑ect than in previous estimates. For particular implementations of quantum corrections in plasma thermodynamics, our calculations show a 0.4% increase in deuterium and a 0.6% decrease in 4He over our baseline. The magnitude of these changes are on the order of uncertainties

  12. Nuclear-polarization correction to the bound-electron g factor in heavy hydrogenlike ions

    OpenAIRE

    Nefiodov, A. V.; Plunien, G.; Soff, G.

    2002-01-01

    The influence of nuclear polarization on the bound-electron $g$ factor in heavy hydrogenlike ions is investigated. Numerical calculations are performed for the K- and L-shell electrons taking into account the dominant virtual nuclear excitations. This determines the ultimate limit for tests of QED utilizing measurements of the bound-electron $g$ factor in highly charged ions.

  13. Nuclear-polarization correction to the bound-electron g factor in heavy hydrogenlike ions.

    Science.gov (United States)

    Nefiodov, A V; Plunien, G; Soff, G

    2002-08-19

    The influence of nuclear polarization on the bound-electron g factor in heavy hydrogenlike ions is investigated. Numerical calculations are performed for the K- and L-shell electrons taking into account the dominant virtual nuclear excitations. This determines the ultimate limit for tests of QED utilizing measurements of the bound-electron g factor in highly charged ions.

  14. Transportation infrastructure upgrades in the South: A compilation of state plans for construction near nuclear reactor sites

    International Nuclear Information System (INIS)

    1992-03-01

    There are currently 27 nuclear reactor sites located in the southern region. In many instances, the most practicable modes of transportation of spent nuclear fuel from these sites we through the use of highway and rail systems. These two transportation modes have important differences that affect their applicability; chief among these, perhaps, is the fact that while highway systems are publicly owned and maintained rail lines are owned by private entities. For this reason, track condition and maintenance, usage rates and other aspects of rail transport can vary widely. This report reviews southern state, department plans for infrastructure upgrades in the vicinity of nuclear reactor sites. This report includes a summary of planned modifications to bridges, access highways, and rail spurs (where applicable) over the next five years. The information contained herein was gathered from interviews with officials within state departments of transportation. With few exceptions, the contact person was an official within the departmental planning division

  15. Nuclear functions and subcellular trafficking mechanisms of the epidermal growth factor receptor family

    Science.gov (United States)

    2012-01-01

    Accumulating evidence suggests that various diseases, including many types of cancer, result from alteration of subcellular protein localization and compartmentalization. Therefore, it is worthwhile to expand our knowledge in subcellular trafficking of proteins, such as epidermal growth factor receptor (EGFR) and ErbB-2 of the receptor tyrosine kinases, which are highly expressed and activated in human malignancies and frequently correlated with poor prognosis. The well-characterized trafficking of cell surface EGFR is routed, via endocytosis and endosomal sorting, to either the lysosomes for degradation or back to the plasma membrane for recycling. A novel nuclear mode of EGFR signaling pathway has been gradually deciphered in which EGFR is shuttled from the cell surface to the nucleus after endocytosis, and there, it acts as a transcriptional regulator, transmits signals, and is involved in multiple biological functions, including cell proliferation, tumor progression, DNA repair and replication, and chemo- and radio-resistance. Internalized EGFR can also be transported from the cell surface to several intracellular compartments, such as the Golgi apparatus, the endoplasmic reticulum, and the mitochondria, in addition to the nucleus. In this review, we will summarize the functions of nuclear EGFR family and the potential pathways by which EGFR is trafficked from the cell surface to a variety of cellular organelles. A better understanding of the molecular mechanism of EGFR trafficking will shed light on both the receptor biology and potential therapeutic targets of anti-EGFR therapies for clinical application. PMID:22520625

  16. Effects of bedrock fractures on radionuclide transport near a vertical deposition hole for spent nuclear fuel

    International Nuclear Information System (INIS)

    Pulkkanen, V.-M.; Nordman, H.

