WorldWideScience

Sample records for projects including nuclear

  1. Nuclear safety project

    International Nuclear Information System (INIS)

    1982-06-01

    The Annual Report 1981 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1981 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on - work completed - results obtained - plans for future work. This report was compiled by the project management. (orig.) [de

  2. Nuclear Safety Project

    International Nuclear Information System (INIS)

    1978-11-01

    The 13th semi-annual report 1/78 is a description of work within the Nuclear Safety Project performed in the first six months of 1978 in the nuclear safety field by KFK institutes and departments and by external institutions on behalf of KfK. It includes for each individual research activity short summaries on - work completed, - essential results, - plans for the near future. (orig./RW) [de

  3. Spent Nuclear Fuel project, project management plan

    International Nuclear Information System (INIS)

    Fuquay, B.J.

    1995-01-01

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

  4. Baltic nuclear projects

    International Nuclear Information System (INIS)

    Adlys, Gediminas; Adliene, Diana

    2009-01-01

    The Authors discuss the Baltic energy policy with respect to new nuclear power plants for Lithuania, Belarus and the Kaliningrad region. The construction of a new nuclear power plant in Lithuania would threaten Russian interests in the region. Therefore Lithuania is looking to Russian plans to build a new nuclear power plant in the Kaliningrad region as an attempt to subvert Lithuania's foreign partners and potential investors from participating in the Visaginas NPP project. However, the authors conclude, that the Visaginas NPP project is and must be the preferential project for the EU and NATO member states.

  5. Project Nuclear Safety

    International Nuclear Information System (INIS)

    1981-11-01

    The semiannual progress report 1981/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1981 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics, work performed, results obtained, plans for future work. This report was compiled by the project management. (orig.) [de

  6. Nuclear safety project

    International Nuclear Information System (INIS)

    1984-11-01

    The semiannual progress report 1984/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1984 in the nuclear safety field by KfK institutes and departements and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./RW) [de

  7. AAEC nuclear power projections

    International Nuclear Information System (INIS)

    Khoe, G.; Fredsall, J.; Scurr, I.; Plotnikoff, W.

    1981-01-01

    The nuclear power capacity projections developed in the May-June period of 1981 by the AAEC are presented. There have been downward revisions for nearly all countries with centrally planned economies. Projections for the year 2000 for the Western World have decreased in aggregate by 4.7% (27Gw) compared to those of 1980. However, this reduction is less than the previous estimate reduction and there appears to have been a stabilisation in the projection

  8. Nuclear Safety Project

    International Nuclear Information System (INIS)

    1983-12-01

    The semiannual progress report 1983/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1983 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics work performed, results obtained and plans for future work. (orig./RW) [de

  9. Nuclear safety project

    International Nuclear Information System (INIS)

    Anon.

    1980-11-01

    The 17th semi-annual report 1980/1 is a description of work within the Nuclear Safety Project performed in the first six months of 1980 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics - work performed, results obtained, plans for future work. (orig.) [de

  10. The Bruce nuclear project

    International Nuclear Information System (INIS)

    Rose, J.B.

    1981-01-01

    This case study assesses the industrial relations impact of the construction of the Bruce Nuclear Power Development. It examines the labour relations system in the Ontario electric power sector and in major building construction. Industrial relations problems and practices at the Bruce project are reviewed. The focus of the study is on the relationship between the project and the rest of the Ontario industrial construction industry

  11. Nuclear safeguards project

    International Nuclear Information System (INIS)

    Mache, H.R.

    1978-10-01

    The present report describes the major activities carried out in 1977 in the framework of the Nuclear Safeguards Project by the institutes of the Kernforschungszentrum Karlsruhe, Kernforschungsanlage Juelich, the European Institute of Transuranium Elements and some industrial firms. (orig.) 891 HP 892 AP [de

  12. Nuclear Waste Education Project

    International Nuclear Information System (INIS)

    1989-01-01

    In summary, both the Atlanta and Albuquerque pilot seminars achieved the Nuclear Waste Education Project's goal of informing citizens on both the substance and the process of nuclear waste policy so that they can better participate in future nuclear waste decisions. Nuclear waste issues are controversial, and the seminars exposed the nature of the controversy, and utilized the policy debates to create lively and provocative sessions. The format and content of any citizen education curriculum must be made to fit the particular goal that has been chosen. If the Department of Energy and the LWVEF decide to continue to foster an informed dialogue among presenters and participants, the principles of controversial issues education would serve this goal well. If, however, the Department of Energy and/or the LWVEF decide to go beyond imparting information and promoting a lively discussion of the issues, towards some kind of consensus-building process, it would be appropriate to integrate more interactive sessions into the format. As one evaluator wrote, ''In-depth participation in finding solutions or establishing policy -- small group discussion'' would have been preferable to the plenary sessions that mostly were in the form of lectures and expert panel discussion. The evaluator continued by saying, ''Since these [small group discussions] would require more time commitment, they might be part of follow-up workshops focused on particular topics.''

  13. Nuclear reactor shield including magnesium oxide

    International Nuclear Information System (INIS)

    Rouse, C.A.; Simnad, M.T.

    1981-01-01

    An improvement is described for nuclear reactor shielding of a type used in reactor applications involving significant amounts of fast neutron flux. The reactor shielding includes means providing structural support, neutron moderator material, neutron absorber material and other components, wherein at least a portion of the neutron moderator material is magnesium in the form of magnesium oxide either alone or in combination with other moderator materials such as graphite and iron

  14. Good performance in nuclear projects

    International Nuclear Information System (INIS)

    1989-01-01

    The nuclear industry has demonstrated good performance in many areas relating to the design, engineering, construction and operation of nuclear facilities. This report of an international symposium held in Tokyo highlights examples of good performance in nuclear projects which can aid the industry in seeking even better performance, thus strengthening the contribution nuclear energy can make to sustainable economic growth

  15. Aerosol simulation including chemical and nuclear reactions

    International Nuclear Information System (INIS)

    Marwil, E.S.; Lemmon, E.C.

    1985-01-01

    The numerical simulation of aerosol transport, including the effects of chemical and nuclear reactions presents a challenging dynamic accounting problem. Particles of different sizes agglomerate and settle out due to various mechanisms, such as diffusion, diffusiophoresis, thermophoresis, gravitational settling, turbulent acceleration, and centrifugal acceleration. Particles also change size, due to the condensation and evaporation of materials on the particle. Heterogeneous chemical reactions occur at the interface between a particle and the suspending medium, or a surface and the gas in the aerosol. Homogeneous chemical reactions occur within the aersol suspending medium, within a particle, and on a surface. These reactions may include a phase change. Nuclear reactions occur in all locations. These spontaneous transmutations from one element form to another occur at greatly varying rates and may result in phase or chemical changes which complicate the accounting process. This paper presents an approach for inclusion of these effects on the transport of aerosols. The accounting system is very complex and results in a large set of stiff ordinary differential equations (ODEs). The techniques for numerical solution of these ODEs require special attention to achieve their solution in an efficient and affordable manner. 4 refs

  16. PROJECTIZING AN OPERATING NUCLEAR FACILITY

    International Nuclear Information System (INIS)

    Adams, N

    2007-01-01

    This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully

  17. Nuclear data project evaluation activity report. October 1998 - October 2000

    International Nuclear Information System (INIS)

    Akovali, Y.; Blackmon, J.; Radford, D.; Smith, M.

    2001-01-01

    This report summarizes the activities of the ORNL Nuclear Data Project since the IAEA Advisory Group meeting in December 1998. The group's future plans are also included. The ORNL Nuclear Data Project's responsibility includes the compilation/evaluation of astrophysics data, as well as the evaluation and compilation of nuclear structure data. The Nuclear Data Project, therefore, is composed of two groups. The Nuclear Data Project staff through September 2000 is listed below. Accomplishments for the period of October 1998 through September 2000 of the nuclear structure data group and the nuclear astrophysics group are submitted in this Nuclear Data Project report

  18. Nuclear data project evaluation activity report. October 1998 - October 2000

    Energy Technology Data Exchange (ETDEWEB)

    Akovali, Y; Blackmon, J; Radford, D; Smith, M [Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    2001-02-01

    This report summarizes the activities of the ORNL Nuclear Data Project since the IAEA Advisory Group meeting in December 1998. The group's future plans are also included. The ORNL Nuclear Data Project's responsibility includes the compilation/evaluation of astrophysics data, as well as the evaluation and compilation of nuclear structure data. The Nuclear Data Project, therefore, is composed of two groups. The Nuclear Data Project staff through September 2000 is listed below. Accomplishments for the period of October 1998 through September 2000 of the nuclear structure data group and the nuclear astrophysics group are submitted in this Nuclear Data Project report.

  19. Canadian national nuclear forensics capability project

    International Nuclear Information System (INIS)

    Ball, J.; Dimayuga, I.; Summerell, I.; Totland, M.; Jonkmans, G.; Whitlock, J.; El-jaby, A.; Inrig, E.

    2015-01-01

    Following the 2010 Nuclear Security Summit, Canada expanded its existing capability for nuclear forensics by establishing a national nuclear forensics laboratory network, which would include a capability to perform forensic analysis on nuclear and other radioactive material, as well as on traditional evidence contaminated with radioactive material. At the same time, the need for a national nuclear forensics library of signatures of nuclear and radioactive materials under Canadian regulatory control was recognized. The Canadian Safety and Security Program, administered by Defence Research and Development Canada's Centre for Security Science (DRDC CSS), funds science and technology initiatives to enhance Canada's preparedness for prevention of and response to potential threats. DRDC CSS, with assistance from Canadian Nuclear Laboratories, formerly Atomic Energy of Canada Limited, is leading the Canadian National Nuclear Forensics Capability Project to develop a coordinated, comprehensive, and timely national nuclear forensics capability. (author)

  20. Canadian national nuclear forensics capability project

    Energy Technology Data Exchange (ETDEWEB)

    Ball, J.; Dimayuga, I., E-mail: joanne.ball@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Summerell, I. [Royal Canadian Mounted Police, Ottawa, Ontario (Canada); Totland, M. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Jonkmans, G. [Defence Research and Development Canada, Ottawa, Ontario (Canada); Whitlock, J. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); El-jaby, A. [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada); Inrig, E. [Defence Research and Development Canada, Ottawa, Ontario (Canada)

    2015-06-15

    Following the 2010 Nuclear Security Summit, Canada expanded its existing capability for nuclear forensics by establishing a national nuclear forensics laboratory network, which would include a capability to perform forensic analysis on nuclear and other radioactive material, as well as on traditional evidence contaminated with radioactive material. At the same time, the need for a national nuclear forensics library of signatures of nuclear and radioactive materials under Canadian regulatory control was recognized. The Canadian Safety and Security Program, administered by Defence Research and Development Canada's Centre for Security Science (DRDC CSS), funds science and technology initiatives to enhance Canada's preparedness for prevention of and response to potential threats. DRDC CSS, with assistance from Canadian Nuclear Laboratories, formerly Atomic Energy of Canada Limited, is leading the Canadian National Nuclear Forensics Capability Project to develop a coordinated, comprehensive, and timely national nuclear forensics capability. (author)

  1. The project 'nuclear safeguards'

    International Nuclear Information System (INIS)

    Gupta, D.

    1976-01-01

    A survey is given on the elaboration and implementation of a nuclear safeguards system which takes into account the economic needs of an expanding nuclear industry as well as the international monitoring commitments of the FRG under the Euratom and Non-Proliferation treaties. (RW) [de

  2. Spent Nuclear Fuel Project Safety Management Plan

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1996-02-01

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

  3. Nuclear safety projects 1995

    International Nuclear Information System (INIS)

    Carl-Erik Christoffersen

    1996-01-01

    Action plans for the prevention of contamination in the Arctic regions is concretized in a number of international projects. The Norwegian Radiation Protection Authority is responsible for the follow-up of 13 projects. The report describes the development of these projects in 1995

  4. Economics of nuclear power projects

    International Nuclear Information System (INIS)

    Chu, I.H.

    1985-01-01

    Nuclear power development in Taiwan was initiated in 1956. Now Taipower has five nuclear units in smooth operation, one unit under construction, two units under planning. The relatively short construction period, low construction costs and twin unit approach had led to the significant economical advantage of our nuclear power generation. Moreover betterment programmes have further improved the availability and reliability factors of our nuclear power plants. In Taipower, the generation cost of nuclear power was even less than half of that of oil-fired thermal power in the past years ever since the nuclear power was commissioned. This made Taipower have more earnings and power rates was even dropped down in March 1983. As Taiwan is short of energy sources and nuclear power is so well-demonstrated nuclear power will be logically the best choice for Taipower future projects

  5. Nuclear Safety Project. Annual report 1983

    International Nuclear Information System (INIS)

    1984-06-01

    The annual report 1983 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1983 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig.) [de

  6. Nuclear safety project. Annual report 1985

    International Nuclear Information System (INIS)

    1986-07-01

    The annual report 1985 is a detailed description (in German language) of work within the nuclear safety project performed in 1985 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./HP) [de

  7. Financing of nuclear projects

    International Nuclear Information System (INIS)

    Diel, R.

    1983-01-01

    Delays in the completion of nuclear power plants aggravate the financing of such ventures because the contractual sums to be paid for interest and amortization are not generated. Moreover, economic feasibility analyses by the banks are rendered ineffective by changes in the underlying data, such as the structure of electricity rates and the supply monopoly held by utilities. The German nuclear power plants at present in operation or under construction were financed mainly through subsidiares of the participating utilities outside the balance sheets of the parent companies. The banks have developed a number of financing concepts to adapt funding to the specific needs of practice. Future nuclear power plants make-up one third of the present capacity of the participating utilities. However, they will require three to four times the previous volume of capital investments. Yet it is certain that the expansion of nuclear power in the Federal Republic of Germany will not be hampered by financial problems. The funding models developed for nuclear power plants have already proved their qualities. However, the problems of nuclear power have not become less. Attention must also be drawn to some weak spots in the financial sector. (orig.) [de

  8. Management of delayed nuclear power plant projects

    International Nuclear Information System (INIS)

    2005-01-01

    The IAEA assists the management of organizations responsible for Nuclear Power Plant Projects with significant delays with respect to the originally scheduled commercial operation. Several Member States have Nuclear Power Plant Projects with delays of five or more years with respect to the originally scheduled commercial operation. The degree of conformance with original construction schedules shows large variations due to several issues, including financial, economic and public opinion factors. Solving the special difficulties related with a delayed NPP project is problematic and dependent on the particular country situation. However it is not regarded as an isolated national problem but as a significant issue with a number of difficulties shared by several Member States. The IAEA collects information and supports the management of delayed NPP projects by identifying main common issues, gathering available experience and addressing specific needs. On this background the IAEA is in the position to provide unique impartial assistance based upon best international practices. This enables Member States to maintain readiness for resuming the project construction when the conditions permit and to strengthen management's abilities for the completion of the project. The IAEA's service is tailored to the needs and requirements of the requesting organization, implemented on-site by international experts and addresses areas such as project control measures, human resources, updating to technological and regulatory requirements, project data, nuclear safety review, physical protection and nuclear security and preparation to resume project construction and operation

  9. Role of participants in nuclear power projects

    International Nuclear Information System (INIS)

    Polliart, A.J.

    1977-01-01

    In this article staffing requirements for nuclear projects (Turnkey Contract) and the owner's staff requirements, project planning, project implementation, and plant construction and commissioning are treated. (HK) [de

  10. Nuclear power: Financing big projects

    International Nuclear Information System (INIS)

    Raabe, G.

    1992-01-01

    Since the early seventies, the Dresdner Bank AG has been intensively engaged in financing nuclear power plants, e.g., the Muelheim-Kaerlich Nuclear Power Station currently down because of legal technicaltities. The bank has also been involved in other large-scale projects in the energy sector and, in addition, has conceptually accompanied the stages of the nuclear fuel cycle, such as enrichment, fuel element fabrication, and reprocessing. However, for political reasons it has not been possible to carry out these projects and finance them in the Federal Republic. With appropriate modifications, these financial models can also be transferred to international projects; after all, the enrichment sector has always been characterized by trilateral ventures. (orig.) [de

  11. NASA's Nuclear Thermal Propulsion Project

    Science.gov (United States)

    Houts, Michael G.; Mitchell, Doyce P.; Kim, Tony; Emrich, William J.; Hickman, Robert R.; Gerrish, Harold P.; Doughty, Glen; Belvin, Anthony; Clement, Steven; Borowski, Stanley K.; hide

    2015-01-01

    The fundamental capability of Nuclear Thermal Propulsion (NTP) is game changing for space exploration. A first generation NTP system could provide high thrust at a specific impulse above 900 s, roughly double that of state of the art chemical engines. Characteristics of fission and NTP indicate that useful first generation systems will provide a foundation for future systems with extremely high performance. The role of a first generation NTP in the development of advanced nuclear propulsion systems could be analogous to the role of the DC- 3 in the development of advanced aviation. Progress made under the NTP project could also help enable high performance fission power systems and Nuclear Electric Propulsion (NEP).

  12. Risk management in nuclear projects

    International Nuclear Information System (INIS)

    Salles, Claudio J.R.

    2002-01-01

    The risk management will be defined by different aspects: danger or loss possibility, or responsibility for damage. The risk management is one stage of project management. The risk management is a continuous process of planning, identification, quantification, answer and risk control to maximize the success potential of activity. The reduction of risk is part of priority establishment. This work will indicate how introduce this important instrument in the management of nuclear projects. (author)

  13. Nuclear Safety Project - annual report 1980

    International Nuclear Information System (INIS)

    1981-08-01

    The Annual Report 1980 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1980 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work completed, essential results, plans for the near future. (orig./RW) [de

  14. Management of delayed nuclear power plant projects

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-09-01

    According to the available information at the IAEA PRIS (Power Reactor Information System) at the end of 1998 there were more than 40 nuclear power plant projects with delays of five or more years with respect to the originally scheduled commercial operation. The degree of conformance with original construction schedules showed large variations due to several issues, including financial, economic and public opinion factors. Taking into account the number of projects with several years delay in their original schedules, it was considered useful to identify the subject areas where exchange of experience among Member States would be mutually beneficial in identification of problems and development of guidance for successful management of the completion of these delayed projects. A joint programme of the IAEA Departments of Nuclear Energy (Nuclear Power Engineering Section) and Technical Co-operation (Europe Section, with additional support from the Latin America and West Asia Sections) was set up during the period 1997-1998. The specific aim of the programme was to provide assistance in the management of delayed nuclear power plants regarding measures to maintain readiness for resuming the project implementation schedule when the conditions permit. The integration of IAEA interdepartmental resources enabled the participation of 53 experts from 14 Member States resulting in a wider exchange of experience and dissemination of guidance. Under the framework of the joint programme, senior managers directly responsible for delayed nuclear power plant projects identified several issues or problem areas that needed to be addressed and guidance on management be provided. A work plan for the development of several working documents, addressing the different issues, was established. Subsequently these documents were merged into a single one to produce the present publication. This publication provides information and practical examples on necessary management actions to preserve

  15. Management of delayed nuclear power plant projects

    International Nuclear Information System (INIS)

    1999-09-01

    According to the available information at the IAEA PRIS (Power Reactor Information System) at the end of 1998 there were more than 40 nuclear power plant projects with delays of five or more years with respect to the originally scheduled commercial operation. The degree of conformance with original construction schedules showed large variations due to several issues, including financial, economic and public opinion factors. Taking into account the number of projects with several years delay in their original schedules, it was considered useful to identify the subject areas where exchange of experience among Member States would be mutually beneficial in identification of problems and development of guidance for successful management of the completion of these delayed projects. A joint programme of the IAEA Departments of Nuclear Energy (Nuclear Power Engineering Section) and Technical Co-operation (Europe Section, with additional support from the Latin America and West Asia Sections) was set up during the period 1997-1998. The specific aim of the programme was to provide assistance in the management of delayed nuclear power plants regarding measures to maintain readiness for resuming the project implementation schedule when the conditions permit. The integration of IAEA interdepartmental resources enabled the participation of 53 experts from 14 Member States resulting in a wider exchange of experience and dissemination of guidance. Under the framework of the joint programme, senior managers directly responsible for delayed nuclear power plant projects identified several issues or problem areas that needed to be addressed and guidance on management be provided. A work plan for the development of several working documents, addressing the different issues, was established. Subsequently these documents were merged into a single one to produce the present publication. This publication provides information and practical examples on necessary management actions to preserve

  16. Spanish Nuclear Industry in Lungmen Project

    International Nuclear Information System (INIS)

    Alomar, F.

    1998-01-01

    Spain's Advanced Nuclear Reactors Programs, under DTN's leadership, has meant an active participation the American Design of Advanced Nuclear Power Plants, in both General Electric and Westinghouse Programs. This collaboration has given to the Companies, which directly involved, an in-depth knowledge of both Development Programs, as well as it has allowed to establish relationships with Nuclear Island DTN's coordination. These Companies included a broad sample of Spanish Companies most interest in the Nuclear Field: DTN representing Spanish Utilities with Nuclear Assets; Empresarios Agrupados and INITEC as a Joint Venture, representing Spanish A/E; Equipos Nucleares, S.A., representing Nuclear Components Manufacturers; Tecnatom, representing Nuclear Services and Engineering and CIEMAT as National Laboratory. Taiwan Electric Power has awarded its two 1300 MWe Lungmen Units to General Electric. Knowledge acquired by these Spanish Companies along FOAKE First of kind then Engineering has allowed them to bid for some authorities in Lungmen NPP and in some cases to get important awards. Furthermore, the good working relationship which has been established has made way for other Spanish Companies to bid for other Project Packages. On a case by case basis the response of Spanish manufacturer has been irregular . In some instances manufactures have stopped manufacturing nuclear components, and in other instances a distinct lack of interest has been detected. (Author)

  17. The Los Alamos National Laboratory Nuclear Vision Project

    International Nuclear Information System (INIS)

    Arthur, E.D.; Wagner, R.L. Jr.

    1996-01-01

    Los Alamos National Laboratory has initiated a project to examine possible futures associated with the global nuclear enterprise over the course of the next 50 years. All major components are included in this study--weapons, nonproliferation, nuclear power, nuclear materials, and institutional and public factors. To examine key issues, the project has been organized around three main activity areas--workshops, research and analyses, and development of linkages with other synergistic world efforts. This paper describes the effort--its current and planned activities--as well as provides discussion of project perspectives on nuclear weapons, nonproliferation, nuclear energy, and nuclear materials focus areas

  18. Nuclear Power Project in Thailand

    International Nuclear Information System (INIS)

    Namwong, Ratanachai

    2011-01-01

    The Electricity Generating Authority of Thailand (EGAT), the main power producer in Thailand, was first interested in nuclear power as an electricity option in 1967 when the electricity demand increased considerably for the first time as a result of the economic and industrial growth. Its viability had been assessed several times during the early seventies in relation to the changing factors. Finally in the late 1970s, the proceeding with nuclear option was suspended for a variety of reasons, for instance, public opposition, economic repercussion and the uncovering of the indigenous petroleum resources. Nonetheless, EGAT continued to maintain a core of nuclear expertise. During 1980s, faced with dwindling indigenous fossil fuel resources and restrictions on the use of further hydro as an energy source, EGAT had essentially reconsidered introducing nuclear power plants to provide a significant fraction to the long term future electricity demand. The studies on feasibility, siting and environmental impacts were conducted. However, the project was never implemented due to economics crisis in 1999 and strong opposition by environmentalists and activists groups. The 1986 Chernobyl disaster was an important cause. After a long dormant period, the nuclear power is now reviewed as one part of the solution for future energy supply in the country. Thailand currently relies on natural gas for 70 percent of its electricity, with the rest coming from oil, coal and hydro-power. One-third of the natural gas consumed in Thailand is imported, mainly from neighbouring Myanmar. According to Power Development Plan (PDP) 2007 rev.2, the total installed electricity capacity will increase from 28,530.3 MW in 2007 to 44,281 MW by the end of plan in 2021. Significantly increasing energy demand, concerns over climate change and dependence on overseas supplies of fossil fuels, all turn out in a favor of nuclear power. Under the current PDP (as revised in 2009), two 1,000- megawatt nuclear

  19. Basic infrastructure for a nuclear power project

    International Nuclear Information System (INIS)

    2006-06-01

    There are several stages in the process of introducing nuclear power in a country. These include development of nuclear policies and regulations, feasibility studies, public consultations, technology evaluation, requests for proposals and evaluations, contracts and financing, supply, construction, commissioning, operation and finally decommissioning. This publication addresses the 'basic' infrastructure needs, which are adequate until the issue of the construction license. It is obvious that a fully developed nuclear infrastructure will be required for the further implementation stages of a nuclear power reactor. The officials and experts in each country will undertake the transition from a basic infrastructure to a fully developed infrastructure that covers the stages of construction, commissioning, operation and decommissioning. The publication is directed to provide guidance for assessing the basic infrastructure necessary for: - A host country to consider when engaging in the implementation of nuclear power, and - A supplier country to consider when assessing whether the recipient country is in an acceptable condition to begin the implementation of a nuclear power project. The target users are decision makers, advisers and senior managers in the governmental organizations, utilities, industrial organizations and regulatory bodies in the countries adopting nuclear power programmes or exporting supplies for these programmes. The governmental organizations that may find this publication useful include: Ministries of Economy, Energy, Foreign Affairs, Finance, Mining, Internal Affairs, Academic Institutions, Nuclear Energy Agencies and Environmental Agencies. This publication was produced within the IAEA programme directed to increase the capability of Member States to plan and implement nuclear power programmes and to establish and enhance national nuclear infrastructure. This publication should be used in conjunction with the IAEA Safety Standards Series and other

  20. Nuclear Safety Project. Annual report 1986

    International Nuclear Information System (INIS)

    1987-09-01

    The annual report 1986 is a detailed description of work within the Nuclear Safety Project performed in 1986 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes individual research activities on dynamic loads and strains of reactor components under accident conditions, fuel behaviour under accident conditions, investigation and control of LWR core-meltdown accidents, improvement of fission product retention and reduction of radiation exposure, and on behaviour, impact and removal of released pollutants. (DG)

  1. Lifecycle management for nuclear engineering project documents

    International Nuclear Information System (INIS)

    Zhang Li; Zhang Ming; Zhang Ling

    2010-01-01

    The nuclear engineering project documents with great quantity and various types of data, in which the relationships of each document are complex, the edition of document update frequently, are managed difficultly. While the safety of project even the nuclear safety is threatened seriously by the false documents and mistakes. In order to ensure the integrality, veracity and validity of project documents, the lifecycle theory of document is applied to build documents center, record center, structure and database of document lifecycle management system. And the lifecycle management is used to the documents of nuclear engineering projects from the production to pigeonhole, to satisfy the quality requirement of nuclear engineering projects. (authors)

  2. Integrated project risk management of nuclear power projects

    International Nuclear Information System (INIS)

    Wang Xiaohui; Xu Yuanhui

    2001-01-01

    The concept and the features of risks in nuclear power projects are introduced, and in terms of nuclear power projects' own features, the Nuclear Power Project Integrated Risk Management Model is presented. The identification, estimation, evaluation, response plan development, control of risks and the theoretical basis of risk management are discussed. The model has feedback and control functions in order to control and manage the risks dynamically

  3. Project Interface Requirements Process Including Shuttle Lessons Learned

    Science.gov (United States)

    Bauch, Garland T.

    2010-01-01

    Most failures occur at interfaces between organizations and hardware. Processing interface requirements at the start of a project life cycle will reduce the likelihood of costly interface changes/failures later. This can be done by adding Interface Control Documents (ICDs) to the Project top level drawing tree, providing technical direction to the Projects for interface requirements, and by funding the interface requirements function directly from the Project Manager's office. The interface requirements function within the Project Systems Engineering and Integration (SE&I) Office would work in-line with the project element design engineers early in the life cycle to enhance communications and negotiate technical issues between the elements. This function would work as the technical arm of the Project Manager to help ensure that the Project cost, schedule, and risk objectives can be met during the Life Cycle. Some ICD Lessons Learned during the Space Shuttle Program (SSP) Life Cycle will include the use of hardware interface photos in the ICD, progressive life cycle design certification by analysis, test, & operations experience, assigning interface design engineers to Element Interface (EI) and Project technical panels, and linking interface design drawings with project build drawings

  4. Designing the owner's nuclear project management organization

    International Nuclear Information System (INIS)

    Cooke, T.C.; Peck, B.H.

    1976-01-01

    Few decisions are more important to an electric utility company than the one to build a nuclear generating facility. This decision will require continuous management attention to the nuclear project for periods of up to ten years on the part of the utility. Effective management of such a large, complex project requires an owner's organization skilled in such areas as engineering, heavy construction, procurement, and project control. The paper describes a method for designing the owner's nuclear organization. Factors considered include the identification of milestone events and phases of the project and identification of key organizational groups and their degree of involvement. A series of important decision milestones is also identified for structuring the organization. A step-by-step analysis involving a set of evaluation criteria results in a recommended organization that can be staffed by the owner according to the degree of involvement desired. This technique of analysis could also be performed using different evaluation criteria resulting in other options for the owner's organization

  5. The project 'nuclear long-distance energy'

    International Nuclear Information System (INIS)

    Harth, R.

    1976-01-01

    The Kernforschungsanlage Juelich is intensively involved in research work with the aim of developing new technological skills for the future supply of energy and to lead the way in industry. In the forefront are a rational utilisation of primary energy and a better adjustment of the energy available, to fulfil requirements. In addition, the supply from nuclear power plants was analysed and a new energy supply system was achieved. It offers the possibility of giving nuclear-produced power to a large proportion of consumers fulfilling their heat and electricity needs, in which the accessible degrees of utilisation lie between 49% and 67%. The project 'nuclear long distance energy' is the theme of a report included in the Congress on Rational Utilisation of Energy, held from 20th to 23rd. september 1976 in Berlin. (orig.) [de

  6. 42 CFR 137.327 - May multiple projects be included in a single construction project agreement?

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false May multiple projects be included in a single construction project agreement? 137.327 Section 137.327 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF...-GOVERNANCE Construction Project Assumption Process § 137.327 May multiple projects be included in a single...

  7. Project management in nuclear equipment manufacture

    International Nuclear Information System (INIS)

    Liu Jiancheng

    2005-01-01

    The completion of the management organization shall be firstly considered in project management for a nuclear power plant. The organization of nuclear equipment quality assurance program and project management consists of 5 departments such as the nuclear power container department, the manufacture department and the quality assurance department. The general manager takes the overall responsibility for the quality of the nuclear press usr bearing equipment, and the vice general manager takes responsibility for the quality, technology and schedule related with the manufacture of the equipment, and organizes the organization department for the audit. The director of the quality assurance department takes the responsibility for the establishment and completion of the quality assurance program, with enough rights authorized by the general manager, including the right not bounded by the cost and schedule, and confirms the implementation of the program by related departments and personnel. The manufacture schedule shall be prepared to ensure the implementation feasibility, process continuity and flexibility. The schedule shall be followed and monitored for the whole process, to check and feedback the implementation. (authors)

  8. Next Generation Nuclear Plant Project Preliminary Project Management Plan

    International Nuclear Information System (INIS)

    Dennis J. Harrell

    2006-01-01

    This draft preliminary project management plan presents the conceptual framework for the Next Generation Nuclear Plant (NGNP) Project, consistent with the authorization in the Energy Policy Act of 2005. In developing this plan, the Idaho National Laboratory has considered three fundamental project planning options that are summarized in the following section. Each of these planning options is literally compliant with the Energy Policy Act of 2005, but each emphasizes different approaches to technology development risks, design, licensing and construction risks, and to the extent of commercialization support provided to the industry. The primary focus of this draft preliminary project management plan is to identify those activities important to Critical Decision-1, at which point a decision on proceeding with the NGNP Project can be made. The conceptual project framework described herein is necessary to establish the scope and priorities for the technology development activities. The framework includes: A reference NGNP prototype concept based on what is judged to be the lowest risk technology development that would achieve the needed commercial functional requirements to provide an economically competitive nuclear heat source and hydrogen production capability. A high-level schedule logic for design, construction, licensing, and acceptance testing. This schedule logic also includes an operational shakedown period that provides proof-of-principle to establish the basis for commercialization decisions by end-users. An assessment of current technology development plans to support Critical Decision-1 and overall project progress. The most important technical and programmatic uncertainties (risks) are evaluated, and potential mitigation strategies are identified so that the technology development plans may be modified as required to support ongoing project development. A rough-order-of-magnitude cost evaluation that provides an initial basis for budget planning. This

  9. Nuclear power. Volume 2: nuclear power project management

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The following topics are discussed: review of nuclear power plants; licensing procedures; safety analysis; project professional services; quality assurance and project organization; construction, scheduling and operation; construction, scheduling and operation; nuclear fuel handling and fuel management; and plant cost management. 116 references, 115 figures, 33 tables

  10. Nuclear power project management information system

    International Nuclear Information System (INIS)

    Zou Lailong; Zhang Peng; Xiao Ziyan; Chun Zengjun; Huang Futong

    2001-01-01

    Project Management Information System is an important infrastructure facility for the construction and operation of Nuclear Power Station. Based on the practice of Lingao nuclear power project management information system (NPMIS), the author describes the NPMIS design goals, system architecture and software functionality, points out the outline issues during the development and deployment of NPMIS

  11. Kazakhstan innovation projects in nuclear technologies field

    International Nuclear Information System (INIS)

    Shkol'nik, V.S.; Tukhvatulin, Sh.T.

    2005-01-01

    At present in the Republic of Kazakhstan in preparation and realization stage there are several innovation projects related with use of advanced nuclear technologies. Projects are as follows: 'Implementation of Kazakhstan thermonuclear reactor tokamak (KTM)'; 'Implementation at the L.N. Gumilev Eurasian National University the inter-disciplinary research complex on the heavy ions accelerator base'; 'Development of the Technological Park 'Nuclear Technologies Center in Kurchatov city'; 'Development the first in the Central-Asian region Center of Nuclear Medicine and Biophysics'. The initiator and principal operator of these projects is the National Nuclear Center of the Republic of Kazakhstan

  12. Feasibility of a joint nuclear project

    International Nuclear Information System (INIS)

    Leung, C.T.

    1980-01-01

    To meet the growing power demand in the late eighties, the People's Republic of China will cooperate with Hong Kong to develop nuclear power. In this paper, the energy policy of China and her nuclear capabilities are reviewed, and some of the foreseeable problems of the China and Hong Kong joint nuclear project are discussed. (author)

  13. Guidance for the application of an assessment methodology for innovative nuclear energy systems. INPRO manual - Overview of the methodology. Vol. 1 of 9 of the final report of phase 1 of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) including a CD-ROM comprising all volumes

    International Nuclear Information System (INIS)

    2008-11-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in the year 2000, based on a resolution of the IAEA General Conference (GC(44)/RES/21). The main objectives of INPRO are (1) to help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner, (2) to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles; and (3) to create a forum to involve all relevant stakeholders that will have an impact on, draw from, and complement the activities of existing institutions, as well as ongoing initiatives at the national and international level. This document follows the guidelines of the INPRO report 'Methodology for the assessment of innovative nuclear reactors and fuel cycles, Report of Phase 1B (first part) of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)', IAEA-TECDOC-1434 (2004), together with its previous report Guidance for the evaluation for innovative nuclear reactors and fuel cycles, Report of Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), IAEA-TECDOC-1362 (2003). This INPRO manual is comprised of an overview volume (laid out in this report), and eight additional volumes (available on a CD-ROM attached to the inside back cover of this report) covering the areas of economics (Volume 2), infrastructure (Volume 3), waste management (Volume 4), proliferation resistance (Volume 5), physical protection (Volume 6), environment (Volume 7), safety of reactors (Volume 8), and safety of nuclear fuel cycle facilities (Volume 9). The overview volume sets out the philosophy of INPRO and a general discussion of the INPRO methodology. This overview volume discusses the relationship of INPRO with the UN concept of sustainability to demonstrate how the

  14. Iraq nuclear facility dismantlement and disposal project

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, J R; Danneels, J [Sandia National Laboratories, Albuquerque, NM (United States); Kenagy, W D [U.S. Department of State, Bureau of International Security and Nonproliferation, Office of Nuclear Energy, Safety and Security, Washington, DC (United States); Phillips, C J; Chesser, R K [Center for Environmental Radiation Studies, Texas Tech University, Lubbock, TX (United States)

    2007-07-01

    The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

  15. Nuclear resonance apparatus including means for rotating a magnetic field

    International Nuclear Information System (INIS)

    Sugimoto, H.

    1983-01-01

    A nuclear magnetic resonance apparatus including magnet apparatus for generating a homogeneous static magnetic field between its magnetic poles, shims of a magnetic substance mounted on the magnetic poles to apply a first gradient magnetic field intensity distribution in a direction orthogonal as to the direction of line of magnetic force of the static magnetic field, gradient magnetic field generating electromagnetic apparatus for generating a second gradient magnetic field having a gradient magnetic field intensity distribution in superimposition with the static magnetic field and for changing the magnetic field gradient of the first gradient magnetic field, an oscillator for generating an oscillating output having a frequency corresponding to the nuclear magnetic resonance condition of an atomic nucleus to be measured, a coil wound around a body to be examined for applying the output of said oscillator as electromagnetic waves upon the body, a receiver for detecting the nuclear magnetic resonance signals received by the coil, a gradient magnetic field controller making a magnetic field line equivalent to the combined gradient magnetic fields and for rotating the line along the section of the body to be examined by controlling said gradient magnetic field generating electromagnetic apparatus and devices for recording the nuclear magnetic resonance signals, for reconstructing the concentration distribution of the specific atomic nuclei in the section of the body, and a display unit for depicting the result of reconstruction

  16. Spent Nuclear Fuel Project dose management plan

    International Nuclear Information System (INIS)

    Bergsman, K.H.

    1996-03-01

    This dose management plan facilitates meeting the dose management and ALARA requirements applicable to the design activities of the Spent Nuclear Fuel Project, and establishes consistency of information used by multiple subprojects in ALARA evaluations. The method for meeting the ALARA requirements applicable to facility designs involves two components. The first is each Spent Nuclear Fuel Project subproject incorporating ALARA principles, ALARA design optimizations, and ALARA design reviews throughout the design of facilities and equipment. The second component is the Spent Nuclear Fuel Project management providing overall dose management guidance to the subprojects and oversight of the subproject dose management efforts

  17. Proven approaches to organise a large decommissioning project, including the management of local stakeholder interests

    International Nuclear Information System (INIS)

    Rodriguez, A.

    2005-01-01

    Full text: Spanish experience holds a relatively important position in the field of the decommissioning of nuclear and radioactive facilities. Decommissioning projects of uranium concentrate mill facilities are near completion; some old uranium mine sites have already been restored; several projects for the dismantling of various small research nuclear reactors and a few pilot plants are at various phases of the dismantling process, with some already completed. The most notable Spanish project in this field is undoubtedly the decommissioning of the Vandellos 1 nuclear power plant that is currently ready to enter a safe enclosure, or dormancy, period. The management of radioactive wastes in Spain is undertaken by 'Empresa Nacional de Residuos Radioactivos, S.A.' (ENRESA), the Spanish national radioactive waste company, constituted in 1984. ENRESA operates as a management company, whose role is to develop radioactive waste management programmes in accordance with the policy and strategy approved by the Spanish Government. Its responsibilities include the decommissioning and dismantling of nuclear installations. Decommissioning and dismantling nuclear installations is an increasingly important topic for governments, regulators, industries and civil society. There are many aspects that have to be carefully considered, planned and organised in many cases well in advance of when they really need to be implemented. The goal of this paper is describe proven approaches relevant to organizing and managing large decommissioning projects, in particular in the case of Vandellos-1 NPP decommissioning. (author)

  18. Nuclear power. Volume 2. Nuclear power project management

    International Nuclear Information System (INIS)

    Pedersen, E.S.

    1978-01-01

    NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 2 contains the following chapters: (1) review of nuclear power plants; (2) licensing procedures; (3) safety analysis; (4) project professional services; (5) quality assurance and project organization; (6) construction, scheduling, and operation; (7) nuclear fuel handling and fuel management; (8) plant cost management; and (9) conclusion

  19. Radiological safety research for nuclear excavation projects - Interoceanic canal studies

    International Nuclear Information System (INIS)

    Klement, A.W. Jr.

    1969-01-01

    The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

  20. Radiological safety research for nuclear excavation projects - Interoceanic canal studies

    Energy Technology Data Exchange (ETDEWEB)

    Klement, Jr, A W [U.S. Atomic Energy Commission, Las Vegas, NV (United States)

    1969-07-01

    The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

  1. Spent Nuclear Fuel Project operational staffing plan

    International Nuclear Information System (INIS)

    Debban, B.L.

    1996-03-01

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

  2. Past nuclear power project experiences of Turkey

    International Nuclear Information System (INIS)

    Kutukcuoglu, A.

    1994-01-01

    In this paper, developments in the world for utilization of nuclear energy and, in parallel to these developments, works undertaken in Turkey are summarized. Besides this, future prospects in the field of nuclear energy in the world and in Turkey, and our opinion about the action to be taken in our county, in the light of past experiences of nuclear power projects that could not be succeeded, are presented

  3. Recruitment schemes in new nuclear projects

    International Nuclear Information System (INIS)

    Tielas, M.

    2012-01-01

    Contracting in New Nuclear Projects: A collaborative model between the Owner and the Supplier is described for building nuclear power plants, and is being implemented in the USA as well as in Europe to solve the problem of the risk in the initial investment as experienced in the past: widely exceeded budgets and construction schedules. (Author)

  4. Spent Nuclear Fuel (SNF) Project Execution Plan

    International Nuclear Information System (INIS)

    LEROY, P.G.

    2000-01-01

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

  5. Spent Nuclear Fuel (SNF) Project Execution Plan

    Energy Technology Data Exchange (ETDEWEB)

    LEROY, P.G.

    2000-11-03

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

  6. ENSAR, a Nuclear Science Project for European Research Area

    NARCIS (Netherlands)

    Turzó, Ketel; Lewitowicz, Marek; Harakeh, Muhsin N.

    2015-01-01

    During the period from September 2010 to December 2014, the European project European Nuclear Science and Applications Research (ENSAR) coordinated research activities of the Nuclear Physics community performing research in three major subfields: Nuclear Structure, Nuclear Astrophysics, and Nuclear

  7. Managing the first nuclear power plant project

    International Nuclear Information System (INIS)

    2007-05-01

    Energy is essential for national development. Nearly every aspect of development - from reducing poverty and raising living standards to improving health care, industrial and agricultural productivity - requires reliable access to modern energy resources. States may have different reasons for considering starting a nuclear power project to achieve their national energy needs, such as: lack of available indigenous energy resources, the desire to reduce dependence upon imported energy, the need to increase the diversity of energy resources and/or mitigation of carbon emission increases. The start of a nuclear power plant project involves several complex and interrelated activities with long duration. Experience shows that the time between the initial policy decision by a State to consider nuclear power up to the start of operation of its first nuclear power plant is about 10 to 15 years and that before specific project management can proceed, several key infrastructure issues have to be in place. The proper management of the wide scope of activities to be planned and implemented during this period represents a major challenge for the involved governmental, utility, regulatory, supplier and other supportive organizations. The main focus is to ensure that the project is implemented successfully from a commercial point of view while remaining in accordance with the appropriate engineering and quality requirements, safety standards and security guides. This publication is aimed at providing guidance on the practical management of a first nuclear power project in a country. There are many other issues, related to ensuring that the infrastructure in the country has been prepared adequately to ensure that the project will be able to be completed, that are only briefly addressed in this publication. The construction of the first nuclear power plant is a major undertaking for any country developing a nuclear power programme. Worldwide experience gained in the last 50 years

  8. Project safety studies - nuclear waste management (PSE)

    International Nuclear Information System (INIS)

    1981-10-01

    The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

  9. Project management for economical nuclear energy

    International Nuclear Information System (INIS)

    Majerle, P.P.

    2005-01-01

    The price of electricity is significantly influenced by the cost of the initial generation asset. The cost of the initial nuclear generation asset is significantly influenced by the design and construction duration. Negative variations in the cost and duration of actual design and construction have historically impacted the early relative economics of nuclear power generation. Successful management of plant design information will mitigate the risks of the design and construction of future nuclear plants. Information management tools that can model the integrated delivery of large complex projects enable the project owners to accurately evaluate project progress, as well as the economic impact of regulatory, political, or market activities not anticipated in the project execution plan. Significant differences exist in the electrical energy markets, project delivery models, and fuel availability between continents and countries. However, each market and project delivery model is challenged by the need to produce economical electrical energy. The information management system presented in this paper provides a means to capture in a single integrated computerized database the design information developed during plant design, procurement, and construction and to allow this information to be updated and retrieved in real time by all project participants. Utilization of the information management system described herein will enable diverse project teams to rapidly and reliably input, share, and retrieve power plant information, thereby supporting project management's goal to make good on its commitment to the economic promise of tomorrow's nuclear electrical power generation by achieving cost-effective construction. (authors)

  10. Nordic projects concerning nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1988-11-01

    The report describes the nature of the work done in the first half of 1988 within the field of nuclear safety (1985-89) under the Nordic program for 1985-89. Five programmes and their documentation, are described and complete lists of addresses and of persons involved is given. (AB)

  11. The nuclear desalination project in Morocco

    International Nuclear Information System (INIS)

    1996-01-01

    The objectives of the seawater desalination demonstration plant in Morocco are to buildup the technical confidence in the utilization of nuclear heating reactor for seawater desalination; to establish a data base for reliable extrapolation of water production costs for a commercial nuclear plant; and to further strengthen the nuclear infrastructure in Morocco. The water production capacity of the demonstration plant would be about 8000 m 3 /d. The objectives of pre-project study are to establish a reliable basis for a decision on a nuclear desalination plant in Morocco, using a small Chinese heating reactor and to train the Morocco experts in reactor technology and licensing aspects

  12. Nuclear project management experience in Korea

    International Nuclear Information System (INIS)

    Jae-Pung Jeon

    1987-01-01

    Korea Electric Power Corporation (KEPCO) has been dereloping nuclear power steadily over last 30 years to support effective economic growth of the nation with cheap electric power. In the course of development, KEPCO has experienced various project management patterns diverging from turn-key contracts with foreign vendors to non-turnkey with local affiliates. To culative own project management capabilities, one has to pay continuous efforts for better management systems development and manpower training. KEPCO is ready to share its priceless experiences gained over last three decades of nuclear project operation with any developing nation. (Liu)

  13. Agency for Nuclear Projects/Nuclear Waste Project Office final progress report

    International Nuclear Information System (INIS)

    1992-01-01

    The Nevada Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) was formally established by Executive Policy in 1983 following passage of the federal Nuclear Waste Policy Act of 1982 (Act). That Act provides for the systematic siting, construction, operation, and closure of high-level radioactive defense and research by-products and other forms of high-level radioactive waste from around the country which will be stored at such repositories. In 1985 the Nevada legislature formally established the NWPO as a distinct and statutorily authorized agency to provide support to the Governor and State Legislature on matters concerning the high-level nuclear waste programs. The NWPO utilized a small, central staff supplemented by contractual services for needed technical and specialized expertise in order to provide high quality oversight and monitoring of federal activities, to conduct necessary independent studies, and to avoid unnecessary duplication of efforts. This report summarizes the results of this ongoing program to ensure that risks to the environment and to human safety are minimized. It includes findings in the areas of hydrogeology, geology, quality assurance activities, repository engineering, legislature participation, socioeconomic affects, risk assessments, monitoring programs, public information dissemination, and transportation activities. The bulk of the reporting deals with the Yucca Mountain facility

  14. Roadmap for biofertilizer development project at Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Khairuddin Abdul Rahim; Ahmad Nazrul Abd Wahid; Phua Choo Kwai Hoe; Pauline Liew Woan Ying; Ahamad Sahali Mardi; Mat Rasol Awang

    2007-01-01

    This paper discusses the roadmap for the Biofertilizer Development Project conducted at the Malaysian Nuclear Agency (Nuclear Malaysia). The project started in 2003 and scheduled to end in 2008. Biofertilizer refers to living microorganisms or materials that contain living microorganisms that contributes to improvement in plant nutrition, soil fertility and crop productivity. The main components of the project are (a) biofertilizer substrate or carrier development, (b) biofertilizer inoculum development based on local indigenous microorganisms (c) biofertilizer product formulation and innovation, and (d) evaluation of efficiency of biofertilizer products on crops under different cropping systems, including under modern agriculture under soilless system. The above components may involve nuclear technology, viz, use of ionising radiation and the use of isotopic tracers. The paper also discusses local and international linkages, including with Forum for Nuclear Cooperation in Asia (FNCA) and the industry, and aspects of commercialisation and technology transfer. (Author)

  15. NORWAY: a nuclear demonstration project?

    CERN Multimedia

    Clery, Daniel

    2007-01-01

    "Egil Lillestøl is a man with a rather unusual mission: he wants his homeland of Norway to take the lead in developement of of a new form of nuclear power. Norway is Europe's largest petroleum exporter, from its North Sea oil and gas fields, and Lillestøl, a physicist at the University of Bergen, believes the country needs to do something about its carbon emissions.

  16. Terrorism cover in France for property damage including nuclear risks

    International Nuclear Information System (INIS)

    Stanislas, A.

    2004-01-01

    The obligation to include terrorism cover in all Property Damage policies issued on the French Market is ruled by an Act of 1986 and introduced under Section R 126-2 of the French Code of Insurance. This section stipulates that Property Damage policies must provide cover for damage resulting from acts of terrorism, with the same deductible and the same limit than that of the other damage covered in the policy. Soon after the dramatic events of September 11, 2001 in the United States and although reinsurers worldwide restricted their offer of capacities, French insurers recognized that they had to maintain this global cover for the benefit of their insurers. After difficult discussions between insurers, reinsurers, brokers, risk managers and representatives of the State, the creation of a new Pool, backed with a State guarantee, was decided in less than three months. Effective January 1, 2002 and called Gestion d'Assurance et de Reassurance des Risques Attentats et Actes de Terrorisme (GAREAT), the Pool offers a multiple layers stop-loss cover for Property Damage only, i.e. excluding TPL policies. Considering that nuclear risks should be treated in the same way as other industrial risks, it was decided that they would be covered by GAREAT as well. In the meantime, by a Decree of December 28, 2001 modifying Section R 126-2, a special provision, aiming at reducing the limit and thus the price of this cover, was introduced in the Code. The purpose of this paper is to expose the present situation applying through GAREAT and, after two years of operation to discuss future developments, including other sources of capacity for the coverage of acts of terrorism in nuclear risks insurance.(author)

  17. Spent nuclear fuel project product specification

    International Nuclear Information System (INIS)

    Pajunen, A.L.

    1998-01-01

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

  18. The EFF Project Status and the NEA Nuclear Data Services

    International Nuclear Information System (INIS)

    Henriksson, H.; Kodeli, I.; Nordborg, C.; Forrest, R.; Batistoni, P.; Fischer, U.

