OECD/NEA thermochemical database

Energy Technology Data Exchange (ETDEWEB)

Byeon, Kee Hoh; Song, Dae Yong; Shin, Hyun Kyoo; Park, Seong Won; Ro, Seung Gy

1998-03-01

This state of the art report is to introduce the contents of the Chemical Data-Service, OECD/NEA, and the results of survey by OECD/NEA for the thermodynamic and kinetic database currently in use. It is also to summarize the results of Thermochemical Database Projects of OECD/NEA. This report will be a guide book for the researchers easily to get the validate thermodynamic and kinetic data of all substances from the available OECD/NEA database. (author). 75 refs.

IRIS-2012 OECD/NEA/CSNI benchmark: Numerical simulations of structural impact

International Nuclear Information System (INIS)

Orbovic, Nebojsa; Tarallo, Francois; Rambach, Jean-Mathieu; Sagals, Genadijs; Blahoianu, Andrei

2015-01-01

A benchmark of numerical simulations related to the missile impact on reinforced concrete (RC) slabs has been launched in the frame of OECD/NEA/CSNI research program “Improving Robustness Assessment Methodologies for Structures Impacted by Missiles”, under the acronym IRIS. The goal of the research program is to simulate RC structural, flexural and punching, behavior under deformable and rigid missile impact. The first phase called IRIS-2010 was a blind prediction of the tests performed at VTT facility in Espoo, Finland. The two simulations were performed related to two series of tests: (1) two tests on the impact of a deformable missile exhibiting damage mainly by flexural (so-called “flexural tests”) or global response and (2) three tests on the impact of a rigid missile exhibiting damage mainly by punching response (so-called “punching tests”) or local response. The simulation results showed significant scatter (coefficient of variation up to 132%) for both flexural and punching cases. The IRIS-2012 is the second, post-test, phase of the benchmark with the goal to improve simulations and reduce the scatter of the results. Based on the IRIS-2010 recommendations and to better calibrate concrete constitutive models, a series of tri-axial tests as well as Brazilian tests were performed as a part of the IRIS-2012 benchmark. 25 teams from 11 countries took part in this exercise. Majority of participants were part of the IRIS-2010 benchmark. Participants showed significant improvement in reducing epistemic uncertainties in impact simulations. Several teams presented both finite element (FE) and simplified analysis as per recommendations of the IRIS-2010. The improvements were at the level of simulation results but also at the level of understanding of impact phenomena and its modeling. Due to the complexity of the physical phenomena and its simulation (high geometric and material non-linear behavior) and inherent epistemic and aleatory uncertainties, the

IRIS-2012 OECD/NEA/CSNI benchmark: Numerical simulations of structural impact

Energy Technology Data Exchange (ETDEWEB)

Orbovic, Nebojsa, E-mail: nebojsa.orbovic@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Ottawa, ON (Canada); Tarallo, Francois [IRSN, Fontenay aux Roses (France); Rambach, Jean-Mathieu [Géodynamique et Structures, Bagneux (France); Sagals, Genadijs; Blahoianu, Andrei [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

2015-12-15

A benchmark of numerical simulations related to the missile impact on reinforced concrete (RC) slabs has been launched in the frame of OECD/NEA/CSNI research program “Improving Robustness Assessment Methodologies for Structures Impacted by Missiles”, under the acronym IRIS. The goal of the research program is to simulate RC structural, flexural and punching, behavior under deformable and rigid missile impact. The first phase called IRIS-2010 was a blind prediction of the tests performed at VTT facility in Espoo, Finland. The two simulations were performed related to two series of tests: (1) two tests on the impact of a deformable missile exhibiting damage mainly by flexural (so-called “flexural tests”) or global response and (2) three tests on the impact of a rigid missile exhibiting damage mainly by punching response (so-called “punching tests”) or local response. The simulation results showed significant scatter (coefficient of variation up to 132%) for both flexural and punching cases. The IRIS-2012 is the second, post-test, phase of the benchmark with the goal to improve simulations and reduce the scatter of the results. Based on the IRIS-2010 recommendations and to better calibrate concrete constitutive models, a series of tri-axial tests as well as Brazilian tests were performed as a part of the IRIS-2012 benchmark. 25 teams from 11 countries took part in this exercise. Majority of participants were part of the IRIS-2010 benchmark. Participants showed significant improvement in reducing epistemic uncertainties in impact simulations. Several teams presented both finite element (FE) and simplified analysis as per recommendations of the IRIS-2010. The improvements were at the level of simulation results but also at the level of understanding of impact phenomena and its modeling. Due to the complexity of the physical phenomena and its simulation (high geometric and material non-linear behavior) and inherent epistemic and aleatory uncertainties, the

The activities of the OECD/NEA in the field of earthquake engineering

International Nuclear Information System (INIS)

Sollogoub, P.; Kitada, Y.; Mathet, E.

2005-01-01

The Working Group on the Integrity and Aging of Components and Structures (IAGE) is established under the senior committee on the Safety of Nuclear Installations (CSNI) of the OECD/NEA (Organization of Economic Cooperation and Development/Nuclear Energy Agency). This Committee deals with safety-related R and D aspects. The mandate of this Working Group is to advise the CSNI on the topical basis for management of plant ageing and to propose general principles to maintain the integrity of systems and components. The Working Group is composed of three sub-groups addressing metallic components, concrete structures and the seismic behavior of structures and components. The groups operate through annual plenary meetings, workshops, state-of-the-art reports, topical opinion papers and benchmarks to produce advises to the CSNI. Twenty five high level experts from fifteen countries attend the Seismic Group (safety authorities, researchers, utilities, and representatives from other international organizations (IAEA, EC)). In this paper the scope of activities and recent tasks of the Seismic Group are presented. (authors)

Presentation on CSNI Activities and Introduction to the Seminar

International Nuclear Information System (INIS)

Amri, A.

2008-01-01

The standing committees of the OECD Nuclear Energy Agency (Nea) which consist of delegates from its Member countries, determine the Agency's programme of work. This paper explains how the Committee on the Safety of Nuclear Installations (CSNI) and its groups of experts function. Programmes of work are carried out in the areas of operating experience and human factors, thermal-hydraulics and coolant system behaviour, reactor component integrity and ageing, confinement of accidental radioactive releases, severe accident management, risk assessment, nuclear fuel safety, nuclear fuel cycle safety, and safety margins. Some of these activities are open to countries who are not Members of the OECD. Selected programmes of work are described briefly. The objectives and the methods of work of the OECD and the Nea are outlined in the first part of the paper. Nea's nuclear reactor safety programme is a varied and evolving patch-work of studies, tasks and projects, interspersed with specialist meetings and workshops. It provides a efficient forum for delegates and experts of Member countries to discuss issues of mutual concern and to arrive at consensus views and conclusions. Because of the nature of its membership, its flexibility, and its methods of working, Nea is in a unique position to provide the international community, quickly and efficiently, with advanced views and complete up-to-date information on a broad range of nuclear safety and regulation issues. Nea's programme is performed in close collaboration with other international organisations, in particular the International Atomic Energy Agency and the Commission of the European Communities.

Proceedings of the OECD/NEA workshop on the relations between seismological data and seismic engineering

International Nuclear Information System (INIS)

2003-01-01

The Committee on the Safety of Nuclear Installations (CSNI) of the OECD-NEA co-ordinates the NEA activities concerning the technical aspects of design, construction and operation of nuclear installations insofar as they affect the safety of such installations. The Integrity and Ageing Working Group (IAGE WG) of the CSNI deals with the integrity of structures and components, and has three sub-groups, dealing with the integrity of metal components and structures, ageing of concrete structures, and the seismic behaviour of structures. The sub-group dealing with the seismic behaviour of structures proposed this workshop. The OECD-NEA workshop on the relations between seismological data and seismic engineering analyses was held on October 17-18, 2002. A field visits in the Izmit area where the fault scarp is still visible was organised on Wednesday October 16, 2002. The Ttirkiye Atom Enerjisi Kurumu, TAEK (Turkish Atomic Energy Agency) in Istanbul, Turkey, hosted the workshop. A recommendation of the OECD workshop on the engineering characterisation of seismic input (hosted by the United States Nuclear Regulatory Commission and organised by Brookhaven National Laboratory on November 15-17, 1999) was to foster the growth of interaction between 'design engineers' and 'ground motion specialists'. The objective of the Istanbul workshop is to address this recommendation. The workshop gave seismologists the opportunity to present observed damages and their related ground motions and design engineers the opportunity to present current techniques used in the evaluation of seismic hazards. Bridging the gap between these two fields was a key objective - this workshop was a forum for bringing together the two communities. In addition, the location of the workshop was particularly interesting and provided possibilities for several of the host country participants to discuss the 1999 Kocaeli earthquake. On the basis of lessons learned from large earthquakes over the last decade, the

Overview of OECD/NEA BEPU Programmes

International Nuclear Information System (INIS)

Amri, Abdallah; Gulliford, Jim; )

2013-01-01

The OECD/NEA paved the way for the development and assessment of BEPU for about 40 years, through concrete tasks: International Standard Problems (ISPs), Benchmarking activities, Development of Validation Matrices, Joint Safety Research Projects, and Specialist meetings. Several NEA related Best-Estimate Plus Uncertainties (BEPU) programmes have been successfully completed: Uncertainty Methods Study (UMS), Best-Estimate Methods - Uncertainty and Sensitivity Evaluation (BEMUSE), Safety Margin Assessment and Application (SM2A), Uncertainty Analysis in Modeling (UAM) Benchmark. New Programmes are underway to address pending issues (e.g., input uncertainties, uncertainties in coupled codes). The present Workshop may highlight new issues to be addressed (e.g., uncertainty analysis for CFD codes). Document available in the slides-form only

OECD/NEA multi-lateral cooperation in the area of structural integrity & aging management

Energy Technology Data Exchange (ETDEWEB)

Breest, A. [Nuclear Energy Agency, Issy-les-Moulineaux (France); Gott, K. [MATSAFE AB, Stockholm (Sweden); Lydell, B. [SIGMA-PHASE Inc., Vail, AZ (United States); Riznic, J. [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

2014-07-01

Several OECD Member Countries have agreed to establish the OECD/NEA 'Component Operational Experience, Degradation & Ageing Programme' (CODAP) to encourage multilateral co-operation in the collection and analysis of data relating to degradation and failure of metallic piping and non-piping metallic passive components in commercial nuclear power plants. The scope of the data collection includes service-induced wall thinning, part through-wall cracks, through-wall cracks with and without active leakage, and instances of significant degradation of metallic passive components, including piping pressure boundary integrity. The OECD/NEA Committee on the Safety of Nuclear Installations (CSNI) acts as an umbrella committee of the Project. CODAP is the continuation of the 2002-2011 'OECD/NEA Pipe Failure Data Exchange Project' (OPDE) and the Stress Corrosion Cracking Working Group of the 2006-2010 'OECD/NEA SCC and Cable Ageing project' (SCAP). OPDE was formally launched in May 2002. Upon completion of the 3rd Term (May 2011), the OPDE project was officially closed to be succeeded by CODAP. SCAP was enabled by a voluntary contribution from Japan. It was formally launched in June 2006 and officially closed with an international workshop held in Tokyo in May 2010. Majority of the Member Organizations of the two projects were the same, often being represented by the same person. In May 2011, thirteen countries signed the CODAP 1st Term agreement (Canada, Chinese Taipei, Czech Republic, Finland, France, Germany, Korea (Republic of), Japan, Slovak Republic, Spain, Sweden, Switzerland and United States of America). The 1st Term (2011-2014) work plan includes the preparation of Topical Reports to foster technical cooperation and to deepen the understanding of national differences in ageing management. The Topical Reports constitute CODAP Event Database and Knowledge Base insights reports and as such act as portals for future in-depth studies of

Selected source term topics. Report to CSNI by an OECD/NEA Group of experts

International Nuclear Information System (INIS)

1987-04-01

CSNI Report 136 summarizes the results of the work performed by the Group of Experts on the Source Term and Environmental Consequences (PWG4) during the period extending from 1983 and 1986. This report is complementary to Part 1, 'Technical Status of the Source Term' of CSNI Report 135, 'Report to CSNI on Source Term Assessment, Containment atmosphere control systems, and accident consequences'; it considers in detail a number of very specific issues thought to be important in the source term area. It consists of: an executive summary (prepared by the Chairman of the Group), a section on conclusions and recommendations, and five technical chapters (fission product chemistry in the primary circuit of a LWR during severe accidents; resuspension/re-entrainment of aerosols in LWRs following a meltdown accident; iodine chemistry under severe accident conditions; effects of combustion, steam explosions and pressurized melt ejection on fission product behaviour; radionuclide removal by pool scrubbing), a technical annex and two appendices

OECD/NEA WGRisk CAPS on PSA for Advanced Reactors: a summary of questionnaires and answers report

International Nuclear Information System (INIS)

Ahn, K.I.; Han, S.J.; Han, S.H.; Yang, J.E.

2012-01-01

Main objectives of the WGRisk CAPS on the probabilistic safety analysis for advanced reactors which was approved by the OECD/NEA CSNI in June 2008, are to 1) characterize the ability of current PSA (Probability Safety Assessment) technology to address key questions regarding the development and licensing of advanced reactor designs; 2) characterize the potential value of advanced PSA methods and tools; and 3) develop recommendations to CSNI for any needed developments. For this purpose, the two following sub-tasks have been set up: -) A survey of participating countries regarding the state of PSA technologies for advanced reactors and -) Organization of an international workshop for detailed follow-up discussions related to the topic. In order to meet the objectives of the CAPS (CSNI Activity Proposal Sheet), the questionnaires to elicit the respondents' viewpoints had been distributed to the WGRisk member countries during the period of 2009 to 2010, and answers from the 12 countries (13 organizations) have been collected until February 2010. This paper summarizes the current status of the answers to the questionnaires and the international status and insights into PSA technologies for advanced reactors. (authors)

Use of OECD/NEA Data Project Products in Probabilistic Safety Assessment

International Nuclear Information System (INIS)

Cherkas, G.; Raducu, Gheorghe; Riznic, J.; Yalaoui, S.; Huang, Hui-Wen; Holy, Jaroslav; Holmberg, Jan-Erik; Sandberg, Jorma; Balmain, Michel; Bonnevialle, Anne-Marie; Curnier, Florence; Georgescu, Gabriel; Lanore, Jeanne-Marie; Lindner, Arndt; Fujimoto, Haruo; Ahn, Kwang-Il; Hwang, Taesuk; Jang, Seung-Cheol; Husarcek, Jan; Kovacs, Zoltan; Vazquez, Teresa; Johanson, Gunnar; Liwaang, Bo; Nyman, Ralph; Dang, Vinh; Schoen, Gerhard; Brook, Kevin; Hamblen, David; Siu, Nathan; Sturzebecher, Karl; Tobin, Margaret; Wood, Jeff; Amri, Abdallah; Breest, Axel

2014-01-01

The Nuclear Energy Agency (NEA)/Committee for the Safety of Nuclear Installations' (CSNI) Working Group on Risk Assessment (WGRISK) is tasked with supporting the improved use of Probabilistic Safety Assessment (PSA) in risk informed regulation and safety management through the analysis of results and the development of perspectives regarding potentially important risk contributors and associated risk reduction strategies. The task consists of the following major activities: Development, distribution, and completion of survey questionnaires; Analysis of survey questionnaire results at a task workshop; Preparation of the final task report. The main objectives of this task, as proposed by WGRISK and approved by CSNI, are the following: - Identification and characterization of the current uses of OECD data project products and data in support of PSA. In this context, the term 'products' refers to data analysis results, technical reports, and other project outputs. - Identification and characterization of technical and programmatic characteristics that either support or impede use of data project products in PSA. This includes an assessment of which PSA parameters could be potentially estimated from the various data project products and gaps between available product information and PSA data needs. - Identification of recommendations for enhancing the usefulness of data project products and the coordination between WGRISK and the data projects. This task report consists of the following sections: - Chapter 1 Provides a general overview of motivation and approach used for this task. - Chapter 2 Describes scope and objectives of the task. - Chapter 3 Provides an overview of the ICDE, FIRE, OPDE/CODAP, and COMPSIS data projects. For each project, the project objectives, project history, data collection methodology and quality assurance, project status, example PSA Applications, and information related to project participation is provided. - Chapter 4 Describes the

OECD/CSNI specialist meeting on nuclear aerosols in reactor safety - Summary and Conclusions

International Nuclear Information System (INIS)

Allelein, Hans-Josef; Boulaud, Denis; Guentay, Salih; Dehbi, Abdelouahab; Hontanon, Esther; Jokiniemi, Jorma; Jones, Alan V.; Koroll, Grant W.; Tinkler, Charles G.; Schaperow, J.; Royen, Jacques

1999-01-01

The Third OECD Specialist Meeting on Nuclear Aerosols in Reactor Safety was organised in Cologne, Germany, from 15-18 June 1998, in collaboration with the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH. It was attended by sixty-five specialists representing thirteen OECD Member countries and the Commission of the European Communities. Thirty-nine papers were presented, in eight sessions. The meeting was concluded by a general discussion devoted to the following topics: - What has been solved up to the level of plant applications and accident management? - Where is more work needed for plant applications? Over the last eight years significant progress has been made in source term modelling and code development. Results have been consolidated in codes which are being used for plant calculations to address safety issues. For example, two countries used their source term codes last year to assess the impact of heating from deposited fission products on the potential for steam generator tube rupture. Also, another source term code was used to assess the need of sprays for fission product removal in the proposed design of a new type of reactor. Over the next few years, experiments and model development will continue, with more emphasis on application to risk-important severe accident scenarios

CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (Project FALSIRE)

Energy Technology Data Exchange (ETDEWEB)

Bass, B.R.; Pugh, C.E.; Keeney-Walker, J. [Oak Ridge National Lab., TN (United States); Schulz, H.; Sievers, J. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Gemany)

1993-06-01

This report summarizes the recently completed Phase I of the Project for Fracture Analysis of Large-Scale International Reference Experiments (Project FALSIRE). Project FALSIRE was created by the Fracture Assessment Group (FAG) of Principal Working Group No. 3 (PWG/3) of the Organization for Economic Cooperation and Development (OECD)/Nuclear Energy Agency`s (NEA`s) Committee on the Safety of Nuclear Installations (CSNI). Motivation for the project was derived from recognition by the CSNI-PWG/3 that inconsistencies were being revealed in predictive capabilities of a variety of fracture assessment methods, especially in ductile fracture applications. As a consequence, the CSNI/FAG was formed to evaluate fracture prediction capabilities currently used in safety assessments of nuclear components. Members are from laboratories and research organizations in Western Europe, Japan, and the United States of America (USA). On behalf of the CSNI/FAG, the US Nuclear Regulatory Commission`s (NRC`s) Heavy-Section Steel Technology (HSST) Program at the Oak Ridge National Laboratory (ORNL) and the Gesellschaft fuer Anlagen--und Reaktorsicherheit (GRS), Koeln, Federal Republic of Germany (FRG) had responsibility for organization arrangements related to Project FALSIRE. The group is chaired by H. Schulz from GRS, Koeln, FRG.

Review of Fast Reactor Activities at OECD (NEA)

International Nuclear Information System (INIS)

Royen, J.

1980-01-01

The Committee on the Safety of Nuclear Installations (CSNI) has recently increased its activity in LMFBR safety, under the guidance of its Group of Senior Experts on LMFBR Safety R & D. This Group, formed in 1978, consists of CSNI delegates (or alternates) from Member countries sponsoring major research in the field, and the Commission of the European Communities. The Group now oversees the preparation of international status reports on relatively well-developed areas of LMFBR safety technology, and the convening of specialist meetings, expert groups and task forces to aid in investigating and resolving problems in less-evolved safety subjects

Proceedings of the OECD-NEA workshop on the evaluation of defects, repair criteria and methods of repair for concrete structures on nuclear power plants

International Nuclear Information System (INIS)

2002-01-01

The Committee on the Safety of Nuclear Installations (CSNI) of the OECD-NEA co-ordinates the NEA activities concerning the technical aspects of design, construction and operation of nuclear installations insofar as they affect the safety of such installations. In 1994, the CSNI approved a proposal to set up a Task Group under its Principal Working Group 3 (recently re-named as the Working Group on Integrity of Components and Structures (IAGE)) to study the need for a programme of international activities in the area of concrete structural integrity and ageing and how such a programme could be organised. The task group reviewed national and international activities in the area of ageing of nuclear power plant concrete structures and the relevant activities of other international agencies. A proposal for a CSNI programme of workshops was developed to address specific technical issues which were prioritised by OECD-NEA task group into three levels of priority: First Priority: loss of prestressing force in tendons of post-tensioned concrete structures; in-service inspection techniques for reinforced concrete structures having thick sections and areas not directly accessible for inspection. Second Priority: viability of development of a performance based database; response of degraded structures (including finite element analysis techniques). Third Priority: instrumentation and monitoring; repair methods; criteria for condition assessment. The working group has progressively worked through the priority list developed during the preliminary study carried out by the Task Group. Currently almost all of the three levels of priority are effectively complete, although in doing so the committee has identified other specific items worthy of consideration. By working logically through the list of priorities the committee has maintained a clarity of purpose which has been important in maintaining efficiency and achieving its objectives. The performance of the group has been

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

International Nuclear Information System (INIS)

2002-01-01

The OECD (CSNI) projects aim to produce results relevant for the safe operation of nuclear power plants through international collaborative projects. In general, the projects consist of advanced experimental programmes that are conducted at specialized facilities. At present, the following OECD (CSNI) projects are in operation: - The Halden Project, covering fuel/materials and I and C/Human Factors issues; - The Cabri Project, addressing reactivity transients on high burnup fuels; - The MASCA Project, which deals with in-vessel corium phenomena; - The OLHF Project, dealing with lower head failure mechanisms; - The SETH Project addressing thermal-hydraulics issues, started in 2001; - The MCCI Project on ex-vessel coolability and melt-concrete interaction. There are significant differences among these projects in terms of their motivation, size and scope. The Halden Project and the Cabri Water Loop Project are large undertakings where the host organisations assume full and direct responsibility for the project establishment and administration - as well as for the negotiation with relevant parties on the terms of participation. In the other cases, instead, the NEA secretariat has a more direct responsibility, conferred by the CSNI, in establishing the project technical and financial basis, as well as for its implementation and administration. The objective of this procedure is to provide a common basis for the establishment and management of the OECD projects in the area of nuclear safety. It is a follow-up of a recommendation expressed by the CSNI Bureau during its meeting in October 2001, where the procedures for the establishment and management of the OECD (CSNI) projects in nuclear safety were addressed. While this procedure attempts at defining general guidelines for project initiation, financing and management, one should bear in mind that each project has its own motivation, background and framework. Thus, some degree of flexibility in project structure

CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (Project FALSIRE)

International Nuclear Information System (INIS)

Bass, B.R.; Pugh, C.E.; Keeney-Walker, J.; Schulz, H.; Sievers, J.

1993-06-01

This report summarizes the recently completed Phase I of the Project for Fracture Analysis of Large-Scale International Reference Experiments (Project FALSIRE). Project FALSIRE was created by the Fracture Assessment Group (FAG) of Principal Working Group No. 3 (PWG/3) of the Organization for Economic Cooperation and Development (OECD)/Nuclear Energy Agency's (NEA's) Committee on the Safety of Nuclear Installations (CSNI). Motivation for the project was derived from recognition by the CSNI-PWG/3 that inconsistencies were being revealed in predictive capabilities of a variety of fracture assessment methods, especially in ductile fracture applications. As a consequence, the CSNI/FAG was formed to evaluate fracture prediction capabilities currently used in safety assessments of nuclear components. Members are from laboratories and research organizations in Western Europe, Japan, and the United States of America (USA). On behalf of the CSNI/FAG, the US Nuclear Regulatory Commission's (NRC's) Heavy-Section Steel Technology (HSST) Program at the Oak Ridge National Laboratory (ORNL) and the Gesellschaft fuer Anlagen--und Reaktorsicherheit (GRS), Koeln, Federal Republic of Germany (FRG) had responsibility for organization arrangements related to Project FALSIRE. The group is chaired by H. Schulz from GRS, Koeln, FRG

OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations - Workshop Proceedings

International Nuclear Information System (INIS)

2013-01-01

Best-Estimate Methods plus Uncertainty Evaluation are gaining increased interest in the licensing process. On the other hand, lessons learnt from the BEMUSE (NEA/CSNI/R(2011)3) and SM2A (NEA/CSNI/R(2011)3) benchmarks, progress of UAM benchmark, and answers to the WGAMA questionnaire on the Use of Best-Estimate Methodologies show that improvements of the present methods are necessary and new applications appear. The objective of this workshop is to provide a forum for a wide range of experts to exchange information in the area of best estimate analysis and uncertainty evaluation methods and address issues drawn-up from BEMUSE, UAM and SM2A activities. Both, improvement of existing methods and recent new developments are included. As a result of the workshop development, a set of recommendations, including lines for future activities were proposed. The organisation of the Workshop was divided into three parts: Opening session including key notes from OECD and IAEA representatives, Technical sessions, and a Wrap-up session. All sessions included a debate with participation from the audience constituted by 71 attendees. The workshop consisted of four technical sessions: a) Development achievements of BEPU methods and State of the Art: The objective of this session was to present the different approaches to deal with Best Estimate codes and uncertainties evaluations. A total of six papers were presented. One initial paper summarized the existing methods; the following open papers were focused on specific methods stressing their bases, peculiarities and advantages. As a result of the session a picture of the current State of the Art was obtained. b) International comparative activities: This session reviewed the set of international activities around the subject of BEPU methods benchmarking and development. From each of the activities a description of the objectives, development, main results, conclusions and recommendations (in case it is finalized) was presented. This

A study on an establishment for collaboration system with the OECD/NEA by means of the analysis of its main activities related to nuclear safety

International Nuclear Information System (INIS)

Song, J. H.; Kim, M. C.; Park, J. S.; Jeong, J. W.; Oh, C. W.

2005-12-01

The OECD Nuclear Energy Agency (NEA) was established on 1st February 1958 under the name of the OEEC European Nuclear Energy Agency. It received its present designation on 20th April 1972, when Japan became its first non-European full member. NEA membership today consists of 28 OECD member countries: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Luxembourg, Mexico, the Netherlands, Norway, Portugal, the Republic of Korea, the Slovak Republic, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The Commission of the European Communities also takes part in the work of the Agency. The mission of the NEA is: o to assist its member countries in maintaining and further developing, through international cooperation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes, as well as o to provide authoritative assessments and to forge common understandings on key issues, as input to government decisions on nuclear energy policy and to broader OECD policy analyses in areas such as energy and sustainable development. OECD Nuclear Energy Agency performs the work putting emphasis on safety enhancement and regulatory safety. Having Analyzed activities areas of Nuclear Development Committee (NDC), Committee on the Safety of Nuclear Installations (CSNI), Committee on Nuclear Regulatory Activities (CNRA) and drew out cooperation methods relating to nuclear safety regulation with them, it will be helpful economically and technically in meeting with improvement of nuclear safety efficiently

Nuclear fuel behavior activities at the OECD/NEA

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

The work programme regarding nuclear fuel behavior issues at OECD/NEA is carried out in two sections. The Nuclear Science and Data Bank Division deals with basic phenomena in fuel behavior under normal operating conditions, while the Safety Division concentrates upon regulation and safety issues in fuel behavior. A new task force addressing these latter issues has been set up and will produce a report providing recommendations in this field. The OECD Nuclear Energy Agency jointly with the International Atomic Energy Agency established an International Fuel Performance Experiments Database which is operated by the NEA Data Bank. (author). 1 tab.

Nuclear fuel behavior activities at the OECD/NEA

International Nuclear Information System (INIS)

1997-01-01

The work programme regarding nuclear fuel behavior issues at OECD/NEA is carried out in two sections. The Nuclear Science and Data Bank Division deals with basic phenomena in fuel behavior under normal operating conditions, while the Safety Division concentrates upon regulation and safety issues in fuel behavior. A new task force addressing these latter issues has been set up and will produce a report providing recommendations in this field. The OECD Nuclear Energy Agency jointly with the International Atomic Energy Agency established an International Fuel Performance Experiments Database which is operated by the NEA Data Bank. (author). 1 tab

The investigation of the national views for the strategic plan 2005-2009 of OECD/NEA

International Nuclear Information System (INIS)

Ko, H. S.; Ryu, J. S.; Lee, K. S.; Yang, M. H.

2004-01-01

OECD/NEA has been developing the Strategic Plan of 2005-2009 which will be used as the guidelines of NEA activities for this period. Korean government is of the view that national interests in the cooperation with OECD/NEA become important and are needed to be reflected to this Strategic Plan. We has prepared and suggested Korean proposal for the Strategic Plan of OECD/NEA

Enhancement of international cooperation for utilization of OECD/NEA Data BAnk

International Nuclear Information System (INIS)

Lee, HaeCho; Chang, JongHwa; Kang, SinBok; Song, TaeGil; Ko, YoungChul; Kim, JinHee; Moon, DongSup; Hwang, HyeSun

2008-06-01

The purpose of research is to register Korean computer codes at OECD/NEA Data Bank and to promote cooperation on use of the computer codes and libraries between the international organization and foreign countries. - 10 computer codes related to nuclear industry have been registered at and supplied to OECD/NEA through this project, which is regarded as good example of close international cooperation among the member states of OECD/NEA - This project has provided member states with motives on creating human networks and high level of expertise between domestic code developers and foreign users of the codes - Expert group in the field of nuclear related computer codes is formed in this project, that is also beneficial for Korea in preparation of exporting and marketing nuclear technologies in the world

Enhancement of international cooperation for utilization of OECD/NEA Data BAnk

Energy Technology Data Exchange (ETDEWEB)

Lee, HaeCho; Chang, JongHwa; Kang, SinBok; Song, TaeGil; Ko, YoungChul; Kim, JinHee; Moon, DongSup; Hwang, HyeSun

2008-06-15

The purpose of research is to register Korean computer codes at OECD/NEA Data Bank and to promote cooperation on use of the computer codes and libraries between the international organization and foreign countries. - 10 computer codes related to nuclear industry have been registered at and supplied to OECD/NEA through this project, which is regarded as good example of close international cooperation among the member states of OECD/NEA - This project has provided member states with motives on creating human networks and high level of expertise between domestic code developers and foreign users of the codes - Expert group in the field of nuclear related computer codes is formed in this project, that is also beneficial for Korea in preparation of exporting and marketing nuclear technologies in the world.

Proceedings of the Second Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs, 23-25 September 2014, OECD-NEA HQ

International Nuclear Information System (INIS)

Massara, S.; ); Bragg-Sitton, Shannon; Pasamehmetoglu, K.; Yang, Jae Ho; Dolley, Evan J.; Rebak, Raul B.; Sowder, Andrew; Cheng, Bo; Kurata, Masaki; Van Nieuwenhove, Rudi; Li, R.; McClellan, Ken; Nelson, Andy; Carmack, Jon; Harp, Jason; Finck, Phillip; ); Kakicuhi, K.

2014-09-01

Under the guidance of the OECD-NEA Nuclear Science Committee, the expert group acts as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance. The expert group focusses on the fundamental properties and behaviour under normal operations and accident conditions for advanced core materials and components (fuels, cladding, control rods, etc.). The materials considered are applicable to Gen II and Gen III Light Water Reactors, as well as Gen III+ reactors under construction. The objective of the expert group is to define and coordinate a programme of work to help advance the scientific knowledge needed to provide the technical underpinning for the development of advanced LWR fuels with enhanced accident tolerance compared to currently used zircaloy/UO 2 fuel systems, as well as other non-fuel core components with important roles in LWR performance under accident conditions. This document brings together the available presentations (slides) given at the Second Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs. Content: 1 - Proposed Agenda; 2 - Expert Group meeting - 23 September 2014: - Introduction and background (S. Massara, OECD-NEA) - Expected outcomes from the TFs meetings scheduled on 24-25 September (K. Pasamehmetoglu, EG Chair, INL); 3 - Task Force 1 (Systems assessment) meeting - 24 September 2014: - Metrics for the Evaluation of LWR Accident Tolerant Fuel (S. Bragg-Sitton, INL); 4 - Task Force 2 (Cladding/core materials) meeting - 24 September 2014: - Summary on SiC Task Force 2 (Clad) meeting (J.H. Yang, KAERI); - Accident Tolerant Advanced Steels Cladding for Commercial Light Water Reactors (E. Dolley, GE); - Molybdenum-Alloy Fuel Cladding Development and Testing - Update from April 2014 NEA ATF Meeting (A. Sowder, EPRI); - Accident Tolerant Control Rod Development in Japan (M. Kurata, JAEA); - IFA-774: The first in-pile test with coated fuel rods (R. Van

Lessons learned from OECD/CSNI ISP on small break LOCA: final report

International Nuclear Information System (INIS)

1996-07-01

This document presents an overview of the results obtained from five recent OECD/CSNI International Standard Problems (ISPs) dealing with phenomenologies typical of Small Break LOCA in PWR nuclear power plants of western design. The experiment in four Integral test Facilities, Lobi, Spes, Bethsy and Lstf and the recorded data from a steam generator tube rupture transient in the Belgian PWR of Doel, were taken as reference for the calculations. Relevant hardware characteristics of the facilities and of the plant are firstly given, including the correlation between key thermalhydraulic phenomena and the reference experimental scenarios. A statistical evaluation of the general data connected with each ISP is then presented. The lessons learned from the ISPs are then considered. Four areas have been identified: code deficiencies and capabilities, scaling of the data, progress in code capabilities and various additional aspects

Analysis of OECD/CSNI ISP-42 phase A PANDA experiment using coupled code R5G (RELAP5-GOTHIC)

International Nuclear Information System (INIS)

Bencik, V.; Debrecin, N.; Grgic, D.; Bajs, T.