    2011-12-01

    Effects of bedrock fractures on radionuclide transport near a vertical deposition hole for spent nuclear fuel are studied computationally. The studied fractures are both natural and excavation damage fractures. The emphasis is on the detailed modelling of geometry in 3D in contrast to the traditional radionuclide transport studies that often concentrate on chain decays, sorption, and precipitation at the expense of the geometry. The built computer model is used to assess the significance of components near a deposition hole for radionuclide transport and to estimate the quality of previously used modelling techniques. The results show nearly exponential decrease of radionuclide mass in the bentonite buffer when the release route is a thin natural fracture. The results also imply that size is the most important property of the tunnel section for radionuclide transport. In addition, the results demonstrate that the boundary layer theory can be used to approximate the release of radionuclides with certain accuracy and that a thin fracture in rock can be modelled, at least to a certain limit, by using a fracture with wider aperture but with same flow rate as the thin fracture. (orig.)

  17. Spent nuclear fuel transportation casks evaluation for water in-leakage

    International Nuclear Information System (INIS)

    Shah, M.J.; Huang, D.T.; Guttmann, J.; Klymyshyn, N.A.; Koeppel, B.J.; Adkins, H.E.

    2004-01-01

    The United States Nuclear Regulatory Commission (USNRC) is responsible for licensing commercial spent fuel storage and transportation systems. To ensure that the regulations are risk-informed, and do not place unnecessary regulatory burden on the industry, the USNRC has been examining its regulations that apply to spent fuel transportation casks for maintaining sub-criticality under hypothetical accident conditions. Code of Federal Regulations, Title 10, Part 71[1] (10 CFR 71), section 71.55(b) requires that, for evaluation of sub-criticality for fissile material packages, water moderation should be assumed to occur to the most reactive credible extent consistent with the chemical and physical form of the contents. This requirement is based on a defense-in-depth policy, and accounts for any possibility of water intrusion into the package. This program is designed to quantify the margins of safety of certified transportation casks to water intrusion following hypothetical accident conditions. This paper describes the current status of analytical work being performed to evaluate two USNRC-certified spent fuel transportation casks, HI-STAR 100[2] and TN-68[3]. The analytical work is performed using the ANSYS registered [4] and LS-DYNA trademark [5] finite element analysis (FEA) codes. The models are sufficiently detailed in the areas of bolt closure interfaces and containment boundaries to evaluate the likelihood water in-leakage under free drop hypothetical accident conditions of 10 CFR 71.73

  18. Measurement and modelling of reactive transport in geological barriers for nuclear waste containment.

    Science.gov (United States)

    Xiong, Qingrong; Joseph, Claudia; Schmeide, Katja; Jivkov, Andrey P

    2015-11-11

    Compacted clays are considered as excellent candidates for barriers to radionuclide transport in future repositories for nuclear waste due to their very low hydraulic permeability. Diffusion is the dominant transport mechanism, controlled by a nano-scale pore system. Assessment of the clays' long-term containment function requires adequate modelling of such pore systems and their evolution. Existing characterisation techniques do not provide complete pore space information for effective modelling, such as pore and throat size distributions and connectivity. Special network models for reactive transport are proposed here using the complimentary character of the pore space and the solid phase. This balances the insufficient characterisation information and provides the means for future mechanical-physical-chemical coupling. The anisotropy and heterogeneity of clays is represented using different length parameters and percentage of pores in different directions. Resulting networks are described as mathematical graphs with efficient discrete calculus formulation of transport. Opalinus Clay (OPA) is chosen as an example. Experimental data for the tritiated water (HTO) and U(vi) diffusion through OPA are presented. Calculated diffusion coefficients of HTO and uranium species are within the ranges of the experimentally determined data in different clay directions. This verifies the proposed pore network model and validates that uranium complexes are diffusing as neutral species in OPA. In the case of U(vi) diffusion the method is extended to account for sorption and convection. Rather than changing pore radii by coarse grained mathematical formula, physical sorption is simulated in each pore, which is more accurate and realistic.