    2006-01-01

    The OECD Nuclear Energy Agency (NEA) Data Bank is part of an international network of data centres in charge of the compilation and dissemination of basic nuclear data. Through its activities in the reaction data field, the NEA participates in the production of data and their distribution to its users. The NEA Data Bank administrates the collection and validation as well as the distribution of the Joint Evaluated Fusion and Fission (JEFF) library. The JEFF project has evolved from two separate projects, namely the European Fusion File (EFF) and the Joint Evaluated File (JEF), to JEFF with the latest release of the library, JEFF-3.1, in May 2005. The EFF Project is a collaborative project with work funded by the European Fusion Development Agreement (EFDA). The tasks within the project comprise new data evaluation and verification of activation and transport data, calculation methods and validation via integral experiments. The EFF project brings together all available expertise in Europe, relating to the nuclear data requirements of existing and future fusion devices. EFF contributed greatly to the successful release of the internationally recognised nuclear data library JEFF-3.1. The NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC) is established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations and validation. WPEC provides a framework for co-operative activities between the participating projects, such as the high priority request list that is a collection of experimental data requests of special interest in a certain project, such as JEFF or ITER. The NEA provides also computer program services for nuclear energy and radiation physics applications. Of special interest for fusion applications are the integral experiments, such as SINBAD, with radiation shielding and dosimetry experiments including many fusion neutronics shielding experiments. (author)

  19. Decommissioning project of commercial nuclear power plant

    International Nuclear Information System (INIS)

    Karigome, S.

    2008-01-01

    Decommissioning project of commercial nuclear power plant in Japan was outlined. It is expected that the land, after the decommissioning of commercial nuclear power plants, will serve as sites for new plants. Steps will be taken to reduce the amount of wastes generated and to recycle/reuse them. Wastes with a radioactivity concentration below the 'clearance level' need not be dealt with as radioactive material, and may be handled in the same way as conventional wastes. The Tokai-1 power station, a 166 MWe carbon dioxide cooled reactor which closed down in 1998, is being decommissioned and the first ten years as 'safe storage' to allow radioactivity to decay. Non-reactor grade components such as turbines were already removed, heat exchanger dismantling started and the reactor will be dismantled, the buildings demolished and the site left ready for reuse. All radioactive wastes will be classified as low-level wastes in three categories and will be buried under the ground. The total cost will be 88.5 billion yen -34.7 billion for dismantling and 53.8 billion for waste treatment including the graphite moderator. (T. Tanaka)

  20. Including the smoking epidemic in internationally coherent mortality projections

    NARCIS (Netherlands)

    Janssen, Fanny; van Wissen, Leo J. G.; Kunst, Anton E.

    2013-01-01

    We present a new mortality projection methodology that distinguishes smoking- and non-smoking-related mortality and takes into account mortality trends of the opposite sex and in other countries. We evaluate to what extent future projections of life expectancy at birth (e 0) for the Netherlands up

  1. Including the smoking epidemic in internationally coherent mortality projections

    NARCIS (Netherlands)

    Janssen, F.; van Wissen, L.J.G.; Kunst, A.E.

    2013-01-01

    We present a new mortality projection methodology that distinguishes smoking- and non-smoking-related mortality and takes into account mortality trends of the opposite sex and in other countries. We evaluate to what extent future projections of life expectancy at birth (e0) for the Netherlands up to

  2. Including the smoking epidemic in internationally coherent mortality projections

    NARCIS (Netherlands)

    Janssen, Fanny; van Wissen, Leo J. G.; Kunst, Anton E.

    We present a new mortality projection methodology that distinguishes smoking- and non-smoking-related mortality and takes into account mortality trends of the opposite sex and in other countries. We evaluate to what extent future projections of life expectancy at birth (e (0)) for the Netherlands up

  3. Project management skills for nuclear power plants

    International Nuclear Information System (INIS)

    Bhatikar, R.J.

    2002-01-01

    Full text: The E and C Division of L and T has executed several power projects in India and abroad and thus possesses the requisite wherewithal to execute nuclear power projects on a fast track basis. To achieve this L and T has set up a separate Strategic Business Unit (SBU) to have a focused attention to the nuclear power industry in the country. All the four important and necessary hallmarks for successful implementation of any project namely (i) engineering capabilities, (ii) sophisticated project management tools, (iii) ability to mobilize resources, and (iv) skilled personnel to execute the project have been adequately addressed. These could be realized either by establishing fruitful collaborations with other specialist Companies and/or creating powerful and multitasking software tools for effective implementation. The execution of nuclear power projects on a fast track basis could be implemented by following the EPC route and by minimizing the number of packages. Details of this scheme for project implementation will be highlighted during the talk

  4. Nuclear industry project audit and countermeasures

    International Nuclear Information System (INIS)

    Li Yongxin; Zhang Jian

    2012-01-01

    With China's increasing use of nuclear energy, nuclear power related construction projects related to the deepening of the audit, some of the nuclear industry in construction field of the dominant issues have been more effective containment, such as inflated workload, high-set fixed standards, to improve billing unit price, which overestimate the risk calculation tools and behavior completed audit of the accounts have been able to escape his stuff. However, some nuclear industry construction field with a hidden problem because of its hidden nature, not easily found, and some even have intensified the trend. Construction funds to the country such problems caused by the loss of waste is enormous, to the breeding of corruption provided the soil is fertile, if not promptly and effectively to stop the breeding will spread. This paper on the current construction of the nuclear industry in several major areas of the hidden problems are discussed, and the angle from the audit of appropriate countermeasures. (authors)

  5. Radiation and nuclear safety included in the environmental health programme

    International Nuclear Information System (INIS)

    Salomaa, S.

    1996-01-01

    Finland is currently preparing a national environmental health programme, the objective of which is to chart the main environmental health problems in Finland, to identify means for securing a healthy environment, and to draw up a practical action programme for preventing and rectifying problems pertaining to environmental health. Radiation and nuclear safety form an essential part of preventive health care. The action programme is based on decisions and programmes approved at the WHO Conference on the Environment and Health, held in Helsinki in June 1994. In addition to the state of the Finnish environment and the health of the Finnish population, the programme addresses the relevant international issues, in particular in areas adjacent to Finland. The Committee on Environmental Health is expected to complete its work by the end of the year. A wide range of representatives from various branches of administration have contributed to the preparation of the programme. Besides physical, biological and chemical factors, the environmental factors affecting health also include the physical environment and the psychological, social and aesthetic features of the environment. Similarly, environmental factors that have an impact on the health of present or future generations, on the essential preconditions of life and on the quality of life are investigated. The serious risk to nature caused by human actions is also considered as a potential risk to human health. (orig.)

  6. Project Icarus: Nuclear Fusion Propulsion Concept Comparison

    Science.gov (United States)

    Stanic, M.

    Project Icarus will use nuclear fusion as the primary propulsion, since achieving breakeven is imminent within the next decade. Therefore, fusion technology provides confidence in further development and fairly high technological maturity by the time the Icarus mission would be plausible. Currently there are numerous (over 2 dozen) different fusion approaches that are simultaneously being developed around the World and it is difficult to predict which of the concepts is going to be the most successful one. This study tried to estimate current technological maturity and possible technological extrapolation of fusion approaches for which appropriate data could be found. Figures of merit that were assessed include: current technological state, mass and volume estimates, possible gain values, main advantages and disadvantages of the concept and an attempt to extrapolate current technological state for the next decade or two. Analysis suggests that Magnetic Confinement Fusion (MCF) concepts are not likely to deliver sufficient performance due to size, mass, gain and large technological barriers of the concept. However, ICF and PJMIF did show potential for delivering necessary performance, assuming appropriate techno- logical advances. This paper is a submission of the Project Icarus Study Group.

  7. New nuclear projects: structure, supply chain and financing

    International Nuclear Information System (INIS)

    Keppler, J.H.; Cometto, M.

    2015-01-01

    In 2015 there were 68 reactors being constructed throughout the world and 159 projects were planned. The projects for the construction of nuclear reactors face challenging issues like financing and management. The NEA (Nuclear Energy Agency) has analysed the feedback experience on a sample of reactor projects and of reactors recently commissioned in order to draw lessons on 3 issues: financing, long-term electricity price, and project management including the supply chain. It is already known that technologies requiring high initial capital like nuclear power or renewable energies, are very sensitive to the long-term price of electricity. The study shows that for a debt ratio below 60%, the risk for the investor is low even if the long-term electricity price drops by 30 %. Because of the complexity of the construction of a nuclear power plant there are mainly 3 types of project management: the turnkey project, the split package approach (a relatively low number of suppliers) and the multi-contract approach. The turnkey approach is favoured by the new entrants in the nuclear world. The harmonization of regulations and the convergence of the safety requirements are necessary to build an efficient and competitive supply chain. (A.C.)

  8. Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

    Bougaenko, S.E.; Kraev, A.E.; Hill, D.L.; Braun, J.C.; Klickman, A.E.

    1998-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project

  9. Indian manpower for mega nuclear project

    CERN Multimedia

    2003-01-01

    "India is supplying critical scientific manpower and high-tech components needed for building a Large Hadron Collider (LHC) - an accelerator used in particle physics research - a mega scientific project of the European Organisation for Nuclear Research (CERN) worth billions of dollars" (1/2 page).

  10. Spent nuclear fuel project product specification

    International Nuclear Information System (INIS)

    PAJUNEN, A.L.

    1999-01-01

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

  11. Nuclear new build: Financing and project management

    International Nuclear Information System (INIS)

    Keppler, Jan Horst; Cometto, Marco

    2015-01-01

    As there are more nuclear power reactors under construction today than at any time in history, the authors present in a first part an economic and financial analysis comparing the respective exposure of gas-fired and nuclear power generation to electricity price uncertainty and examine the option of leaving the market in the case of a permanent fall in electricity prices. In a second part, the study more specifically addresses the financial risk associated with the development of a new nuclear project, taking into account not only uncertainty about the future evolution of prices but also about the cost of construction and operations, as well as the implications of different ratios of fixed cost to variable cost for bondholders and equity investors. The authors then address the issue of the management of new build projects and their supply chains, as the nuclear industry is undergoing a number of important developments with massive and discontinuous technological changes that are underway as generation II nuclear power plants (NPPs) are substituted by larger and more complex generation III/III+ plants. The loss of skill and human capital as engineers of the nuclear building boom of the 1970's and 1980's retire must also be factored in, as well as the reconfiguration of the global supply chain, which is driven both by new possibilities in data management, externalisation and logistics, and a secular shift of activity from the United States, Japan, Europe and Korea to China, Southeast Asia and the Middle East

  12. Nuclear Desalination Demonstration Project (NDDP) in India

    International Nuclear Information System (INIS)

    Tewari, P.K.; Misra, B.M.

    2001-01-01

    In order to gainfully employ the years of experience and expertise in various aspects of desalination activity, BARC (India) has undertaken installation of a hybrid nuclear desalination plant coupled to 170 MW(e) PHWR station at Kalpakkam, Chennai in the Southeast coast of India. The integrated system, called the Nuclear Desalination Demonstration Project (NDDP), will thus meet the dual needs of process water for nuclear power plant and drinking water for the neighbouring people. NDDP aims for demonstrating the safe and economic production of good quality water by nuclear desalination of seawater. It comprises a 4500 m 3 /d Multistage Flash (MSF) and a 1800 m 3 /d Reverse Osmosis (RO) plant. MSF section uses low pressure steam from Madras Atomic Power Station (MAPS), Kalpakkam. The objectives of the NDDP (Kalpakkam) are as follows: to establish the indigenous capability for the design, manufacture, installation and operation of nuclear desalination plants; to generate necessary design inputs and optimum process parameters for large scale nuclear desalination plant; to serve as a demonstration project to IAEA welcoming participation from interested member states. The hybrid plant is envisaged to have a number of advantages: a part of high purity desalted water produced from MSF plant will be used for the makeup demineralised water requirement (after necessary polishing) for the power station; blending of the product water from RO and MSF plants would provide requisite quality drinking water; the RO plant will continue to be operated to provide the water for drinking purposes during the shutdown of the power station

  13. Initiating a nuclear power project - client's viewpoint

    International Nuclear Information System (INIS)

    Rieh, C.H.

    1985-01-01

    Based upon our experience in Korea, for any country that wants to effectively introduce nuclear plants, the authors recommend the following preparation for accepting the advanced nuclear technology prior to its implementation: training personnel, organizing domestic industries for the technology transfer, and establishing laws, regulations and licensing procedures related to nuclear development. Technical self-sufficiency in nuclear power plant construction and operation must be achieved step by step under a long term master plan. Localization, or internal self-sufficiency, is enhanced by repetitive construction of the same reactor type using a non-turnkey construction method. The project owner should, most of all, improve his management capability for the success of the project along with economic effectiveness. International cooperation among the developing countries who are introducing or planning to introduce nuclear power plant, is expected to play an important role in resolving unique problems which may commonly exist in their nuclear program. In this regard, Korea is prepared to share its accumulated experiences with other developing countries

  14. The Jeff evaluated nuclear data project

    Energy Technology Data Exchange (ETDEWEB)

    Koning, A.J.; Duijvestijn, M.C.; Hogenbirk, A.; Van der Marck, S.C.; Avrigeanu, M.; Avrigeanu, V.; Batistoni, P.; Pillon, M.; Bauge, E.; Bersillon, O.; Dos-Santos-Uzarralde, P.; Lopez Jimenez, M.J.; Morillon, B.; Romain, P.; Be, M.M.; Duchemin, B.; Huynh, T.D.; Jouanne, C.; Mounier, C.; Bem, P.; Bernard, D.; Bouland, O.; Courcelle, A.; Dupont, E.; Jacqmin, R.; Litaize, O.; Noguere, G.; Saint Jean, C. de; Santamarina, A.; Serot, O.; Sublet, J.Ch.; Bidaud, A.; Dean, C.J.; Perry, R.J.; Duhamel, I.; Nouri, A.; Gunsing, F.; Ridikas, D.; Fischer, U.; Leichtle, D.; Pereslavtsev, P.; Simakov, S.; Forrest, R.A.; Haeck, W.; Henriksson, H.; Kodeli, I.; Nordborg, C.; Rugama, Y.; Sartori, E.; Keinert, J.; Mattes, M.; Kellett, M.A.; Nichols, A.L.; Kopecky, J.; Leeb, H.; Leppanen, J.; Menapace, E.; Pescarini, M.; Mills, R.W.; Perel, R.L.; Plompen, A.J.M.; Rullhusen, P.; Seidel, K.; Tagesen, S.; Vonach, H.; Trkov, A

    2008-07-01

    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. JEFF-3.1 comprises a significant update of actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library JEFF-3.1/A, the decay data and fission yield sub-libraries, and fusion-related data files from the EFF project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory and shielding of thermal and fast systems. Compared with earlier releases, JEFF-3.1 provides improved performance with respect to a variety of scientific and industrial applications. Following on from the public release of JEFF-3.1, the French nuclear power industry has selected this suite of nuclear applications libraries for inclusion in their production codes. (authors)

  15. The Jeff evaluated nuclear data project

    International Nuclear Information System (INIS)

    Koning, A.J.; Duijvestijn, M.C.; Hogenbirk, A.; Van der Marck, S.C.; Avrigeanu, M.; Avrigeanu, V.; Batistoni, P.; Pillon, M.; Bauge, E.; Bersillon, O.; Dos-Santos-Uzarralde, P.; Lopez Jimenez, M.J.; Morillon, B.; Romain, P.; Be, M.M.; Duchemin, B.; Huynh, T.D.; Jouanne, C.; Mounier, C.; Bem, P.; Bernard, D.; Bouland, O.; Courcelle, A.; Dupont, E.; Jacqmin, R.; Litaize, O.; Noguere, G.; Saint Jean, C. de; Santamarina, A.; Serot, O.; Sublet, J.Ch.; Bidaud, A.; Dean, C.J.; Perry, R.J.; Duhamel, I.; Nouri, A.; Gunsing, F.; Ridikas, D.; Fischer, U.; Leichtle, D.; Pereslavtsev, P.; Simakov, S.; Forrest, R.A.; Haeck, W.; Henriksson, H.; Kodeli, I.; Nordborg, C.; Rugama, Y.; Sartori, E.; Keinert, J.; Mattes, M.; Kellett, M.A.; Nichols, A.L.; Kopecky, J.; Leeb, H.; Leppanen, J.; Menapace, E.; Pescarini, M.; Mills, R.W.; Perel, R.L.; Plompen, A.J.M.; Rullhusen, P.; Seidel, K.; Tagesen, S.; Vonach, H.; Trkov, A.

    2008-01-01

    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. JEFF-3.1 comprises a significant update of actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library JEFF-3.1/A, the decay data and fission yield sub-libraries, and fusion-related data files from the EFF project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory and shielding of thermal and fast systems. Compared with earlier releases, JEFF-3.1 provides improved performance with respect to a variety of scientific and industrial applications. Following on from the public release of JEFF-3.1, the French nuclear power industry has selected this suite of nuclear applications libraries for inclusion in their production codes. (authors)

  16. Nuclear human resource projection up to 2030 in KOREA

    International Nuclear Information System (INIS)

    Min, Byung Joo; Lee, Man Ki; Nam, Kee Yung; Jeong, Ki Ho

    2011-01-01

    The prospects for growth of the nuclear power industry in Korea have improved remarkably as the demand for energy increases in stride with economic development. Meanwhile, as nuclear energy development is enhanced, nuclear technology has also improved evolutionarily and innovatively in the areas of reactor design and safety measures. As nuclear technology development in Korea advances, more human resources are required. Accordingly, the need for a well-managed program of human resource development (HRD) aimed at assuring needed capacities, skills, and knowledge and maintaining valuable human resources through education and training in various nuclear-related fields has been recognized. A well-defined and object-oriented human resource development and management (HRD and M) is to be developed in order to balance between the dynamics of supply and demand of the workforce in the nuclear industry. The HRD and M schemes include a broad base of disciplines, education, sciences, and technologies within a framework of national sustainable development goals, which are generally considered to include economics, environment, and social concerns. In this study, the projection methodology considering a variety of economic, social, and environmental factors was developed. Using the developed methodology, medium- and long-term nuclear human resources projections up to 2030 were conducted in compliance with the national nuclear technology development programmes and plans

  17. Nuclear data evaluation methodology including estimates of covariances

    Directory of Open Access Journals (Sweden)

    Smith D.L.

    2010-10-01

    Full Text Available Evaluated nuclear data rather than raw experimental and theoretical information are employed in nuclear applications such as the design of nuclear energy systems. Therefore, the process by which such information is produced and ultimately used is of critical interest to the nuclear science community. This paper provides an overview of various contemporary methods employed to generate evaluated cross sections and related physical quantities such as particle emission angular distributions and energy spectra. The emphasis here is on data associated with neutron induced reaction processes, with consideration of the uncertainties in these data, and on the more recent evaluation methods, e.g., those that are based on stochastic (Monte Carlo techniques. There is no unique way to perform such evaluations, nor are nuclear data evaluators united in their opinions as to which methods are superior to the others in various circumstances. In some cases it is not critical which approaches are used as long as there is consistency and proper use is made of the available physical information. However, in other instances there are definite advantages to using particular methods as opposed to other options. Some of these distinctions are discussed in this paper and suggestions are offered regarding fruitful areas for future research in the development of evaluation methodology.

  18. Measures to improve nuclear power project management

    International Nuclear Information System (INIS)

    Ma Xinchao

    2012-01-01

    Focusing on correct application of ability level principle in setting organizational structure, the effective management system has been established, and 8 practical management regimes have been developed. Personnel training and management work shall be well done and enhanced. Experience feedback in construction management shall be well done for all systems. Exchange of construction and management techniques shall be actively carried out. All staff shall participate in safety management. KPI system is adopted for assessing stakeholders' project management method, and PDCA cycle is adopted for continued improved. Management level upgrading measures are proposed to ensure the smooth construction of nuclear power project. Setting forth and popularizing management theory can provide reference for and promote the smooth progress of various nuclear power projects. (author)

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

    International Nuclear Information System (INIS)

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

  20. Spent nuclear fuel project technical databook

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1998-01-01

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values

  1. Spent nuclear fuel project technical databook

    Energy Technology Data Exchange (ETDEWEB)

    Reilly, M.A.

    1998-07-22

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

  2. Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability

    Energy Technology Data Exchange (ETDEWEB)

    Golay, Michael [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    2016-10-30

    This project aims to go beyond effective communication in understanding how to design nuclear enterprise projects that will gain stakeholder acceptability. Much of what we are studying is generally applicable to controversial projects, and we expect our results to be of broad value beyond the nuclear arena. Acceptability is more than effective communication; it also requires varying degrees of engagement with a disparate number of stakeholder groups. In the nuclear enterprise, previous attempts have been well designed physically (i.e., technologically sound), but have floundered by being insensitive concerning acceptance. Though effective communication is a necessary, but insufficient, condition for such success, there is a lack of scholarship regarding how to gain stakeholder acceptance for new controversial projects, including nuclear ones. Our work is building a model for use in assessing the performance of a project in the area of acceptability. In the nuclear-social nexus, gaining acceptance requires a clear understanding of factors regarded as being important by the many stakeholders that are common to new nuclear project (many of whom hold an effective veto power). Projects tend to become socially controversial when public beliefs, expert opinion and decision-maker understanding are misaligned. As such, stakeholder acceptance is hypothesized as both an ongoing process and an initial project design parameter comprised of complex, social, cognitive and technical components. Controversial projects may be defined as aspects of modern technologies that some people question, or are cautious about. They could range from genetic modifications, biological hazards, effects of chemical agents, nuclear radiation or hydraulic fracturing operations. We intend that our work will result in a model likely to be valuable for refining project design and implementation to increase the knowledge needed for successful management of stakeholder relationships.

  3. Energy secretary's priorities include San Francisco area research projects

    CERN Multimedia

    Widener, A

    2003-01-01

    "Bay Area research labs got a big boost Monday when the Secretary of Energy unveiled his priorities for major research projects his agency hopes to fund over the next two decades. Among the agency's 28 top priorities are a major computer expansion and an experiment examining the expanding universe that could be housed at Lawrence Berkeley Lab and a powerful X-ray laser planned for the Stanford Linear Accelerator Center" (1 page).

  4. The nuclear fuel cycle including essential aspects of safety

    International Nuclear Information System (INIS)

    Warnemuende, R.; May, H.

    1978-11-01

    When judging nuclear energy not only the reactor but also the whole fuel cycle is of importance. The fuel cycle consists of the supply, i.e. the process from uranium ore to the insertion of fuel elements into the reactor and the waste management, the removal of fuel elements from the reactor and the final storage of radioactive waste. The different stages of the nuclear fuel cycle are well known with regard to their technical difficulties, their problems of industrial safety and pollution. Although it is possible to compare them qualitatively, they still differ partly to a considerable extent, from a quantitative point of view. However, the fact that technical solutions are available for all kinds of tasks can be stated. It is significant for the Federal Republic of Germany that all essential preparatory work for closing the nuclear fuel cycle has been carried out and that safety problems will no longer be in the way of the large-scale realization of uranium enrichment, reprocessing of nuclear fuels and final storage of radioactive waste. Further research and development activities will serve its technical and economic optimization. (orig.) [de

  5. Nuclear matter descriptions including quark structure of the hadrons

    International Nuclear Information System (INIS)

    Huguet, R.

    2008-07-01

    It is nowadays well established that nucleons are composite objects made of quarks and gluons, whose interactions are described by Quantum chromodynamics (QCD). However, because of the non-perturbative character of QCD at the energies of nuclear physics, a description of atomic nuclei starting from quarks and gluons is still not available. A possible alternative is to construct effective field theories based on hadronic degrees of freedom, in which the interaction is constrained by QCD. In this framework, we have constructed descriptions of infinite nuclear matter in relativistic mean field theories taking into account the quark structure of hadrons. In a first approach, the in medium modifications of mesons properties is dynamically obtained in a Nambu-Jona-Lasinio (NJL) quark model. This modification is taken into account in a relativistic mean field theory based on a meson exchange interaction between nucleons. The in-medium modification of mesons masses and the properties of infinite nuclear matter have been studied. In a second approach, the long and short range contributions to the in-medium modification of the nucleon are determined. The short range part is obtained in a NJL quark model of the nucleon. The long range part, related to pions exchanges between nucleons, has been determined in the framework of Chiral Perturbation theory. These modifications have been used to constrain the couplings of a point coupling relativistic mean field model. A realistic description of the saturation properties of nuclear matter is obtained. (author)

  6. [Nuclear energy and environment: review of the IAEA environmental projects].

    Science.gov (United States)

    Fesenko, S; Fogt, G

    2012-01-01

    The review of the environmental projects of the International Atomic Energy Agency is presented. Basic IAEA documents intended to protect humans and the Environment are considered and their main features are discussed. Some challenging issues in the area of protection of the Environment and man, including the impact of nuclear facilities on the environment, radioactive waste management, and remediation of the areas affected by radiological accidents, nuclear testing and sites of nuclear facilities are also discussed. The need to maintain the existing knowledge in radioecology and protection of the environment is emphasised.

  7. Progressive Finland sees progress with nuclear projects

    Energy Technology Data Exchange (ETDEWEB)

    Dalton, David [NucNet, Brussels (Belgium)

    2016-02-15

    The Finnish Hanhikivi-1 reactor project is firmly on track and a licence has been granted for construction of a final disposal facility for spent nuclear fuel - the first final repository in the world to enter the construction phase. Significant progress has been made with plans for Finland to build its sixth nuclear reactor unit at Hanhikivi. Fennovoima's licensing manager Janne Liuko said the company expects to receive the construction licence for the Generation III+ Hanhikivi-1 plant in late 2017. The application was submitted to the Finnish Ministry of Employment and the Economy in June 2015.

  8. A Study on Site Selecting for National Project including High Level Radioactive Waste Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kilyoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Many national projects are stopped since sites for the projects are not determined. The sites selections are hold by NIMBY for unpleasant facilities or by PYMFY for preferable facilities among local governments. The followings are the typical ones; NIMBY projects: high level radioactive waste disposal, THAAD, Nuclear power plant(NPP), etc. PIMFY projects: South-east new airport, KTX station, Research center for NPP decommission, etc. The site selection for high level radioactive waste disposal is more difficult problem, and thus government did not decide and postpone to a dead end street. Since it seems that there is no solution for site selection for high level radioactive waste disposal due to NIMBY among local governments, a solution method is proposed in this paper. To decide a high level radioactive waste disposal, the first step is to invite a bid by suggesting a package deal including PIMFY projects such as Research Center for NPP decommission. Maybe potential host local governments are asked to submit sealed bids indicating the minimum compensation sum that they would accept the high level radioactive waste disposal site. If there are more than one local government put in a bid, then decide an adequate site by considering both the accumulated PESS point and technical evaluation results. By considering how fairly preferable national projects and unpleasant national projects are distributed among local government, sites selection for NIMBY or PIMFY facilities is suggested. For NIMBY national projects, risk, cost benefit analysis is useful and required since it generates cost value to be used in the PESS. For many cases, the suggested method may be not adequate. However, similar one should be prepared, and be basis to decide sites for NIMBY or PIMFY national projects.

  9. Advanced nuclear reactor public opinion project

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-07-25

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

  10. Advanced nuclear reactor public opinion project

    International Nuclear Information System (INIS)

    Benson, B.

    1991-01-01

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions

  11. Status Report Kuwait Nuclear Data Project

    Energy Technology Data Exchange (ETDEWEB)

    Farhan, A. [Kuwait Nuclear Data Center, Kuwait University, Kuwait (Kuwait)

    2013-08-15

    This report covers the Kuwaiti group's activities for the period April 2011 - January 2013. The Kuwait Group will continue its collaboration in order to fulfill its commitments. The Kuwait Nuclear Data Project has permanent responsibility for evaluating and updating ENSDF for A = 74 -80. The status of the mass chains is: - A = 74 (2006), - A = 75 (1999) {radical}, - A = 76 (1995) {radical}, - A = 77 (2012), - A = 78 (2009), - A = 79 (2002), - A = 80 (2005)

  12. Nuclear safety research project. Annual report 1995

    International Nuclear Information System (INIS)

    Hueper, R.

    1996-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1995 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1996. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

  13. Economic evaluation of nuclear plant project

    International Nuclear Information System (INIS)

    Tolba, Adel.

    1988-01-01

    The present work is an attempt to prepare a ''fair price'' estimate to serve as bench mark in the course of economic evaluation of bids to construct nuclear power plants. The methodology of determining the present value of all capital investment is used. Running costs of nuclear fuel, operation, and maintenance are also determined. As a result, levelized energy cost is calculated. Sensitivity analysis for different parameters has been conducted, and the results of which are included in this paper

  14. A Guide to Running a Recycling Project. [Includes Recycling Handbook].

    Science.gov (United States)

    Oregon Recycling Information and Organizing Network, Portland.

    This guide, designed for both students and adults, is intended for individuals who feel they might be interested in establishing a recycling depot. The guide includes such pertinent information as deciding how to set up a depot, markets and transportation, preparation of materials, where to place the depot and when to operate it, publicity and…

  15. Nuclear medicine. In vivo diagnosis, PET not included

    International Nuclear Information System (INIS)

    Herain, C.; Machacek, C.; Menechal, P.; Aubert, B.; Rehel, J.L.; Vidal, J.P.; Biau, A.; Barbe, R.; Lahaye, T.; Gauron, C.; Barret, C.; Donnarieix, D.; Gambini, D.; Gondran, C.; Guerin, C.; Marande, J.L.; Mercier, J.; Paycha, F.; Pierrat, N.

    2011-12-01

    This document deals with radiation protection measures and practices in the medical sector, more particularly when performing in vivo diagnosis in nuclear medicine. It indicates the concerned personnel, the procedure process, the associated hazards and the risks related to ionizing radiation (for sealed and unsealed sources). It describes how risk is to be assessed and exposure levels are to be determined (elements of risk assessment, delimitation of controlled and monitored areas, personnel classification). It presents the different aspects of a risk management strategy (risk reduction, technical measures for the premises, the installation, radioactive wastes, and for radioactive effluents, protection measures and equipment, training and information, prevention, treatment of incidents and dysfunctions). It describes the various aspects of medical monitoring (personnel, pregnant and breast feeding women, medical and post-occupational file, processing of anomalies and incidents). It presents how risk management is to be assessed, and briefly evokes other related risks. An appendix presents an example of a workstation study in case of nuclear medicine

  16. US company's new nuclear project progresses

    International Nuclear Information System (INIS)

    Archie, Jeffrey B.

    2011-01-01

    Operated by South Carolina Electric and Gas Company in the southeastern United States, V.C. Summer Nuclear Station has maintained a reputation of excellence for more than 25 years. The key to its success: placing safety as its first priority, keeping a keen focus on operations, establishing a culture of continuous learning, and embracing collaboration with industry peers. This philosophy guides its new nuclear project, which SCE and G has undertaken to meet the need for baseload generation in its service area in a manner that is clean, safe, reliable, and efficient. In the process, SCE and G is generating jobs and boosting the economy. Site preparation has been under way since 2009. SCE and G anticipates receiving its combined construction and operating license from the Nuclear Regulatory Commission, the independent, federal agency that oversees commercial nuclear power plants in the U.S., in late 2011 or early 2012, which will allow major construction to commence. The 2 new reactors are scheduled to begin commercial operation in 2016 and 2019, respectively, placing V.C. Summer at the forefront of a U.S. nuclear renaissance and carrying its legacy of excellence into the future. (orig.)

  17. Denmark's greenhouse gas projections until 2012, an update including a preliminary projection until 2017

    International Nuclear Information System (INIS)

    Fenham, J.

    2003-01-01

    This report presents the results of a project financed by the Danish Energy Agency. The purpose of the project is to make 'with measures' projections of the emissions from Danish sources of the greenhouse gases, CO 2 , CH 4 , N 2 O, HFCs, PFCs and SF 6 . The 'with measures' projection encompasses currently implemented and adopted policies and measures. The time period covered is from 1972, the first year detailed Danish energy statistics were produced, until the first commitment period (2008-2012) under the Kyoto Protocol to the Climate Convention. A preliminary projection is also made for the second commitment period (2013-2017), but here no projections are available for the agricultural sector and the emissions from this sector has therefore been kept equal to the emissions in the first commitment period. Estimations of HFCs, PFCs and SF 6 -emissions and projections cover the period from 1993 until 2020. Only emissions caused by human activities are included in the calculations. However, it can sometimes be difficult to draw the borderline between emissions from nature and anthropogenic emissions. Due to small differences between the methodology used in this project and the methodology (CORINAIR) used by the National Environmental Research Institute for the purpose of annual reporting the estimated emissions presented for the period 1990-2000 may deviate from the official emission estimates report to the EU and the Climate Convention (UNFCCC). Therefore the GHG emission estimates presented in this report for the period until 2000 should only be seen as an illustration of the order of magnitude. This is also the case for the parts of the trend analyses, which are based on the historic data coming from this project. The description of the emissions in the report is structured according to the IPCC sectors: 1) Energy. 2) Industrial processes. 3) Agriculture. 4) Land use change and forestry. 5) Waste. The NMVOC emission from solvent use and other sources is included

  18. Radiation protection in nuclear emergencies, including thyroid blockage with iodine

    International Nuclear Information System (INIS)

    Niklas, K.

    1991-01-01

    The Government of the Federal Republic of Germany has set emergency reference levels of radiation doses at which countermeasures such as sheltering, evacuation, iodine prophylaxis and resettlement should be considered in case of severe accidents in nuclear installations. Emergency facilities are to be set up for a range of meausres to protect the public, such as assessment of contamination and subsequent decontamination. Recommendations as to further therapeutic measures will be made by medical personnel. The administration of stable iodine can block or reduce the accumulation of radioiodine in the thyroid gland. Stable potassium iodine tablets (100 mg each) will be distributed by the local authorities. Since iodine deficiency is still prevalent in large parts of the Federal Republic of Germany, iodine prophylaxis will be recommended only when relatively high radiation doses to the thyroid gland are to be expected. Resettlement of the population must be considered if an excessive dose is expected in the affected area over a long period. (orig.) [de

  19. Financing strategy for Indonesian Nuclear Power Project

    International Nuclear Information System (INIS)

    Subki, I.M.; Arbie, B.; Adiwardojo; Seotrisnanto, A.Y.

    1998-01-01

    In anticipation of the introduction in the early 2000s of a nuclear power plant, the Government of Indonesia (GOI), through the National Atomic Energy Agency (BATAN) , has formulated a Bid Invitation Specification (BIS) in parallel with the completion of the NPP Feasibility Study. This BIS formulation assumed an open international tender for the first unit of the NPP with project financing as a conventional loan. The GOI's recent policy is to minimize government financial support for power development. This paper summarizes a financing strategy for the Indonesian NPP project to make the NPP economically viable, and provides a general discussion on project financing using a conventional approach, Build--Own-Operate (BOO) and a counter-purchase approach. Innovative approaches for financing are still being pursued in order to obtain an optimum solution for investors and owners, to fulfill the Indonesian government's requirements. (author)

  20. A desk evaluation review of project RAF/4/004 nuclear instruments maintenance. Project desk evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-04-15

    A Project Desk Evaluation (PDE) is an intensive review process, using agreed guidelines, of the design, implementation, and the outputs of a project. This project was originally intended for six selected countries in Africa, namely, Algeria, Egypt, Ghana, Libya, Zaire and Zambia. Ethiopia and Tanzania joined in 1993 and it has now been extended to two other countries, Madagascar and Sudan. This is a step forward towards developing the infrastructure for nuclear instrumentation and maintenance is as many countries in Africa as require this service. A project summary along with financial data and recommendations for improvements are given. A table where total assistance provided to ten selected african countries is included.

  1. A desk evaluation review of project RAF/4/004 nuclear instruments maintenance. Project desk evaluation

    International Nuclear Information System (INIS)

    1994-01-01

    A Project Desk Evaluation (PDE) is an intensive review process, using agreed guidelines, of the design, implementation, and the outputs of a project. This project was originally intended for six selected countries in Africa, namely, Algeria, Egypt, Ghana, Libya, Zaire and Zambia. Ethiopia and Tanzania joined in 1993 and it has now been extended to two other countries, Madagascar and Sudan. This is a step forward towards developing the infrastructure for nuclear instrumentation and maintenance is as many countries in Africa as require this service. A project summary along with financial data and recommendations for improvements are given. A table where total assistance provided to ten selected african countries is included

  2. State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, January 1992

    International Nuclear Information System (INIS)

    1992-01-01

    The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada's responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency's oversight responsibilities: (1) Assure that the health and safety of Nevada's citizens are adequately protected with regard to any federal high-level radioactive waste program within the State; (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987; (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State; (4) Work closely and consult with affected local governments and State agencies; (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository

  3. Future global manpower shortages in nuclear industries with special reference to india including remedial measures

    International Nuclear Information System (INIS)

    Ghosh Hazra, G.S.

    2008-01-01

    -2050. Service sector in India accounts for about 50% of GDP which will continue to increase further and will provide more jobs and better paid jobs than core industries and there will be continued shift of choice of employment towards service sector creating deep gap of manpower resource requirement in basic and core industries. There are reports that some countries may have to abandon some future projects because of non availability skilled manpower in core industries. The installed capacity of nuclear power in India in the year 2052 will be about 200 G We from the present about 4 G We which will be a manifold increase. This will need about estimated 1,30,000 skilled manpower from the present about 12,000 persons in nuclear industries. Moreover, the need for competent persons in nuclear industries because of high safety requirements of nuclear installations will further add to the problem. The following short-term strategies to retain and attract new employees in nuclear industries may be envisaged amongst others: - Recruit employees prior to the departure of experienced technical staff to facilitate knowledge transfer in time. - Increase compensation and the number of higher level positions. - Increase permanent entry-level intake of skilled manpower taking into account historical turn-over rate. - Implement attractive student loan repayment programs by tying up with banks and financial institutions. - Implement well researched strategies and measures including reassessing the practical capacity which nations including India can achieve in power generation in future taking practical aspects of manpower shortage. - Implement advanced technology which requires lesser manpower. - Implement higher level of automation in nuclear industries. The paper aims to highlight the acute problems of future manpower shortages in nuclear industries globally with special reference to India and discusses some remedial measures which may be taken to address the issue. (author)

  4. Great expectations. Projections of nuclear power around the world

    International Nuclear Information System (INIS)

    McDonald, Alan; Rogner, Hans-Holger; Gritsevskyi, Andrii

    2009-01-01

    In its 2008 edition of Energy, Electricity and Nuclear Power Estimates for the Period to 2030, the International Atomic Energy Agency (IAEA) has again revised its projections for nuclear power upwards. Every year since 1981 the IAEA has published 2 updated projections for the world's nuclear power generating capacity, a low projection and a high projection. The low projection is a down to earth, business-as-usual projection. The high projection takes into account government and corporate announcements about longer-term plans for nuclear investments as well as potential new national policies, e.g., to combat climate change. The results for the 2008 projections are presented. In the low projection, the projected nuclear power capacity in 2030 is 473 GW(e), some 27% higher than today's 372 GW(e). In the high projection, nuclear capacity in 2030 is 748 GW(e), double today's capacity. But while projections for nuclear power's future rose, its share of the world's electricity generation today dropped from 15% in 2006 to 14% in 2007. The main reason is that while total global electricity generation rose 4.8% from 2007 to 2008, nuclear electricity actually dropped slightly. The overall message from the IAEA's 2008 edition of Energy, Electricity and Nuclear Power Estimates for the Period to 2030 is that global electricity use will grow significantly, that nuclear power will have to expand more rapidly than it has done recently in order to maintain its share, and that nuclear power can meet the challenge. (orig.)

  5. Regional nuclear fuel cycle centers study project

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  6. Spent Nuclear Fuel (SNF) Project Product Specification

    International Nuclear Information System (INIS)

    PAJUNEN, A.L.

    2000-01-01

    The process for removal of Spent Nuclear Fuel (SNF) from the K Basins has been divided into major sub-systems. The Fuel Retrieval System (FRS) removes fuel from the existing storage canisters, cleans it, and places it into baskets. The multi-canister overpack (MCO) loading system places the baskets into an MCO that has been pre-loaded in a cask. The cask, containing a loaded MCO, is then transferred to the Cold Vacuum Drying (CVD) Facility. After drying at the CVD Facility, the cask, and MCO, are transferred to the Canister Storage Building (CSB), where the MCO is removed from the cask, staged, inspected, sealed (by welding), and stored until a suitable permanent disposal option is implemented. The purpose of this document is to specify the process related characteristics of an MCO at the interface between major process systems. The characteristics are derived from the primary technical documents that form the basis for safety analysis and design calculations. This document translates the calculation assumptions into implementation requirements and describes the method of verifying that the requirement is achieved. These requirements are used to define validation test requirements and describe requirements that influence multiple sub-project safety analysis reports. This product specification establishes limits and controls for each significant process parameter at interfaces between major sub-systems that potentially affect the overall safety and/or quality of the SNF packaged for processing, transport, and interim dry storage. The product specifications in this document cover the SNF packaged in MCOs to be transported throughout the SNF Project. The description of the product specifications are organized in the document as follows: Section 2.0--Summary listing of product specifications at each major sub-system interface. Section 3.0--Summary description providing guidance as to how specifications are complied with by equipment design or processing within a major

  7. Spent Nuclear Fuel (SNF) Project Product Specification

    Energy Technology Data Exchange (ETDEWEB)

    PAJUNEN, A.L.

    2000-12-07

    The process for removal of Spent Nuclear Fuel (SNF) from the K Basins has been divided into major sub-systems. The Fuel Retrieval System (FRS) removes fuel from the existing storage canisters, cleans it, and places it into baskets. The multi-canister overpack (MCO) loading system places the baskets into an MCO that has been pre-loaded in a cask. The cask, containing a loaded MCO, is then transferred to the Cold Vacuum Drying (CVD) Facility. After drying at the CVD Facility, the cask, and MCO, are transferred to the Canister Storage Building (CSB), where the MCO is removed from the cask, staged, inspected, sealed (by welding), and stored until a suitable permanent disposal option is implemented. The purpose of this document is to specify the process related characteristics of an MCO at the interface between major process systems. The characteristics are derived from the primary technical documents that form the basis for safety analysis and design calculations. This document translates the calculation assumptions into implementation requirements and describes the method of verifying that the requirement is achieved. These requirements are used to define validation test requirements and describe requirements that influence multiple sub-project safety analysis reports. This product specification establishes limits and controls for each significant process parameter at interfaces between major sub-systems that potentially affect the overall safety and/or quality of the SNF packaged for processing, transport, and interim dry storage. The product specifications in this document cover the SNF packaged in MCOs to be transported throughout the SNF Project. The description of the product specifications are organized in the document as follows: Section 2.0--Summary listing of product specifications at each major sub-system interface. Section 3.0--Summary description providing guidance as to how specifications are complied with by equipment design or processing within a major

  8. Nuclear heating solutions. Realizations and projects

    International Nuclear Information System (INIS)

    Dumitrescu, Monica; Prisecaru, Ilie

    2009-01-01

    Considering the present situation of thermal energy in Romania and having in view the fact that Romania is a Kyoto protocol signatory state one estimates that the development of the nuclear energy will have a promising growth. According with the statement of the National Energetic Observer, Romania became a net energy resource importer for the past 30 years and the estimations about the future are not optimistic. The finite reserves of fossil fuel (coal and natural gas), the gradual reduction of their share in the national energy balance with a tendency to become insignificant after 2025, as well as the present situation of the thermal power plants which are already beyond their operation life, all these indicate the nuclear energy as being the most reliable and sustainable future source for thermal energy production. Having in view these circumstances the paper aims at a short presentation of the existing nuclear solutions for district heating. Also, reviewed are the reactor projects that are under different development stage in the world, as well as the best nuclear solutions to be possibly implemented in Romania. The article represents a synthesis of the documentation made by PhD student Monica Dumitrescu in her preparation stage. (authors)

  9. NASA's nuclear electric propulsion technology project

    International Nuclear Information System (INIS)

    Stone, J.R.; Sovey, J.S.

    1992-07-01

    The National Aeronautics and Space Administration (NASA) has initiated a program to establish the readiness of nuclear electric propulsion (NEP) technology for relatively near-term applications to outer planet robotic science missions with potential future evolution to system for piloted Mars vehicles. This program was initiated in 1991 with a very modest effort identified with nuclear thermal propulsion (NTP); however, NEP is also an integral part of this program and builds upon NASA's Base Research and Technology Program in power and electric propulsion as well as the SP-100 space nuclear power program. The NEP Program will establish the feasibility and practicality of electric propulsion for robotic and piloted solar system exploration. The performance objectives are high specific impulse (200 greater than I(sub sp) greater than 10000 s), high efficiency (over 0.50), and low specific mass. The planning for this program was initially focussed on piloted Mars missions, but has since been redirected to first focus on 100-kW class systems for relatively near-term robotic missions, with possible future evolution to megawatt-and multi-megawatt-class systems applicable to cargo vehicles supporting human missions as well as to the piloted vehicles. This paper reviews current plans and recent progress for the overall nuclear electric propulsion project and closely related activities. 33 refs

  10. Projected cost comparison of nuclear electricity

    International Nuclear Information System (INIS)

    Juhn, P.E.; Hu, C.W.

    2000-01-01

    Comparison of electricity generation costs has been done in the late years through a large co-operation between several organisations. The studies are aiming to provide reliable comparison of electricity generating costs of nuclear and conventional base load power plants. This paper includes the result of the joint IAEA/OECD study published in 1997. (author)

  11. The EFF project status and the NEA nuclear data services

    Energy Technology Data Exchange (ETDEWEB)

    Henriksson, H. [OECD Nuclear Energy Agency, 12 Blvd des Iles, 92130 Issy-les-Moulineaux (France)], E-mail: henriksson@nea.fr; Batistoni, P. [Associazione Euratom-ENEA sulla Fusione, Via E. Fermi 45, 00044 Frascati (Italy); Fischer, U. [Association FZK-Euratom, Postfach 3640, 76021 Karlsruhe (Germany); Forrest, R. [Euratom/UKAEA Fusion Association, Culham Science Centre, Oxfordshire OX14 3DB (United Kingdom); Kodeli, I.; Nordborg, C. [OECD Nuclear Energy Agency, 12 Blvd des Iles, 92130 Issy-les-Moulineaux (France)

    2007-10-15

    The OECD Nuclear Energy Agency (NEA) Data Bank participates in the production of data and their distribution to users including the collection and validation as well as the distribution of the Joint Evaluated Fission and Fusion (JEFF) library. The JEFF project has evolved from two separate projects, namely the European Fusion File (EFF) and the Joint Evaluated File (JEF), with the release of JEFF-3.1, in May 2005. The NEA also provides tools for the EFF project, such as computer codes for nuclear energy and radiation physics applications. Of special interest for fusion applications are the integral experiments collected in the SINBAD database, with radiation shielding and dosimetry experiments including many fusion neutronics shielding experiments. In this paper an overview will be given of the NEA, and some examples of nuclear data services offered, such as the SINBAD database. JANIS, a display program evaluated and experimental data developed at the NEA will be mentioned briefly. The main emphasis will be given to the EFF project including the contents of the new JEFF-3.1 library, released in May 2005. Examples of recent work are given as well as a discussion on the forth-coming evaluation efforts among the EFF collaborators.

  12. The EFF project status and the NEA nuclear data services

    International Nuclear Information System (INIS)

    Henriksson, H.; Batistoni, P.; Fischer, U.; Forrest, R.; Kodeli, I.; Nordborg, C.

    2007-01-01

    The OECD Nuclear Energy Agency (NEA) Data Bank participates in the production of data and their distribution to users including the collection and validation as well as the distribution of the Joint Evaluated Fission and Fusion (JEFF) library. The JEFF project has evolved from two separate projects, namely the European Fusion File (EFF) and the Joint Evaluated File (JEF), with the release of JEFF-3.1, in May 2005. The NEA also provides tools for the EFF project, such as computer codes for nuclear energy and radiation physics applications. Of special interest for fusion applications are the integral experiments collected in the SINBAD database, with radiation shielding and dosimetry experiments including many fusion neutronics shielding experiments. In this paper an overview will be given of the NEA, and some examples of nuclear data services offered, such as the SINBAD database. JANIS, a display program evaluated and experimental data developed at the NEA will be mentioned briefly. The main emphasis will be given to the EFF project including the contents of the new JEFF-3.1 library, released in May 2005. Examples of recent work are given as well as a discussion on the forth-coming evaluation efforts among the EFF collaborators

  13. International project GT-MHR - New generation of nuclear reactors

    International Nuclear Information System (INIS)

    Vasyaev, A.; Kodochigov, N.; Kuzavkov, N.; Kuznetsov, L.

    2001-01-01

    Gas turbine-modular helium reactor (GT-MHR) is the reactor of new generation, which satisfies the requirements of the progressing large-scale nuclear power engineering. The activities in GT-MHR Project started in 1995. In 1997 the Conceptual Design was developed under four-side Agreement (MINATOM, General Atomics, FRAMATOME, Fuji Electric); it has passed through the internal and international reviews, has been approved and recommended for further development as one of new trends in creation of new generation plants. Starting from 1999, the activities in the development of the Preliminary Design of the plant were deployed under the Agreement between the Government of the United States of America and the Government of the Russian Federation on Scientific and Technical Cooperation in the Management of Plutonium That Has Been Withdrawn From Nuclear Military Programs dated July 24, 1998. The activities are established under the Contract between MINATOM and OKBM Russia, and under the General Agreement between Department of Energy (DOE), USA and OKBM. The GT-MHR Project is included into 'Development Strategy of Russian Nuclear Power in the first Half of the XXI-st Century' providing for 'the participation in an international project on the development and construction of GT-MHR nuclear power plant till year 2010 and 'operation of GT-MHR prototype unit and creation of fuel fabrication facility (within framework of International Project) till year 2030'. (author)

  14. Tecnatom support to new nuclear power plant projects

    International Nuclear Information System (INIS)

    Manrique, A. B.

    2009-10-01

    Tecnatom is a Spanish engineering company with more than 50 years of experience working for the nuclear industry all over the world. It has worked in over 30 countries in activities related to the operation and maintenance of nuclear power plants. Along this half century of history. Tecnatom has been providing its services to nuclear utilities, regulators, NPP vendors, NPP owners / operators and nuclear fuel manufacturers not only in Spain but also abroad. It started to work in the design of new nuclear power plants in the early 90 s and since then has continued collaborating with different suppliers in the design and licensing of new reactors especially in the areas of plant systems design, man-machine interface design, main control room simulators building, training, qualification of equipment and PSI/ISI engineering services. Some challenges to the reactivation of nuclear power plants construction are common worldwide, including: regulatory processes, workforce availability, construction project management, etc. Being some keys to success the following: apply qualified resources, enough resources for early planning, project leadership, organization and integration, establish a strong integrated management team. The goal of this paper is to inform regarding the capabilities of Tecnatom in the construction of new power plants. (Author)

  15. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    Baumann, B.L.

    1983-01-01

    The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

  16. Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods

    Science.gov (United States)

    Mariani, Robert Dominick

    2014-09-09

    Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350.degree. C. to 750.degree. C., and a second additive having a solubility in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350.degree. C. to 750.degree. C. and a solubility of the second additive in the first additive over the temperature range extending from 350.degree. C. to 750.degree. C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.