2010-01-01

In the paper, the results of the analysis of OECD/CSNI ISP-42 Phase A experiment at PANDA facility using stand-alone codes RELAP5/mod3.3 and GOTHIC 7.2b as well as coupled code R5G (RELAP5/mod3.3-GOTHIC 7.2b) are presented. PANDA is a large-scale thermal-hydraulic test facility installed at PSI (Paul Scherrer Institute) in Switzerland. The OECD/CSNI ISP-42 test consists of six sequential phases (Phase A through F). The present work deals with the post-test calculation of the Phase A, including the break of the main steam line and the Passive Containment Cooling (PCC) System Start-Up. The objective of the test is to investigate the start-up phenomenology of passive cooling system when steam is injected into cold vessel filled with air. The calculation was performed using stand-alone RELAP5/mod3.3 and GOTHIC 7.2b models, and then the same calculation was performed using coupled code with RELAP5 being responsible for reactor part of the model and GOTHIC being responsible for containment part of the model. The prediction capability, running time and modeling aspects were discussed for all three cases. (authors)

OECD/NEA activities on the safety of new reactors

International Nuclear Information System (INIS)

Reig, Javier

2010-01-01

The Nuclear Energy Agency, a member of the OECD family, has as mission, in line with the overall aim of the OECD, to assist Agency's member countries in maintaining and further developing through international cooperation, the scientific, technological and legal bases for a safe, environmentally friendly and economic use of nuclear energy for peaceful purposes. Our members include very advanced nuclear countries and represent a big part of the world's nuclear capacity. In addition, we have a well established and formal relationship with the Russian Federation and the IAEA. Two years ago, the NEA celebrated its 50th anniversary of providing assistance to its member countries in supporting the safe use of nuclear power. Nuclear power will remain a key part of the energy mix for many decades to come and, as such, the NEA looks forward to continuing its value-adding work in the field of nuclear power. Korea joined the NEA in 24 May, 1993. While the NEA is satisfied that we have in place an effective process of work, we are always looking for ways to improve. This is the reason why we have since 1999 a series of strategic plans in order to better focus on the objectives that member countries assign to the Agency for meeting the economical, environmental and societal challenges of the coming years. The important changes that have occurred in the energy and nuclear landscapes, as well as in the OECD framework, are the basis for these revisions insofar as they influence the NEA's role and activities. We are now completing the process for the new Strategic Plan which will apply from 2011 to 2017. Nuclear safety and regulation is and will continue to be the first priority of the Agency. The NEA will assist member countries to continue sharing information, best practices and lessons learned to enhance nuclear safety worldwide

Thermal cycling in LWR components in OECD-NEA member countries - CSNI integrity and ageing working group

International Nuclear Information System (INIS)

Faidy, Claude; Chapuliot, Stephane; Mathet, Eric

2005-01-01

Thermal cycling is a widespread and recurring problem in nuclear power plants worldwide. Several incidents with leakage of primary water inside the containment challenged the integrity of NPPs although no release outside of containment occurred. Thermal cycling was not taken into account at the design stage. Regulatory bodies, utilities and researchers have to address it for their operating plants. It is a complex phenomenon that involves and links thermal hydraulic, fracture mechanic, materials and plant operation. Thermal cycling is connected either to operating transients (low cycle fatigue) or to complex phenomenon like stratification, vortex and mixing (low and high cycle fatigue). The former is covered by existing rules and codes. The latter is partially addressed by national rules and constitutes the subject of this report. In 2002, the Committee on the Safety of Nuclear Installations (CSNI) requested the working group on the integrity of reactor components and structures (IAGE WG) to prepare a program of work on thermal cycling to provide information to NEA member countries on operational experience, regulatory policies, countermeasures in place, current status of research and development, and to identify areas where research is needed both at national and international levels. The working group proposed a 3 fold program that covered: - Review of operating experience, regulatory framework, countermeasures and current research; - Benchmark to assess calculation capabilities in NEA member countries for crack initiation and propagation under a cyclic thermal loading, and ultimately to develop screening criteria to identify susceptible components; results of the benchmark were published in 2005; - Organisation of an international conference in cooperation with the EPRI and the USNRC on fatigue of reactor components. This conference reviews progress in the areas and provides a forum for discussion and exchange of information between high level experts. The

OECD/NEA component operational experience, degradation and ageing project

International Nuclear Information System (INIS)

Gott, K.; Nevander, O.; Riznic, J.; Lydell, B.

2015-01-01

Several OECD Member Countries have agreed to establish the OECD/NEA 'Component Operational Experience, Degradation and Ageing Programme' (CODAP) to encourage multilateral co-operation in the collection and analysis of data relating to degradation and failure of metallic piping and non-piping metallic passive components in commercial nuclear power plants. The scope of the data collection includes service-induced wall thinning, part through-wall cracks, through-wall cracks with and without active leakage, and instances of significant degradation of metallic passive components, including piping pressure boundary integrity. CODAP is the continuation of the 2002-2011 'OECD/NEA Pipe Failure Data Exchange Project' (OPDE) and the Stress Corrosion Cracking Working Group of the 2006-2010 - OECD/NEA SCC and Cable Ageing project - (SCAP). OPDE was formally launched in May 2002. Upon completion of the 3. Term (May 2011), the OPDE project was officially closed to be succeeded by CODAP. In May 2011, 13 countries signed the CODAP first Term agreement. The first Term (2011-2014) work plan includes the development of a web-based relational event database on passive, metallic components in commercial nuclear power plants, a web-based knowledge base on material degradation, codes and standards relating to structural integrity and national practices for managing material degradation. The work plan also addresses the preparation of Topical Reports to foster technical cooperation and to deepen the understanding of national differences in ageing management. These Topical Reports are in the public domain and available for download on the NEA web site. Published in 2014, a first Topical Report addressed flow accelerated corrosion (FAC) of carbon steel and low alloy steel piping. A second Topical Report addresses operating experience with electro-hydraulic control (EHC) and instrument air (IA) system piping

ISP 22 OECD/NEA/CSNI International standard problem n. 22. Evaluation of post-test analyses

International Nuclear Information System (INIS)

1992-07-01

The present report deals with the open re-evaluation of the originally double-blind CSNI International Standard Problem 22 based on the test SP-FW-02 performed in the SPES facility. The SPES apparatus is an experimental simulator of the Westinghouse PWR-PUN plant. The test SP-FW-02 (ISP22) simulates a complete loss of feedwater with delayed injection of auxiliary feedwater. The main parts of the report are: outline of the test facility and of the SP-FW-02 experiment; overview of pre-test activities; overview of input models used by post-test participants; evaluation of participant predictions; evaluation of qualitative and quantitative code accuracy of pre-test and post-test calculations

Proceedings of the Joint IAEA/CSNI Specialists' Meeting on Fracture Mechanics Verification by Large-Scale Testing

International Nuclear Information System (INIS)

1993-10-01

This report provides the proceedings of a Specialists' Meeting on Fracture Mechanics Verification by Large-Scale Testing that was held in Oak Ridge, Tennessee, on October 23-25, 1992. The meeting was jointly sponsored by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development. In particular, the International Working Group (IWG) on Life Management of Nuclear Power Plants (LMNPP) was the IAEA sponsor, and the Principal Working Group 3 (PWG-3) (Primary System Component Integrity) of the Committee for the Safety of Nuclear Installations (CSNI) was the NEA's sponsor. This meeting was preceded by two prior international activities that were designed to examine the state-of-the-art in fracture analysis capabilities and emphasized applications to the safety evaluation of nuclear power facilities. The first of those two activities was an IAEA Specialists' Meeting on Fracture Mechanics Verification by Large-Scale Testing that was held at the Staatliche Materialprufungsanstalt (MPA) in Stuttgart, Germany, on May 25-27, 1988; the proceedings of that meeting were published 1991.1 The second activity was the CSNI/PWG-3's Fracture Assessment Group's Project FALSIRE (Fracture Analyses of Large-Scale International Reference Experiments). The proceedings of the FALSIRE workshop that was held in Boston, Massachusetts, U.S.A., on May 8-10, 1990, was recently published by the Oak Ridge National Laboratory (ORNL). Those previous activities identified capabilities and shortcomings of various fracture analysis methods based on analyses of six available large-scale experiments. Different modes of fracture behavior, which ranged from brittle to ductile, were considered. In addition, geometry, size, constraint and multiaxial effects were considered. While generally good predictive capabilities were demonstrated for brittle fracture, issues were identified relative to predicting fracture behavior at higher

Source term assessment, containment atmosphere control systems, and accident consequences. Report to CSNI by an OECD/NEA Group of experts

International Nuclear Information System (INIS)

1987-04-01

CSNI Report 135 summarizes the results of the work performed by CSNI's Principal Working Group No. 4 on the Source Term and Environmental Consequences (PWG4) during the period extending from 1983 to 1986. This document contains the latest information on some important topics relating to source terms, accident consequence assessment, and containment atmospheric control systems. It consists of five parts: (1) a Foreword and Executive Summary prepared by PWG4's Chairman; (2) a Report on the Technical Status of the Source Term; (3) a Report on the Technical Status of Filtration and Containment Atmosphere Control Systems for Nuclear Reactors in the Event of a Severe Accident; (4) a Report on the Technical Status of Reactor Accident Consequence Assessment; (5) a list of members of PWG4

The study for effective utilization on the nuclear information of OECD/NEA

International Nuclear Information System (INIS)

Ko, H. S.; Oh, K. B.; Lee, H. M.

2001-01-01

As a group of nuclear-advanced countries, the OECD/NEA mainly deals with the aspects of science and technology and future policy of nuclear energy. It is very important for us to develop nuclear advanced technology and enhance the global environemnt of nuclear utilization and development through the OECD/NEA. It is required for us to timely obtain and analyse the up-to-date nuclear technology information and to build up a system to collect and distribute nuclear technology information from NEA committees. In this study, measures for effective utilization of the NEA information have been established through the analysis of the activities of the experts meeting in each standing technical committee and of technology information. In this regard, it is also developed a homepage to disseminate reports from NEA Committees participants as one of the strengthening measures

OECD/NEA Study on the Economics of Long Term Operation of NPP

International Nuclear Information System (INIS)

Lokhov, Alexey; Cameron, Ron

2012-01-01

The OECD Nuclear Energy Agency (NEA) established the Ad Hoc expert group on the Economics of Long-term Operation (LTO) of Nuclear Power Plants. The primary aim of this group is to collect and analyse technical and economic data on the upgrade and lifetime extension experience in OECD countries, and to assess the likely applications for future extensions. This paper describes the key elements of the methodology of economic assessment of LTO and initial findings for selected NEA member countries. (author)

Proceedings of the Start-up Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs, 28-29 April 2014, OECD-NEA HQ

International Nuclear Information System (INIS)

Kurata, Masaki; Bragg-Sitton, Shannon; Pasamehmetoglu, K.; Sowder, Andrew; Koo, Yang-Hyun; Yang, Jae-Ho; Kim, Hyun-Gil; Zhou, Y.; Forgeron, T.; Guedeney, Ph.; Brachet, J.C.; Michaux, A.; Chauvin, Nathalie; Waeckel, N.; Ambard, A.; Blanpain, P.; Bischoff, J.; Zvonarev, Yu.; Verwerft, M.; Weber, M.; Lambrinou, K.; Koonen, E.; Van Dyck, S.; PETIT, Marc; Cornet, Stephanie; ); YAMAJI, Akifumi; ); Inozemtsev, V.; )

2014-04-01

Expert Group meeting on ATF for LWR's (M. Verwerft, SCK-CEN); 4 - Potential links with other related activities: - Recent and Current Activities of the Working Group on Fuel Safety - NEA/CSNI (M. Petit, IRSN); - Nuclear Science Committee Working Party on Scientific Issues of the Fuel Cycle, Activities on Innovative Fuels - EGIF (S. Massara for S. Cornet, OECD-NEA); - NSC/WPRS Activities on Reactor Fuel Performance (EGRFP) and IFPE database (J. Gulliford for A. Yamaji, OECD-NEA); - IAEA Coordinated Research Projects (CRP) in the area of Fuel Engineering and ATF plans (V. Inozemtsev, IAEA); 5 - Collaborative framework: Outcome of the discussion on Task Forces to be constituted within this Expert Group and Preliminary list of actions agreed during the meeting. 6 - Documents shared during the meeting by S. Bragg-Sitton (INL): - Advanced Fuels Campaign, Light Water Reactor Accident Tolerant Fuel Performance Metrics (DoE Report); - Development of advanced accident tolerant fuels for commercial LWRs (S. Bragg-Sitton, Nuclear News, March 2014, p. 83-91); 7 - Documents shared during the meeting by K. Terrani (ORNL) from a special issue of 'Journal of Nuclear Materials' on Accident Tolerant Fuels for LWRs (no. 448, 2014): - Forward for special JNM issue on accident tolerant fuels for LWRs (Preface); - Accident tolerant fuels for LWRs: A perspective (S.J. Zinkle et al.); - Silicon carbide composite for light water reactor fuel assembly applications (Ken Yueh, Kurt A. Terrani); - Stability of SiC-matrix microencapsulated fuel constituents at relevant LWR conditions (L.L. Snead et al.); - Preparation of UC 0.07-0.10 N 0.90-0.93 spheres for TRISO coated fuel particles (R.D. Hunt et al.); - Carbothermic synthesis of 820 lm uranium nitride kernels: Literature review, thermodynamics, analysis, and related experiments (T.B. Lindemer et al.); - Fission product release and survivability of UN-kernel LWR TRISO fuel (T.M. Besmann et al.); - Advanced oxidation-resistant iron

Overview of CSNI separate effects tests validation matrix

Energy Technology Data Exchange (ETDEWEB)

Aksan, N. [Paul Scherrer Institute, Villigen (Switzerland); Auria, F.D. [Univ. of Pisa (Italy); Glaeser, H. [Gesellschaft fuer anlagen und Reaktorsicherheit, (GRS), Garching (Germany)] [and others

1995-09-01

An internationally agreed separate effects test (SET) Validation Matrix for thermal-hydraulic system codes has been established by a sub-group of the Task Group on Thermal Hydraulic System Behaviour as requested by the OECD/NEA Committee on Safety of Nuclear Installations (SCNI) Principal Working Group No. 2 on Coolant System Behaviour. The construction of such a Matrix is an attempt to collect together in a systematic way the best sets of openly available test data for code validation, assessment and improvement and also for quantitative code assessment with respect to quantification of uncertainties to the modeling of individual phenomena by the codes. The methodology, that has been developed during the process of establishing CSNI-SET validation matrix, was an important outcome of the work on SET matrix. In addition, all the choices which have been made from the 187 identified facilities covering the 67 phenomena will be investigated together with some discussions on the data base.

Second OECD (NEA) CSNI specialist meeting on molten core debris-concrete interactions

International Nuclear Information System (INIS)

Alsmeyer, H.

1992-11-01

The 37 contributions concentrated on two main topics. The first topic is the 'classical' core debris-concrete interaction, both experimental and theoretical. Integral effects and separate effects were addressed in thermal hydraulics and heat transfer, material interaction, and aerosol release during concrete erosion, with some applications to prototypical nuclear power plants. The second topic is the possibility of controlling and ending the erosion of the concrete by spreading of the core melt, and/or achieving coolability by the addition of water. (orig./HP) [de

Future direction for implementing the cooperation with OECD/NEA

International Nuclear Information System (INIS)

Kim, Kyoung Pyo; Hong, Yong Don

1999-03-01

The Nuclear Energy Agency (NEA) within the Organization for Economic Cooperation and Development (OECD) ia an intergovernmental organization consisting of industrialized countries with shared democratic principles and free market economics. The objectives of the agency are to identify key issues related to nuclear energy and to address these issues as well as to implement joint R and D projects, contributing to the development of nuclear energy as a safe, environmentally-acceptable and economical energy source through cooperation among its participating countries. Appropriate measures to effectively implement international nuclear cooperation and strategies to upgrade Korea's status in the international arena as well as ways to utilize the agency for our benefits through analysis of its policy and current status of the agency as a multilateral nuclear cooperative body are also presented in this report. Analysis of information about the agency's activities and acquisition of capabilities to collect relevant information, coupled with efforts to enhance Korea's status in the international nuclear arena by actively being involved in the international organizations such as OECD/NEA are required to positively deal with rapid changes in the international nuclear arena and establish effective national nuclear policies. This report can be utilized as valuable material not only in establishing national nuclear policy by giving an overview of the report prepared by the high level advisory group on the future of the OECD Nuclear Energy Agency, who recently wrapped up their activities, but also in promoting the understanding of the agency's activities and the agency's long-term perspective mapped out in 1995. Future plans and strategies for effective implementation of nuclear cooperation with the agency, including ways to participate in the agency's activities, with KAERI taking a leading role, and in the NEA joint R and D projects, ways to strengthen capabilities, to analyze

Overview of the burnup credit activities at OECD/NEA/NSC

International Nuclear Information System (INIS)

Brady Raap, M.C.; Nomura, Y.; Sartori, E.

2001-01-01

This article summarizes activities of the OECD/NEA Burnup Credit Expert Panel, a subordinate group to the Working Party on Nuclear Criticality Safety (WPNCS). The WPNCS of the OECD/NEA coordinates and carries out work in the domain of criticality safety at the international level. Particular attention is devoted to establishing sound databases required in this area and to addressing issues of high relevance such as burnup credit. The activities of the expert panel are aimed toward improving safety and identifying economic solutions to issues concerning the back-end of the fuel cycle. The main objective of the activities of the OECD/NEA Burnup Credit Expert Panel is to demonstrate that the available criticality safety calculational tools are appropriate for application to burned fuel systems and that a reasonable safety margin can be established. The method established by the expert panel for investigating the physics and predictability of burnup credit is based on the specification and comparison of calculational benchmark problems. A wide range of fuel types, including PWR, BWR, MOX, and VVER fuels, has been or are being addressed by the expert panel. The objective and status of each of these benchmark problems is reviewed in this article. It is important to note that the focus of the expert panel is the comparison of the results submitted by each participant to assess the capability of commonly used code systems, not to quantify the physical phenomena investigated in the comparisons or to make recommendations for licensing action. (author)

Proceedings of the specialist meeting on safety performance indicators

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-05-28

In 1998, the OECD/NEA committee on Nuclear Regulatory Activities (CNRA) initiated an activity with the objective of advancing the discussion on how to enhance and measure regulatory effectiveness in relation to nuclear installations. One of the outcome of this activity was to establish a Task group to develop internal (direct) performance indicators which would be used to monitor regulatory efficiency. On the initiative of the NEA/CSNI Working Group on Operating Experience the Spanish CSN hosted a workshop (Madrid, 2000) to review the state of the art on Safety Performance Indicators. This workshop, which was co-sponsored by the IAEA and WANO was attended by 73 participants from 19 countries, representing the industry, regulators, service companies as well as international organisations. The conclusions were: 1. there is considerable development effort on performance indicators in many countries; 2. utilities continue to rely on the WANO Performance indicators system which consists of indicators in 8 key areas and receives data from virtually all commercial NPP's in the world; 3. Regulators do not have a common set of performance indicators. This document gathers the 25 presentations given during this workshop. After this workshop, a joint CNRA/CSNI task group was launched in December 2000 to exchange information and develop external (indirect) indicators to measure regulatory effectiveness, i.e. impact on licensee's safety performance. These external indicators are, in other words, the traditional plant performance indicators (PI's). The task force consisted of regulators, organisations which have a performance indicators system in operation or under testing. The task force met in Paris on February 19-20, 2001 and the work performed by the group is summarized in a report (NEA-CSNI-R--2001-11) attached in appendix to these proceedings.

Proceedings of the specialist meeting on safety performance indicators

International Nuclear Information System (INIS)

2002-01-01

In 1998, the OECD/NEA committee on Nuclear Regulatory Activities (CNRA) initiated an activity with the objective of advancing the discussion on how to enhance and measure regulatory effectiveness in relation to nuclear installations. One of the outcome of this activity was to establish a Task group to develop internal (direct) performance indicators which would be used to monitor regulatory efficiency. On the initiative of the NEA/CSNI Working Group on Operating Experience the Spanish CSN hosted a workshop (Madrid, 2000) to review the state of the art on Safety Performance Indicators. This workshop, which was co-sponsored by the IAEA and WANO was attended by 73 participants from 19 countries, representing the industry, regulators, service companies as well as international organisations. The conclusions were: 1. there is considerable development effort on performance indicators in many countries; 2. utilities continue to rely on the WANO Performance indicators system which consists of indicators in 8 key areas and receives data from virtually all commercial NPP's in the world; 3. Regulators do not have a common set of performance indicators. This document gathers the 25 presentations given during this workshop. After this workshop, a joint CNRA/CSNI task group was launched in December 2000 to exchange information and develop external (indirect) indicators to measure regulatory effectiveness, i.e. impact on licensee's safety performance. These external indicators are, in other words, the traditional plant performance indicators (PI's). The task force consisted of regulators, organisations which have a performance indicators system in operation or under testing. The task force met in Paris on February 19-20, 2001 and the work performed by the group is summarized in a report (NEA-CSNI-R--2001-11) attached in appendix to these proceedings

OECD/NEA study on the economics of the long-term operation of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lokhov, A.; Cameron, R. [OECD Nuclear Energy Agency, 12, boulevard des Iles, 92130 Issy-les-Moulineaux (France)

2012-07-01

The OECD Nuclear Energy Agency (NEA) established the Ad hoc expert group on the Economics of Long-term Operation (LTO) of Nuclear Power Plants. The primary aim of this group is to collect and analyse technical and economic data on the upgrade and lifetime extension experience in OECD countries, and to assess the likely applications for future extensions. This paper describes the key elements of the methodology of economic assessment of LTO and initial findings for selected NEA member countries. (authors)

Proceedings of the Third Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs, 3-5 March 2015, OECD-NEA HQ

International Nuclear Information System (INIS)

Bischoff, Jeremy; Gandrille, Pascal; Forgeron, Thierry; Brachet, Jean-Christophe; Lorrette, Christophe; Valot, C.; Freyss, M.; Braun, J.; Sauder, C.; Moatti, Marie; Waeckel, Nicolas; Ambard, Antoine; Pasamehmetoglu, Kemal; Johnston, Emma; Bragg-Sitton, Shannon M.; Kurata, M.; Hallstadius, Lars; Ohta, H.; Ogata, T.; Besmann, T.; Chauvin, Nathalie; Cornet, Stephanie; Massara, S.; Kohyama, Akira; Kishimoto, Hirotatsu; Park, Joon Soo; Nakazato, Naofumi; Hayasaka, Daisuke; Asakura, Yuuki; Kanda, Chisato; Kohyama, Akira; Terrani, Kurt; Katoh, Yutai; Yamamoto, Yukinori; Field, Kevin; Snead, Lance; Hu, Xunxiang; Dryepondt, Sebastien; Unocic, Kinga A.; Hoelzer, David T.; Pint, Bruce A.; Besmann, T.; Steinbrueck, M.; Grosse, M.; Jianu, A.; Weisenburger, A.; Avincola, V.; Ahmad, S.; Tang, C.; Heuser, Brent J.; Sickafus, Kurt; Kim, Hyun-Gil; Kim, Il-Hyun; Jung, Yang-Il; Park, Dong-Jun; Park, Jung-Hwan; Park, Jeong-Yong; Koo, Yang-Hyun; Lee, B.O.; Van Nieuwenhove, Rudi; Kim, Young; Rebak, Raul; Dolly, Evan; Dolley, E.J.; Rebak, R.B.; Maloy, Stu; Yang, Jae-Ho; Kim, Dong-Joo; Kim, Keon-Sik; Koo, Yang-Hyun; Lee, Won Jae; Tulenko, James S.; Puide, Mattias; Liu, T.; Gueneau, C.; Gosse, S.; Dupin, N.; Barber, D.; Corcoran, E.; Dumas, J.C.; Hania, R.; Kaye, M.; Turchi, P.

2015-03-01

Under the guidance of the OECD-NEA Nuclear Science Committee, the expert group acts as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance. The expert group focusses on the fundamental properties and behaviour under normal operations and accident conditions for advanced core materials and components (fuels, cladding, control rods, etc.). The materials considered are applicable to Gen II and Gen III Light Water Reactors, as well as Gen III+ reactors under construction. The objective of the expert group is to define and coordinate a programme of work to help advance the scientific knowledge needed to provide the technical underpinning for the development of advanced LWR fuels with enhanced accident tolerance compared to currently used zircaloy/UO 2 fuel systems, as well as other non-fuel core components with important roles in LWR performance under accident conditions. This document brings together the available presentations (slides) given at the Third Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs. Content: 1 - Task Force 1 (Systems assessment) meeting, 3-4 March 2015: - French evaluation of ATF Concepts (J. Bischoff, AREVA); - Technology Readiness Levels - TRL - for Fuels (K. Pasamehmetoglu, INL); - TRL-definition for advanced fuel concept applied for commercial LWRs in Japan (M. Kurata, JAEA); - Application of TRLs in NNL (E. Johnston, NNL); - Technology Readiness Levels for Advanced Nuclear Fuel and Materials (S. Bragg-Sitton, INL); 1a - Definition of the illustrative scenarios: - AREVA's proposal concerning scenario for Accident Tolerant Fuel studies (P. Gandrille); - A Simplified Accident Scenario (L. Hallstadius); - Accident Scenarios for ATF Performance Evaluation of BWR and PWR in Japan (H. Ohta, CRIEPI); 1b - Related NEA activities: - Working Party on Multi-scale Modelling of Fuels and Structural Materials for Nuclear Systems - WPMM, Expert

The OECD/NEA Data Bank, its computer program services and benchmarking activities

International Nuclear Information System (INIS)

Sartori, E.; Galan, J.M.

1998-01-01

The OECD/NEA Data Bank collects, tests and distributes computer programs and numerical data in the field of nuclear energy applications. This activity is coordinated with several similar centres in the United States (ESTSC, NNDC, RSIC) and outside the OECD area through an arrangement with the IAEA. This information is shared worldwide for the benefit of scientists and engineers working on the safe and economic use of nuclear energy. The OECD/NEA Nuclear Science Committee the supervising body of the Data Bank has conducted a series of international computer code benchmark exercises with the aim of verifying the correctness of codes, of building confidence in models used for predicting macroscopic behaviour of nuclear systems and to drive towards refinement of models where necessary. Exercises involving nuclear cross section predictions, in-core reactor physics issues, such as pin cells for different type of reactors, plutonium recycling, reconstruction of pin power within assemblies, core transients, reactor shielding and dosimetry, away from reactor issues such as criticality safety for transport and storage of spent fuel, shielding of radioactive material packages and other problems connected with the back end of the fuel cycle, are listed and the relevant references provided. (author)

Activities of the OECD/NEA Data Bank and its computer program service

International Nuclear Information System (INIS)

Sartori, E.

1991-01-01

The OECD/NEA Data Bank collects, tests and distributes computer programs and numerical data in the field of nuclear energy applications. This activity is coordinated with several similar centres in the United States (NESC, NNDC, RSIC) and outside the OECD are through an arrangement with the IAEA. This valuable information is shared worldwide for the benefit of scientists and engineers working on the safe and economic use of nuclear energy for peaceful applications. This article covers mainly the activities of the computer program service. (author). 4 figs

The role of the NEA incident reporting system in trend and pattern studies

International Nuclear Information System (INIS)

Ishack, G.; Iwabuchi, H.

1990-01-01

When the Incident Reporting System of the OECD Nuclear Energy Agency (NEA-IRS) was first instituted in 1980, Members recognized the fact that since the data thus collected only pertains to significant safety-related incidents, the system cannot be used for in-depth statistical analyses. Rather, the NEA-IRS is best suited, in addition to single event assessments, to studies that provide indications related to system, component or human performance; these indications could also initiate trend analyses on more complete data bases. Examples are the generic studies on the Loss of Containment Functions (completed last year) and the Loss of Residual Heat Removal (due for completion this year), and the studies related to the human factor. Another type of use of the IRS data was started last year by the NEA Principal Working Group 1 on Operating Experience and Human Factors (PWG 1) in response to the encouragement of the OECD/NEA Committee on the Safety of Nuclear Installations (CSNI), to make the best use of Operating Experience, notably of information disseminated through the NEA-IRS. These applications consisted of scanning the IRS data base for events that could be of interest to specialized domains such as radiation protection, fracture mechanics and fire protection. In the paragraphs which follow, some highlights of the results of these scans are presented (reference is made at the end of this paper to the reports detailing the results of these applications)

Activities of the OECD-NEA in the field of fast reactors

International Nuclear Information System (INIS)

Royen, J.

1977-01-01

The OECD-NEA is performing the following activities in the field of fast reactors: Held ad hoc meetings of senior experts on safety, development and economics of LMFBR type reactors; publishing a Nuclear Safety Research Index (the index is now expanded to cover fast reactors) and distribution; collect test computer programmes, as well as neutron data

Operating experience relating to on-site electric power sources. Proceedings of a Specialist Meeting

International Nuclear Information System (INIS)

1986-02-01

The reliability of on-site electric power sources of nuclear power plants usually consisting of diesel generators, gas turbine generators and DC power sources, has been a matter of concern during reactor operations. The frequent recurrence and the important consequences of failures relating to on-site electric power sources have led to a general consensus that they form one of the most significant features influencing the total performance of the safety Systems. This has also been confirmed by surveys performed on the incidents reported through the NEA Incident Reporting System (IRS). Accordingly, a recommendation to organise a Specialist Meeting on the subject was made at the third annual meeting of CSNI Principal Working Group No. 1 (Operating Experience and Human Factors). At the 12. meeting of the CSNI held in November 1984. the Committee endorsed the proposal and accepted an offer by the United Kingdom to host and organise the Specialist Meeting. The Specialist Meeting, sponsored by the CSNI, was held in London, United Kingdom from 16 to 18 October 1985. It was hosted by H.M. Nuclear Installations Inspectorate of the Health and Safety Executive. The purpose of the meeting was to promote the exchange of Information on operating experience relating to on-site electric power sources and to look for measures to further improve their reliability In the areas of design, operation and licensing. The meeting was organised by a Programme Group which included nominated members of CSNI PWG No. 1. the Programme Group met in May and June 1985 in Paris to agree on the programme and practical arrangements for the meeting. As a result of the review of the abstracts which had been contributed in response to the Call for Papers, 28 papers were accepted for presentation during the meeting. Approximately 60 delegates from 13 Member countries, and the NEA Secretariat, attended the meeting. Session summaries prepared by the respective session chairmen are Included prior to the

Operating experience relating to on-site electric power sources. Proceedings of a Specialist Meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-02-15

The reliability of on-site electric power sources of nuclear power plants usually consisting of diesel generators, gas turbine generators and DC power sources, has been a matter of concern during reactor operations. The frequent recurrence and the important consequences of failures relating to on-site electric power sources have led to a general consensus that they form one of the most significant features influencing the total performance of the safety Systems. This has also been confirmed by surveys performed on the incidents reported through the NEA Incident Reporting System (IRS). Accordingly, a recommendation to organise a Specialist Meeting on the subject was made at the third annual meeting of CSNI Principal Working Group No. 1 (Operating Experience and Human Factors). At the 12. meeting of the CSNI held in November 1984. the Committee endorsed the proposal and accepted an offer by the United Kingdom to host and organise the Specialist Meeting. The Specialist Meeting, sponsored by the CSNI, was held in London, United Kingdom from 16 to 18 October 1985. It was hosted by H.M. Nuclear Installations Inspectorate of the Health and Safety Executive. The purpose of the meeting was to promote the exchange of Information on operating experience relating to on-site electric power sources and to look for measures to further improve their reliability In the areas of design, operation and licensing. The meeting was organised by a Programme Group which included nominated members of CSNI PWG No. 1. the Programme Group met in May and June 1985 in Paris to agree on the programme and practical arrangements for the meeting. As a result of the review of the abstracts which had been contributed in response to the Call for Papers, 28 papers were accepted for presentation during the meeting. Approximately 60 delegates from 13 Member countries, and the NEA Secretariat, attended the meeting. Session summaries prepared by the respective session chairmen are Included prior to the

Nuclear model codes and related software distributed by the OECD/NEA Data Bank

International Nuclear Information System (INIS)

Sartori, E.

1993-01-01

Software and data for nuclear energy applications is acquired, tested and distributed by several information centres; in particular, relevant computer codes are distributed internationally by the OECD/NEA Data Bank (France) and by ESTSC and EPIC/RSIC (United States). This activity is coordinated among the centres and is extended outside the OECD area through an arrangement with the IAEA. This article covers more specifically the availability of nuclear model codes and also those codes which further process their results into data sets needed for specific nuclear application projects. (author). 2 figs

The contribution of the CSNI Principal Working Group on Confinement of Accidental Radioactive Releases to the technical consensus and spreading of knowledge on severe accidents

International Nuclear Information System (INIS)

De Boeck, B.; Royen, J.

1999-01-01

The Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) is an international committee made up of scientists and engineers. It was set up 1973 to develop and co-ordinate the activities of the NEA concerning the technical aspects of the design, construction and operation of nuclear installations insofar as they affect the safety of such installations. The Committee's purpose is to foster international cooperation in nuclear safety amongst the Member countries. Five Principal Working Groups (PWG) operate under the leadership of CSNI. PWG4 is named 'Confinement of Accidental Radioactive Releases' and its main activities are State of the Art Reports, International Standard Problem exercises, Specialist Meetings and Technical Opinion Papers. Together with other groups of experts involved in severe accident work, PWG4 has strongly contributed to the understanding of phenomena and the development of the knowledge base in that area, to the resolution of technical issues, and to the dissemination of the results. Taking examples from the products of the work of PWG4, the paper shows how this working group fosters international co-operation in the area of severe accidents and their management, and contributes to the development of a technical consensus. (author)

Status of direct containment heating in CSNI member countries. Report of task group on ex-vessel thermal-hydraulics

International Nuclear Information System (INIS)

1989-03-01

The status of activities on direct containment heating in the light water reactor program in OECD/CSNI countries is presented. Experimental and analytical studies are reviewed. Approaches or measures are discussed for accident management in relation to direct containment heating. A discussion is given of common and diverging views among the countries based, in part, on response to a questionnaire. The key issues are discussed and recommendations are provided for future CSNI work on direct containment heating

Proceedings of the OECD/NEA/CSNI workshop on the implementation of hydrogen mitigation techniques

International Nuclear Information System (INIS)

Koroll, G.W.; Rohde, J.; Royen, J.

1997-03-01

The Workshop on the Implementation of Hydrogen Mitigation Techniques was held in Winnipeg, Manitoba,Canada from 1996 May 13 to 15. It was organized in collaboration with the Whiteshell Laboratories of Atomic Energy of Canada Limited (AECL), Ontario Hydro and the CANDU Owner's Group (COG). Sixty-five experts from twelve OECD Member countries and the Russian Federation attended the meeting. Papers presented in the sessions included topics: accident management and analysis, relevant aspects of hydrogen production, distribution and mixing, engineering, technology, possible side-effects consequences and new designs. The objectives of the Workshop were the following: to establish the state of the art of hydrogen mitigation techniques, with emphasis on igniters and catalytic recombiners; to exchange information on Member countries' strategies in managing hydrogen mitigation, and to establish dialogue as to differences in approach; to determine whether there is now an adequate technical basis for such strategies or whether more work is needed; to exchange information on future plans for implementation of hydrogen mitigation techniques

Further evaluation of the CSNI separate effect test activity

Energy Technology Data Exchange (ETDEWEB)

D`Auria, F.; Aksan, S.N.; Glaeser, H. [and others

1995-09-01

An internationally agreed Separate Effect Test (SET) Validation Matrix for the thermalhydraulic system codes has been established by a subgroup of the Task Group on Thermalhydraulic System Behaviour as requested by OECD/NEA Committee on the Safety of Nuclear Installations (CSNI) Principal Working Group No. 2 on Coolant System Behavior. The construction of such matrix constituted an attempt to collect together in a systematic way the best sets of openly available test data to select for code validation. As a final result, 67 phenomena have been identified and characterized, roughly 200 facilities have been considered and more than 1000 experiments have been selected as useful for the validation of the codes. The objective of the present paper is to provide additional evaluation of the obtained data base and to supply an a-posteriori judgement in relation to (a) the data base adequacy, (b) the phenomenon, and (c) the need for additional experiments. This has been provided independently by each of the authors. The main conclusions are that large amount of data are available for certain popular phenomena e.g. heat transfer, but data are severely lacking in more esoteric areas e.g. for characterizing phenomena such as parallel channel instability and boron mixing and transport.