  19. Transport of Cobalt 60 from the Argentine Nuclear Power Plant in Embalse

    International Nuclear Information System (INIS)

    Lopez Vietri, J.R.

    2011-01-01

    Full text: The purpose of this presentation is to point out some relevant issues related to the transport of cobalt 60 for domestic uses and export from the Argentine Nuclear Power Plant located in Embalse (ENPP). It is remarked that in last 22 years, ENPP produced about 2600 PBq (70 MCi) of Co-60, and that Argentina is the third Co-60 producer, after Canada and Russia. It is mentioned that in Argentina there are facilities which manufacture Zircaloy seamless tubes and reactivity control bars containing cobalt 59 to be used in ENPP, the operation of Candu reactor at ENPP including cobalt-related activities, and the manufacture and commercialization of Co-60 sealed sources. The Argentine Nuclear Regulatory Authority verifies the compliance of nuclear activities with regulatory standards, including those related to the transport of radioactive material. Then, it is described the process for obtaining Co-60 at ENPP with an activity concentration to allow its use in medicine and industry. After that, is considered in detail the type of package used for the transport of Co-60 from ENPP: it is to say, Type B(U) package designs that must be approved by the Competent Authority origin of the design, and they are able to withstand routine, normal and accident conditions of transport, including severe impacts, fires and immersion in water. The overall dimensions of packages are about 1.0 m to 1.5 m diameter by 1.2 m to 1.8 m high, as well as the gross mass could vary from 6500 kg to 9500 kg. Radioactive contents consist of Co-60 sealed sources (called pencils), with an activity range from 8 PBq to 16 PBq. Then, it is considered activities prior to dispatch of Type B(U) packages at ENPP, including the preparation of radioactive contents, packaging and package (labelling and marking) as well as necessary tests and documentation for transport in order to fulfil pertinent requirements of package design operation manual of the package and related standards. Finally, it is pointed

  20. Integrated System for Retrieval, Transportation and Consolidated Storage of Used Nuclear Fuel in the US - 13312

    International Nuclear Information System (INIS)

    Bracey, William; Bondre, Jayant; Shelton, Catherine; Edmonds, Robert

    2013-01-01

    The current inventory of used nuclear fuel assemblies (UNFAs) from commercial reactor operations in the United States totals approximately 65,000 metric tons or approximately 232,000 UNFAs primarily stored at the 104 operational reactors in the US and a small number of decommissioned reactors. This inventory is growing at a rate of roughly 2,000 to 2,400 metric tons each year, (Approx. 7,000 UNFAs) as a result of ongoing commercial reactor operations. Assuming an average of 10 metric tons per storage/transportation casks, this inventory of commercial UNFAs represents about 6,500 casks with an additional of about 220 casks every year. In January 2010, the Blue Ribbon Commission (BRC) [1] was directed to conduct a comprehensive review of policies for managing the back end of the nuclear fuel cycle and recommend a new plan. The BRC issued their final recommendations in January 2012. One of the main recommendations is for the United States to proceed promptly to develop one or more consolidated storage facilities (CSF) as part of an integrated, comprehensive plan for safely managing the back end of the nuclear fuel cycle. Based on its extensive experience in storage and transportation cask design, analysis, licensing, fabrication, and operations including transportation logistics, Transnuclear, Inc. (TN), an AREVA Subsidiary within the Logistics Business Unit, is engineering an integrated system that will address the complete process of commercial UNFA management. The system will deal with UNFAs in their current storage mode in various configurations, the preparation including handling and additional packaging where required and transportation of UNFAs to a CSF site, and subsequent storage, operation and maintenance at the CSF with eventual transportation to a future repository or recycling site. It is essential to proceed by steps to ensure that the system will be the most efficient and serve at best its purpose by defining: the problem to be resolved, the criteria to