  17. The project of Esfahan Nuclear Technology Center (ENTEC) and the transfer of nuclear tecnology in Iran

    International Nuclear Information System (INIS)

    Khazaneh, Reza

    1977-01-01

    In 1974, the Atomic Energy Organization of Iran (AEOI) decided to set up a Nuclear Technology Center on Esfahan (ENTEC) in collaboration with France's Technicatome Company and the CEA. This center is scheduled to go into operation during 1976-1980. The purposes for setting up ENTEC are threefold: a. to give scientific and technical support to the operation of nuclear power plants and nuclear industries in Iran. b. to carry out research and development in the area of nuclear technology on an industrial level. c. to give supplementary education and training to the manpower needs for the AEOI. To carry out the program of technology transfer, temporary laboratories have been set up in Tehran for engineers, technicians and training programs have been organized primarily in France. The ENTEC project will also include a school for education of junior scientists and engineers in the field of nuclear technology

  18. Implementing national nuclear safety plan at the preliminary stage of nuclear power project development

    International Nuclear Information System (INIS)

    Xue Yabin; Cui Shaozhang; Pan Fengguo; Zhang Lizhen; Shi Yonggang

    2014-01-01

    This study discusses the importance of nuclear power project design and engineering methods at the preliminary stage of its development on nuclear power plant's operational safety from the professional view. Specifically, we share our understanding of national nuclear safety plan's requirement on new reactor accident probability, technology, site selection, as well as building and improving nuclear safety culture and strengthening public participation, with a focus on plan's implications on preliminary stage of nuclear power project development. Last, we introduce China Huaneng Group's work on nuclear power project preliminary development and the experience accumulated during the process. By analyzing the siting philosophy of nuclear power plant and the necessity of building nuclear safety culture at the preliminary stage of nuclear power project development, this study explicates how to fully implement the nuclear safety plan's requirements at the preliminary stage of nuclear power project development. (authors)

  19. Nuclear outages: an approach to project controls

    International Nuclear Information System (INIS)

    Bryson, R.

    1985-01-01

    The annual budget for maintaining and operating a nuclear power plant has risen dramatically over the past 5 years. NRC-mandated plant improvements and outage related expenses are often cited to be the main contributors to these escalating budgets. Nuclear utilities have responded by developing programs to improve plant availability and outage costs through improved outage performance. Utilities recognize that for capital improvements the program to control costs does no begin with outage planning, but rather more appropriately up front during the engineering phase. To support their management objectives, utilities have been developing comprehensive project control systems for concurrently reducing capital expenditures, outage-related costs, and time. This paper provides an approach to project controls that, rather than using one all inclusive comprehensive system, requires five separate monitoring systems - one for each phase of an activity's life cycle. Through the integration of these discrete but interrelated systems, utility management acquires the necessary tools for comprehensive planning and control of their modification program and effective detailed monitoring for all outage-related activities

  20. Hanford Spent Nuclear Fuel Project recommended path forward

    International Nuclear Information System (INIS)

    Fulton, J.C.

    1994-10-01

    The Spent Nuclear Fuel Project (the Project), in conjunction with the U.S. Department of Energy-commissioned Independent Technical Assessment (ITA) team, has developed engineered alternatives for expedited removal of spent nuclear fuel, including sludge, from the K Basins at Hanford. These alternatives, along with a foreign processing alternative offered by British Nuclear Fuels Limited (BNFL), were extensively reviewed and evaluated. Based on these evaluations, a Westinghouse Hanford Company (WHC) Recommended Path Forward for K Basins spent nuclear fuel has been developed and is presented in Volume I of this document. The recommendation constitutes an aggressive series of projects to construct and operate systems and facilities to safely retrieve, package, transport, process, and store K Basins fuel and sludge. The overall processing and storage scheme is based on the ITA team's proposed passivation and vault storage process. A dual purpose staging and vault storage facility provides an innovative feature which allows accelerated removal of fuel and sludge from the basins and minimizes programmatic risks beyond any of the originally proposed alternatives. The projects fit within a regulatory and National Environmental Policy Act (NEPA) overlay which mandates a two-phased approach to construction and operation of the needed facilities. The two-phase strategy packages and moves K Basins fuel and sludge to a newly constructed Staging and Storage Facility by the year 2000 where it is staged for processing. When an adjoining facility is constructed, the fuel is cycled through a stabilization process and returned to the Staging and Storage Facility for dry interim (40-year) storage. The estimated total expenditure for this Recommended Path Forward, including necessary new construction, operations, and deactivation of Project facilities through 2012, is approximately $1,150 million (unescalated)

  1. Project for the formation of a nuclear consciousness

    International Nuclear Information System (INIS)

    Pereira, O.S.; Rosa, M.D.S.; Negretti, C.; Faletti, R.

    1998-01-01

    The acceptance of the use of nuclear energy and radioactivity is still a controversial subject - it is taboo, plagued by prejudice and the lack of information. The 1987 radiological accident with Cs-137 in Goiania reinforced old prejudices and negative images surrounding this issue. For this reason, the Physics Department of the Pio XII High School in Sao Paulo developed an interdisciplinary project for high school students on the formation of a nuclear consciousness. In this project, several aspects of this topic were discussed in chemistry, biology, Portuguese and computer science classes. In 1995, teachers and students analysed the atomic bomb explosions of Hiroshima and Nagasaki, in 1996, the nuclear accident at Chernobyl, and in 1997, the radiological accident of Goiania. Beyond studying other basic subjects related to this issue (nuclear chemistry, radiation, energy, genetics, etc.), the work included the discussion of the risks and benefits of the nuclear era, and by considering the many sides of the issue, a balanced view was sought in the presentations to students. Work in 1997 ended with the production by the students of 15 amateur videos which reviewed the causes and effects of the Goiania accident, with some presentations going so far as reconstituting the accident. (author)

  2. 42 CFR 137.329 - What environmental considerations must be included in the construction project agreement?

    Science.gov (United States)

    2010-10-01

    ... must be included in the construction project agreement? The construction project agreement must include..., and (d) An assurance that no action will be taken on the construction phase of the project that would... 42 Public Health 1 2010-10-01 2010-10-01 false What environmental considerations must be included...

  3. Technical management of difference in CEPR nuclear power project

    International Nuclear Information System (INIS)

    Guo Ruiting

    2014-01-01

    The Thesis dissertate the application of technical management of difference in CEPR Nuclear Power Project from EPR technical bases, condition of a nuclear power plant site, engineering and procurement, construction, quality management, schedule management and experience feedback aspects. (author)

  4. ERP project implementation and risk management of nuclear power enterprise

    International Nuclear Information System (INIS)

    Wang Fei

    2008-01-01

    According to the characteristic and development trend of nuclear power enterprise informatization, combined with the general ERP implementation experience, the method is proposed to ensure the successful implementation and risk management of ERP project in nuclear power enterprise. (authors)

  5. Nuclear chemistry project. Progress report, January 1, 1978--December 31, 1978

    International Nuclear Information System (INIS)

    Naumann, R.A.

    1978-01-01

    Research on the nuclear chemistry project is summarized including Coulomb capture of negative muons by atoms and molecules, nuclear structure and spectroscopy, and the preparation and use of radioactive targets both to study the internal electric fields acting on the nuclei of foreign atoms introduced in metallic solids by radioactive decay and determination of nuclear moments by optical hyperfine spectroscopy

  6. 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

  7. Nordic projects in the field of nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1988-05-01

    This report deseribes the work in 1987 within the Nordic program concerning nuclear safety 1985-1989. The report has the form of a handbook meant for those in Scandinavia who are involved in nuclear safety, and it is based on statements from the constituent subject fields of the program. The first chapter is a short summary of the work and results over the year. In the next chapter an account is given of the ongoing projects within each of the subject fields. An economic survey of the entire program and a list of the reports and articles published in 1987 is included in the publication as well. Chapter 5 is a complete list of adresses comprising participants, project managers, program coordinators and members of the advisory group. (SH) 74 refs

  8. Nordic projects in the field of nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1989-07-01

    This report describes the work in 1988 within the Nordic program concerning nuclear safety 1985-1989. The report has the form of a handbook meant for those in Scandinavia who are involeved in nuclear safety, and it is based on statements from the constituent subject fields of the program. The first chapter is a short summary of the work and results over the year. In the next chapter an account is given of the ongoing projects within each of the subject fields. An economic survey of the entire program and a list of the reports and articles published in 1988 is included in the publicaltion as well. Chapter 5 is a complete list of adresses comprising participants, project managers, program coordinators and members of the advirosy group. (SH)

  9. Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements

    International Nuclear Information System (INIS)

    KLEM, M.J.

    2000-01-01

    In 1998, a major change in the technical strategy for managing Multi Canister Overpacks (MCO) while stored within the Canister Storage Building (CSB) occurred. The technical strategy is documented in Baseline Change Request (BCR) No. SNF-98-006, Simplified SNF Project Baseline (MCO Sealing) (FDH 1998). This BCR deleted the hot conditioning process initially adopted for the Spent Nuclear Fuel Project (SNF Project) as documented in WHC-SD-SNF-SP-005, Integrated Process Strategy for K Basins Spent Nuclear Fuel (WHC 199.5). In summary, MCOs containing Spent Nuclear Fuel (SNF) from K Basins would be placed in interim storage following processing through the Cold Vacuum Drying (CVD) facility. With this change, the needs for the Hot Conditioning System (HCS) and inerting/pressure retaining capabilities of the CSB storage tubes and the MCO Handling Machine (MHM) were eliminated. Mechanical seals will be used on the MCOs prior to transport to the CSB. Covers will be welded on the MCOs for the final seal at the CSB. Approval of BCR No. SNF-98-006, imposed the need to review and update the CSB functions and requirements baseline documented herein including changing the document title to ''Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements.'' This revision aligns the functions and requirements baseline with the CSB Simplified SNF Project Baseline (MCO Sealing). This document represents the Canister Storage Building (CSB) Subproject technical baseline. It establishes the functions and requirements baseline for the implementation of the CSB Subproject. The document is organized in eight sections. Sections 1.0 Introduction and 2.0 Overview provide brief introductions to the document and the CSB Subproject. Sections 3.0 Functions, 4.0 Requirements, 5.0 Architecture, and 6.0 Interfaces provide the data described by their titles. Section 7.0 Glossary lists the acronyms and defines the terms used in this document. Section 8.0 References lists the

  10. Bid Preparation and Evaluation for Nuclear Power Plant Project Management

    International Nuclear Information System (INIS)

    Mohd Idris Taib, Mohd Khairulezwan Abdul Manan and Nur Farizan Amadzun

    2011-01-01

    Bid preparation and evaluation is one of the main activities in Nuclear Power Plant Project management. International Atomic Energy Agency guide and Korean experience was studied for Malaysian requirement in realization of first Nuclear Power Plant. Several aspects shall be taken into consideration such as political scenario, financial capabilities, sitting, human resource, technologies, fuel supplies and decommissioning for long term exceeded hundred years. Bidding process and activities is proposed for our country requirement. The main activities included but unlimited to Bid Invitation Specification, Bid Evaluation Process, Technical Evaluation, Economic Bid Evaluation and Contracting. On the end of day, Malaysia need safe and reliable Nuclear Power Plant. Malaysian Economic Transformation Programme also get benefit from spin-off localization products and services as well as Technology Transfer Programme. (author)

  11. Critical path analysis in early stage of nuclear power project

    International Nuclear Information System (INIS)

    Xie Ahai

    2009-01-01

    The technical program and contract model as well as project management system and preliminary design defined in the early stage of nuclear power project are the key condition impact on the quality, schedule and cost of the nuclear power project. This paper, taking the CPR1000 coastal nuclear power station as an example, analyzes the critical path in the early stage of nuclear power project for five fields, i.e. licensing, design and procurement, site preparation, tender of construction contracts and construction preparation, and organization. (authors)

  12. Financing of nuclear power projects in developing countries

    International Nuclear Information System (INIS)

    1991-06-01

    This document is a summary of the ''Topical Seminar on Financing of Nuclear Power Projects in Developing Countries, held in Jakarta between 4-7 September, 1990. The seminar presentations were divided into the following sessions: Keynote session (3 papers), Perspective of Nuclear and Fossil-fired Generation Costs (9 papers), Assessment of Problems and Constraints for the Financing of Large Power Projects, with particular Attention to Nuclear Power Projects (9 papers), Mechanisms for Financing Nuclear Power Projects in Developing Countries (11 papers). A separate abstract was prepared for each of these papers. Refs, figs, tabs and charts

  13. Project designing of Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Krychtalek, Z.; Linek, V.

    1989-01-01

    The geological and seismic parameters are listed of the Temelin nuclear power plant. The division of the site in building zones is described. The main zones consist of the power generation unit zone with the related auxiliary buildings of hot plants and of the auxiliary buildings of the nonactive part with industrial buildings. The important buildings are interconnected with communication and technology bridges. Cooling towers and spray pools and the entrance area are part of the urbanistic design. The architectonic design of the buildings uses standard building elements and materials. The design of the buildings is based on the requirements on their function and on structural load and on the demands of maximal utilization of the type of the reinforced concrete prefab structure system. The structure is made of concrete or steel cells. The project design is based on Soviet projects. The layout is shown of the main power generation units and a section is presented of a 1,000 MW unit. (J.B.). 2 figs

  14. Qinshan Phase III (CANDU) nuclear power project quality assurance

    International Nuclear Information System (INIS)

    Wang Lingen; Du Jinxiang

    2001-01-01

    The completion and implementation of quality assurance system of Qinshan Phase III (CANDU) nuclear power project are presented. Some comments and understanding with consideration of the project characteristics are put forward

  15. An alternative projection model of future nuclear capacity

    International Nuclear Information System (INIS)

    Takei, Mitsuo

    1985-01-01

    There is generally a high degree of uncertainty involved in the projection of growth of any energy source, especially when the projection extends 50 years ahead. The 1982 OECD/NEA Report, 'Nuclear Energy and its Fuel Cycle Prospect to 2025' notes the downturn in past projections of nuclear capacity over the past decade. It is obvious that rapidly changing conditions have affected overall worldwide energy and economic growth and the field of nuclear power has been subject to changes specific to itself. These have caused past projections to become obsolete and therefore it would seem necessary to implement a new projection method to improve the accuracy of present forecasting. (author)

  16. The Thai-Canadian nuclear human resources development linkage project

    International Nuclear Information System (INIS)

    Sumitra, Tatchai; Chankow, Nares; Bradley, K.; Bereznai, G.

    1998-01-01

    The Thai-Canadian Nuclear Human Resources Development Linkage Project (the P roject ) was initiated in 1994 in order to develop the engineering and scientific expertise needed for Thailand to decide whether and how the country can best benefit from the establishment of a nuclear power program. The Project was designed to upgrade current academics and people in industry, and to develop an adequate supply of new technical personnel for academic, industry, utility, regulatory and other government institutions. The key Project objectives included the establishment of a Chair in Nuclear Engineering at Chulalongkorn University, the upgrading of the current Masters level curriculum, the establishment of undergraduate and doctorate level curricula, development and delivery of an industrial training program for people in industry and government, exchanges of Thai and Canadian academics and industry experts to establish common research programs and teaching interests, and a public education program that was to test in Thailand some of the techniques that have been successfully used in Canada. (author)

  17. Study on archive management for nuclear facility decommissioning projects

    International Nuclear Information System (INIS)

    Huang Ling; Gong Jing; Luo Ning; Liao Bing; Zhou Hao

    2011-01-01

    This paper introduces the main features and status of the archive management for nuclear facility decommissioning projects, and explores and discusses the countermeasures in its archive management. Taking the practice of the archive management system of a reactor decommissioning project as an example, the paper illustrates the establishment of archive management system for the nuclear facility decommissioning projects. The results show that the development of a systematic archive management principle and system for nuclear decommissioning projects and the construction of project archives for the whole process from the design to the decommissioning by digitalized archive management system are one effective route to improve the complete, accurate and systematic archiving of project documents, to promote the standardization and effectiveness of the archive management and to ensure the traceability of the nuclear facility decommissioning projects. (authors)

  18. Spent nuclear fuel project quality assurance program plan

    International Nuclear Information System (INIS)

    Lacey, R.E.

    1997-01-01

    This main body of this document describes how the requirements of 10 CFR 830.120 are met by the Spent Nuclear Fuel Project through implementation of WHC-SP-1131. Appendix A describes how the requirements of DOE/RW-0333P are met by the Spent Nuclear Fuel Project through implementation of specific policies, manuals, and procedures

  19. Annual colloquium 1976 of the project nuclear safety

    International Nuclear Information System (INIS)

    1976-11-01

    The present report gives the full text of the nine papers read during the annual colloquium 1976 of the Project Nuclear Safety at Karlsruhe Nuclear Research Centre, in which the main activities and findings of the project in 1976 are contained. (RW) [de

  20. Construction of special structures for nuclear power projects

    International Nuclear Information System (INIS)

    Raghavan, N.

    2003-01-01

    Construction is a very important stage in the course of realization of Nuclear Power Projects and as much care has be devoted to this stage as to the planning and engineering stages. While the setting up of nuclear power projects used to take over seven years in the past, the time period has now been considerably reduced to about five years with advancements in construction engineering, project management and design techniques, on the basis of new initiatives from the owner agency, Nuclear Power Corporation of India. In this article, the constructional aspects of the specialized structures for nuclear power generation are looked into. (author)

  1. Management of difference in a nuclear power project

    International Nuclear Information System (INIS)

    Guo Ruiting

    2012-01-01

    The Thesis dissertate the application of Management of Difference in a Nuclear Power Project from nuclear safety regulation requirement, selection of a nuclear power plant site, engineering and procurement, construction, operation and maintenance, quality management, schedule management and experience feedback aspects. (author)

  2. A study on the enhancement of nuclear cooperation with African countries including utilization of radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Maeng Ho; Oh, K. B; Lee, H. M. and others

    2005-05-15

    In this study, potential countries for nuclear cooperation in African region and possible cooperation areas were investigated between Korea and African countries including radioisotopes and more fields were also analysed in depth in order to suggest the recommendations for future cooperation to be considered as follows; First, current status and perspectives of demand and supply of energy and electricity in the African countries, use and development of nuclear energy and international nuclear cooperation were analyzed. Second, current status of nuclear cooperation between Korea and African countries were investigated as well as analysis of future cooperation potential and countries having potential for nuclear cooperation and possible cooperative activities were suggested considering potential of nuclear market in mid- and long term base and step by step. Third, desirable strategies and directions for the establishment and promotion of nuclear cooperation relations between Korea and African developing countries were suggested in order to develope cooperative relations in efficient and effective manners with African developing countries.

  3. A study on the enhancement of nuclear cooperation with African countries including utilization of radioisotope

    International Nuclear Information System (INIS)

    Yang, Maeng Ho; Oh, K. B; Lee, H. M. and others

    2005-05-01

    In this study, potential countries for nuclear cooperation in African region and possible cooperation areas were investigated between Korea and African countries including radioisotopes and more fields were also analysed in depth in order to suggest the recommendations for future cooperation to be considered as follows; First, current status and perspectives of demand and supply of energy and electricity in the African countries, use and development of nuclear energy and international nuclear cooperation were analyzed. Second, current status of nuclear cooperation between Korea and African countries were investigated as well as analysis of future cooperation potential and countries having potential for nuclear cooperation and possible cooperative activities were suggested considering potential of nuclear market in mid- and long term base and step by step. Third, desirable strategies and directions for the establishment and promotion of nuclear cooperation relations between Korea and African developing countries were suggested in order to develope cooperative relations in efficient and effective manners with African developing countries

  4. Engineering schedule control of nuclear power project planning and management

    International Nuclear Information System (INIS)

    Meng Hao

    2014-01-01

    Nuclear power design is the important part of project management of nuclear power project, it is the way to control the project organization, design schedule, design progress, design quality and cost control. The good schedule system and control is the key to the success for the project. It is also analyzed the problem during the project, by using some theory and analyze the project structure, design schedule management, IED and document management and interface management propose some new idea for better improve the design management to finally better improve the management quality and efficiency. (author)

  5. ANNETTE Project: Contributing to The Nuclearization of Fusion

    Science.gov (United States)

    Ambrosini, W.; Cizelj, L.; Dieguez Porras, P.; Jaspers, R.; Noterdaeme, J.; Scheffer, M.; Schoenfelder, C.

    2018-01-01

    The ANNETTE Project (Advanced Networking for Nuclear Education and Training and Transfer of Expertise) is well underway, and one of its work packages addresses the design, development and implementation of nuclear fusion training. A systematic approach is used that leads to the development of new training courses, based on identified nuclear competences needs of the work force of (future) fusion reactors and on the current availability of suitable training courses. From interaction with stakeholders involved in the ITER design and construction or the JET D-T campaign, it became clear that the lack of nuclear safety culture awareness already has an impact on current projects. Through the collaboration between the European education networks in fission (ENEN) and fusion (FuseNet) in the ANNETTE project, this project is well positioned to support the development of nuclear competences for ongoing and future fusion projects. Thereby it will make a clear contribution to the realization of fusion energy.

  6. ANNETTE Project: Contributing to The Nuclearization of Fusion

    Directory of Open Access Journals (Sweden)

    Ambrosini W.

    2018-01-01

    Full Text Available The ANNETTE Project (Advanced Networking for Nuclear Education and Training and Transfer of Expertise is well underway, and one of its work packages addresses the design, development and implementation of nuclear fusion training. A systematic approach is used that leads to the development of new training courses, based on identified nuclear competences needs of the work force of (future fusion reactors and on the current availability of suitable training courses. From interaction with stakeholders involved in the ITER design and construction or the JET D-T campaign, it became clear that the lack of nuclear safety culture awareness already has an impact on current projects. Through the collaboration between the European education networks in fission (ENEN and fusion (FuseNet in the ANNETTE project, this project is well positioned to support the development of nuclear competences for ongoing and future fusion projects. Thereby it will make a clear contribution to the realization of fusion energy.

  7. Purchasing management experience of Haiyang nuclear power project construction period

    International Nuclear Information System (INIS)

    Ma Yuqin

    2013-01-01

    Purchasing is one of the important aspects to ensure the safety and quality of the nuclear power plant. This paper, combining the purchasing peculiarity and purchasing process of Haiyang nuclear power project, summarizes experiences of Haiyang nuclear power project in promoting its purchasing management level in aspects of purchasing method choosing, purchasing plan management, purchasing process optimization, purchasing contract implementation and purchasing surveillance, etc. (author)

  8. The impact of project management on nuclear construction lead times

    International Nuclear Information System (INIS)

    Radlaver, M.A.; Bauman, D.S.; Chapel, S.W.

    1985-01-01

    A two-year study of lead times for nuclear power plants found that construction time is affected by six fundamental influences. One of the six is project management. An analysis of construction management teams at 26 nuclear units found that many of the most successful shared five general characteristics: nuclear power experience, skill in project control, adaptability and initiative, commitment to success, and communication and coordination skill

  9. Hanford spent nuclear fuel project update

    Energy Technology Data Exchange (ETDEWEB)

    Williams, N.H.

    1997-08-19

    Twenty one hundred metric tons of spent nuclear fuel (SNF) are currently stored in the Hanford Site K Basins near the Columbia River. The deteriorating conditions of the fuel and the basins provide engineering and management challenges to assure safe current and future storage. DE and S Hanford, Inc., part of the Fluor Daniel Hanford, Inc. lead team on the Project Hanford Management Contract, is constructing facilities and systems to move the fuel from current pool storage to a dry interim storage facility away from the Columbia River, and to treat and dispose of K Basins sludge, debris and water. The process starts in K Basins where fuel elements will be removed from existing canisters, washed, and separated from sludge and scrap fuel pieces. Fuel elements will be placed in baskets and loaded into Multi-Canister Overpacks (MCOs) and into transportation casks. The MCO and cask will be transported to the Cold Vacuum Drying Facility, where free water within the MCO will be removed under vacuum at slightly elevated temperatures. The MCOs will be sealed and transported via the transport cask to the Canister Storage Building.

  10. Estimation of Externalities for Juragua Nuclear Project

    International Nuclear Information System (INIS)

    Mora, H. R.; Carbonell, L. T.

    2002-01-01

    Estimation of externalities allows taking into account environmental impacts due to any activity in total costs calculation. In the present work, the external costs of electricity generation from nuclear energy were calculated considering three scenarios: normal operation (routine releases), accident situation and solid waste disposal. A comparison between these results and those obtained for electricity generation from fossil fuels was made. IAEA proposals of Simplified methodologies were used for externality calculations. The Juragua project was selected as a study case; it is based in two energetic blocks both PWR, VVER 440/318 type with a plant capacity of 417 MWe each. Four impact ways were considered for all scenarios: (1) Inhalation of radionuclides in the air, (2) External irradiation from radionuclides immersed in clouds, (3) External irradiation from deposited radionuclides and (4) Ingestion of radionuclides in agricultural products. Besides, two impact categories (local and regional) for all scenarios were considered. The total cost of externalities was 0.01425 c/kWh, value smaller than the one obtained for electricity generation from fossil fuel (0.256 c/kWh). For the normal operation scenario, the external cost calculated was 0.00112 c/kWh, for accident situation 0.01103 c/kWh, and for the solid wastes management scenario 0.0021 c/kWh. The high value obtained for solid waste disposal scenario is due to repository placement features. (author)

  11. Legal and Political Obstacles and Opportunities for Successful Nuclear Projects

    International Nuclear Information System (INIS)

    Yanovskiy, M.

    2014-01-01

    Every business suffers from excessive regulations, unpredictable changes in legislation, various kinds of the political rent, extorting practices like 'big business social responsibility' and more. The industries with long-term return-of-investment (ROI) are most vulnerable to political and legal risks. For the nuclear industry, long-lasted public perception of radiation as an imminent threat caused the present over-regulation look natural. Therefore ROI is above two decades, essentially precluding private entrepreneurship activity. While durable solution includes changing public perception and updating regulation, both are 'facts on the ground' and 'habits are hard to break'. Political alliances, appeal to public opinion and lobbying are legitimate methods for promoting industry's interests in a democratic state. However in case of the nuclear industry, bureaucratic and political interests seem too strong to be overpowered by regular lobbying activities. Durable solutions we are searching for should not only eliminate the present legal and political obstacles, but also prevent them in near- to middle-term future. Such solutions would mitigate risks and remove barriers in number of industries, including nuclear industry as well. Particularly, 'not in my backyard' (NIMBY) attitude to nuclear installations is often viewed as a formidable problem. However, this problem has pretty old and reliable solution via compensation for real estate devaluation, if such takes place. Such solution may preclude some projects, but makes others predictable and reliable (e.g. in sparsely populated or relatively poor areas)

  12. Spent Nuclear Fuel project interface control plan

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1995-01-01

    This implementation process philosophy is in keeping with the ongoing reengineering of the WHC Controlled Manuals to achieve interface control within the SNF Project. This plan applies to all SNF Project sub-project to sub-project, and sub-project to exteranl (both on and off the Hanford Site) interfaces

  13. Point Lepreau nuclear project unlocks power future of New Brunswick

    Energy Technology Data Exchange (ETDEWEB)

    Burgess, E J [New Brunswick Electric Power Commission, Fredericton (Canada)

    1976-08-01

    Projects under development will increase the generating capacity of New Brunswick Electric Power Commission from 1.47 to 3.14 GW. Of these projects, the most significant is the 0.63 GW Point Lepreau CANDU reactor. Progress in the construction of the power reactor is summarized. The concrete reactor building was slipformed in April 1976. A second nuclear unit at Point Lepreau is being considered. Information is also provided on the new oil-fired station at Coleson Cove, a new oil- or coal-fired unit at Dalhousie and further hydro units at Mactaquac. A 0.16 GW pumped storage hydro unit at Green River is being considered. Information on transmission (Including the HVDC system), substations, and connection with Hydro Quebec is included.

  14. Projected role of nuclear power in Egypt and problems encountered in implementing the first nuclear plant

    International Nuclear Information System (INIS)

    Effat, K.E.A.; Sirry, H.; El-Fouly, M.F.; El-Sharkawy, E.; El-Saiedi, A.F.

    1977-01-01

    This paper reviews the present and projected power demands in Egypt and the factors behind the decision to introduce a nuclear power generation program. Different problems encountered and anticipated in introducing the first nuclear power plant are also discussed

  15. Overview of the spent nuclear fuel project at Hanford

    International Nuclear Information System (INIS)

    Daily, J.L.

    1995-02-01

    The Spent Nuclear Fuel Project's mission at Hanford is to open-quotes Provide safe, economic and environmentally sound management of Hanford spent nuclear fuel in a manner which stages it to final disposition.close quotes The inventory of spent nuclear fuel (SNF) at the Hanford Site covers a wide variety of fuel types (production reactor to space reactor) in many facilities (reactor fuel basins to hot cells) at locations all over the Site. The 2,129 metric tons of Hanford SNF represents about 80% of the total US Department of Energy (DOE) inventory. About 98.5% of the Hanford SNF is 2,100 metric tons of metallic uranium production reactor fuel currently stored in the 1950s vintage K Basins in the 100 Area. This fuel has been slowly corroding, generating sludge and contaminating the basin water. This condition, coupled with aging facilities with seismic vulnerabilities, has been identified by several groups, including stakeholders, as being one of the most urgent safety and environmental concerns at the Hanford Site. As a direct result of these concerns, the Spent Nuclear Fuel Project was recently formed to address spent fuel issues at Hanford. The Project has developed the K Basins Path Forward to remove fuel from the basins and place it in dry interim storage. Alternatives that addressed the requirements were developed and analyzed. The result is a two-phased approach allowing the early removal of fuel from the K Basins followed by its stabilization and interim storage consistent with the national program

  16. Nuclear emergency preparedness. Final report of the Nordic Nuclear Safety Research Project BOK-1

    DEFF Research Database (Denmark)

    Lauritzen, B.

    2002-01-01

    Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, “Nuclear Emergency Preparedness”, was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects:Laboratory measurements and quality assurance (BOK-1.......1); Mobile measurements and measurement strategies (BOK-1.2); Field measurements and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in theNordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project...

  17. Training implementation matrix. Spent Nuclear Fuel Project (SNFP)

    International Nuclear Information System (INIS)

    EATON, G.L.

    2000-01-01

    This Training Implementation Matrix (TIM) describes how the Spent Nuclear Fuel Project (SNFP) implements the requirements of DOE Order 5480.20A, Personnel Selection, Qualification, and Training Requirements for Reactor and Non-Reactor Nuclear Facilities. The TIM defines the application of the selection, qualification, and training requirements in DOE Order 5480.20A at the SNFP. The TIM also describes the organization, planning, and administration of the SNFP training and qualification program(s) for which DOE Order 5480.20A applies. Also included is suitable justification for exceptions taken to any requirements contained in DOE Order 5480.20A. The goal of the SNFP training and qualification program is to ensure employees are capable of performing their jobs safely and efficiently

  18. Survey of Public Understanding on Energy Resources including Nuclear Energy (I)

    International Nuclear Information System (INIS)

    Park, Se-Moon; Song, Sun-Ja

    2007-01-01

    Women in Nuclear-Korea (WINK) surveyed the public understanding on various energy resources in early September 2006 to offer the result for establishment of the nuclear communication policy. The reason why this survey includes other energy resources is because the previous works are only limited on nuclear energy, and also aimed to know the public's opinion on the present communication skill of nuclear energy for the public understanding. The present study is purposed of having data how public understands nuclear energy compared to other energies, such as fossil fuels, hydro power, and other sustainable energies. The data obtained from this survey have shown different results according to the responded group; age, gender, residential area, etc. Responded numbers are more than 2,000 of general public and university students. The survey result shows that nuclear understanding is more negative in women than in men, and is more negative in young than older age

  19. Managing nuclear knowledge: IAEA activities and international coordination. Including resource material full text CD-ROM

    International Nuclear Information System (INIS)

    2005-06-01

    The present CD-ROM summarizes some activities carried out by the Departments of Nuclear Energy and Nuclear Safety and Security in the area of nuclear knowledge management in the period 2003-2005. It comprises, as open resource, most of the relevant documents in full text, including policy level documents, reports, presentation material by Member States and meeting summaries. The collection starts with a reprint of the report to the IAEA General Conference 2004 on Nuclear Knowledge [GOV/2004/56-GC(48)/12] summarizing the developments in nuclear knowledge management since the 47th session of the General Conference in 2003 and covers Managing Nuclear Knowledge including safety issues and Information and Strengthening Education and Training for Capacity Building. It contains an excerpt on Nuclear Knowledge from the General Conference Resolution [GC(48)/RES/13] on Strengthening the Agency's Activities Related to Nuclear Science, Technology and Applications. On the CD-ROM itself, all documents can easily be accessed by clicking on their titles on the subject pages (also printed at the end of this Working Material). Part 1 of the CD-ROM covers the activities in the period 2003-2005 and part 2 presents a resource material full text CD-ROM on Managing Nuclear Knowledge issued in October 2003

  20. New nuclear projects in the world. Sustainable Nuclear Energy

    International Nuclear Information System (INIS)

    Leon, P. T.

    2011-01-01

    Nuclear power has experienced a major boom in the last few years, primarily because it is a non-CO 2 emitting energy source, it can be produced at competitive costs and it can boost a country's security of supply. there are still two issues to be addressed in relation to the currently used technologies: the degree to which the energy content of nuclear fuel is used, and wastes. A solution to both these aspects would ut nuclear power in the category of sustainable energy. The article provides details on current nuclear plans in the wold, the impact of the Fukushima accident on different countries nuclear plans and the European initiatives for sustainable nuclear energy development. (Author)

  1. Engineer, procure, construct (EPC) for nuclear projects in OPG

    Energy Technology Data Exchange (ETDEWEB)

    Elliott, M. [Ontario Power Generation, Toronto, Ontario (Canada)

    2011-07-01

    OPG is exploring the use of EPC contracts for Nuclear Plant Design Modifications. Although OPG has used EPC outside of the nuclear island, this new initiative will begin to use EPC inside the plant, including upgrades to existing stations and mid-life refurbishment of Darlington. Benchmarking has shown that apart from new build, nuclear utilities rarely use this method inside the plant so OPG is using a step-by-step approach starting with projects with low complexity and low plant impact. The expected benefits are reduced interfaces and a simplified accountability model leading to schedule and cost improvements and lower rework. Design packages that incorporate construction input before issue will be a significant improvement. OPG's early challenges in moving to EPC include clearly defining roles, responsibilities and interfaces between the vendors and OPG, and modifying governance to match the new model. OPG intends to oversee the work while holding the vendor accountable for needs skill development on both sides. Vendors are expected to establish an engaged organization with complete knowledge of plant conditions, processes and streamlined methods to gain operations input. Vendors are also expected to identify and fix any quality issues before the modifications are commissioned and to have an in-house corrective action program to continuously improve. Vendors' early challenges include presenting one face to OPG rather than a collection of joint venture partners. This presentation describes OPG's plans and early feedback on this exciting new initiative.

  2. Engineer, procure, construct (EPC) for nuclear projects in OPG

    International Nuclear Information System (INIS)

    Elliott, M.

    2011-01-01

    OPG is exploring the use of EPC contracts for Nuclear Plant Design Modifications. Although OPG has used EPC outside of the nuclear island, this new initiative will begin to use EPC inside the plant, including upgrades to existing stations and mid-life refurbishment of Darlington. Benchmarking has shown that apart from new build, nuclear utilities rarely use this method inside the plant so OPG is using a step-by-step approach starting with projects with low complexity and low plant impact. The expected benefits are reduced interfaces and a simplified accountability model leading to schedule and cost improvements and lower rework. Design packages that incorporate construction input before issue will be a significant improvement. OPG's early challenges in moving to EPC include clearly defining roles, responsibilities and interfaces between the vendors and OPG, and modifying governance to match the new model. OPG intends to oversee the work while holding the vendor accountable for needs skill development on both sides. Vendors are expected to establish an engaged organization with complete knowledge of plant conditions, processes and streamlined methods to gain operations input. Vendors are also expected to identify and fix any quality issues before the modifications are commissioned and to have an in-house corrective action program to continuously improve. Vendors' early challenges include presenting one face to OPG rather than a collection of joint venture partners. This presentation describes OPG's plans and early feedback on this exciting new initiative.

  3. Spent nuclear fuel project design basis capacity study

    Energy Technology Data Exchange (ETDEWEB)

    Cleveland, K.J.

    1996-09-09

    A parametric study of the Spent Nuclear Fuel Project system capacity is presented. The study was completed using a commercially available software package to develop a summary level model of the major project systems. Alternative configurations, sub-system cycle times, and operating scenarios were tested to identify their impact on total project duration and equipment requirements.

  4. Evaluation of nuclear facility decommissioning projects. Project summary report, Elk River Reactor

    International Nuclear Information System (INIS)

    Miller, R.L.; Adams, J.A.

    1982-12-01

    This report summarizes information concerning the decommissioning of the Elk River Reactor. Decommissioning data from available documents were input into a computerized data-handling system in a manner that permits specific information to be readily retrieved. The information is in a form that assists the Nuclear Regulatory Commission in its assessment of decommissioning alternatives and ALARA methods for future decommissionings projects. Samples of computer reports are included in the report. Decommissioning of other reactors, including NRC reference decommissioning studies, will be described in similar reports

  5. Financing arrangements for nuclear power projects in developing countries

    International Nuclear Information System (INIS)

    1993-01-01

    This reference book reviews the main features and problems or difficulties involved in the financing of nuclear power projects with special reference to developing countries. It provides basic information and advice to developing countries interested in nuclear power projects as part of their power sector planning. The book outlines the general characteristics of financing a nuclear power project and presents innovative approaches for power generation financing. It discusses the special conditions and requirements of nuclear power projects and their financing complexities. The focus is on the practical issues that need to be dealt with in order to successfully finance these power projects, as well as the constraints faced by most developing countries. Possible ways and means of dealing with these constraints are presented. 58 refs, figs and tabs

  6. Enhancing Safety Culture in Complex Nuclear Industry Projects

    International Nuclear Information System (INIS)

    Gotcheva, N.

    2016-01-01

    This paper presents an on-going research project “Management principles and safety culture in complex projects” (MAPS), supported by the Finnish Research Programme on Nuclear Power Plant Safety 2015-2018. The project aims at enhancing safety culture and nuclear safety by supporting high quality execution of complex projects in the nuclear industry. Safety-critical industries are facing new challenges, related to increased outsourcing and complexity in technology, work tasks and organizational structures (Milch and Laumann, 2016). In the nuclear industry, new build projects, as well as modernisation projects are temporary undertakings often carried out by networks of companies. Some companies may have little experience in the nuclear industry practices or consideration of specific national regulatory requirements. In large multinational subcontractor networks, the challenge for assuring nuclear safety arises partly from the need to ensure that safety and quality requirements are adequately understood and fulfilled by each partner. Deficient project management practices and unsatisfactory nuclear safety culture in project networks have been recognised as contributing factors to these challenges (INPO, 2010). Prior evidence indicated that many recent major projects have experienced schedule, quality and financial challenges both in the nuclear industry (STUK, 2011) and in the non-nuclear domain (Ahola et al., 2014; Brady and Davies, 2010). Since project delays and quality issues have been perceived mainly as economic problems, project management issues remain largely understudied in safety research. However, safety cannot be separated from other performance aspects if a systemic view is applied. Schedule and quality challenges may reflect deficiencies in coordination, knowledge and competence, distribution of roles and responsibilities or attitudes among the project participants. It is increasingly understood that the performance of the project network in all

  7. Status of the Korean nuclear hydrogen production project

    International Nuclear Information System (INIS)

    Jonghwa, Chang; Won-Jae, Lee

    2010-01-01

    The rapid climate changes and the heavy reliance on imported fuel in Korea have motivated interest in the hydrogen economy. The Korean government has set up a long-term vision for transition to the hydrogen economy. To meet the expected demand of hydrogen as a fuel, hydrogen production using nuclear energy was also discussed. Recently the Korean Atomic Energy Committee has approved nuclear hydrogen production development and demonstration which will lead to commercialisation in late 2030's. An extensive research and development programme for the production of hydrogen using nuclear power has been underway since 2004 in Korea. During the first three years, a technological area was identified for the economic and efficient production of hydrogen using a VHTR. A pre-conceptual design of the commercial nuclear hydrogen production plant was also performed. As a result, the key technology area in the core design, the hydrogen production process, the coupling between reactor and chemical side, and the coated fuel were identified. During last three years, research activities have been focused on the key technology areas. A nuclear hydrogen production demonstration plant (NHDD) consisting of a 200 MWth capacity VHTR and five trains of water-splitting plants was proposed for demonstration of the performance and the economics of nuclear hydrogen. The computer tools for the VHTR and the water-splitting process were created and validated to some extent. The TRISO-coated particle fuel was fabricated and qualified. The properties of high temperature materials, including nuclear graphite, were studied. The sulphur-iodine thermochemical process was proved on a 3 litre/ hour scale. A small gas loop with practical pressure and temperature with the secondary sulphur acid loop was successfully built and commissioned. The results of the first phase research increased the confidence in the nuclear hydrogen technology. From 2009, the government decided to support further key technology

  8. Computational nuclear quantum many-body problem: The UNEDF project

    Science.gov (United States)

    Bogner, S.; Bulgac, A.; Carlson, J.; Engel, J.; Fann, G.; Furnstahl, R. J.; Gandolfi, S.; Hagen, G.; Horoi, M.; Johnson, C.; Kortelainen, M.; Lusk, E.; Maris, P.; Nam, H.; Navratil, P.; Nazarewicz, W.; Ng, E.; Nobre, G. P. A.; Ormand, E.; Papenbrock, T.; Pei, J.; Pieper, S. C.; Quaglioni, S.; Roche, K. J.; Sarich, J.; Schunck, N.; Sosonkina, M.; Terasaki, J.; Thompson, I.; Vary, J. P.; Wild, S. M.

    2013-10-01

    The UNEDF project was a large-scale collaborative effort that applied high-performance computing to the nuclear quantum many-body problem. The primary focus of the project was on constructing, validating, and applying an optimized nuclear energy density functional, which entailed a wide range of pioneering developments in microscopic nuclear structure and reactions, algorithms, high-performance computing, and uncertainty quantification. UNEDF demonstrated that close associations among nuclear physicists, mathematicians, and computer scientists can lead to novel physics outcomes built on algorithmic innovations and computational developments. This review showcases a wide range of UNEDF science results to illustrate this interplay.

  9. Bond to deliver our nuclear projects from bondage

    International Nuclear Information System (INIS)

    Subramanian, T.K.

    1985-01-01

    This paper examines the Internal Revenue Service (IRS) ruling that prevents the use of Pollution Control Revenue Bonds (PCRB) as a source of capital to complete nuclear projects, advances arguments that prevention of pollutants should be treated at least in par with the removal, alteration, or disposal of realized pollution, recommends reexamination of the IRS ruling, and emphasizes the need for the nuclear community and ultimately the US Congress to take a fresh look at the applicability of the PCRB tax exemption incentives for the nuclear safety-related structures and systems, at least for the completion of suspended nuclear projects

  10. Europairs project: creating an alliance of nuclear and non-nuclear industries for developing nuclear cogeneration

    International Nuclear Information System (INIS)

    Hittner, Dominique; Bogusch, Edgar; Viala, Celine; Angulo, Carmen; Chauvet, Vincent; Fuetterer, Michael A.; De Groot, Sander; Von Lensa, Werner; Ruer, Jacques; Griffay, Gerard; Baaten, Anton

    2010-01-01

    Developers of High Temperature Reactors (HTR) worldwide acknowledge that the main asset for market breakthrough is its unique ability to address growing needs for industrial cogeneration of heat and power (CHP) owing to its high operating temperature and flexibility, adapted power level, modularity and robust safety features. HTR are thus well suited to most of the non-electric applications of nuclear energy, which represent about 80% of total energy consumption. This opens opportunities for reducing CO 2 emissions and securing energy supply which are complementary to those provided by systems dedicated to electricity generation. A strong alliance between nuclear and process heat user industries is a necessity for developing a nuclear system for the conventional process heat market, much in the same way as the electronuclear development required a close partnership with utilities. Initiating such an alliance is one of the objectives of the EUROPAIRS project just started in the frame of the EURATOM 7. Framework Programme (FP7) under AREVA coordination. Within EUROPAIRS, process heat user industries express their requirements whereas nuclear industry will provide the performance window of HTR. Starting from this shared information, an alliance will be forged by assessing the feasibility and impact of nuclear CHP from technical, industrial, economical, licensing and sustainability perspectives. This assessment work will allow pointing out the main issues and challenges for coupling an HTR with industrial process heat applications. On this basis, a Road-map will be elaborated for achieving an industrially relevant demonstration of such a coupling. This Road-map will not only take into consideration the necessary nuclear developments, but also the required adaptations of industrial application processes and the possible development of heat transport technologies from the nuclear heat source to application processes. Although only a small and short project (21 months

  11. New Nuclear Materials Including Non Metallic Fuel Elements. Vol. I. Proceedings of the Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements

    International Nuclear Information System (INIS)

    1963-01-01

    One of the major aims of the International Atomic Energy Agency in furthering the peaceful uses of atomic energy is to encourage the development of economical nuclear power. Certainly, one of the more obvious methods of producing economical nuclear power is the development of economical fuels that can be used at high temperatures for long periods of time, and which have sufficient strength and integrity to operate under these conditions without permitting the release of fission products. In addition it is desirable that after irradiation these new fuels be economically reprocessed to reduce further the cost of the fuel cycle. As nuclear power becomes more and more competitive with conventional power the interest in new and more efficient higher-temperature fuels naturally increases rapidly. For these reasons, the Agency organized a Conference on New Nuclear Materials Technology, Including Non-Metallic Fuel Elements, which was held from 1 to 5 July 1963 at the International Hotel, Prague, with the assistance and co-operation of the Government of the Czechoslovak Socialist Republic. A total of 151 scientists attended, from 23 countries and 4 international organizations. The participants heard and discussed more than 60 scientific papers

  12. The IAEA project on nuclear and non-nuclear wastes

    International Nuclear Information System (INIS)

    Seitz, Roger

    1998-01-01

    Radioactive and chemotoxic agents are common in electricity generation waste. Data and assessments illustrate that nuclear and non-nuclear fuel chains result in waste posing potential long-term hazards. Efforts are focussed on filling data gaps and approaches for comparing impacts of radioactive and chemotoxic agents

  13. Integrated project management information systems: the French nuclear industry experience

    International Nuclear Information System (INIS)

    Jacquin, J.-C.; Caupin, G.-M.

    1990-01-01

    The article discusses the desirability of integrated project management systems within the French nuclear power industry. Change in demand for nuclear generation facilities over the last two decades has necessitated a change of policy concerning organization, cost and planning within the industry. Large corporate systems can benefit from integrating equipment and bulk materials tracking. Project management for the nuclear industry will, in future, need to incorporate computer aided design tools and project management information systems data bases as well as equipment and planning data. (UK)

  14. Integrated project management information systems: the French nuclear industry experience

    Energy Technology Data Exchange (ETDEWEB)

    Jacquin, J.-C.; Caupin, G.-M.

    1990-03-01

    The article discusses the desirability of integrated project management systems within the French nuclear power industry. Change in demand for nuclear generation facilities over the last two decades has necessitated a change of policy concerning organization, cost and planning within the industry. Large corporate systems can benefit from integrating equipment and bulk materials tracking. Project management for the nuclear industry will, in future, need to incorporate computer aided design tools and project management information systems data bases as well as equipment and planning data. (UK).

  15. The International Science and Technology Center (ISTC) and ISTC projects related to nuclear safety. Information review

    International Nuclear Information System (INIS)

    Tocheny, Lev V.

    2003-01-01

    The ISTC is an intergovernmental organization created ten years ago by Russia, USA, EU and Japan in Moscow. The Center supports numerous science and technology projects in different areas, from biotechnologies and environmental problems to all aspects of nuclear studies, including those focused on the development of effective innovative concepts and technologies in the nuclear field, in general, and for improvement of nuclear safety, in particular. The presentation addresses some technical results of the ISTC projects as well as methods and approaches employed by the ISTC to foster close international collaboration and manage projects towards fruitful results. (author)

  16. Nuclear criticality project plan for the Hanford Site tank farms

    Energy Technology Data Exchange (ETDEWEB)

    Bratzel, D.R., Westinghouse Hanford

    1996-08-06

    The mission of this project is to provide a defensible technical basis report in support of the Final Safety Analysis Report (FSAR). This technical basis report will also be used to resolve technical issues associated with the nuclear criticality safety issue. The strategy presented in this project plan includes an integrated programmatic and organizational approach. The scope of this project plan includes the provision of a criticality technical basis supporting document (CTBSD) to support the FSAR as well as for resolution of the nuclear criticality safety issue. Specifically, the CTBSD provides the requisite technical analysis to support the FSAR hazard and accident analysis as well as for the determination of the required FSAR limits and controls. The scope of The CTBSD will provide a baseline for understanding waste partitioning and distribution phenomena and mechanistics for current operational activities inclusive of single-shell tanks, double-shell tanks, double-contained receiver tanks, and miscellaneous underground storage tanks.. Although the FSAR does not include future operational activities, the waste partitioning and distribution phenomena and mechanistics work scope identified in this project plan provide a sound technical basis as a point of departure to support independent safety analyses for future activities. The CTBSD also provides the technical basis for resolution of the technical issues associated with the nuclear criticality safety issue. In addition to the CTBSD, additional documentation will be required to fully resolve U.S. Department of Energy-Headquarters administrative and programmatic issues. The strategy and activities defined in this project plan provide a CTBSD for the FSAR and for accelerated resolution of the safety issue in FY 1996. On April 30, 1992, a plant review committee reviewed the Final Safety Analysis Reports for the single-shell, double-shell, and aging waste tanks in light of the conclusions of the inadequate waste

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

    International Nuclear Information System (INIS)

    Sokolov, F.

    2001-01-01

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

  18. Report made on behalf of the commission of foreign affairs about the project of law, adopted by the senate, authorizing the approval of the agreement between the French government and the preliminary commission of the organization of the nuclear test ban treaty, about the conduct of the activities relative to the international control facilities, including the post-certification activities

    International Nuclear Information System (INIS)

    Cazenave, R.

    2003-12-01

    France and the preliminary commission of the comprehensive nuclear test ban treaty organization (CTBTO) concluded on July 13, 2001, an agreement about the conduct of the activities relative to the international surveillance facilities. This agreement aims at organizing the modalities of implementation of the surveillance activities carried out by the technical secretariat of the preliminary committee of CTBTO in the French territory. This document is the report of the French national assembly about the project of law for the approval of this agreement. It presents the difficult implementation of an international test ban system, the French commitment in the comprehensive nuclear test ban treaty (CTBT), and the main dispositions of the agreement of July 13, 2001. (J.S.)

  19. Technology assessment Jordan Nuclear Power Plant Project

    International Nuclear Information System (INIS)

    2010-01-01

    Preliminary regional analysis was carried out for identification of potential sites for NPP, followed by screening of these sites and selecting candidate sites. Aqaba sites are proposed, where it can use the sea water for cooling: i.Site 1; at the sea where it can use the sea water for direct cooling. ii.Site 2; 10 km to the east of Gulf of Aqaba shoreline at the Saudi Arabia borders. iii.Site 3, 4 km to the east of Gulf of Aqaba shoreline. Only the granitic basement in the east of the 6 km²site should be considered as a potential site for a NPP. Preliminary probabilistic seismic hazard assessment gives: Operating-Basis Earthquake-OBE (475 years return period) found to be in the range of 0.163-0.182 g; Safe Shutdown Earthquake-SSE (10,000 years return period) found to be in the range of 0.333-0.502g. The process include also setting up of nuclear company and other organizational matters. Regulations in development are: Site approval; Construction permitting; Overall licensing; Safety (design, construction, training, operations, QA); Emergency planning; Decommissioning; Spent fuel and RW management. JAEC's technology assessment strategy and evaluation methodology are presented

  20. The Los Alamos National Laboratory nuclear vision project

    International Nuclear Information System (INIS)

    Arthur, E.D.; Wagner, R.L. Jnr.