Application of the Relap5-3D to phase 1 and 3 of the OECD-CSNI/NSC PWR MSLB benchmark related to TMI-1

International Nuclear Information System (INIS)

D'Auria, F.; Galassi, G.; Spadoni, A.; Hassan, Y.

2001-01-01

The Relap5-3D, the latest in the series of the Relap5 code, distinguishes from the previous versions by the fully integrated, multi-dimensional thermalhydraulic and kinetic modeling capability. It has been applied to Phase I and III of OECD-CSNI/ NSC PWR MSLB Benchmark adopting the same thermalhydraulic input deck already used with Relap5/Parcs and Relap5/Quabbox coupled codes during the previous MSLB analysis. The OECD jointly with the US NRC proposed the PWR MSLB Benchmark in order to gather a common understanding about the coupling between thermal hydraulics and neutronics, and evaluating the behavior of this transient with different coupled codes, giving emphasis to the 3-D modeling. This paper deals with the application of Relap5-3D code to phase I and III of the PWR MSLB Benchmark. The Relap5-3D is a thermal hydraulics-neutronics internally coupled code, the thermal hydraulics module is the INEEL version of Relap and the neutronics module is derived from NESTLE multi-dimension kinetics code. (author)

Differences in Approach between Nuclear and Conventional Seismic Standards with regard to Hazard Definition - CSNI Integrity And Ageing Working Group

International Nuclear Information System (INIS)

Djaoudi, Ali; Labbe, Pierre; Murphy, Andrew; Kitada, Yoshio

2008-01-01

The Committee on the safety of Nuclear Installations (CSNI) of the OECD-NEA co-ordinates the NEA activities related to maintaining and advancing the scientific and technological knowledge base of the safety of nuclear installations. The Integrity and Ageing of Components and Structures Working Group of the CSNI is responsible for work related to the development and use of methods, data and information to assess the behaviour of materials and structures. It has three sub-groups, dealing with the integrity of metal components and structures, ageing of concrete structures, and the seismic behaviour of structures. The CSNI, at its meeting in June 2003, agreed to initiate an activity aimed to identify any difference between nuclear and non-nuclear conventional standards and their potential significance with regard to seismic hazards and design methods. There was a perception, mainly in some of the European countries that nuclear seismic hazard and design standards may be lagging behind developments in similar standards for conventional facilities. Adequate answer to such perception, need the examination of the following aspects and their significance on the seismic assessment of structures and components: - The safety philosophy behind the seismic nuclear and conventional standards. - The differences in approach regarding the seismic hazard definition. - The difference in approach regarding the design and the methods of analysis. These topics are examined in this report. Appendices A to H of this report contain a brief description of the conventional and the nuclear approaches in the NEA member countries: Belgium, Canada, Czech Republic, Germany, Japan, South Korea, Spain,and USA. The following general conclusions can be drawn: - The approach adopted by the nuclear seismic standards is more conservative and more reliable (in particular for meeting the continued operation criteria) than the recommended by the currently applicable force based conventional seismic codes

OECD/NEA benchmark for time-dependent neutron transport calculations without spatial homogenization

Energy Technology Data Exchange (ETDEWEB)

Hou, Jason, E-mail: jason.hou@ncsu.edu [Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695 (United States); Ivanov, Kostadin N. [Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695 (United States); Boyarinov, Victor F.; Fomichenko, Peter A. [National Research Centre “Kurchatov Institute”, Kurchatov Sq. 1, Moscow (Russian Federation)

2017-06-15

Highlights: • A time-dependent homogenization-free neutron transport benchmark was created. • The first phase, known as the kinetics phase, was described in this work. • Preliminary results for selected 2-D transient exercises were presented. - Abstract: A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for the time-dependent neutron transport calculations without spatial homogenization has been established in order to facilitate the development and assessment of numerical methods for solving the space-time neutron kinetics equations. The benchmark has been named the OECD/NEA C5G7-TD benchmark, and later extended with three consecutive phases each corresponding to one modelling stage of the multi-physics transient analysis of the nuclear reactor core. This paper provides a detailed introduction of the benchmark specification of Phase I, known as the “kinetics phase”, including the geometry description, supporting neutron transport data, transient scenarios in both two-dimensional (2-D) and three-dimensional (3-D) configurations, as well as the expected output parameters from the participants. Also presented are the preliminary results for the initial state 2-D core and selected transient exercises that have been obtained using the Monte Carlo method and the Surface Harmonic Method (SHM), respectively.

ISP 33. OECD/NEA/CSNI International Standard Problem n. 33. Pactel natural circulation stepwise coolant inventory reduction experiment. Comparison report. Volume 1 + 2

International Nuclear Information System (INIS)

Purhonen, H.; Kouhia, J.; Holmstrom, H.

1994-12-01

This is the comparison report of the CSNI ISP n.33, which is based on a natural circulation experiment with various coolant inventories conducted in Pactel facility (Finland), a 1/305 volumetrically scaled, full-height simulator of a Russian type VVER-440 pressurized water reactor. It presents all submitted blind calculational results from different countries, using various codes (Athlet, Cathare2, etc.) and compares them with the experimental data. The Pactel facility and the ISP 33 experiment are described, and the summaries of the participants, the computer codes and the nodalizations used for the blind calculations are presented

Proceedings of the OECD/NEA/CSNI workshop on the implementation of hydrogen mitigation techniques

Energy Technology Data Exchange (ETDEWEB)

Koroll, G.W. [Atomic Energy of Canada Limited, Pinawa, Manitoba (Canada); Rohde, J. [GRS, Koln (Germany); Royen, J. [OECD NEA, Issy-les-Moulineaux (France)

1997-03-01

The Workshop on the Implementation of Hydrogen Mitigation Techniques was held in Winnipeg, Manitoba,Canada from 1996 May 13 to 15. It was organized in collaboration with the Whiteshell Laboratories of Atomic Energy of Canada Limited (AECL), Ontario Hydro and the CANDU Owner's Group (COG). Sixty-five experts from twelve OECD Member countries and the Russian Federation attended the meeting. Papers presented in the sessions included topics: accident management and analysis, relevant aspects of hydrogen production, distribution and mixing, engineering, technology, possible side-effects consequences and new designs. The objectives of the Workshop were the following: to establish the state of the art of hydrogen mitigation techniques, with emphasis on igniters and catalytic recombiners; to exchange information on Member countries' strategies in managing hydrogen mitigation, and to establish dialogue as to differences in approach; to determine whether there is now an adequate technical basis for such strategies or whether more work is needed; to exchange information on future plans for implementation of hydrogen mitigation techniques.

Overview of work at the OECD/Nea data bank for the TDB project

International Nuclear Information System (INIS)

Mompean, F.

2002-01-01

The NEA TDB Project aims at making available a comprehensive, internally consistent and quality-assured chemical thermodynamic database of selected chemical elements in order to meet the specialized modelling requirements for safety assessments of radioactive waste disposal systems. The project was initiated by the NEA in 1984 and reorganized in 1998. During the period 1984-1998 (TDB Project Phase I, TDB-I), reviews on the chemical thermodynamics for the following elements were completed: U, Am and Tc. A further review originating from TDB-I and dealing with data for Np and Pu appeared in print in May 2001. Although not strictly a part of TDB-I, a further collective publication of OECD/NEA [5] is a much-cited reference in the field of aquatic chemistry. The second phase of the TDB Project (TDB Project Phase II, TDB-II) was started in 1998 following an agreement between the following Participating Organisations. (author)

OECD-Nuclear Energy Agency. 25 years of international cooperation within the framework of the NEA

Energy Technology Data Exchange (ETDEWEB)

Stadie, Klaus B. [OECD, Paris (France). Safety and Regulation

2015-11-15

The nuclear atomic association NEA of the OECD, to which 23 western industrial countries belong to, was established 25 years ago (1959) as ''Nuclear Energy Agency'', almost simultaneously with other large international nuclear energy organisations. The NEA undertook special tasks during the international cooperation, which have shifted over time. A special feature today is the cooperation by means of international committees, which are supported by a small own staff of the organisation. The focus points lie within the area of safety and regimentation and on chosen scientific and technical studies.

OECD and NEA countries' national frameworks for nuclear activities

International Nuclear Information System (INIS)

Kuzeyli, Kaan

2016-01-01

To assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes, the NEA serves as a forum for sharing and analysing information and experience among its member countries in order to pool and maintain their technical expertise and human infrastructure and to support nuclear activities by providing them with nuclear policy analyses. Comprehensive and effective legal regimes are necessary to help achieve confidence in the peaceful use of nuclear energy. These regimes, whose goals are to protect the public and the natural environment from the risks inherent in such activities, include regulation at a national level, co-operation at bilateral and multilateral levels and international harmonisation of national policies and legislation through adherence to international conventions. Regimes need to be strong enough to set and enforce limits, and flexible enough to keep pace with technological advances and changing public concerns. The NEA collects, analyses and disseminates information on nuclear law in general and on topical nuclear legal issues in particular. Nuclear law is the body of special legal norms created to regulate the conduct of legal or natural persons engaged in activities related to fissionable materials, ionising radiation and exposure to natural sources of radiation. In 1995, the NEA began publishing country profiles entitled Nuclear Legislation in OECD and NEA Countries - Regulatory and Institutional Frameworks for Nuclear Activities or the 'Grand Orange', a name which was adopted and became widely used because of the colour of the initial cover. Since 2006, these country profiles can be downloaded free online both in English and French from the NEA web site. The NEA endeavours to complement country profiles by publishing online an English, non

OECD/NEA expert group on assay data of spent nuclear fuel

International Nuclear Information System (INIS)

Rugama, Y.; Gauld, I.; Suyama, Kenya

2009-01-01

In the area of criticality safety, management of spent nuclear fuel is a key issue for many NEA member countries. The importance of measured isotopic assay data from Post-Irradiation Examination (PIE) experiments to validate computer code predictions of spent fuel composition used in safety-related studies has long been recognized by members of the OECD/NEA/NSC/WPNCS (Working Party on Nuclear Criticality Safety). These data are particularly important in criticality analyses related to any application of burnup credit as well as to evaluation of criticality and safety in geologic repositories and fuel cycle applications such as reprocessing. Under the auspices of the WPNCS, an Expert Group on assay data has been formed to share best-practice radiochemical analysis methods, computational analysis procedures and data needs, and isotopic validation data. Through member country collaboration, the database of publicly available spent fuel measurements is being revised and expanded to include more recent measurements, with findings to be documented in a state-of-the-art report. (author)

CSNI International standard problems (ISP). Brief descriptions (1975-1999)

International Nuclear Information System (INIS)

2000-03-01

Over the last twenty-five years the NEA Committee on the Safety of Nuclear Installations (CSNI) has sponsored a considerable number of international activities to promote the exchange of experience between its Member countries in the use of nuclear safety codes and testing materials. A primary goal of these activities is to increase confidence in the validity and accuracy of analytical tools or testing procedures which are needed in warranting the safety of nuclear installations, and to demonstrate the competence of involved institutions. International Standard Problems (ISPs) exercises are comparative exercises in which predictions or recalculations of a given physical problem with different best-estimate computer code are compared with each other and above all with the results of a carefully specified experimental study. ISP exercises are performed as 'open' or 'blind' problems. In an open Standard Problem exercise the results of the experiment are available to the participants before performing the calculations, while in a blind Standard Problem exercise the experimental results are locked until the calculation results are made available for comparison. The CSNI-promoted ISP activity started in the early 70's and is still underway. Parallel to other national and international programs the CSNI has sponsored over more than 25 years forty-seven International Standard Problem exercises. This program has been focused mainly on the applicability of large thermal-hydraulic code systems simulating the behaviour of nuclear coolant and containment systems, fuel behaviour under accident conditions, hydrogen distribution, core-concrete interactions and fission product release and transport. One ISP exercise was organised in connection with a seismic ultimate dynamic response test. ISP exercises have proven to be very valuable to participating countries. They have been fruitful to identify code application problems and to amplify the contacts between the experimental and

OECD/NEA International Benchmark exercises: Validation of CFD codes applied nuclear industry; OECD/NEA internatiion Benchmark exercices: La validacion de los codigos CFD aplicados a la industria nuclear

Energy Technology Data Exchange (ETDEWEB)

Pena-Monferrer, C.; Miquel veyrat, A.; Munoz-Cobo, J. L.; Chiva Vicent, S.

2016-08-01

In the recent years, due, among others, the slowing down of the nuclear industry, investment in the development and validation of CFD codes, applied specifically to the problems of the nuclear industry has been seriously hampered. Thus the International Benchmark Exercise (IBE) sponsored by the OECD/NEA have been fundamental to analyze the use of CFD codes in the nuclear industry, because although these codes are mature in many fields, still exist doubts about them in critical aspects of thermohydraulic calculations, even in single-phase scenarios. The Polytechnic University of Valencia (UPV) and the Universitat Jaume I (UJI), sponsored by the Nuclear Safety Council (CSN), have actively participated in all benchmark's proposed by NEA, as in the expert meetings,. In this paper, a summary of participation in the various IBE will be held, describing the benchmark itself, the CFD model created for it, and the main conclusions. (Author)

NEA activities in 1991. 20. Annual report of the OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

1992-01-01

This annual report gives informations on OECD Nuclear Energy Agency activities in 1991. This report is divided into ten chapters: 1 Trends in nuclear power. 2 Nuclear development and the fuel cycle. 3 Nuclear safety and regulation. 4 Radiation protection. 5 Radioactive waste management and disposal. 6 Nuclear science: Reactor physics, nuclear data, NEA data bank. 7 Joint projects and coordinated research programs. 8 Legal affairs. 9 informations programs. 10 relations with non-member countries

2013 NEA Annual Report

International Nuclear Information System (INIS)

2014-01-01

The Nuclear Energy Agency (NEA) is a semi-autonomous body within the Organisation for Economic Co-operation and Development (OECD), located in the Paris area in France. The objective of the Agency is to assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes. 2013 was a year of continuing progress by the OECD Nuclear Energy Agency in a number of important areas, marked in particular by an increased scope and reach. Following the accession of the Russian Federation on 1 January 2013, the 31 members of the Agency now account for 90% of installed nuclear power generating capacity in the world, further expanding the significant international role that the NEA can play in the scientific, technological, legal and safety-related aspects of nuclear energy. The NEA is a central part of concerted international efforts to enhance co-operation in the nuclear energy field. As part of these efforts, in 2013 the NEA and the China Atomic Energy Authority (CAEA) signed a Joint Declaration on Co-operation in the Field of Peaceful Uses of Nuclear Energy. The purpose of this co-operation is to enhance the exchange of experience and information at the international level so as to make nuclear power safer, and to ensure robust scientific, technological and legal bases for its development and use in an environmentally friendly and economical manner. The NEA remains fully committed to these objectives, and in view of ongoing work following the 2011 accident at the Fukushima Daiichi nuclear power plant, the Agency published in September 2013 a summary of key actions and member country responses entitled The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt. NEA actions in response to the accident have primarily been led by the three committees

Results of an OECD/NEA comparison of minimum critical values

International Nuclear Information System (INIS)

Weber, Wolf; Mennerdahl, Dennis

2003-01-01

An OECD/NEA expert group has compiled international data on existing minimum critical values for UO 2 -, PuO 2 -, UNH- and PuNH-systems to identify any significant discrepancies in the data and to propose explanations. The paper examines the spread of the compiled data and the influence of the time of generation of the data on the spread. It turns out, that the remarkable spread reduces by omitting values older than five years. Considering only data generated in the last three years, the spread further reduces. The number of cases with a large spread in the reported minimum critical values falls from 28 to four cases, and the smallest and largest data values converge. (author)

Proceedings of the OECD/CSNI specialist meeting on advanced instrumentation and measurement techniques

Energy Technology Data Exchange (ETDEWEB)

Lehner, J [comp.

1998-09-01

In the last few years, tremendous advances in the local instrumentation technology for two-phase flow have been accomplished by the applications of new sensor techniques, optical or beam methods and electronic technology. The detailed measurements gave new insight to the true nature of local mechanisms of interfacial transfer between phases, interfacial structure and two-phase flow turbulent transfers. These new developments indicate that more accurate and reliable two-phase flow models can be obtained, if focused experiments are designed and performed by utilizing this advanced instrumentation. The purpose of this Specialist Meeting on Advanced Instrumentation and Measurement Techniques was to review the recent instrumentation developments and the relation between thermal-hydraulic codes and instrumentation capabilities. Four specific objectives were identified for this meeting: bring together international experts on instrumentation, experiments, and modeling; review recent developments in multiphase flow instrumentation; discuss the relation between modeling needs and instrumentation capabilities, and discuss future directions for instrumentation development, modeling, and experiments.

Proceedings of the OECD/CSNI specialist meeting on advanced instrumentation and measurement techniques

International Nuclear Information System (INIS)

Lehner, J.

1998-09-01

In the last few years, tremendous advances in the local instrumentation technology for two-phase flow have been accomplished by the applications of new sensor techniques, optical or beam methods and electronic technology. The detailed measurements gave new insight to the true nature of local mechanisms of interfacial transfer between phases, interfacial structure and two-phase flow turbulent transfers. These new developments indicate that more accurate and reliable two-phase flow models can be obtained, if focused experiments are designed and performed by utilizing this advanced instrumentation. The purpose of this Specialist Meeting on Advanced Instrumentation and Measurement Techniques was to review the recent instrumentation developments and the relation between thermal-hydraulic codes and instrumentation capabilities. Four specific objectives were identified for this meeting: bring together international experts on instrumentation, experiments, and modeling; review recent developments in multiphase flow instrumentation; discuss the relation between modeling needs and instrumentation capabilities, and discuss future directions for instrumentation development, modeling, and experiments

ISP-31 OECD/NEA/CSNI International Standard Problem n.31. Cora-13 experiment on severe fuel damage. Comparison report

International Nuclear Information System (INIS)

Firnhaber, M.; Trambauer, K.; Hagen, S.; Hofmann, P.; Schanz, G.; Sepold, L.

1993-07-01

The severe fuel damage experiment CORA-13 has been offered as CSNI-International Standard Problem (ISP) No. 31. The out-of-pile experiment CORA-13 was executed in November 1990 at Kernforschungszentrum Karlsruhe. The major objectives of this experiment were to investigate the behavior of PWR fuel elements during early core degradation and fast cooldown due to refill. Measured quantities are boundary conditions, bundle temperatures, hydrogen generation and the final bundle configuration. The ISP was conducted as a blind exercise. Boundary conditions which could not be measured, but which are necessary for simplified test simulation (axial power profile, shroud insulation temperature, bundle refill flow) were estimated using ATHLET-CD. Results to the ISP were submitted by 9 participants using different versions of SCDAP/RELAP5, and codes such as FRAS-SFD, ICARE2, KESS-III, MELCOR. The thermal behavior up to significant oxidation has been predicted quite well by most of the codes. In general, the capability of the codes in calculating the main degradation phenomena has been clearly illustrated and weaknesses concerning the modelling of some degradation processes have been identified. Among the degradation phenomena involved in the test, the more severe limitations concern the UO 2 -ZrO 2 dissolution by molten Zr, the solubility limits in the resulting U-Zr-O mixture and the cladding failure by the molten mixture

OECD/CSNI specialist meeting on advanced instrumentation and measurements techniques: summary and conclusions

International Nuclear Information System (INIS)

1997-01-01

This specialist meeting on Advanced Instrumentation and Measurements Techniques was held in Santa Barbara (USA) in 1997 and attracted some 70 participants in ten technical sessions and a session of the round table discussions, with a total of 41 papers. It was intended to bring together the international experts in multi-phase flow instrumentation, experiment and modeling to review the state-of-the-art of the two-phase flow instrumentation methods and to discuss the relation between modeling needs and instrumentation capabilities. The following topics were included: Modeling needs and future direction for improved constitutive relations, interfacial area transport equation, and multi-dimensional two-fluid model formulation; local instrumentation developments for void fraction, interfacial area, phase velocities, turbulence, entrainment, particle size, thermal non-equilibrium, shear stress, nucleation, condensation and boiling; global instrumentation developments for void fraction, mass flow, two-phase level, non-condensable concentration, flow regimes, low flow and break flow; relation between modeling needs and instrumentation capabilities, future directions for experiments focused on modeling needs and for instrumentation developments

Organisational factors important to the safe operation of NPPs

International Nuclear Information System (INIS)

Frischknecht, Albert; Baumont, Genevieve

2000-01-01

The purpose of this paper is to present the achievements of a group of human factor specialists known as Expanded Task Force on Human Factors (ETF). ETF is part of the Principal Working Group No.1 (PWG1) on 'Operating Experience and Human Factors' of the Committee on Nuclear Safety Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). Today, as shown by incident analysis, technology is so far developed that human behaviour and organisational deficiencies can contribute to a major part of the root causes of incidents in nuclear power plants. The influence of the organisation on the safe behaviour and performance of individuals is recognised as a relevant issue for the safety of nuclear power plants (NPPs). The need for an up-to-date basis of knowledge in this area was recognised by CSNI and therefore the ETF organised a workshop, in Switzerland, in 1998, on Organisational Factors. During the workshop, different aspects of organisational influences on the safe operation of NPPs were discussed and twelve important organisational factors concerning safety related activities in a NPP were identified. The result of the workshop is summarised in a state-of-the-art Report (SOAR) 'Identification and Assessment of Organisational Factors Related to the Safety of NPPs' issued by the OECD/NEA. The present paper gives an overview on the main findings of the workshop and conclusions concerning the evaluation of organisational factors. (author)

Proceedings of the Second OECD/NEA Organisation Meeting on Increased Accident Tolerance of Fuels for LWRs

International Nuclear Information System (INIS)

Massara, Simone; ); Bragg-Sitton, Shannon; Braase, Lori; Merrill, Brad; Teague, Melissa; Stanek, Chris R.; Montgomery, Robert H.; Ott, Larry J.; Robb, Kevin; Snead, Lance; Farmer, Mitch; Billone, Michael C.; Todosow, Michael; Brown, Nicholas; Brachet, J.C.; Le Flem, M.; Sauder, C.; Idarraga-Trujillo, I.; Michaux, A.; Lorrette, C.; Le Saux, M.; Blanpain, P.; Park, Jeong-Yong; Yang, Jae-Ho; Kim, Weon-Ju; Koo, Yang-Hyun; Liu, T.; Hallstadius, Lars; Lahoda, Ed; Waeckel, N.; Bonnet, J.M.; Vitanza, Carlo; Ohta, Hirokazu; Ogata, Takanari; Nakamura, Kinya; Dyck, Gary; Inozemtsev, Victor; )

2013-01-01

Under the guidance of the OECD-NEA Nuclear Science Committee, the expert group acts as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance. The expert group focusses on the fundamental properties and behaviour under normal operations and accident conditions for advanced core materials and components (fuels, cladding, control rods, etc.). The materials considered are applicable to Gen II and Gen III Light Water Reactors, as well as Gen III+ reactors under construction. The objective of the expert group is to define and coordinate a programme of work to help advance the scientific knowledge needed to provide the technical underpinning for the development of advanced LWR fuels with enhanced accident tolerance compared to currently used zircaloy/UO 2 fuel systems, as well as other non-fuel core components with important roles in LWR performance under accident conditions. This document brings together the available presentations (slides) given at the 2. Meeting on Increased Accident Tolerance of Fuels for LWRs. Content: 1 - Overview of the exchanges after the December-2012 Workshop through the discussion forum established at the OECD-NEA (S. Massara, NEA); 2 - Metrics Development for Enhanced Accident Tolerant LWR Fuels (S. Bragg-Sitton, INL); 3 - Candidate ATF Clad Technologies and Key Feasibility Issues (L. Snead, ORNL); 4 - CEA studies on nuclear fuel claddings for LWRs enhanced accident tolerant fuel. Some recent results, pending issues and prospects (J.C. Brachet, CEA); 5 - Current status on the accident tolerant fuel development in the Republic of Korea (J.Y. Park, J.H. Chang, KAERI); 6 - The current status of fuel R and D in the P.R. of China (T. Liu, CGN). Session 2: Key elements for a work programme on ATF: 7 - Beneficial characteristics of ATF (metrics) (L. Hallstadius, Westinghouse); 8 - Reactor types of interest (applicability) (L. Ott, ORNL); 9 - Impact on normal operations

State-of-art technology of fuels for burning minor actinides. An OECD/NEA study

International Nuclear Information System (INIS)

Ogawa, Toru; Konings, R.J.M.; Pillon, S.; Schram, R.P.C.; Verwerft, M.; Wallenius, J.

2005-01-01

At OECD/NEA, Working Party on Scientific Issues in Partitioning and Transmutation was formed for 2000-2004, which studied the status and trends of scientific issues in Partitioning and Transmutation (P and T). The study included the scientific and technical issues of fuels and materials, which are related to dedicated systems for transmutation. This paper summarizes the state-of-art technology of the fuels for burning minor actinides (neptunium, americium and curium). (author)

Proceedings of the 2nd CSNI Specialist Meeting on Simulators and Plant Analysers

International Nuclear Information System (INIS)

Tiihonen, O.

1999-01-01

The safe utilisation of nuclear power plants requires the availability of different computerised tools for analysing the plant behaviour and training the plant personnel. These can be grouped into three categories: accident analysis codes, plant analysers and training simulators. The safety analysis of nuclear power plants has traditionally been limited to the worst accident cases expected for the specific plant design. Many accident analysis codes have been developed for different plant types. The scope of the analyses has continuously expanded. The plant analysers are now emerging tools intended for extensive analysis of the plant behaviour using a best estimate model for the whole plant including the reactor and full thermodynamic process, both combined with automation and electrical systems. The comprehensive model is also supported by good visualisation tools. Training simulators with real time plant model are tools for training the plant operators to run the plant. Modern training simulators have also features supporting visualisation of the important phenomena occurring in the plant during transients. The 2nd CSNI Specialist Meeting on Simulators and Plant Analysers in Espoo attracted some 90 participants from 17 countries. A total of 49 invited papers were presented in the meeting in addition to 7 simulator system demonstrations. Ample time was reserved for the presentations and informal discussions during the four meeting days. (orig.)

Consideration of probabilistic safety objectives in OECD/NEA member countries: Short overview and update

International Nuclear Information System (INIS)

Versteeg, M.F.; Andrews, R.M.

1994-01-01

Almost every member country of the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD) uses probabilistic safety criteria (PSC), in one way or another, for the safety assessment of nuclear power plants. The choice of the PSC, their applicability, and whether or not these PSC are used in a formal and/or legal way, is dependent on the political and regulatory situation. The spectrum of utilization includes the use as design requirements and the use as a regulatory and licensing tool be the authorities. The paper summarises the various PSC applied to the assessment of nuclear power plant in the OECD member countries and presents in more detail the use of PSC on the public health level in the Netherlands, United Kingdom and USA. 10 refs, 1 fig., 6 tabs

ISP - 26 OECD/NEA/CSNI International standard problem n. 26. Rosa-4 LSTF Cold-Leg Small-Break Loca experiment. Comparison report

International Nuclear Information System (INIS)

1992-02-01

This report is the final comparison report for the CSNI ISP-26 which was performed for a 5 pc cold-leg small-break LOCA experiment conducted in the ROSA-IV Large scale test facility (LSTF), and simulation of the thermal-hydraulic response of a pressurized water reactor during a small break loss-of-coolant accident or an operational transient. The facility has an overall scaling factor of 1/48, with hot and cold legs sized to conserve the volume scaling. Both the initial steady-state conditions and the test procedures are designed to minimize the effects of scaling compromises. 10 seconds into the break, the turbine throttle valve was closed at a pressurizer pressure of 12.97 MPa. The turbine bypass was inactive, since loss-of-offsite power was assumed concurrently with the scram. The reactor coolant pumps stopped at 265 seconds. The core was uncovered between 120 seconds and 155 seconds into the break. The comparison report presents all the nineteen submitted calculations. A summary description of the participants as well as the computer codes and input decks used by them is provided

Analysis of an OECD/NEA high-temperature reactor benchmark

International Nuclear Information System (INIS)

Hosking, J. G.; Newton, T. D.; Koeberl, O.; Morris, P.; Goluoglu, S.; Tombakoglu, T.; Colak, U.; Sartori, E.

2006-01-01

This paper describes analyses of the OECD/NEA HTR benchmark organized by the 'Working Party on the Scientific Issues of Reactor Systems (WPRS)', formerly the 'Working Party on the Physics of Plutonium Fuels and Innovative Fuel Cycles'. The benchmark was specifically designed to provide inter-comparisons for plutonium and thorium fuels when used in HTR systems. Calculations considering uranium fuel have also been included in the benchmark, in order to identify any increased uncertainties when using plutonium or thorium fuels. The benchmark consists of five phases, which include cell and whole-core calculations. Analysis of the benchmark has been performed by a number of international participants, who have used a range of deterministic and Monte Carlo code schemes. For each of the benchmark phases, neutronics parameters have been evaluated. Comparisons are made between the results of the benchmark participants, as well as comparisons between the predictions of the deterministic calculations and those from detailed Monte Carlo calculations. (authors)

Analyses and results of the OECD/NEA WPNCS EGUNF benchmark phase II. Technical report; Analysen und Ergebnisse zum OECD/NEA WPNCS EGUNF Benchmark Phase II. Technischer Bericht

Energy Technology Data Exchange (ETDEWEB)

Hannstein, Volker; Sommer, Fabian

2017-05-15

The report summarizes the performed studies and results in the frame of the phase II benchmarks of the expert group of used nuclear fuel (EGUNF) of the working party of nuclear criticality safety (WPNCS) of the nuclear energy agency (NEA) of the organization for economic co-operation and development (OECD). The studies specified within the benchmarks have been realized to the full extent. The scope of the benchmarks was the comparison of a generic BWR fuel element with gadolinium containing fuel rods with several computer codes and cross section libraries of different international working groups and institutions. The used computational model allows the evaluation of the accuracy of fuel rod and their influence of the inventory calculations and the respective influence on BWR burnout credit calculations.

Report of a CSNI workshop on uncertainty analysis methods. Volume 1 + 2

International Nuclear Information System (INIS)

Wickett, A.J.; Yadigaroglu, G.

1994-08-01

The OECD NEA CSNI Principal Working Group 2 (PWG2) Task Group on Thermal Hydraulic System Behaviour (TGTHSB) has, in recent years, received presentations of a variety of different methods to analyze the uncertainty in the calculations of advanced unbiased (best estimate) codes. Proposals were also made for an International Standard Problem (ISP) to compare the uncertainty analysis methods. The objectives for the Workshop were to discuss and fully understand the principles of uncertainty analysis relevant to LOCA modelling and like problems, to examine the underlying issues from first principles, in preference to comparing and contrasting the currently proposed methods, to reach consensus on the issues identified as far as possible while not avoiding the controversial aspects, to identify as clearly as possible unreconciled differences, and to issue a Status Report. Eight uncertainty analysis methods were presented. A structured discussion of various aspects of uncertainty analysis followed - the need for uncertainty analysis, identification and ranking of uncertainties, characterisation, quantification and combination of uncertainties and applications, resources and future developments. As a result, the objectives set out above were, to a very large extent, achieved. Plans for the ISP were also discussed. Volume 1 contains a record of the discussions on uncertainty methods. Volume 2 is a compilation of descriptions of the eight uncertainty analysis methods presented at the workshop

The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt

International Nuclear Information System (INIS)

2013-01-01

Following the March 2011 accident at the Fukushima Daiichi nuclear power plant, all NEA member countries took early action to ensure and confirm the continued safety of their nuclear power plants and the protection of the public. After these preliminary safety reviews, all countries with nuclear facilities carried out comprehensive safety reviews, often referred to as 'stress tests', which reassessed safety margins of nuclear facilities with a primary focus on challenges related to conditions experienced at the Fukushima Daiichi nuclear power plant, for example extreme external events and the loss of safety functions, or capabilities to cope with severe accidents. As appropriate, improvements are being made to safety and emergency response systems to ensure that nuclear power plants are capable of withstanding events that lead to loss of electrical power and/or cooling capability. In the weeks following the accident, the NEA immediately began establishing expert groups in the nuclear safety and radiological protection areas, as well as contributing to information exchange with the Japanese authorities and other international organisations. It promptly provided a forum for high-level decision makers and regulators within the G8-G20 frameworks. The NEA actions taken at the international level in response to the accident have been carried out primarily by the three NEA standing technical committees concerned with nuclear and radiation safety issues - the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Radiation Protection and Public Health (CRPPH) - under the leadership of the CNRA. More than two years following the accident, the NEA continues to assist the Japanese authorities in dealing with their nuclear safety and recovery efforts as well as to facilitate international co-operation on nuclear safety and radiological protection matters. It is strongly supporting the establishment of

OECD/NEA/CSNI Status Report on Filtered Containment Venting

International Nuclear Information System (INIS)

Jacquemain, D.; Guentay, S.; Basu, S.; Sonnenkalb, M.; Lebel, L.; Ball, J.; Allelein, H.J.; Liebana Martinez, B.; Eckardt, B.; Losch, N.; Ammirabile, L.; ); Gryffroy, D.; Sallus, L.; Kroes, A.; Rensonnet, T.; Anden, A.; Gyepi-Garbrah, S.; Viktorov, A.; Duspiva, J.; Routamo, T.; Guieu, S.; Hotta, A.; Nakamura, H.; Song, J.H.; Ha, K.S.; Filio, C.; Kuznetsov, M.V.; Kubisova, L.; Nemec, T.; Frid, W.; Loy, D.; Pellini, D.; Zieger, T.; Herranz Puebla, L.; Amri, A.; Kissane, M.; )

2014-01-01

This Status Report provides a comprehensive description of safety requirements associated with Filtered Containment Venting Systems (FCVSs) (Chapter 3) and of the status of FCVS implementation (Chapter 4) as provided by the various contributing countries. The different level of detail describing the accident management situation in different countries in relation to FCVS reflects in part the reality of the different levels of the current regulatory and/or technological appraisal of FCVS internationally. Further, the safety requirements differ in various countries being more-or-less prescriptive with FCVS not necessarily explicitly mandated or not considered as the primary measure to prevent containment over-pressurization. The following requirements may be prescribed for FCVS depending on venting strategies and objectives: vent capacity, vent opening and closing pressures, vent timing, venting system design requirements, consideration of possible hydrogen loads, radiological objectives, FCVS decontamination factors (DFs) for radioactive aerosols, for molecular iodine, etc. These are all discussed in detail in the report. A description of the FCV strategies for emergency operating procedures (EOPs) and SAM domains is provided in Chapter 5. FCVS are considered to be an additional system to protect the containment integrity. FCVSs are typically to be used in SAs as part of the overall applied SAM strategy for PWRs and BWRs, while they are also used in DBA for some PHWRs (CANDUs). Operation of a FCVS is also considered in some countries and for some reactor designs for accident management other than countering the long-term over-pressurization of the containment, e.g., for BWRs in the case of loss of heat sink to remove decay heat or to reduce the hydrogen inventory in the containment. Chapter 6 presents the well-known existing filtration technologies e.g., scrubbers, deep-bed filtration and different sorption systems. Details of systems for which information was received from designers can be found in the Appendices of the report. Part of the information concerning the existing filtration-systems performance is proprietary and was not disclosed by FCVS designers. However, two major aspects can be underlined concerning existing systems: - most of the available systems were designed on knowledge-bases which were existing in the late 1980's. Some have been updated depending on the system design and implementation; - and, given the possible extension of the domain of FCVS use, the demonstration of the systems performance should be consequently extended to more challenging conditions. Both aspects are discussed in the report. It was also thought valuable to provide FCVS general design requirements and specific design aspects and recommend state-of-the-art qualification of filter technologies for reliable function and performance of FCVS. This is provided in chapter 7. This chapter, as well as others in the report (particularly chapters 9 and 10), can be used as a guide for FCVS implementation. Source-term (ST) evaluations are factored into accident analysis in different countries. ST evaluation studies presented in Chapter 8 of the report are limited to countries which have done specific ST evaluations in view of FCVS performance and provided detailed information. As for FCVS filtration, besides aerosols, specific attention is being given to organic iodides and iodine-oxide particles as they may contribute significantly to the ST in some accidents. Possible contributions of ruthenium-oxide species to the ST is under investigation in on-going R and D programmes. Filtration of noble gases released through the venting process has been discussed but no reliable technology exists for efficient retention of these species and the benefit of reducing their releases in the environment has to be balanced with drawbacks that could result on-site from radioactivity accumulation in the system designed for their retention. Deterministic consequence analyses show large reduction of radiological impacts and, in studies performed in France and in the US, of radiological costs when comparing effective filtered releases against unfiltered releases. In most countries, calculated reduction of radiological impacts appears sufficient to conclude that FCVS are beneficial to SAM. In the cost/benefits studies performed in the US, these benefits are weighted by the estimated low probability of a SA, and have not been cost-justified. Chapter 9 and 10 describe currently assessed benefits and negative aspects related to FCVS use and the related potential improvements or countermeasures for existing systems. These chapters may also be used to guide the design, implementation and operation of future FCVS to reduce these risks. Generally, all contributing countries recognized through this work the potential benefits of FCVS for emergency response, reduction of the extent of land contamination and health effects and increased social acceptability of nuclear power plant installations. FCVS should, however, be considered in conjunction with other SAM strategies, e.g., no large benefit is expected for containment by-pass scenarios which have to be managed by other SAMM. FCVSs implemented before Fukushima were mainly designed to manage long-term pressure build-up in the containment; new FCVS may perhaps be designed to deal with more challenging conditions. The robustness, the safe use and the reliability of FCVSs for such conditions should be further assessed either to improve existing systems or to propose upgraded design requirements for future systems

Managing nuclear safety research facilities and capabilities in a changing nuclear industry: the contribution of the OECD/NEA

International Nuclear Information System (INIS)

Royen, J.

2000-01-01

Although the safety level of nuclear power plants in OECD countries is very satisfactory and the technologies basic to the resolution of safety issues have advanced considerably, continued nuclear safety research work is necessary to address many of the residual concerns, and it remains an important element in ensuring the safe operation of nuclear power plants. However, the funding levels of national Government safety research programmes have been reduced over recent years. There is concern about the ability of OECD Member countries to sustain an adequate level of nuclear safety research capability. The OECD/NEA has a key role to play in organizing reflection and exchange of information on the most efficient use of available technical resources, and in the international management of nuclear safety research facilities and capabilities in a changing nuclear industry. Possible initiatives are mentioned in the paper. (author)

INL Results for Phases I and III of the OECD/NEA MHTGR-350 Benchmark

Energy Technology Data Exchange (ETDEWEB)

Gerhard Strydom; Javier Ortensi; Sonat Sen; Hans Hammer

2013-09-01

The Idaho National Laboratory (INL) Very High Temperature Reactor (VHTR) Technology Development Office (TDO) Methods Core Simulation group led the construction of the Organization for Economic Cooperation and Development (OECD) Modular High Temperature Reactor (MHTGR) 350 MW benchmark for comparing and evaluating prismatic VHTR analysis codes. The benchmark is sponsored by the OECD's Nuclear Energy Agency (NEA), and the project will yield a set of reference steady-state, transient, and lattice depletion problems that can be used by the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC), and vendors to assess their code suits. The Methods group is responsible for defining the benchmark specifications, leading the data collection and comparison activities, and chairing the annual technical workshops. This report summarizes the latest INL results for Phase I (steady state) and Phase III (lattice depletion) of the benchmark. The INSTANT, Pronghorn and RattleSnake codes were used for the standalone core neutronics modeling of Exercise 1, and the results obtained from these codes are compared in Section 4. Exercise 2 of Phase I requires the standalone steady-state thermal fluids modeling of the MHTGR-350 design, and the results for the systems code RELAP5-3D are discussed in Section 5. The coupled neutronics and thermal fluids steady-state solution for Exercise 3 are reported in Section 6, utilizing the newly developed Parallel and Highly Innovative Simulation for INL Code System (PHISICS)/RELAP5-3D code suit. Finally, the lattice depletion models and results obtained for Phase III are compared in Section 7. The MHTGR-350 benchmark proved to be a challenging simulation set of problems to model accurately, and even with the simplifications introduced in the benchmark specification this activity is an important step in the code-to-code verification of modern prismatic VHTR codes. A final OECD/NEA comparison report will compare the Phase I and III

Review of the OECD specialist meeting on continuous monitoring techniques for assuring coolant circuit integrity

International Nuclear Information System (INIS)

Thie, J.A.

1986-01-01

This article summarizes the OECD Specialist Meeting on Continuous Monitoring Techniques for Assuring Coolant Circuit Integrity held August 12-14, 1985, in London. The conference was organized by the Organization for Economic Cooperation and Development's (OECD's) Committee on the Safety for Nuclear Installations and hosted by Her Majesty's Nuclear Installation Inspectorate at King's College. Many other conferences have addressed analysis and inspection approaches to ensuring primary-system integrity, but the OECD meeting was structured to pay attention to the continuous monitoring approach - possibly the first conference to be so designed. The specific technologies represented were vibrations, noise (i.e., random fluctuations in signals), leaks, acoustic emission, and cyclic fatigue. Although water reactors dominate the papers, all reactor types were included. A diverse group of about 50 attendees from 11 countries participated, including representatives from utilities, suppliers, regulators, and researchers

Fuel safety criteria and review by OECD / CSNI task force

International Nuclear Information System (INIS)

Van Doesburg, W.

1999-01-01

Full text of publication follows: with the advent of advanced fuel and core designs, and the implementation of more accurate (best estimate or statistical) design and analysis methods, there is a general feeling that safety margins have been or are being reduced. Historically, fuel safety margins were defined by adding conservatism to the safety limits, which in turn were also fixed in a conservative manner, here, the expression 'conservatism' expresses the fact that bounding or limiting numbers were chosen for model parameters, plant and fuel design data, and fuel operating history values. Unfortunately, as these conservatisms were not quantified (or quantifiable), the amount of safety available or the reduction thereof is difficult to substantiate. For the regulator, it is important to know the margin available with the utilities' request for approval of new fuel or methods; likewise, for the utility and vendor it is important to know what margins exist and what they are based on, to identify in which direction they can make further progress and optimize fuel and fuel cycle cost. Naturally, each party involved will have to decide on how much margin should be in place, to establish operational criteria and ensure that these can actually be met during operation. To assess the margins issue, safety criteria themselves need to be reviewed first. Most - if not all - of the currently existing safety criteria were established during the 60's and early 70's, and verified against experiments with fuel available at that time - mostly at zero exposure. Of course, verification was performed as designs progressed in later years, primarily with the aim to be able to prove that safety criteria were adequate as long as the said conservatisms would be retained, and not with the aim to reestablish limits. The mandate to the OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria (TFFSC) is to assess the adequacy of existing fuel safety criteria, in view of the 'new design' elements (new

NEA Annual Report 2016

International Nuclear Information System (INIS)

Magwood, William D. IV

2017-01-01

The Nuclear Energy Agency (NEA) is a specialised agency within the Organisation for Economic Co-operation and Development (OECD), an intergovernmental organisation of industrialised countries, based in Paris, France. The OECD is a unique forum in which its 35 member countries work together to create better policies for better lives. The objective of the NEA is to assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally sound and economical use of nuclear energy for peaceful purposes. It provides authoritative assessments and forges common understandings on key issues as input to government decisions on nuclear energy policy and to broader OECD analyses in areas such as energy and the sustainable development of low-carbon economies. The NEA co-operates with a range of multilateral organisations, including the European Commission and the International Atomic Energy Agency. This 2016 annual report presents: 1 - Message from the Director-General; 2 - The Economic Challenges of Nuclear Energy; 3 - Nuclear Technology in 2016; 4 - NEA Activities by Sector: Nuclear Development; Nuclear Safety and Regulation; Human Aspects of Nuclear Safety; Radioactive Waste Management; Radiological Protection; Nuclear Science; Data Bank; Legal Affairs; 5 - General Information: Information and Communications; Organisational Structure of the NEA; NEA Publications and Brochures Produced in 2016

Proceedings of the Joint IAEA/CSNI Specialists` Meeting on Fracture Mechanics Verification by Large-Scale Testing held at Pollard Auditorium, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

Pugh, C.E.; Bass, B.R.; Keeney, J.A. [comps.] [Oak Ridge National Lab., TN (United States)

1993-10-01

This report contains 40 papers that were presented at the Joint IAEA/CSNI Specialists` Meeting Fracture Mechanics Verification by Large-Scale Testing held at the Pollard Auditorium, Oak Ridge, Tennessee, during the week of October 26--29, 1992. The papers are printed in the order of their presentation in each session and describe recent large-scale fracture (brittle and/or ductile) experiments, analyses of these experiments, and comparisons between predictions and experimental results. The goal of the meeting was to allow international experts to examine the fracture behavior of various materials and structures under conditions relevant to nuclear reactor components and operating environments. The emphasis was on the ability of various fracture models and analysis methods to predict the wide range of experimental data now available. The individual papers have been cataloged separately.

CSNI technical opinion papers no.10. The role of human and organisational factors in nuclear power plant modifications

International Nuclear Information System (INIS)

2009-01-01

Nuclear power plant modifications may be needed for a number of different reasons. These include physical ageing of plant systems, structures and components; obsolescence in hardware and software; feedback from operating experience; and opportunities for improved plant safety, reliability or capability. However, experience has also shown that weaknesses in the design and/or implementation of modifications can present significant challenges to plant safety. They can also have a considerable impact on the commercial performance of the plant. It is therefore important that the plant modification process reflect a recognition of the potential impact of human errors and that it incorporate suitable measures to minimise the potential for such errors. In this context, the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Working Group on Human and Organisational Factors organised an international workshop in 2003 to discuss the role of human and organisational performance in the nuclear plant modification process. This technical opinion paper represents the consensus of specialists in human and organisational factors (HOF) in the NEA member countries on commendable practices and approaches to dealing with nuclear plant modifications. It considers factors that should be taken into account when developing a modification process and identifies some lessons learnt from application of the process. The paper should be of particular interest of nuclear safety regulators and nuclear power plant operators. (author)

Technology relevance of the 'uncertainty analysis in modelling' project for nuclear reactor safety

International Nuclear Information System (INIS)

D'Auria, F.; Langenbuch, S.; Royer, E.; Del Nevo, A.; Parisi, C.; Petruzzi, A.

2007-01-01

The OECD/NEA Nuclear Science Committee (NSC) endorsed the setting up of an Expert Group on Uncertainty Analysis in Modelling (UAM) in June 2006. This Expert Group reports to the Working Party on Scientific issues in Reactor Systems (WPRS) and because it addresses multi-scale / multi-physics aspects of uncertainty analysis, it will work in close co-ordination with the benchmark groups on coupled neutronics-thermal-hydraulics and on coupled core-plant problems, and the CSNI Group on Analysis and Management of Accidents (GAMA). The NEA/NSC has endorsed that this activity be undertaken with Prof. K. Ivanov from the Pennsylvania State University (PSU) as the main coordinator and host with the assistance of the Scientific Board. The objective of the proposed work is to define, coordinate, conduct, and report an international benchmark for uncertainty analysis in best-estimate coupled code calculations for design, operation, and safety analysis of LWRs entitled 'OECD UAM LWR Benchmark'. At the First Benchmark Workshop (UAM-1) held from 10 to 11 May 2007 at the OECD/NEA, one action concerned the forming of a sub-group, led by F. D'Auria, member of CSNI, responsible for defining the objectives, the impact and benefit of the UAM for safety and licensing. This report is the result of this action by the subgroup. (authors)

OECD/NEA working party on nuclear criticality safety: Challenge of new realities

International Nuclear Information System (INIS)

Nomura, Y.; Brady, M.C.; Briggs, J.B.; Sartori, E.

1998-01-01

New issues in criticality safety continue to emerge as spent fuel storage facilities reach the saturation point, fuel enrichments and burn-ups increase and new types of plutonium-carrying fuels are being developed. The new challenges related to the manipulation, transportation and storage of fuel demand further work to improve models predicting behavior through new experiments, especially where there is a lack of data in the present databases. This article summarizes the activities of the OECD/NEA working groups that coordinate and carry out work in the domain of criticality safety. Particular attention is devoted to establishing sound databases required in this area and to addressing issues of high relevance such as burn-up credit. This is aimed toward improving safety and identifying economic solutions to issues concerning the back end of the fuel cycle

Overview of the activities of the OECD/NEA/NSC working party on nuclear criticality safety

International Nuclear Information System (INIS)

Nouri, A.; Blomquist, R.; Bradyraap, M.; Briggs, B.; Cousinou, P.; Nomura, Y.; Weber, W.

2003-01-01

The OECD Nuclear Energy Agency (NEA) started dealing with criticality-safety related subjects back in the seventies. In the mid-nineties, several activities related to criticality-safety were grouped together into the Working Party on Nuclear Criticality Safety. This working party has since been operating and reporting to the Nuclear Science Committee. Six expert groups co-ordinate various activities ranging from experimental evaluations to code and data inter-comparisons for the study of static and transient criticality behaviours. The paper describes current activities performed in this framework and the achievements of the various expert groups. (author)

Selected examples on multi physics researches at KFKI AEKI-results for phase I of the OECD/NEA UAM benchmark

International Nuclear Information System (INIS)

Panka, I.; Kereszturi, A.; Maraczy, C.

2010-01-01

Nowadays, there is a tendency to use best estimate plus uncertainty methods in the field of nuclear energy. This implies the application of best estimate code systems and the determination of the corresponding uncertainties. For the latter one an OECD benchmark was set up. The objective of the OECD/NEA Uncertainty Analysis in Best-Estimate Modeling (UAM) LWR benchmark is to determine the uncertainties of the coupled reactor physics/thermal hydraulics LWR calculations at all stages. In this paper the AEKI participation in Phase I will be presented. This Phase is dealing with the evaluation of the uncertainties of the neutronic calculations starting from the pin cell spectral calculations up to the stand-alone neutronics core simulations. (Authors)

OECD/NEA working party on nuclear criticality safety: challenge of new realities

International Nuclear Information System (INIS)

Nomura, Y.; Brady, M.C.; Briggs, J.B.; Sartori, E.

1998-01-01

New issues in critically safety continue to emerge as spent fuel storage facilities reach the saturation point, fuel enrichments and burn-ups increase and new types of plutonium-carrying fuels are being developed. The new challenges related to the manipulation, transportation and storage of fuel demand further work to improve models predicting behaviour through new experiments, especially where there is a lack of data the present databases. This article summarizes the activities of the OECD/NEA working groups that co-ordinate and carry out work in the domain of criticality safety. Particular attention is devoted to establishing sound databases required in this area and to addressing issues of high relevance such as burn-up credit. This is aimed toward improving safety and identifying economic solutions to issues concerning the back end of the fuel cycle. (authors)

Synthesis of the turbulent mixing in a rod bundle with vaned spacer grids based on the OECD-KAERI CFD benchmark exercise

International Nuclear Information System (INIS)

Lee, Jae Ryong; Kim, Jungwoo; Song, Chul-Hwa

2014-01-01

Highlights: • OECD/KAERI international CFD benchmark exercise was operated by KAERI. • The purpose is to validate relevant CFD codes based on the MATiS-H experiments. • Blind calculation results were synthesized in terms of mean velocity and RMS. • Quality of control volume rather than the number of it was emphasized. • Major findings were followed OECD/NEA CSNI report. - Abstract: The second international CFD benchmark exercise on turbulent mixing in a rod bundle has been launched by OECD/NEA, to validate relevant CFD (Computational Fluid Dynamics) codes and develop problem-specific Best Practice Guidelines (BPG) based on the KAERI (Korea Atomic Energy Research Institute) MATiS-H experiments on the turbulent mixing in a 5 × 5 rod array having two different types of vaned spacer grids: split and swirl types. For this 2nd international benchmark exercise (IBE-2), the MATiS-H testing provided a unique set of experimental data such as axial and lateral velocity components, turbulent intensity, and vorticity information. Blind CFD calculation results were submitted by twenty-five (25) participants to KAERI, who is the host organization of the IBE-2, and then analyzed and synthesized by comparing them with the MATiS-H data. Based on the synthesis of the results from both the experiments and blind CFD calculations for the IBE-2, and also by comparing with the IBE-1 benchmark exercise on the mixing in a T-junction, useful information for simulating this kind of complicated physical problem in a rod bundle was obtained. And some additional Best Practice Guidelines (BPG) are newly proposed. A summary of the synthesis results obtained in the IBE-2 is presented in this paper

Synthesis of the turbulent mixing in a rod bundle with vaned spacer grids based on the OECD-KAERI CFD benchmark exercise

Energy Technology Data Exchange (ETDEWEB)

Lee, Jae Ryong; Kim, Jungwoo; Song, Chul-Hwa, E-mail: chsong@kaeri.re.kr

2014-11-15

Highlights: • OECD/KAERI international CFD benchmark exercise was operated by KAERI. • The purpose is to validate relevant CFD codes based on the MATiS-H experiments. • Blind calculation results were synthesized in terms of mean velocity and RMS. • Quality of control volume rather than the number of it was emphasized. • Major findings were followed OECD/NEA CSNI report. - Abstract: The second international CFD benchmark exercise on turbulent mixing in a rod bundle has been launched by OECD/NEA, to validate relevant CFD (Computational Fluid Dynamics) codes and develop problem-specific Best Practice Guidelines (BPG) based on the KAERI (Korea Atomic Energy Research Institute) MATiS-H experiments on the turbulent mixing in a 5 × 5 rod array having two different types of vaned spacer grids: split and swirl types. For this 2nd international benchmark exercise (IBE-2), the MATiS-H testing provided a unique set of experimental data such as axial and lateral velocity components, turbulent intensity, and vorticity information. Blind CFD calculation results were submitted by twenty-five (25) participants to KAERI, who is the host organization of the IBE-2, and then analyzed and synthesized by comparing them with the MATiS-H data. Based on the synthesis of the results from both the experiments and blind CFD calculations for the IBE-2, and also by comparing with the IBE-1 benchmark exercise on the mixing in a T-junction, useful information for simulating this kind of complicated physical problem in a rod bundle was obtained. And some additional Best Practice Guidelines (BPG) are newly proposed. A summary of the synthesis results obtained in the IBE-2 is presented in this paper.

Sixteen Years of International Co-operation. The OECD/NEA Co-operative Programme on Decommissioning

International Nuclear Information System (INIS)

Menon, S.; Valencia, L.

2002-01-01

The Co-operative Programme on Decommissioning under the administration of the Radioactive Waste Management Committee of the OECD Nuclear Energy Agency (NEA) has recently completed sixteen years of operation. The Programme, which is essentially an information exchange programme between decommissioning projects, came into being in 1985. It has grown from an initial 10 decommissioning projects from 7 countries to 39 projects from 14 countries today. From purely information exchange to start with, the Programme has, in later years, been functioning as a voice for the collective expression of views of the implementers of nuclear decommissioning. During the first sixteen years of the operation of the Co-operative Programme, nuclear decommissioning has grown from local specialist activities within projects to a competitive commercial industry. By the dismantling and release from regulatory control of over a dozen diverse nuclear facilities, the Programme has been able to demonstrate in practice, that nuclear decommissioning can be performed safely both for the workers and the public, and that this can be done at reasonable costs in an environmentally friendly fashion. During the recent years, discussions and work within the Co-operative Programme, specially within some of the Task Groups, have had/are having effects and repercussions not just in the field of nuclear decommissioning, but can possibly affect activities and regulations in other industries. This paper describes how the Programme and its activities and procedures have evolved over the years and indicate the directions of developments in the organization and execution of decommissioning projects. Finally, it gives a brief overview of the achievements of the Cooperative Programme and visualizes future developments in the field of nuclear decommissioning

The OECD/NEA/NSC PBMR coupled neutronics/thermal hydraulics transient benchmark: The PBMR-400 core design

International Nuclear Information System (INIS)

Reitsma, F.; Ivanov, K.; Downar, T.; De Haas, H.; Gougar, H. D.

2006-01-01

The Pebble Bed Modular Reactor (PBMR) is a High-Temperature Gas-cooled Reactor (HTGR) concept to be built in South Africa. As part of the verification and validation program the definition and execution of code-to-code benchmark exercises are important. The Nuclear Energy Agency (NEA) of the Organisation for Economic Cooperation and Development (OECD) has accepted, through the Nuclear Science Committee (NSC), the inclusion of the Pebble-Bed Modular Reactor (PBMR) coupled neutronics/thermal hydraulics transient benchmark problem in its program. The OECD benchmark defines steady-state and transients cases, including reactivity insertion transients. It makes use of a common set of cross sections (to eliminate uncertainties between different codes) and includes specific simplifications to the design to limit the need for participants to introduce approximations in their models. In this paper the detailed specification is explained, including the test cases to be calculated and the results required from participants. (authors)

Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme

International Nuclear Information System (INIS)

Crecy, A. de; Bazin, P.; Glaeser, H.; Skorek, T.; Joucla, J.; Probst, P.; Fujioka, K.; Chung, B.D.; Oh, D.Y.; Kyncl, M.; Pernica, R.; Macek, J.; Meca, R.; Macian, R.; D'Auria, F.; Petruzzi, A.; Batet, L.; Perez, M.; Reventos, F.

2008-01-01

This paper presents the results and the main lessons learnt from the phase 3 of BEMUSE, an international benchmark activity sponsored by the Committee on the Safety of Nuclear Installations [CSNI: Committee on the Safety of Nuclear Installations (NEA, OECD), 2007. BEMUSE Phase III Report. NEA/CSNI R(2007) 4, October 2007] of the OECD/NEA. The phase 3 of BEMUSE aimed at performing Uncertainty and Sensitivity Analyses of thermal-hydraulic codes used for the calculation of LOFT L2-5 experiment, which simulated a Large-Break Loss-of-Coolant-Accident (LB-LOCA). Eleven participants coming from ten organisations and eight countries took part in this benchmark. In the first section of this paper, the context of BEMUSE is described as well as the methods used by the participants. In the second section, the results of the benchmark are presented. The majority of the participants find uncertainty bands which envelop the experimental data fairly well, however the width of these bands is much diverged. A synthesis of the sensitivity analysis results has been made and is expected to provide a useful basis for further uncertainty analysis dealing with LB-LOCA. Finally, recommendations are given both for uncertainty and sensitivity analysis

An analysis of the CSNI/GREST core concrete interaction chemical thermodynamic benchmark exercise using the MPEC2 computer code

International Nuclear Information System (INIS)

Muramatsu, Ken; Kondo, Yasuhiko; Uchida, Masaaki; Soda, Kunihisa

1989-01-01

Fission product (EP) release during a core concrete interaction (CCI) is an important factor of the uncertainty associated with a source term estimation for an LWR severe accident. An analysis was made on the CCI Chemical Thermodynamic Benchmark Exercise organized by OECD/NEA/CSNI Group of Experts on Source Terms (GREST) for investigating the uncertainty in thermodynamic modeling for CCI. The benchmark exercise was to calculate the equilibrium FP vapor pressure for given system of temperature, pressure, and debris composition. The benchmark consisted of two parts, A and B. Part A was a simplified problem intended to test the numerical techniques. In part B, the participants were requested to use their own best estimate thermodynamic data base to examine the variability of the results due to the difference in thermodynamic data base. JAERI participated in this benchmark exercise with use of the MPEC2 code. Chemical thermodynamic data base needed for analysis of Part B was taken from the VENESA code. This report describes the computer code used, inputs to the code, and results from the calculation by JAERI. The present calculation indicates that the FP vapor pressure depends strongly on temperature and Oxygen potential in core debris and the pattern of dependency may be different for different FP elements. (author)

Proceedings of a specialist meeting on boron reactivity transients

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

The CSNI Specialist Meeting on Boron Dilution Reactivity Transients was hosted by the Penn State University in collaboration with the US Nuclear Regulatory Commission and the TRAC Users Group. More than 70 experts from 12 OECD countries, as well as experts from Russia and other non-OECD countries attended the meeting. Thirty papers were presented in five technical sessions. The purpose of the meeting was to bring together experts involved in the different activities related to boron dilution transients. The experts came from all involved parties, including research organizations, regulatory authorities, vendors and utilities. Information was openly shared and discussed on the experimental results, plant and systems analysis, numerical analysis of mixing and probability and consequences of these transients. Regulatory background and licensing implications were also included to provide the proper frame work for the technical discussion. Each of these areas corresponded to a separate session. The meeting focused on the thermal-hydraulic aspects because of the current interest in that subject and the significant amount of new technical information being generated. Three papers of the same conference are already available in INIS as individual reports: Potential for boron dilution during small-break LOCAs in PWRs (Ref. number: 27029412); Analysis of boron dilution in a four-loop PWR (Ref. number: 27051651); Probability and consequences of a rapid boron dilution sequence in a PWR (Ref. number: 27029411)

OECD-NEA criticality working group - a status report and the burnup credit challenge

International Nuclear Information System (INIS)

Whitesides, G.E.

1993-01-01

A Working Group established by the organization for Economic Co-operation and Development's Nuclear Energy Agency (OECD-NEA), Paris, has examined the validity of computational methods used for calculations that evaluate the nuclear criticality safety issues involved in the storage, handling and transportation of fissile materials. The basic goal of this Working Group is to attempt to define and implement a procedure that can be shown to demonstrate the validity of the various computational methods used to make criticality safety calculations. The current activities of the Working Group involve an effort to establish the validity of computational methods used to evaluate the criticality safety of the storage, handling, and transportation of spent light-water-reactor fuel elements in which one seeks to take credit for the fissile material burnup and/or buildup of fission products. (J.P.N.)

2017 NEA Annual Report: Nuclear Power in 2017; Innovation and Education: Necessary Enablers for Sustainable Nuclear Energy, or the Virtuous Circle; NEA Activities by Sector

International Nuclear Information System (INIS)

2018-01-01

The NEA Annual Report of the OECD Nuclear Energy Agency (NEA) for the year ending on 31 December 2017 provides an overview of the status of nuclear power in OECD countries and illustrative descriptions of the Agency's activities and international joint projects. Content: 1 - Message from the Director-General; 2 - Innovation and Education: Necessary Enablers for Sustainable Nuclear Energy, or the Virtuous Circle; 3 - Nuclear Technology in 2017; 4 - NEA Activities by Sector: Nuclear Development, Nuclear Safety and Regulation, Human Aspects of Nuclear Safety, Radiological Protection, Radioactive Waste Management, Nuclear Science, Data Bank, Legal Affairs, 5 - General Information: Information and Communications, Organisational Structure of the NEA, NEA Committee Structure in 2017, NEA Management Structure in 2017, NEA Publications and Brochures Produced in 2017

The third phase of the OECD/NEA TDB project: TDB III

International Nuclear Information System (INIS)

Mompean, F.J.; Illemassene, M.; Perrone, J.

2005-01-01

In 2003 with a foreseen duration of four years. The main objective of this new phase is to extend the existing critically reviewed database for elements of relevance in radioactive waste management, paying attention to the needs of the various national programmes. Following the decision by the Project Management Board (integrated by representatives of 16 organisations with responsibilities in radioactive waste management in 12 OECD member countries) the elements contemplated in this new phase are Th, Sn and Fe, with a higher priority being allocated to inorganic species and compounds. In addition to the corresponding review teams for these elements, an additional expert team has been constituted to prepare guidelines for the evaluation of thermodynamic data for solid solutions. As was the case in TDB Phase II, the basic project review methodology remains unaltered in TDB III. The Figure illustrates the relationship between the various TDB bodies, with an International Organisation, the OECD NEA, acting as Project Coordinator and linking the independent scientific teams and the project governing bodies. This organizational paradigm has proven successful with the recent completion of the five Phase II Reviews (Update, Ni, Se, Zr and Organic Ligands). The review and expert team activities were started in 2004 (except for Fe, being started in 2005) following an initiation stage. This preliminary stage was designed in order to tailor the team compositions to the existing literature for each element. The first reviews stemming from TDB III are scheduled to appear in published form in 2007. The successful completion of these objectives will add three further reports to the current series of nine volumes (dealing with the chemical thermodynamics of U, Np, Pu, Am, Tc, Ni, Se, Zr and compounds and complexes of these elements with oxalate, citrate, EDTA and isa). (authors)

State of Art Report for the OECD-NEA Loss-of-Forced Cooling (LOFC) Test Project using HTTR Reactor

International Nuclear Information System (INIS)

Jun, Ji Su

2011-05-01

The OECD/NEA Project is planned to perform the LOFC (Loss Of Forced Cooling) test using the HTTR (High Temperature engineering Test Reactor) in Japan from 31 March 2011 to 31 March 2013 in order to obtain the data for the code validation of the VHTR safety analysis. Based on the Project Agreement Document, this report gives a description of the HTTR-LOFC test, HTTR test facility, project schedule and deliverable items as the technical state art of the project, and appends the full translation of the project agreement articles on the project management

OECD/CSNI Workshop on In-Vessel Core Debris Retention and Coolability - Summary and Conclusions

International Nuclear Information System (INIS)

Behbahani, Ali-Reza; Drozd, Andrzej; Kim, Sang-Baik; Micaelli, Jean-Claude; Okkonen, Timo; Sugimoto, Jun; Trambauer, Klaus; Tuomisto, Harri

1999-01-01

In the spring of 1994 an OECD Workshop on Large Pool Heat transfer was held in Grenoble. The scope of this workshop was the investigation of (1) molten pool heat transfer, (2) heat transfer to the surrounding water, and (3) the feasibility of in-vessel core debris cooling through external cooling of the vessel. Since this time, experimental test series have been completed (e.g., COPO, ULPU, CORVIS) and new experimental programs (e.g., BALI, SONATA, RASPLAV, debris and gap heat transfer) have been established to consolidate and expand the data base for further model development and to improve the understanding of in-vessel debris retention and coolability in a nuclear power plant. Discussions within the CSNI's PWG-2 and the Task Group on Degraded Core Cooling (TG-DCC) have led to the conclusion that the time was ripe for organizing a new international Workshop with the objectives: - to review the results of experimental research that has been conducted in this area; - to exchange information on the results of member countries experiments and model development on in-vessel core debris retention and coolability; - to discuss areas where additional experimental research is needed in order to provide an adequate data base for analytical model development for core debris retention and coolability. The scope of this workshop was limited to the phenomena connected to in-vessel core debris retention and coolability and did not include steam explosion and fission product issues. The workshop was structured into the following sessions: Key note papers; Experiments and model development; Debris bed heat transfer; Corium properties, molten pool convection and crust formation; Gap formation and gap cooling; Creep behaviour of reactor pressure vessel lower head; Ex-vessel boiling and critical heat flux phenomena; Scaling to reactor severe accident conditions and reactor applications. Compared to the previous workshop held in Grenoble in 1994, large progress has been made in the

Experimental facilities for gas-cooled reactor safety studies. Task group on Advanced Reactor Experimental Facilities (TAREF)

International Nuclear Information System (INIS)

2009-01-01

In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) which focused on facilities suitable for current and advanced water reactor systems. In a subsequent collective opinion on the subject, the CSNI recommended to conduct a similar exercise for Generation IV reactor designs, aiming to develop a strategy for ' better preparing the CSNI to play a role in the planned extension of safety research beyond the needs set by current operating reactors'. In that context, the CSNI established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facilities suitable for performing safety research relevant to gas-cooled reactors and sodium fast reactors. This report addresses gas-cooled reactors; a similar report covering sodium fast reactors is under preparation. The findings of the TAREF are expected to trigger internationally funded CSNI projects on relevant safety issues at the key facilities identified. Such CSNI-sponsored projects constitute a means for efficiently obtaining the necessary data through internationally co-ordinated research. This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for gas-cooled reactors and identifies priorities for organizing international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems. (author)

In-vessel core degradation in LWR severe accidents: a state of the art report to CSNI january 1991

International Nuclear Information System (INIS)

1991-11-01

This state of the art report on in-vessel core degradation has been produced at the request of CSNI Principal Working Group 2. The objective of the report is to present to CSNI member countries the status of research and related information on in-vessel degraded core behaviour in both Pressurised Water Reactors (PWR) and Boiling Water Reactors (BWR). Information on experiments, codes and comparisons of calculations with experiments up to january 1991 is summarised and reviewed. Integrated codes, which are wider in scope than just in-vessel degradation are covered as well as specialist, degraded core codes. Implications for PWR and BWR plant calculations are considered. Conclusions and recommendations for research, plant calculations and further CSNI activity in this area are the subject of the final chapter. A major conclusion of the report is that early phase core degradation is relatively well understood. However, codes need further development to bring them up to date with the experimental database, particularly to include low temperature liquefaction processes. These processes significantly affect early phase core degradation and their neglect could affect assessments of accident management actions (including recriticality in BWR severe accidents)

NEA Annual Report 2014

International Nuclear Information System (INIS)

2015-01-01

The OECD Nuclear Energy Agency (NEA) was established on 1 February 1958. Current NEA membership consists of 31 countries: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Korea, Luxembourg, Mexico, the Netherlands, Norway, Poland, Portugal, Russia, the Slovak Republic, Slovenia, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The European Commission also takes part in the work of the Agency. The mission of the NEA is: - to assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes; - to provide authoritative assessments and to forge common understandings on key issues, as input to government decisions on nuclear energy policy and to broader OECD policy analyses in areas such as energy and sustainable development. Specific areas of competence of the NEA include the safety and regulation of nuclear activities, radioactive waste management, radiological protection, nuclear science, economic and technical analyses of the nuclear fuel cycle, nuclear law and liability, and public information. The NEA Data Bank provides nuclear data and computer program services for participating countries. In these and related tasks, the NEA works in close collaboration with the International Atomic Energy Agency in Vienna, with which it has a Co-operation Agreement, as well as with other international organisations in the nuclear field. This document summarizes the 2014 activities of NEA. Content: 1. Message from the Director-General; 2. Nuclear Power in 2014; 3. The Fukushima Daiichi Accident and NEA Follow-up; 4. NEA Activities by Sector: Nuclear Development, Nuclear Safety and Regulation, Radioactive Waste Management, Radiological Protection, Nuclear Science, Data Bank

The University of Pisa calculations for the Phase I of the OECD/NEA UAM Benchmark

International Nuclear Information System (INIS)

Ball, M.; Parisi, C.; D'Auria, F.