    1996-01-01

    The aims, methodology and approach of the Nuclear Vision Project are described. It is not an attempt to predict the future but aims to explore alternative futures and their implications. Some essential elements of the study are: the future of nuclear power and other civil applications; nuclear weapons and proliferation; the institutions associated with, and public opinions about, nuclear science and technology; and environment-related issues. The overall objective is to create a ''global vision'' of how to balance the benefits and dangers of nuclear technology. (6 figures; 12 references). (UK)

  1. Nuclear heating - a review of projects in several countries

    International Nuclear Information System (INIS)

    Vymetal, L.

    1980-01-01

    A review is presented of projects and studies of nuclear heat generation and district heating in the USSR, France, Sweden, Finland, USA, FRG, and CSSR. Attention is primarily paid to the nuclear sources, i.e., nuclear power and heating plants and special reactors for nuclear heating plants. The questions of heat transmission and costs are also dealt with. The review is based on the literature published between 1976 and 1979. An important source were materials from the conference on the use of low-potential heat from nuclear reactors held in Otaniemi (Finland) in 1977. (author)

  2. Cost estimating for large nuclear projects

    International Nuclear Information System (INIS)

    Duggal, A.; Hunt, M.

    2004-01-01

    In today's market, the generation of electricity is a very competitive business, which is constantly under the watchful eye of the media and public. Nuclear power faces a lot of competition from other sources such as hydro, coal and gas. Controlling costs, monitoring costs, feedback, industry knowledge and up to date cost estimating tools are essential for a nuclear company to compete on a long term basis. This paper reviews the terminology and estimating principles used for the construction of new nuclear plants, lifetime operating costs, and the costs associated with refurbishment work. (author)

  3. Tunnel Boring Machine for nuclear waste repository research project

    International Nuclear Information System (INIS)

    Janzon, H.A.

    1994-01-01

    A description is presented of a Tunnel Boring Machine and its intended use on a research project underway in Sweden for demonstrating and testing methods for rock investigation at a suitable depth for a deep repository for nuclear waste

  4. Annual report of the nuclear safeguards project 1978

    International Nuclear Information System (INIS)

    Mache, H.R.

    1980-05-01

    The present report describes the major activities carried out in 1978 in the framework of the Nuclear Safeguards Project by the institutes of the Kernforschungszentrum Karlsruhe, Kernforschungsanlage Juelich, the European Institute of Transuranium Elements and some industrial firms. (orig.) [de

  5. Annual report of the Nuclear Safeguards Project 1980

    International Nuclear Information System (INIS)

    Mache, H.R.

    1981-10-01

    The present report describes the major activities carried out in 1980 in the framework of the Nuclear Safeguards Project by the Institutes of the Kernforschungszentrum Karlsruhe and the European Institute of Transuranium Elements. (orig.) [de

  6. Annual report of the Nuclear Safeguards Project l976

    International Nuclear Information System (INIS)

    1977-07-01

    The present report describes the major activities carried out in 1976 in the framework of the Nuclear Safeguards Project by the institutes of the Gesellschaft fuer Kernforschung Karlsruhe, the European Institute of Transuranium Elements and some industrial firms. (orig.) [de

  7. Topical and working papers on nuclear power capacity projections

    International Nuclear Information System (INIS)

    As a part of the overall work programme of WG. 1, Sub-Group 1A/2A was formed jointly with WG. 2 and given the responsibility for estimating the growth of nuclear power up to the year 2025 and the associated demands for nuclear fuels, heavy water, enrichment and other fuel cycle services. In carrying out the first part of its task, the estimation of nuclear power capacity growth, sub-Group 1A/2A prepared 6 working papers which contain the following information: A critique of recent world energy demand forecasts; world energy demand and installed capacity to the year 2025; nuclear power growth projections 1977-2000 for developing countries; long range world nuclear power growth projections; INFCE forecasts of nuclear generating capacity 1985-2025

  8. Nuclear project back on track / Matt Garrick

    Index Scriptorium Estoniae

    Garrick, Matt

    2011-01-01

    1. juuniks on Leedu valitsus saanud Visaginasesse rajatava tuumaelektrijaama puudutavad investeerimisettepanekud Hitachi-GE Nuclear Energy Limited, General Electric Co. ja Westlinghouse Electric Company poolt. Peaminister Andrius Kubiliuse sõnul toob tuumaelektrijaam Leetu energiasõltumatuse

  9. Nuclear data. Situation and future projects

    International Nuclear Information System (INIS)

    Bioux, P.

    1995-01-01

    Nuclear power provides the major part of the electricity generation in France, using a system of highly developed Pressurized Water Reactors. Electricite de France, which is responsible for the exploitation of this system, is concerned to ensure the continuity of the expertise and facilities which provide relevant basic scientific information contributing to the efficient exploitation of the system and, in particular, the continuity of the means for providing relevant nuclear data. The nuclear data requirements for the exploitation of the existing nuclear power system have been largely met. However, there remain some needs, in particular in the field of reactor neutronics. Furthermore if one considers the future (for example, the next 10 years) it is not certain that will be possible to meet the needs which are expected to arise. The review, commissioned on behalf of EDF, about the current status and future expectations for work in this field, has shown certain tendencies in the international situation. In particular one notes a general reduction in the effort both in Western Europe and the United States. This negative tendency can perhaps be explained by the almost general reduction world-wide in new nuclear power developments. However, unresolved problems remain, such as the development of methods for reducing the stocks of plutonium and the incineration and storage of a nuclear waste of long duration. In addition improvements in the accuracy of nuclear data could result in non-negligible economic benefits in the exploitation of the existing nuclear facilities. For these very important reasons it is desirable to reverse the present trend. (author). 2 annexes

  10. The brief introduction to decommissioning of nuclear reactor projects

    International Nuclear Information System (INIS)

    Zhao Shixin

    1991-01-01

    The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste

  11. The brief introduction to decommissioning of nuclear reactor projects

    Energy Technology Data Exchange (ETDEWEB)

    Shixin, Zhao [Beijing Inst. of Nuclear Engineering (China)

    1991-08-01

    The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste.

  12. Present status and future development of Qinshan nuclear power project

    International Nuclear Information System (INIS)

    Ouyang Yu

    1987-01-01

    Qinshan 300 MWe Nuclear power Project is the first domestically designed and constructed nuclear power plant in China. Here is a brief description of its progress in design work, equipment manufacture and site construction since the first structural concrete in March 1985. In Qinshan area four units of 600 MWe each are planned to be built with collaboration of proper foreign partners. (author)

  13. Computational Nuclear Quantum Many-Body Problem: The UNEDF Project

    OpenAIRE

    Bogner, Scott; Bulgac, Aurel; Carlson, Joseph A.; Engel, Jonathan; Fann, George; Furnstahl, Richard J.; Gandolfi, Stefano; Hagen, Gaute; Horoi, Mihai; Johnson, Calvin W.; Kortelainen, Markus; Lusk, Ewing; Maris, Pieter; Nam, Hai Ah; Navratil, Petr

    2013-01-01

    The UNEDF project was a large-scale collaborative effort that applied high-performance computing to the nuclear quantum many-body problem. UNEDF demonstrated that close associations among nuclear physicists, mathematicians, and computer scientists can lead to novel physics outcomes built on algorithmic innovations and computational developments. This review showcases a wide range of UNEDF science results to illustrate this interplay.

  14. Report of the Nevada Commission on Nuclear Projects

    International Nuclear Information System (INIS)

    1986-11-01

    This summary represents the major conclusions reached by the Commission on Nuclear Projects. They reflect the Commission's experience with the high-level nuclear waste disposal program since 1985 and are the result of the Commission's scrutiny of both State and federal repository-related activities

  15. ANNETTE Project : contributing to the nuclearization of fusion

    NARCIS (Netherlands)

    Ambrosini, W.; Cizelj, L.; Dieguez Porras, P.; Jaspers, R.; Noterdaeme, J.; Scheffer, M.; Schoenfelder, C.

    2018-01-01

    The ANNETTE Project (Advanced Networking for Nuclear Education and Training and Transfer of Expertise) is well underway, and one of its work packages addresses the design, development and implementation of nuclear fusion training. A systematic approach is used that leads to the development of new

  16. Handling and carrying head for nuclear fuel assemblies and installation including this head

    International Nuclear Information System (INIS)

    Artaud, R.; Cransac, J.P.; Jogand, P.

    1986-01-01

    The present invention proposes a handling and carrying head ensuring efficiently the cooling of the nuclear fuel asemblies it transports so that any storage in liquid metal in a drum within or adjacent the reactor vessel is suppressed. The invention claims also a nuclear fuel handling installation including the head; it allows a longer time between loading and unloading campaigns and the space surrounding the reactor vessel keeps free without occupying a storage zone within the vessel [fr

  17. New Nuclear Materials Including Non Metallic Fuel Elements. Vol. II. Proceedings of the Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements

    International Nuclear Information System (INIS)

    1963-01-01

    One of the major aims of the International Atomic Energy Agency in furthering the peaceful uses of atomic energy is to encourage the development of economical nuclear power. Certainly, one of the more obvious methods of producing economical nuclear power is the development of economical fuels that can be used at high temperatures for long periods of time, and which have sufficient strength and integrity to operate under these conditions without permitting the release of fission products. In addition it is desirable that after irradiation these new fuels be economically reprocessed to reduce further the cost of the fuel cycle. As nuclear power becomes more and more competitive with conventional power the interest in new and more efficient higher-temperature fuels naturally increases rapidly. For these reasons, the Agency organized a Conference on New Nuclear Materials Technology, Including Non-Metallic Fuel Elements, which was held from 1 to 5 July 1963 at the International Hotel, Prague, with the assistance and co-operation of the Government of the Czechoslovak Socialist Republic. A total of 151 scientists attended, from 23 countries and 4 international organizations. The participants heard and discussed more than 60 scientific papers. The Agency wishes to thank the scientists who attended this Conference for their papers and for many spirited discussions that truly mark a successful meeting. The Agency wishes also to record its gratitude for the assistance and generous hospitality accorded the Conference, the participants and the Agency's staff by the Government of the Czechoslovak Socialist Republic and by the people of Prague. The scientific information contained in these Proceedings should help to quicken the pace of progress in the fabrication of new and m ore economical fuels, and it is hoped that these proceedings will be found useful to all workers in this and related fields

  18. International project on innovative nuclear reactors and fuel cycles

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  19. Project and feedback experience on nuclear facility decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Santiago, J.L. [ENRESA (Spain); Benest, T.G. [United Kingdom Atomic Energy Authority, Windscale, Cumbria (United Kingdom); Tardy, F.; Lefevre, Ph. [Electricite de France (EDF/CIDEN), 69 - Villeurbanne (France); Willis, A. [VT Nuclear Services (United Kingdom); Gilis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R. [Belgoprocess (Belgium); Jeanjacques, M. [CEA Saclay, 91 - Gif sur Yvette (France); Bohar, M.P.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.; Binet, C. [CEA Fontenay aux Roses, 92 (France); Fontana, Ph.; Fraize, G. [CEA Marcoule 30 (France); Seurat, Ph. [AREVA NC, 75 - Paris (France); Chesnokov, A.V.; Fadin, S.Y.; Ivanov, O.P.; Kolyadin, V.I.; Lemus, A.V.; Pavlenko, V.I.; Semenov, S.G.; Shisha, A.D.; Volkov, V.G.; Zverkov, Y.A. [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)

    2008-11-15

    This series of 6 short articles presents the feedback experience that has been drawn from various nuclear facility dismantling and presents 3 decommissioning projects: first, the WAGR project that is the UK demonstration project for power reactor decommissioning (a review of the tools used to dismantle the reactor core); secondly, the dismantling project of the Bugey-1 UNGG reactor for which the dismantling works of the reactor internals is planned to be done underwater; and thirdly, the decommissioning project of the MR reactor in the Kurchatov Institute. The feedback experience described concerns nuclear facilities in Spain (Vandellos-1 and the CIEMAT research center), in Belgium (the Eurochemic reprocessing plant), and in France (the decommissioning of nuclear premises inside the Fontenay-aux-roses Cea center and the decommissioning of the UP1 spent fuel reprocessing plant at the Marcoule site). (A.C.)

  20. Project and feedback experience on nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Santiago, J.L.; Benest, T.G.; Tardy, F.; Lefevre, Ph.; Willis, A.; Gilis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R.; Jeanjacques, M.; Bohar, M.P.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.; Binet, C.; Fontana, Ph.; Fraize, G.; Seurat, Ph.; Chesnokov, A.V.; Fadin, S.Y.; Ivanov, O.P.; Kolyadin, V.I.; Lemus, A.V.; Pavlenko, V.I.; Semenov, S.G.; Shisha, A.D.; Volkov, V.G.; Zverkov, Y.A.

    2008-01-01

    This series of 6 short articles presents the feedback experience that has been drawn from various nuclear facility dismantling and presents 3 decommissioning projects: first, the WAGR project that is the UK demonstration project for power reactor decommissioning (a review of the tools used to dismantle the reactor core); secondly, the dismantling project of the Bugey-1 UNGG reactor for which the dismantling works of the reactor internals is planned to be done underwater; and thirdly, the decommissioning project of the MR reactor in the Kurchatov Institute. The feedback experience described concerns nuclear facilities in Spain (Vandellos-1 and the CIEMAT research center), in Belgium (the Eurochemic reprocessing plant), and in France (the decommissioning of nuclear premises inside the Fontenay-aux-roses Cea center and the decommissioning of the UP1 spent fuel reprocessing plant at the Marcoule site). (A.C.)

  1. Current issues in nuclear power projects decision making

    International Nuclear Information System (INIS)

    Yanev, Y.; Rogner, H.

    2011-01-01

    Concluding Comments: Firm government commitment and support - imminent; New financing approaches/models are emerging, repackaging existing methods and combination of project finance/co-operative mode; Global financial crisis will make financing for investors very challenging, especially for large scale infrastructure projects like NNP –financial regulators to impose tougher rules (Basel III, UK bank levy, US Financial Regulatory Bill, etc; Pure project finance is still challenging for nuclear projects - the availability of finance for new NPPs will depend on the initial government support. This presentation presents a “free market” view on investment in nuclear power projects; If the public sector (governments) wishes to invest in nuclear power as part of its socioeconomic development priorities, finance is not a real obstacle; It becomes an issue in the presence of other equally important development needs and private sector participation is sought

  2. International project on innovative nuclear reactors and fuel cycles (INPRO)

    International Nuclear Information System (INIS)

    Omoto, A.

    2006-01-01

    The IAEA's project INPRO was initiated in order to provide a forum for discussion of experts and policy makers on all aspects of nuclear energy planning as well as on the development and deployment of innovative nuclear energy systems (INS). It brings together technology holders users and potential users to consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles, but it pays particular attention to the needs of developing countries. Currently INPRO members count 24 including even three countries, which are not yet operating nuclear reactors. Its initial phase has produced an outlook into the future of the energy markets and defined basic principles, user requirements and criteria in the following areas as TECDOC1362 in June 2003; Economics, Environment, Fuel Cycle and Waste, Safety, Proliferation Resistance and Crosscutting Issues. This assessment methodology can be applied for screening an INS, comparing different INS to find a preferred INS consistent with the needs of a given state, and identifying RD and D needs. The methodology has be validated through case studies and updated as TECDOC1434 in December 2004. Currently, besides producing a manual for each chapter of TECDOC1434, six assessment studies of various INS options are being carried out and the number of such studies is increasing. Further several tasks are ongoing including modeling and analysis of global and regional balance of resources and INS deployment scenarios in order to gain the better perspective of future implication of INS deployment as well as to identify challenges and opportunities of INS. It is envisioned that INPRO will continue to develop with three planned major pillars of activity; methodology, infrastructure and coordination for planning of R and D activities. The paper discusses the progress and status of INPRO as well as the future prospect of INPRO activities

  3. Colorado School of Mines low energy nuclear physics project

    International Nuclear Information System (INIS)

    Cecil, F.E.

    1993-01-01

    This report summarizes the accomplishments of the project ''Studies of nuclear reactions at very low energies''. This project was undertaken in 1987 and completed in 1993. All but one of the major objectives of this study have been accomplished. Specifically the authors have completed their investigation of the (p,γ) on light nuclei, a study of the Oppenheimer-Phillips effect, a measurements of the astrophysically interesting reaction D(α,γ) 6 Li at low energies and an extension of the reaction D(d,γ) 4 He to lower energies than previously observed. Preliminary investigation of te reaction 7 Li( 3 He,p) 9 Be was begun and is continuing under a separate DOE grant. In addition to these tasks, they have completed some very interesting projects which were not included in the original proposal. These include a study of the (d,γ) reactions on 6 Li, 7 Li and 10 B and an investigation of the possibility of observing terrestrial antineutrinos from the beta decay chains of U and Th as a diagnostic of terrestrial heat flow

  4. Spent Nuclear Fuel Project Configuration Management Plan

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1995-01-01

    This document is a rewrite of the draft ''C'' that was agreed to ''in principle'' by SNF Project level 2 managers on EDT 609835, dated March 1995 (not released). The implementation process philosphy was changed in keeping with the ongoing reengineering of the WHC Controlled Manuals to achieve configuration management within the SNF Project

  5. Calculation Method for the Projection of Future Spent Nuclear Fuel Discharges

    International Nuclear Information System (INIS)

    B. McLeod

    2002-01-01

    This report describes the calculation method developed for the projection of future utility spent nuclear fuel (SNF) discharges in regard to their timing, quantity, burnup, and initial enrichment. This projection method complements the utility-supplied RW-859 data on historic discharges and short-term projections of SNF discharges by providing long-term projections that complete the total life cycle of discharges for each of the current U.S. nuclear power reactors. The method was initially developed in mid-1999 to update the SNF discharge projection associated with the 1995 RW-859 utility survey (CRWMS M and O 1996). and was further developed as described in Rev. 00 of this report (CRWMS M and O 2001a). Primary input to the projection of SNF discharges is the utility projection of the next five discharges from each nuclear unit, which is provided via the revised final version of the Energy Information Administration (EIA) 1998 RW-859 utility survey (EIA 2000a). The projection calculation method is implemented via a set of Excel 97 spreadsheets. These calculations provide the interface between receipt of the utility five-discharge projections that are provided in the RW-859 survey, and the delivery of projected life-cycle SNF discharge quantities and characteristics in the format requisite for performing logistics analysis to support design of the Civilian Radioactive Waste Management System (CRWMS). Calculation method improvements described in this report include the addition of a reactor-specific maximum enrichment-based discharge burnup limit. This limit is the consequence of the enrichment limit, currently 5 percent. which is imposed as a Nuclear Regulatory Commission (NRC) license condition on nuclear fuel fabrication plants. In addition, the calculation method now includes the capability for projecting future nuclear plant power upratings, consistent with many such recent plant uprates and the prospect of additional future uprates. Finally. this report

  6. Global mainpower requirements for projected nuclear programmes

    International Nuclear Information System (INIS)

    Hammond, S.B.; Lane, J.A.; Rogov, A.; Skjoeldebrand, R.

    1976-01-01

    The scarcity of trained engineers and technicians may be an important bottleneck to the continued growth of nuclear power, particularly in developing countries, if steps are not taken at an early date to insure against such a limitation. This paper presents a quantitative indication of both regional and global needs for trained manpower in all sectors of the nuclear power industry and compares these with estimates of the corresponding output of engineers. Studies of a few selected countries are also presented to illustrate potential problems on a national scale. (orig./UA) [de

  7. Nuclear power project construction quality acceptance standards Implementation and discussion

    International Nuclear Information System (INIS)

    Lai Shifu

    2013-01-01

    Project quality construction acceptance is an important element of nuclear power project quality management. Based on characteristics of NPP construction and refer to national construction quality acceptance code and industry regulation, this paper introduces and discusses NPP construction quality acceptance regulation improvement and implementation under current situation. (authors)

  8. Post contract / Project management in Nuclear Malaysia

    International Nuclear Information System (INIS)

    Mohd Jamil Hashim

    2010-01-01

    Full-text: Post contract is a period from issuance certificate of practical completion until final statement of account of the project. If this procedure not completed the whole project will at large, create customers un-satisfaction, contractual obligation not complied, record not completed and financial setback. With the usage terms of contract, standard JKR circulars, treasury circulars and JKR quality manual BKJ will produce new Standard operating procedure, SOP with regards to these matters. In doing so it shall increase customer satisfaction and reduce time to finalise project and provide good record system. Keywords: Post contract, certificate of practical completion, final account, customer satisfaction, Standard operating procedure. (author)

  9. Projection and analysis of nuclear components

    International Nuclear Information System (INIS)

    Heeschen, U.

    1980-01-01

    The classification and the types of analysis carried out in pipings for quality control and safety of nuclear power plants, are presented. The operation and emergency conditions with emphasis of possible simplifications of calculations are described. (author/M.C.K.) [pt

  10. Summary report of project SIREN (Search, Intercept, Retrieve, Expulsion, Nuclear)

    International Nuclear Information System (INIS)

    Buden, D.

    1992-12-01

    Project SIREN (Search, Intercept, Retrieve, Expulsion, Nuclear) has evaluated the technologies and operational strategies needed to rendezvous with and capture aerospace radioactive materials (e.g., a distressed or spent space reactor core) before such materials can reenter the terrestrial atmosphere and to move these captured materials to a space destination for proper disposal. The use of systems external to a satellite allows multiple attempts to prevent the nuclear materials from reentering the atmosphere. SIREN also has investigated means to prevent the breakup of nuclear-powered systems already in space. The SIREN project has determined that external means can be used reliably to prevent nuclear materials from reentering the terrestrial environment, prepared a computer model that can be used to evaluate the means to dispose of radioactive materials, assessed the hazards from existing nuclear power systems in space, and in discussions with Russian Federation representatives determined interest in joint activities in this area

  11. Proceedings of the first annual Nuclear Criticality Safety Technology Project

    International Nuclear Information System (INIS)

    Rutherford, D.A.

    1994-09-01

    This document represents the published proceedings of the first annual Nuclear Criticality Safety Technology Project (NCSTP) Workshop, which took place May 12--14, 1992, in Gaithersburg, Md. The conference consisted of four sessions, each dealing with a specific aspect of nuclear criticality safety issues. The session titles were ''Criticality Code Development, Usage, and Validation,'' ''Experimental Needs, Facilities, and Measurements,'' ''Regulation, Compliance, and Their Effects on Nuclear Criticality Technology and Safety,'' and ''The Nuclear Criticality Community Response to the USDOE Regulations and Compliance Directives.'' The conference also sponsored a Working Group session, a report of the NCSTP Working Group is also presented. Individual papers have been cataloged separately

  12. The challenges of new nuclear projects. E.ON Experience

    International Nuclear Information System (INIS)

    Spechty, J.; Perez Rodriguez, J. L.

    2012-01-01

    E.ON is one of the largest privately-owned energy companies in the world. Its portfolio of nuclear assets in composed of 21 nuclear power plants on 13 sites located in Germany and Sweden, 9 of which are directly operated by E.ON. At present E.ON develops large-scale construction projects in two of the European countries willing to commit to new nuclear build-Finland and UK - for which its experience as the best nuclear power plant operator in Europe is key. (Author)

  13. Application study of the project management on the nuclear power projects in China Institute of Atomic Energy

    International Nuclear Information System (INIS)

    Ji Cunxing

    2012-01-01

    The article introduced the actions of foreign and domestic nuclear power technical services in China Institute of Atomic Energy, the project management theory is applied to the organization, implementation and control of the nuclear power projects. It is analyzed the quality, schedule , investment etc of nuclear power projects, the improving measures and suggestions are bring forward on the project management organization, quality assurance, reduce cost etc. It will raise its nuclear power project management level in China Institute of Atomic Energy. (author)

  14. Analysis of advanced European nuclear fuel cycle scenarios including transmutation and economic estimates

    International Nuclear Information System (INIS)

    Rodríguez, Iván Merino; Álvarez-Velarde, Francisco; Martín-Fuertes, Francisco

    2014-01-01

    Highlights: • Four fuel cycle scenarios have been analyzed in resources and economic terms. • Scenarios involve Once-Through, Pu burning, and MA transmutation strategies. • No restrictions were found in terms of uranium and plutonium availability. • The best case cost and the impact of their uncertainties to the LCOE were analyzed. - Abstract: Four European fuel cycle scenarios involving transmutation options (in coherence with PATEROS and CP-ESFR EU projects) have been addressed from a point of view of resources utilization and economic estimates. Scenarios include: (i) the current fleet using Light Water Reactor (LWR) technology and open fuel cycle, (ii) full replacement of the initial fleet with Fast Reactors (FR) burning U–Pu MOX fuel, (iii) closed fuel cycle with Minor Actinide (MA) transmutation in a fraction of the FR fleet, and (iv) closed fuel cycle with MA transmutation in dedicated Accelerator Driven Systems (ADS). All scenarios consider an intermediate period of GEN-III+ LWR deployment and they extend for 200 years, looking for long term equilibrium mass flow achievement. The simulations were made using the TR E VOL code, capable to assess the management of the nuclear mass streams in the scenario as well as economics for the estimation of the levelized cost of electricity (LCOE) and other costs. Results reveal that all scenarios are feasible according to nuclear resources demand (natural and depleted U, and Pu). Additionally, we have found as expected that the FR scenario reduces considerably the Pu inventory in repositories compared to the reference scenario. The elimination of the LWR MA legacy requires a maximum of 55% fraction (i.e., a peak value of 44 FR units) of the FR fleet dedicated to transmutation (MA in MOX fuel, homogeneous transmutation) or an average of 28 units of ADS plants (i.e., a peak value of 51 ADS units). Regarding the economic analysis, the main usefulness of the provided economic results is for relative comparison of

  15. Project for construction of a new nuclear unit in Armenia

    International Nuclear Information System (INIS)

    2010-01-01

    WorleyParsons Project Description Scope of work: Management Services for Implementation of the Project on Construction of New Nuclear Unit(s) in the Republic of Armenia. Client: Ministry of Energy and Natural Resources (MENR), Republic of Armenia •Contract signed on 29 of May 2009 •Project divided into 4 Phases. Addendum 1 covers phase I and II signed on 27 of July. Contract entered into force 7 of August

  16. Nuclear carrier business volume projections, 1980-2000

    International Nuclear Information System (INIS)

    Lebo, R.G.; McKeown, M.S.; Rhyne, W.R.

    1980-05-01

    The expected number of shipments of commodities in the nuclear fuel cycle are projected for the years 1980 thru 2000. Projections are made for: yellowcake (U 3 O 8 ); natural, enriched and reprocessed uranium hexafluoride (UF 6 ); uranium dioxide powder (UO 2 ); plutonium dioxide powder (PuO 2 ); fresh UO 2 and mixed oxide (MOX) fuel; spent UO 2 fuel; low-level waste (LLW); transuranic (TRU) waste; high-activity TRU waste; high-level waste (HLW), and cladding hulls. Projections are also made for non-fuel cycle commodities such as defense TRU wastes and institutional wastes, since they also are shipped by the commercial transportation industry. Projections of waste shipments from LWRs are based on the continuation of current volume reduction and solidification techniques now used by the utility industry. Projections are also made based on a 5% per year reduction in LWR waste volume shipped which is assumed to occur as a result of increased implementation of currently available volume reduction systems. This assumption results in a net 64% decrease in the total waste shipped by the year 2000. LWR waste shipment projections, and essentially all other projections for fuel cycle commodities covered in this report, are normalized to BWR and PWR generating capacity projections set forth by the Department of Energy (DOE) in their low-growth projection of April, 1979. Therefore these commodity shipment projections may be altered to comply with future changes in generating capacity projections. Projected shipments of waste from the reprocessing of spent UO 2 fuel are based on waste generation rates proposed by Nuclear Fuels Services, Allied-General Nuclear Services, Exxon Nuclear, and the DOE. Reprocessing is assumed to begin again in 1990, with mixed oxide fresh fuel available for shipment by 1991

  17. Spent nuclear fuel project design basis capacity study

    International Nuclear Information System (INIS)

    Cleveland, K.J.

    1998-01-01

    A parametric study of the Spent Nuclear Fuel Project system capacity is presented. The study was completed using a commercially available software package to develop a summary level model of the major project systems. A base case, reflecting the Fiscal Year 1998 process configuration, is evaluated. Parametric evaluations are also considered, investigating the impact of higher fuel retrieval system productivity and reduced shift operations at the canister storage building on total project duration

  18. Spent Nuclear Fuel (SNF) Project Design Verification and Validation Process

    International Nuclear Information System (INIS)

    OLGUIN, L.J.

    2000-01-01

    This document provides a description of design verification and validation activities implemented by the Spent Nuclear Fuel (SNF) Project. During the execution of early design verification, a management assessment (Bergman, 1999) and external assessments on configuration management (Augustenburg, 1999) and testing (Loscoe, 2000) were conducted and identified potential uncertainties in the verification process. This led the SNF Chief Engineer to implement corrective actions to improve process and design products. This included Design Verification Reports (DVRs) for each subproject, validation assessments for testing, and verification of the safety function of systems and components identified in the Safety Equipment List to ensure that the design outputs were compliant with the SNF Technical Requirements. Although some activities are still in progress, the results of the DVR and associated validation assessments indicate that Project requirements for design verification are being effectively implemented. These results have been documented in subproject-specific technical documents (Table 2). Identified punch-list items are being dispositioned by the Project. As these remaining items are closed, the technical reports (Table 2) will be revised and reissued to document the results of this work

  19. A new nuclear power project in the United States: Reality or fantasy?

    International Nuclear Information System (INIS)

    Redding, J.R.; Veitch, C.

    1996-01-01

    There is a way to go before a new nuclear project in the US is a reality. On the other hand, the prospects are not so remote that it is in the realm of fantasy. The authors think that if US companies have the opportunity to supply and build Advanced Nuclear Plants of US design outside the US, then the first US nuclear project has a chance to be economically competitive in the US. If these are built on budget and schedule, it will demonstrate to potential lenders that financing nuclear projects in the US does not represent an undue risk. The support of the US government in the export market is vital. Without the concerted effort of the government, including Department of Commerce, Department of State and the US ExIm bank, US suppliers will be at a significant disadvantage when facing international competition for orders. The authors think it is in the best interest of the government to supply such support. Nuclear projects outside the US sustains and creates high tech jobs in the US. It maintains the health of US nuclear technology which generates over 20% of the electricity in the US. Finally, it gives the US influence over the direction of nuclear programs in other countries, particularly developing countries which are intent upon increasing their use of nuclear energy. Those opposed to nuclear energy articulate a future that does not include its use. It is vital that nuclear professionals articulate a future that does include nuclear energy and its many socioeconomic benefits

  20. Spent nuclear fuel project integrated schedule plan

    International Nuclear Information System (INIS)

    Squires, K.G.

    1995-01-01

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

  1. Spent nuclear fuel project integrated schedule plan

    Energy Technology Data Exchange (ETDEWEB)

    Squires, K.G.

    1995-03-06

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

  2. Will Iran Give up its Nuclear Project?

    International Nuclear Information System (INIS)

    Galbert, Simond de

    2016-01-01

    In July 2015 an agreement on Iran's nuclear program was reached. However, the restrictions imposed upon Tehran are less strict than the objectives set by the Security Council. Many analysts have doubts about Iran's sincerity and think that time is on Iran's side. Shifting strategic balances in the Middle East, possible leadership changes within the Iranian regime, and the resolve of the international community will all impact on the program's future

  3. Nuclear Criticality Technology and Safety Project parameter study database

    International Nuclear Information System (INIS)

    Toffer, H.; Erickson, D.G.; Samuel, T.J.; Pearson, J.S.

    1993-03-01

    A computerized, knowledge-screened, comprehensive database of the nuclear criticality safety documentation has been assembled as part of the Nuclear Criticality Technology and Safety (NCTS) Project. The database is focused on nuclear criticality parameter studies. The database has been computerized using dBASE III Plus and can be used on a personal computer or a workstation. More than 1300 documents have been reviewed by nuclear criticality specialists over the last 5 years to produce over 800 database entries. Nuclear criticality specialists will be able to access the database and retrieve information about topical parameter studies, authors, and chronology. The database places the accumulated knowledge in the nuclear criticality area over the last 50 years at the fingertips of a criticality analyst

  4. Proceedings of the nuclear criticality technology safety project

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

  5. Steam gasification of coal, project prototype plant nuclear process heat

    International Nuclear Information System (INIS)

    Heek, K.H. van

    1982-05-01

    This report describes the tasks, which Bergbau-Forschung has carried out in the field of steam gasification of coal in cooperation with partners and contractors during the reference phase of the project. On the basis of the status achieved to date it can be stated, that the mode of operation of the gas-generator developed including the direct feeding of caking high volatile coal is technically feasible. Moreover through-put can be improved by 65% at minimum by using catalysts. On the whole industrial application of steam gasification - WKV - using nuclear process heat stays attractive compared with other gasification processes. Not only coal is conserved but also the costs of the gas manufactured are favourable. As confirmed by recent economic calculations these are 20 to 25% lower. (orig.) [de

  6. Proceedings of the nuclear criticality technology safety project

    International Nuclear Information System (INIS)

    Sanchez, R.G.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings

  7. Design interface management system for nuclear power plant project

    International Nuclear Information System (INIS)

    Wang Jun

    2012-01-01

    Design interfaces exist between different participants and during the whole course of a nuclear power project, and include different disciplinary requirements. The purpose of interface management is to establish a procedure, which can be efficiently used to control the complex design interfaces and ensure its compliance with NPP design requirements. To this end, a complete work procedures and relationship will be defined and classified, so as to set up the structure of interface management system. The system consists of three levels, i.e. working procedure level, management tool level and technical document level. Two management routes, i.e. administration route and technical route, are adopted so as to conduct management efficiently. (author)

  8. Palo Verde Nuclear Generating Station: an example of the state role in regional nuclear projects

    International Nuclear Information System (INIS)

    Pasternak, A.

    1980-10-01

    A nuclear power plant siting policy which confines new construction to existing sites will lead to the formation of large regional power centers, each involving many utilities from several states. The Palo Verde Nuclear Project in Arizona has been examined in terms of the role state regulation plays in large regional nuclear projects. State regulatory processes do not reflect the regional nature of large power centers. Decisions and actions by individual state regulatory commissions create risk and uncertainty for all the utility participants in regional projects. A climate and mechanism to encourage and facilitate interstate cooperation are needed to enhance the viability of the confined siting policy and the regional power center concept

  9. 18-months fuel cycle engineering and its project management of the Daya Bay Nuclear Power Station

    International Nuclear Information System (INIS)

    Fu Xiangang; Jiao Ping; Liu Yong; Wu Zhiming

    2002-01-01

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

  10. Project report about the motives of the future law project 'security and nuclear clearness'

    International Nuclear Information System (INIS)

    2003-11-01

    This project aims to prevent the hazards in relation with nuclear activities for man and his environment, as well to reinforce information on risks associated to these activities and on measures taken to avoid them. (N.C.)

  11. Belene Nuclear Power Plant project status

    International Nuclear Information System (INIS)

    Nikolov

    2008-01-01

    The status of the Belene project with the following main features is described: Reactor type - PWR, Russian Design Plant supplier - ASE, AREVA NP/Siemens Reactor thermal power - 2 x 3012 MW Electric output -2 x 1060 MW Net efficiency - 35 % Capacity factor - 90 % Design Life Time - 60 years

  12. Spent Nuclear Fuel Project Document Management Plan

    International Nuclear Information System (INIS)

    Connor, M.D.; Harizison, G.L.; Rice, W.C.

    1995-12-01

    The SNF Project Document Management Plan identifies and describes the currently available systems and processes for implementing and maintaining an effective document control and records management program. This program governs the methods by which documents are generated, released, distributed, maintained current, retired, and ultimately disposed

  13. Nuclear emergency preparedness. Final report of the Nordic nuclear safety research project BOK-1

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, Bent [Risoe National Lab., Roskilde (Denmark)

    2002-02-01

    Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, 'Nuclear Emergency Preparedness', was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects: Laboratory measurements and quality assurance (BOK-1.1); Mobile measurements and measurement strategies (BOK-1.2); Field measurement and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in the Nordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project outline, objectives and organization are described and main results presented. (au)

  14. Nuclear emergency preparedness. Final report of the Nordic nuclear safety research project BOK-1

    International Nuclear Information System (INIS)

    Lauritzen, Bent

    2002-02-01

    Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, 'Nuclear Emergency Preparedness', was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects: Laboratory measurements and quality assurance (BOK-1.1); Mobile measurements and measurement strategies (BOK-1.2); Field measurement and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in the Nordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project outline, objectives and organization are described and main results presented. (au)

  15. Evaluation of Nuclear Data for Nuclear R and D Projects

    International Nuclear Information System (INIS)

    Chang, J. H.; Lee, Y. O.; Gil, C. S. and others

    2005-04-01

    Nuclear structure database, neutron data, charged particle data, and high energy service were improved and the libraries of WIMSD-5B, HELIOS, KASHIL-E6 were updated in response to the relevant users' requests. Measured resonance data, 19 nuclides for high burn-up fuel, isotopes for the thorium cycle were evaluated. Gamma production cross sections for underground resource exploration and for the development of in-core detector were also evaluated. The computer code system for theoretical model calculation was improved for the high energy nuclear data and, then applied to the evaluation for the accelerator and space applications. For the production of radioisotope, 'KAERI Charged Particle Cross Section Library' was published. Various libraries such as for MCNP4C, WIMSD-5, fast reactor, shielding, fission product burnup, and reactor benchmark were generated, and a code system for neutron and charged particle transport simulation was installed and their library production system was developed. Neutron capture cross sections were measured using facilities in Kyoto Univ. and TIT of Japan, and in Dubna, Russia. The TOF facility at PAL was upgraded and measurements were performed for 12 samples. Fast neutron measurement system was designed and built in the VDG facility, and its characteristics were also estimated

  16. Gas core nuclear rocket feasibility project

    International Nuclear Information System (INIS)

    Howe, S.D.; DeVolder, B.; Thode, L.; Zerkle, D.

    1997-09-01

    The next giant leap for mankind will be the human exploration of Mars. Almost certainly within the next thirty years, a human crew will brave the isolation, the radiation, and the lack of gravity to walk on and explore the Red planet. However, because the mission distances and duration will be hundreds of times greater than the lunar missions, a human crew will face much greater obstacles and a higher risk than those experienced during the Apollo program. A single solution to many of these obstacles is to dramatically decrease the mission duration by developing a high performance propulsion system. The gas core nuclear rocket (GCNR) has the potential to be such a system. The gas core concept relies on the use of fluid dynamic forces to create and maintain a vortex. The vortex is composed of a fissile material which will achieve criticality and produce high power levels. By radiatively coupling to the surrounding fluids, extremely high temperatures in the propellant and, thus, high specific impulses can be generated. The ship velocities enabled by such performance may allow a 9 month round trip, manned Mars mission to be considered. Alternatively, one might consider slightly longer missions in ships that are heavily shielded against the intense Galactic Cosmic Ray flux to further reduce the radiation dose to the crew. The current status of the research program at the Los Alamos National Laboratory into the gas core nuclear rocket feasibility will be discussed

  17. Management information system for cost-schedule integration control for nuclear power projects

    International Nuclear Information System (INIS)

    Liu Wei; Wang Yongqing; Tian Li

    2001-01-01

    Based on the project management experience abroad and at home, a cost-schedule integration control model was developed to improve nuclear power project management. The model integrates cost data with the scheduling data by unity coding to efficiently implement cost-schedule integration control on line. The software system architecture and database is designed and implemented. The system functions include estimating and forecasting dynamically cash flow, scheduling and evaluating deviation from the cost-schedule plan, etc. The research and development of the system should improve the architecture of computer integrated management information systems for nuclear power projects in China

  18. Report of the State of Nevada Commission on Nuclear Projects

    International Nuclear Information System (INIS)

    1990-12-01

    This third biennial Report of the Nevada Commission on Nuclear Projects has been prepared in fulfillment of the requirements of NRS 459.0092, which stipulates that the Commission shall report to the Governor and Legislature on any matter relating to radioactive waste disposal the Commission deems appropriate and advise and make recommendations on the policy of the State concerning nuclear waste disposal projects. Chapter One of the Report presents a brief overview of the Commission's functions and statutory charges. It also contains a summary of developments which have affected the overall nuclear waste disposl issue since the last Commission Report was published in November, 1988. Chapter Two contains a synthesis of Commission activities and reports on the findings of the Commission relative to the geotechnical, environmental, socioeconomic, transportation, intergovernmental and legal aspects of federal and State nuclear waste program efforts

  19. Project approach study for nuclear power plants in the Netherlands

    International Nuclear Information System (INIS)

    1985-11-01

    The new nuclear program in the Netherlands comprises the construction of two to four nuclear power plants up to the year 2000. The main objective pursued with the implementation of the nuclear program is the supply of low-cost electricity in the future. In order to prepare the program and to provide a basis for further decisions, the Ministry of Economic Affairs has entrusted Motor-Columbus Consulting Engineers Inc., Baden, Switzerland, with a study to determine the most suitable project approach option(s) for the implementation of the future nuclear program in the Netherlands. In carrying out this study, Motor-Columbus investigated the following main project approach options: 1. turnkey contract approach; 2. split-package contract approach; 3. multi-contract approach. It is concluded that if applied in the appropriate way, the normal turnkey contract approach represents the most suitable approach under the prevailing situation in the Netherlands. (orig.)

  20. Schedule control in Ling Ao nuclear power project

    International Nuclear Information System (INIS)

    Xie Ahai

    2007-01-01

    Ling Ao Nuclear Power Station (LANP) is first one built up by self-reliance in China with power capacity 990x2 MWe. The results of quality control, schedule control and cost control are satisfactory. The commercial operation days of Unit 1 and Unit 2 were 28th May 2002 and 8th Jan. 2003 respectively, which were 48 days and 66 days in advance of the project schedule. This paper presents the practices of self-reliance schedule control system in LANP. The paper includes 10 sections: schedule control system; targets of schedule control; schedule control at early stage of project; construction schedule; scheduling practice; Point curves; schedule control of design and procurement; a good practice of construction schedule control on site; commissioning and startup schedule; schedule control culture. Three figures are attached. The main contents of the self-reliance schedule control system are as follows: to draw up reasonable schedules and targets; to setup management mechanism and procedures; to organize powerful project management team; to establish close monitoring system; to provide timely progress reports and statistics information. Five kinds of schedule control targets are introduced, i.e. bar-chart schedule; milesones; Point curves; interface management; hydraulic test schedule of auxiliary piping loops; EMR/EMC/EESR issuance schedules. Six levels of bar-chart schedules were adopted in LANP, but the bar-chart schedules were not satisfactory for complicated erection condition on site, even using six levels of schedules. So a kind of Point curves was developed and their advantages are explained. Scheduling method of three elements: activity, duration, logic, which was adopted in LANP, is introduced. The duration of each piping activities in LANP level 2 project schedule was calculated based on the relevant working Point quantities. The analysis and adjustment of Point curves are illustrated, i.e. balance of monthly quantities; possible production in the peakload

  1. Including Health in Environmental Assessments of Major Transport Infrastructure Projects: A Documentary Analysis.

    Science.gov (United States)

    Riley, Emily; Harris, Patrick; Kent, Jennifer; Sainsbury, Peter; Lane, Anna; Baum, Fran

    2018-05-10

    Transport policy and practice impacts health. Environmental Impact Assessments (EIAs) are regulated public policy mechanisms that can be used to consider the health impacts of major transport projects before they are approved. The way health is considered in these environmental assessments (EAs) is not well known. This research asked: How and to what extent was human health considered in EAs of four major transport projects in Australia. We developed a comprehensive coding framework to analyse the Environmental Impact Statements (EISs) of four transport infrastructure projects: three road and one light rail. The coding framework was designed to capture how health was directly and indirectly included. We found that health was partially considered in all four EISs. In the three New South Wales (NSW) projects, but not the one South Australian project, this was influenced by the requirements issued to proponents by the government which directed the content of the EIS. Health was assessed using human health risk assessment (HHRA). We found this to be narrow in focus and revealed a need for a broader social determinants of health approach, using multiple methods. The road assessments emphasised air quality and noise risks, concluding these were minimal or predicted to improve. The South Australian project was the only road project not to include health data explicitly. The light rail EIS considered the health benefits of the project whereas the others focused on risk. Only one project considered mental health, although in less detail than air quality or noise. Our findings suggest EIAs lag behind the known evidence linking transport infrastructure to health. If health is to be comprehensively included, a more complete model of health is required, as well as a shift away from health risk assessment as the main method used. This needs to be mandatory for all significant developments. We also found that considering health only at the EIA stage may be a significant

  2. Compiling Utility Requirements For New Nuclear Power Plant Project

    International Nuclear Information System (INIS)

    Patrakka, Eero

    2002-01-01

    Teollisuuden Voima Oy (TVO) submitted in November 2000 to the Finnish Government an application for a Decision-in-Principle concerning the construction of a new nuclear power plant in Finland. The actual investment decision can be made first after a positive decision has been made by the Government and the Parliament. Parallel to the licensing process, technical preparedness has been upheld so that the procurement process can be commenced without delay, when needed. This includes the definition of requirements for the plant and preliminary preparation of bid inquiry specifications. The core of the technical requirements corresponds to the specifications presented in the European Utility Requirement (EUR) document, compiled by major European electricity producers. Quite naturally, an amount of modifications to the EUR document are needed that take into account the country- and site-specific conditions as well as the experiences gained in the operation of the existing NPP units. Along with the EUR-related requirements concerning the nuclear island and power generation plant, requirements are specified for scope of supply as well as for a variety of issues related to project implementation. (author)

  3. KfK Nuclear Safety Project. First semiannual report 1985

    International Nuclear Information System (INIS)

    1985-11-01

    The semiannual progress report 1985/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1985 in the nuclear safety field by KfK institutes and departements and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics: work performed, results obtained and plans for future work. (orig./HP) [de

  4. Procedures for initiation, cost-sharing and management of OECD projects in nuclear safety

    International Nuclear Information System (INIS)

    2002-01-01

    , finances and management should be considered in order to accommodate requirements and boundary conditions that might differ from case to case. Flexibility might include consideration of in-kind contributions when applicable for project furtherance. This proposal is primarily concerned with projects that are organised by the NEA secretariat upon CSNI recommendations and initiative. One should also notice that the NEA Nuclear Safety Division has for some time operated a database on common cause events denominated ICDE. Two additional databases, one on fire events (FIRE database) and one on piping failure (OPDE database) have started in 2002. They are smaller projects, which do not have a host country. These procedures apply also to these projects, with the exception that, for the latter ones, costs are equally shared among participants

  5. Overview of implementing a project control system in the nuclear utility industry

    International Nuclear Information System (INIS)

    Cooprider, D.H.

    1994-01-01

    During the late 1980s, a metamorphosis began at Florida Power and Light Company (FPL). A strategic step in nuclear engineering's efforts to become more cost effective began in January 1990. A project control department was formed. The initial mission was to provide support for nuclear engineering design activities associated with FPL's two twin-unit nuclear power generation facilities - Turkey Point and St. Lucie. Later, the goal expanded to include the division's materials management, nuclear licensing, and information management departments. The project control group was organized along the lines of the organizations served. Separate dedicated groups were established for each plant. Since most engineering activity was based at the Juno Beach headquarters, the project control staff also was based there

  6. NASA's nuclear thermal propulsion technology project

    International Nuclear Information System (INIS)

    Peecook, K.M.; Stone, J.R.

    1992-07-01

    The nonnuclear subsystem technologies required for incorporating nuclear thermal propulsion (NTP) into space-exploration missions are discussed. Of particular interest to planned missions are such technologies as materials, instrumentation and controls, turbomachinery, CFD modeling, nozzle extension designs and models, and analyses of exhaust plumes. NASA studies are described and/or proposed for refractory metals and alloys, robotic NTP controls, and turbopump materials candidates. Alternative nozzle concepts such as aerospikes and truncated plugs are proposed, and numerical simulations are set forth for studying heavy molecules and the backstreaming of highly reactive free-radical hydrogen in the exhaust plume. The critical technologies described in the paper are central to the development of NTP, and NTP has the potential to facilitate a range of space exploration activities. 3 refs

  7. Nuclear power programmes and medium term projections in the OECD area

    International Nuclear Information System (INIS)

    Miida, J.; Haeussermann, W.; Mankin, S.

    1977-01-01

    The paper describes nuclear power growth forecasts up to 1985 on an individual country basis for the OECD area, based on present nuclear programmes. For the period between 1985 and the year 2000, no individual countries' estimates are given. The projections for this period are subdivided into three main areas: OECD Europe, North America and OECD Pacific Region. These projections are derived from the presently prevailing estimates concerning total energy growth, the increasing share of electricity requirements in total energy requirements and the growth of the nuclear share in electrical installed capacity. The basic assumptions are discussed and the combination of various possibilities results in upper and lower growth limits, which should include the most likely development. An attempt is also made to describe probable scenarios of nuclear reactor strategies, taking into account developments under way in the OECD area. Finally, the factors liable to influence nuclear power growth in a positive or negative way are briefly analysed

  8. CORONA project -contribution to VVER nuclear education and training

    International Nuclear Information System (INIS)

    Ilieva, M.; Miteva, R.; Takov, T.

    2016-01-01

    CORONA Project is established to stimulate the transnational mobility and lifelong learning amongst VVER end users. The project aims to provide a special purpose structure for training of specialists and to maintain the nuclear expertise by gathering the existing and generating new knowledge in the VVER area. CORONA Project consists of two parts: CORONA I (2011-2014) ''Establishment of a regional center of competence for VVER technology and Nuclear Applications'', co-financed by the Framework Program 7 of the European Union (EU) and CORONA II (2015-2018) ''Enhancement of training capabilities in VVER technology through establishment of VVER training academy'', co-financed by HORIZON 2020, EURATOM 2014-2015. The selected form of the CORONA Academy, together with the online availability of the training opportunities will allow trainees from different locations to access the needed knowledge on demand. The project will target also new-comers in VVER community like Vietnam, Turkey, Belarus, etc. (authors)

  9. A basic framework for managing time of nuclear plant projects

    International Nuclear Information System (INIS)

    Beck, J.R.

    1987-01-01

    One of the crucial problems that faces managers of nuclear power plant projects is how to obtain more effective and efficient utilization of their company's resources. Analysis of this problem showed that improvement was necessary in the time management area. Time management is one of the primary functions of project groups. Much has been written about planning and scheduling, and there are many modern techniques (CPM, PERT, etc.) available to a project group to manage time. So, why is time management still a problem? One reason is that nuclear projects are generally very complex and involve many organizations requiring the same resources. It is the intent of this paper to present a comprehensive and basic framework on which to either build a time management system or use as a basis to assess an existing system

  10. Probabilistic cost estimating of nuclear power plant construction projects

    International Nuclear Information System (INIS)

    Finch, W.C.; Perry, L.W.; Postula, F.D.

    1978-01-01

    This paper shows how to identify and isolate cost accounts by developing probability trees down to component levels as justified by value and cost uncertainty. Examples are given of the procedure for assessing uncertainty in all areas contributing to cost: design, factory equipment pricing, and field labor and materials. The method of combining these individual uncertainties is presented so that the cost risk can be developed for components, systems and the total plant construction project. Formats which enable management to use the probabilistic cost estimate information for business planning and risk control are illustrated. Topics considered include code estimate performance, cost allocation, uncertainty encoding, probabilistic cost distributions, and interpretation. Effective cost control of nuclear power plant construction projects requires insight into areas of greatest cost uncertainty and a knowledge of the factors which can cause costs to vary from the single value estimates. It is concluded that probabilistic cost estimating can provide the necessary assessment of uncertainties both as to the cause and the consequences

  11. Nuclear economics 2000: Deterministic and probabilistic projections of nuclear and coal electric power generation costs for the year 2000

    International Nuclear Information System (INIS)

    Williams, K.A.; Delene, J.G.; Fuller, L.C.; Bowers, H.I.