2009-01-01

In this paper we present the Univ. of Pisa preliminary results for the first exercise of the Phase I of the OECD/NEA Benchmark on the Uncertainty in Analysis and Modeling. The scope of exercise one is to address the uncertainties due to the basic nuclear data as well as the impact of processing the nuclear and covariance data, selection of multi-group structure and self-shielding treatment. DRAGON code and TSUNAMI code were employed, using the available covariance data matrix. The execution of DRAGON calculations required the use of ANGELO and LAMBDA codes for the extension of the covariance matrix from the original SCALE 44 group structure to DRAGON 69 group structure. The uncertainties for the main cross sections were evaluated and are presented here. (authors)

Specialist meeting on selected containment severe accident management strategies. Summary and conclusions

International Nuclear Information System (INIS)

1994-01-01

The CSNI Specialist Meeting on Selected Containment Severe Accident Management Strategies held in Stockholm, Sweden in June 1994 was organised by the Task Group on Containment Aspects of Severe Accident Management (CAM) of CSNI's Principal Working Group on the Confinement of Accidental Radioactive Releases (PWG4) in collaboration with the Swedish Nuclear Power Inspectorate (SKI). Conclusions and recommendations are given for each of the sessions of the workshops: Containment accident management strategies (general aspects); hydrogen management techniques and other containment accident management techniques; surveillance and protection of containment function

CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings

Energy Technology Data Exchange (ETDEWEB)

1984-08-01

On September 1 and 2, 1983, the CSNI subcommittee on primary system integrity held a special meeting in Monterey, California, on the subject of leak-before-break in nuclear reactor piping systems. The purpose of the meeting was to provide an international forum for the exchange of ideas, positions, and research results; to identify areas requiring additional research and development; and to determine the general attitude toward acceptance of the leak-before-break concept. The importance of the leak-before-break issue was evidenced by excellent attendance at the meeting and through active participation by the meeting attendees. Approximately 125 people representing fifteen different nations attended the meeting. The meeting was divided into four technical sessions addressing the following areas: Application of Piping Fracture Mechanics to Leak-Before Break, Leak Rate and Leak Detection, Leak-Before-Break Studies, Methods and Results, Current and Proposed Positions on Leak-Before-Break.

CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings

International Nuclear Information System (INIS)

1984-08-01

On September 1 and 2, 1983, the CSNI subcommittee on primary system integrity held a special meeting in Monterey, California, on the subject of leak-before-break in nuclear reactor piping systems. The purpose of the meeting was to provide an international forum for the exchange of ideas, positions, and research results; to identify areas requiring additional research and development; and to determine the general attitude toward acceptance of the leak-before-break concept. The importance of the leak-before-break issue was evidenced by excellent attendance at the meeting and through active participation by the meeting attendees. Approximately 125 people representing fifteen different nations attended the meeting. The meeting was divided into four technical sessions addressing the following areas: Application of Piping Fracture Mechanics to Leak-Before Break, Leak Rate and Leak Detection, Leak-Before-Break Studies, Methods and Results, Current and Proposed Positions on Leak-Before-Break

Proceedings of the specialist meeting on personal dosimetry and area monitoring suitable for radon and daughter products

International Nuclear Information System (INIS)

Anon.

1979-01-01

The programme of work of the OECD Nuclear Energy Agency includes topics relating to radiation and environmental protection matters in mining and milling operations. A first Specialist Meeting on Personal Dosimetry and Area Monitoring suitable for Radon and Daughter Products was organised in October 1976 at Elliot Lake, Canada. The proceedings were published by NEA some months later. Following an enquiry among interested persons, NEA decided to organise a new meeting on the same subject in Paris from 20th to 22nd November 1978. The meeting dealt with questions relating to personal dosimetry techniques, the monitoring of the atmosphere in mines and their neighbourhood, as well as in buildings

Falsire: CSNI project for fracture analyses of large-scale international reference experiments (Phase 1). Comparison report

International Nuclear Information System (INIS)

1994-01-01

A summary of the recently completed Phase I of the Project for Fracture Analysis of Large-Scale International Reference Experiments (Project FALSIRE) is presented. Project FALSIRE was created by the Fracture Assessment Group (FAG) of Principal Working Group No. 3 (PWG/3) of the OECD/NEA Committee on the Safety of Nuclear Installations (CSNI), formed to evaluate fracture prediction capabilities currently used in safety assessments of nuclear vessel components. The aim of the Project FALSIRE was to assess various fracture methodologies through interpretive analyses of selected large-scale fracture experiments. The six experiments used in Project FALSIRE (performed in the Federal Republic of Germany, Japan, the United Kingdom, and the U.S.A.) were designed to examine various aspects of crack growth in reactor pressure vessel (RPV) steels under pressurized-thermal-shock (PTS) loading conditions. The analysis techniques employed by the participants included engineering and finite-element methods, which were combined with Jr fracture methodology and the French local approach. For each experiment, analysis results provided estimates of variables such as crack growth, crack-mouth-opening displacement, temperature, stress, strain, and applied J and K values. A comparative assessment and discussion of the analysis results are presented; also, the current status of the entire results data base is summarized. Some conclusions concerning predictive capabilities of selected ductile fracture methodologies, as applied to RPVs subjected to PTS loading, are given, and recommendations for future development of fracture methodologies are made

Assessment of the uncertainties of COBRA sub-channel calculations by using a PWR type rod bundle and the OECD NEA UAM and the PSBT benchmarks data

International Nuclear Information System (INIS)

Panka, I.; Kereszturi, A.

2014-01-01

The assessment of the uncertainties of COBRA-IIIC thermal-hydraulic analyses of rod bundles is performed for a 5-by-5 bundle representing a PWR fuel assembly. In the first part of the paper the modeling uncertainties are evaluated in the term of the uncertainty of the turbulent mixing factor using the OECD NEA/NRC PSBT benchmark data. After that the uncertainties of the COBRA calculations are discussed performing Monte-Carlo type statistical analyses taking into account the modeling uncertainties and other uncertainties prescribed in the OECD NEA UAM benchmark specification. Both steady-state and transient cases are investigated. The target quantities are the uncertainties of the void distribution, the moderator density, the moderator temperature and the DNBR. We will see that - beyond the uncertainties of the geometry and the boundary conditions - it is very important to take into account the modeling uncertainties in case of bundle or sub-channel thermo-hydraulic calculations.

Establishment of data base files of thermodynamic data developed by OECD/NEA. Pt. 1. Thermodynamic data of Np and Pu

International Nuclear Information System (INIS)

Yoshida, Yasushi; Sasamoto, Hiroshi

2004-01-01

Thermodynamic data base for compounds and complexes of actinides and fission products specialized in modeling requirements for safety assessments of radioactive waste disposal systems are being developed by NEA TDB project of OECD/NEA. In this project, relevant data bases for compounds and complexes of Np and Pu were published in 2001. JNC established the data base files available for geochemical calculation codes using these Np and Pu published data. And this procedure for establishment and contents of data base files are described in this report. These data base files were prepared as the formats of major geochemical codes PHREEQE, PHREEQC, EQ3/6 and Geochemist's workbench. Additionally modification for data in the thermodynamic data base files which had been already published by JNC was also done. This procedure and revised data bases are shown in the appendix of this report. (author)

OECD/NEA data bank scientific and integral experiments databases in support of knowledge preservation and transfer

International Nuclear Information System (INIS)

Sartori, E.; Kodeli, I.; Mompean, F.J.; Briggs, J.B.; Gado, J.; Hasegawa, A.; D'hondt, P.; Wiesenack, W.; Zaetta, A.

2004-01-01

The OECD/Nuclear Energy Data Bank was established by its member countries as an institution to allow effective sharing of knowledge and its basic underlying information and data in key areas of nuclear science and technology. The activities as regards preserving and transferring knowledge consist of the: 1) Acquisition of basic nuclear data, computer codes and experimental system data needed over a wide range of nuclear and radiation applications; 2) Independent verification and validation of these data using quality assurance methods, adding value through international benchmark exercises, workshops and meetings and by issuing relevant reports with conclusions and recommendations, as well as by organising training courses to ensure their qualified and competent use; 3) Dissemination of the different products to authorised establishments in member countries and collecting and integrating user feedback. Of particular importance has been the establishment of basic and integral experiments databases and the methodology developed with the aim of knowledge preservation and transfer. Databases established thus far include: 1) IRPhE - International Reactor Physics Experimental Benchmarks Evaluations, 2) SINBAD - a radiation shielding experiments database (nuclear reactors, fusion neutronics and accelerators), 3) IFPE - International Fuel Performance Benchmark Experiments Database, 4) TDB - The Thermochemical Database Project, 5) ICSBE - International Nuclear Criticality Safety Benchmark Evaluations, 6) CCVM - CSNI Code Validation Matrix of Thermal-hydraulic Codes for LWR LOCA and Transients. This paper will concentrate on knowledge preservation and transfer concepts and methods related to some of the integral experiments and TDB. (author)

OECD Nuclear Energy Agency activities on PTS evaluation

International Nuclear Information System (INIS)

Miller, A.

1997-01-01

The Safety Division of the OECD Nuclear Energy Agency provides the secretariat for the Committee on the Safety of Nuclear Installations (CSNI), which deals with technological aspects, and for the Committee for Nuclear Regulatory Activities (CNRA) dealing with regulatory aspects. Under these committees, activities are carried out through five Principal Working Groups (PWGs). The relevant group for PTS is PWG-3 on the integrity of structures and components. There is also PWG-2 on coolant system behavior, but the thermal hydraulic aspects of PTS have not been considered by PWG-2. PWG-3 carries out it work in a similar manner to the IAEA IWG LMNPP, by preparing reports and organizing round robins, Specialists Meetings and Workshops. The general context of RPV PTS has been considered in several workshops: on the 'Complementary roles of Fracture Mechanics and Non-Destructive Examination in the Safety Assessment of Components' in Wuerenlingen in 1988; on the 'Safety Assessment of RPVs' in Espoo in 1990; and on 'Fracture Mechanics Verification by Large Scale Testing' (joint with IAEA) at Oak Ridge in 1992. Activities specific to PTS have been an international survey on regulatory practices on PTS carried out in 1991, and a series of fracture round robins addressing PTS conditions organized by GRS in Germany and ORNL in the USA. 3 refs, 5 tabs

OECD Nuclear Energy Agency activities on PTS evaluation

Energy Technology Data Exchange (ETDEWEB)

Miller, A [NEA Nuclear Safety Div., Issy-les-Moulineaux (France)

1997-09-01

The Safety Division of the OECD Nuclear Energy Agency provides the secretariat for the Committee on the Safety of Nuclear Installations (CSNI), which deals with technological aspects, and for the Committee for Nuclear Regulatory Activities (CNRA) dealing with regulatory aspects. Under these committees, activities are carried out through five Principal Working Groups (PWGs). The relevant group for PTS is PWG-3 on the integrity of structures and components. There is also PWG-2 on coolant system behavior, but the thermal hydraulic aspects of PTS have not been considered by PWG-2. PWG-3 carries out it work in a similar manner to the IAEA IWG LMNPP, by preparing reports and organizing round robins, Specialists Meetings and Workshops. The general context of RPV PTS has been considered in several workshops: on the `Complementary roles of Fracture Mechanics and Non-Destructive Examination in the Safety Assessment of Components` in Wuerenlingen in 1988; on the `Safety Assessment of RPVs` in Espoo in 1990; and on `Fracture Mechanics Verification by Large Scale Testing` (joint with IAEA) at Oak Ridge in 1992. Activities specific to PTS have been an international survey on regulatory practices on PTS carried out in 1991, and a series of fracture round robins addressing PTS conditions organized by GRS in Germany and ORNL in the USA. 3 refs, 5 tabs.

OECD/NEA Radiological characterisation in decommissioning - Evaluation of questionnaire. Strategies for Radiological Characterisation used by Decommissioning Projects in OECD Countries

International Nuclear Information System (INIS)

Thierfeldt, Stefan; Haneke, K.

2012-01-01

In the first half of 2011, the Radiological Characterization and Decommissioning Task Group (RCD) of the WPDD of the OECD/NEA has prepared a questionnaire on the characterisation of nuclear facilities that has been circulated among nuclear installations in various OECD countries. The aim of this questionnaire was to gather information on the approaches and methods that are used for radiological characterisation (RC) for systems and components, for buildings and for sites (land), on domestic and international guidance and regulations that govern RC, and on the experience with RC that is already available in the particular country. The number of responses to this questionnaire that were received in the second half of 2011 was very satisfactory, so that a broad overview is now available from the following countries: Belgium, Canada, Denmark, Finland, France, Germany, Japan, Korea, Spain, Sweden, and United Kingdom. The presentation deals with the results that were obtained from the evaluation of these questionnaires and gives overviews of the objectives of characterisation, the input data for planning of characterisation, the measurement techniques that were used for metallic structures and components, for buildings and for sites, the data management and QA measures, the obstacles that were encountered, the experience with availability of as-built plans, the regulatory framework and guidelines, and the costs for RC. All information on RC is further broken down with respect to the operational phase (where RC is used for preliminary decommissioning planning), the transition phase (where RC supports decommissioning planning) and the actual decommissioning phase (where RC is needed for dismantling, decontamination and treatment of systems, components, buildings etc.). The presentation also offers conclusions on these subjects. (authors)

CSNI International standard problems (ISP): brief descriptions (1975-1997)

International Nuclear Information System (INIS)

1997-07-01

Over the last twenty years (1975-1999) the NEA Committee on the Safety of Nuclear Installations (CSNI) has sponsored more than forty International Standard Problems (ISPs) in the fields of in-vessel thermal-hydraulic behaviour, fuel behaviour under accident conditions, fission product release and transport, core/concrete interactions, hydrogen distribution and mixing, containment thermal-hydraulic, and iodine behaviour in the containment. ISPs are comparative exercises in which predictions of different computer codes for a given physical problem are compared with each other or with the results of a carefully controlled experimental study. The main goal of ISP exercises is to increase confidence in the validity and accuracy of analytical tools or testing procedures which are needed in warranting the safety of nuclear installations, and to demonstrate the competence of involved institutions. ISP exercises are performed as 'open' or 'blind' problems. The main characteristics of 41 ISPs completed between 1975 and 1999, and 3 containment analysis standard problems (CASPs) are briefly presented

Application of NEA/CSNI standard problem 3 (blowdown and flow reversal in the IETA-1 rig) to the validation of the RELAP-UK Mk IV code

International Nuclear Information System (INIS)

Bryce, W.M.

1977-10-01

NEA/CSNI Standard Problem 3 consists of the modelling of an experiment on the IETI-1 rig, in which there is initially flow upwards through a feeder, heated section and riser. The inlet and outlet are then closed and a breach opened at the bottom so that the flow reverses and the rig depressurises. Calculations of this problem by many countries using several computer codes have been reported and show a wide spread of results. The purpose of the study reported here was the following. First, to show the sensitivity of the calculation of Standard Problem 3. Second, to perform an ab initio best estimate calculation using the RELAP-UK Mark IV code with the standard recommended options, and third, to use the results of the sensitivity study to show where tuning of the RELAP-UK Mark IV recommended model options was required. This study has shown that the calculation of Standard Problem 3 is sensitive to model assumptions and that the use of the loss-of-coolant accident code RELAP-UK Mk IV with the standard recommended model options predicts the experimental results very well over most of the transient. (U.K.)

Review of fast reactor activities at OECD (NEA), March 1979

Energy Technology Data Exchange (ETDEWEB)

Royen, J

1979-07-01

In February 1978, OECD(NEA) published an expert group report on 'Nuclear Fuel Cycle Requirements and Supply Considerations, Through the Long Term'. In publishing this report, the Agency sought to fulfil three objectives. First, as a source of data on uranium and fuel cycle services, the report identified future imbalances between supply and demand, and possible areas for international cooperation in the resolution of such problems. Secondly, in examining several alternative nuclear power scenarios through the long term (defined as the year 2025), it showed the comparative needs of advanced reactors for uranium and for supporting services, thereby establishing the basis for further development of uranium resources and specific reactor systems. Finally, as a comprehensive data source, it should provide assistance to those having responsibilities in planning, forecasting, and programme management in areas relating to the fuel cycle. An analysis of alternative reactor strategies in the longer term makes it clear that continued reliance on thermal converters in this period will result in rapid depletion of known uranium resources. Even with dramatic increases in known resources, nuclear power would be able to play only a temporary role in satisfying world energy needs. The use of advanced near-breeders (including those which utilise thorium) can do much to reduce the total rate of depletion of uranium resources, but their requirements will still result in eventual depletion of known resources. On the other hand, breeder reactors would provide a virtually inexhaustible source of energy supply within foreseeable extensions of known uranium resources. In fact, the introduction of breeders in the longer term could, by the year 2025, reduce annual requirements for uranium at or below levels for the year 2000. By the year 2025, the cumulative uranium requirements of the breeder can have reached a plateau, while the cumulative requirements of other reactor strategies would

Proceedings of the first part of a joint OECD(NEA)/CEC workshop on recent advances in reactor accident consequence assessment

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-02-15

The first part of the Joint Workshop, organised by the NEA, is focused on the progress achieved in the work of CSNI's GRECA (Group of Experts on Accident Consequences). The program is composed of the following papers. Session 1: characteristics of the Chernobyl release and fallout that affect transport and behaviour of radioactive substances in the environment; Chernobyl accident and hot particles in the fallout; radionuclides associated with colloids and particles in the Chernobyl fallout; source term in the Chernobyl accident; long range transport of radionuclides; parameters in consequence calculations for an urban area. Session 2: review of evaluations concerning radionuclide transfer to foodstuffs via plants in view of the data available after the Chernobyl accident; GRECA review of Chernobyl data on transfer to animal products; Chernobyl accident radiometric data (Cs-137 in fresh water fishes of north Italy lakes); distribution of Cs-137 in water sediment and fish in the Ijsselmeer (Netherlands); uptake in the human body resulting from the Chernobyl accident; radioactivity of people in the nordic countries following the Chernobyl accident; preparations for an international study to evaluate long-range transport models against the Chernobyl accident

The OECD/NEA workshop on the indemnification of nuclear damage in the event of a nuclear accident

International Nuclear Information System (INIS)

Wagstaff, F.

2002-01-01

Since 1993, the OECD Nuclear Energy Agency (OECD/NEA) has run the International Nuclear Emergency Exercise (INEX) Program. The program serves to discuss an effective accident management approach on the basis of a simulated nuclear accident situation together with the states involved and their institutions, and also elaborate measures for its further improvement. At the present time, the INEX Program has reached Phase 3 in which, for the first time, also aspects of liability for the consequences of accidents were included. These aspects were made the subject of a workshop held after an emergency exercise. The scenario covered was based on an INES level-4 accident in the French Gravelines Nuclear Power Station situated close to the French-Belgian border. The workshop dealt with these topics, among others: the application of the Paris Convention on Third Party Liability, the Brussels Supplementary Convention, and the Vienna Convention on Civil Liability for Nuclear Damage as well as the Supplementary Compensation Convention of 1997. It was seen that there was a clear need for further discussion, especially to shed more light on the interrelationship of these treaties. (orig.) [de

TRACE/PARCS analysis of the OECD/NEA Oskarshamn-2 BWR stability benchmark

Energy Technology Data Exchange (ETDEWEB)

Kozlowski, T. [Univ. of Illinois, Urbana-Champaign, IL (United States); Downar, T.; Xu, Y.; Wysocki, A. [Univ. of Michigan, Ann Arbor, MI (United States); Ivanov, K.; Magedanz, J.; Hardgrove, M. [Pennsylvania State Univ., Univ. Park, PA (United States); March-Leuba, J. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Hudson, N.; Woodyatt, D. [Nuclear Regulatory Commission, Rockville, MD (United States)

2012-07-01

On February 25, 1999, the Oskarshamn-2 NPP experienced a stability event which culminated in diverging power oscillations with a decay ratio of about 1.4. The event was successfully modeled by the TRACE/PARCS coupled code system, and further analysis of the event is described in this paper. The results show very good agreement with the plant data, capturing the entire behavior of the transient including the onset of instability, growth of the oscillations (decay ratio) and oscillation frequency. This provides confidence in the prediction of other parameters which are not available from the plant records. The event provides coupled code validation for a challenging BWR stability event, which involves the accurate simulation of neutron kinetics (NK), thermal-hydraulics (TH), and TH/NK. coupling. The success of this work has demonstrated the ability of the 3-D coupled systems code TRACE/PARCS to capture the complex behavior of BWR stability events. The problem was released as an international OECD/NEA benchmark, and it is the first benchmark based on measured plant data for a stability event with a DR greater than one. Interested participants are invited to contact authors for more information. (authors)

NEA Data Bank Progress Report 2010-2011

International Nuclear Information System (INIS)

2011-01-01

The OECD NEA Data Bank provides scientist in member countries with reference materials in the field of nuclear energy applications. The services include the compilation, verification, and distribution of nuclear data, chemical thermodynamic data, integral benchmark experiments, as well as computer programs and associated application libraries. The Data Bank also develops and maintains databases and related administration/retrieval tools, including the JANIS display software. The Data Bank works in close co-operation with the Nuclear Science Section, especially in the field of computer codes and associated application libraries benchmarking, integral experiments, nuclear data evaluation co-operation, and knowledge preservation. These activities are in essence international and organised in close collaboration with other main national and international organisations. More information on the NEA Data Bank can be found at www.oecd-nea.org/databank.

TRACE/PARCS validation for BWR stability based on OECD/NEA Oskarshamn-2 benchmark

International Nuclear Information System (INIS)

Kozlowski, T.; Roshan, S.; Lefvert, T.; Downar, T.; Xu, Y.; Wysocki, A.; Ivanov, K.; Magedanz, J.; Hardgrove, M.; Netterbrant, C.; March-Leuba, J.; Hudson, N.; Sandervag, O.; Bergman, A.

2011-01-01

On February 25, 1999, the Oskarshamn-2 NPP experienced a stability event, which culminated in diverging power oscillations with decay ratio greater than 1.3. The event was successfully modeled by TRACE/PARCS coupled code system and the details of the modeling and solution are described in the paper. The obtained results show excellent agreement with the plant data, capturing the entire behavior of the transient including onset of instability, growth of oscillation (decay ratio) and the oscillation frequency. The event allows coupled code validation for BWR with a real, challenging stability event, which challenges accuracy of neutron kinetics (NK), thermal-hydraulics (TH) and TH/NK coupling. The success of this work has demonstrated the ability of 3-D coupled code systems to capture the complex behavior of BWR stability events. The problem is released as an international OECD/NEA benchmark, and it is the first benchmark based on measured plant data for a stability event with a DR greater than one. Interested participants are invited to contact authors for more information. (author)

Operating Plan and Guidelines (2011 - 2016)

International Nuclear Information System (INIS)

2011-01-01

The Committee on Nuclear Regulatory Activities (CNRA) of the OECD Nuclear Energy Agency (NEA) is an international committee made up primarily of senior nuclear regulators. It was established in 1989 as a forum for the exchange of information and experience among regulatory organisations and for the review of developments which could affect regulatory requirements. The Committee is responsible for the programme of the NEA, concerning the regulation, licensing and inspection of nuclear installations. In particular, the Committee reviews current practices and operating experience. The Joint CSNI/CNRA Strategic Plan states that: The Operating Plan for each committee aligns with the Joint CNRA/ CSNI Strategic Plan. The Committee's Operating Plans describes each Committee's organisation, priorities, and operating procedures to be used in fulfilling their mandates in accordance with this strategic plan. Specific attention will be given to ensure that cross-cutting issues are satisfactorily dealt with. This report represents such an operating plan. The intention is that it should fit onto a new third rung on the ladder representing the hierarchy of documents that govern the work of CNRA. At the top of this hierarchy is the Strategic Plan of the NEA; immediately below that is the Joint CSNI/CNRA Strategic Plan; followed by the new operating plan and the guidelines for methods of work. This plan sets the basis for establishing the current CNRA Programme of Work. Since the issuance of the last plan in 2007 there has been a significant shift and many member countries are now constructing new facilities or in the process of legislative or technical processing for new licenses. This comes along in an atmosphere in which current operating plants requesting power up-rates, extended licenses, and substantial activity in new licensing and new construction. It is clear that all these activities require similar attention from the regulators and operators, and the responsibilities

Proceedings of the CSNI Specialist Meeting on Transient Two-Phase Flow - Current Issues in System Thermal Hydraulics

Energy Technology Data Exchange (ETDEWEB)

Reocreux, M; Rubinstein, M C [CEA-IPSN/DRS/SEMAR, Centre d' Etudes Nucleaires de Cadarache, 13108 Saint Paul-lez-Durance (France)

1992-07-01

The 4. Specialists' Meeting on Transient Two Phase Flow was organized by the Safety Research Department of the French Nuclear Safety and Protection Institute at the request of the OECD Committee for the Safety of Nuclear Installations. After Toronto in 1976, Paris in 1978 and Pasadena in 1981, the Aix-en-Provence meeting was in keeping with the course of studies initiated by the Thermalhydraulic Systems Behavior Task Group of the Principal Working Group No.2 for discussing the achievements and defining the needs of safety research in accident thermal-hydraulics. 60 Specialists from 14 Countries (Belgium, Canada, Finland, France, Germany, Italy, Japan, the Netherlands, the United Kingdom, the USA, Spain, Sweden, Switzerland, Taiwan) attended the meeting, representing a large spectrum of experts from National Safety Authorities, Research Laboratories, Universities, Vendors and Utilities. These specialists had to review the 15-year research period which had elapsed since the last meetings. This period had been characterized by the issuance of the large thermalhydraulic computer codes for LWR accidents, the performance of several hundreds of separate effect tests for the development and the qualification of the physical models, the carrying-out of the large experimental programmes on system loops (up to scale 1) for verifying the computer codes. Although this research was mainly characterized by remarkable success, limitations still exist. In a safety approach, there need to be well identified and handled, and the specialists were asked to exchange their views in order to determine which solutions they expected to be affordable in the future. Safety applications have already started which use these latest research achievements. They raise specific problems such as the use of validation matrices, the evaluation of uncertainties, the identification and the control of unavoidable users' effects. The specialists were required to exchange their experience of applications

Proceedings of the CSNI Specialist Meeting on Transient Two-Phase Flow - Current Issues in System Thermal Hydraulics

International Nuclear Information System (INIS)

Reocreux, M.; Rubinstein, M.C.

1992-01-01

The 4. Specialists' Meeting on Transient Two Phase Flow was organized by the Safety Research Department of the French Nuclear Safety and Protection Institute at the request of the OECD Committee for the Safety of Nuclear Installations. After Toronto in 1976, Paris in 1978 and Pasadena in 1981, the Aix-en-Provence meeting was in keeping with the course of studies initiated by the Thermalhydraulic Systems Behavior Task Group of the Principal Working Group No.2 for discussing the achievements and defining the needs of safety research in accident thermal-hydraulics. 60 Specialists from 14 Countries (Belgium, Canada, Finland, France, Germany, Italy, Japan, the Netherlands, the United Kingdom, the USA, Spain, Sweden, Switzerland, Taiwan) attended the meeting, representing a large spectrum of experts from National Safety Authorities, Research Laboratories, Universities, Vendors and Utilities. These specialists had to review the 15-year research period which had elapsed since the last meetings. This period had been characterized by the issuance of the large thermalhydraulic computer codes for LWR accidents, the performance of several hundreds of separate effect tests for the development and the qualification of the physical models, the carrying-out of the large experimental programmes on system loops (up to scale 1) for verifying the computer codes. Although this research was mainly characterized by remarkable success, limitations still exist. In a safety approach, there need to be well identified and handled, and the specialists were asked to exchange their views in order to determine which solutions they expected to be affordable in the future. Safety applications have already started which use these latest research achievements. They raise specific problems such as the use of validation matrices, the evaluation of uncertainties, the identification and the control of unavoidable users' effects. The specialists were required to exchange their experience of applications

A review of the OECD/NEA Study on the economics of the nuclear fuel cycle

International Nuclear Information System (INIS)

Zarimpas, N.; Stevens, G.H.; Nuclear Energy Agency

1994-01-01

The paper presents an overview of the recent study carried out by OECD's Nuclear Energy Agency on the economics of the nuclear fuel cycle. The investment appraisal method of deriving the lifetime levelised fuel cost required the examination of the entire fuel cycle cash outflow based on component prices. The cash outflows were discounted to a base date using the selected discount rate which was set, for the reference case, at 5 per cent per annum (real). The levelised fuel cycle cost was derived in mills/kWh terms by equating the net present value of the entire fuel cycle cost and the net present value of the total electrical output over the station lifetime, where both have been discounted to the same date. The study's reference fuel cycle options and costs are discussed and a comparison with earlier NEA work is provided. 6 refs., 2 tabs., 3 figs

The NEA thermochemical database project. 30 years of accomplishments

International Nuclear Information System (INIS)

Ragoussi, Maria-Eleni; Brassinnes, Stephane

2015-01-01

The NEA Thermochemical Database (TDB) Project (www.oecd-nea.org/dbtdb/) provides a database of chemical thermodynamic values treating the most significant elements related to nuclear waste management. The work carried out since the initiation of TDB in 1984 has resulted in the publication of thirteen major reviews and a large set of selected values that have become an international reference in the field, as they are characterized for their accuracy, consistency and high quality. Herein, we describe the basis, scientific principles and organization of the TDB project, together with its evolution from its inception to the present organization as a joint undertaking under Article 5(b) of the Statute of the OECD Nuclear Energy Agency (NEA).

Summary Record of the 15th Meeting of the Working Group on Risk Assessment (WGRISK)

International Nuclear Information System (INIS)

2015-01-01

The main mission of the working group on risk assessment (WGRISK) is to advance the understanding and utilisation of probabilistic safety assessment (PSA) in ensuring the continued safety of nuclear installations in member countries. While PSA methodology has matured greatly over the years, further work is required. WGRISK has been active in several of these areas, including: human reliability; software reliability; low power and shutdown risk. In order to maintain a current perspective, the working group collaborates and assists other working groups within the CSNI, such as operating experience and organisational factors as well as keeping close co-ordination with other international organisations. Over the past twenty years, the NEA PWG5 and now WGRISK have looked at the technology and methods used for identifying contributors to risk and assessing their importance. Work during much of this period was concentrated on Level-1 PSA methodology. In recent years the focus has shifted into more specific PSA methodologies and risk-informed applications. This document summarizes the content of the 15. Meeting of WGRISK: - presentation of the new WGRISK Bureau, - Approval of the 14. WGRISK Meeting Summary Record [NEA/SEN/SIN/WGRISK (2013)1], - Use and Development of PSA in NEA Member Countries and by other International Organisations, - Report by the WGRISK Secretariat on the current WGRISK programme of work, actions taken by CSNI and CNRA and other recent developments in OECD/NEA, - Development of BPGs on failure mode taxonomy for reliability assessment of digital I and C systems for PSA [Task 2010-3], - Update Use of OECD Data Project Products in PSA [Task 2011-1], - Status report on the common WGHOF/WGRISK HRA Task, - Outcome on the International Workshop on PSA of Natural External Hazards Including Earthquakes, April 2014 [Task 2012-1], - Status report on the International Workshop on Fire PRA [Task 2012-2], - PSA insights relating to the loss of electrical sources

NEA Data Bank Progress Report 2011-2012

International Nuclear Information System (INIS)

Matsumoto, K.; Duppont, E.

2012-01-01

The Data Bank (DB) of the OECD Nuclear Energy Agency (NEA) provides scientists in member countries with reference materials in the field of nuclear energy applications. The services include the compilation, verification, and distribution of nuclear data, chemical thermodynamic data, integral benchmark experiments, as well as computer programs and associated application libraries. The Data Bank also develops and maintains databases and related administration/retrieval tools, including the JANIS display software. The Data Bank works in close co-operation with the Nuclear Science Section, especially in the field of computer codes and associated application libraries benchmarking, integral experiments, nuclear data evaluation co-operation, and knowledge preservation. These activities are in essence international and organised in close collaboration with other main national and international organisations. More information on the NEA Data Bank can be found at www.oecd-nea.org/databank.

A Summary of the MARS Analysis Results about OECD/SETH PANDA Tests

International Nuclear Information System (INIS)

Bae, Sung Won; Chung, Bub Dong

2007-01-01

The thermal-hydraulic phenomena in a multicompartment space like the containment building under accidents are very complicated and unpredictable as a result of many interacting processes, such as sprays, hydrogen recombiners, etc. Many thermal-hydraulic phenomena, governing the containment response under postulated accidents, have been identified by the SESAR/CAF (OECD) as 'research needs' for current and advanced LWRs. Due to the recent extension of the numerical computation capability and the technology, the safety analysis field is requested to expand their analysis domain beyond the current primary system. In particular, hydrogen mixing and transport has been found to be of special importance for safety and regulation. Up to dates, OECD/CSNI has been leading many experimental projects, for example, OECD-PKL, ISP47, OECD-PANDA, focusing the gas mixing, stratification and vapor condensation phenomena. As the one of the activities, the OECD-SETH group has launched the PANDA Project in order to provide an experimental data base for a multi-dimensional code assessment in 2002. PANDA is a large scale thermal-hydraulic facility to provide a resolved experimental data base about the gas mixing and stratification phenomena. OECD-SETH group expects the PANDA Project will meet the increasing needs for adequate experimental data for a 3D distribution of relevant variables like the temperature, velocity and steam-air concentrations that are measured with a sufficient resolution and accuracy

Proceedings of the workshop on operator training for severe accident management and instrumentation capabilities during severe accidents

International Nuclear Information System (INIS)

2001-01-01

This Workshop was organised in collaboration with Electricite de France (Service Etudes et Projets Thermiques et Nucleaires). There were 34 participants, representing thirteen OECD Member countries, the Russian Federation and the OECD/NEA. Almost half the participants represented utilities. The second largest group was regulatory authorities and their technical support organisations. Basically, the Workshop was a follow-up to the 1997 Second Specialist Meeting on Operator Aids for Severe Accident Management (SAMOA-2) [Reports NEA/CSNI/R(97)10 and 27] and to the 1992 Specialist Meeting on Instrumentation to Manage Severe Accidents [Reports NEA/CSNI/R(92)11 and (93)3]. It was aimed at sharing and comparing progress made and experience gained from these two meetings, emphasizing practical lessons learnt during training or incidents as well as feedback from instrumentation capability assessment. The objectives of the Workshop were therefore: - to exchange information on recent and current activities in the area of operator training for SAM, and lessons learnt during the management of real incidents ('operator' is defined hear as all personnel involved in SAM); - to compare capabilities and use of instrumentation available during severe accidents; - to monitor progress made; - to identify and discuss differences between approaches relevant to reactor safety; - and to make recommendations to the Working Group on the Analysis and Management of Accidents and the CSNI (GAMA). The meeting confirmed that only limited information is needed for making required decisions for SAM. In most cases existing instrumentation should be able to provide usable information. Additional instrumentation requirements may arise from particular accident management measures implemented in some plants. In any case, depending on the time frame where the instrumentation should be relied upon, it should be assessed whether it is likely to survive the harsh environmental conditions it will be exposed

Analysis of CSNI benchmark test on containment using the code CONTRAN

International Nuclear Information System (INIS)

Haware, S.K.; Ghosh, A.K.; Raj, V.V.; Kakodkar, A.