    1987-06-01

    The total busbar electric generating costs were estimated for locations in ten regions of the United States for base-load nuclear and coal-fired power plants with a startup date of January 2000. For the Midwest region a complete data set that specifies each parameter used to obtain the comparative results is supplied. When based on the reference set of input variables, the comparison of power generation costs is found to favor nuclear in most regions of the country. Nuclear power is most favored in the northeast and western regions where coal must be transported over long distances; however, coal-fired generation is most competitive in the north central region where large reserves of cheaply mineable coal exist. In several regions small changes in the reference variables could cause either option to be preferred. The reference data set reflects the better of recent electric utility construction cost experience (BE) for nuclear plants. This study assumes as its reference case a stable regulatory environment and improved planning and construction practices, resulting in nuclear plants typically built at the present BE costs. Today's BE nuclear-plant capital investment cost model is then being used as a surrogate for projected costs for the next generation of light-water reactor plants. An alternative analysis based on today's median experience (ME) nuclear-plant construction cost experience is also included. In this case, coal is favored in all ten regions, implying that typical nuclear capital investment costs must improve for nuclear to be competitive

  12. Engineering for new-built nuclear power plant projects

    International Nuclear Information System (INIS)

    Gonzalez Lopez, A.

    2012-01-01

    This article reviews the opportunities existing in the market (electrical utilities and reactor vendors) for an engineering company with the profile of Empresarios Agrupados (EA) in new-built nuclear power plant projects. To do this, reference is made to some representative examples of projects in which EA has been participating recently. the article concludes sharing with the reader some lessons learned from this participation. (Author)

  13. Evaluating Tobacco Control Policies in 28 Countries (including 9 EU countries: The ITC Project

    Directory of Open Access Journals (Sweden)

    Geoffrey Fong

    2016-03-01

    Full Text Available Since its start in 2002, the ITC Project has been conducting evaluation studies of tobacco control policies via prospective cohort surveys of tobacco users in 28 countries, including 9 EU countries. This presentation will focus on the design of the ITC Project and how it differs from and complements existing evidence-gathering systems (monitoring and surveillance systems in measuring and understanding the impact of FCTC policies. The presentation will also describe the ITC Project's most recent initiatives: (1 the EUREST-PLUS study focusing on measuring the impact of the Tobacco Products Directive, and (2 a large-scale international cohort study of e-cigarettes starting in the United States, Canada, England, and Australia.

  14. Optimized application of systems engineering to nuclear waste repository projects

    International Nuclear Information System (INIS)

    Miskimin, P.A.; Shepard, M.

    1986-01-01

    The purpose of this presentation is to describe a fully optimized application of systems engineering methods and philosophy to the management of a large nuclear waste repository project. Knowledge gained from actual experience with the use of the systems approach on two repository projects is incorporated in the material presented. The projects are currently evaluating the isolation performance of different geologic settings and are in different phases of maturity. Systems engineering methods were applied by the principal author at the Waste Isolation Pilot Plant (WIPP) in the form of a functional analysis. At the Basalt Waste Isolation Project (BWIP), the authors assisted the intergrating contractor with the development and application of systems engineering methods. Based on this experience and that acquired from other waste management projects, an optimized plan for applying systems engineering techniques was developed. The plan encompasses the following aspects: project organization, developing and defining requirements, assigning work responsibilities, evaluating system performance, quality assurance, controlling changes, enhancing licensability, optimizing project performance, and addressing regulatory issues. This information is presented in the form of a roadmap for the practical application of system engineering principles to a nuclear waste repository project

  15. Experience in nuclear materials accountancy, including the use of computers, in the UKAEA

    International Nuclear Information System (INIS)

    Anderson, A.R.; Adamson, A.S.; Good, P.T.; Terrey, D.R.

    1976-01-01

    The UKAEA have operated systems of nuclear materials accountancy in research and development establishments handling large quantities of material for over 20 years. In the course of that time changing requirements for nuclear materials control and increasing quantities of materials have required that accountancy systems be modified and altered to improve either the fundamental system or manpower utilization. The same accountancy principles are applied throughout the Authority but procedures at the different establishments vary according to the nature of their specific requirements; there is much in the cumulative experience of the UKAEA which could prove of value to other organizations concerned with nuclear materials accountancy or safeguards. This paper reviews the present accountancy system in the UKAEA and summarizes its advantages. Details are given of specific experience and solutions which have been found to overcome difficulties or to strengthen previous weak points. Areas discussed include the use of measurements, the establishment of measurement points (which is relevant to the designation of MBAs), the importance of regular physical stock-taking, and the benefits stemming from the existence of a separate accountancy section independent of operational management at large establishments. Some experience of a dual system of accountancy and criticality control is reported, and the present status of computerization of nuclear material accounts is summarized. Important aspects of the relationship between management systems of accountancy and safeguards' requirements are discussed briefly. (author)

  16. Extension of Hartree-Fock theory including tensor correlation in nuclear matter

    Science.gov (United States)

    Hu, Jinniu; Toki, Hiroshi; Ogawa, Yoko

    2013-10-01

    We study the properties of nuclear matter in the extension of Hartree-Fock theory including tensor correlation using a realistic nucleon-nucleon (NN) interaction. The nuclear wave function consists of the Hartree-Fock and two-particle-two-hole (2p-2h) states, following the concept of the tensor-optimized shell model (TOSM) for light nuclei. The short range repulsion and strong tensor force of realistic NN interaction provide high momentum components, which are taken into account in a many-body framework by introducing 2p-2h states. Single particle states are determined by the variational principle of the total energy with respect to 2p-2h amplitudes and Hartree-Fock (HF) single-particle states. The resulting differential equation is almost identical with that of Brueckner-Hartree-Fock (BHF) theory by taking two-body scattering terms only. We calculate the equation of state (EOS) of nuclear matter in this framework with the Bonn potential as a realistic NN interaction. We found similar results to BHF theory with slightly repulsive effects in the total energy. The relativistic effect is discussed for the EOSs of nuclear matter in both non-relativistic and relativistic frameworks. The momentum distribution has large components at high momenta due to 2p-2h excitations. We also obtain the EOSs of pure neutron matter, where the tensor effect is small in the iso-vector channel.

  17. Information management for nuclear power stations: project description

    International Nuclear Information System (INIS)

    Halpin, D.W.

    1978-03-01

    A study of the information management structure required to support nuclear power plant construction was performed by a joint university-industry group under the sponsorship of the Department of Energy (DOE), formerly the Energy Research and Development Administration (ERDA). The purpose of this study was (1) to study methods for the control of information during the construction and start-up of nuclear power plants, and (2) identify those data elements intrinsic to nuclear power plants which must be maintained in a structured format for quick access and retrieval. Maintenance of the massive amount of data needed for control of a nuclear project during design, procurement, construction, start-up/testing, and operational phases requires a structuring which allows immediate update and retrieval based on a wide variety of access criteria. The objective of the research described has been to identify design concepts which support the development of an information control system responsive to these requirements. A conceptual design of a Management Information Data Base System which can meet the project control and information exchange needs of today's large nuclear power plant construction projects has been completed and an approach recommended for development and implementation of a complete operational system

  18. Planning construction of integrative schedule management for nuclear power project

    International Nuclear Information System (INIS)

    Zeng Zhenglin; Wang Wenying; Peng Fei

    2012-01-01

    This paper introduces the planning construction of integrative schedule management for Nuclear Power Project. It details schedule management system and the requirement of schedulers and the mode of three schedule management flats. And analysis it combing with the implementation of construction water and all special schedules before FCD to further propose the improving and researching direction for the integrative schedule management. (authors)

  19. General criteria for the project of nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    1979-01-01

    Recommendations are presented establishing the general criteria for the project of nuclear fuel reprocessing plants to be licensed according to the legislation in effect. They apply to all the plant's systems, components and structures which are important to operation safety and to the public's health and safety. (F.E.) [pt

  20. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

  1. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    International Nuclear Information System (INIS)

    Sanchez, R.G.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda

  2. Activity report of the ENEA nuclear data project in 2005

    International Nuclear Information System (INIS)

    Ventura, A.

    2006-03-01

    Descriptions are given of the nuclear data activities at the Bologna Research Centre of the Italian National Agency for New Technologies, Energy and the Environment (ENEA), in the year 2005. This work has been done within the P9H6 project of the Division for Advanced Physics Technologies. (author)

  3. Problems of angular momentum projection in nuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Sorensen, R A [Carnegie-Mellon Univ., Pittsburgh, Pa. (USA)

    1977-05-09

    In nuclear models approximate wave functions are often used which do not have sharp angular momentum as required of the exact wave functions. It seems obvious that model wave functions of this type should be improved by projection onto states of good angular momentum. It is not the purpose of this paper to discuss the technical difficulties of projection (which can be formidable for many particle systems), but rather to present in an elementary way certain fundamental ambiguities in the use of projection. An application to high spin states near the yrast line is suggested.

  4. Problems of angular momentum projection in nuclear physics

    International Nuclear Information System (INIS)

    Sorensen, R.A.

    1977-01-01

    In nuclear models approximate wave functions are often used which do not have sharp angular momentum as required of the exact wave functions. It seems obvious that model wave functions of this type should be improved by projection onto states of good angular momentum. It is not the purpose of this paper to discuss the technical difficulties of projection (which can be formidable for many particle systems), but rather to present in an elementary way certain fundamental ambiguities in the use of projection. An application to high spin states near the yrast line is suggested. (Auth.)

  5. Experience of international projects implementation at Leningrad Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Zavialov, L.A. [Leningrad Nuclear Power Plant ' Rosenergoatom' , Leningrad Region, 188540, Sosnovy Bor (Russian Federation)

    2008-07-01

    During the period of 1992-2007 more than 60 different projects of different specificity and budget have been successfully implemented in frames of Technical Assistance for the Commonwealth of Independent States (TACIS) Program, Project financed by European Bank for Reconstruction and Development (EBRD), as well as in frames of Agreements on Cooperation between Leningrad NPP and Radiation and Nuclear safety Authority of Finland (STUK) and Swedish Nuclear Power Inspectorate, International Co-operation Program SKI-ICP(SIP). All these projects were directed to the safety increasing of the Leningrad NPP reactor, type RBMK-1000. Implementation of the technical aid projects has been performed by different foreign companies such as Aarsleff Oy, (Finland), SGN (France), Nukem (Germany), Jergo AB (Sweden), SABAROS (Switzerland), Westinghouse (USA), Nordion (Canada), Bruel and Kjer (Denmark), Data System and Solutions (UK), SVT Braundshuz (Germany) WICOTEC (Sweden), Studsvik (Sweden) and etc. which has enough technical and organizational experience in implementation of such projects, as well as all necessary certificates and licenses for works performance. Selection of a Contractor/Supplier for a joined work performance has been carried out in accordance with the tender procedure, technical specification and a planned budget. Project financing was covered by foreign Consolidated Funds and Authorities interested in increasing of Leningrad NPP safety, which have valid intergovernmental agreements with Russian Federation on the technical assistance to be provided to the NPPs. At present time all joined international projects implemented at Leningrad NPP are financed jointly with LNPP. All projects can be divided into technical aid projects connected with development and turnkey implementation of systems and complexes and projects for supply of equipment which has no analogues in Russia but successfully used all over the world. Positive experience of the joined projects

  6. Experience of international projects implementation at Leningrad Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zavialov, L.A.

    2008-01-01

    During the period of 1992-2007 more than 60 different projects of different specificity and budget have been successfully implemented in frames of Technical Assistance for the Commonwealth of Independent States (TACIS) Program, Project financed by European Bank for Reconstruction and Development (EBRD), as well as in frames of Agreements on Cooperation between Leningrad NPP and Radiation and Nuclear safety Authority of Finland (STUK) and Swedish Nuclear Power Inspectorate, International Co-operation Program SKI-ICP(SIP). All these projects were directed to the safety increasing of the Leningrad NPP reactor, type RBMK-1000. Implementation of the technical aid projects has been performed by different foreign companies such as Aarsleff Oy, (Finland), SGN (France), Nukem (Germany), Jergo AB (Sweden), SABAROS (Switzerland), Westinghouse (USA), Nordion (Canada), Bruel and Kjer (Denmark), Data System and Solutions (UK), SVT Braundshuz (Germany) WICOTEC (Sweden), Studsvik (Sweden) and etc. which has enough technical and organizational experience in implementation of such projects, as well as all necessary certificates and licenses for works performance. Selection of a Contractor/Supplier for a joined work performance has been carried out in accordance with the tender procedure, technical specification and a planned budget. Project financing was covered by foreign Consolidated Funds and Authorities interested in increasing of Leningrad NPP safety, which have valid intergovernmental agreements with Russian Federation on the technical assistance to be provided to the NPPs. At present time all joined international projects implemented at Leningrad NPP are financed jointly with LNPP. All projects can be divided into technical aid projects connected with development and turnkey implementation of systems and complexes and projects for supply of equipment which has no analogues in Russia but successfully used all over the world. Positive experience of the joined projects

  7. Path-integral isomorphic Hamiltonian for including nuclear quantum effects in non-adiabatic dynamics

    Science.gov (United States)

    Tao, Xuecheng; Shushkov, Philip; Miller, Thomas F.

    2018-03-01

    We describe a path-integral approach for including nuclear quantum effects in non-adiabatic chemical dynamics simulations. For a general physical system with multiple electronic energy levels, a corresponding isomorphic Hamiltonian is introduced such that Boltzmann sampling of the isomorphic Hamiltonian with classical nuclear degrees of freedom yields the exact quantum Boltzmann distribution for the original physical system. In the limit of a single electronic energy level, the isomorphic Hamiltonian reduces to the familiar cases of either ring polymer molecular dynamics (RPMD) or centroid molecular dynamics Hamiltonians, depending on the implementation. An advantage of the isomorphic Hamiltonian is that it can easily be combined with existing mixed quantum-classical dynamics methods, such as surface hopping or Ehrenfest dynamics, to enable the simulation of electronically non-adiabatic processes with nuclear quantum effects. We present numerical applications of the isomorphic Hamiltonian to model two- and three-level systems, with encouraging results that include improvement upon a previously reported combination of RPMD with surface hopping in the deep-tunneling regime.

  8. Completion of Mochovce 1 and 2 nuclear power plant project

    International Nuclear Information System (INIS)

    Valach, J.

    2000-01-01

    Commissioning of the Mochovce Nuclear Power Plant unit 2 fully completed the Mochovce unit 1 and 2 project. The power plant construction passed through a complicated evolution since early 80's. The genesis started with the change of the plant location due to a seismic resistance requirement raised by the former Czechoslovak Atomic Energy Commission, change of the design and contractor of the Instrumentation and Control system in early 90's, halt of construction in 1993 till 1996 due to a lack of funding, as well as a series of international reviews of safety aspects. All the obstacles had been overcome in the end, and completion works were re-started in 1996. Looking back to the unit 1 and 2 completion project, I would like to highlight some aspects of the project, particularly the level of safety, technical and organisational conditions, and terms of funding. The most important argument for completion of the plant was that VVER 440/213 reactor units were distinguished with very high level of passive safety, even overcoming Western-type PWR's in some aspects. The replacement of the original I and C system was another important contribution to the initial level of safety. International safety reviews performed at Mochovce NPP between 1990 and 1995 (Siemens, EdF, IAEA, RlSKAUDIT) confirmed the high level of safety of VVER 440/213 reactors, however, pointed out at some safety issues which had not been dealt with in the design. Those included e.g. the 'external risks', primary-to-secondary leaks, qualification of pressurizer safety valves, and others. It is necessary to stress that the Safety Improvement Programme defined for Mochovce NPP to comply with international standards did not become the most important part of the completion project due to external pressures, but based on natural requirements on nuclear power plant safety level generally accepted in 90's. The good example could be the seismic resistance of the plant which, though designed as seismic resistant

  9. IAEA Nuclear Security Assessment Methodologies (NUSAM) Project for Regulated Facilities

    International Nuclear Information System (INIS)

    Jang, Sung Soon

    2016-01-01

    Nuclear Security Assessment Methodologies (NUSAM) is a coordinate research project. The objectives of the NUSAM project is to establish a risk informed, performance-based methodological framework in a systematic, structured, comprehensive and appropriately transparent manner; to provide an environment for the sharing and transfer of knowledge and experience; and to provide guidance on, and practical examples of good practices in assessing the security of nuclear and other radioactive materials, as well as associated facilities and activities. The author worked as an IAEA scientific secretary of the NUAM project from 2013 to 2015. IAEA launched this project in 2013 and performed many activities: meetings, document development, table-top exercises and computer simulations. Now the project is in the final stage and will be concluded in the late 2016. The project will produce documents on NUSAM assessment methods and case study documents on NPP, Irradiator Facility and Transport. South Korea as a main contributor to this project will get benefits from the NUSAM. In 2014, South Korea introduced force-on-force exercises, which could be used as the assessment of physical protection system by the methods of NUSAM

  10. IAEA Nuclear Security Assessment Methodologies (NUSAM) Project for Regulated Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Sung Soon [Korea Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2016-05-15

    Nuclear Security Assessment Methodologies (NUSAM) is a coordinate research project. The objectives of the NUSAM project is to establish a risk informed, performance-based methodological framework in a systematic, structured, comprehensive and appropriately transparent manner; to provide an environment for the sharing and transfer of knowledge and experience; and to provide guidance on, and practical examples of good practices in assessing the security of nuclear and other radioactive materials, as well as associated facilities and activities. The author worked as an IAEA scientific secretary of the NUAM project from 2013 to 2015. IAEA launched this project in 2013 and performed many activities: meetings, document development, table-top exercises and computer simulations. Now the project is in the final stage and will be concluded in the late 2016. The project will produce documents on NUSAM assessment methods and case study documents on NPP, Irradiator Facility and Transport. South Korea as a main contributor to this project will get benefits from the NUSAM. In 2014, South Korea introduced force-on-force exercises, which could be used as the assessment of physical protection system by the methods of NUSAM.

  11. National participation in nuclear projects: An effort worth trying

    International Nuclear Information System (INIS)

    Albisu, F.

    1986-04-01

    National participation in nuclear power projects was a star subject in the seventies in dealings between supplying and receiving countries; around it international gatherings like ICONTT conferences, IAEA meetings, and others were almost institutionalized. The fact that many of those dealings, which were prosecuted for extended periods, are not being materialized into actual projects (suffice it to mention those of Mexico, Pakistan, Turkey, Egypt, China, etc.) has provided a slow shift of the title role in the international nuclear picture to the apparent main obstacles to that materialization, that is, financial and/or non-proliferation aspects. But, in fact, a growing, well planned participation by a country's industry, its organizations and its individuals in its nuclear programme is clearly the most important product (other than, obviously, power itself) that can be derived from such a programme. A product from which many other sectors benefit. This paper deals with significant aspects of the national participation effort, among other: existing industrial infrastructure, and its evaluation; technology transfer channels and its implications; situations where national participation may look less easy to implement: turnkey projects, shop-mounted or barge-installed blocks or complete plants, etc.; progressive participation along the project, and with subsequent projects; the role of the utility and the Government. Cases drawn from the experience of the author's company in several countries, and specially the case of Spain, are commented. (author)

  12. Review of nuclear fuel cycle alternatives including certain features pertaining to weapon proliferation

    International Nuclear Information System (INIS)

    Williams, D.C.; Rosenstroch, B.

    1978-01-01

    Largely as a result of concerns over nuclear weapon proliferation, the U.S. program to develop and commercialize the plutonium-fueled breeder reactor has been slowed down; interest in alternative fuel cycles has increased. The report offers an informal review of the various nuclear fuel cycle options including some aspects relevant to weapon proliferation, although no complete review of the latter subject is attempted. Basic principles governing breeding, reactor safety, and efficient utilization of fission energy resources (thorium and uranium) are discussed. The controversial problems of weapon proliferation and its relation to fuel reprocessing (which is essential for efficient fuel cycles) are reviewed and a number of proposed approaches to reducing proliferation risks are noted. Some representative specific reactor concepts are described, with emphasis on their development status, their potentials for resource utilization, and their implications for proliferation

  13. The International Science and Technology Center: Scope of activities and scientific projects in the field of nuclear data

    International Nuclear Information System (INIS)

    Klepatsky, Alexander B.

    2002-01-01

    The review of the ISTC (The International Science and Technology Center) Programs and activities including Science Project Program, Partner Program, Seminar Program and others is presented. Project funding by technology area, by funding Parties, by CIS (Commonwealth of Independent States) States etc. is demonstrated with emphasis on projects in the field of nuclear data. The ISTC opportunities for international cooperation in the fields of nuclear data measurements, calculation, evaluation and dissemination are discussed. (author)

  14. Nuclear threats in the vicinity of the Nordic countries. Final report of the Nordic Nuclear Safety Research project SBA-1

    International Nuclear Information System (INIS)

    Eikelmann, I.M.H.

    2002-11-01

    The acute phase of a nuclear accident and the possibility of high exposure of the populations are always the most important threats in the emergency preparedness work. Radioactive contamination from an accident can however also cause long term effects for land use and enhanced doses to special population groups and economic problems for agriculture, reindeer industry, hunting, tourism and recreation. For planning purposes it is always valuable to be aware of surrounding radiation hazards and other potential threats. Thus, mapping such threats in a Nordic context is an important factor in emergency preparedness in the area. This report presents a cross-disciplinary study from the NKS research program 1998-2001.The scope of the project was to prepare a 'base of knowledge' regarding possible nuclear threats in the vicinity of the Nordic countries. This base of knowledge will, by modere information technology as different websites, be made available to authorities, media and the population. The users of the websites can easily get information on different types of nuclear installations and threats. The users can get an overview of the situation and, if they so wish, make their own judgements. The project dealt with a geographical area including North-west Russia and the Baltic states. The results from the different activities in the project were generated in a web based database called the 'the base of knowledge'. Key words Nuclear threats, Nordic countries, nuclear power plants, nuclear ship, nuclear waste, literature database, base of knowledge, webaccessed information, atmospheric transport, decommissioning of submarines, nuclear installations, waste management, radioactive contamination in marine environment, radioactive sources, criticality analysis. (au)

  15. Nuclear threats in the vicinity of the Nordic countries. Final report of the Nordic Nuclear Safety Research project SBA-1

    Energy Technology Data Exchange (ETDEWEB)

    Eikelmann, I.M.H. [Norwegian Radiation Protection Authority (Norway)

    2002-11-01

    The acute phase of a nuclear accident and the possibility of high exposure of the populations are always the most important threats in the emergency preparedness work. Radioactive contamination from an accident can however also cause long term effects for land use and enhanced doses to special population groups and economic problems for agriculture, reindeer industry, hunting, tourism and recreation. For planning purposes it is always valuable to be aware of surrounding radiation hazards and other potential threats. Thus, mapping such threats in a Nordic context is an important factor in emergency preparedness in the area. This report presents a cross-disciplinary study from the NKS research program 1998-2001.The scope of the project was to prepare a 'base of knowledge' regarding possible nuclear threats in the vicinity of the Nordic countries. This base of knowledge will, by modere information technology as different websites, be made available to authorities, media and the population. The users of the websites can easily get information on different types of nuclear installations and threats. The users can get an overview of the situation and, if they so wish, make their own judgements. The project dealt with a geographical area including North-west Russia and the Baltic states. The results from the different activities in the project were generated in a web based database called the 'the base of knowledge'. Key words Nuclear threats, Nordic countries, nuclear power plants, nuclear ship, nuclear waste, literature database, base of knowledge, webaccessed information, atmospheric transport, decommissioning of submarines, nuclear installations, waste management, radioactive contamination in marine environment, radioactive sources, criticality analysis. (au)

  16. Identification of High Confidence Nuclear Forensics Signatures. Results of a Coordinated Research Project and Related Research

    International Nuclear Information System (INIS)

    2017-08-01

    The results of a Coordinated Research Project and related research on the identification of high confidence nuclear forensic isotopic, chemical and physical data characteristics, or signatures, provides information on signatures that can help identify the origin and history of nuclear and other radioactive material encountered out of regulatory control. This research report compiles findings from investigations of materials obtained from throughout the nuclear fuel cycle to include radioactive sources. The report further provides recent results used to identify, analyse in the laboratory, predict and interpret these signatures relative to the requirements of a nuclear forensics examination. The report describes some of the controls on the incorporation and persistence of these signatures in these materials as well as their potential use in a national system of identification to include a national nuclear forensics library.

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

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  18. Cancellation of the Kaiseraugst nuclear power plant project

    International Nuclear Information System (INIS)

    Blocher, C.; Schoenenberger, J.; Stucky, G.

    1988-01-01

    The nuclear power plant project at Kaiseraugst has been worked on for over 20 years. In 1985 the Swiss Parliament decided to license the plant. The cost of the work to date is about 1.2 x10 6 Swiss Franks. Continuation of the project is only sensible if it can be realized within a foreseeable space of time. It is probable that the discussions concerning future energy, environment and safety will continue for a long time. If this is clear that the Kaiseraugst project will not be realized during the next five to ten years for social, civic and political reasons. A continuation of the project is not justifiable. Kernkraftwerk Kaiseraugst AG must be adequately compensated. A motion has been presented to Parliament which charges the Government to negotiate with Kernkraftwerk Kaiseraugst AG for cancellation of the project

  19. Nevada Nuclear Waste Storage Investigations. FY 1979 project plan

    International Nuclear Information System (INIS)

    1979-03-01

    This document presents the management and cost for the Nevada Nuclear Waste Storage Investigations (disposal of high-level wastes at Nevada Test Site) and provides a complete description of the overall project, management structure, technical approach, and work breakdown structure. The document is organized into five major sections. Section I summarizes the history of the project and indicates a potential future course of action. FY 1979 project work is briefly described in Section II. Section III outlines the delegated responsibilities of all project management functions. A list of critical questions that guide the technical approach of the project are presented in Section IV. Section V contains subtask work plans which outline the work in detail for this fiscal year

  20. The status report on the nuclear data project in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, G.N.; Baek, W.Y.; Kang, H.S.; Choi, J.Y.; Cho, M.H.; Ko, I.S.; Namkung, W. [Pohang Accelerator Laboratory, POSTECH, Pohang (Korea, Republic of); Chang, J.H.

    1999-03-01

    The nuclear data project as one of the nation-wide nuclear R and D programs was launched by the Korea Atomic Energy Research Institute (KAERI) in 1996. Its main goals are to establish a nuclear data system, to construct the infrastructure for the nuclear data productions and evaluations, and to develop a highly reliable nuclear data system. In order to build the infrastructure for the nuclear data production, KAERI wants to build an intense pulsed neutron source by utilizing accelerator facilities, technologies, and manpower at the Pohang Accelerator Laboratory (PAL). The PAL proposed the Pohang Neutron Facility (PNF), which consists of a 100-MeV electron linac, a water-cooled Ta target, and at least three different time-of-flight (TOF) paths. The 100-MeV electron linac was designed and constructed based on experiences obtained from construction and operation of the 2-GeV linac at PAL. We report a status report on the nuclear data production and evaluation in Korea. (author)

  1. Co-operation of the CMEA member countries in the development of different reactor types, including certain aspects of their nuclear fuel cycle

    International Nuclear Information System (INIS)

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

    1977-01-01

    The report gives an account of the problems of the projected development of atomic power and evaluates its role in the fuel and power complex and long-range development of interconnected power systems of the CMEA member countries. The report emphasizes the importance of scientific and technical co-operation in the creation of thermal and fast-neutron power reactors with 1000-1500MW(e) units, and in the elaboration of nuclear plants for heating services. The positive experience of the international scientific and research group of scientists of the CMEA member countries carrying out reactor-physics studies on critical assemblies is mentioned. The report contains basic conclusions from the forecasts for nuclear power in the CMEA member countries up to 1990, including forecasting methodology; the role of nuclear power plants in saving natural and enriched uranium for a projected period; and the impact of nuclear power development rates on its structure (thermal and fast reactor ratio). It lists the impacts of scientific and technical co-operation of the CMEA member countries on the fuel cycle, including the transport of spent nuclear fuel, its recovery, reprocessing and radioactive waste disposal. Particular effects of co-operation of the CMEA member countries on the radiation safety of nuclear power plants and environmental protection are analysed. The report notes the role of the international economic associations Interatomenergo and Interatominstrument in the accelerated development of nuclear power. (author)

  2. Technical modifications and management innovations in exporting nuclear reactor projects

    International Nuclear Information System (INIS)

    Mao Xiaoming; Qin Xijiu; Ding Hu; Xue Zhaoqun; Wen Shengjun

    2009-01-01

    As a main channel for the foreign economic cooperation of China nuclear industry, China Zhongyuan Engineering Corporation (CZEC) has been constantly engaged in technical modifications and management innovations in its exporting nuclear reactor projects. In the implementation of heavy water research reactor contract in Algeria, CZEC had established a complete and adequate design standards system in compliance with the international standards, and made significant modifications to the reference reactor in the aspects of reactor power and reactor safety, solved quite some technical issues which-affected the reactor technical performance. The modifications and improvements enabled the technical parameters, safety features, reactor multipurpose application to attain to the advanced level in the world. In the 300 MWe PWR NPPs in Pakistan, safety features had been updated in line with upgrading regulatory requisites. The design philosophy and technology application demonstrated CZEC' s creation and innovation on basis of constant safety enhancement of nuclear power projects. Efforts had also been made by CZEC' s creation and innovation on basis of constant safety enhancement of nuclear power projects. Efforts had also been made by CZEC in promoting China made equipment items and components exportation. (authors)

  3. Nuclear facility projects in Finland: quality of environmental impact assessment (EIA) processes

    International Nuclear Information System (INIS)

    Vaatainen, A.

    2001-01-01

    In Finland, three public EIA hearings arranged by the contact authority concerning nuclear facilities were organised in 1999: the EIAs of two reactors planned to be constructed in Eurajoki (Olkiluoto) and in Loviisa, and the EIA of a final disposal facility of spent nuclear fuel, to be situated either in Olkiluoto, Loviisa, Romuvaara or Kivetty. Additionally, an application for a decision-in-principle concerning a final disposal facility to be constructed in Olkiluoto was submitted. The Ministry of Trade and Industry is the contact authority in all nuclear projects in Finland. Probably due to the simultaneity of the processes and the great importance of nuclear facility projects to the whole of society, the public opinions did not include only views about environmental impacts of each project, but also opposing and overall views about the use of nuclear energy and its safety. As for the final disposal project, alternative methods were introduced and opposition to the project itself was expressed instead of or in addition to the environmental impacts. (author)

  4. Projections of spent fuel to be discharged by the U.S. nuclear power industry

    International Nuclear Information System (INIS)

    Alexander, C.W.; Kee, C.W.; Croff, A.G.; Blomeke, J.O.

    1977-10-01

    Calculated properties of spent fuel projected to be discharged and accumulated by the U.S. nuclear power industry through the year 2031 A.D. are presented. The projections are based on installed nuclear capacities of 380 and 543 GW(e) in the year 2000 and 2030, respectively. They include compilations of the grams of the elements, curies of radioactivity, thermal decay power, photon and neutron emission rates, and radiotoxicities of the assemblies that are accumulated at a Spent Unreprocessed Fuel Facility (SURFF), allowing for delays of 5 and 10 years before shipment to SURFF

  5. Projections of spent fuel to be discharged by the U. S. nuclear power industry

    Energy Technology Data Exchange (ETDEWEB)

    Alexander, C.W.; Kee, C.W.; Croff, A.G.; Blomeke, J.O.

    1977-10-01

    Calculated properties of spent fuel projected to be discharged and accumulated by the U.S. nuclear power industry through the year 2031 A.D. are presented. The projections are based on installed nuclear capacities of 380 and 543 GW(e) in the year 2000 and 2030, respectively. They include compilations of the grams of the elements, curies of radioactivity, thermal decay power, photon and neutron emission rates, and radiotoxicities of the assemblies that are accumulated at a Spent Unreprocessed Fuel Facility (SURFF), allowing for delays of 5 and 10 years before shipment to SURFF.

  6. Data base on dose reduction research projects for nuclear power plants: Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A.; Baum, J.W.

    1989-05-01

    This is the third volume in a series of reports that provide information on dose-reduction research and health physics technology for nuclear power plants. The information is taken from data base maintained by Brookhaven National Laboratory's ALARA Center for the Nuclear Regulatory Commission. This report presents information on 80 new projects, covering a wide area of activities. Projects on steam generator degradation, decontamination, robotics, improvement in reactor materials, and inspection techniques, among others, are described in the research section. The section on health physics technology includes some simple and very cost-effective projects to reduce radiation exposures. Collective dose data from the United States and other countries are also presented. In the conclusion, we suggest that although new advanced reactor design technology will eventually reduce radiation exposures at nuclear power plants to levels below serious concern, in the interim an aggressive approach to dose reduction remains necessary. 20 refs.

  7. Financing Nuclear Power Plant Projects. A New Paradigm?

    International Nuclear Information System (INIS)

    Pehuet Lucet, Fabienne

    2015-05-01

    There are currently 435 operable nuclear power reactors around the world, with a further 71 under construction. Two main proven financing models were applied to nuclear plants in the past: the national model, and the corporate model. The historical model of financing is the national model. It allowed for the most efficient risk allocation model in then-regulated national electricity markets: government or state-owned utilities with government guarantee assumed the risks of building nuclear power plants locally. The national model has proven to be efficient in France, Russia and the USA where it was modified to support private business initiatives. It was then replicated in Japan, Korea and China where significant nuclear programs were developed. In the corporate business model, the owner of the plant assumes most of the risk, but various schemes are used to mitigate the owner's risk by transmitting large areas of risks to others: vendors for construction risk as in Finland, government through loans guarantees etc. As projects became international, a set of common principles were approved by OECD countries concerning financing and the role of Export Credit Agencies. The objective was to provide competition rules whereby exporters compete on the basis of the price and quality of their products rather than the financial terms provided. Various combinations of these models were and still are implemented. Pure Project Finance was not implemented for nuclear power plants, but the model nurtures reflections about new financing models. The context in which nuclear power projects are now decided and financed changed drastically: it is a new paradigm. Risk allocation and financial conditions are at the forefront of competition to win new nuclear projects' tenders insofar as reducing uncertainties is a decisive competition edge. In a context of electricity market deregulation and high construction risks, investors and lenders require more and more securities to

  8. Nuclear employee data system (NEDS), a pilot project

    International Nuclear Information System (INIS)

    Britz, W.L.

    1984-01-01

    This paper describes a pilot project being funded by six east coast nuclear utilities: the Nuclear Employee Data System (NEDS). The NEDS is to be a customized computer-based information management system that will receive, update, and maintain in-processing information among the NEDS participating utilities. A comprehensive set of data requirements has been preliminarily identified and characterized into areas of: personal information, security information, health physics information, respiratory protective equipment information, medical information, and training information. The NEDS is expected to become operational next summer

  9. Denmark's greenhouse gas projections until 2012, an update including a preliminary projection until 2017

    Energy Technology Data Exchange (ETDEWEB)

    Fenham, J. [Risoe National Lab., Roskilde (Denmark)

    2003-07-01

    This report presents the results of a project financed by the Danish Energy Agency. The purpose of the project is to make 'with measures' projections of the emissions from Danish sources of the greenhouse gases, CO{sub 2}, CH{sub 4}, N{sub 2}O, HFCs, PFCs and SF{sub 6}. The 'with measures' projection encompasses currently implemented and adopted policies and measures. The time period covered is from 1972, the first year detailed Danish energy statistics were produced, until the first commitment period (2008-2012) under the Kyoto Protocol to the Climate Convention. A preliminary projection is also made for the second commitment period (2013-2017), but here no projections are available for the agricultural sector and the emissions from this sector has therefore been kept equal to the emissions in the first commitment period. Estimations of HFCs, PFCs and SF{sub 6}-emissions and projections cover the period from 1993 until 2020. Only emissions caused by human activities are included in the calculations. However, it can sometimes be difficult to draw the borderline between emissions from nature and anthropogenic emissions. Due to small differences between the methodology used in this project and the methodology (CORINAIR) used by the National Environmental Research Institute for the purpose of annual reporting the estimated emissions presented for the period 1990-2000 may deviate from the official emission estimates report to the EU and the Climate Convention (UNFCCC). Therefore the GHG emission estimates presented in this report for the period until 2000 should only be seen as an illustration of the order of magnitude. This is also the case for the parts of the trend analyses, which are based on the historic data coming from this project. The description of the emissions in the report is structured according to the IPCC sectors: 1) Energy. 2) Industrial processes. 3) Agriculture. 4) Land use change and forestry. 5) Waste. The NMVOC emission from

  10. Global nuclear renaissance - today's issues, challenges and differences relative to the first wave of nuclear plant projects

    International Nuclear Information System (INIS)

    Gardner, William N.

    2010-01-01

    The development and negotiation of an Engineering, Procurement and Construction (EPC) contract is a multi-disciplined and time consuming process. Relative to the first wave on new nuclear build projects of the 1950's - 1970's, today's EPC contracts are more complex for a variety of reasons including more demanding regulatory and environmental requirements, global supply chain versus localization issues and different world wide economic considerations. This paper discusses the impacts of some of these challenges on developing an EPC contract in today's Nuclear Renaissance. (authors)

  11. Angra 1 nuclear power plant full scope simulator development project

    Energy Technology Data Exchange (ETDEWEB)

    Selvatici, Edmundo; Castanheira, Luiz Carlos C.; Silva Junior, Nilo Garcia da, E-mail: edsel@eletronuclear.gov.br, E-mail: lccast@eletronuclear.gov.br, E-mail: nilogar@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (SCO/ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Superintendencia de Coordenacao da Operacao; Zazo, Francisco Javier Lopez; Ruiz, Jose Antonio, E-mail: jlopez@tecnatom.es, E-mail: jaruiz@tecnatom.es [Tecnatom S.A., San Sebastian de los Reyes, Madrid (Spain)

    2015-07-01

    Specific Full Scope Simulators are an essential tool for training NPP control room operators, in the formation phase as well as for maintaining their qualifications. In the last years availability of a Plant specific simulator has also become a Regulator requirement for Nuclear Power Plant operation. By providing real-time practical training for the operators, the use of a simulator allows improving the operator's performance, reducing the number of unplanned shutdowns and more effective response to abnormal and emergency operating conditions. It can also be used, among other uses, to validate procedures, test proposed plant modifications, perform engineering studies and to provide operation training for the technical support staff of the plant. The NPP site, in Angra dos Reis-RJ, Brazil, comprises the two units in operation, Unit 1, 640 MWe, Westinghouse PWR and Unit 2, 1350 MWe, KWU/Areva PWR and one unit in construction, Unit 3, 1405 MWe, KWU/Areva PWR, of the same design of Angra 2. Angra 2 has had its full scope simulator from the beginning, however this was not the case of Angra 1, that had to train its operators abroad, due to lack of a specific simulator. Eletronuclear participated in all the phases of the project, from data supply to commissioning and validation. The Angra 1 full scope simulator encompasses more than 80 systems of the plant including the Primary system, reactor core and associated auxiliary systems, the secondary system and turbo generator as well as all the Plant operational and safety I and C. The Angra 1 Main Control Room panels were reproduced in the simulator control room as well as the remote shutdown panels that are outside the control room. This paper describes the project for development of the Angra 1 NPP Full Scope Simulator, supplied by Tecnatom S.A., in the period of Feb.2012 to Feb.2015. (author)

  12. Spent Nuclear Fuel (SNF) Project Design Basis Capacity Study

    International Nuclear Information System (INIS)

    CLEVELAND, K.J.

    2000-01-01

    This study of the design basis capacity of process systems was prepared by Fluor Federal Services for the Spent Nuclear Fuel Project. The evaluation uses a summary level model of major process sub-systems to determine the impact of sub-system interactions on the overall time to complete fuel removal operations. The process system model configuration and time cycle estimates developed in the original version of this report have been updated as operating scenario assumptions evolve. The initial document released in Fiscal Year (FY) 1996 varied the number of parallel systems and transport systems over a wide range, estimating a conservative design basis for completing fuel processing in a two year time period. Configurations modeling planned operations were updated in FY 1998 and FY 1999. The FY 1998 Base Case continued to indicate that fuel removal activities at the basins could be completed in slightly over 2 years. Evaluations completed in FY 1999 were based on schedule modifications that delayed the start of KE Basin fuel removal, with respect to the start of KW Basin fuel removal activities, by 12 months. This delay resulted in extending the time to complete all fuel removal activities by 12 months. However, the results indicated that the number of Cold Vacuum Drying (CVD) stations could be reduced from four to three without impacting the projected time to complete fuel removal activities. This update of the design basis capacity evaluation, performed for FY 2000, evaluates a fuel removal scenario that delays the start of KE Basin activities such that staffing peaks are minimized. The number of CVD stations included in all cases for the FY 2000 evaluation is reduced from three to two, since the scenario schedule results in minimal time periods of simultaneous fuel removal from both basins. The FY 2000 evaluation also considers removal of Shippingport fuel from T Plant storage and transfer to the Canister Storage Building for storage

  13. Angra 1 nuclear power plant full scope simulator development project

    International Nuclear Information System (INIS)

    Selvatici, Edmundo; Castanheira, Luiz Carlos C.; Silva Junior, Nilo Garcia da

    2015-01-01

    Specific Full Scope Simulators are an essential tool for training NPP control room operators, in the formation phase as well as for maintaining their qualifications. In the last years availability of a Plant specific simulator has also become a Regulator requirement for Nuclear Power Plant operation. By providing real-time practical training for the operators, the use of a simulator allows improving the operator's performance, reducing the number of unplanned shutdowns and more effective response to abnormal and emergency operating conditions. It can also be used, among other uses, to validate procedures, test proposed plant modifications, perform engineering studies and to provide operation training for the technical support staff of the plant. The NPP site, in Angra dos Reis-RJ, Brazil, comprises the two units in operation, Unit 1, 640 MWe, Westinghouse PWR and Unit 2, 1350 MWe, KWU/Areva PWR and one unit in construction, Unit 3, 1405 MWe, KWU/Areva PWR, of the same design of Angra 2. Angra 2 has had its full scope simulator from the beginning, however this was not the case of Angra 1, that had to train its operators abroad, due to lack of a specific simulator. Eletronuclear participated in all the phases of the project, from data supply to commissioning and validation. The Angra 1 full scope simulator encompasses more than 80 systems of the plant including the Primary system, reactor core and associated auxiliary systems, the secondary system and turbo generator as well as all the Plant operational and safety I and C. The Angra 1 Main Control Room panels were reproduced in the simulator control room as well as the remote shutdown panels that are outside the control room. This paper describes the project for development of the Angra 1 NPP Full Scope Simulator, supplied by Tecnatom S.A., in the period of Feb.2012 to Feb.2015. (author)

  14. Data base on nuclear power plant dose reduction research projects

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A.; Baum, J.W.

    1986-10-01

    Staff at the ALARA Center of Brookhaven National Laboratory have established a data base of information about current research that is likely to result in lower radiation doses to workers. The data base, concerned primarily with nuclear power generation, is part of a project that the ALARA Center is carrying out for the Nuclear Regulatory Commission. This report describes its current status. A substantial amount of research on reducing occupational exposure is being done in the US and abroad. This research is beginning to have an impact on the collective dose expenditures at nuclear power plants. The collective radiation doses in Europe, Japan, and North America all show downward trends. A large part of the research in the US is either sponsored by the nuclear industry through joint industry organizations such as EPRI and ESEERCO or is done by individual corporations. There is also significant participation by smaller companies. The main emphasis of the research on dose reduction is on engineering approaches aimed at reducing radiation fields or keeping people out of high-exposure areas by using robotics. Effective ALARA programs are also underway at a large number of nuclear plants. Additional attention should be given to non-engineering approaches to dose reduction, which are potentially very useful and cost effective but require quantitative study and analysis based on data from nuclear power plants. 9 refs., 1 fig.

  15. The Nuclear and Radiochemistry in Chemistry Education Curriculum Project

    International Nuclear Information System (INIS)

    Robertson, J.D.; Missouri University, Columbia, MO; Kleppinger, E.W.

    2005-01-01

    Given the mismatch between supply of and demand for nuclear scientists, education in nuclear and radiochemistry has become a serious concern. The Nuclear and Radiochemistry in Chemistry Education (NRIChEd) Curriculum Project was undertaken to reintroduce the topics normally covered in a one-semester radiochemistry course into the traditional courses of a four-year chemistry major: general chemistry, organic chemistry, quantitative and instrumental analysis, and physical chemistry. NRIChEd uses a three-pronged approach that incorporates radiochemistry topics when related topics in the basic courses are covered, presents special topics of general interest as a vehicle for teaching nuclear and radiochemistry alongside traditional chemistry, and incorporates the use of non-licensed amounts of radioactive substances in demonstrations and student laboratory experiments. This approach seeks not only to reestablish nuclear science in the chemistry curriculum, but to use it as a tool for elucidating fundamental and applied aspects of chemistry as well. Moreover, because of its relevance in many academic areas, nuclear science enriches the chemistry curriculum by encouraging interdisciplinary thinking and problem solving. (author)

  16. Data base on nuclear power plant dose reduction research projects

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A.; Dionne, B.J.; Baum, J.W.

    1985-12-01

    This report contains project information on the research and development activities of the nuclear power industry in the area of dose reduction. It is based on a data base of information set up at the ALARA Center of Brookhaven National Laboratory. One purpose of this report is to draw attention to work in progress and to enable researchers and subscribers to obtain further information from the investigators and project managers. Information is provided on 180 projects, divided according to whether they are oriented to Engineering Research or to Health Physics Technology. The report contains indices on main category, project manager, principal investigator, sponsoring organization, contracting organization, and subject. This is an initial report. It is intended that periodic updates be issued whenever sufficient material has been accumulated.

  17. Data base on nuclear power plant dose reduction research projects

    International Nuclear Information System (INIS)

    Khan, T.A.; Dionne, B.J.; Baum, J.W.

    1985-12-01

    This report contains project information on the research and development activities of the nuclear power industry in the area of dose reduction. It is based on a data base of information set up at the ALARA Center of Brookhaven National Laboratory. One purpose of this report is to draw attention to work in progress and to enable researchers and subscribers to obtain further information from the investigators and project managers. Information is provided on 180 projects, divided according to whether they are oriented to Engineering Research or to Health Physics Technology. The report contains indices on main category, project manager, principal investigator, sponsoring organization, contracting organization, and subject. This is an initial report. It is intended that periodic updates be issued whenever sufficient material has been accumulated

  18. Nuclear Fuel Assembly Assessment Project and Image Categorization

    Energy Technology Data Exchange (ETDEWEB)

    Lindsey, C.S.; Lindblad, T.; Waldemark, K. [Royal Inst. of Tech., Stockholm (Sweden); Hildingsson, Lars [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    1998-07-01

    A project has been underway to add digital imaging and processing to the inspection of nuclear fuel by the International Atomic Energy Agency. The ultimate goals are to provide the inspector not only with the advantages of Ccd imaging, such as high sensitivity and digital image enhancements, but also with an intelligent agent that can analyze the images and provide useful information about the fuel assemblies in real time. The project is still in the early stages and several interesting sub-projects have been inspired. Here we give first a review of the work on the fuel assembly image analysis and then give a brief status report on one of these sub-projects that concerns automatic categorization of fuel assembly images. The technique could be of benefit to the general challenge of image categorization

  19. Generation of complete electronic nuclear medicine reports including static, dynamic and gated images

    International Nuclear Information System (INIS)

    Beretta, M.; Pilon, R.; Mut, F.

    2002-01-01

    Aim: To develop a procedure for the creation of nuclear medicine reports containing static and dynamic images. The reason for implementing this technique is the lack of adequate solutions for an electronic format of nuclear medicine results allowing for rapid transmission via e-mail, specially in the case of dynamic and gated SPECT studies, since functional data is best presented in dynamic mode. Material and Methods: Clinical images were acquired in static, whole body, dynamic and gated mode, corresponding to bone studies, diuretic renogram, radionuclide cystography and gated perfusion SPECT, as well as respective time-activity curves. Image files were imported from a dedicated nuclear medicine computer system (Elscint XPert) to a Windows-based PC through a standard ethernet network with TCP-IP communications protocol, using a software developed by us which permits the conversion from the manufacturer's original format into a bitmap format (.bmp) compatible with commercially available PC software. For cardiac perfusion studies, background was subtracted prior to transferring to reduce the amount of information in the file; this was not done for other type of studies because useful data could be eliminated. Dynamic images were then processed using commercial software to create animated files and stored in .gif format. Static images were re-sized and stored in .jpg format. Original color or gray scale was always preserved. All the graphic material was then merged with a previously prepared report text using HTML format. The report also contained reference diagrams to facilitate interpretation. The whole report was then compressed into a self-extractable file, ready to be sent by electronic mail. Reception of the material was visually checked for data integrity including image quality by two experienced nuclear medicine physicians. Results: The report presented allows for simultaneous visualization of the text, diagrams and images either static, dynamic, gated or

  20. Co-benefits of including CCS projects in the CDM in India's power sector

    International Nuclear Information System (INIS)

    Eto, R.; Murata, A.; Uchiyama, Y.; Okajima, K.

    2013-01-01

    This study examines the effects of the inclusion of the co-benefits on the potential installed capacity of carbon dioxide capture and storage (CCS) projects with a linear programming model by the clean development mechanism (CDM) in India's power sector. It is investigated how different marginal damage costs of air pollutants affect the potential installed capacity of CCS projects in the CDM with a scenario analysis. Three results are found from this analysis. First, large quantity of IGCC with CCS becomes realizable when the certified emission reduction (CER) prices are above US$56/tCO 2 in the integrated Northern, Eastern, Western, and North-Eastern regional grids (NEWNE) and above US $49/tCO 2 in the Southern grid. Second, including co-benefits contributes to decrease CO 2 emissions and air pollutants with introduction of IGCC with CCS in the CDM at lower CER prices. Third, the effects of the co-benefits are limited in the case of CCS because CCS reduces larger amount of CO 2 emissions than that of air pollutants. Total marginal damage costs of air pollutants of US$250/t and US$200/t lead to CER prices of US$1/tCO 2 reduction in the NEWNE grid and the Southern grid. - Highlights: • We estimate effects of co-benefits on installed capacity of CCS projects in the CDM. • We develop a linear programming (LP) model of two grids of India. • Including co-benefits contributes to introduce IGCC with CCS in the CDM at lower CER prices

  1. Nuclear electric propulsion: An integral part of NASA's nuclear propulsion project

    International Nuclear Information System (INIS)

    Stone, J.R.