1994-01-01

A programme of experimental as well as analytical studies on the behaviour of nuclear reactor containment is being actively pursued. A large number ol' experiments on pressure and temperature transients have been carried out on a one-tenth scale model vapour suppression pool containment experimental facility, simulating the 220 MWe Indian Pressurised Heavy Water Reactors. A programme of development of computer codes is underway to enable prediction of containment behaviour under accident conditions. This includes codes for pressure and temperature transients, hydrogen behaviour, aerosol behaviour etc. As a part of this ongoing work, the code CONTRAN (CONtainment TRansient ANalysis) has been developed for predicting the thermal hydraulic transients in a multicompartment containment. For the assessment of the hydrogen behaviour, the models for hydrogen transportation in a multicompartment configuration and hydrogen combustion have been incorporated in the code CONTRAN. The code also has models for the heat and mass transfer due to condensation and convection heat transfer. The structural heat transfer is modeled using the one-dimensional transient heat conduction equation. Extensive validation exercises have been carried out with the code CONTRAN. The code CONTRAN has been successfully used for the analysis of the benchmark test devised by Committee on the Safety of Nuclear Installations (CSNI) of the Organisation for Economic Cooperation and Development (OECD), to test the numerical accuracy and convergence errors in the computation of mass and energy conservation for the fluid and in the computation of heat conduction in structural walls. The salient features of the code CONTRAN, description of the CSNI benchmark test and a comparison of the CONTRAN predictions with the benchmark test results are presented and discussed in the paper. (author)

2012 NEA Annual Report

International Nuclear Information System (INIS)

2013-01-01

After a message from the Director-General of the Nuclear Energy Agency (NEA, a semi-autonomous body within the OECD) and an overview of the Fukushima accident and NEA follow-up, this annual report presents the various technical programmes in which the NEA is committed. These programmes deal with nuclear development and the fuel cycle, nuclear safety and regulation, radioactive waste management, radiological protection, nuclear science, data bank, legal affairs, joint projects and other cooperative projects. The report then presents activities of the technical secretariat (Generation IV International Forum or GIF, Multinational Design Evaluation Programme or MDEP), and some general information about the NEA (organisational structure, publications in 2012) and about its activities of information and communication activities, and regarding the relationship between nuclear energy and civil society

Update Knowledge Base for Long-term Core Cooling Reliability

International Nuclear Information System (INIS)

Agrell, Maria; Sandervag, Oddbjoern; Amri, Abdallah; ); Bang, Young S.; Blomart, Philippe; Broecker, Annette; Pointner, Winfried; Ganzmann, Ingo; Lenogue, Bruno; Guzonas, David; Herer, Christophe; Mattei, Jean-Marie; Tricottet, Matthieu; Masaoka, Hideaki; Soltesz, Vojtech; Tarkiainen, Seppo; Ui, Atsushi; Villalba, Cristina; Zigler, Gilbert

2013-11-01

This revision of the Knowledge Base for Emergency Core Cooling System Recirculation Reliability (NEA/CSNI/R (95)11) describes the current status (late 2012) of the knowledge base on emergency core cooling system (ECCS) and containment spray system (CSS) suction strainer performance and long-term cooling in operating power reactors. New reactors, such as the AP1000, EPR and APR1400 that are under construction in some Organization for Economic Co-operation and Development (OECD) member countries, are not addressed in detail in this revision. The containment sump (also known as the emergency or recirculation sump in pressurized water reactors (PWRs) and pressurized heavy water reactors (PHWRs) or the suppression pools or wet wells in boiling water reactors (BWRs)) and associated ECCS strainers are parts of the ECCS in both reactor types. All nuclear power plants (NPPs) are required to have an ECCS that is capable of mitigating a design basis accident (DBA). The containment sump collects reactor coolant, ECCS injection water, and containment spray solutions, if applicable, after a loss-of-coolant accident (LOCA). The sump serves as the water source to support long-term recirculation for residual heat removal, emergency core cooling, and containment atmosphere clean-up. This water source, the related pump suction inlets, and the piping between the source and inlets are important safety-related components. In addition, if fibrous material is deposited at the fuel element spacers, core cooling can be endangered. The performance of ECCS/CSS strainers was recognized many years ago as an important regulatory and safety issue. One of the primary concerns is the potential for debris generated by a jet of high-pressure coolant during a LOCA to clog the strainer and obstruct core cooling. The issue was considered resolved for all reactor types in the mid-1990s and the OECD/NEA/CSNI published report NEA/CSNI/R(95)11 in 1996 to document the state of knowledge of ECCS performance

Proceedings of the joint WANO/OECD-NEA workshop on pre-stress loss in NPP containments

International Nuclear Information System (INIS)

1997-01-01

This joint WANO/OECD-NEA workshop on pre-stress loss in NPP containments started with Opening Remarks (by OECD and EDF) and two presentations on 'Creep and Shrinkage of Concrete: Physical Origins, Practical Measurements', and 'Past, Present and Future Techniques for Predicting Creep and Shrinkage of Concrete'. It was then followed by papers and presentations from 12 countries, which titles are: Assessment of Creep Methodologies for Predicting Prestressing Forces Losses in Nuclear Power Plant Containments; Prestress Behaviour in Belgian NPP Containments; Presentation of Gentilly 2 NPP Containment (abstract only); Containment Structure Monitoring and Prestress Losses; Experience from Daya Bay Nuclear Power Plant (China); Prestress losses in NPP containments - the EDF experience; Prestress Force Monitoring on the THTR Prestressed Concrete Reactor Vessel During 19 Years; NPP Containment Design: Evolution and Indian Experience; In-Service Inspections and R and D of PCCVs in Japan; Comparison of Grouted and Un-grouted Tendons in NPP Containments; Prestress Losses in Containment of VVER 1000 Units; Prestressing in Nuclear Power Plants; Anchor Lift-off Measuring System for 37 T 15 Tendons; Monitoring of Stressed-Strained State and Forces in Reinforcing Cables of Prestressed Containment Shells of Nuclear Power Plants; Long-Term In-Service Monitoring of Pre-stressing in Magnox Pre-stressed Concrete Pressure Vessels; The Measurement of Un-bonded Tendon Loads in PCPV and Primary Containment Buildings; The Long Term In-service Performance of Corrosion Protection to Prestressing Tendons in AGR Prestressed Concrete Pressure Vessels; Prestress Force Losses in Containments of U.S. Nuclear Power Plants. Discussions and a synthesis are also presented

An overview of the activities of the OECD/NEA Task Force on adapting computer codes in nuclear applications to parallel architectures

Energy Technology Data Exchange (ETDEWEB)

Kirk, B.L. [Oak Ridge National Lab., TN (United States); Sartori, E. [OCDE/OECD NEA Data Bank, Issy-les-Moulineaux (France); Viedma, L.G. de [Consejo de Seguridad Nuclear, Madrid (Spain)

1997-06-01

Subsequent to the introduction of High Performance Computing in the developed countries, the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) created the Task Force on Adapting Computer Codes in Nuclear Applications to Parallel Architectures (under the guidance of the Nuclear Science Committee`s Working Party on Advanced Computing) to study the growth area in supercomputing and its applicability to the nuclear community`s computer codes. The result has been four years of investigation for the Task Force in different subject fields - deterministic and Monte Carlo radiation transport, computational mechanics and fluid dynamics, nuclear safety, atmospheric models and waste management.

An overview of the activities of the OECD/NEA Task Force on adapting computer codes in nuclear applications to parallel architectures

International Nuclear Information System (INIS)

Kirk, B.L.; Sartori, E.; Viedma, L.G. de

1997-01-01

Subsequent to the introduction of High Performance Computing in the developed countries, the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) created the Task Force on Adapting Computer Codes in Nuclear Applications to Parallel Architectures (under the guidance of the Nuclear Science Committee's Working Party on Advanced Computing) to study the growth area in supercomputing and its applicability to the nuclear community's computer codes. The result has been four years of investigation for the Task Force in different subject fields - deterministic and Monte Carlo radiation transport, computational mechanics and fluid dynamics, nuclear safety, atmospheric models and waste management

Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements

Energy Technology Data Exchange (ETDEWEB)

Ebert, D.

1997-07-01

This is a report on the CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements held at Annapolis, Maryland, USA November 5-8, 1996. This experts` meeting consisted of 140 participants from 21 countries; 65 invited papers were presented. The meeting was divided into five areas: (1) current and prospective plans of thermal hydraulic codes development; (2) current and anticipated uses of thermal-hydraulic codes; (3) advances in modeling of thermal-hydraulic phenomena and associated additional experimental needs; (4) numerical methods in multi-phase flows; and (5) programming language, code architectures and user interfaces. The workshop consensus identified the following important action items to be addressed by the international community in order to maintain and improve the calculational capability: (a) preserve current code expertise and institutional memory, (b) preserve the ability to use the existing investment in plant transient analysis codes, (c) maintain essential experimental capabilities, (d) develop advanced measurement capabilities to support future code validation work, (e) integrate existing analytical capabilities so as to improve performance and reduce operating costs, (f) exploit the proven advances in code architecture, numerics, graphical user interfaces, and modularization in order to improve code performance and scrutibility, and (g) more effectively utilize user experience in modifying and improving the codes.

Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements

International Nuclear Information System (INIS)

Ebert, D.

1997-07-01

This is a report on the CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements held at Annapolis, Maryland, USA November 5-8, 1996. This experts' meeting consisted of 140 participants from 21 countries; 65 invited papers were presented. The meeting was divided into five areas: (1) current and prospective plans of thermal hydraulic codes development; (2) current and anticipated uses of thermal-hydraulic codes; (3) advances in modeling of thermal-hydraulic phenomena and associated additional experimental needs; (4) numerical methods in multi-phase flows; and (5) programming language, code architectures and user interfaces. The workshop consensus identified the following important action items to be addressed by the international community in order to maintain and improve the calculational capability: (a) preserve current code expertise and institutional memory, (b) preserve the ability to use the existing investment in plant transient analysis codes, (c) maintain essential experimental capabilities, (d) develop advanced measurement capabilities to support future code validation work, (e) integrate existing analytical capabilities so as to improve performance and reduce operating costs, (f) exploit the proven advances in code architecture, numerics, graphical user interfaces, and modularization in order to improve code performance and scrutibility, and (g) more effectively utilize user experience in modifying and improving the codes

Summary and conclusions of the specialist meeting on severe accident management programme development

International Nuclear Information System (INIS)

1992-01-01

The CSNI Specialist meeting on severe accident management programme development was held in Rome and about seventy experts from thirteen countries attended the meeting. A total of 27 papers were presented in four sessions, covering specific aspects of accident management programme development. It purposely focused on the programmatic aspects of accident management rather than on some of the more complex technical issues associated with accident management strategies. Some of the major observations and conclusions from the meeting are that severe accident management is the ultimate part of the defense in depth concept within the plant. It is function and success oriented, not event oriented, as the aim is to prevent or minimize consequences of severe accidents. There is no guarantee it will always be successful but experts agree that it can reduce the risks significantly. It has to be exercised and the importance of emergency drills has been underlined. The basic structure and major elements of accident management programmes appear to be similar among OECD member countries. Dealing with significant phenomenological uncertainties in establishing accident management programmes continues to be an important issue, especially in confirming the appropriateness of specific accident management strategies

CSNI/NEA Rasplav seminar 2000. Summary and conclusions

International Nuclear Information System (INIS)

2001-01-01

various boundary conditions were investigated. The work involved a combination of integral and separate effect tests including molten-salt tests to investigate non-eutectic mixtures and the effects of stratification, extension of the material property database to allow interpretation and modelling of the experimental data. The CSNI decided to hold a seminar where the major outcome of the RASPLAV Project could be presented and discussed also in the context of other experienced activities on Severe Accidents. The objectives of the seminar are: - to review the experimental results of the RASPLAV Project; - to exchange information on complementary research; - to discuss the progress made on understanding severe accident progression; - to discuss the applicability to nuclear power plants and use of the results. The Seminar was intended to provide an in-depth review of the RASPLAV Project in terms of the technical capabilities, results and analyses produced during the project execution. The application of the results and their significance for power plant applications were addressed. Relevant results of the complementary research carried out at various laboratories were also presented. The seminar consisted of five sessions organised as follows: - Opening and overview; - Experimental results; - Theoretical Analyses; - Application and complementary research; - Conclusion

CSNI/NEA Rasplav seminar 2000. Summary and conclusions

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-01-15

various boundary conditions were investigated. The work involved a combination of integral and separate effect tests including molten-salt tests to investigate non-eutectic mixtures and the effects of stratification, extension of the material property database to allow interpretation and modelling of the experimental data. The CSNI decided to hold a seminar where the major outcome of the RASPLAV Project could be presented and discussed also in the context of other experienced activities on Severe Accidents. The objectives of the seminar are: - to review the experimental results of the RASPLAV Project; - to exchange information on complementary research; - to discuss the progress made on understanding severe accident progression; - to discuss the applicability to nuclear power plants and use of the results. The Seminar was intended to provide an in-depth review of the RASPLAV Project in terms of the technical capabilities, results and analyses produced during the project execution. The application of the results and their significance for power plant applications were addressed. Relevant results of the complementary research carried out at various laboratories were also presented. The seminar consisted of five sessions organised as follows: - Opening and overview; - Experimental results; - Theoretical Analyses; - Application and complementary research; - Conclusion.

Reactor based plutonium disposition - physics and fuel behaviour benchmark studies of an OECD/NEA experts group

International Nuclear Information System (INIS)

D'Hondt, P.; Gehin, J.; Na, B.C.; Sartori, E.; Wiesenack, W.

2001-01-01

One of the options envisaged for disposing of weapons grade plutonium, declared surplus for national defence in the Russian Federation and Usa, is to burn it in nuclear power reactors. The scientific/technical know-how accumulated in the use of MOX as a fuel for electricity generation is of great relevance for the plutonium disposition programmes. An Expert Group of the OECD/Nea is carrying out a series of benchmarks with the aim of facilitating the use of this know-how for meeting this objective. This paper describes the background that led to establishing the Expert Group, and the present status of results from these benchmarks. The benchmark studies cover a theoretical reactor physics benchmark on a VVER-1000 core loaded with MOX, two experimental benchmarks on MOX lattices and a benchmark concerned with MOX fuel behaviour for both solid and hollow pellets. First conclusions are outlined as well as future work. (author)

OECD/NEA BENCHMARK FOR UNCERTAINTY ANALYSIS IN MODELING (UAM FOR LWRS – SUMMARY AND DISCUSSION OF NEUTRONICS CASES (PHASE I

Directory of Open Access Journals (Sweden)

RYAN N. BRATTON

2014-06-01

Full Text Available A Nuclear Energy Agency (NEA, Organization for Economic Co-operation and Development (OECD benchmark for Uncertainty Analysis in Modeling (UAM is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the “Neutronics Phase”, which is devoted mostly to the propagation of nuclear data (cross-section uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: 238U radiative capture and inelastic scattering (n, n’ as well as the average number of neutrons released per fission event of 239Pu.

Synthesis of the OECD/NEA-PSI CFD benchmark exercise

Energy Technology Data Exchange (ETDEWEB)

Andreani, Michele, E-mail: Michele.andreani@psi.ch; Badillo, Arnoldo; Kapulla, Ralf

2016-04-01

Highlights: • A benchmark exercise on stratification erosion in containment was conducted using a test in the PANDA facility. • Blind calculations were provided by nineteen participants. • Results were compared with experimental data. • A ranking was made. • A large spread of results was observed, with very few simulations providing accurate results for the most important variables, though not for velocities. - Abstract: The third International Benchmark Exercise (IBE-3) conducted under the auspices of OECD/NEA is based on the comparison of blind CFD simulations with experimental data addressing the erosion of a stratified layer by an off-axis buoyant jet in a large vessel. The numerical benchmark exercise is based on a dedicated experiment in the PANDA facility conducted at the Paul Scherrer Institut (PSI) in Switzerland, using only one vessel. The use of non-prototypical fluids (i.e. helium as simulant for hydrogen, and air as simulant for steam), and the consequent absence of the complex physical effects produced by steam condensation enhanced the suitability of the data for CFD validation purposes. The test started with a helium–air layer at the top of the vessel and air in the lower part. The helium-rich layer was gradually eroded by a low-momentum air/helium jet emerging at a lower elevation. Blind calculation results were submitted by nineteen participants, and the calculation results have been compared with the PANDA data. This report, adopting the format of the reports for the two previous exercises, includes a ranking of the contributions, where the largest weight is given to the time progression of the erosion of the helium-rich layer. In accordance with the limited scope of the benchmark exercise, this report is more a collection of comparisons between calculated results and data than a synthesis. Therefore, the few conclusions are based on the mere observation of the agreement of the various submissions with the test result, and do not

Proceedings of a specialist meeting on leak before break in reactor piping and vessels

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

This Specialist Meeting was organised by EDF, Framatome and CEA with the participation of SFEN, and it was sponsored jointly by the CEC DG XI, Nuclear Electric, IAEA, US NRC, and by the Principal Working Group 3 (PWG-3) on Reactor Component Integrity of the NEA CSNI. The activities of PWG-3 fall into three main areas: Non-Destructive Examination (NDE), fracture analysis and aging/materials degradation. In fracture analysis, the activities are organised by the Fracture Analysis Group, and include the round robins on Fracture Analysis of Large Scale International Reference Experiments (FALSIRE). The topic of the workshop falls mainly into the second area of fracture analysis. The objective of the meeting was to present the current state of the art in Leak-Before-Break (LBB) methodology development, validation, and application in an international forum. With particular emphasis on industrial applications and regulatory policies, the seminar provided an opportunity to compare approaches, experiences, and codifications developed by different countries. The seminar was organized into four topic areas: status of LBB applications; technical issues in LBB methodology; complementary requirements (leak detection and inspection); LBB assessment and margins. As a result of this seminar, an improved understanding of LBB gained through sharing of different viewpoints from different countries, permits consideration of: simplified pipe support design and possible elimination of loss-of-coolant-accident (LOCA) mechanical consequences for specific cases; defense-in-depth type of applications without support modifications; support of safety cases for plants designed without the LOCA hypothesis. In support of these activities, better estimates of the limits to the LBB approach should follow, as well as an improvement in codifying methodologies. The formal proceedings of the meeting were published by US NRC as a NUREG report (NUREG/CP--0155). This includes the final versions of papers

Proceedings of a specialist meeting on leak before break in reactor piping and vessels

International Nuclear Information System (INIS)

1996-01-01

This Specialist Meeting was organised by EDF, Framatome and CEA with the participation of SFEN, and it was sponsored jointly by the CEC DG XI, Nuclear Electric, IAEA, US NRC, and by the Principal Working Group 3 (PWG-3) on Reactor Component Integrity of the NEA CSNI. The activities of PWG-3 fall into three main areas: Non-Destructive Examination (NDE), fracture analysis and aging/materials degradation. In fracture analysis, the activities are organised by the Fracture Analysis Group, and include the round robins on Fracture Analysis of Large Scale International Reference Experiments (FALSIRE). The topic of the workshop falls mainly into the second area of fracture analysis. The objective of the meeting was to present the current state of the art in Leak-Before-Break (LBB) methodology development, validation, and application in an international forum. With particular emphasis on industrial applications and regulatory policies, the seminar provided an opportunity to compare approaches, experiences, and codifications developed by different countries. The seminar was organized into four topic areas: status of LBB applications; technical issues in LBB methodology; complementary requirements (leak detection and inspection); LBB assessment and margins. As a result of this seminar, an improved understanding of LBB gained through sharing of different viewpoints from different countries, permits consideration of: simplified pipe support design and possible elimination of loss-of-coolant-accident (LOCA) mechanical consequences for specific cases; defense-in-depth type of applications without support modifications; support of safety cases for plants designed without the LOCA hypothesis. In support of these activities, better estimates of the limits to the LBB approach should follow, as well as an improvement in codifying methodologies. The formal proceedings of the meeting were published by US NRC as a NUREG report (NUREG/CP--0155). This includes the final versions of papers

CSNI International Standard Problems (ISP). Brief descriptions (1975-1994)

International Nuclear Information System (INIS)

1994-07-01

Between 1975 and 1994 the NEA Committee on the Safety of Nuclear Installations (CSNI) has sponsored some forty International Standard Problems (ISPs) in the fields of in-vessel thermal-hydraulic behaviour, fuel behaviour under accident conditions, fission product release and transport, core/concrete interactions, hydrogen distribution and mixing, containment thermal-hydraulics. ISPs are comparative exercises in which predictions of different computer codes for a given physical problem are compared with each other or with the results of a carefully controlled experimental study. The main goal of ISP exercises is to increase confidence in the validity and accuracy of tools which are used in assessing the safety of nuclear installations. Moreover, they enable code users to gain experience and demonstrate their competence. ISPs are performed as 'open' or 'blind' problems. In an open Standard Problem the results of the experiment are available to the participants before performing the calculations, while in a blind Standard Problem the results are locked until the calculational results are made available for comparison. Experiments selected to support ISP exercises are exceptionally well documented; they provide the framework for several code validation matrices. This report briefly describes 36 ISPs and 3 containment analysis standard problems (CASP)

Reactor physics activities in NEA member countries

International Nuclear Information System (INIS)

1990-01-01

This document is a compilation of National activity reports presented at the thirty-third Meeting of the NEA Committee on Reactor Physics, held at OECD Headquarters, Paris, from 15th - 19th October 1990

NEA annual report 2000

International Nuclear Information System (INIS)

2000-01-01

In this 2000 annual report, the Nuclear Energy Agency (NEA), notes that in the medium and long term, the evolution of the nuclear energy programs in OECD countries is likely to be influenced by the implementation of sustainable development policies integrating economic, environmental and socials goals. This report is divided in four chapters. The first one gives general information on nuclear industry. The chapter 2 deals with trends in nuclear power. The chapter 3 gathers technical programs in nuclear development and fuel cycle, nuclear safety and regulation, radiation protection, radioactive waste management, nuclear science and data bank, legal affairs, joint projects and other co-operative projects. The last chapter gathers general information on information program, NEA publications, main workshops and seminar and organisation charts of the NEA. (A.L.B.)

Severe accident management (SAM), operator training and instrumentation capabilities - Summary and conclusions

International Nuclear Information System (INIS)

2002-01-01

The Workshop on Operator Training for Severe Accident Management (SAM) and Instrumentation Capabilities During Severe Accidents was organised in collaboration with Electricite de France (Service Etudes et Projets Thermiques et Nucleaires). There were 34 participants, representing thirteen OECD Member countries, the Russian Federation and the OECD/NEA. Almost half the participants represented utilities. The second largest group was regulatory authorities and their technical support organisations. Basically, the Workshop was a follow-up to the 1997 Second Specialist Meeting on Operator Aids for Severe Accident Management (SAMOA-2) [Reports NEA/CSNI/R(97)10 and 27] and to the 1992 Specialist Meeting on Instrumentation to Manage Severe Accidents [Reports NEA/CSNI/R(92)11 and (93)3]. It was aimed at sharing and comparing progress made and experience gained from these two meetings, emphasizing practical lessons learnt during training or incidents as well as feedback from instrumentation capability assessment. The objectives of the Workshop were therefore: - to exchange information on recent and current activities in the area of operator training for SAM, and lessons learnt during the management of real incidents ('operator' is defined hear as all personnel involved in SAM); - to compare capabilities and use of instrumentation available during severe accidents; - to monitor progress made; - to identify and discuss differences between approaches relevant to reactor safety; - and to make recommendations to the Working Group on the Analysis and Management of Accidents and the CSNI (GAMA). The Workshop was organised into five sessions: - 1: Introduction; - 2: Tools and Methods; - 3: Training Programmes and Experience; - 4: SAM Organisation Efficiency; - 5: Instrumentation Capabilities. It was concluded by a Panel and General Discussion. This report presents the summary and conclusions: the meeting confirmed that only limited information is needed for making required decisions

Proceedings of the OECD/CSNI specialists meeting on boron dilution reactivity transients

International Nuclear Information System (INIS)

1997-06-01

The purpose of the meeting was to bring together experts involved in the different activities related to boron dilution transients. The experts came from all involved parties, including research organizations, regulatory authorities, vendors and utilities. Information was openly shared and discussed on the experimental results, plant and systems analysis, numerical analysis of mixing and probability and consequences of these transients. Regulatory background and licensing implications were also included to provide the proper frame work for the technical discussion. Each of these areas corresponded to a separate session. The meeting focused on the thermal-hydraulic aspects because of the current interest in that subject and the significant amount of new technical information being generated

Intergovernmental organisation activities: European Atomic Energy Community, International Atomic Energy Agency, OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

Anon.

2012-01-01

European Atomic Energy Community: Proposed legislative instruments, Adopted legislative instruments, Non-legislative instruments, Other activities (meetings). International Atomic Energy Agency: IAEA Action Plan on Nuclear Safety. OECD Nuclear Energy Agency: The Russian Federation to join the OECD Nuclear Energy Agency; Participation by the regulatory authorities of India and the United Arab Emirates in the Multinational Design Evaluation Programme (MDEP); NEA International Workshop on Crisis Communication, 9-10 May 2012; International School of Nuclear Law: 2013; Next NEA International Nuclear Law Essentials Course

Proceedings of the CSNI/IAEA workshop on maintaining oversight of licensee safety culture - methods and approaches. Held from 21 to 23 May 2007 in Chester, UK

International Nuclear Information System (INIS)

2008-01-01

Weaknesses in safety culture have contributed to a number of high profile events in the nuclear and other high hazard sectors. The nuclear industry also faces challenges such as deregulation, out-sourcing, phase-out, upgrading and new builds which, if not properly planned and implemented, have the potential to make a negative impact on safety culture. These factors have fostered an increasing awareness of the need for licensees to develop a strong safety culture to support successful and sustainable nuclear safety performance. Regulatory bodies are taking a growing interest in this issue, and several are actively working to develop and implement approaches to maintaining oversight of licensee safety culture. However, these approaches are not yet well-established, and it was considered prudent to share experiences and developing methodologies in order to disseminate good practices and avoid potential pitfalls. An NEA/CSNI/IAEA workshop was therefore held in Chester, UK, in May 2007 in order to explore and discuss the approaches that different regulatory bodies are taking to maintain oversight of licensee safety culture. It was organised by the UK Nuclear Installations Inspectorate on behalf of the CSNI's Working Group on Human and Organisational Factors. This report sets out the findings of the Chester workshop. The workshop was attended by 50 representatives of nuclear regulatory bodies in 20 countries plus IAEA, WANO, EU and NEA. It included both specialists in safety culture and site/resident inspectors, whose attendance was facilitated by the CNRA's Working Group on Inspection Practices. The workshop comprised structured discussion sessions, in which a set of issues were explored by small discussion groups and then discussed in plenary, complemented by short presentations on national regulatory positions. The workshop revealed a broad consensus that nuclear regulators should have processes in place to maintain oversight of licensee safety culture. The approaches

CIEMAT’s contribution to the phase II of the OECD-NEA RIA benchmark on thermo-mechanical fuel codes performance

Energy Technology Data Exchange (ETDEWEB)

Sagrado, I.C.; Vallejo, I.; Herranz, L.E.

2015-07-01

As a part of the international efforts devoted to validate and/or update the current fuel safety criteria, the OECD-NEA has launched a second phase of the RIA benchmark on thermomechanical fuel codes performance. CIEMAT contributes simulating the ten scenarios proposed with FRAPTRAN and SCANAIR. Both codes lead to similar predictions during the heating-up; however, during the cooling-down significant deviations may appear. They are mainly caused by the estimations of gap closure and re-opening and the clad to water heat exchange approaches. The uncertainty analysis performed for the SCANAIR estimations leads to uncertainty ranges below 15% and 28% for maximum temperatures and deformations, respectively. The corresponding sensitivity analysis shows that, in addition to the injected energy, special attention should be paid to fuel thermal expansion and clad yield stress models. (Author)

Overview of OECD-NEA Nuclear Science and Data Bank Activities

International Nuclear Information System (INIS)

Gulliford, Jim

2012-01-01

Overview: • NEA Areas of Work, Standing Committees; • Nuclear Science & the Data Bank: – Working Parties & Expert Groups; – integral experiments databases; – linked Data Bank/Nuclear Science products. • Reactor Physics and Criticality Integral Experiments: – ICSBEP& IRPhE evaluations; – Database tools (DICE, IDAT, SFCOMPO-X). • Other Activities related to Fast Reactors: – WPRS SFR Task Force; – Nuclear Data, WPEC sub-group on data adjustment; – Fuel Cycle and Materials. • Looking Ahead: – Uncertainty Analysis for transient modelling; – Russian Accession to the NEA and Data Bank; – Impact of Fukushima on Nuclear Science Programmes of Work

Iodine-129. Proceedings of an NEA specialist meeting. Paris, 13-16 June 1977. Iode-129. Compte rendu d'une reunion de specialistes de l'AEN. Paris, 13-16 juin 1977

Energy Technology Data Exchange (ETDEWEB)

1977-01-01

In the framework of its programme on effluent releases from the nuclear fuel cycle and its radiological significance, the Committee on Radiation Protection and Public Health decided to organise meetings of specialists directly involved with research or regulatory aspects of effluent releases in order to note the status of present knowledge in this field. A first meeting of this type on iodine 129 was organised by the OECD Nuclear Energy Agency. This publication reproduces papers presented at this meeting.

Radioactive waste management and decommissioning at the NEA

International Nuclear Information System (INIS)

2010-11-01

The OECD Nuclear Energy Agency (NEA) seeks to assist its member countries in developing safe, sustainable and societally acceptable strategies for the management of all types of radioactive materials, with particular emphasis on the management of long-lived waste and spent fuel and on decommissioning of disused nuclear facilities. The programme of work in these areas is carried out for the most part by the Radioactive Waste Management Committee (RWMC) assisted by three working parties: - The Forum on Stakeholder Confidence (FSC). - The Integration Group for the Safety Case (IGSC). - The Working Party on Decommissioning and Dismantling (WPDD). Other NEA Committees also have interests in this field: the Committee on Radiation Protection and Public Health (CRPPH) and the Nuclear Development Committee (NDC). The OECD/NEA is at the forefront in addressing both the technical and societal requirements for durable and sustainable waste management and decommissioning solutions. Through the RWMC it provides a neutral forum where policy makers, regulators and implementing organisations can discuss issues of common interest and develop solutions that meet the diverse needs of its member countries

Trend and pattern analyses of operational data from nuclear power plants

International Nuclear Information System (INIS)

Amesz, J.

1990-01-01

One step towards maximizing the benefits gained from plant operating experience is the establishment of a rigorous scheme of classification and storage of operational data related to equipment failures and/or human errors. The analysis of data thus collected can fall into one of the following two categories: in-depth analysis of individual incidents which are considered to be of major significance from the safety point of view; and trend and pattern analyses of the stored data with the aim of identifying situations that warrant further studies or that require particular attention. In order to perform the second type of analyses, various approaches/systems are being used by organizations with interests in the nuclear power domain. Similar methodologies may be used in general industrial safety as well. For the purpose of facilitating a comparison between the different methods, the OECD/NEA Committee on the Safety of Nuclear Installations (CSNI) decided to organize a specialist meeting jointly with the Commission of the European Communities (CEC) for a systematic and comprehensive review of the matter

International co-operation in the field of operational safety

International Nuclear Information System (INIS)

Dupuis, M.C.

1988-10-01

Operational safety in nuclear power plants is without doubt a field where international co-operation is in constant progress. Accounting for over 80 per cent of the 400 reactors in service throughout the world, the menber countries of the OECD Nuclear Energy Agency (NEA) are constantly striving to improve the exchange and use of the wealth of information to be gained not just from power plant accidents and incidents but from the routine operation of these facilities. The Committee on the Safety of Nuclear Installations (CSNI) helps the Steering Committee for Nuclear Energy to meet the NEA's objectives in the safety field, namely: - to promote co-operation between the safety bodies of member countries - to contribute to the safety and regulation of nuclear activities. The CSNI relies on the technical back-up of several different working groups made up of experts appointed by the member countries. For the past three years I have had the honour of chairing Principal Working Group 1 (PWG 1), which deals with operating experience and human factor. It is in this capacity that I will attempt to outline the group's various activities and its findings illustrated by a few examples

An analysis of CSNI standard problem, No. 8

International Nuclear Information System (INIS)

Sasaki, Shinobu; Araya, Fumimasa

1980-03-01

The CSNI International Standard Problem (ISP8), based on the Semiscale S-06-3 Test, was analyzed in the course of verification work of the computer code ALARM-P1. In this report, described was the result of the initial trial, which had been submitted to the CSNI. Due to the limitations of ALARM-P1 capability, only the blowdown portion of the transient was calculated. Though the hydraulic behavior before ECCS injection agreed with the test data, the ALARM-P1 could not continue calculation after 26 seconds due to severe predicted instability following the ECCS injection. The prediction of surface temperature of the heater rods was also unsatisfactory. Several problems to be improved have been identified both in the analytical model and the input data. (author)

CFD validation in OECD/NEA t-junction benchmark.

Energy Technology Data Exchange (ETDEWEB)

Obabko, A. V.; Fischer, P. F.; Tautges, T. J.; Karabasov, S.; Goloviznin, V. M.; Zaytsev, M. A.; Chudanov, V. V.; Pervichko, V. A.; Aksenova, A. E. (Mathematics and Computer Science); (Cambridge Univ.); (Moscow Institute of Nuclar Energy Safety)

2011-08-23

and benchmark data. The numerical scheme has a very small scheme diffusion and is the second and the first order accurate in space and time, correspondingly. We compare and contrast simulation results for three computational fluid dynamics codes CABARET, Conv3D, and Nek5000 for the T-junction thermal striping problem that was the focus of a recent OECD/NEA blind benchmark. The corresponding codes utilize finite-difference implicit large eddy simulation (ILES), finite-volume LES on fully staggered grids, and an LES spectral element method (SEM), respectively. The simulations results are in a good agreement with experimenatl data. We present results from a study of sensitivity to computational mesh and time integration interval, and discuss the next steps in the simulation of this problem.