    1992-01-01

    NASA has initiated a technology program to establish the readiness of nuclear propulsion technology for the Space Exploration Initiative (SEI). This program was initiated with a very modest effort identified with nuclear thermal propulsion (NTP); however, nuclear electric propulsion (NEP) is also an integral part of this program and builds upon NASA's Base Research and Technology Program in power and electric propulsion as well as the SP-100 space nuclear power program. Although the Synthesis Group On America's SEI has identified NEP only as an option for cargo missions, recent studies conducted by NASA-Lewis show that NEP offers the potential for early manned Mars missions as well. Lower power NEP is also of current interest for outer planetary robotic missions. Current plans are reviewed for the overall nuclear propulsion project, with emphasis on NEP and those elements of NTP program which have synergism with NEP

  2. Financing Nuclear Projects. Case Study: Unit 2 Cernavoda NPP

    International Nuclear Information System (INIS)

    Chirica, Teodor; Constantin, Carmencita; Dobrin, Marian

    2003-01-01

    The implementation of a Nuclear Power Plant (NPP) is a major undertaking for all entities involved, due to the necessity of planning work and coordination of the implementation process of the different fields of interest, starting with the governmental authorities and ending with the public. Having in view the specific investment costs (relatively high) for a NPP, finding an adequate financing structure is possible through an iterative process that involves first an assessment of the technical performances of the project and secondly, the mathematical modelling of the financing structure effects on the projects. In this respect, the paper will be focused on the main steps needed in order to promote an investment project in nuclear field, starting with the decision phase, providing the documentation requested by the local and international authorities to promote the project and ending with the negotiation of the contracts (commercial contract, financing contract, purchase contract, etc). The case study will be focused on the phases achieved in order to promote the Unit 2 NPP Cernavoda completion works project. (authors)

  3. Financing nuclear projects. Case study: Unit 2 Cernavoda NPP

    International Nuclear Information System (INIS)

    Chirica, T.; Pall, S.; Lebedev, A.; Dobrin, M.

    2003-01-01

    The implementation of a Nuclear Power Plant (NPP) in a country is a major undertaking for all entities involved, due to the necessity of planning work and co-ordination of the implementation process of the different fields of interest, starting with the governmental authorities and ending with the people. Having in view the specific investment cost (relatively high) for a NPP, to find an adequate financing structure is possible through an iterative process that involves first an assessment of the technical performances of the project and second, the mathematical modelling of the financing structure effects on the project. In this respect, the paper proposed will be focused on the main steps needed in order to promote an investment project in nuclear field, starting with the decision phase, providing the documentations requested by the local and international authorities to promote the project and ending with the negotiation of the contracts (commercial contract, financing contract, power purchase contract, etc.) The case study will be focused on the phases achieved in order to promote the Unit 2 Cernavoda NPP completion works project. (author)

  4. Computer-integrated design and information management for nuclear projects

    International Nuclear Information System (INIS)

    Gonzalez, A.; Martin-Guirado, L.; Nebrera, F.

    1987-01-01

    Over the past seven years, Empresarios Agrupados has been developing a comprehensive, computer-integrated system to perform the majority of the engineering, design, procurement and construction management activities in nuclear, fossil-fired as well as hydro power plant projects. This system, which is already in a production environment, comprises a large number of computer programs and data bases designed using a modular approach. Each software module, dedicated to meeting the needs of a particular design group or project discipline, facilitates the performance of functional tasks characteristic of the power plant engineering process

  5. Cash flow forecasting model for nuclear power projects

    International Nuclear Information System (INIS)

    Liu Wei; Guo Jilin

    2002-01-01

    Cash flow forecasting is very important for owners and contractors of nuclear power projects to arrange the capital and to decrease the capital cost. The factors related to contractor cash flow forecasting are analyzed and a cash flow forecasting model is presented which is suitable for both contractors and owners. The model is efficiently solved using a cost-schedule data integration scheme described. A program is developed based on the model and verified with real project data. The result indicates that the model is efficient and effective

  6. Project plan remove special nuclear material from PFP project plutonium finishing plant; TOPICAL

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617,Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

  7. Project plan remove special nuclear material from PFP project plutonium finishing plant

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617, Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

  8. Economical aspects of a nuclear power plant project

    International Nuclear Information System (INIS)

    Meldonian, N.L.; Santos, E.M. dos

    1992-01-01

    This work describes different aspects and parameters that should be regarded as guidelines for economic evaluation of small and medium power plant projects. The main objective of an economic evaluation is to establish the plant's unitary cost and its economic figure of merit. To achieve that, a number of studies must be undertaken to compare the global competitiveness of a nuclear power plant with other energetic alternatives. These studies involve macro economy, energy generation, electricity transmission and global feasibility of the enterprise. It is concluded that the economic evaluation of a nuclear power plant should be considered as the culmination of a long process of planning at a national level. The main reasons are the investments involved, the technological developments required and political implications of the utilization of nuclear power energy. (author)

  9. Advanced nuclear reactor public opinion project. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-07-25

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

  10. Design of management information system for nuclear industry architectural project costs

    International Nuclear Information System (INIS)

    Zhang Xingzhi; Li Wei

    1996-01-01

    Management Information System (MIS) for nuclear industry architectural project is analysed and designed in detail base on quota management and engineering budget management of nuclear industry in respect of the practice of Qinshan Second Phase 2 x 600 MW Project

  11. South Ukraine Nuclear Power Plant. Advanced Computer Information System Project

    International Nuclear Information System (INIS)

    Hord, J.; Afanasiev, N.; Smith, C.; Kudinov, Yu.

    1997-01-01

    The South Ukraine upgrade is the first of many that will take place in the former eastern bloc countries over the next several years. Westron is currently developing a similar system for the Zaporozhe nuclear power plant. In addition, there are eleven other WWER type units in operation in the Ukraine, as well as twenty seven others in operation throughout Eastern and Central Europe and Russia - all potential upgrade projects. (author)

  12. Next Generation Nuclear Plant Project 2009 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Larry Demick; Jim Kinsey; Keith Perry; Dave Petti

    2010-05-01

    The mission of the NGNP Project is to broaden the environmental and economic benefits of nuclear energy technology to the United States and other economies by demonstrating its applicability to market sectors not served by light water reactors (LWRs). Those markets typically use fossil fuels to fulfill their energy needs, and high temperature gas-cooled reactors (HTGRs) like the NGNP can reduce this dependence and the resulting carbon footprint.

  13. A Project in Support of Nuclear Technology Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Young Cheol; Kim, Kyoung Pyo; Yi, Ji Ho [and others

    2007-12-15

    The results and contents of the project are as follows; - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. - Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. - Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. - Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. - Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy information and computer software developed in the advanced countries.

  14. A Project in Support of Nuclear Technology Cooperation

    International Nuclear Information System (INIS)

    Lee, Kyu Jung; Choi, Pyong Hoon; Yi, Ji Ho and others

    2004-12-01

    The result and contents of the project are as follows; - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. - Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. - Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. - Using the INIS output data, it has provided domestic users with searching INIS CD-Rom DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. - Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Effective management of computer codes for nuclear application and establishment of information exchange mechanism for rapid technical support. - acquisition of nuclear computer codes from NEA Data Bank an registration of new software developed by domestic organization

  15. Nuclear New Build: Insights into Financing and Project Management

    International Nuclear Information System (INIS)

    Horst Keppler, Jan; Cometto, Marco; Kim, Sang-Baik; Sozoniuk, Vladislav; Rothwell, Geoffrey; Thompson, Orme; Savage, Chris; Mancini, Mauro; Leigne, Philippe; Bickford, Erica; Crozat, Matt

    2015-01-01

    Nuclear new build has been progressing steadily since the year 2000, with the construction of 94 new reactors initiated and 56 completed reactors connected to the grid. Among these new reactors are some of the first generation III/III+ reactors of their kind. Drawing on a combination of conceptual analysis, expert opinion and seven in-depth case studies, this report provides policy makers and stakeholders with an overview of the principal challenges facing nuclear new build today, as well as ways to address and overcome them. It focuses on the most important challenges of building a new nuclear power plant, namely assembling the conditions necessary to successfully finance and manage highly complex construction processes and their supply chains. Different projects have chosen different paths, but they nonetheless share a number of features. Financing capital-intensive nuclear new build projects requires, for example, the long-term stabilisation of electricity prices whether through tariffs, power purchase agreements or contracts for difference. In construction, the global convergence of engineering codes and quality standards would also promote both competition and public confidence. In addition, change management, early supply chain planning and 'soft issues' such as leadership, team building and trust have emerged over and again as key factors in the new build construction process. This report looks at ongoing trends in these areas and possible ways forward. (authors)

  16. A Project in Support of Nuclear Technology Cooperation

    International Nuclear Information System (INIS)

    Ko, Young Cheol; Kim, Kyoung Pyo; Yi, Ji Ho

    2007-12-01

    The results and contents of the project are as follows; - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. - Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. - Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. - Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. - Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy information and computer software developed in the advanced countries

  17. A Project in Support of Nuclear Technology Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Young Cheol; Kim, Kyoung Pyo; Yi, Ji Ho (and others)

    2007-12-15

    The results and contents of the project are as follows; - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. - Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. - Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. - Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. - Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy information and computer software developed in the advanced countries.

  18. Improved best estimate plus uncertainty methodology, including advanced validation concepts, to license evolving nuclear reactors

    International Nuclear Information System (INIS)

    Unal, C.; Williams, B.; Hemez, F.; Atamturktur, S.H.; McClure, P.

    2011-01-01

    Research highlights: → The best estimate plus uncertainty methodology (BEPU) is one option in the licensing of nuclear reactors. → The challenges for extending the BEPU method for fuel qualification for an advanced reactor fuel are primarily driven by schedule, the need for data, and the sufficiency of the data. → In this paper we develop an extended BEPU methodology that can potentially be used to address these new challenges in the design and licensing of advanced nuclear reactors. → The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. → The methodology includes a formalism to quantify an adequate level of validation (predictive maturity) with respect to existing data, so that required new testing can be minimized, saving cost by demonstrating that further testing will not enhance the quality of the predictive tools. - Abstract: Many evolving nuclear energy technologies use advanced predictive multiscale, multiphysics modeling and simulation (M and S) capabilities to reduce the cost and schedule of design and licensing. Historically, the role of experiments has been as a primary tool for the design and understanding of nuclear system behavior, while M and S played the subordinate role of supporting experiments. In the new era of multiscale, multiphysics computational-based technology development, this role has been reversed. The experiments will still be needed, but they will be performed at different scales to calibrate and validate the models leading to predictive simulations for design and licensing. Minimizing the required number of validation experiments produces cost and time savings. The use of multiscale, multiphysics models introduces challenges in validating these predictive tools - traditional methodologies will have to be modified to address these challenges. This paper gives the basic aspects of a methodology that can potentially be used to address these new challenges in

  19. Human factors design of nuclear power plant control rooms including computer-based operator aids

    International Nuclear Information System (INIS)

    Bastl, W.; Felkel, L.; Becker, G.; Bohr, E.

    1983-01-01

    The scientific handling of human factors problems in control rooms began around 1970 on the basis of safety considerations. Some recent research work deals with the development of computerized systems like plant balance calculation, safety parameter display, alarm reduction and disturbance analysis. For disturbance analysis purposes it is necessary to homogenize the information presented to the operator according to the actual plant situation in order to supply the operator with the information he most urgently needs at the time. Different approaches for solving this problem are discussed, and an overview is given on what is being done. Other research projects concentrate on the detailed analysis of operators' diagnosis strategies in unexpected situations, in order to obtain a better understanding of their mental processes and the influences upon them when such situations occur. This project involves the use of a simulator and sophisticated recording and analysis methods. Control rooms are currently designed with the aid of mock-ups. They enable operators to contribute their experience to the optimization of the arrangement of displays and controls. Modern control rooms are characterized by increasing use of process computers and CRT (Cathode Ray Tube) displays. A general concept for the integration of the new computerized system and the conventional control panels is needed. The technical changes modify operators' tasks, and future ergonomic work in nuclear plants will need to consider the re-allocation of function between man and machine, the incorporation of task changes in training programmes, and the optimal design of information presentation using CRTs. Aspects of developments in control room design are detailed, typical research results are dealt with, and a brief forecast of the ergonomic contribution to be made in the Federal Republic of Germany is given

  20. Rehabilitation and modernization project of units 1 and 2 of Laguna Verde Nuclear Power Plant. A strengthening project to 120%. (2nd phase)

    International Nuclear Information System (INIS)

    Liebana, B.; Merino, A.; Garcia, J. L.; Gomez, M.; Martinez, I.; Ruiz, L.

    2010-01-01

    The power increase of the Laguna Verde Nuclear Power Plant is a project for the rehabilitation and modernization of the turbo and associated equipment to get an increase of its power and of its service life. The project scope includes the design, the engineering, the equipment supply, the installation, the testing and the commissioning. This article presents the work of the second phase.

  1. Decontamination and decommissioning project for the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Paik, S. T.; Park, S. W. (and others)

    2007-02-15

    The final goal of this project is to complete the decommissioning of the Korean Research Reactor no.1 and no. 2(KRR-1 and 2) and uranium conversion plant safely and successfully. The goal of this project in 2006 is to complete the decontamination of the inside reactor hall of the KRR-2 which will be operating as a temporary storage for the radioactive waste until the construction and operation of the national repository site. Also the decommissioning work of the KRR-1 and auxiliary facilities is being progress. As the compaction of decommissioning project is near at hand, a computer information system was developed for a systematically control and preserve a technical experience and decommissioning data for the future reuse. The nuclear facility decommissioning, which is the first challenge in Korea, is being closed to the final stages. We completed the decommissioning of all the bio-shielding concrete for KRR-2 in 2005 and carried out the decontamination and waste material grouping of the roof, wall and bottom of the reactor hall of the KRR-2. The decommissioning for nuclear facility were demanded the high technology, remote control equipment and radioactivity analysis. So developed equipment and experience will be applied at the decommissioning for new nuclear facility in the future.

  2. Engineering for new-built nuclear power plant projects; Ingenieria para proyectos de nuevas centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Lopez, A.

    2012-11-01

    This article reviews the opportunities existing in the market (electrical utilities and reactor vendors) for an engineering company with the profile of Empresarios Agrupados (EA) in new-built nuclear power plant projects. To do this, reference is made to some representative examples of projects in which EA has been participating recently. the article concludes sharing with the reader some lessons learned from this participation. (Author)

  3. CORR Guidelines. Preparing and Conducting Review Missions of Construction Project Readiness for Nuclear Power Plants

    International Nuclear Information System (INIS)

    2013-01-01

    The construction readiness review (CORR) mission for nuclear power plant projects has been established with the aim of conducting peer reviews of construction projects related to nuclear power plants. Such a mission provides a detailed assessment of readiness for construction, construction progress, readiness for turnover, as well as recommendations for improvement. Organizations in Member States, such as nuclear utilities, owners, regulators and technical support organizations, can benefit from such reviews. A team of international experts with complementing specialities will conduct the CORR mission. The review is based on appropriate IAEA publications, such as IAEA Safety Standards Series Guides and IAEA Nuclear Energy Series publications, as well as on internationally recognized project and construction management guides. Mission findings are summarized in a mission report, which includes a list of recommendations, suggestions and identified good practices. The review is not intended to be a regulatory inspection or an audit against international codes and standards. Rather, it is a peer review aimed at improving implementation processes and procedures through an exchange of technical experiences and practices at the working level. The mission is applicable at any stage of a nuclear power plant construction project, although two specific phases are targeted: (1) start of construction mission (Phase 1 mission) and (2) an in-progress mission (Phase 2 mission). Missions are initiated when official requests are submitted by Member States through the appropriate IAEA channels

  4. Analysis of the efficiency of some international projects in Ukraine for future of nuclear energy

    International Nuclear Information System (INIS)

    Radovskaya, O.; Pysmennaya, U.; Zenyuk, D.

    2001-01-01

    The report presents the review of the status and perspectives for nuclear energy development in Ukraine. The role of certain projects for young experts is evaluated - among these projects the basic one is the IAEA Technical Co-operation Project UKR/4/006 S trategy for Nuclear Energy Development , as well as projects of the Ukrainian Nuclear Society and the Institute of Nuclear and Energy Law. (authors)

  5. Study on nuclear power plant project construction and management mode in China

    International Nuclear Information System (INIS)

    Wang Kai; Chen Lian

    2009-01-01

    Project management mode plays a key role in project construction, especially in nuclear power field. From the aspects of right, responsibility and benefit, this paper discussed the differences among the common used project management modes. Also the main kinds of the construction management modes used in China's nuclear power plants were summarized. At last, considering the experience of Ningde nuclear power plant, this paper put forward several perspectives about the selection of project management mode in nuclear power plant construction. (authors)

  6. Design management of general contractor under nuclear power project EPC mode

    International Nuclear Information System (INIS)

    Su Shaojian

    2013-01-01

    Design management has not yet formed a theoretical system recognized, general contractor design managers under nuclear power project EPC Mode lack the clear theory basis. This paper aims to discuss Design management from the angle of general contractor under nuclear power project EPC mode, Gives the concept of design management Clearly, by Combining the characteristics of nuclear power project, Gives the specific content and meaning of the design management of nuclear power project. (authors)

  7. The feasibility of uranium enrichment in Brazil for use in nuclear bombs and the conceptual project of a nuclear explosive

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1990-05-01

    This work reports the steps to define a brazilian system of nuclear safeguards under the congress responsibility. It discusses as well the feasibility of uranium enrichment for nuclear weapons, the construction of a nuclear submarine and the conceptual project of a nuclear explosive. (A.C.A.S.)

  8. Progress on the Hanford K basins spent nuclear fuel project

    International Nuclear Information System (INIS)

    Culley, G.E.; Fulton, J.C.; Gerber, E.W.

    1996-01-01

    This paper highlights progress made during the last year toward removing the Department of Energy's (DOE) approximately, 2,100 metric tons of metallic spent nuclear fuel from the two outdated K Basins at the Hanford Site and placing it in safe, economical interim dry storage. In the past year, the Spent Nuclear Fuel (SNF) Project has engaged in an evolutionary process involving the customer, regulatory bodies, and the public that has resulted in a quicker, cheaper, and safer strategy for accomplishing that goal. Development and implementation of the Integrated Process Strategy for K Basins Fuel is as much a case study of modern project and business management within the regulatory system as it is a technical achievement. A year ago, the SNF Project developed the K Basins Path Forward that, beginning in December 1998, would move the spent nuclear fuel currently stored in the K Basins to a new Staging and Storage Facility by December 2000. The second stage of this $960 million two-stage plan would complete the project by conditioning the metallic fuel and placing it in interim dry storage by 2006. In accepting this plan, the DOE established goals that the fuel removal schedule be accelerated by a year, that fuel conditioning be closely coupled with fuel removal, and that the cost be reduced by at least $300 million. The SNF Project conducted coordinated engineering and technology studies over a three-month period that established the technical framework needed to design and construct facilities, and implement processes compatible with these goals. The result was the Integrated Process Strategy for K Basins Fuel. This strategy accomplishes the goals set forth by the DOE by beginning fuel removal a year earlier in December 1997, completing it by December 1999, beginning conditioning within six months of starting fuel removal, and accomplishes it for $340 million less than the previous Path Forward plan

  9. Decontamination and Decommissioning Project for the Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Paik, S. T.; Park, S. W. and others

    2006-02-15

    The final goal of this project is to complete safely and successfully the decommissioning of the Korean Research Reactor no.1 (KRR-1) and the Korean Research Reactor no.2 (KRR-2), and uranium conversion plant (UCP). The dismantling of the reactor hall of the KRR-2 was planned to complete till the end of 2004, but it was delayed because of a few unexpected factors such as the development of a remotely operated equipment for dismantling of the highly radioactive parts of the beam port tubes. In 2005, the dismantling of the bio-shielding concrete structure of the KRR-2 was finished and the hall can be used as a temporary storage space for the radioactive waste generated during the decommissioning of the KRR-1 and KRR-2. The cutting experience of the shielding concrete by diamond wire saw and the drilling experience by a core boring machine will be applied to another nuclear facility dismantling. An effective management tool of the decommissioning projects, named DECOMIS, was developed and the data from the decommissioning projects were gathered. This system provided many information on the daily D and D works, waste generation, radiation dose, etc., so an effective management of the decommissioning projects is expected from next year. The operation experience of the uranium conversion plant as a nuclear fuel cycle facility was much contributed to the localization of nuclear fuels for both HWR and PWR. It was shut down in 1993 and a program for its decontamination and dismantling was launched in 2001 to remove all the contaminated equipment and to achieve the environment restoration. The decommissioning project is expected to contribute to the development of the D and D technologies for the other domestic fuel cycle facilities and the settlement of the new criteria for decommissioning of the fuel cycle related facilities.

  10. Siting and early-stage project management of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Kai; Li Guojin

    2013-01-01

    In this paper, difficulties and challenges facing in siting of nuclear power plant after Fukushima nuclear accident is introduced. The key points for siting are analyzed. The site characteristics related to nuclear safety and the evaluated methods are discussed. From project management perspective, main procedures and key points for the early-stage of a nuclear power project are described. (authors)

  11. Resource Letter MP-1: The Manhattan Project and related nuclear research

    Science.gov (United States)

    Reed, B. Cameron

    2005-09-01

    This Resource Letter provides a guide to literature on the Manhattan Project and related nuclear research. Books and journal articles are cited for the following topics: general works, technical works, biographical and autobiographical works, the German nuclear program, and technical papers of historical interest. A list of videos and websites dealing with the Manhattan Project, nuclear weapons, and nuclear issues is also given.

  12. Reliability and limitation of various diagnostic methods including nuclear medicine in myocardial disease

    International Nuclear Information System (INIS)

    Tokuyasu, Yoshiki; Kusakabe, Kiyoko; Yamazaki, Toshio

    1981-01-01

    Electrocardiography (ECG), echocardiography, nuclear method, cardiac catheterization, left ventriculography and endomyocardial biopsy (biopsy) were performed in 40 cases of cardiomyopathy (CM), 9 of endocardial fibroelastosis and 19 of specific heart muscle disease, and the usefulness and limitation of each method was comparatively estimated. In CM, various methods including biopsy were performed. The 40 patients were classified into 3 groups, i.e., hypertrophic (17), dilated (20) and non-hypertrophic.non-dilated (3) on the basis of left ventricular ejection fraction and hypertrophy of the ventricular wall. The hypertrophic group was divided into 4 subgroups: 9 septal, 4 apical, 2 posterior and 2 anterior. The nuclear study is useful in assessing the site of the abnormal ventricular thickening, perfusion defect and ventricular function. Echocardiography is most useful in detecting asymmetric septal hypertrophy. The biopsy gives the sole diagnostic clue, especially in non-hypertrophic.non-dilated cardiomyopathy. ECG is useful in all cases but correlation with the site of disproportional hypertrophy was not obtained. (J.P.N.)

  13. International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). 2011 Progress Report. Enhancing Global Nuclear Energy Sustainability

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-05-15

    safety under normal and design basis accident conditions is a key requirement for the development of nuclear power. Severe accident prevention and mitigation measures received increased attention following the Fukushima accident. Parallel to the above mentioned development, the INPRO Methodology shall be updated in the areas of safety and infrastructure, taking into account new requirements and guidelines. The INPRO Methodology requires that a major release of radioactivity from a nuclear installation should be prevented for all practical purposes, so that in the case of an accident there is no need for evacuation measures outside the plant site. Although the accident at TEPCO's Fukushima Daiichi nuclear power plant did not reveal any new phenomena, some relevant areas have to be analysed in more depth. Following the 'stress tests' which were performed for operating power plants in many countries, INPRO's nuclear energy systems assessment for innovative nuclear installations will have to consider the combined effects of extreme external hazards, including the implications of having multiple nuclear units on one site with shared services. The accident also revealed the importance of the safety culture during all phases of a nuclear project. In that light, the INPRO Methodology in the area of infrastructure will be reviewed. For a newcomer country, it is also important to assess the levels of support or concerns about nuclear technology both within the country and in neighbouring countries. The development of new and innovative nuclear reactors and fuel cycles will be a key pillar in further strengthening the safe use of nuclear energy in the long term. Under INPRO, a new project will be developed to study the nuclear safety issues impacting innovative nuclear reactors and fuel cycles using the INPRO Methodology including consideration of combined multiple simultaneous natural and technical disasters and/or human error. The plan is to evaluate advanced nuclear energy

  14. International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). 2011 Progress Report. Enhancing Global Nuclear Energy Sustainability

    International Nuclear Information System (INIS)

    2012-05-01

    safety under normal and design basis accident conditions is a key requirement for the development of nuclear power. Severe accident prevention and mitigation measures received increased attention following the Fukushima accident. Parallel to the above mentioned development, the INPRO Methodology shall be updated in the areas of safety and infrastructure, taking into account new requirements and guidelines. The INPRO Methodology requires that a major release of radioactivity from a nuclear installation should be prevented for all practical purposes, so that in the case of an accident there is no need for evacuation measures outside the plant site. Although the accident at TEPCO's Fukushima Daiichi nuclear power plant did not reveal any new phenomena, some relevant areas have to be analysed in more depth. Following the 'stress tests' which were performed for operating power plants in many countries, INPRO's nuclear energy systems assessment for innovative nuclear installations will have to consider the combined effects of extreme external hazards, including the implications of having multiple nuclear units on one site with shared services. The accident also revealed the importance of the safety culture during all phases of a nuclear project. In that light, the INPRO Methodology in the area of infrastructure will be reviewed. For a newcomer country, it is also important to assess the levels of support or concerns about nuclear technology both within the country and in neighbouring countries. The development of new and innovative nuclear reactors and fuel cycles will be a key pillar in further strengthening the safe use of nuclear energy in the long term. Under INPRO, a new project will be developed to study the nuclear safety issues impacting innovative nuclear reactors and fuel cycles using the INPRO Methodology including consideration of combined multiple simultaneous natural and technical disasters and/or human error. The plan is to evaluate advanced nuclear energy

  15. Spent Nuclear Fuel project systems engineering management plan

    International Nuclear Information System (INIS)

    Womack, J.C.

    1995-01-01

    The purpose of the WHC Systems Engineering Management Plan (SEMP) is to describe the systems engineering approach and methods that will be integrated with established WHC engineering practices to enhance the WHC engineering management of the SNF Project. The scope of the SEMP encompasses the efforts needed to manage the WHC implementation of systems engineering on the SNF Project. This implementation applies to, and is tailored to the needs of the SNF project and all its subprojects, including all current and future subprojects

  16. Nuclear project sites on Shimokita Peninsula in summer 1989

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The present report outlines the current progress in the nuclear projects implemented on the Shimokita Peninsula. At Rokkashomura, Japan Nuclear Fuel Industries is building a uranium enrichment plant. The basic work began in October 1988 and was completed by the end of May, and building work on the plant began. The plant building construction has now progressed to 50% for the first unit of 150,000 SUW/year. The site for the low level radioactive waste storage facility is still flat ground. For the reprocessing plant, Japan Nuclear Fuel Service's permit for waste management business is still before STA. Only road construction, unrelated to licensing, is going on. The completion of the safety examination for reprocessing is expected around 1991. At Higashidorimura, a fishery cooperative has rejected the proposal of compensation, and the compensation problem is at a stalemate. Following a zig-zag course in political disturbances, the Nuclear Ship Mutsu entered its port at Sekinehama in January 1988. Corrosion dots were found on some of the fuel assemblies, and Japan Atomic Energy Research Institute plans to carry out the recovery work in this autumn. Site acquisition procedures for building an Ohma nuclear power plant are now under way. (N.K.)

  17. A project-based system for including farmers in the EU ETS

    DEFF Research Database (Denmark)

    Brandt, Urs Steiner; Svendsen, Gert Tinggaard

    2011-01-01

    as ‘the missing link’ in past climate negotiations. We argue that farmers have relatively low marginal reduction costs and that consequences in terms of the effect on permit price and technology are overall positive in the EU Emission Trading System (ETS). Thus, we propose a project-based system......Farmers in the EU do not trade greenhouse gases under the Kyoto agreement. This is an empirical puzzle because agriculture is a significant contributor of greenhouse gases (GHG) in the EU and may harvest private net gains from trade. Furthermore, the US has strongly advocated land-use practices...... for including the farming practices in the EU ETS that reduces the uncertainty from measuring emission reduction in this sector. The system encourages GHG reduction either by introducing a new and less polluting practice or by reducing the polluting activity. When doing so, farmers will receive GHG permits...

  18. Practical Calculational Scheme Implementing the Wilsonian RG Results for Nuclear Effective Field Theory Including Pions

    International Nuclear Information System (INIS)

    Kubo, H.; Harada, K.; Sakaeda, T.; Yamamoto, Y.

    2013-01-01

    On the basis of the Wilsonian renormalization group (WRG) analysis of nuclear effective field theory (NEFT) including pions, we propose a practical calculational scheme in which the short-distance part of one-pion exchange (S-OPE) is removed and represented as contact terms. The long-distance part of one-pion exchange (L-OPE) is treated as perturbation. The use of dimensional regularization (DR) for diagrams consisting only of contact interactions considerably simplifies the calculation of scattering amplitude and the renormalization group equations. NLO results for nucleon-nucleon elastic scattering in the S-waves are obtained and compared with experiments. A brief comment on NNLO calculations is given. (author)

  19. Analysis of advanced European nuclear fuel cycle scenarios including transmutation and economical estimates

    International Nuclear Information System (INIS)

    Merino Rodriguez, I.; Alvarez-Velarde, F.; Martin-Fuertes, F.

    2013-01-01

    Four European fuel cycle scenarios involving transmutation options have been addressed from a point of view of resources utilization and economics. Scenarios include the current fleet using Light Water Reactor (LWR) technology and open fuel cycle (as a reference scenario), a full replacement of the initial fleet with Fast Reactors (FR) burning U-Pu MOX fuel and two fuel cycles with Minor Actinide (MA) transmutation in a fraction of the FR fleet or in dedicated Accelerator Driven Systems (ADS).Results reveal that all scenarios are feasible according to nuclear resources demand. Regarding the economic analysis, the estimations show an increase of LCOE - averaged over the whole period - with respect to the reference scenario of 20% for Pu management scenario and around 35% for both transmutation scenarios respectively.

  20. Analysis of advanced European nuclear fuel cycle scenarios including transmutation and economical estimates

    Energy Technology Data Exchange (ETDEWEB)

    Merino Rodriguez, I.; Alvarez-Velarde, F.; Martin-Fuertes, F.

    2013-07-01

    Four European fuel cycle scenarios involving transmutation options have been addressed from a point of view of resources utilization and economics. Scenarios include the current fleet using Light Water Reactor (LWR) technology and open fuel cycle (as a reference scenario), a full replacement of the initial fleet with Fast Reactors (FR) burning U-Pu MOX fuel and two fuel cycles with Minor Actinide (MA) transmutation in a fraction of the FR fleet or in dedicated Accelerator Driven Systems (ADS).Results reveal that all scenarios are feasible according to nuclear resources demand. Regarding the economic analysis, the estimations show an increase of LCOE - averaged over the whole period - with respect to the reference scenario of 20% for Pu management scenario and around 35% for both transmutation scenarios respectively.

  1. Application of the graded management approach to Battelle's nuclear project

    International Nuclear Information System (INIS)

    Voth, C.B.

    1996-01-01

    Battelle's graded management approach provides an effective and efficient method to perform the Battelle Columbus Laboratories Decommissioning Project (BCLDP). The project is managed by Battelle under their US Nuclear Regulatory Commission (NRC) license but is partially funded by the US Department of Energy (DOE) on a cost-shared basis. Battelle's graded management approach adheres to the regulations and orders governing the BCLDP by the interaction of various plans, procedures, permits, and work instructions. By independent assessment, quality control, and worker training, Battelle has been able to establish a cost-effective approach to performing work and, at the same time, have a controlled checks and balance system to assure the proper safety considerations and project particulars are taken into account

  2. Uncertainty-driven nuclear data evaluation including thermal (n,α) applied to 59Ni

    Science.gov (United States)

    Helgesson, P.; Sjöstrand, H.; Rochman, D.

    2017-11-01

    This paper presents a novel approach to the evaluation of nuclear data (ND), combining experimental data for thermal cross sections with resonance parameters and nuclear reaction modeling. The method involves sampling of various uncertain parameters, in particular uncertain components in experimental setups, and provides extensive covariance information, including consistent cross-channel correlations over the whole energy spectrum. The method is developed for, and applied to, 59Ni, but may be used as a whole, or in part, for other nuclides. 59Ni is particularly interesting since a substantial amount of 59Ni is produced in thermal nuclear reactors by neutron capture in 58Ni and since it has a non-threshold (n,α) cross section. Therefore, 59Ni gives a very important contribution to the helium production in stainless steel in a thermal reactor. However, current evaluated ND libraries contain old information for 59Ni, without any uncertainty information. The work includes a study of thermal cross section experiments and a novel combination of this experimental information, giving the full multivariate distribution of the thermal cross sections. In particular, the thermal (n,α) cross section is found to be 12.7 ± . 7 b. This is consistent with, but yet different from, current established values. Further, the distribution of thermal cross sections is combined with reported resonance parameters, and with TENDL-2015 data, to provide full random ENDF files; all of this is done in a novel way, keeping uncertainties and correlations in mind. The random files are also condensed into one single ENDF file with covariance information, which is now part of a beta version of JEFF 3.3. Finally, the random ENDF files have been processed and used in an MCNP model to study the helium production in stainless steel. The increase in the (n,α) rate due to 59Ni compared to fresh stainless steel is found to be a factor of 5.2 at a certain time in the reactor vessel, with a relative

  3. 25 CFR 170.915 - May tribal employment taxes or fees be included in an IRR project budget?

    Science.gov (United States)

    2010-04-01

    ... Preference § 170.915 May tribal employment taxes or fees be included in an IRR project budget? Yes. The cost of tribal employment taxes or fees may be included in the budget for an IRR program or project... 25 Indians 1 2010-04-01 2010-04-01 false May tribal employment taxes or fees be included in an IRR...

  4. Annual Report of the Tandem Accelerator Center, Nuclear and Solid State Research Project, University of Tsukuba

    International Nuclear Information System (INIS)

    1978-01-01

    In 1977, 12 UD Pelletron tandem accelerator has been operated by the University's researchers and engineers. Except for the tank opening for regular inspection we met twice the troubles which forced to change the accelerating tube. The experiences teach us that it needs about 20 days to finish the conditioning after changing the accelerating tube. A sputter ion source of new version is now being installed on the top floor. Two devices for the detection of X-rays were tested. An apparatus for bombardment of samples in air for biological and medical sciences has been successfully used. The subjects of researches on nuclear physics cover the light-ion reactions, heavy-ion reactions and nuclear spectroscopy. A special emphasis has been put on the measurements on vector- and tensor-analyzing powers in the light-ion reactions, because of a higher efficiency of the polarized ion source. Elaborate works on the heavy-ion reactions including the angular correlation patterns and excitation functions have been made in parallel. Papers of these works are now being prepared, a few having been published already. Moreover, in the University of Tsukuba, a new research system, called Special Research Project on Nuclear and Solid State Sciences Using Accelerated Beams (Nuclear and Solid State Research Project) started in 1978 and will continue for five years. In this research project, researchers from various Institutes in the University of Tsukuba, as well as visiting researchers from other institutions in Japan and from abroad, participate. Using a variety of accelerated beams, i.e. of heavy, light and polarized beams, this research project aims mainly at the high excitation, short life, transient and inhomogeneous states both in nuclear and extra-nuclear world. It covers both fundamental research in nuclear, atomic and solid state sciences as well as their application in various fields. (J.P.N.)

  5. Improved best estimate plus uncertainty methodology including advanced validation concepts to license evolving nuclear reactors

    International Nuclear Information System (INIS)

    Unal, Cetin; Williams, Brian; McClure, Patrick; Nelson, Ralph A.

    2010-01-01

    Many evolving nuclear energy programs plan to use advanced predictive multi-scale multi-physics simulation and modeling capabilities to reduce cost and time from design through licensing. Historically, the role of experiments was primary tool for design and understanding of nuclear system behavior while modeling and simulation played the subordinate role of supporting experiments. In the new era of multi-scale multi-physics computational based technology development, the experiments will still be needed but they will be performed at different scales to calibrate and validate models leading predictive simulations. Cost saving goals of programs will require us to minimize the required number of validation experiments. Utilization of more multi-scale multi-physics models introduces complexities in the validation of predictive tools. Traditional methodologies will have to be modified to address these arising issues. This paper lays out the basic aspects of a methodology that can be potentially used to address these new challenges in design and licensing of evolving nuclear technology programs. The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. An enhanced calibration concept is introduced and is accomplished through data assimilation. The goal is to enable best-estimate prediction of system behaviors in both normal and safety related environments. To achieve this goal requires the additional steps of estimating the domain of validation and quantification of uncertainties that allow for extension of results to areas of the validation domain that are not directly tested with experiments, which might include extension of the modeling and simulation (M and S) capabilities for application to full-scale systems. The new methodology suggests a formalism to quantify an adequate level of validation (predictive maturity) with respect to required selective data so that required testing can be minimized for

  6. Improved best estimate plus uncertainty methodology including advanced validation concepts to license evolving nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Unal, Cetin [Los Alamos National Laboratory; Williams, Brian [Los Alamos National Laboratory; Mc Clure, Patrick [Los Alamos National Laboratory; Nelson, Ralph A [IDAHO NATIONAL LAB

    2010-01-01

    Many evolving nuclear energy programs plan to use advanced predictive multi-scale multi-physics simulation and modeling capabilities to reduce cost and time from design through licensing. Historically, the role of experiments was primary tool for design and understanding of nuclear system behavior while modeling and simulation played the subordinate role of supporting experiments. In the new era of multi-scale multi-physics computational based technology development, the experiments will still be needed but they will be performed at different scales to calibrate and validate models leading predictive simulations. Cost saving goals of programs will require us to minimize the required number of validation experiments. Utilization of more multi-scale multi-physics models introduces complexities in the validation of predictive tools. Traditional methodologies will have to be modified to address these arising issues. This paper lays out the basic aspects of a methodology that can be potentially used to address these new challenges in design and licensing of evolving nuclear technology programs. The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. An enhanced calibration concept is introduced and is accomplished through data assimilation. The goal is to enable best-estimate prediction of system behaviors in both normal and safety related environments. To achieve this goal requires the additional steps of estimating the domain of validation and quantification of uncertainties that allow for extension of results to areas of the validation domain that are not directly tested with experiments, which might include extension of the modeling and simulation (M&S) capabilities for application to full-scale systems. The new methodology suggests a formalism to quantify an adequate level of validation (predictive maturity) with respect to required selective data so that required testing can be minimized for cost

  7. Practice and innovation on safety management of Haiyang Nuclear Power Project

    International Nuclear Information System (INIS)

    Wei Guohu

    2011-01-01

    From the perspective of owner, this article has introduced the safety management model and practice of Haiyang Nuclear Power Project, one of AP1000 Self-reliance Program supporting projects of China. And the article has summarized characteristics of the safety management of Haiyang Project for reference and communication with nuclear or other projects. (author)

  8. Spent nuclear fuels project characterization data quality objectives strategy

    International Nuclear Information System (INIS)

    Lawrence, L.A.; Thornton, T.A.; Redus, K.S.

    1994-12-01

    A strategy is presented for implementation of the Data Quality Objectives (DQO) process to the Spent Nuclear Fuels Project (SNFP) characterization activities. Westinghouse Hanford Company (WHC) and the Pacific Northwest Laboratory (PNL) are teaming in the characterization of the SNF on the Hanford Site and are committed to the DQO process outlined in this strategy. The SNFP characterization activities will collect and evaluate the required data to support project initiatives and decisions related to interim safe storage and the path forward for disposal. The DQO process is the basis for the activity specific SNF characterization requirements, termed the SNF Characterization DQO for that specific activity, which will be issued by the WHC or PNL organization responsible for the specific activity. The Characterization Plan prepared by PNL defines safety, remediation, and disposal issues. The ongoing Defense Nuclear Facility Safety Board (DNFSB) requirement and plans and the fuel storage and disposition options studies provide the need and direction for the activity specific DQO process. The hierarchy of characterization and DQO related documentation requirements is presented in this strategy. The management of the DQO process and the means of documenting the DQO process are described as well as the tailoring of the DQO process to the specific need of the SNFP characterization activities. This strategy will assure stakeholder and project management that the proper data was collected and evaluated to support programmatic decisions

  9. On Brazil's participation in the International Project on Innovative Nuclear Reactors and Fuels Cycles (INPRO)

    International Nuclear Information System (INIS)

    Goncalves Filho, Orlando Joao Agostinho

    2007-01-01

    In response to a resolution of its 44th General Conference (GC(44)/RES/21) held in September 2000, the International Atomic Energy Agency launched in May 2001 the International Project on Innovative Nuclear Reactors and Fuels Cycles (INPRO) with the objective of supporting the safe, sustainable, economic and proliferation-resistant use of nuclear technology to meet the global energy needs of the 21st century. Brazil joined the project from its beginnings and in 2005 submitted a proposal for the screening assessment using INPRO methodology of two small-size light-water reactors as potential components of an innovative nuclear reactor system (INS) completed with a conventional open nuclear fuel cycle. The INS reactor components currently being assessed are the International Reactor Innovative and Secure (IRIS) that is being developed by an international consortium made of 21 organizations from 10 countries (Brazil included) led by the Westinghouse Company, and the Fixed Bed Nuclear Reactor (FBNR) that is being developed at the Federal University of Rio Grande do Sul. This paper gives an overview of Brazil's participation in INPRO, highlighting the objective, scope and intermediate results of the assessment study being performed, and the possibilities for participation in one or two collaborative research projects under INPRO Phase 2 Action Plan for 2008-2009. (author)

  10. Seminar on the organization and management of a commercial nuclear power project

    International Nuclear Information System (INIS)

    Peddicord, K.L.; Alvis, J.M.; Chitkara, K.K.

    1986-01-01

    A main function of student branches of the American Nuclear Society (ANS) is to identify activities that contribute to the professional development and growth of its student members. Over the past several years, the ANS student branch at Texas A and M University has toured the construction site of the South Texas Nuclear Project (STNP), which is jointly owned by the Houston Lighting and Power Company (HL and P), the City of San Antonio, the Central Power and Light Company, and the City of Austin. This year, student branch organizers recognized that another aspect of a commercial nuclear power plant was not being covered either in the academic course work or the plant tours. This facet includes the organization and management required to undertake a major nuclear power project. To fill this gap, HL and P sponsored a one-day seminar that covered the various managerial functions for STNP. The seminar on the Organization and Management at a Commercial Nuclear Power Project was very interesting and beneficial. Other ANS branches and utilities may find this to be a useful model for future activities

  11. Nuclear emergency planning in Spain. The PLABEN review project

    International Nuclear Information System (INIS)

    Lentijo Lentijo, J. C.; Vila Pena, M.

    2002-01-01

    The international rules and recommendations for nuclear emergency planning and the Spanish experience gained in the management of event with radiological risk have noticed that is necessary to review the planning radiological bases for emergencies in nuclear power plants and to define the planning radiological bases for radiological emergencies that could happen in radioactive facilities or in activities out of the regulatory framework. The paper focuses on CSN actions concerning the Plaben review project related to define the new radiological principles taking into account the current international recommendations for interventions, make a proposal about the organisation and operation of the provincial radiological action group and the national support level for radiological emergency response. (Author) 7 refs

  12. Outline of research project on nuclear fusion, 1985

    International Nuclear Information System (INIS)

    Uchida, Taijiro

    1985-08-01

    When the advance of nuclear fusion research during 10 years hereafter is predicted, the next project should start the research toward nuclear burning, adopt the diversified ways, and develop the research in wide related fields. The central subject such as the containment of plasma is studies with large experimental facilities, but in the related fields, the research subsidies must be utilized positively. The organization to perform the research compries 6 groups, 1) reactor materials and plasma-wall interactions 2) science and engineering of tritium, and influence on living things, 4) development of superconducting magnets, 5) fusion blanket engineering, and 6) design and assessment of thermonuclear reactors. The distribution and management of the scientific research subsidy are explained. All of the subjects of planned and publicly invited research a listed, and the researchers concerned, the amount of subsidy, the objective and the plan of execution in fiscal year 1984 of each research are outlined. (J.P.N.)

  13. Outline of research project on nuclear fusion, 1984

    International Nuclear Information System (INIS)

    Uchida, Taijiro

    1984-08-01

    When the advance of nuclear fusion research during 10 years hereafter is predicted, the next project should start the research toward nuclear burning, adopt the diversified ways, a nd develop the research in wide related fields. The central subject such as the containment of plasma is studies with large experimental facilities, but in the related fields, the research subsidies must be utilized positively. The organization to perform the research compries 6 groups, 1) reactor materials and plasma-wall interaction, 2) science and engineering of tritium and influence on living things, 3) fundamentals of core control, 4) development of superconducting magnets, 5) fusion blanket engineering, and 6) design and assessment of thermonuclear reactors. The distribution and management of the scientific research subsidy are explained. All of the subjects of planned and publicly invited research a listed, and the researchers concerned, the amount of subsidy, the objective and the plan of execution in fiscal 1983 of each research are outlined. (J.P.N.)

  14. Financing of nuclear projects. Lessons from a recent experience

    International Nuclear Information System (INIS)

    Shubert, U.

    2004-01-01

    The advantages of mandating BNP Paribas as a lead bank and arranger for NPP Belene are presented. BNPP has an excellent record and credentials in Nuclear Power Plant Projects internationally and in the local energy sector and very recent experience as a lead bank for the fifth nuclear power plant in Finland. BNPP has a proven track record as Provider of rapid and efficient ECA financing in terms of: managing in parallel the number of ECA contractual relations, so as to provide 'matching opportunities' between the ECAs and leverage to improve their terms and conditions, and to harmonize them in one set of unified legal documentation. There is no cost to the Government of Bulgaria until the signing of the Facility Documentation

  15. Educational project for the nuclear power and nuclear waste public acceptance fostering

    International Nuclear Information System (INIS)

    Constantin, M.; Diaconu, Daniela

    2005-01-01

    Full text: Until now, public acceptance of nuclear power in Romania can be assessed as good. The main motivations could be: the primacy effect of the information, the poverty, the absence of the interest, the relative low informing level. However we expect important changes in the near future: more active NGOs with anti-nuclear opinion, the public's awareness will be more important, serious opposition against the continuation of the nuclear development may appear followed by a reformulation of the Romanian ecologists ideas. The problem of radioactive nuclear wastes (RNW) is the most sensitive and, related to the public opinion, we expect it will become crucial in 10-15 years. The main assumption of our project is that children who are now in schools will be tomorrow's decision makers on 'nuclear energy and RNW. Thus, we intend to prepare the young generation for the future participation in the decision making process related to RNW. The paper shows the main ideas (initial conditions obtained by actual knowledge level measurements, constraints, methods, information contents, evaluation methods and produced outputs) of the educational proposed programme. The work is part of the Romanian contribution to COWAM FP6 project. (authors)

  16. Nuclear targets within the project of solving CHAllenges in Nuclear DAta

    Science.gov (United States)

    Sibbens, Goedele; Moens, André; Vanleeuw, David; Lewis, David; Aregbe, Yetunde

    2017-09-01

    In the frame of the European Commission funded integrated project CHANDA (solving CHAllenges in Nuclear DAta) the importance of nuclear target preparation for the accurateness and reliability of experimental nuclear data is set in a dedicated work package (WP3). The global aim of WP3 is the development of a network for nuclear target preparation and characterization, enabling to coordinate the target production corresponding to the experimental requirements. Therefore, a set of tasks within the work package needs to be followed. Primarily, an inventory of target related facilities and radioisotope providers was created. In the next step a priority list of target requests was made in agreement with the target user considering the technical specification, the scheduled experiments and the availability of the target laboratories. A set of target requests has been assigned to the Target Preparation laboratory of the European Commission - Joint Research Centre - Directorate G (EC-JRC.G.2) in Geel, Belgium. This contribution gives an overview of the nuclear targets that are produced within the CHANDA project. The equipment and techniques available for the preparation and characterization of uranium, plutonium and neptunium layers with an areal density ranging from 60 to 205 μg cm-2 will be emphasized.

  17. Identifying Issues in Applying Integrated Project Delivery to Domestic Nuclear Power Plant Construction Projects

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Joo [Korean Nuclear Society, Daejeon (Korea, Republic of)

    2016-05-15

    Integrated Project Delivery (IPD) is defined as that people, systems, business structures, and practices of key stakeholders are incorporated into a single-team, with a single process, which executes a project in a way of optimizing the project's outcome, increasing values delivered to the end user, reducing waste, and maximizing efficiency throughout the phases of engineering to construction. The researcher had carried out literature review in terms of IPD to identify major characteristics of IPD which are presented in the following section and had compared such characteristics against peculiarities of nuclear power plant (NPP) construction projects in order to shed light on obstacles in possible application of IPD method to domestic NPP construction projects in the coming days. In this research, three (3) major characteristics of IPD were identified: 1) key stakeholders signing one balanced contract, forming de facto one body, sharing risk and reward 2) an integrated project team being formed in the early stage of a project and providing input to minimize time and cost loss from rework downstream 3) team members co-locating, having open and direct communication, making decisions on time, and pursuing the success of the project itself.

  18. Neptuno-nuclear European platform of training and university organizations project

    International Nuclear Information System (INIS)

    Comsa, Olivia; Meglea, Claudia; Banutoiu, Marina; Paraschiva, M. V.; Meglea, S.

    2003-01-01

    The project focuses on a harmonised approach to education and training in nuclear engineering in Europe and its implementation, including better integration of national resources and capabilities. The expected result is an operational network for training and life-long learning schemes as well as for academic education at the master, doctoral and post doctoral degree, underpinning: - sustainability of European's excellence in nuclear technology; - harmonised approaches to safety and best practices, both operational and regulatory at European level in Member States and Accession Countries; - preservation of competence and expertise for the continued safe use of nuclear energy and other uses of irradiations in industry and medicine; - harmonised approach for training and education in nuclear engineering. In the network: - we implement the roadmap for nuclear education in Europe as developed and demonstrated in the ongoing Euratom FP5 project ENEM; - we warrant the end-user relevance of the education at all levels by recruiting (part-time) professors out of industry and by providing (re-)training of nuclear industry personnel; - we teach advanced courses preferably at selected centres of excellence; - bridging leading edge research and new knowledge generation with teaching and education; -creating nuclei of excellence for doctoral schools in nuclear engineering and sciences; - we facilitate transnational access to research infrastructure. The final aim of the NEPTUNO initiative is to guarantee sufficient people, means and knowledge (resources) to make possible the safe and efficient applications of the nuclear technology to the civil and industry in the medium and long term. This will be accomplished by the design, development and testing of a system able to achieve the sustainable integration of education and training in nuclear engineering and safety in Europe. Thus, by responding to the EC objective for call for proposals, a joint approach to be widely applied in

  19. A project-based system for including farmers in the EU ETS.

    Science.gov (United States)

    Brandt, Urs Steiner; Svendsen, Gert Tinggaard

    2011-04-01

    Farmers in the EU do not trade greenhouse gases under the Kyoto agreement. This is an empirical puzzle because agriculture is a significant contributor of greenhouse gases (GHG) in the EU and may harvest private net gains from trade. Furthermore, the US has strongly advocated land-use practices as 'the missing link' in past climate negotiations. We argue that farmers have relatively low marginal reduction costs and that consequences in terms of the effect on permit price and technology are overall positive in the EU Emission Trading System (ETS). Thus, we propose a project-based system for including the farming practices in the EU ETS that reduces the uncertainty from measuring emission reduction in this sector. The system encourages GHG reduction either by introducing a new and less polluting practice or by reducing the polluting activity. When doing so, farmers will receive GHG permits corresponding to the amount of reduction which can be stored for later use or sold in the EU ETS. Copyright © 2010 Elsevier Ltd. All rights reserved.

  20. Thermal hydraulic feasibility assessment of the spent nuclear fuel project

    International Nuclear Information System (INIS)

    Heard, F.J.

    1996-01-01

    A series of analyses have been completed investigating the thermal-hydraulic performance and feasibility of the Spent Nuclear Fuel Project (SNFP) Integrated Process Strategy (IPS). The goal was to develop a series of thermal-hydraulic models that could respond to all process and safety related issues that may arise pertaining to the SNFP, as well as provide a basis for validation of the results. Results show that there is a reasonable envelope for process conditions and requirements that are thermally and hydraulically acceptable

  1. Purposes and related aspects of the nuclear power plant aging Project

    International Nuclear Information System (INIS)

    Garaud, J.; Reynes, L.; Montardy, A. de

    1989-01-01

    The purposes and some aspects of the nuclear power plant Lifetime project is presented. The work is focused on the study of the aging of the PWR type power plant components. The project consists in two phases. The first one involves: the status reports and the analysis of the lifetime data of the most sensitive units, as well as the applied actions and proposals, the influence of the exploitation modes, the safety and the cost prospectives. The second phase includes: the definition, the contracts, the complementary actions and their achievement, the reasons and the surveyance improvements, the development of the decision supporting means, the summary and the conclusions. The selected units for the project first step and the project of actions, are listed. The first conclusions of the project show that most of the 900 MW PWR reactor components will have about 40 years of service life [fr

  2. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    PICKETT, W.W.

    2000-09-22

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure.

  3. DESIGN VERIFICATION REPORT SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2003-02-12

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Revision 3 of this document incorporates MCO Cover Cap Assembly welding verification activities. Verification activities for the installed and operational SSCs have been completed.

  4. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    International Nuclear Information System (INIS)

    PICKETT, W.W.

    2000-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure

  5. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2001-05-15

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted in section 3

  6. DESIGN VERIFICATION REPORT SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2003-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Revision 3 of this document incorporates MCO Cover Cap Assembly welding verification activities. Verification activities for the installed and operational SSCs have been completed

  7. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2001-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted in section 3.1.5 and will be

  8. National project : advanced robot for nuclear power plant

    International Nuclear Information System (INIS)

    Tsunemi, T.; Takehara, K.; Hayashi, T.; Okano, H.; Sugiyama, S.

    1993-01-01

    The national project 'Advanced Robot' has been promoted by the Agency of Industrial science and Technology, MITI for eight years since 1983. The robot for a nuclear plant is one of the projects, and is a prototype intelligent one that also has a three dimensional vision system to generate an environmental model, a quadrupedal walking mechanism to work on stairs and four fingered manipulators to disassemble a valve with a hand tool. Many basic technologies such as an actuator, a tactile sensor, autonomous control and so on progress to high level. The prototype robot succeeded functionally in official demonstration in 1990. More refining such as downsizing and higher intelligence is necessary to realize a commercial robot, while basic technologies are useful to improve conventional robots and systems. This paper presents application studies on the advanced robot technologies. (author)

  9. Joint Arab project for building of nuclear power plants

    International Nuclear Information System (INIS)

    Mosbah, D.S.

    2010-01-01

    Recently many Arab countries have expressed their interest in adopting nuclear power for electricity generation and seawater desalination in their energy strategies and hence sought assistance from IAEA and Arab Atomic Energy Agency. The Council of the League of Arab States at the summit level encouraged member states to develop peaceful use of atomic energy in different aspects of development, especially in energy generation and to establish a cooperative Arab program in this field. The burden of infrastructure can be reduced significantly if an Arab country forms a sharing partnership with other Arab countries. The sharing can be between two or more Arab states. It can include physical facilities, common programmes and knowledge, which will reflect in economic benefits. The sharing can also contribute in a significant manner to harmonization of codes and standards in general and regulatory framework in particular. This article outlines the major direct benefits of joint nuclear Arab programme to build a Nuclear Power Plants. (author)

  10. Fatigue evaluation including environmental effects for primary circuit components in nuclear power plants

    International Nuclear Information System (INIS)

    Seichter, Johannes; Reese, Sven H.; Klucke, Dietmar

    2013-01-01

    The influence of LWR coolant environment to the lifetime of materials in Nuclear Power Plants is in discussion internationally. Environmental phenomena were investigated in laboratory tests and published in recent years. The discussion is mainly focused both on the transition from laboratory to real plant components and on numerical calculation procedures. Since publishing of the NUREG/CR-6909 report in 2007, formulae for calculating the Fen factors have been modified several times. Various calculation procedures like the so called 'Strain-integrated Method' and 'Simplified Approach' have been published while each approach yields to different results. The recent revision of the calculation procedure, proposed by ANL in 2012, is presented and discussed with regard to possible variations in the results depending on the assumptions made. In German KTA Rules the effect of environmentally assisted fatigue (EAF) is taken into account by means of so called attention thresholds. If the threshold value is exceeded, further measures like NDT, in-service inspections including fracture mechanical evaluations or detailed assessment procedures have to be performed. One way to handle those measures is to apply sophisticated procedures and to show that the calculated CUF is below the defined attention thresholds. On the basis of a practical example, methods and approaches will be discussed and recommendations in terms of avoiding over-conservatism and misinterpretation will be presented.

  11. Fatigue evaluation including environmental effects for primary circuit components in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seichter, Johannes [Siempelkamp Pruef- und Gutachter-Gesellschaft mbH, Dresden (Germany); Reese, Sven H.; Klucke, Dietmar [Component Technology Global Unit Generation, E.ON Kernkraft GmbH, Hannover (Germany)

    2013-05-15

    The influence of LWR coolant environment to the lifetime of materials in Nuclear Power Plants is in discussion internationally. Environmental phenomena were investigated in laboratory tests and published in recent years. The discussion is mainly focused both on the transition from laboratory to real plant components and on numerical calculation procedures. Since publishing of the NUREG/CR-6909 report in 2007, formulae for calculating the Fen factors have been modified several times. Various calculation procedures like the so called 'Strain-integrated Method' and 'Simplified Approach' have been published while each approach yields to different results. The recent revision of the calculation procedure, proposed by ANL in 2012, is presented and discussed with regard to possible variations in the results depending on the assumptions made. In German KTA Rules the effect of environmentally assisted fatigue (EAF) is taken into account by means of so called attention thresholds. If the threshold value is exceeded, further measures like NDT, in-service inspections including fracture mechanical evaluations or detailed assessment procedures have to be performed. One way to handle those measures is to apply sophisticated procedures and to show that the calculated CUF is below the defined attention thresholds. On the basis of a practical example, methods and approaches will be discussed and recommendations in terms of avoiding over-conservatism and misinterpretation will be presented.

  12. A comparative assessment of the economics of plutonium disposition including comparison with other nuclear fuel cycles

    International Nuclear Information System (INIS)

    Williams, K.A.; Miller, J.W.; Reid, R.L.

    1997-01-01

    DOE has been evaluating three technologies for the disposition of approximately 50 metric tons of surplus plutonium from defense-related programs: reactors, immobilization, and deep boreholes. As part of the process supporting an early CY 1997 Record of Decision (ROD), a comprehensive assessment of technical viability, cost, and schedule has been conducted. Oak Ridge National Laboratory has managed and coordinated the life-cycle cost (LCC) assessment effort for this program. This paper discusses the economic analysis methodology and the results prior to ROD. Other objectives of the paper are to discuss major technical and economic issues that impact plutonium disposition cost and schedule. Also to compare the economics of a once-through weapons-derived MOX nuclear fuel cycle to other fuel cycles, such as those utilizing spent fuel reprocessing. To evaluate the economics of these technologies on an equitable basis, a set of cost estimating guidelines and a common cost-estimating format were utilized by all three technology teams. This paper also includes the major economic analysis assumptions and the comparative constant-dollar and discounted-dollar LCCs

  13. Thermosetting polymer for dynamic nuclear polarization: Solidification of an epoxy resin mixture including TEMPO

    Energy Technology Data Exchange (ETDEWEB)

    Noda, Yohei, E-mail: noda.yohei@jaea.go.jp [Quantum Beam Science Centre, Sector of Nuclear Science Research, Japan Atomic Energy Agency, Shirakata-Shirane, Tokai, Ibaraki 319-1195 (Japan); Kumada, Takayuki [Quantum Beam Science Centre, Sector of Nuclear Science Research, Kansai Photon Science Institute, Japan Atomic Energy Agency, Kizugawa, Kyoto 619-0215 (Japan); Yamaguchi, Daisuke; Shamoto, Shin-ichi [Quantum Beam Science Centre, Sector of Nuclear Science Research, Japan Atomic Energy Agency, Shirakata-Shirane, Tokai, Ibaraki 319-1195 (Japan)

    2015-03-11

    We investigated the dynamic nuclear polarization (DNP) of typical thermosetting polymers (two-component type epoxy resins; Araldite{sup ®} Standard or Araldite{sup ®} Rapid) doped with a (2,2,6,6-tetramethylpiperidine-1-yl)oxy (TEMPO) radical. The doping process was developed by carefully considering the decomposition of TEMPO during the solidification of the epoxy resin. The TEMPO electron spin in each two-component paste decayed slowly, which was favorable for our study. Furthermore, despite the dissolved TEMPO, the mixture of the two-component paste successfully solidified. With the resulting TEMPO-doped epoxy-resin samples, DNP experiments at 1.2 K and 3.35 T indicated a magnitude of a proton-spin polarization up to 39%. This polarization is similar to that (35%) obtained for TEMPO-doped polystyrene (PS), which is often used as a standard sample for DNP. To combine this solidification of TEMPO-including mixture with a resin-casting technique enables a creation of polymeric target materials with a precise and complex structure.

  14. 25 CFR 170.623 - How are IRR Program projects and activities included in a self-governance agreement?

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false How are IRR Program projects and activities included in a self-governance agreement? 170.623 Section 170.623 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE... self-governance agreement? To include an IRR Program project or activity in a self-governance agreement...

  15. The Sydvaerme project: District heating from the Barsebeck nuclear power plant

    International Nuclear Information System (INIS)

    Josefsson, L.

    1977-01-01

    The paper presents a summary report of a study on district heating from Barsebeck Nuclear Power Plant in Sweden, prepared cooperatively by the cities of Malmoe, Lund, Helsingborg, Landskrona and the electric power company Sydkraft. A future number 3 generating set at the Barsebeck nuclear power station could be designed for combined production of heat and electric power. The generating set could be completed after 1983, and could then supply about 65% of total district heating requirements. The first stage of the investigation includes a proposal for a technically feasible solution, sufficiently detailed to permit both technical and economic evaluation of the project. (author)

  16. Project of law relative to the sanitary consequences of French nuclear weapons tests

    International Nuclear Information System (INIS)

    2009-05-01

    In order to make easy the indemnifications and to include the persons having participate to nuclear weapons tests (Sahara and French Polynesia) and populations leaving in the concerned areas, the project of law relative to the repair of sanitary consequences of nuclear weapons tests proposes to create a right to integral repair of prejudices for the persons suffering of a radioinduced disease coming from these tests. The American example and the British example are given for comparison. The modalities of financing are detailed as well as the social economic and administrative impacts. (N.C.)

  17. Supporting PECO countries in combating illicit trafficking of nuclear materials - Status of ongoing projects

    International Nuclear Information System (INIS)

    Janssens, W.; Daures, P.; Cromboom, O.; Mayer, K.; Koch, L.

    2001-01-01

    . The Romanian Police has been equipped with specific personal detection devices and nuclear data software (Nuclide 2000) upon request. As EUROPOL showed interest during the kick-off meeting, a close co-operation is being organised including training for Europol staff and a common follow-up of the above-cited projects. Participation to the demonstration exercises is foreseen. Last but not least, as a spin-off of the project with Poland, an additional project for the improvement of the detection of nuclear material at the Polish/Russian border around Kaliningrad has recently been submitted. (author)

  18. HRTEM study of α-AlMnSi crystals including non-crystallographic projection axes

    International Nuclear Information System (INIS)

    Song, G.L.; Bursill, L.A.

    1997-01-01

    The structure of α-AlMnSi is examined by atomic resolution high-resolution transmission electron microscopy (HRTEM) and computer-based image matching techniques. Six distinct zone axes are examined; including both normal crystallographic and non-crystallographic zones axes of the structural motifs, which have m3-bar 5 icosahedral symmetry. The results provide a sound basis for understanding HRTEM images of the quasicrystalline alloy i-AlMnSi; thus it was examined to what extent the requirements for obtaining so-called structure images of complex alloy structures may be met experimentally and define when the images may be reliably interpreted on the basis of computer simulation and image-matching at about 0.17nm resolution. Most difficulty was experienced in obtaining the experimental images, especially for the non-crystallographic zones, which are very sensitive to slight changes in orientation off the desired zone axis or projection, the rate at which the crystal thickness is increasing (wedge-angle) and the orientation of the surfaces of the specimen. Surface amorphous layers due to oxidation and/or electron-induced irradiation damage also limit the efficiency of the HRTEM analysis. For the thin specimens used for HRTEM, both the electron diffraction patterns and the HRTEM images are characteristic of Im3-bar space group symmetry. It is suggested that this Im3-bar symmetry may be an example of a statistical symmetry, where the local symmetry is close to Pm3-bar but the average symmetry is Im3-bar. The transition from Pm3-bar to Im3-bar may be understood in terms of an analysis of small changes in the outer shells of the large icosahedral structural elements which are located at the corners and body-centers of the cubic unit cell. 21 refs., 3 tabs., 10 figs

  19. Elaboration of a guide including relevant project and logistic information: a case study

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Tchaikowisky M. [Faculdade de Tecnologia e Ciencias (FTC), Itabuna, BA (Brazil); Bresci, Claudio T.; Franca, Carlos M.M. [PETROBRAS, Rio de Janeiro, RJ (Brazil)

    2009-07-01

    For every mobilization of a new enterprise it is necessary to quickly obtain the greatest amount of relative information in regards to location and availability of infra-structure, logistics, and work site amenities. Among this information are reports elaborated for management of the enterprise, (organizational chart, work schedule, objectives, contacts, etc.) as well as geographic anomalies, social-economic and culture of the area to be developed such as territorial extension, land aspects, local population, roads and amenities (fuel stations ,restaurants and hotels), infra-structure of the cities (health, education, entertainment, housing, transport, etc.) and logistically the distance between cities the estimated travel time, ROW access maps and notable points, among other relevant information. With the idea of making this information available for everyone involved in the enterprise, it was elaborated for GASCAC Spread 2A a rapid guide containing all the information mentioned above and made it available for all the vehicles used to transport employees and visitors to the spread. With this, everyone quickly received the majority of information necessary in one place, in a practical, quick, and precise manner, since the information is always used and controlled by the same person. This study includes the model used in the gas pipeline GASCAC Spread 2A project and the methodology used to draft and update the information. Besides the above, a file in the GIS format was prepared containing all necessary planning, execution and tracking information for enterprise activities, from social communication to the execution of the works previously mentioned. Part of the GIS file information was uploaded to Google Earth so as to disclose the information to a greater group of people, bearing in mind that this program is free of charge and easy to use. (author)

  20. HRTEM study of {alpha}-AlMnSi crystals including non-crystallographic projection axes

    Energy Technology Data Exchange (ETDEWEB)

    Song, G.L.; Bursill, L.A.

    1997-06-01

    The structure of {alpha}-AlMnSi is examined by atomic resolution high-resolution transmission electron microscopy (HRTEM) and computer-based image matching techniques. Six distinct zone axes are examined; including both normal crystallographic and non-crystallographic zones axes of the structural motifs, which have m3-bar 5 icosahedral symmetry. The results provide a sound basis for understanding HRTEM images of the quasicrystalline alloy i-AlMnSi; thus it was examined to what extent the requirements for obtaining so-called structure images of complex alloy structures may be met experimentally and define when the images may be reliably interpreted on the basis of computer simulation and image-matching at about 0.17nm resolution. Most difficulty was experienced in obtaining the experimental images, especially for the non-crystallographic zones, which are very sensitive to slight changes in orientation off the desired zone axis or projection, the rate at which the crystal thickness is increasing (wedge-angle) and the orientation of the surfaces of the specimen. Surface amorphous layers due to oxidation and/or electron-induced irradiation damage also limit the efficiency of the HRTEM analysis. For the thin specimens used for HRTEM, both the electron diffraction patterns and the HRTEM images are characteristic of Im3-bar space group symmetry. It is suggested that this Im3-bar symmetry may be an example of a statistical symmetry, where the local symmetry is close to Pm3-bar but the average symmetry is Im3-bar. The transition from Pm3-bar to Im3-bar may be understood in terms of an analysis of small changes in the outer shells of the large icosahedral structural elements which are located at the corners and body-centers of the cubic unit cell. 21 refs., 3 tabs., 10 figs.

  1. International project on innovative nuclear reactors and fuel cycles

    International Nuclear Information System (INIS)

    Mourogov, V. M.; Juhn, P. E.

    2003-01-01

    In response to two IAEA General Conference Resolutions in September 2000, the IAEA has launched the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) in May 2001. As of February 2003, 12 IAEA Member States and the European Commission have become members of INPRO. In total, 19 cost-free experts have been nominated by these Member States and the European Commission to work for the INPRO project at the IAEA. Four meetings of the INPRO Steering Committee (SC), which is the decision and review body of INPRO, were held, two in 2001 and another two in 2002. The objective of INPRO, which is composed of two phases (Phase 1 and Phase 2), is to support safe, economic and proliferation resistant use of nuclear technology, in a sustainable manner, to meet the global energy needs in the next 50 years and beyond. During Phase 1, work is also subdivided in two sub phases: The currently on-going Phase 1A is focussing on the selection of criteria and development of methodologies and guidelines for the comparison of different reactor and fuel cycle concepts and approaches, taking into account the compilation and review of such concepts and approaches, and determination of user requirements in the areas of economics; environment; safety; proliferation-resistance; and cross cutting issues. The preliminary results of Phase 1A with respect to user requirements are summarized in the paper

  2. Summaries of special research project on nuclear fusion 1980

    International Nuclear Information System (INIS)

    Uchida, Taijiro

    1981-09-01

    This is a report of the research project entitled ''Nuclear fusion'', supported by the grant in aid for fusion research from the Ministry of Education in the fiscal year 1980. The research project was started in April, 1980, and comprises the following seventeen subjects of nuclear fusion research. 1) Heavy irradiation effects, 2) plasma-wall interaction, 3) neutronics, 4) welding engineering, 5) science and technology of tritium, 6) biological effects of tritium, 7) diagnostics of high temperature plasma, 8) new lasers, 9) fundamentals of plasma heating, 10) high efficiency energy conversion, 11) theory and computer simulation, 12) superconducting materials, 13) fundamental phenomena of superconductivity, 14) magnet technology, 15) heat transfer and structural engineering, 16) system design, and 17) resources and assessment of fusion energy. 43 summaries concerning reactor materials and plasma-wall interaction, 29 summaries concerning the science, technology and biological effects of tritium, 41 summaries concerning the fundamentals of reactor plasma control, 15 summaries concerning the technology of superconducting magnets, and 14 summaries concerning the design of fusion reactors and its evaluation are collected in this report, and their results and progress can be known. (Kako, I.)

  3. A project in support of nuclear technology cooperation

    International Nuclear Information System (INIS)

    Hwang, Deok Ku; Choi, Pyung Hoon; Lee, Ji Ho

    2001-12-01

    The results and contents of the project are as follows; Establish strategies of international cooperation in an effort to promote our nation's leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB nd INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing

  4. Including Energy Efficiency and Renewable Energy Policies in Electricity Demand Projections

    Science.gov (United States)

    Find more information on how state and local air agencies can identify on-the-books EE/RE policies, develop a methodology for projecting a jurisdiction's energy demand, and estimate the change in power sector emissions.

  5. Research on quality assurance classification methodology for domestic AP1000 nuclear power projects

    International Nuclear Information System (INIS)

    Bai Jinhua; Jiang Huijie; Li Jingyan

    2012-01-01

    To meet the quality assurance classification requirements of domestic nuclear safety codes and standards, this paper analyzes the quality assurance classification methodology of domestic AP1000 nuclear power projects at present, and proposes the quality assurance classification methodology for subsequent AP1000 nuclear power projects. (authors)

  6. Nuclear waste glass melter design including the power and control systems

    International Nuclear Information System (INIS)

    Chapman, C.C.

    1982-01-01

    An energy balance of a joule-heated nuclear waste glass melter is used to discuss the problems in the design of the melter geometry and in the specifications of the power and control systems. The relationships between geometry, electrode current density, production rate, load voltage, and load power are presented graphically. The influence of liquid feeding on the surface of the glass and the variability of nuclear waste glass on the design and control during operation is discussed. 10 refs

  7. Startup and operation at the Browns Ferry Nuclear Plant (includes March 22, 1975, cabel tray fire)

    International Nuclear Information System (INIS)

    Metke, R.G.

    1977-01-01

    This paper addresses itself to significant events experienced during startup and operation of the three unit Browns Ferry Nuclear Plant located near Athens, Alabama. It consists of two major parts: (1) Resolution of significant equipment problems, and (2) Description of the March 22, 1975, cable tray fire. Identification of principal problems and their solutions should help prevent similar obstacles and related costly delays at other nuclear stations

  8. Nuclear Reactor/Hydrogen Process Interface Including the HyPEP Model

    International Nuclear Information System (INIS)

    Steven R. Sherman

    2007-01-01

    The Nuclear Reactor/Hydrogen Plant interface is the intermediate heat transport loop that will connect a very high temperature gas-cooled nuclear reactor (VHTR) to a thermochemical, high-temperature electrolysis, or hybrid hydrogen production plant. A prototype plant called the Next Generation Nuclear Plant (NGNP) is planned for construction and operation at the Idaho National Laboratory in the 2018-2021 timeframe, and will involve a VHTR, a high-temperature interface, and a hydrogen production plant. The interface is responsible for transporting high-temperature thermal energy from the nuclear reactor to the hydrogen production plant while protecting the nuclear plant from operational disturbances at the hydrogen plant. Development of the interface is occurring under the DOE Nuclear Hydrogen Initiative (NHI) and involves the study, design, and development of high-temperature heat exchangers, heat transport systems, materials, safety, and integrated system models. Research and development work on the system interface began in 2004 and is expected to continue at least until the start of construction of an engineering-scale demonstration plant

  9. Project quality management under EPC mode by the owner of nuclear power plant

    International Nuclear Information System (INIS)

    Xu Hui; Hu Miao

    2014-01-01

    As the first completely independent nuclear power project in China, Fangjiashan nuclear power project is constructed under EPC mode of general project contracting. This paper, taking the project as an example, aims to explore how the project owners carry out quality management for the installation project during the construction of the nuclear power plant based on EPC mode. It has certain reference value for the management of following nuclear power projects which adopting the EPC construction mode. It will play a positive role in improving China's overall self-management abilities in the nuclear power construction, and lay a solid foundation for follow-up nuclear power construction in China. (authors)

  10. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    International Nuclear Information System (INIS)

    1995-01-01

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system

  11. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  12. Analysis of advanced european nuclear fuel cycle scenarios including transmutation and economical estimates

    International Nuclear Information System (INIS)

    Merino Rodriguez, I.; Alvarez-Velarde, F.; Martin-Fuertes, F.

    2013-01-01

    In this work the transition from the existing Light Water Reactors (LWR) to the advanced reactors is analyzed, including Generation III+ reactors in a European framework. Four European fuel cycle scenarios involving transmutation options have been addressed. The first scenario (i.e., reference) is the current fleet using LWR technology and open fuel cycle. The second scenario assumes a full replacement of the initial fleet with Fast Reactors (FR) burning U-Pu MOX fuel. The third scenario is a modification of the second one introducing Minor Actinide (MA) transmutation in a fraction of the FR fleet. Finally, in the fourth scenario, the LWR fleet is replaced using FR with MOX fuel as well as Accelerator Driven Systems (ADS) for MA transmutation. All scenarios consider an intermediate period of GEN-III+ LWR deployment and they extend for a period of 200 years looking for equilibrium mass flows. The simulations were made using the TR-EVOL code, a tool for fuel cycle studies developed by CIEMAT. The results reveal that all scenarios are feasible according to nuclear resources demand (U and Pu). Concerning to no transmutation cases, the second scenario reduces considerably the Pu inventory in repositories compared to the reference scenario, although the MA inventory increases. The transmutation scenarios show that elimination of the LWR MA legacy requires on one hand a maximum of 33% fraction (i.e., a peak value of 26 FR units) of the FR fleet dedicated to transmutation (MA in MOX fuel, homogeneous transmutation). On the other hand a maximum number of ADS plants accounting for 5% of electricity generation are predicted in the fourth scenario (i.e., 35 ADS units). Regarding the economic analysis, the estimations show an increase of LCOE (Levelized cost of electricity) - averaged over the whole period - with respect to the reference scenario of 21% and 29% for FR and FR with transmutation scenarios respectively, and 34% for the fourth scenario. (authors)

  13. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1995-11-01

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement

  14. SRT project: tele-robotics maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Gomez-Santamaria, J.; Calleja, J.M.; Carmena, P.; Avello, A.; Rubio, Y.A.

    2001-01-01

    The main aim of the SRT project was to develop a family of robots to help in the operation of nuclear power plants. Four robotic systems were developed and this paper focuses on three of them: ANAES -a steam leak detector through noise analysis-, MALIBA -a master-slave tele-operation system with force feedback- and ROBICEN -a compact pneumatic wall climbing robot-. ANAES (the Spanish acronym of spectrum analysis) consists of a set of sensor heads attached to a computer. Each head has two microphones and a video camera installed on it, and a DC motor that rotates the head. The heads are shielded with lead and boron steel, especially near the video camera. The noise generated by the plant is recorded every day at the same time and the software compares the recorded noise with the mean values of past records. The system can discern whether the noise has remarkably changed and, through phase analysis of the sound recorded by both microphones, identifies the direction of arrival (DOA) of the new noise, probably a steam leak. Using several heads, the new noise source can be identified. The video camera can be used to ease the location of the steam leaks. The stationariness of the measured noise has been tested in C.N. Cofrentes -a Spanish BWR-6 reactor-. A finished system with six heads has recently been installed in the MSR (moisture separator reheater) of the same plant. MALIBA is a master-slave tele-operated system with force feedback. It consists of two robots: a Stewart platform used as master robot and an open chain robot used as slave. The slave robot follows faithfully the movements of the master, and the master robot can reflect a force proportional to the force exerted by the slave on the environment. Three tools have been developed for the slave robot: a robot hand that includes a small video camera, a pneumatic drill and a rectifier. The results obtained have shown its effectiveness for the designed operations. ROBICEN is a lightweight pneumatic robot

  15. SRT project: tele-robotics maintenance of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Gomez-Santamaria, J. [Iberdrola SA, Madrid (Spain); Calleja, J.M.; Carmena, P. [Endesa, Madrid (Spain); Avello, A.; Rubio, Y.A. [CEIT-Centro de Estudias e Investigaciones Tecnicas de Guipuzcoa, San Sebastian (Spain)

    2001-07-01

    The main aim of the SRT project was to develop a family of robots to help in the operation of nuclear power plants. Four robotic systems were developed and this paper focuses on three of them: ANAES -a steam leak detector through noise analysis-, MALIBA -a master-slave tele-operation system with force feedback- and ROBICEN -a compact pneumatic wall climbing robot-. ANAES (the Spanish acronym of spectrum analysis) consists of a set of sensor heads attached to a computer. Each head has two microphones and a video camera installed on it, and a DC motor that rotates the head. The heads are shielded with lead and boron steel, especially near the video camera. The noise generated by the plant is recorded every day at the same time and the software compares the recorded noise with the mean values of past records. The system can discern whether the noise has remarkably changed and, through phase analysis of the sound recorded by both microphones, identifies the direction of arrival (DOA) of the new noise, probably a steam leak. Using several heads, the new noise source can be identified. The video camera can be used to ease the location of the steam leaks. The stationariness of the measured noise has been tested in C.N. Cofrentes -a Spanish BWR-6 reactor-. A finished system with six heads has recently been installed in the MSR (moisture separator reheater) of the same plant. MALIBA is a master-slave tele-operated system with force feedback. It consists of two robots: a Stewart platform used as master robot and an open chain robot used as slave. The slave robot follows faithfully the movements of the master, and the master robot can reflect a force proportional to the force exerted by the slave on the environment. Three tools have been developed for the slave robot: a robot hand that includes a small video camera, a pneumatic drill and a rectifier. The results obtained have shown its effectiveness for the designed operations. ROBICEN is a lightweight pneumatic robot

  16. Evaluation of nuclear data for R and D projects; development of database for medical nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Tae Suk [Catholic University, Seoul (Korea); Shin, D. O. [Kyung Hee University, Seoul (Korea); Joh, C. W.; Chang, J. S. [Ajou University, Suwon (Korea); Choi, Y. [Sungkyunkwan University, Seoul (Korea); Kim, S. H. [Hanyang University, Seoul (Korea); Park, S. Y. [National Cancer Center, Seoul (Korea); Shin, D. H.; Lee, S [Kyonggi University, Seoul (Korea)

    2002-04-01

    Medical nuclear data used in the country is not provided by academic associations and organizations concerned and even by government organizations concerned. This is aimed to investigate the diagnostic and therapeutic equipments in the clinical use and the domestic present status of nuclear data and physical properties of sealed or unsealed radioactive isotopes and to establish the nuclear database. About 120 domestic centers take nuclear medicine tests and 52 medical centers do radiotherapy. The 30-odd different kinds of radionuclides are usually used in nuclear medicine in the country. The 30-odd kinds of unsealed sources are used for diagnosis and therapy and 10-odd kinds of sealed sources for brachytherapy in the country. The special radiotherapy includes Gamma-knife, linac-based stereotactic radiosurgery, conformal radiotherapy and Intensity modulated radiotherapy. The nuclear data base has been completed on the basis of these data collected and the web site made is available with ease to anyone who want to get nuclear data. 39 refs., 20 figs., 8 tabs. (Author)

  17. Data base on dose reduction research projects for nuclear power plants

    International Nuclear Information System (INIS)

    Khan, T.A.; Yu, C.K.; Roecklein, A.K.

    1994-05-01

    This is the fifth volume in a series of reports that provide information on dose reduction research and health physics technology or nuclear power plants. The information is taken from two of several databases maintained by Brookhaven National Laboratory's ALARA Center for the Nuclear Regulatory Commission. The research section of the report covers dose reduction projects that are in the experimental or developmental phase. It includes topics such as steam generator degradation, decontamination, robotics, improvements in reactor materials, and inspection techniques. The section on health physics technology discusses dose reduction efforts that are in place or in the process of being implemented at nuclear power plants. A total of 105 new or updated projects are described. All project abstracts from this report are available to nuclear industry professionals with access to a fax machine through the ACEFAX system or a computer with a modem and the proper communications software through the ACE system. Detailed descriptions of how to access all the databases electronically are in the appendices of the report

  18. Data base on dose reduction research projects for nuclear power plants. Volume 5

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A.; Yu, C.K.; Roecklein, A.K. [Brookhaven National Lab., Upton, NY (United States)

    1994-05-01

    This is the fifth volume in a series of reports that provide information on dose reduction research and health physics technology or nuclear power plants. The information is taken from two of several databases maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. The research section of the report covers dose reduction projects that are in the experimental or developmental phase. It includes topics such as steam generator degradation, decontamination, robotics, improvements in reactor materials, and inspection techniques. The section on health physics technology discusses dose reduction efforts that are in place or in the process of being implemented at nuclear power plants. A total of 105 new or updated projects are described. All project abstracts from this report are available to nuclear industry professionals with access to a fax machine through the ACEFAX system or a computer with a modem and the proper communications software through the ACE system. Detailed descriptions of how to access all the databases electronically are in the appendices of the report.

  19. Data base on dose reduction research projects for nuclear power plants. Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A.; Vulin, D.S.; Liang, H.; Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

    1992-08-01

    This is the fourth volume in a series of reports that provide information on dose reduction research and health physics technology for nuclear power plants. The information is taken from a data base maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. This report presents information on 118 new or updated projects, covering a wide range of activities. Projects including steam generator degradation, decontamination, robotics, improvement in reactor materials, and inspection techniques, among others, are described in the research section of the report. The section on health physics technology includes some simple and very cost-effective projects to reduce radiation exposures. Included in this volume is a detailed description of how to access the BNL data bases which store this information. All project abstracts from this report, as well as many other useful documents, can be accessed, with permission, through our on-line system, ACE. A computer equipped with a modem, or a fax machine is all that is required to connect to ACE. Many features of ACE, including software, hardware, and communications specifics, are explained in this report.

  20. Data base on dose reduction research projects for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Khan, T.A.; Vulin, D.S.; Liang, H.; Baum, J.W. (Brookhaven National Lab., Upton, NY (United States))

    1992-08-01

    This is the fourth volume in a series of reports that provide information on dose reduction research and health physics technology for nuclear power plants. The information is taken from a data base maintained by Brookhaven National Laboratory's ALARA Center for the Nuclear Regulatory Commission. This report presents information on 118 new or updated projects, covering a wide range of activities. Projects including steam generator degradation, decontamination, robotics, improvement in reactor materials, and inspection techniques, among others, are described in the research section of the report. The section on health physics technology includes some simple and very cost-effective projects to reduce radiation exposures. Included in this volume is a detailed description of how to access the BNL data bases which store this information. All project abstracts from this report, as well as many other useful documents, can be accessed, with permission, through our on-line system, ACE. A computer equipped with a modem, or a fax machine is all that is required to connect to ACE. Many features of ACE, including software, hardware, and communications specifics, are explained in this report.

  1. Overview of ACTYS project on development of indigenous state-of-the-art code suites for nuclear activation analysis

    International Nuclear Information System (INIS)

    Subhash, P.V.; Tadepalli, Sai Chaitanya; Deshpande, Shishir P.; Kanth, Priti; Srinivasan, R.

    2017-01-01

    Rigorous activation calculations are warranted for safer and efficient design of future fusion machines. Suitable activation codes, which yield accurate results with faster performance yet include all fusion relevant reactions are a prerequisite. To meet these, an indigenous project called ACTYS-Project is initiated and as a result, four state-of-art codes are developed so far. The goal of this project is to develop indigenous state-of-the-art code suites for nuclear activation analysis

  2. Regional projections of nuclear and fossil electric power generation costs

    International Nuclear Information System (INIS)

    Smolen, G.R.; Delene, J.G.; Fuller, L.C.; Bowers, H.I.

    1983-12-01

    The total busbar electric generating costs were estimated for locations in ten regions of the United States for base load nuclear and coal-fired power plants with a startup date of January 1995. A complete data set is supplied which specifies each parameter used to obtain the comparative results. When the comparison is based on reference cost parameters, nuclear- and coal-fired generation costs are found to be very close in most regions of the country. Nuclear power is favored in the South Atlantic region where coal must be transported over long distances, while coal-fired generation is favored in the Central and North Central regions where large reserves of cheaply mineable coal exist. The reference data set reflects recent electric utility construction experience. Significantly lower nuclear capital investment costs would result if regulatory reform and improved construction practices were instituted. The electric power generation costs for base load oil- and natural gas-fired plants were also estimated. These plants were found to be noncompetitive in all regions for those scenarios most likely to develop. Generation cost sensitivity to changes in various parameters was examined at a reference location. The sensitivity parameters included capital investment costs, lead times, capacity factors, costs of money, and coal and uranium prices. In addition to the levelized lifetime costs, year-by-year cash flows and revenue requirements are presented. The report concludes with an analysis of the economic merits of recycling spent fuel in light-water reactors

  3. Study on the maturity model of nuclear power project management in China

    International Nuclear Information System (INIS)

    Chen Changbing; Li Huiqiang; Zheng Yanguo

    2009-01-01

    Based on the general project management maturity model, this paper discussed the establishment of nuclear power engineering project management maturity model in China, and proposed a basic framework in order to provide a way for improving and evaluating the ability of nuclear power project management in China. (authors)

  4. Methodology for cost estimate in projects for nuclear power plants decommissioning

    International Nuclear Information System (INIS)

    Salij, L.M.

    2008-01-01

    The conceptual approaches to cost estimating of nuclear power plants units decommissioning projects were determined. The international experience and national legislative and regulatory basis were analyzed. The possible decommissioning project cost classification was given. It was shown the role of project costs of nuclear power plant units decommissioning as the most important criterion for the main project decisions. The technical and economic estimation of deductions to common-branch fund of decommissioning projects financing was substantiated

  5. Colorado School of Mines low energy nuclear physics project

    International Nuclear Information System (INIS)

    Cecil, F.E.

    1991-01-01

    A major accomplishment of this project in the past year is the completion of a fairly comprehensive paper describing the survey of radiative capture reactions of protons on light nuclei at low energies. In addition we have completed a preliminary set of measurements of (d,p)/(d,α) cross section ratios on the charge symmetric nuclei 6 Li and 10 B as a test of the Oppenheimer-Phillips effect. While the 6 Li data remain inconclusive, the 10 B data show solid evidence for the Oppenheimer-Phillips enhancement of the (d,p) reaction relative to the (d,α) reaction for deuteron bombarding energies below about 100 keV. We have continued our investigation of fusion reaction products from deuterium-metal systems at room temperatures with the startling observation of intense burst of energetic charged particles from deuterium gas loaded thin titaium foils subject to non-equilibrium thermal and electrical conditions. We have completed two projects involving the application of the low energy particle accelerator to material science problems; firstly a study of the transformation of crystalline to amorphous Fe-Zr systems by proton irradiation and secondly the effects of ion bombardment on the critical temperature of YBCO high-temperature superconductors. Finally we have made progress in several instrumentation projects which will be used in some of the up-coming measurements of nuclear cross sections at very low energies

  6. Radiological and environmental consequences. Final report of the Nordic Nuclear Safety Research project BOK-2

    International Nuclear Information System (INIS)

    Palsson, S.E.

    2002-11-01

    Final report of the Nordic Nuclear Safety Research project BOK-2, Radiological and Environmental Consequences. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. This report focuses on the project itself and gives a general summary of the studies undertaken. A separate technical report summarises the work done by each research group and gives references to papers published in scientific journals. The topics in BOK-2 included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. (au)

  7. Development and application of project management computer system in nuclear power station

    International Nuclear Information System (INIS)

    Chen Junpu

    2000-01-01

    According to the experiences in the construction of Daya Bay and Lingao nuclear power plants presents, the necessity to use the computers for management and their application in the nuclear power engineering project are explained

  8. A project-based system for including farmers in the EU ETS

    DEFF Research Database (Denmark)

    Brandt, Urs Steiner; Svendsen, Gert Tinggaard

    2011-01-01

    as ‘the missing link’ in past climate negotiations. We argue that farmers have relatively low marginal reduction costs and that consequences in terms of the effect on permit price and technology are overall positive in the EU Emission Trading System (ETS). Thus, we propose a project-based system...

  9. Progress and status of the international project on innovative nuclear reactors and fuel cycles (INPRO) - 5182

    International Nuclear Information System (INIS)

    Ponomarev, A.; Fesenko, G.; Grigoriev, F.G.; Korinny, A.; Phillips, J.R.; Rho, K.

    2015-01-01

    The IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000 through IAEA General Conference resolution. INPRO cooperates with Member States to ensure that sustainable nuclear energy is available to help meet the energy needs of the 21. century. INPRO membership has grown to 41 members and 16 observers. The paper presents the current prospectus of the INPRO programme and details the most recent achievements in the following 7 projects: 1) the GAINS project (Global Architecture of Innovative Nuclear Energy Systems with thermal and fast reactors and a closed nuclear fuel cycle); 2) the SYNERGIES project applies and amends the analytical framework developed in GAINS project to examine more specifically the various forms of regional collaboration among nuclear energy suppliers and users; 3) the KIND project (Key Indicators for Innovative Nuclear Energy Systems) has the objective of developing guidance on the evaluation on innovative nuclear technologies; 4) the ROADMAPS project addresses several possible stages toward nuclear energy sustainability; 5) the RISC project aims at demonstrating that the evolution of safety requirements and technical innovations provide continual progress towards the avoidance of evacuation measures outside NPP sites in case of severe accidents; 6) the FANES project has the objective of carrying out feasibility analyses of advanced and innovative fuels for different reactor systems; and 7) the WIRAF project aims at identifying problematic waste from innovative reactor designs and corresponding nuclear fuel cycles

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

    Energy Technology Data Exchange (ETDEWEB)

    McGrath, M.A.; Volkov, B.

    2011-07-01

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

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

    International Nuclear Information System (INIS)

    McGrath, M.A.; Volkov, B.

    2011-01-01

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

  12. CMIP5-based global wave climate projections including the entire Arctic Ocean

    Science.gov (United States)

    Casas-Prat, M.; Wang, X. L.; Swart, N.

    2018-03-01

    This study presents simulations of the global ocean wave climate corresponding to the surface winds and sea ice concentrations as simulated by five CMIP5 (Coupled Model Intercomparison Project Phase 5) climate models for the historical (1979-2005) and RCP8.5 scenario future (2081-2100) periods. To tackle the numerical complexities associated with the inclusion of the North Pole, the WAVEWATCH III (WW3) wave model was used with a customized unstructured Spherical Multi-Cell grid of ∼100 km offshore and ∼50 km along coastlines. The climate model simulated wind and sea ice data, and the corresponding WW3 simulated wave data, were evaluated against reanalysis and hindcast data. The results show that all the five sets of wave simulations projected lower waves in the North Atlantic, corresponding to decreased surface wind speeds there in the warmer climate. The selected CMIP5 models also consistently projected an increase in the surface wind speed in the Southern Hemisphere (SH) mid-high latitudes, which translates in an increase in the WW3 simulated significant wave height (Hs) there. The higher waves are accompanied with increased peak wave period and increased wave age in the East Pacific and Indian Oceans, and a significant counterclockwise rotation in the mean wave direction in the Southern Oceans. The latter is caused by more intense waves from the SH traveling equatorward and developing into swells. Future wave climate in the Arctic Ocean in summer is projected to be predominantly of mixed sea states, with the climatological mean of September maximum Hs ranging mostly 3-4 m. The new waves approaching Arctic coasts will be less fetch-limited as ice retreats since a predominantly southwards mean wave direction is projected in the surrounding seas.

  13. Projects of SR sources including research and development for insertion devices in the USSR

    International Nuclear Information System (INIS)

    Kulipanov, G.

    1990-01-01

    Some technical information on the electron and positron storage rings - SR sources that are being constructed, used or developed at the Novosibirsk Institute of Nuclear Physics (INP), is given. The parameters and construction of wigglers and undulators (electromagnetic, superconducting, and based on permanent magnets) that are intended to be used at such storage rings are described. Various schemes of installation of wigglers, undulators and FEL at storage rings is considered. The ways of minimizing the influence of their magnetic fields on particle motion in storage rings are treated. (author)

  14. A desk evaluation review of project VIE/4/009 design and production of nuclear instruments. Project desk evaluation

    International Nuclear Information System (INIS)

    1994-01-01

    A Project Desk Evaluation (PDE) is an intensive review process, using agreed guidelines, of the design, implementation, and the output of a project. This project is exclusively dealing with the design and production of nuclear instruments. The aim of this project would be to develop a viable capability for maintenance and repair of the nuclear instruments at the Dalat Research Institute (DNRI), the premier nuclear centre in Viet Nam, and also to meet the steadily increasing needs of DNRI, as well as of other national institutions, hospitals and universities engaged in the application of nuclear technologies, particularly in the southern part of the country. Project Summary with financial data is given along with training programme. 1 tab

  15. A desk evaluation review of project VIE/4/009 design and production of nuclear instruments. Project desk evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-09

    A Project Desk Evaluation (PDE) is an intensive review process, using agreed guidelines, of the design, implementation, and the output of a project. This project is exclusively dealing with the design and production of nuclear instruments. The aim of this project would be to develop a viable capability for maintenance and repair of the nuclear instruments at the Dalat Research Institute (DNRI), the premier nuclear centre in Viet Nam, and also to meet the steadily increasing needs of DNRI, as well as of other national institutions, hospitals and universities engaged in the application of nuclear technologies, particularly in the southern part of the country. Project Summary with financial data is given along with training programme. 1 tab.

  16. Arenas for risk governance in nuclear waste management - The European Union ARGONA Project

    Energy Technology Data Exchange (ETDEWEB)

    Jonsson, Josefin P.; Wetzel, Carina (Swedish Radiation Safety Authority, SE-171 16 Stockholm (Sweden)); Andersson, Kjell; Lidberg, Maria (Karita Research AB, Box 6048, SE-187 06 Taeby (Sweden))

    2009-12-15

    There is a large knowledge base about governance issues but how to implement the new processes of transparency and participation is not self-evident. In other words there is a common demand for bridging the gap between research and implementation for the governance of nuclear waste management. There are legal, organizational, historical and cultural factors that set conditions which have to be understood for effective implementation. We must also understand how deliberative methods and the transparency approach relate to each other, and to formal decision-making in representative democracy. Therefore, the ARGONA project intends to demonstrate how participation and transparency link to the political and legal systems and how new approaches can be implemented in nuclear waste management programmes. For this purpose, the project includes: Studies of the context within which processes of participation and transparency take place, in order to understand how the processes can be used in the waste management programs. Studies of theory - in order to build participation and transparency on a firm ground; Case studies - to understand how different processes work; Implementation - to make a difference, learn and demonstrate. The project now approaches its finalization and it is foreseen that the reporting, in addition to 25 deliverables to the European Commission, will include a full final report, a summary final report and recommendations with proposed guidelines that can be considered by national actors of nuclear waste programmes as well as the European Commission

  17. Arenas for risk governance in nuclear waste management - The European Union ARGONA Project

    International Nuclear Information System (INIS)

    Jonsson, Josefin P.; Wetzel, Carina; Andersson, Kjell; Lidberg, Maria

    2009-12-01

    There is a large knowledge base about governance issues but how to implement the new processes of transparency and participation is not self-evident. In other words there is a common demand for bridging the gap between research and implementation for the governance of nuclear waste management. There are legal, organizational, historical and cultural factors that set conditions which have to be understood for effective implementation. We must also understand how deliberative methods and the transparency approach relate to each other, and to formal decision-making in representative democracy. Therefore, the ARGONA project intends to demonstrate how participation and transparency link to the political and legal systems and how new approaches can be implemented in nuclear waste management programmes. For this purpose, the project includes: Studies of the context within which processes of participation and transparency take place, in order to understand how the processes can be used in the waste management programs. Studies of theory - in order to build participation and transparency on a firm ground; Case studies - to understand how different processes work; Implementation - to make a difference, learn and demonstrate. The project now approaches its finalization and it is foreseen that the reporting, in addition to 25 deliverables to the European Commission, will include a full final report, a summary final report and recommendations with proposed guidelines that can be considered by national actors of nuclear waste programmes as well as the European Commission

  18. The Ongkharak Nuclear Research Center (ONRC) research reactor project: a status review

    International Nuclear Information System (INIS)

    Rusch, R.; Jacobi, A. Jr.; Yamkate, P.

    2001-01-01

    The new Ongkharak Nuclear Research Center in the vicinity of Bangkok, Thailand is planned to replace the more than 30 years old facilities located in the Chatuchak district, Bangkok. An international team led by general atomics (GA) is designing and constructing the new research complex. It comprises a 10 MW TRIGA type reactor, an isotope production and a centralized waste processing and storage facility. Electrowatt-Ekono Ltd. was hired by the Thai Government Agency, the Office of Atomic Energy for Peace (OAEP), as a consultant to the project. As the project is now approaching the end of its 4 th year, it now stands at a decisive turning point. Basic design is nearly completed and detailed design is well advanced. The turnkey part of the contract including the reactor island, the isotope and waste facilities are still awaiting the issuance of the Construction Permit. Significant progress has been made on the other part of the project, which includes all the supporting infrastructure facilities. The Preliminary Safety Analysis Report (PSAR), prepared by GA, has been reviewed by various parties, including by nuclear safety experts from the IAEA, which has provided continuous support to the OAEP. Experts from the Argonne National Laboratory have been involved in the reviews as well. The PSAR is now under consideration at the Nuclear Facility Safety Sub-Committee (NFSS) of the Thai Atomic Energy for Peace Commission for issuing the Construction Permit of the ONRC Research Reactor. The following paper gives an overview of the project and its present status, outlining the features of the planned facilities and the issues the project is presently struggling with. Major lessons of the past 4 years are highlighted and an outlook into the future is attempted. (orig.)

  19. Spent Nuclear Fuel Project Cold Vacuum Drying Facility Operations Manual

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, (Cold Vacuum Drying Facility Design Requirements), Rev. 4. and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  20. Nuclear safety research project (PSF). 1999 annual report

    International Nuclear Information System (INIS)

    Muehl, B.

    2000-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report summarizes the R and D results of PSF during 1999. The research tasks cover three main topics: Light Water Reactor safety, innovative systems, and studies related to the transmutation of actinides. The importance of the Light Water Reactor safety, however, has decreased during the last year in favour of the transmutation of actinides. Numerous institutes of the research centre contribute to the PSF programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2000. (orig.) [de

  1. 3DEXPERIENCE: a digital platform to optimize nuclear projects

    International Nuclear Information System (INIS)

    Grand, T.; Le Ngoc

    2016-01-01

    Dassault Systemes has developed a digital platform 3DEXPERIENCE that enables all the enterprises working on a project to use common software and built databases in a collaborative environment. Now It is possible to simulate all the construction steps of a reactor and 3DEXPERIENCE is already used in the Chinese and Russian nuclear industries. For instance 3DEXPERIENCE allows the testing of different construction scenarios in order to find the best one to cope with the delay of a supplier for a component. The Russian feedback experience shows an average 15% gain in engineering man-hours for the construction of a reactor and up to 25% for its commissioning. The use of 3DEXPERIENCE for the dismantling of ancient facilities is more difficult since in most cases it does not exist a digital description of the facility. (A.C.)

  2. Public Acceptance Activities Concerning Nuclear Fuel Cycle Project in Amour Prefecture

    International Nuclear Information System (INIS)

    Akizuki, Harumi; Manager, Deputy

    1993-01-01

    Following the Chernobyl accident, a campaign against the use of nuclear power was staged throughout the prefecture. However, after a series of elections, including the Amour Prefecture elections held in February 1991, opposition against the use of nuclear power has gradually diminished. According to an opinion poll conducted by a local paper prior to the Upper House elections of July last year, over 60% of Amour residents approved of the construction of the nuclear fuel cycle facility. In July last year, the project management organization was incorporated and the head office moved to Amour Prefecture. Prompted by this, the company, intends to show Amour residents that it is committed to living in harmony with the prefecture

  3. International Remote Monitoring Project Embalse Nuclear Power Station, Argentina Embalse Remote Monitoring System

    International Nuclear Information System (INIS)

    Schneider, Sigfried L.; Glidewell, Donnie D.; Bonino, Anibal; Bosler, Gene; Mercer, David; Maxey, Curt; Vones, Jaromir; Martelle, Guy; Busse, James; Kadner, Steve; White, Mike; Rovere, Luis

    1999-01-01

    The Autoridad Regulatoria Nuclear of Argentina (ARN), the International Atomic Energy Agency (IAEA), ABACC, the US Department of Energy, and the US Support Program POTAS, cooperated in the development of a Remote Monitoring System for nuclear nonproliferation efforts. This system was installed at the Embalse Nuclear Power Station last year to evaluate the feasibility of using radiation sensors in monitoring the transfer of spent fuel from the spent fuel pond to dry storage. The key element in this process is to maintain continuity of knowledge throughout the entire transfer process. This project evaluated the fundamental design and implementation of the Remote Monitoring System in its application to regional and international safeguard efficiency. New technology has been developed to enhance the design of the system to include storage capability on board sensor platforms. This evaluation has led to design enhancements that will assure that no data loss will occur during loss of RF transmission of the sensors

  4. Finance structure and public enlightenment program of the first Turkish nuclear power plant project (a case study)

    International Nuclear Information System (INIS)

    Lutfi Sarici, E.