Uranium supply/demand projections to 2030 in the OECD/NEA-IAEA ''Red Book''. Nuclear growth projections, global uranium exploration, uranium resources, uranium production and production capacity

International Nuclear Information System (INIS)

Vance, Robert

2009-01-01

World demand for electricity is expected to continue to grow rapidly over the next several decades to meet the needs of an increasing population and economic growth. The recognition by many governments that nuclear power can produce competitively priced, base load electricity that is essentially free of greenhouse gas emissions, combined with the role that nuclear can play in enhancing security of energy supplies, has increased the prospects for growth in nuclear generating capacity. Since the mid-1960s, with the co-operation of their member countries and states, the OECD Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA) have jointly prepared periodic updates (currently every 2 years) on world uranium resources, production and demand. These updates have been published by the OECD/NEA in what is commonly known as the ''Red Book''. The 2007 edition replaces the 2005 edition and reflects information current as of 1 st January 2007. Uranium 2007: Resources, Production and Demand presents, in addition to updated resource figures, the results of a recent review of world uranium market fundamentals and provides a statistical profile of the world uranium industry. It contains official data provided by 40 countries (and one Country Report prepared by the IAEA Secretariat) on uranium exploration, resources, production and reactor-related requirements. Projections of nuclear generating capacity and reactor-related uranium requirements to 2030 as well as a discussion of long-term uranium supply and demand issues are also presented. (orig.)

Establishment of data base files of thermodynamic data developed by OECD/NEA. Pt. 2. Thermodynamic data of Tc, U, Np, Pu and Am with auxiliary species

International Nuclear Information System (INIS)

Yoshida, Yasushi; Shibata, Masahiro

2005-03-01

Thermodynamic data base for compounds and complexes of actinides and fission products with auxiliary species specialized in modeling requirements for safety assessment of radioactive waste disposal systems are being developed by NEA TDB project of OECD/NEA. In this project, relevant data bases for compounds and complexes of U, Am, Tc, Np and Pu with auxiliary species were updated and published in 2003. JNC established the data base files available for geochemical calculation codes using these updated data. The procedure for establishment and contents of data base files are described in this report. These data base files were prepared as the formats of major geochemical codes PHREEQE, PHREEQC, EQ3/6 and Geochemist's workbench. Additionally modification for data in the thermodynamic data base files which had been already published by JNC was also done. This procedure and revised data bases are shown in the appendix of this report. (author)

OECD/NEA expert group on uncertainty analysis for criticality safety assessment: Results of benchmark on sensitivity calculation (phase III)

Energy Technology Data Exchange (ETDEWEB)

Ivanova, T.; Laville, C. [Institut de Radioprotection et de Surete Nucleaire IRSN, BP 17, 92262 Fontenay aux Roses (France); Dyrda, J. [Atomic Weapons Establishment AWE, Aldermaston, Reading, RG7 4PR (United Kingdom); Mennerdahl, D. [E Mennerdahl Systems EMS, Starvaegen 12, 18357 Taeby (Sweden); Golovko, Y.; Raskach, K.; Tsiboulia, A. [Inst. for Physics and Power Engineering IPPE, 1, Bondarenko sq., 249033 Obninsk (Russian Federation); Lee, G. S.; Woo, S. W. [Korea Inst. of Nuclear Safety KINS, 62 Gwahak-ro, Yuseong-gu, Daejeon 305-338 (Korea, Republic of); Bidaud, A.; Sabouri, P. [Laboratoire de Physique Subatomique et de Cosmologie LPSC, CNRS-IN2P3/UJF/INPG, Grenoble (France); Patel, A. [U.S. Nuclear Regulatory Commission (NRC), Washington, DC 20555-0001 (United States); Bledsoe, K.; Rearden, B. [Oak Ridge National Laboratory ORNL, M.S. 6170, P.O. Box 2008, Oak Ridge, TN 37831 (United States); Gulliford, J.; Michel-Sendis, F. [OECD/NEA, 12, Bd des Iles, 92130 Issy-les-Moulineaux (France)

2012-07-01

The sensitivities of the k{sub eff} eigenvalue to neutron cross sections have become commonly used in similarity studies and as part of the validation algorithm for criticality safety assessments. To test calculations of the sensitivity coefficients, a benchmark study (Phase III) has been established by the OECD-NEA/WPNCS/EG UACSA (Expert Group on Uncertainty Analysis for Criticality Safety Assessment). This paper presents some sensitivity results generated by the benchmark participants using various computational tools based upon different computational methods: SCALE/TSUNAMI-3D and -1D, MONK, APOLLO2-MORET 5, DRAGON-SUSD3D and MMKKENO. The study demonstrates the performance of the tools. It also illustrates how model simplifications impact the sensitivity results and demonstrates the importance of 'implicit' (self-shielding) sensitivities. This work has been a useful step towards verification of the existing and developed sensitivity analysis methods. (authors)

Actinide separation chemistry in nuclear waste streams, an OECD Nuclear Energy Agency review

International Nuclear Information System (INIS)

Madic, C.

1997-01-01

The separation of actinide elements from various waste materials, either produced in nuclear fuel cycle or in the past during nuclear weapon production, represent a significant issue facing developed countries. Improvements in the efficiencies of the separation processes can be expected from a better knowledge of the chemistry of these elements in these complex matrices. The Nuclear Science Committee of the OECD/NEA has established a task force of experts in actinide chemistry to review the current and developing separation techniques and chemical processes. Recommendations were made for future research and development programs. This article presents briefly the work of the Task Force which will be published soon as an OECD/NEA/NSC Report. (author)

Preliminary Results for the OECD/NEA Time Dependent Benchmark using Rattlesnake, Rattlesnake-IQS and TDKENO

Energy Technology Data Exchange (ETDEWEB)

DeHart, Mark D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Mausolff, Zander [Univ. of Florida, Gainesville, FL (United States); Weems, Zach [Univ. of Florida, Gainesville, FL (United States); Popp, Dustin [Univ. of Florida, Gainesville, FL (United States); Smith, Kristin [Univ. of Florida, Gainesville, FL (United States); Shriver, Forrest [Univ. of Florida, Gainesville, FL (United States); Goluoglu, Sedat [Univ. of Florida, Gainesville, FL (United States); Prince, Zachary [Texas A & M Univ., College Station, TX (United States); Ragusa, Jean [Texas A & M Univ., College Station, TX (United States)

2016-08-01

One goal of the MAMMOTH M&S project is to validate the analysis capabilities within MAMMOTH. Historical data has shown limited value for validation of full three-dimensional (3D) multi-physics methods. Initial analysis considered the TREAT startup minimum critical core and one of the startup transient tests. At present, validation is focusing on measurements taken during the M8CAL test calibration series. These exercises will valuable in preliminary assessment of the ability of MAMMOTH to perform coupled multi-physics calculations; calculations performed to date are being used to validate the neutron transport solver Rattlesnake\\cite{Rattlesnake} and the fuels performance code BISON. Other validation projects outside of TREAT are available for single-physics benchmarking. Because the transient solution capability of Rattlesnake is one of the key attributes that makes it unique for TREAT transient simulations, validation of the transient solution of Rattlesnake using other time dependent kinetics benchmarks has considerable value. The Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD) has recently developed a computational benchmark for transient simulations. This benchmark considered both two-dimensional (2D) and 3D configurations for a total number of 26 different transients. All are negative reactivity insertions, typically returning to the critical state after some time.

Preliminary Results for the OECD/NEA Time Dependent Benchmark using Rattlesnake, Rattlesnake-IQS and TDKENO

International Nuclear Information System (INIS)

DeHart, Mark D.; Mausolff, Zander; Weems, Zach; Popp, Dustin; Smith, Kristin; Shriver, Forrest; Goluoglu, Sedat; Prince, Zachary; Ragusa, Jean

2016-01-01

One goal of the MAMMOTH M&S project is to validate the analysis capabilities within MAMMOTH. Historical data has shown limited value for validation of full three-dimensional (3D) multi-physics methods. Initial analysis considered the TREAT startup minimum critical core and one of the startup transient tests. At present, validation is focusing on measurements taken during the M8CAL test calibration series. These exercises will valuable in preliminary assessment of the ability of MAMMOTH to perform coupled multi-physics calculations; calculations performed to date are being used to validate the neutron transport solver Rattlesnake\\citelesnake) and the fuels performance code BISON. Other validation projects outside of TREAT are available for single-physics benchmarking. Because the transient solution capability of Rattlesnake is one of the key attributes that makes it unique for TREAT transient simulations, validation of the transient solution of Rattlesnake using other time dependent kinetics benchmarks has considerable value. The Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD) has recently developed a computational benchmark for transient simulations. This benchmark considered both two-dimensional (2D) and 3D configurations for a total number of 26 different transients. All are negative reactivity insertions, typically returning to the critical state after some time.

Challenges and Enhancements to Defence-in-Depth (DiD) in Light of the Fukushima Daiichi NPP Accident. Proceedings of a Joint CNRA/CSNI Workshop, Paris, France, 5 June 2013

International Nuclear Information System (INIS)

Niel, Jean-Christophe; Autorite de surete nucleaire - ASN; ); Echavarri, Luis; ); Schneider, Thierry; ); Borchardt, Bill; Wanner, Hans; Park, Youn Won; Glenn, Tracy; Regaldo, Jacques; Fuketa, Toyoshi; Repussard, Jacques; Bolshov, Leonid; Chevet, Pierre Frank

2014-01-01

An international Workshop on Challenges and Enhancements to Defence in Depth (DiD) in Light of the Fukushima Daiichi Accident was jointly organised by the NEA Committee on Nuclear Regulatory Activities (CNRA) and the NEA Committee on the Safety on Nuclear Installations (CSNI), with input from the NEA Committee on Radiation Protection and Public Health (CRPPH), on 5 June 2013 in Paris. About 100 participants from NEA member countries, India, the International Atomic Energy Agency (IAEA), the World Association of Nuclear Operators (WANO) and Eurelectric held in-depth discussions on the defence-in-depth concept and its implementation in the post-Fukushima context. They also considered additional steps to be taken at the national and international levels to address the challenges identified and to make further enhancements to nuclear safety, along with future NEA activities in support of these processes. The concept of DiD - of multiple levels of protection - has been developed and refined by the nuclear safety community over many years. The concept is based on the experience and practice of high hazard industry in general as well as developments within the nuclear industry. The accident at the Fukushima Daiichi Nuclear Power Station in Japan on the 11 March 2011 demonstrated the importance of the concept of DiD, how these multiple levels of protection can operate and how some can be challenged. Just as with the nuclear accidents at Three Mile Island and Chernobyl and accidents from other industries (e.g. chemical, aerospace, oil and gas), the NEA felt it important that lessons learned are used to further develop the concept and implementation of Defence-in-Depth to help ensure and enhance the safe operation of nuclear power plants around the world. The NEA has therefore looked at the concept and implementation of Defence-in-Depth and possible challenges and enhancements. It was noted that a great deal of interest has been shown in this area, particularly in the

OECD/NEA International Conference on Global Nuclear Safety Enhancement Organised in co-operation with the Nuclear Regulation Authority (NRA) of Japan On the Occasion of the 50. Anniversary of Japan Joining the OECD

International Nuclear Information System (INIS)

Tanaka, Shunichi; Oshima, Kenzo; Fuketa, Toyoshi; Echavarri, Luis E.; ); Ostendorff, William C.; Viktorovich Ferapontov, Alexey; Lachaume, Jean-Luc; Yoo, Guk Hee; Lyons, James E.; ); Weightman, Mike; ); Gurria, Angel; ); Ishihara, Hirotaka

2014-04-01

On 8 April 2014 in Tokyo, Japan, an international conference on enhancing global nuclear safety was held by the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-operation and Development(OECD), in co-operation with the Nuclear Regulation Authority (NRA) of Japan. This document brings together the 12 presentations (slides) given at this conference organized in 3 sessions: 1 - Opening Session: Opening Remarks (S. Tanaka); Statement by L.E. Echavarri; Session 1 - Global Safety Enhancements: USNRC Actions in Response to the Fukushima Nuclear Accident (W.C. Ostendorff); Synergy of National and International Regulatory Efforts to Enhance Global Nuclear Safety (A. Viktorovich Ferapontov); Global Safety Enhancements, The French Nuclear Safety Authority (ASN)'s position (J.L. Lachaume); Nuclear Safety and Security Commission builds up safety and security (G.H. Yoo); Session 2 - Learning from Experience to Improve Safety: Lessons Learned from the Fukushima Dai-ichi Accident and Responses in New Regulatory Requirements (T. Fuketa); NEA Activities to Enhance the Nuclear Regulatory Framework (L.E. Echavarri); Learning from Experience to Improve Safety - its importance, its mechanisms and its challenges (J.E. Lyons); Learning from Experience to Improve Nuclear Safety - A Perspective from the UK (M. Weightman); Conclusions and Closing Remarks (A. Gurria, H. Ishihara)

Source convergence diagnostics using Boltzmann entropy criterion application to different OECD/NEA criticality benchmarks with the 3-D Monte Carlo code Tripoli-4

International Nuclear Information System (INIS)

Dumonteil, E.; Le Peillet, A.; Lee, Y. K.; Petit, O.; Jouanne, C.; Mazzolo, A.

2006-01-01

The measurement of the stationarity of Monte Carlo fission source distributions in k eff calculations plays a central role in the ability to discriminate between fake and 'true' convergence (in the case of a high dominant ratio or in case of loosely coupled systems). Recent theoretical developments have been made in the study of source convergence diagnostics, using Shannon entropy. We will first recall those results, and we will then generalize them using the expression of Boltzmann entropy, highlighting the gain in terms of the various physical problems that we can treat. Finally we will present the results of several OECD/NEA benchmarks using the Tripoli-4 Monte Carlo code, enhanced with this new criterion. (authors)

NEA’S Plans for Strengthening International Implementation of the Application of Defence in Depth Philosophies in Nuclear Power Countries

Energy Technology Data Exchange (ETDEWEB)

Blundell, N., E-mail: Neil.BLUNDELL@oecd.org [Nuclear Safety Division, OECD NEA, Paris (France)

2014-10-15

Full text: Following the Fukushima Daiichi Accident the OECD NEA established and delivered three tasks related to Defence in Depth for its member states. These consisted of: • A review of member state and NEA activities directly related to the accident by the Fukushima Senior Task Group set up by the OECD NEA Committee for Nuclear Regulatory Activities (CNRA). • An international expert review of the NEA’s wide ranging joint nuclear safety research portfolio. • A joint workshop on ‘Challenges and Enhancements to Defence in Depth (DiD) in light of the Fukushima Daiichi Accident’ on 5th June 2013 by both the OECD NEA Committee for Nuclear Regulatory Activities (CNRA) and Committee for the Safety of Nuclear Installations (CSNI). These tasks encompassed firstly, how the NEA member states understand the concept of DiD and its value within Nuclear Safety. Secondly, how DiD is implemented at present, focussing on how it is implemented to deal with external events, and finally what future areas the NEA members considered NEA as a whole should be carrying forward to enhance the understanding and implementation of Defence-in-Depth. Such areas included: • Exploring what the DiD safety goal concept ”practically eliminate large and early offsite releases” means and how is it implemented. • Independence and margins in the implementation of DiD. • Human interventions considering catastrophic external events effects on emergency response and recovery. • Detailed identification of additional safety research after Fukushima. This presentation provides a summary of those tasks and NEA’s international programme of activities to bring its members together in those areas they highlighted to deliver enhancement in the understanding and implementation of defence in depth. (author)

ISP-50 Specifications for a Direct Vessel Injection Line Break Test with the ATLAS

International Nuclear Information System (INIS)

Choi, Ki Yong; Baek, Won Pil; Kim, Yeon Sik; Park, Hyun Sik; Cho, Seok; Kang, Kyoung Ho; Choi, Nam Hyun; Min, Kyoung Ho

2009-06-01

An OECD/NEA International Standard Problem Exercise (ISP) focussing on a DVI line break simulation result with the ATLAS was approved by the NEA Committee on the Safety of Nuclear Installation (CSNI) meeting in December 2008 and was numbered by ISP-50. The ISP-50 program will be operated by an operating agency, KAERI for three years starting from the physical year 2009. Fourteen international organizations confirmed their participation in the ISP-50, including NRC (USA), JAEA, JNES (Japan), GRS (Germany), KFKI-AEKI (Hungary), EDO Gidropress (Russia), VTT, Fortum (Finland), NRI (Czech Republic), Univ. of Pisa (Italy), KINS, KNF, KOPEC, and KAERI (Korea). In addition, KTH in Sweden and HSE in UK are considering late participation. Recently, NPIC and CIAE in China hope to join the ISP-50. As for the safety analysis codes, nine codes are expected to be used for the ISP-50: MARS-3D, RELAP5- 3D, RELAP5, TRACE, CATHARE, APROS, ATHELET, TRAP, and KORSAR. It is the first ISP exercise in Korea in which a domestic test facility is utilized by international nuclear society and this exercise will contribute to extending our physical understanding on thermal hydraulic phenomena during the DVI line break accidents and to verifying the best-estimate thermal-hydraulic safety analysis codes. This report was prepared to define technical specifications of the ISP-50 exercise according the guideline provided by OECD/CSNI. It includes general objectives, phases, deliverables to participants, parameters required for comparison and the time table

Activities of the AZTLAN team on the OECD/Nea benchmark on fast reactors

Energy Technology Data Exchange (ETDEWEB)

Lopez S, R.; Gomez T, A.; Puente E, F. [ININ, Carretera Mexico-Toluca s/n, Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E.; Arriaga R, L., E-mail: armando.gomez@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, 07738 Ciudad de Mexico (Mexico)

2017-09-15

In the present paper, the activities of the AZTLAN Platform Fast Reactor Group on the OECD/Nea Benchmark will be described. The main objective of these activities is to test the group staff and capabilities as well as the domestic code reliability by putting them into test in this exercise with different institutions from around the world. Six different core configurations were treated; these are described in two different versions of the Benchmark document. The main tools used by the group were the Finnish stochastic Monte Carlo code Serpent for full core calculations and macroscopic Cross Sections (X S) generation, and the domestic deterministic code AZNHEX for full core calculations. Different calculations were performed, such as full core calculations under nominal conditions, with control rods fully and partially inserted and with the sodium voided in the active zone as well as different reactivity shift values due to various conditions of radial and axial expansion of the fuel elements and structural material. The results obtained in the full core calculations and most of the reactivity shift calculations obtained by our group were indeed comparable to the ones obtained by different institutions when using similar methodologies. Given these favorable results it can be said that the main objective was met and the group showed their capabilities, as well as its possibility to collaborate with other institutes, placing Mexico in a good position in fast reactor analysis. Future work will continue with the calculations not yet treated and with the new core specifications on the new versions of the Benchmark document. (Author)

Synopsis of the results of ISP-39 on FARO test L-14

Energy Technology Data Exchange (ETDEWEB)

Addabbo, C.; Annunziato, A.; Magallon, D. [Commission of the European Communities, Ispra (Italy). Joint Research Center

1998-01-01

This paper provides a synopsis of the salient results from the ISP(International Standard Problem)-39 exercise promoted by OECD-CSNI in the frame of the NEA activities aimed at fostering international cooperation in reactor safety research and development. ISP-39 has been conceived to benchmark the predictive capabilities of computer codes used in the evaluation of FCI and quenching phenomenologies of relevance in water cooled reactors severe accidents safety analysis. The ISP-39 reference case is FARO test L-14, a non-energetic FCI test performed in the FARO experimental installation under realistic melt composition and prototypical test conditions. (author)

OECD/NEA Sandia Fuel Project phase I: Benchmark of the ignition testing

Energy Technology Data Exchange (ETDEWEB)

Adorni, Martina, E-mail: martina_adorni@hotmail.it [UNIPI (Italy); Herranz, Luis E. [CIEMAT (Spain); Hollands, Thorsten [GRS (Germany); Ahn, Kwang-II [KAERI (Korea, Republic of); Bals, Christine [GRS (Germany); D' Auria, Francesco [UNIPI (Italy); Horvath, Gabor L. [NUBIKI (Hungary); Jaeckel, Bernd S. [PSI (Switzerland); Kim, Han-Chul; Lee, Jung-Jae [KINS (Korea, Republic of); Ogino, Masao [JNES (Japan); Techy, Zsolt [NUBIKI (Hungary); Velazquez-Lozad, Alexander; Zigh, Abdelghani [USNRC (United States); Rehacek, Radomir [OECD/NEA (France)

2016-10-15

Highlights: • A unique PWR spent fuel pool experimental project is analytically investigated. • Predictability of fuel clad ignition in case of a complete loss of coolant in SFPs is assessed. • Computer codes reasonably estimate peak cladding temperature and time of ignition. - Abstract: The OECD/NEA Sandia Fuel Project provided unique thermal-hydraulic experimental data associated with Spent Fuel Pool (SFP) complete drain down. The study conducted at Sandia National Laboratories (SNL) was successfully completed (July 2009 to February 2013). The accident conditions of interest for the SFP were simulated in a full scale prototypic fashion (electrically heated, prototypic assemblies in a prototypic SFP rack) so that the experimental results closely represent actual fuel assembly responses. A major impetus for this work was to facilitate severe accident code validation and to reduce modeling uncertainties within the codes. Phase I focused on axial heating and burn propagation in a single PWR 17 × 17 assembly (i.e. “hot neighbors” configuration). Phase II addressed axial and radial heating and zirconium fire propagation including effects of fuel rod ballooning in a 1 × 4 assembly configuration (i.e. single, hot center assembly and four, “cooler neighbors”). This paper summarizes the comparative analysis regarding the final destructive ignition test of the phase I of the project. The objective of the benchmark is to evaluate and compare the predictive capabilities of computer codes concerning the ignition testing of PWR fuel assemblies. Nine institutions from eight different countries were involved in the benchmark calculations. The time to ignition and the maximum temperature are adequately captured by the calculations. It is believed that the benchmark constitutes an enlargement of the validation range for the codes to the conditions tested, thus enhancing the code applicability to other fuel assembly designs and configurations. The comparison of

CNRA/CSNI workshop on licensing and operating experience of computer-based I and C systems - Summary and conclusions

International Nuclear Information System (INIS)

2002-01-01

The OECD Workshop on Licensing and Operating Experience of Computer-Based I and C Systems, was sponsored by both the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organised in collaboration with the Czech State Office for Nuclear Safety (SUJB), the Czech Power Board CEZ a.s., I and C Energo a.s. and the Nuclear Research Institute, Rez near Prague. The objectives of the Workshop were to exchange the experience gained by both the regulators and the industry in different countries in the licensing and operation of computer-based I and C systems, to discuss the existing differences in their licensing approaches in various countries, to consider the safety aspects of their practical use, and to discuss the ways of promoting future international co-operation in the given area. The scope of the Workshop included: - review of the progress made since the CNRA/CSNI workshop which was held in 1996 - current and future regulatory needs and/or requirements for the computer-based I and C systems - progress made in software life cycle activities, including verification and validation, and safety/hazards analysis - benefits of applying the computer-based I and C systems to improve plant performance and safety. The Technical Sessions and Discussion Sessions covered the following topics: Opening Session: Advances made in the use and planning of computer-based I and C systems; Topic 1: National and international standards and guides for computer-based safety systems; Topic 2: Regulatory aspects; Topic 3: Analysis and assessment of digital I and C systems; Topic 4: Software life cycle activities; Topic 4: Experience with applications, system aspects, potential limits and future trends and needs; Final Session: Workshop summary. The workshop provided a unique opportunity for people with experience in licensing, developing, manufacturing, implementing, maintaining or

Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities. Japan

International Nuclear Information System (INIS)

2017-01-01

The NEA has updated, in coordination with the Permanent Delegation of Japan to the OECD, the report on the Regulatory and Institutional Framework for Nuclear Activities in Japan. This country report provides comprehensive information on the regulatory and institutional framework governing nuclear activities in Japan. It provides a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. Content: I - General Regulatory Regime: Introduction; Mining regime; Radioactive substances and equipment; Nuclear installations (Reactor Regulation, Emergency response); Trade in nuclear materials and equipment; Radiological protection; Radioactive waste management; Nuclear safeguards and nuclear security; Transport; Nuclear third party liability. II - Institutional Framework: Regulatory and supervisory authorities (Cabinet Office, Nuclear Regulation Authority (NRA), Ministry of Economy, Trade and Industry (METI), The Agency for Natural Resources and Energy (ANRE), Ministry of Land, Infrastructure, Transport and Tourism (MLIT), Ministry of Education, Culture, Sports, Science and Technology (MEXT)); Advisory bodies (Atomic Energy Commission (AEC), Reactor Safety Examination Committee, Nuclear Fuel Safety Examination Committee, Radiation Council, Other advisory bodies); Public and semi-public agencies (Japan Atomic Energy Agency (JAEA), National Institutes for Quantum and Radiological Science and Technology (QST), Nuclear Damage Compensation and Decommissioning Facilitation Corporation (NDF), Nuclear Waste Management Organisation (NUMO))

Nea study on the impact of advanced fuel cycles on waste management policies

International Nuclear Information System (INIS)

Cavedon, J.M.

2007-01-01

This study was carried out by the ad hoc Expert Group on the Impact of Advanced Fuel Cycles on Waste Management Policies convened under the auspices of the NEA Committee for Technical and Economic Studies on Nuclear Energy Development and the Fuel Cycle (NDC); the Integrated Group on Safety Case from the Radioactive Waste Management Committee provided support in the field of waste repository issues; the Nuclear Science Committee Working Group on Flowsheet Studies also provided some input data. The full report on this study is published as the NEA Report number 5990 - OECD 2006 by OECD Publications - ISBN 92-64-02296-1. The following text is extracted from the Executive Summary of the report. (author)

Proceedings of the CSNI workshop on International Standard Problem 48 - Analysis of 1:4-scale prestressed concrete containment vessel model under severe accident conditions

International Nuclear Information System (INIS)

2005-01-01

At the CSNI meeting in June 2002, the proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia test was approved. Objectives were to extend the understanding of capacities of actual containment structures based on results of the recent PCCV Model test and other previous research. The ISP was sponsored by the USNRC, and results had been made available thanks to NUPEC and to the USNRC. Sandia National Laboratory was contracted to manage the technical aspects of the ISP. At the end of the ISP48, a workshop was organized in Lyon, France on April 6-7, 2005 hosted by Electricite de France. Its overall objective was to present results obtained by participants in the ISP 48 and to assess the current practices and the state of the art with respect to the calculation of concrete structures under severe accident conditions. Experience from other areas in civil engineering related to the modelling of complex structures was greatly beneficial to all. Information obtained as a result of this assessment were utilized to develop a consensus on these calculations and identify issues or 'gaps' in the present knowledge for the primary purpose of formulating and prioritizing research needs on this topic. The ISP48 exercise was published in the report referenced NEA/CSNI/R(2005)5 in 3 volumes. Volume 1 contains the synthesis of the exercise; Volumes 2 and 3 contain individual contributions of participating organizations. The CSNI Working Group on the Integrity and Ageing and in particular its sub-group on the behaviour of concrete structures has produced extensive material over the last few years. The complete list of references is given in this document. These proceedings gather the papers and presentations given by the participants at the Lyon workshop

The CSNI program: current priorities and future outlook

International Nuclear Information System (INIS)

Dircks, W.J.

1986-01-01

This paper gives a brief and general account of activities within the working groups of the CSNI. The five Principal Working groups cover the following areas: operating experience and human factors; reactor transients and primary circuit breaks; primary circuit integrity; reactor accident source term, and environmental consequences; and, risk assessment

OECD/NEA source convergence benchmark program: overview and summary of results

International Nuclear Information System (INIS)

Blomquist, Roger; Nouri, Ali; Armishaw, Malcolm; Jacquet, Olivier; Naito, Yoshitaka; Miyoshi, Yoshinori; Yamamoto, Toshihiro

2003-01-01

This paper describes the work of the OECD Nuclear Energy Agency Expert Group on Source Convergence in Criticality Safety Analysis. A set of test problems is presented, some computational results are given, and the effects of source convergence difficulties are described

Key regulatory and safety issues emerging NEA activities. Lessons Learned from Fukushima Dai-ichi NPS Accident - Key Regulatory and Safety Issues

International Nuclear Information System (INIS)

Nakoski, John

2013-01-01

A presentation was provided on the key safety and regulatory issues and an update of activities undertaken by the NEA and its members in response to the accident at the Fukushima Daiichi nuclear power stations (NPS) on 11 March 2011. An overview of the accident sequence and the consequences was provided that identified the safety functions that were lost (electrical power, core cooling, and primary containment) that lead to units 1, 2, and 3 being in severe accident conditions with large off-site releases. Key areas identified for which activities of the NEA and member countries are in progress include accident management; defence-in-depth; crisis communication; initiating events; operating experience; deterministic and probabilistic assessments; regulatory infrastructure; radiological protection and public health; and decontamination and recovery. For each of these areas, a brief description of the on-going and planned NEA activities was provided within the three standing technical committees of the NEA with safety and regulatory mandates (the Committee on Nuclear Regulatory Activities - CNRA, the Committee on the Safety of Nuclear Installations - CSNI, and the Committee on Radiation Protection and Public Health - CRPPH). On-going activities of CNRA include a review of enhancement being made to the regulatory aspects for the oversight of on-site accident management strategies and processes in light of the lessons learned from the accident; providing guidance to regulators on crisis communication; and supporting the peer review of the safety assessments of risk-significant research reactor facilities in light of the accident. Within the scope of the CSNI mandate, activities are being undertaken to better understand accident progression; characteristics of new fuel designs; and a benchmarking study of fast-running software for estimating source term under severe accident conditions to support protective measure recommendations. CSNI also has ongoing work in human

NEA international co-operative projects

International Nuclear Information System (INIS)

1989-01-01

This text is consecrated at the international co-operative projects of the OECD Nuclear Energy Agency (NEA) in the field of reactor safety (Halden reactor project, Loft project, studies on the damaged Three Mile Island unit-2 reactor, inspection of reactor steel components, incident reporting system) and in the field of radioactive waste management (Stripa project, geochemical data bases, Alligator river project, seabed disposal of high-level radioactive waste, decommissioning of nuclear facilities)

OECD/NEA source convergence benchmark program. Overview and summary of results

International Nuclear Information System (INIS)

Blomquist, Roger; Nouri, Ali; Armishaw, Malcolm; Jacquet, Olivier; Naito, Yoshitaka; Miyoshi, Yoshinori; Yamamoto, Toshihiro

2003-01-01

This paper describes the work of the OECD Nuclear Energy Agency Expert Group on Source Convergence in Criticality Safety Analysis. A set of test problems is presented, some computational results are given, and the effects of source convergence difficulties are described. (author)

Meeting summary of the second CSNI specialist meeting on simulators and plant analyzers - Current Issues in Nuclear Power Plant Simulation

International Nuclear Information System (INIS)

1998-01-01

The Second CSNI Specialist Meeting on Simulators and Plant Analyzers: Current Issues in Nuclear Power Plant Simulation was held in Espoo, Finland, from September 29 through October 2, 1997. It was organised by CSNI Principal Working Group on Coolant System Behaviour (PWG2), Task Group on Thermal Hydraulic Applications (TG-THA), in co-operation with Technical Research Centre of Finland. The meeting in Espoo attracted some 90 participants from 17 countries. A total of 49 invited papers were presented in the meeting in addition to 7 simulator system demonstrations. Ample time was reserved for the presentations and informal discussions during the four meeting days. The previous meeting held in Lappeenranta, Finland, in 1992 collected some 85 participants from 12 countries, presenting a total of 40 papers. The meeting was structured into 6 sessions covering the important aspects of development and use of simulators and plant analyzers: Session I: New objectives, Requirements and Concepts. This session covered the progress experienced since the 1. simulator meeting and tried to address the changing role of simulators based on the changes in users' needs and developing possibilities. Session II: Trends in Simulation Technology. This session was reserved for studying the current trends in the simulation technology: software environments, visualisation, simulator configuration tools, programming languages and computer systems. Session III: Training and human factor studies using simulators. This session was created for studying the status of different uses of simulators such as educational simulators, human factor studies and integrated safety assessment in addition to traditional training. Regarding to the severe accidents, a question was raised whether the simulator use should be for training or education. Session IV: Modelling techniques. The session on modelling techniques was included to cover recent developments in the modelling techniques applicable to training

OECD/SERENA Project Report. Summary and Conclusions

International Nuclear Information System (INIS)

2015-02-01

The OECD/SERENA Project Integration Report summarises the outcome of a broad range of activities conducted in the framework of the Organisation for Economic Cooperation and Development (OECD) Steam Explosion Resolution for Nuclear Applications Project (OECD/SERENA) to address remaining issues on fuel-coolant interaction (FCI) mechanisms and their effect on ex-vessel steam explosion energetics. The scope the OECD/SERENA project was to resolve uncertainties in the remaining issues and to bring the code capabilities to an adequate level for use in reactor safety applications. This scope was accomplished with the completion of three major tasks: (1) an experimental programme consisting of two sets of steam explosion experiments in two different facilities; (2) an analytical programme consisting of pre-test calculations in support of test specifications and post-test calculations in support of data analysis and code assessment, and also a code benchmark exercise; and (3) a reactor calculation exercise repeating the one performed in the framework of the CSNI/WGAMA SERENA activity performed from 2001 to 2006 (also referred to as SERENA Phase I, published as CSNI/R(2007)/11). The objectives of the experimental programme were to provide data: (1) to clarify the explosion behaviour of prototypic corium melts and for validation of steam explosion models for prototypic materials; and (2) for steam explosion behaviour in two different geometries to verify the geometrical extrapolation capabilities of the codes. These objectives were to be accomplished by conducting complementary sets of six experiments each at two different facilities: KROTOS at the Commissariat l'Energie Atomique et aux Energies Alternatives (CEA) in Cadarache, France, representing one-dimensional FCI configuration involving nominally 5 kilograms of prototypic corium melt, and TROI at Korea Atomic Energy Research Institute (KAERI) in Daejeon, Korea, representing multi-dimensional FCI configuration

CSNI international standard problem procedures - CSNI Report No. 17 - Revision 4

International Nuclear Information System (INIS)

Micaelli, J.C.

2004-01-01

Assessing the safety of a nuclear installation requires the use of a number of highly specialised tools: computer codes, experimental facilities and their instrumentation, special measurement techniques, methods for testing materials and components and so on. These tools may vary to some extent in different countries and many of them are extremely complex and costly to produce and use. A highly effective way of increasing confidence in the validity and accuracy of such tools is provided by International Standard Problem (ISP) Exercises in which they are gauged against one another and/or against an agreed standard. For example, predictions of different computer codes for a given physical problem may be compared with each other and with the results of a carefully controlled experimental study which also could be a real plant transient. This kind of comparative exercise is clearly suitable for an international venture. CSNI is of the opinion that ISP exercises are useful and should be continued. ISPs are performed as 'open' or as 'blind' problems. In an open problem results of an experiment are available to participants before it is evaluated. In a blind problem results of the experiment are not made known to the participants until after delivery of the calculated results. Depending on the kind of experiment and its objectives, certain boundary and initial conditions of the experiment are communicated to the participants before they start the exercise. This is necessary where it is difficult to guarantee the reproducibility of experiments. For all ISPs the participants are provided with a complete description of the experimental facility. The Lead Country (proposing the ISP) must decide whether the data can be withheld temporarily (blind ISP) or whether the data will be published before the analysis of participating countries is completed (open ISP). It is recommended that ISPs be conducted blind, where possible. ISPs require a considerable expenditure of resources

Review of fast reactor activities at OECD (NEA)

International Nuclear Information System (INIS)

Stephens, M.