    2000-01-01

    This paper deals with four closely related subjects. These are: the positioning of nuclear energy in Turkey's energy planning by presenting supply and demand figures of electricity, giving emphasis to resource availability, pointing out the necessity of diversification of resources; the ongoing situation for realization of the Akkuyu Project with its updated milestones, alternative offers requested for the Akkuyu Nuclear Power Plant and member companies of the consortiums who already have submitted the three bids; the financing of big-scale energy investment projects in developing countries by giving special emphasis to the Akkuyu Nuclear Power Plant Project including the financing requirements in the Bid Specifications, OECD rules for financing, the requirements of financial agents, and financing means of domestic participation; public enlightenment during establishment of nuclear power in Turkey. (author)

  5. New nuclear projects in the world. Sustainable Nuclear Energy; Nuevos proyectos nucleares en el mundo. energia nuclear sostenible

    Energy Technology Data Exchange (ETDEWEB)

    Leon, P. T.

    2011-07-01

    Nuclear power has experienced a major boom in the last few years, primarily because it is a non-CO{sub 2} emitting energy source, it can be produced at competitive costs and it can boost a country's security of supply. there are still two issues to be addressed in relation to the currently used technologies: the degree to which the energy content of nuclear fuel is used, and wastes. A solution to both these aspects would ut nuclear power in the category of sustainable energy. The article provides details on current nuclear plans in the wold, the impact of the Fukushima accident on different countries nuclear plans and the European initiatives for sustainable nuclear energy development. (Author)

  6. Application of ABWR construction database to nuclear power plant project

    International Nuclear Information System (INIS)

    Takashima, Atsushi; Katsube, Yasuhiko

    1999-01-01

    Tokyo Electric Power Company (TEPCO) completed the construction of Kashiwazaki-Kariwa Nuclear Power Station Unit No. 6 and No. 7 (K-6/7) as the first advanced boiling water reactors (ABWR) in the world successfully. K-6 and K-7 started their commercial operations in November, 1996 and in July, 1997 respectively. We consider ABWR as a standard BWR in the world as well as in Japan because ABWR is highly reputed. However, because the interval of our nuclear power plant construction is going to be longer, our engineering level on plant construction will be declining. Hence it is necessary for us to maintain our engineering level. In addition to this circumstance, we are planning to wide application of separated purchase orders for further cost reduction. Also there is an expectation for our contribution to ABWR plant constructions overseas. As facing these circumstances, we have developed a construction database based on our experience for ABWR construction. As the first step of developing the database for these use, we analyzed our own activities in the previous ABWR construction. Through this analysis, we could define activity units of which the project consists. As the second step, we clarified the data which are treated in each activity unit and the interface among them. By taking these steps, we could develop our database efficiently. (author)

  7. Thermal hydraulic feasibility assessment for the Spent Nuclear Fuel Project

    International Nuclear Information System (INIS)

    Heard, F.J.; Cramer, E.R.; Beaver, T.R.; Thurgood, M.J.

    1996-01-01

    A series of scoping analyses have been completed investigating the thermal-hydraulic performance and feasibility of the Spent Nuclear Fuel Project (SNFP) Integrated Process Strategy (IPS). The SNFP was established to develop engineered solutions for the expedited removal, stabilization, and storage of spent nuclear fuel from the K Basins at the U.S. Department of Energy's Hanford Site in Richland, Washington. The subject efforts focused on independently investigating, quantifying, and establishing the governing heat production and removal mechanisms for each of the IPS operations and configurations, obtaining preliminary results for comparison with and verification of other analyses, and providing technology-based recommendations for consideration and incorporation into the design bases for the SNFP. The goal was to develop a series fo thermal-hydraulic models that could respond to all process and safety-related issues that may arise pertaining to the SNFP. A series of sensitivity analyses were also performed to help identify those parameters that have the greatest impact on energy transfer and hence, temperature control. It is anticipated that the subject thermal-hydraulic models will form the basis for a series of advanced and more detailed models that will more accurately reflect the thermal performance of the IPS and alleviate the necessity for some of the more conservative assumptions and oversimplifications, as well as form the basis for the final process and safety analyses

  8. A project in support of nuclear technology cooperation

    International Nuclear Information System (INIS)

    Jung, Ki Jung; Choi, Pyong Hoon; Lee, Ji Ho

    2003-12-01

    Establish strategies of international cooperation in an effort to promote our nation's leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate. Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. Based on the construction of INIS database sent by memeber states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB and INIS online database, INIS SDI service, non-conventional literature delivery services and announce INIS to users. Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing

  9. Current status and prospects on Rokkasho nuclear fuel cycle project

    International Nuclear Information System (INIS)

    Suzuki, Mitsuo

    2003-01-01

    JNFL has been established aiming at fulfillment of Nuclear Fuel Cycle, as well as to contribute to the long-term and stable supply of nuclear power in Japan. 'Uranium Enrichment Plant' with its production of 1,050 SWU/y and planned to be expand to 1,500 SWU/y, 'Low Level Radioactive Waste Disposal Center' with 150,000/200 l drums stored, out of its 400,000 drums capacity, and 'Vitrified Waste Storage Center' with 760 canisters stored, out of its 1440 canisters capacity, are already in its operation. It is now preparing for the operation of '800 t/y Reprocessing Plant' and construction of '130t HM/y MOX Fuel Fabrication Plant'. As for the Reprocessing Plant, 780t of spent fuels has been already received and stored in the storage pools. Main plant is now in the course of test operation and planned to start the commercial operation by July 2006. Due to some defects found during the course of its construction, JNFL is now reviewing the Total Quality Assurance Structure to improve and reinforce its system. And for the MOX Fuel Fabrication Plant, activities towards obtaining the local autonomy's agreement for the construction are being made energetically. It is essential to obtain the good understanding of the public community to promote these projects successfully; JNFL is putting its best efforts to dispatch all the necessary information to the public in a timely manner. (author)

  10. Spent nuclear fuel project high-level information management plan

    Energy Technology Data Exchange (ETDEWEB)

    Main, G.C.

    1996-09-13

    This document presents the results of the Spent Nuclear Fuel Project (SNFP) Information Management Planning Project (IMPP), a short-term project that identified information management (IM) issues and opportunities within the SNFP and outlined a high-level plan to address them. This high-level plan for the SNMFP IM focuses on specific examples from within the SNFP. The plan`s recommendations can be characterized in several ways. Some recommendations address specific challenges that the SNFP faces. Others form the basis for making smooth transitions in several important IM areas. Still others identify areas where further study and planning are indicated. The team`s knowledge of developments in the IM industry and at the Hanford Site were crucial in deciding where to recommend that the SNFP act and where they should wait for Site plans to be made. Because of the fast pace of the SNFP and demands on SNFP staff, input and interaction were primarily between the IMPP team and members of the SNFP Information Management Steering Committee (IMSC). Key input to the IMPP came from a workshop where IMSC members and their delegates developed a set of draft IM principles. These principles, described in Section 2, became the foundation for the recommendations found in the transition plan outlined in Section 5. Availability of SNFP staff was limited, so project documents were used as a basis for much of the work. The team, realizing that the status of the project and the environment are continually changing, tried to keep abreast of major developments since those documents were generated. To the extent possible, the information contained in this document is current as of the end of fiscal year (FY) 1995. Programs and organizations on the Hanford Site as a whole are trying to maximize their return on IM investments. They are coordinating IM activities and trying to leverage existing capabilities. However, the SNFP cannot just rely on Sitewide activities to meet its IM requirements

  11. Uranium from German nuclear power projects of the 1940s - a nuclear forensic investigation

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, Klaus; Wallenius, Maria; Luetzenkirchen, Klaus; Horta, Joan; Nicholl, Adrian; Rasmussen, Gert; Belle, Pieter van; Varga, Zsolt [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Karlsruhe (Germany); Buda, Razvan; Erdmann, Nicole [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Karlsruhe (Germany); Institut fuer Kernchemie, Universitaet Mainz (Germany); Kratz, Jens-Volker; Trautmann, Norbert [Institut fuer Kernchemie, Universitaet Mainz (Germany); Fifield, L. Keith; Tims, Stephen G. [Department of Nuclear Physics, Research School of Physics and Engineering, The Australian National University, Canberra, ACT (Australia); Froehlich, Michaela B. [Department of Nuclear Physics, Research School of Physics and Engineering, The Australian National University, Canberra, ACT (Australia); Universitaet Wien, Fakultaet fuer Chemie, Institut fuer Anorganische Chemie, Vienna (Austria); Steier, Peter [Universitaet Wien, Fakultaet fuer Physik, Isotopenforschung und Kernphysik, Vienna (Austria)

    2015-11-02

    Here we present a nuclear forensic study of uranium from German nuclear projects which used different geometries of metallic uranium fuel. Through measurement of the {sup 230}Th/{sup 234}U ratio, we could determine that the material had been produced in the period from 1940 to 1943. To determine the geographical origin of the uranium, the rare-earth-element content and the {sup 87}Sr/{sup 86}Sr ratio were measured. The results provide evidence that the uranium was mined in the Czech Republic. Trace amounts of {sup 236}U and {sup 239}Pu were detected at the level of their natural abundance, which indicates that the uranium fuel was not exposed to any major neutron fluence. (copyright 2015 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  12. Uranium from German nuclear power projects of the 1940s - a nuclear forensic investigation

    International Nuclear Information System (INIS)

    Mayer, Klaus; Wallenius, Maria; Luetzenkirchen, Klaus; Horta, Joan; Nicholl, Adrian; Rasmussen, Gert; Belle, Pieter van; Varga, Zsolt; Buda, Razvan; Erdmann, Nicole; Kratz, Jens-Volker; Trautmann, Norbert; Fifield, L. Keith; Tims, Stephen G.; Froehlich, Michaela B.; Steier, Peter

    2015-01-01

    Here we present a nuclear forensic study of uranium from German nuclear projects which used different geometries of metallic uranium fuel. Through measurement of the 230 Th/ 234 U ratio, we could determine that the material had been produced in the period from 1940 to 1943. To determine the geographical origin of the uranium, the rare-earth-element content and the 87 Sr/ 86 Sr ratio were measured. The results provide evidence that the uranium was mined in the Czech Republic. Trace amounts of 236 U and 239 Pu were detected at the level of their natural abundance, which indicates that the uranium fuel was not exposed to any major neutron fluence. (copyright 2015 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  13. Seismic response of nuclear reactors in layered liquefiable soil deposits including nonlinear soil-structure interaction

    International Nuclear Information System (INIS)

    Zaman, M.; Mamoon, S.M.

    1989-01-01

    Analysis of seismic response of structures located at a site with potential for soil liquefaction has drawn attention of many researchers. The topic is particularly important in the design of critical facilities like nuclear reactors and defense installations. This paper presents the results of a study involving evaluation of coupled seismic response of structures (model nuclear reactors) and characteristics of soil liquefaction at a site. The analysis procedure employed is based on the nonlinear finite element (FE) technique and accounts for the interaction effects due to a neighboring structure. Emphasis is given to the following features: prediction of spatial and temporal variation of pore water pressure; identification of the on-set of liquefaction based on the effective stress approach, and tracing the propagation of the liquefied zones with time and resulting response of the structures

  14. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    International Nuclear Information System (INIS)

    Michael Kruzic

    2007-01-01

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D and D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release

  15. Supernova equations of state including full nuclear ensemble with in-medium effects

    Science.gov (United States)

    Furusawa, Shun; Sumiyoshi, Kohsuke; Yamada, Shoichi; Suzuki, Hideyuki

    2017-01-01

    We construct new equations of state for baryons at sub-nuclear densities for the use in core-collapse supernova simulations. The abundance of various nuclei is obtained together with thermodynamic quantities. The formulation is an extension of the previous model, in which we adopted the relativistic mean field theory with the TM1 parameter set for nucleons, the quantum approach for d, t, h and α as well as the liquid drop model for the other nuclei under the nuclear statistical equilibrium. We reformulate the model of the light nuclei other than d, t, h and α based on the quasi-particle description. Furthermore, we modify the model so that the temperature dependences of surface and shell energies of heavy nuclei could be taken into account. The pasta phases for heavy nuclei and the Pauli- and self-energy shifts for d, t, h and α are taken into account in the same way as in the previous model. We find that nuclear composition is considerably affected by the modifications in this work, whereas thermodynamical quantities are not changed much. In particular, the washout of shell effect has a great impact on the mass distribution above T ∼ 1 MeV. This improvement may have an important effect on the rates of electron captures and coherent neutrino scatterings on nuclei in supernova cores.

  16. Safety in nuclear power plant operation, including commissioning and decommissioning. A code of practice

    International Nuclear Information System (INIS)

    1978-01-01

    Safe operation of a nuclear power plant postulates satisfactory siting, design, construction and commissioning, together with proper management and operation of the plant. This Code of Practice deals with the safety aspects of management, commissioning, operation and decommissioning of the plant. It forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to land-based stationary thermal neutron power plants. It has been prepared for the use of those responsible for the operation of stationary nuclear power plants, the main function of which is the generation of electrical and/or thermal power, and for the use of those responsible for regulating the operation of such plants. It is not intended for application to reactors used solely for experimental or research purposes. The provisions in the Code are designed to provide assurance that operational activities are carried out without undue radiological hazard to the general public and to persons on the site. It should be understood that the provisions in the Code set forth minimum requirements which shall be met in order to achieve safe operation of a nuclear power plant

  17. The new Wallula CO2 project may revive the old Columbia River Basalt (western USA) nuclear-waste repository project

    Science.gov (United States)

    Schwartz, Michael O.

    2018-02-01

    A novel CO2 sequestration project at Wallula, Washington, USA, makes ample use of the geoscientific data collection of the old nuclear waste repository project at the Hanford Site nearby. Both projects target the Columbia River Basalt (CRB). The new publicity for the old project comes at a time when the approach to high-level nuclear waste disposal has undergone fundamental changes. The emphasis now is on a technical barrier that is chemically compatible with the host rock. In the ideal case, the waste container is in thermodynamic equilibrium with the host-rock groundwater regime. The CRB groundwater has what it takes to represent the ideal case.

  18. Supporting innovation. International Project on Innovative Nuclear Reactors and Fuel Cycles moves into first phase

    International Nuclear Information System (INIS)

    Gowin, Peter J.; Kupitz, Juergen

    2001-01-01

    Work has been initiated through the IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), including technical meetings and workshops scheduled over the coming months. Among activities is an information 'side event' on INPRO at the IAEA General Conference in September 2001. Among topics addressed at the Steering Committee Meeting earlier this year are user requirements and nuclear development criteria in the area of safety; safety issues related to waste management technologies of innovative nuclear reactors and fuel cycles; methodology of assessment and comparison of innovative nuclear technology with respect to INPRO; user requirements on environmental impacts of innovative reactors, fuel cycles, and waste management; and user requirements and nuclear energy development criteria in the area of non-proliferation and proliferation resistance. In December 2001, the second meeting of the INPRO Steering Committee is scheduled. At the inaugural meeting earlier this year, the Steering Committee stressed the unique role of INPRO relative to other national and international initiatives on innovative nuclear power technologies. The role lies in identifying the needs and requirements of a spectrum of developing and developed countries; and contributing explicitly to the debate on the global acceptability of nuclear power. As of August 2001, the following countries or entities have become members of INPRO: Argentina, Canada, China, France, Germany, India, Netherlands, Russian Federation, Spain, Turkey, and the European Commission. In total, 14 experts have been nominated by their respective governments or international organizations. All IAEA Member States are also free to participate in the Steering Committee as observers. The Terms of Reference define INPRO's rationale and purpose, in the context of energy needs and developments. They state that the 'long-term outlook for nuclear energy should be considered in the broader perspective of future

  19. The Heysham 2 and Torness nuclear power station projects

    International Nuclear Information System (INIS)

    Cameron, P.J.

    1989-01-01

    At the beginning of the design of the Heysham 2 and Torness Nuclear Power Stations in the UK, it was agreed that the Hinkley Point B/Hunterston B Advanced Gas Cooled reactor design would be repeated. However, the Hinkley Point B/Hunterston B designs dated from 1964, and inevitably safety requirements had escalated in the intervening years. Furthermore, operating experience gained from Hinkley Point B/Hunterston B showed that it was desirable to make changes to particular features. Design changes were therefore included where it was considered essential to improve performance, to improve safety and to improve engineering. The resulting station designs are described. (author)

  20. The TACIS Nuclear Programme: Assistance in Upgrading Russian Nuclear Power Stations - An Overview of the Individual Projects in the Internet

    International Nuclear Information System (INIS)

    Bieth, Michel; Schoels, Hubert

    2006-01-01

    The European Union' TACIS1 programme has been established for the New Independent States (NIS), among them in the Russian Federation since 1991. One priority of TACIS funding is Nuclear Safety. The European Commission has made available a total of 944 Million Euros for nuclear safety programmes covering the period 1991-2003. The TACIS nuclear safety programme is devoted to the improvement of the safety of Soviet designed nuclear installations in providing technology and safety culture transfer. JRC is carrying out works in the following areas: On-Site Assistance for TACIS operating Nuclear Power Plants; Design Safety and Dissemination of TACIS results; Reactor Pressure Vessel Embrittlement for VVER; Regulatory Assistance; Industrial Waste Management; Nuclear Safeguards; All TACIS projects, dealing with these areas of activity are now available in so called Project Description Sheets (PDS) or Project Results Sheets (PRS) in the Internet for everybody. JRC has created in the Internet an easy to open and to browse database which contains the result of works in relation to the above mentioned nuclear activities. This presentation gives an on-line overview of the app. 430 projects which have been implemented so far since the outset of the TACIS Nuclear Programme in the Russian Federation, which is representative to the other CIS countries, benefiting from the TACIS. The presentation will mainly consist of an on-line-demonstration of the TACIS Nuclear WEB Page, created by JRC. (authors)

  1. The appliction of project management in operations preparation of nuclear power station

    International Nuclear Information System (INIS)

    Tang Zhengrong; Zhang Zhixiong

    2001-01-01

    Concept, history, characteristics of the project management is introduced. Analysis is performed on the suitability of application of project management approach in nuclear power station operations preparation. Then the application of project management is detailed in order to present the readers our study and practice. Theory and practice indicate that the project management is a useful management tool for operations preparation of nuclear power station to achieve a good performance

  2. The application of project management in operations preparation of nuclear power station

    International Nuclear Information System (INIS)

    Zhang Zhixiong; Tang Zhengrong

    2000-01-01

    The author first presents a brief introduction of the concept, history, characteristics of project management. Analysis is performed on the suitability of application of project management approach in nuclear power station operations preparation. Then the application of project management is detailed in order to present the readers authors' study and practice. Theory and practice indicate that the project management is a useful management tool for operations preparation of nuclear power station to achieve a good performance

  3. The surgical care improvement project and prevention of post-operative infection, including surgical site infection.

    Science.gov (United States)

    Rosenberger, Laura H; Politano, Amani D; Sawyer, Robert G

    2011-06-01

    In response to inconsistent compliance with infection prevention measures, the Centers for Medicare & Medicaid Services collaborated with the U.S. Centers for Disease Control and Prevention on the Surgical Infection Prevention (SIP) project, introduced in 2002. Quality improvement measures were developed to standardize processes to increase compliance. In 2006, the Surgical Care Improvement Project (SCIP) developed out of the SIP project and its process measures. These initiatives, published in the Specifications Manual for National Inpatient Quality Measures, outline process and outcome measures. This continually evolving manual is intended to provide standard quality measures to unify documentation and track standards of care. Seven of the SCIP initiatives apply to the peri-operative period: Prophylactic antibiotics should be received within 1 h prior to surgical incision (1), be selected for activity against the most probable antimicrobial contaminants (2), and be discontinued within 24 h after the surgery end-time (3); (4) euglycemia should be maintained, with well-controlled morning blood glucose concentrations on the first two post-operative days, especially in cardiac surgery patients; (6) hair at the surgical site should be removed with clippers or by depilatory methods, not with a blade; (9) urinary catheters are to be removed within the first two post-operative days; and (10) normothermia should be maintained peri-operatively. There is strong evidence that implementation of protocols that standardize practices reduce the risk of surgical infection. The SCIP initiative targets complications that account for a significant portion of preventable morbidity as well as cost. One of the goals of the SCIP guidelines was a 25% reduction in the incidence of surgical site infections from implementation through 2010. Process measures are becoming routine, and as we practice more evidence-based medicine, it falls to us, the surgeons and scientists, to be active

  4. Manpower development for nuclear power programme. China. Project findings and recommendations

    International Nuclear Information System (INIS)

    Csik, B.J.

    1992-01-01

    The United Nations Development Program (UNDP) project was conceived in April 1985, implementation was started on preliminary authorization by summer 1986, and it was approved and signed in early 1987. The duration was originally planned for three years with a UNDP input of US$ 1,657.500 (including Government cost sharing of US$ 280,000). The project is now essentially completed with a few items still pending, though committed as firmly planned, and the current cost estimate is US$ 1,707.617. The objective of the project was to assist in establishing long-term training programmes in two training centres in the People's Republic of China (Qinshan and Suzhou) and strengthen the training capabilities at these centres. The two centres are intended to provide specialized comprehensive training in basic and applied nuclear power engineering disciplines as well as in construction, operation and maintenance of nuclear power plants to technical personnel assigned to the nuclear power plants in the People's Republic of China

  5. Fatigue evaluation including environmental effects for primary circuit components in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seichter, Johannes [Siempelkamp Pruef- und Gutachter-Gesellschaft mbH, Dresden (Germany); Reese, Sven H.; Klucke, Dietmar [E.ON Kernkraft GmbH, Hannover (Germany). Component Technology

    2013-06-01

    The influence of LWR coolant environment to the lifetime of materials in nuclear power plants is being discussed internationally. Environmental phenomena had been investigated in laboratory tests and published in recent years. The discussion is mainly focused both on the transition from laboratory to real plant components and on numerical calculation procedures. Since publishing of the NUREG/CR-6909 report in 2007, formulae for calculating the Fen factors have been modified several times. Various calculation procedures are discussed and recommendations are made how to avoid extremely conservative results. (orig.)

  6. 42 CFR 137.275 - May Self-Governance Tribes include IHS construction programs in a construction project agreement...

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false May Self-Governance Tribes include IHS construction... OF HEALTH AND HUMAN SERVICES TRIBAL SELF-GOVERNANCE Construction Purpose and Scope § 137.275 May Self-Governance Tribes include IHS construction programs in a construction project agreement or in a funding...

  7. Effects of embedment including slip and separation on seismic SSI response of a nuclear reactor building

    International Nuclear Information System (INIS)

    Saxena, Navjeev; Paul, D.K.

    2012-01-01

    Highlights: ► Both the slip and separation of reactor base reduce with increase in embedment. ► The slip and separation become insignificant beyond 1/4 and 1/2 embedment respectively. ► The stresses in reactor reduce significantly upto 1/4 embedment. ► The stress reduction with embedment is more pronounced in case of tensile stresses. ► The modeling of interface is important beyond 1/8 embedment as stresses are underestimated otherwise. - Abstract: The seismic response of nuclear reactor containment building considering the effects of embedment, slip and separation at soil–structure interface requires modeling of the soil, structure and interface altogether. Slip and separation at the interface causes stress redistribution in the soil and the structure around the interface. The embedment changes the dynamic characteristics of the soil–structure system. Consideration of these aspects allows capturing the realistic response of the structure, which has been a research gap and presented here individually as well as taken together. Finite element analysis has been carried out in time domain to attempt the highly nonlinear problem. The study draws important conclusions useful for design of nuclear reactor containment building.

  8. Brief introduction to project management of full scope simulator for Qinshan 300 MW Nuclear Power Unit

    International Nuclear Information System (INIS)

    Chen Jie

    1996-01-01

    The key points in development and engineering project management of full scope simulator for Qinshan 300 MW Nuclear Power Unit are briefly introduced. The Gantt chart, some project management methods and experience are presented. The key points analysis along with the project procedure will be useful to the similar project

  9. Two Gonostomatid Ciliates from the Soil of Lombardia, Italy; including Note on the Soil Mapping Project.

    Science.gov (United States)

    Bharti, Daizy; Kumar, Santosh; La Terza, Antonietta

    2015-01-01

    Two gonostomatid ciliates, Gonostomum paronense n. sp. and G. strenuum, isolated from the soil sample of paddy field, Lombardia, Italy, were investigated using live observation and protargol impregnation. Gonostomum paronense n. sp. is mainly characterized by a tailed body, frontoventral cirri arranged in pairs, and presence of pretransverse and transverse cirri. Morphologically and morphometrically, the new species is similar to Gonostomum namibiense in having a tailed body and frontoventral cirral pairs; however, it differs mainly in the number of frontoventral cirral pairs (seven vs. three). Phylogenetic analyses based on the SSU rDNA sequences show that the new species is more closely related to G. namibiense than to G. strenuum, supporting the morphological classification based on the cirral pattern and the tailed body. However, due to the poor nodal support and absence of gene sequence of the type species Gonostomum, a more robust phylogeny of this group still remains unresolved. The biometric data of the Italian population of Gonostomum strenuum overlap with those from other known populations. Both species were collected from the industrial area of Parona, in the framework of the "Soil Mapping, Lombardia" project in which, for the first time in Italy, soil ciliates were used as bioindicators of soil quality. © 2015 The Author(s) Journal of Eukaryotic Microbiology © 2015 International Society of Protistologists.

  10. Evaluation of nuclear facility decommissioning projects. Status report. Humboldt Bay Power Plant Unit 3, SAFSTOR decommissioning

    International Nuclear Information System (INIS)

    Baumann, B.L.; Haffner, D.R.; Miller, R.L.; Scotti, K.S.

    1986-06-01

    This document explains the purpose of the US Nuclear Regulatory Commission's (NRC) Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program and summarizes information concerning the decommissioning of the Humboldt Bay Power Plant (HBPP) Unit 3 facility. Preparations to put this facility into a custodial safe storage (SAFSTOR) mode are currently scheduled for completion by June 30, 1986. This report gives the status of activities as of June 1985. A final summary report will be issued after completion of this SAFSTOR decommissioning activity. Information included in this status report has been collected from the facility decommissioning plan, environmental report, and other sources made available by the licensee. This data has been placed in a computerized data base system which permits data manipulation and summarization. A description of the computer reports that can be generated by the decommissioning data system (DDS) for Humboldt Bay and samples of those reports are included in this document

  11. Low Energy Nuclear Reaction Aircraft- 2013 ARMD Seedling Fund Phase I Project

    Science.gov (United States)

    Wells, Douglas P.; McDonald, Robert; Campbell, Robbie; Chase, Adam; Daniel, Jason; Darling, Michael; Green, Clayton; MacGregor, Collin; Sudak, Peter; Sykes, Harrison; hide

    2014-01-01

    This report serves as the final written documentation for the Aeronautic Research Mission Directorate (ARMD) Seedling Fund's Low Energy Nuclear Reaction (LENR) Aircraft Phase I project. The findings presented include propulsion system concepts, synergistic missions, and aircraft concepts. LENR is a form of nuclear energy that potentially has over 4,000 times the energy density of chemical energy sources. It is not expected to have any harmful emissions or radiation which makes it extremely appealing. There is a lot of interest in LENR, but there are no proven theories. This report does not explore the feasibility of LENR. Instead, it assumes that a working system is available. A design space exploration shows that LENR can enable long range and high speed missions. Six propulsion concepts, six missions, and four aircraft concepts are presented. This report also includes discussion of several issues and concerns that were uncovered during the study and potential research areas to infuse LENR aircraft into NASA's aeronautics research.

  12. Current status and future direction of INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles)

    International Nuclear Information System (INIS)

    Omoto, Akira; Moriwaki, Masanao; Sugimoto, Jun; Nakai, Ryodai

    2007-01-01

    INPRO is an international forum to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles so as to ensure that nuclear energy is available to contribute to a sustainable development of the human, and IAEA becomes the secretariat for INPRO. The number of the members counts 28 by recent participation of Japan and U.S.A. now, and it is a unique forum to bring together both technology users and technology holders, that includes 5 countries which do not still have nuclear power generation. Until now it was phase I, and focused its activities to make clear the desired characteristics of nuclear energy system toward the future, and to develop methodology to evaluate various nuclear energy systems, but it shifted to phase II from July, 2006, and it planned three areas of activities such as improvement of evaluation methodology, institutional/infrastructure oriented activities and a collaborative project of technology development. Current status and future direction of INPRO was presented to encourage Japan in significant contributions of these three areas. (T. Tanaka)

  13. O projeto do submarino nuclear brasileiro The Brazilian nuclear submarine project

    Directory of Open Access Journals (Sweden)

    João Roberto Martins Filho

    2011-12-01

    Full Text Available O artigo procura reconstruir a trajetória do programa do submarino nuclear brasileiro desde suas origens, no governo Geisel, aos dias atuais. Lançando mão do conceito de oportunismo tecnológico, procura analisar a atitude dos diferentes governos federais sobre o projeto, mostrando que os governos neoliberais de Fernando Collor, Itamar Franco e Fernando Henrique Cardoso cortaram radicalmente verbas para o programa, sem, no entanto, suspendê-lo por completo. Surpreendentemente, parece haver uma continuidade entre os governos militares e o governo Lula, quanto ao apoio decidido à ideia do submarino nuclear. Quanto às relações de força na Marinha, o texto conclui que não há divergências significativas sobre a relevância do programa, o que não exclui choques de personalidades navais, em virtude do caráter autárquico assumido pelo projeto e da dificuldade de continuá-lo apenas com verbas da própria força. O artigo utilizou entrevistas recentes com atores-chaves do processo.The article aims to reconstruct the history of the Brazilian nuclear-powered submarine program, from its origins to the present. Using the concept of technological opportunism, it seeks to understand the position of the different federal administrations vis-à-vis the project, concluding that the Collor, Franco and Cardoso administrations did not support the program. However, they did not terminate the project. Surprisingly, there is a continuity between the military governments and the Lula administration, in the decisive support each gave to the program. With repect to the Navy, the analysis concludes that there were no significant disagreements, with the exception of personal conflicts originating in the autarchic features that the program had assumed and in the problem of scarcity of resources. The article is based on interviews with key actors.

  14. NPP-Nuclear Island Design. From conceptual design to Project execution

    International Nuclear Information System (INIS)

    Lanchet, Dominique

    2014-01-01

    The second day opened with the lecture of Dominique Lanchet, Design Senior Vice President at AREVA Engineering and Project. Dominique Lanchet gave us an overview of the steps of a Nuclear Island Design creation from the conceptual design to the project execution, giving the examples of the EPR and ATMEA1 TM nuclear reactors

  15. Bulk material management mode of general contractors in nuclear power project

    International Nuclear Information System (INIS)

    Zhang Jinyong; Zhao Xiaobo

    2011-01-01

    The paper introduces the characteristics of bulk material management mode in construction project, and the advantages and disadvantages of bulk material management mode of general contractors in nuclear power project. In combination with the bulk material management mode of China Nuclear Power Engineering Co., Ltd, some improvement measures have been put forward as well. (authors)

  16. Discussion on organization structure system of nuclear power projects in China

    International Nuclear Information System (INIS)

    Wang Zhi

    2011-01-01

    With the development of the nuclear power industry in China, several AE companies were born and now play a major role in building nuclear power projects in China and overseas. After studying current organization structure systems of all nuclear power AE companies in China and comparing with successful foreign ones, this paper proposes some approaches to optimize the structure. (author)

  17. Environmental assessment of nuclear projects in Canada - process, participation, lessons learned

    International Nuclear Information System (INIS)

    Underdown, G.A.; Brown, P.A.; Morrison, R.W.

    1995-01-01

    This paper documents public participation in decision-making for five cases of nuclear-based projects in Canada. Two cases involve the application of the Federal Environmental Assessment and Review Process (EARP), a formal, non-judicial process for public involvement in projects with a potential environmental impact. It is being applied to the development of new Uranium mines and the disposal of used nuclear fuels. The siting of radioactive waste facilities, generally unwanted by the communities, presents many difficult challenges which needs to be addressed before a project goes through the EARP process. An open, consultative, community-based approach to decision-making about siting is being applied in the three cases: Port Hope, Scarborough and Surrey. A number of lessons have been learned, the most important that there is a need to establish an acceptable process that includes 'getting the science right' on a project before attempting to find a site. The EARP, in most cases, provides a good mechanism for the sharing of information about a potential between the proponents and the public as long as there are no major unresolved contentious issues such as the unwanted siting of a waste facility in a particular community. 19 refs

  18. Discussion on the post-project assessment of environmental impact for nuclear facilities

    International Nuclear Information System (INIS)

    Shang Zhaorong

    2013-01-01

    The paper introduces the background of post-project assessment of environmental impact in the world and focuses on the characteristic of environmental impact assessment for Chinese nuclear facilities construction projects, analyzes the necessity, principle and contents of post-project assessment of environmental impact on current Chinese nuclear facilities operation. It is considered that to start the post-project assessment of environmental impact, perfect the post-project assessment mechanism, introduce the post-project assessment into environmental impact assessment system are just at the night time. (author)

  19. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2000-11-03

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those

  20. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2000-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted

  1. Resource Letter MP-2: The Manhattan project and related nuclear research

    Science.gov (United States)

    Reed, B. Cameron

    2011-02-01

    This Resource Letter is a supplement to my earlier Resource Letter MP-1 and provides further sources on the Manhattan Project and related nuclear research. Books and journal articles are cited for the following topics: General works, technical works, biographical and autobiographical works, foreign wartime programs and allied intelligence, technical papers of historical interest, and postwar policy and technical developments. I also give a list of videos and websites dealing with the Manhattan Project, nuclear weapons, and nuclear issues.

  2. Hanford K basins spent nuclear fuel project update

    International Nuclear Information System (INIS)

    Williams, N.H.; Hudson, F.G.

    1997-07-01

    Twenty one hundred metric tons of spent nuclear fuel (SNF) are currently stored in the Hanford Site K Basins near the Columbia River. The deteriorating conditions of the fuel and the basins provide engineering and management challenges to assure safe current and future storage. DE and S Hanford, Inc., part of the Fluor Daniel Hanford, Inc. lead team on the Project Hanford Management Contract, is constructing facilities and systems to move the fuel from current pool storage to a dry interim storage facility away from the Columbia River, and to treat and dispose of K Basins sludge, debris and water. The process starts in K Basins where fuel elements will be removed from existing canisters, washed, and separated from sludge and scrap fuel pieces. Fuel elements will be placed in baskets and loaded into Multi-Canister Overpacks (MCOs) and into transportation casks. The MCO and cask will be transported to the Cold Vacuum Drying Facility, where free water within the MCO will be removed under vacuum at slightly elevated temperatures. The MCOs will be sealed and transported via the transport cask to the Canister Storage Building

  3. Nuclear criticality safety program for environmental restoration projects

    International Nuclear Information System (INIS)

    Marble, R.C.; Brown, T.D.

    1994-05-01

    The Fernald Environmental Management Project (FEMP), formerly known as the Feed Materials Production Center (FMPC), is located on a 1050 acre site approximately twenty miles northwest of Cincinnati, Ohio. The production area of the site covers approximately 136 acres in the central portion of the site. Surrounding the core production area is a buffer consisting of leased grazing land, reforested land, and unused areas. The uranium processing facility was designed and constructed in the early 1950s. During the period from 1952 to 1989 the site produced uranium feed material and uranium products used in the United States weapons complex. Production at the site ended in 1989, when the site was shut down for what was expected to be a short period of time. However, the FUTC was permanently shut down in 1991, and the site's mission was changed from production to environmental restoration. The objective of this paper is to give an update on activities at the Fernald Site and to describe the Nuclear Criticality Safety issues that are currently being addressed

  4. Pharmacological Interventions Including Medical Injections for Neck Pain: An Overview as Part of the ICON§ Project

    Science.gov (United States)

    Peloso, Paul M; Khan, Mahweesh; Gross, Anita R; Carlesso, Lisa; Santaguida, Lina; Lowcock, Janet; MacDermid, Joy C; Walton, Dave; Goldsmith, Charlie H; Langevin, Pierre; Shi, Qiyun

    2013-01-01

    Objectives: To conduct an overview (review-of-reviews) on pharmacological interventions for neck pain. Search Strategy: Computerized databases and grey literature were searched from 2006 to 2012. Selection Criteria: Systematic reviews of randomized controlled trials (RCT) in adults with acute to chronic neck pain reporting effects of pharmacological interventions including injections on pain, function/disability, global perceived effect, quality of life and patient satisfaction. Data Collection & Analysis: Two independent authors selected articles, assessed risk of bias and extracted data The GRADE tool was used to evaluate the body of evidence and an external panel provided critical review. Main Results: We found 26 reviews reporting on 47 RCTs. Most pharmacological interventions had low to very low quality methodologic evidence with three exceptions. For chronic neck pain, there was evidence of: a small immediate benefit for eperison hydrochloride (moderate GRADE, 1 trial, 157 participants);no short-term pain relieving benefit for botulinum toxin-A compared to saline (strong GRADE; 5 trial meta-analysis, 258 participants) nor for subacute/chronic whiplash (moderate GRADE; 4 trial meta-analysis, 183 participants) including reduced pain, disability or global perceived effect; andno long-term benefit for medial branch block of facet joints with steroids (moderate GRADE; 1 trial, 120 participants) over placebo to reduce pain or disability; Reviewers' Conclusions: While in general there is a lack of evidence for most pharmacological interventions, current evidence is against botulinum toxin-A for chronic neck pain or subacute/chronic whiplash; against medial branch block with steroids for chronic facet joint pain; but in favour of the muscle relaxant eperison hydrochloride for chronic neck pain. PMID:24155805

  5. The opalinus clay project - disposal of medium and highly-active nuclear wastes

    International Nuclear Information System (INIS)

    Mueller, U.

    2003-01-01

    This article describes the project to demonstrate the feasibility of disposing of long-living medium-active and highly-radioactive nuclear wastes in sedimentary rock in Switzerland. The disposal tasks to be carried out are reviewed and the solutions proposed are described, including short-term handling, intermediate storage and final disposal of low, medium and highly-active wastes. The present state of affairs is described and, in particular, the feasibility of implementing a final storage facility in the opalinus clay beds to be found in northern Switzerland. The project for such a facility in the wine-growing area of the canton of Zurich is described in detail, including the storage concept, the technology to be used and operational aspects as well as questions of safety

  6. Development of a quantitative safety assessment method for nuclear I and C systems including human operators

    International Nuclear Information System (INIS)

    Kim, Man Cheol

    2004-02-01

    Conventional PSA (probabilistic safety analysis) is performed in the framework of event tree analysis and fault tree analysis. In conventional PSA, I and C systems and human operators are assumed to be independent for simplicity. But, the dependency of human operators on I and C systems and the dependency of I and C systems on human operators are gradually recognized to be significant. I believe that it is time to consider the interdependency between I and C systems and human operators in the framework of PSA. But, unfortunately it seems that we do not have appropriate methods for incorporating the interdependency between I and C systems and human operators in the framework of Pasa. Conventional human reliability analysis (HRA) methods are not developed to consider the interdependecy, and the modeling of the interdependency using conventional event tree analysis and fault tree analysis seem to be, event though is does not seem to be impossible, quite complex. To incorporate the interdependency between I and C systems and human operators, we need a new method for HRA and a new method for modeling the I and C systems, man-machine interface (MMI), and human operators for quantitative safety assessment. As a new method for modeling the I and C systems, MMI and human operators, I develop a new system reliability analysis method, reliability graph with general gates (RGGG), which can substitute conventional fault tree analysis. RGGG is an intuitive and easy-to-use method for system reliability analysis, while as powerful as conventional fault tree analysis. To demonstrate the usefulness of the RGGG method, it is applied to the reliability analysis of Digital Plant Protection System (DPPS), which is the actual plant protection system of Ulchin 5 and 6 nuclear power plants located in Republic of Korea. The latest version of the fault tree for DPPS, which is developed by the Integrated Safety Assessment team in Korea Atomic Energy Research Institute (KAERI), consists of 64

  7. Pulley system including emergency locking means for nuclear reactor vessel inspection apparatus

    International Nuclear Information System (INIS)

    Reyes, R.D.

    1979-01-01

    A pulley system for driving the manipulating arm of a nuclear reactor vessel inspection device is disclosed. Two drive pulleys and pulley take-up spools are disposed in driving engagement with a motor. The pulley cable is looped about a first set of idler pulleys fixed to the manipulator arm which is to be driven along the main or central column of the inspection device. Two additional idler pulleys, a second set, are used to define another portion of the pulley cable loop, which portion serves to equalize unbalanced forces in the cable. When the drive motor is actuated, only that portion of the pulley cable between the drive set and the first set of idler pulleys moves. Depending on the direction of movement, the manipulator arm is raised or lowered with equal force on each side thereof minimizing wear and potential hazards. In addition, to guard against the possible dangers resulting from a snapped pulley cable, a restraining clip is secured to the cable between the second set of idler pulleys and is appropriately sized to jam between one of the idler pulleys and its support bracket. 3 claims

  8. Rise and fall of public opposition in specific social movements. [Including nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Leahy, P J [Akron Univ., OH (USA); Mazur, A [Syracuse Univ., NY (USA)

    1980-08-01

    This article reports a comparative study of four 'specific' social movements which involve aspects of technological controversy: Fluoridation, the ABM, Nuclear Power Plants, and Legalized Abortion. A theoretical model of the rise and fall of public opposition in these movements over time is suggested. Quantitative indicators are developed and applied to this historical model. Rise and fall of controversy follows a regular sequence: Activities of protest leaders increase during periods of great national concern over issues that are complementary to the movement; during these periods, social and economic resources are relatively available to the movement. As the activity of protest leaders increases, mass media coverage of their activities increases. As mass media coverage increases, opposition to the technology among the wider public increases. As the activity of the leaders wanes, mass media coverage declines, and so does opposition among the wider public. The paper concludes with a discussion of the relevance of this perspective for making predictions about the future course of 'specific' social movements.

  9. Fire Risk Scoping Study: Investigation of nuclear power plant fire risk, including previously unaddressed issues

    International Nuclear Information System (INIS)

    Lambright, J.A.; Nowlen, S.P.; Nicolette, V.F.; Bohn, M.P.

    1989-01-01

    An investigation of nuclear power plant fire risk issues raised as a result of the USNRC sponsored Fire Protection Research Program at Sandia National Laboratories has been performed. The specific objectives of this study were (1) to review and requantify fire risk scenarios from four fire probabilistic risk assessments (PRAs) in light of updated data bases made available as a result of USNRC sponsored Fire Protection Research Program and updated computer fire modeling capabilities, (2) to identify potentially significant fire risk issues that have not been previously addressed in a fire risk context and to quantify the potential impact of those identified fire risk issues where possible, and (3) to review current fire regulations and plant implementation practices for relevance to the identified unaddressed fire risk issues. In performance of the fire risk scenario requantifications several important insights were gained. It was found that utilization of a more extensive operational experience base resulted in both fire occurrence frequencies and fire duration times (i.e., time required for fire suppression) increasing significantly over those assumed in the original works. Additionally, some thermal damage threshold limits assumed in the original works were identified as being nonconservative based on more recent experimental data. Finally, application of the COMPBRN III fire growth model resulted in calculation of considerably longer fire damage times than those calculated in the original works using COMPBRN I. 14 refs., 2 figs., 16 tabs

  10. A project in support of Nuclear Technology Cooperation

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho [and others

    2005-12-15

    Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate.

  11. A project in support of Nuclear Technology Cooperation

    International Nuclear Information System (INIS)

    Jung, Ki Jung; Choi, Pyong Hoon; Yi, Ji Ho

    2005-12-01

    Establish the integrated management system of information resources and to automate business flow and to improve business productivity through efficient information sharing. - Promotion of domestic nuclear energy technology by utilizing nuclear energy informations and computer software developed in the advanced countries. - Establish strategies of international cooperation in an effort to promote our nation's Leading role in international society, to form the foundation for the effective transfer of nuclear technology to developing countries, and to cope with the rapidly changing international nuclear climate

  12. Fatigue load considerations and use of high efficiency materials in the nuclear refurbishment projects: a structural engineering perspective

    Energy Technology Data Exchange (ETDEWEB)

    Mohee, F. M., E-mail: fmm_p@yahoo.com [Univ. of Waterloo, ON (Canada)

    2014-07-01

    For the Darlington refurbishment project in Canada, fatigue load consideration is a very crucial component in the analysis and design of different structures in the nuclear facilities. New and innovative structural materials having much higher ultimate tensile strength and modulus of elasticity, that are free from corrosion, should be considered along with fatigue load during the analysis and design of the nuclear refurbishment projects. The structural analysis should include beam, column and slabs, vibrating, rotating and crane supporting structures, robotic structures, pipe supports, Serapid chain and associated automated gate structures, flask supporting structures, processing unit and lidding unit support structures. (author)

  13. Schedule and staffing of a nuclear power project

    International Nuclear Information System (INIS)

    Polliart, A.J.; Csik, B.

    1977-01-01

    Establishment of construction schedule: a) preliminary construction schedule; b) PERT (Program Evaluation Review Techniques) analytical method; c) identify key milestone target dates; d) inter-action by participants and contribution to support revised construction schedule. - Construction schedule control: a) ability to update and modify construction schedule; b) alternate plans to circumvent restraints (problems); c) critical path activity-controls; d) continuous review and report system. - Updating construction site reports to include: 1) progress, 2) accomplishments, 3) potential problems and alternate plans; b) progress reports on related support services; c) total assessment of participating groups on schedule; d) information required by management for decisions. - Typical causes for delays in project schedule. (orig.) [de

  14. Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy

    International Nuclear Information System (INIS)

    TRAWINSKI, B.J.

    2000-01-01

    The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system

  15. Decommissioning of the research nuclear reactor WWR-S Magurele - Bucharest. General presentation of the project

    International Nuclear Information System (INIS)

    Dragulescu, Emilian; Dragusin, Mitica; Popa, Victor; Boicu, Alin; Tuca, Carmen; Iorga, Ioan; Vrabie, Ionut; Mustata, Carmen

    2003-01-01

    A decommissioning project was worked out concerning the nuclear facility research reactor WWR-S Magurele-Bucharest to remove the radioactive and hazardous materials and so to exclude any risk for human health and environment. The project involves the four phases named assessment, development, operations and closeout. There are two major parts to the assesment phase: preliminary characterisation and the review and decision-making process. Characterisation is needed to develop project baseline data, which should include sufficient chemical, physical, and radiological characterisation to meet planning needs. Based on the conclusions of these studies, possible decommissioning alternative will be analyzed and: the best alternative chosen, final goal identified, risk assessments are evaluated. Also, taken into account are: regulations supporting assessment, land use considerations, financial concerns, disposal availability, public involvement, technology developments. After a decommissioning alternative was chosen, detailed engineering will begin following appropriate regulatory guidance. The plan will include characterisation information, namely: review of decommissioning alternatives; justification for the selected alternative; provision for regulatory compliance; predictions of personnel exposure, radioactive waste volume, and cost. Other activities are: scheduling, preparation for decommissioning operations; coordination, documentation, characterization report, feasibility studies, Decommissioning Plan, project daily report, radiological survey, airborne sampling records, termination survey of the site. The operations imply: identification and sequencing the operations on contaminated materials, storing on site the wastes, awaiting processing or disposal, and packaging of materials for transport to processing or disposal facilities.The key operations are: worker protection, health and safety program, review of planing work, work area assessment, work area controls

  16. Uranium, resources, production and demand including other nuclear fuel cycle data

    International Nuclear Information System (INIS)

    1975-12-01

    The uranium reserves exploitable at a cost below 15 dollars/lb U 3 O 8 , are 210,000 tonnes. While present uranium production capacities amount to 26,000 tonnes uranium per year, plans have been announced which would increase this capacity to 44,000 tonnes by 1978. Given an appropriate economic climate, annual capacities of 60,000 tonnes and 87,000 tonnes could be attained by 1980 and 1985, respectively, based on presently known reserves. However, in order to maintain or increase such a capacity beyond 1985, substantial additional resources would have to be identified. Present annual demand for natural uranium amounts to 18,000 tonnes and is expected to establish itself at 50,000 tonnes by 1980 and double this figure by 1985. Influences to increase this demand in the medium term could come from shortages in other fuel cycle capacities, i.e. enrichment (higher tails assays) and reprocessing (no uranium and plutonium recycle). However, the analysis of the near term uranium supply and demand situation does not necessarily indicate a prolongation of the current tight uranium market. Concerning the longer term, the experts believe that the steep increase in uranium demand foreseen in the eighties, according to present reactor programmes, with doubling times of the order of 6 to 7 years, will pose formidable problems for the uranium industry. For example, in order to provide reserves sufficient to support the required production rates, annual additions to reserves must almost triple within the next 15 years. Efforts to expand world-wide exploration levels to meet this challenge would be facilitated if a co-ordinated approach were adopted by the nuclear industry as a whole

  17. Overview of Nuclear Energy: Present and Projected Use

    International Nuclear Information System (INIS)

    Stanculescu, Alexander

    2011-01-01

    Several factors will influence the contribution of nuclear energy to the future energy mix. Among them, the most important are the degree of global commitment to greenhouse gas reduction, continued vigilance in safety and safeguards, technological advances, economic competitiveness and innovative financing arrangements for new nuclear power plant constructions, the implementation of nuclear waste disposal, and, last but not least, public perception, information and education. The paper presents an overview of the current nuclear energy situation, possible development scenarios, of reactor technology, and of non-electric applications of nuclear energy.

  18. Overview of Nuclear Energy: Present and Projected Use

    Energy Technology Data Exchange (ETDEWEB)

    Alexander Stanculescu

    2011-09-01

    Several factors will influence the contribution of nuclear energy to the future energy mix. Among them, the most important are the degree of global commitment to greenhouse gas reduction, continued vigilance in safety and safeguards, technological advances, economic competitiveness and innovative financing arrangements for new nuclear power plant constructions, the implementation of nuclear waste disposal, and, last but not least, public perception, information and education. The paper presents an overview of the current nuclear energy situation, possible development scenarios, of reactor technology, and of non-electric applications of nuclear energy.

  19. Overview of nuclear energy: Present and projected use

    Energy Technology Data Exchange (ETDEWEB)

    Stanculescu, Alexander [Idaho National Laboratory 2525 North Fremont Avenue, Idaho Falls, Idaho 83415 (United States)

    2012-06-19

    Several factors will influence the contribution of nuclear energy to the future energy mix. Among them, the most important are the degree of global commitment to greenhouse gas reduction, continued vigilance in safety and safeguards, technological advances, economic competitiveness and innovative financing arrangements for new nuclear power plant constructions, the implementation of nuclear waste disposal, and, last but not least, public perception, information and education. The paper presents an overview of the current nuclear energy situation, possible development scenarios, of reactor technology, and of non-electric applications of nuclear energy.

  20. Use of the project management methodology to establish physical protection system at nuclear facility

    International Nuclear Information System (INIS)

    Gramotkin, F.; Kuzmyak, I.; Kravtsov, V.

    2015-01-01

    The paper considers the possibility of using the project management methodology developed by the Project Management Institute (USA) in nuclear security in terms of modernization or development of physical protection system at nuclear facility. It was demonstrated that this methodology allows competent and flexible management of the projects on physical protection, ensuring effective control of their timely implementation in compliance with the planned budget and quality