1981-01-01

The Committee on the Safety of Nuclear Installations initiated several reports in 1979. Status reports are published on: the role of fission gas release in case of fuel element failure; reactivity monitoring in a LMFBR at shutdown; increasing the reliability of fast reactor shutdown systems. A report is planned on the interactions between sodium and concrete. LMFBR safety issue that were studied are concerned with containment R and D; natural circulation cooling; and fuel failure modelling. Nuclear Development Division was concerned with Gas cooled fast reactors technology. Nuclear Science Division dealt with fast reactor physics and nuclear data for fast reactors. NEA Data Bank provides technical support and acts as a computer code library and nuclear data centre

Overview of nuclear data activities at the OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

Michel-Sendis, F.; Dupont, E.; Gulliford, J.; Nordborg, G.

2011-01-01

The Nuclear Energy Agency (NEA) is a specialised agency within the Organisation for Economic Co-operation and Development (OECD). The mission of the NEA is to assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for the safe, environmentally friendly and economical use of nuclear energy for peaceful purposes. All activities relevant to nuclear data measurements, evaluations and applications are managed by the NEA Nuclear Science Committee through the Nuclear Science section and the Data Bank, which work closely together. This paper gives an overview of current and planned nuclear data activities at the Nuclear Energy Agency through the program of work of the Data Bank in general and of the NEA Working Party on international nuclear data Evaluation Co-operation (WPEC) in particular. (authors)

Fast Reactor Knowledge Preservation Activities at the OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

Hill, Ian

2013-01-01

• NEA is organizing significant activities are ongoing to preserve fast reactor information: – Integral experiments supporting fast reactors; – Often “use it, or lose it”; – Difficult to preserve everything, critical information is identified; – Organisation is a large but important task; – Electronic databases needed to manage the data. • Authoritative Handbooks and state of the art reports: – These tend to be the documents that last. • OECD/NEA will continue to support member countries in fast reactor knowledge preservation: – forum for exchange of information; – collaborative activities

Establishment of data base files of thermodynamic data developed by OECD/NEA. Part 4. Addition of thermodynamic data for iron, tin and thorium

International Nuclear Information System (INIS)

Yoshida, Yasushi; Kitamura, Akira

2014-12-01

Thermodynamic data for compounds and complexes of elements with auxiliary species specialized in modeling requirements for safety assessments of radioactive waste disposal systems have been developed by the Thermochemical Data Base (TDB) project of the Nuclear Energy Agency in the Organization for Economic Co-operation and Development (OECD/NEA). Recently, thermodynamic data for aqueous complexes, solids and gases of thorium, tin and iron (Part 1) have been published in 2008, 2012 and 2013, respectively. These thermodynamic data have been selected on the basis of NEA’s guidelines which describe peer review and data selection, extrapolation to zero ionic strength, assignment of uncertainty, and temperature correction; therefore the selected data are considered to be reliable. The reliability of selected thermodynamic data of TDB developed by Japan Atomic Energy Agency (JAEA-TDB) has been confirmed by comparing with selected data by the NEA. For this comparison, text files of the selected data on some geochemical calculation programs are required. In the present report, the database files for the NEA’s TDB with addition of selected data for iron, tin and thorium to the previous files have been established for use of PHREEQC, Geochemist’s Workbench and EQ3/6. In addition, as an example of confirmation of quality, dominant species in iron TDB were compared in Eh-pH diagram and differences between JAEA-TDB and NEA-TDB were shown. Data base files established in the present study will be at the Website of thermodynamic, sorption and diffusion database in JAEA (http://migrationdb.jaea.go.jp/). A CD-ROM is attached as an appendix. (J.P.N.)

Discussion of OECD LWR Uncertainty Analysis in Modelling Benchmark

International Nuclear Information System (INIS)

Ivanov, K.; Avramova, M.; Royer, E.; Gillford, J.

2013-01-01

The demand for best estimate calculations in nuclear reactor design and safety evaluations has increased in recent years. Uncertainty quantification has been highlighted as part of the best estimate calculations. The modelling aspects of uncertainty and sensitivity analysis are to be further developed and validated on scientific grounds in support of their performance and application to multi-physics reactor simulations. The Organization for Economic Co-operation and Development (OECD) / Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC) has endorsed the creation of an Expert Group on Uncertainty Analysis in Modelling (EGUAM). Within the framework of activities of EGUAM/NSC the OECD/NEA initiated the Benchmark for Uncertainty Analysis in Modelling for Design, Operation, and Safety Analysis of Light Water Reactor (OECD LWR UAM benchmark). The general objective of the benchmark is to propagate the predictive uncertainties of code results through complex coupled multi-physics and multi-scale simulations. The benchmark is divided into three phases with Phase I highlighting the uncertainty propagation in stand-alone neutronics calculations, while Phase II and III are focused on uncertainty analysis of reactor core and system respectively. This paper discusses the progress made in Phase I calculations, the Specifications for Phase II and the incoming challenges in defining Phase 3 exercises. The challenges of applying uncertainty quantification to complex code systems, in particular the time-dependent coupled physics models are the large computational burden and the utilization of non-linear models (expected due to the physics coupling). (authors)

Participation in the international comparison of probabilistic consequence assessment codes organized by OECD/NEA and CEC. Final Report

International Nuclear Information System (INIS)

Rossi, J.

1994-02-01

Probabilistic Consequence Assessment (PCA) methods are exploited not only in risk evaluation but also to study alternative design features, reactor siting recommendations and to obtain acceptable dose criteria by the radiation safety authorities. The models are programmed into computer codes for these kind of assessment. To investigate the quality and competence of different models, OECD/NEA and CEC organized the international code comparison exercise, which was participated by the organizations from 15 countries. There were seven codes participating in the exercise. The objectives of the code comparison exercise were to compare the results by the codes, to contribute to PCA code quality assurance, to harmonize the codes, to provide a forum for discussion on various approaches and to produce the report on the exercise. The project started in 1991 and the results of the calculations were completed in autumn 1992. The international report consists of two parts: the Overview Report for decision makers and the supporting detailed Technical Report. The results of the project are reviewed as an user of the ARANO-programme of VTT and trends of it's further development are indicated in this report. (orig.) (11 refs., 13 figs., 4 tabs.)

RELAP5-3D Results for Phase I (Exercise 2) of the OECD/NEA MHTGR-350 MW Benchmark

Energy Technology Data Exchange (ETDEWEB)

Gerhard Strydom

2012-06-01

The coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D has recently been initiated at the Idaho National Laboratory (INL) to provide a fully coupled prismatic Very High Temperature Reactor (VHTR) system modeling capability as part of the NGNP methods development program. The PHISICS code consists of three modules: INSTANT (performing 3D nodal transport core calculations), MRTAU (depletion and decay heat generation) and a perturbation/mixer module. As part of the verification and validation activities, steady state results have been obtained for Exercise 2 of Phase I of the newly-defined OECD/NEA MHTGR-350 MW Benchmark. This exercise requires participants to calculate a steady-state solution for an End of Equilibrium Cycle 350 MW Modular High Temperature Reactor (MHTGR), using the provided geometry, material, and coolant bypass flow description. The paper provides an overview of the MHTGR Benchmark and presents typical steady state results (e.g. solid and gas temperatures, thermal conductivities) for Phase I Exercise 2. Preliminary results are also provided for the early test phase of Exercise 3 using a two-group cross-section library and the Relap5-3D model developed for Exercise 2.

NEA activities in 1994

International Nuclear Information System (INIS)

1995-01-01

This report deals with the activities in 1994 of the OECD Nuclear Energy Agency including : trends in nuclear power, nuclear development and fuel cycle (data, tools, methodologies, nuclear industry and its context, fuel cycle policy, energy policy reviews), reactor safety and regulation (exchange of operating experience and human factors, accident prevention activities, severe-accident phenomenology and management, structural integrity, probabilistic safety assessment, fuel cycle safety, regulatory approaches to severe-accident issues, inspection practices), radiation protection (radiation protection today and tomorrow, application of radiation protection standards, protection of workers, international emergency exercises), radioactive waste management (the philosophical and ethical basis of disposal, safety assessment and site investigations, other radiation waste management activities), nuclear science (scientific studies, validation of working methods, the NEA data bank, projects in support of other NEA programmes), joint projects (the Rasplav project, the Halden reactor project, information system on occupational exposure, decommissioning of nuclear facilities), legal affairs (liability and nuclear safety assistance to Eastern Europe, training seminar on nuclear law, information on nuclear law), information programme (review of Nea information programme, publications programme, a major information forum), and relations with non m ember countries (NEA relations with non-members countries, the Central and Eastern European Countries and New Independent States of the former Soviet Union programme of co-operation and assistance). (O.L.). 22 figs

Factors affecting the future of nuclear power in OECD Europe

International Nuclear Information System (INIS)

Thompson, S.

1997-01-01

This report provides a brief review of nuclear power in OECD Europe and addresses the prospects for its future over, say, the next quarter century. Most of the data and findings are drawn from studies published by the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-operation and Development (OECD). The NEA is a small agency with a rather modest budget whose 27 members are industrialized countries from North America, Asia and Europe. The Agency works to pool the expertise of our member countries to produce technical, economic and legal work of considerable depth and quality addressing issues of common interest to those countries. Our work covers such fields as nuclear science, nuclear power economics, nuclear safety, radiation protection, waste management and nuclear liability. The studies carried out in the framework of the Agency require fewer resources than would be needed by our member countries if they were to pursue them individually, which is especially important at a time of cut-backs in national programmes in such critical areas as nuclear safety research. (author)

NEA activities in 1983. 12. Activity report

International Nuclear Information System (INIS)

1984-01-01

This report describes the main features of the Agency's work during 1983 and discusses the state and prospects of the nuclear industry in OECD countries. Trends in nuclear power, nuclear development and the fuel cycles nuclear safety technology and licensing, radiological and environmental impacts of nuclear fuel cycle activities, legal affairs, nuclear science, joint undertakings and other NEA joint projects, organisation and administration are reviewed

The CSNI International Standard Problem Programme: Overall Presentation on Objectives; Rationale and Lessons Learnt: a Joint Venture of the Thermalhydraulic International Community

International Nuclear Information System (INIS)

Reocreux, M.

2008-01-01

The CSNI International Standard Problems have been one of the key activities of the CSNI thermal hydraulics groups during the last 25 years. After recalling the way the international standard problems were initiated in the late 1970 years -they were called at that time CSNI LOCA Standard Problem- the process which has led to make from the ISPs a full CSNI activity, is described. Rules have been defined which formalized the way experimental results were provided and the way the comparison exercise were performed. The long series of ISPs from 1975 up to nowadays is described, explaining the different trends in the ISPs choices. The findings which have been obtained are reviewed on both technical and programmatic aspects.

CSNI technical opinion papers no.5. Managing and regulating organisational change in nuclear installations

International Nuclear Information System (INIS)

2004-01-01

Nuclear licensees are increasingly required to adapt to a more challenging commercial environment as electricity markets are liberalized. One of the costs that is often perceived as being amenable to control is staffing, and hence there is significant exploration of new strategies for managing this cost - for example, by reducing staffing levels, changing organisational structures, adopting new shift strategies, introducing new technology or increasing the proportion of work carried out by external contractors. However, if changes to staffing levels or organisational structures and systems are inadequately conceived or executed they have the potential to affect the way in which safety is managed. In this context, the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Special Expert Group on Human and Organisational Factors (SEGHOF) organised an international workshop to discuss the management and regulation of organisational change in 2001. This technical opinion paper distills the findings of that workshop and sets out the factors that regulatory bodies might reasonably expect to be addressed within licensees arrangements to manage organisational change. The paper should be of particular interest to both regulators and managers of nuclear utilities. (author)

The Nuclear Energy Agency of the OECD through its history

International Nuclear Information System (INIS)

Echavarri, L.

2008-01-01

This year, 2008, marks the 50th Anniversary of the OECD Nuclear Energy Agency (NEA). During these years the Agency has adapted to the evolution of the world energy situation. At the beginning the Agency launches international collaboration projects to establish the technological bases required for nuclear energy, then helps member countries in the construction of nuclear power plants and later analyzes the safety criteria as a consequence of the Three Miles Island and Chernobyl accidents. Based on this experience, the NEA faces the X XI Century prepared to contribute, even more, to a better international collaboration for a safe, environmentally friendly and economical use of the nuclear energy. (Author)

Summary of OECD survey of education in the nuclear energy field in Finland

International Nuclear Information System (INIS)

Kalli, H.

1999-01-01

This summary is a part of the work in the OECD/NEA/NDC expert group on the survey and analysis of education in the nuclear field. The text will later be published as a country report in the final report by expert group. (author)

The NEA and the IAEA: partnering for progress

International Nuclear Information System (INIS)

Marcus, G.H.

2005-01-01

This presentation aims to answer the following question: What is the difference between the OECD Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA)? Or, to put it bluntly, why are two international intergovernmental agencies needed in the nuclear field? This careful analysis shows that each agency has different areas of emphasis and different strengths. (A.L.B.)

Workshop on iodine aspects of severe accident management. Summary and conclusions

International Nuclear Information System (INIS)

2000-03-01

Following a recommendation of the OECD Workshop on the Chemistry of Iodine in Reactor Safety held in Wuerenlingen (Switzerland) in June 1996 [Summary and Conclusions of the Workshop, Report NEA/CSNI/R(96)7], the CSNI decided to sponsor a Workshop on Iodine Aspects of Severe Accident Management, and their planned or effective implementation. The starting point for this conclusion was the realization that the consolidation of the accumulated iodine chemistry knowledge into accident management guidelines and procedures remained, to a large extent, to be done. The purpose of the meeting was therefore to help build a bridge between iodine research and the application of its results in nuclear power plants, with particular emphasis on severe accident management. Specifically, the Workshop was expected to answer the following questions: - what is the role of iodine in severe accident management? - what are the needs of the utilities? - how can research fulfill these needs? The Workshop was organized in Vantaa (Helsinki), Finland, from 18 to 20 May 1999, in collaboration with Fortum Engineering Ltd. It was attended by forty-six specialists representing fifteen Member countries and the European Commission. Twenty-eight papers were presented. These included four utility papers, representing the views of Electricite de France (EDF), Teollisuuden Voima Oy and Fortum Engineering Ltd (Finland), the Nuclear Energy Institute (USA), and Japanese utilities. The papers were presented in five sessions: - iodine speciation; - organic compound control; - iodine control; - modeling; - iodine management; A sixth session was devoted to a general discussion on iodine management under severe accident conditions. This report summarizes the content of the papers and the conclusions of the workshop

CSNI post-Fukushima activity on filtered containment venting systems: status in OECD countries and guidance for improvements and future designs - 15008

International Nuclear Information System (INIS)

Jacquemain, D.; Guentay, S.; Basu, S.; Sonnenkalb, M.; Lebel, L.; Allelein, H.J.; Liebana, B.; Eckardt, B.; Ammirabile, L.

2015-01-01

Stress tests performed after the Fukushima' s accident have led many countries to consider the implementation of Filtered Containment Venting Systems (FCVS) and strategies at their Nuclear Power Plants (NPP). Where not earlier applied, this could be considered as part of severe accident management (SAM) measures to enhance the response capability to severe accident (SA) situations. In addition, some countries are considering upgrading existing FCVS and their operation procedures for safe and reliable use in conditions which were not necessarily fully addressed at their design stage (e.g., robustness to hazards and hydrogen combustion loads, prolonged or repetitive use during a SA and manual operation without power supply). The CSNI report details safety design and qualification requirements for FCVS, FCV strategies for emergency operating procedures and SAM domains, implemented filtration technologies, performed source term evaluations in view of FCVS and provides guidance for the improvement of existing systems and for the design of future systems. Main outcomes of the report are presented in this paper

OECD/NEA burnup credit criticality benchmarks phase IIIA: Criticality calculations of BWR spent fuel assemblies in storage and transport

Energy Technology Data Exchange (ETDEWEB)

Okuno, Hiroshi; Naito, Yoshitaka [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Ando, Yoshihira [Toshiba Corp., Kawasaki, Kanagawa (Japan)

2000-09-01

The report describes the final results of Phase IIIA Benchmarks conducted by the Burnup Credit Criticality Calculation Working Group under the auspices of the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA). The benchmarks are intended to confirm the predictive capability of the current computer code and data library combinations for the neutron multiplication factor (k{sub eff}) of a layer of irradiated BWR fuel assembly array model. In total 22 benchmark problems are proposed for calculations of k{sub eff}. The effects of following parameters are investigated: cooling time, inclusion/exclusion of FP nuclides and axial burnup profile, and inclusion of axial profile of void fraction or constant void fractions during burnup. Axial profiles of fractional fission rates are further requested for five cases out of the 22 problems. Twenty-one sets of results are presented, contributed by 17 institutes from 9 countries. The relative dispersion of k{sub eff} values calculated by the participants from the mean value is almost within the band of {+-}1%{delta}k/k. The deviations from the averaged calculated fission rate profiles are found to be within {+-}5% for most cases. (author)

Proceedings of the specialist meeting on the safety of water reactors fuel elements

International Nuclear Information System (INIS)

1973-01-01

This specialist meeting on the safety of water reactors fuel elements was held in Saclay (France) in October 1973, and was organized by CSNI and CEA. It attracted specialists from 14 countries. Session I was devoted to normal operating conditions (coolant-cladding and fuel-cladding interactions, fission product release, effects of cladding deformation on fuel element performances and reactor operating limits); Session II was devoted to operating reactor accidents and failures, anomalous transients and handling accidents; Session III was devoted to modifications to be applied to fuel elements in order to enhance their safety and reliability; Session IV was devoted to Loss-of-Coolant Accidents (LOCA)(cladding behaviour during the accident, assembly behaviour during the accident, criteria to be considered for the study of fuel element behaviour during a LOCA)

Contribution from twenty two years of CSNI International Standard Problems

International Nuclear Information System (INIS)

1998-03-01

This report provides a brief overview on the contribution of some CSNI International Standard Problems (ISPs) to nuclear reactor safety issues (41 ISPs performed over the last 22 years). This CSNI activity on ISPs has been one of the major activities of the Principal Working Group no.2 on Coolant System Behaviour. Its domain extended from thermal-hydraulics to several other accident domains following the main concerns of nuclear reactor safety, e.g., LOCA predictions fuel behaviour, operator procedures, containment thermal-hydraulics severe accidents, VVERs, etc. ISPs are providing unique material and benefits for some safety related issues. Clearly, all the technical findings and benefits provided by ISPs are still needed and contribute to advancement of nuclear safety. The report provides some overview on the general objectives of ISPs, content and types of ISPs, and technical domains covered by ISPs, followed by a synthesis of technical findings and benefits to the scientific community

IRS Guidelines: Joint IAEA/NEA International Reporting System for Operating Experience

International Nuclear Information System (INIS)

2010-01-01

The International Reporting System for Operating Experience (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the OECD Nuclear Energy Agency (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants which are operated worldwide. This objective can be achieved by providing timely and detailed information on lessons learned from operating and construction experience at the international level. This information could be related to issues and events that are related to safety. The purpose of these guidelines is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the effectiveness of the system expected by all Member States operating nuclear power plants. As this system is owned by the Member States, the IRS Guidelines have been developed and approved by the IRS National Co-ordinators with the assistance of both Secretariats (IAEA/NEA).

Advanced thermal-hydraulic and neutronic codes: current and future applications. Summary and conclusions

International Nuclear Information System (INIS)

2001-05-01

An OECD Workshop on Advanced Thermal-Hydraulic and Neutronic Codes Applications was held from 10 to 13 April 2000, in Barcelona, Spain, sponsored by the Committee on the Safety of Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organised in collaboration with the Spanish Nuclear Safety Council (CSN) and hosted by CSN and the Polytechnic University of Catalonia (UPC) in collaboration with the Spanish Electricity Association (UNESA). The objectives of the Workshop were to review the developments since the previous CSNI Workshop held in Annapolis [NEA/CSNI/ R(97)4; NUREG/CP-0159], to analyse the present status of maturity and remnant needs of thermal-hydraulic (TH) and neutronic system codes and methods, and finally to evaluate the role of these tools in the evolving regulatory environment. The Technical Sessions and Discussion Sessions covered the following topics: - Regulatory requirements for Best-Estimate (BE) code assessment; - Application of TH and neutronic codes for current safety issues; - Uncertainty analysis; - Needs for integral plant transient and accident analysis; - Simulators and fast running codes; - Advances in next generation TH and neutronic codes; - Future trends in physical modeling; - Long term plans for development of advanced codes. The focus of the Workshop was on system codes. An incursion was made, however, in the new field of applying Computational Fluid Dynamic (CFD) codes to nuclear safety analysis. As a general conclusion, the Barcelona Workshop can be considered representative of the progress towards the targets marked at Annapolis almost four years ago. The Annapolis Workshop had identified areas where further development and specific improvements were needed, among them: multi-field models, transport of interfacial area, 2D and 3D thermal-hydraulics, 3-D neutronics consistent with level of details of thermal-hydraulics. Recommendations issued at Annapolis included: developing small pilot/test codes for

Proceedings of the workshop on advanced thermal-hydraulic and neutronic codes: current and future applications

International Nuclear Information System (INIS)

2001-01-01

An OECD Workshop on Advanced Thermal-Hydraulic and Neutronic Codes Applications was held from 10 to 13 April 2000, in Barcelona, Spain, sponsored by the Committee on the Safety of Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organised in collaboration with the Spanish Nuclear Safety Council (CSN) and hosted by CSN and the Polytechnic University of Catalonia (UPC) in collaboration with the Spanish Electricity Association (UNESA). The objectives of the Workshop were to review the developments since the previous CSNI Workshop held in Annapolis [NEA/CSNI/ R(97)4; NUREG/CP-0159], to analyse the present status of maturity and remnant needs of thermal-hydraulic (TH) and neutronic system codes and methods, and finally to evaluate the role of these tools in the evolving regulatory environment. The Technical Sessions and Discussion Sessions covered the following topics: - Regulatory requirements for Best-Estimate (BE) code assessment; - Application of TH and neutronic codes for current safety issues; - Uncertainty analysis; - Needs for integral plant transient and accident analysis; - Simulators and fast running codes; - Advances in next generation TH and neutronic codes; - Future trends in physical modeling; - Long term plans for development of advanced codes. The focus of the Workshop was on system codes. An incursion was made, however, in the new field of applying Computational Fluid Dynamic (CFD) codes to nuclear safety analysis. As a general conclusion, the Barcelona Workshop can be considered representative of the progress towards the targets marked at Annapolis almost four years ago. The Annapolis Workshop had identified areas where further development and specific improvements were needed, among them: multi-field models, transport of interfacial area, 2D and 3D thermal-hydraulics, 3-D neutronics consistent with level of details of thermal-hydraulics. Recommendations issued at Annapolis included: developing small pilot/test codes for

Joint IAEA/NEA IRS guidelines

International Nuclear Information System (INIS)

1997-01-01

The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants

Report by the scientific secretary on major IAEA activities during 1989-1991

International Nuclear Information System (INIS)

Kossilov, A.

1992-01-01

Major IAEA activities in the field of nuclear power plant control and instrumentation in 1989-1991 are described: IAEA/OECD/NEA International Symposium on ''Balancing Automation and Human Action in Nuclear Power Plants'', Munich, Germany, 9-13 July 1990; specialists meetings; cooperation with OECD/NEA; a Review Report on ''Control Rooms and Man-Machine Interface in Nuclear Power Plants''; Advisory Group Meeting on ''The Balance Between Automation and Human Actions in NPP Operation''; use of simulators for training and maintaining competence; the guidelines for control room design; operator support systems in NPPs

Trend and pattern analysis of operational data through cooperation between OECD countries

International Nuclear Information System (INIS)

Dupuis, M.C.

1989-05-01

This papers deals with trend analyses achieved by NEA/OECD countries to assess operational safety experience. It describes the main features of the incident Reporting System operated by NEA to collect relevant safety events from nuclear power plants. It presents the results of exchange methods within Principal Working Group no 1 in charge of operating experience and human factors; the use of preselected IRS incidents is illustrated by the study of losses of containment functions performed by PWGl; some trends resulting from enlarged international exchanges dealing with operational data are highlighted through two examples: reducing scram frequency and improving technical specifications

Trend and pattern analysis of operational data through cooperation between OECD countries

International Nuclear Information System (INIS)

Dupuis, M.C.

1990-01-01

This papers deals with trend analyses achieved by NEA/OECD countries to assess operational safety experience. It describes the main features of the Incident Reporting System operated by NEA to collect relevant safety events from nuclear power plants. It presents the results of exchange methods within Principal Working Group n 0 1 in charge of operating experience and human factors; the use of preselected IRS incidents is illustrated by the study of losses of containment functions performed by PWG1; some trends resulting from enlarged international exchanges dealing with operational data are highlighted through two examples: reducing scram frequency and improving technical specifications

NEA activities in 1993. 22. Annual Report of the OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

1994-01-01

The titles and themes of the ten chapters of this report on NEA activities are: trends in nuclear energy; nuclear development and the fuel cycle (potential contribution of nuclear energy, policy alternatives, maintaining the nuclear option, prospective); reactor safety and regulation (safety research, regulatory approach, safety assessment, accident phenomenology and management, human factors, international standards); radiation protection (revision of the standards, assessment of the protection, international emergency exercises); radioactive waste management (long term safety assessment, in situ evaluation, other radioactive wastes); nuclear science (role, nuclear data, use of supercomputers, actinide transmutation, NEA Data Bank); joint projects (Three Mile Island vessel investigation, Halden reactor project...); legal affairs (liability aspects...); information programme; relations with non-member countries. 28 figs

JANIS: NEA JAva-based Nuclear Data Information System

Science.gov (United States)

Soppera, Nicolas; Bossant, Manuel; Cabellos, Oscar; Dupont, Emmeric; Díez, Carlos J.

2017-09-01

JANIS (JAva-based Nuclear Data Information System) software is developed by the OECD Nuclear Energy Agency (NEA) Data Bank to facilitate the visualization and manipulation of nuclear data, giving access to evaluated nuclear data libraries, such as ENDF, JEFF, JENDL, TENDL etc., and also to experimental nuclear data (EXFOR) and bibliographical references (CINDA). It is available as a standalone Java program, downloadable and distributed on DVD and also a web application available on the NEA website. One of the main new features in JANIS is the scripting capability via command line, which notably automatizes plots generation and permits automatically extracting data from the JANIS database. Recent NEA software developments rely on these JANIS features to access nuclear data, for example the Nuclear Data Sensitivity Tool (NDaST) makes use of covariance data in BOXER and COVERX formats, which are retrieved from the JANIS database. New features added in this version of the JANIS software are described along this paper with some examples.

Proceedings of the third CSNI workshop on iodine chemistry in reactor safety

International Nuclear Information System (INIS)

Ishigure, Kenkichi; Saeki, Masakatsu; Soda, Kunihisa; Sugimoto, Jun

1992-03-01

This issue is the collection of the papers presented at the CSNI (Committee on the Safety of Nuclear Installations) workshop on iodine chemistry in reactor safety. The 31 of the presented papers are indexed individually. (J.P.N.)

OECD/NEA burnup credit criticality benchmarks phase IIIB: Burnup calculations of BWR fuel assemblies for storage and transport

International Nuclear Information System (INIS)

Okuno, Hiroshi; Naito, Yoshitaka; Suyama, Kenya

2002-02-01

The report describes the final results of the Phase IIIB Benchmark conducted by the Expert Group on Burnup Credit Criticality Safety under the auspices of the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD). The Benchmark was intended to compare the predictability of current computer code and data library combinations for the atomic number densities of an irradiated PWR fuel assembly model. The fuel assembly was irradiated under specific power of 25.6 MW/tHM up to 40 GWd/tHM and cooled for five years. The void fraction was assumed to be uniform throughout the channel box and constant, at 0, 40 and 70%, during burnup. In total, 16 results were submitted from 13 institutes of 7 countries. The calculated atomic number densities of 12 actinides and 20 fission product nuclides were found to be for the most part within a range of ±10% relative to the average, although some results, esp. 155 Eu and gadolinium isotopes, exceeded the band, which will require further investigation. Pin-wise burnup results agreed well among the participants. The results in the infinite neutron multiplication factor k ∞ also accorded well with each other for void fractions of 0 and 40%; however some results deviated from the averaged value noticeably for the void fraction of 70%. (author)

OECD/NEA burnup credit criticality benchmarks phase IIIB. Burnup calculations of BWR fuel assemblies for storage and transport

Energy Technology Data Exchange (ETDEWEB)

Okuno, Hiroshi; Naito, Yoshitaka; Suyama, Kenya [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-02-01

The report describes the final results of the Phase IIIB Benchmark conducted by the Expert Group on Burnup Credit Criticality Safety under the auspices of the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD). The Benchmark was intended to compare the predictability of current computer code and data library combinations for the atomic number densities of an irradiated PWR fuel assembly model. The fuel assembly was irradiated under specific power of 25.6 MW/tHM up to 40 GWd/tHM and cooled for five years. The void fraction was assumed to be uniform throughout the channel box and constant, at 0, 40 and 70%, during burnup. In total, 16 results were submitted from 13 institutes of 7 countries. The calculated atomic number densities of 12 actinides and 20 fission product nuclides were found to be for the most part within a range of {+-}10% relative to the average, although some results, esp. {sup 155}Eu and gadolinium isotopes, exceeded the band, which will require further investigation. Pin-wise burnup results agreed well among the participants. The results in the infinite neutron multiplication factor k{sub {infinity}} also accorded well with each other for void fractions of 0 and 40%; however some results deviated from the averaged value noticeably for the void fraction of 70%. (author)

Implications of draft ICRP recommendations: the View of the OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

Magnusson, S.; Lazo, T.

2006-01-01

Full text: The OECD Nuclear Energy Agency has taken an active interest in the work being performed by the International Commission on Radiological Protection (ICRP) to develop a new set of general recommendations. As several key junctures, the Nea, through the lead of its Committee on Radiation Protection and Public Health (C.R.P.P.H.) has performed in-depth analyses of the possible implications that draft ICRP materials, in order to inform policy makers of the regulatory and application implications that would result should draft ICRP Recommendations for a system of radiological protection be published. Comments from the Nea have constructively contributed to the ICRP development process, and it is hoped that the final ICRP recommendations in this area will be developed to best serve the needs of national and international radiation protection policy makers, regulators and implementers. Having assessed and commented on previous drafts, the C.R.P.P.H. has co-ordinated the views of all the relevant standing technical committees within the OECD Nuclear Energy Agency to provide constructive suggestions as to how the text could be usefully improved. Comments were requested from the Nea committees dealing with radioactive waste management, nuclear safety, nuclear regulatory activities, nuclear development and nuclear science. The present paper summarises the results of the C.R.P.P.H. review process related to the new ICRP recommendations. (author)

NEA activities in 1989

International Nuclear Information System (INIS)

1990-01-01

This report presents the main features of the Agency work during 1989. It deals with trends in nuclear power; nuclear development and the fuel cycle; nuclear safety and licensing; radiation protection; radioactive waste management; legal affairs; nuclear science; joint undertakings and other NEA joint projects; information programmes; organization and administration. A list of workshops, specialist meetings and symposia organized during 1989 and a list of publications and other matter produced in 1989 are included

Nuclear data activities at the NEA Data Bank

International Nuclear Information System (INIS)

Hasegawa, A.; Henriksson, H.; Mompean, F.J.; Nordborg, C.; Rugama, Y.; Sartori, E.

2008-01-01

The OECD Nuclear Energy Agency (NEA) Data Bank is an international centre of reference for its member countries with respect to basic nuclear tools, such as computer codes and nuclear data. The Data Bank is part of an international network of data centres in charge of the compilation and dissemination of basic nuclear data. The NEA nuclear data services include the collection of data, validation and distribution of the Nuclear Data libraries via the NEA web-site, offering easy access to databases containing bibliographical and experimental information, as well as evaluated libraries, e.g., the Joint Evaluated Fission and Fusion (JEFF) library. The selection and distribution of chemical thermodynamic data for radioactive waste management applications is the subject of the Thermochemical Database Project (TDB), supported by 17 organisations in 12 member countries and co-ordinated by the NEA Data Bank. In support of data evaluation, and generation of project oriented data libraries, relevant computer codes in the field of nuclear models, experimental data processing and evaluated data processing are made available to experts with the support of the member countries. Large collections of benchmark experiments for data and code validation are also available from the NEA in areas such as criticality safety (ICSBEP), radiation shielding (SINBAD), fuel performance (IFPE) and reactor physics (IRPhE). The NEA Working Party on international nuclear data Evaluation Co-operation (WPEC) provides a framework for co-operative activities between the six major evaluation projects (BROND, CENDL, Endf, FENDL, JEFF and JENDL). (authors)

The coupled code system DORT-TD/THERMIX and its application to the OECD/NEA/NSC PBMR400 MW coupled neutronics thermal hydraulics transient benchmark

International Nuclear Information System (INIS)

Pautz, A.; Tyobeka, B.; Ivanov, K.

2009-01-01

In new reactor designs that are still under review such as the Pebble Bed Modular Reactor (PBMR), not much experimental data exists to benchmark newly developed computer codes against. Such a situation requires that nuclear engineers and designers of this novel reactor design must resort to the validation of a newly developed code through a code-to-code benchmarking exercise because there are validated codes that are currently in use to analyze this reactor design, albeit very few of them. There are numerous HTR core physics benchmarks that are currently being pursued by different organizations, for different purposes. One such benchmark exercise is the PBMR-400MW OECD/NEA coupled neutronics/thermal hydraulics transient benchmark. In this paper, a newly developed coupled neutronics thermal hydraulics code system, DORT-TD/THERMIX with both transport and diffusion theory options, is used to simulate both the steady-state as well as several transient scenarios in this benchmark problem. (orig.)

Rasplav. A unique OECD/Russian experimental/analytical program in severe accident management/mitigation

International Nuclear Information System (INIS)

Speis, T.P.; Behbahani, A.

1995-01-01

In 1994 the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (NEA-OECD) sponsored the RASPLAV project in Russia to carry out an integrated program of experiments and analyses to address the conditions under which a degraded/molten core can be retained inside the reactor pressure vessel via cooling of the vessel from outside. The background, the objectives, the technical issues associated with, the utilization of the results and the benefits to the participating countries are discussed, involving Russian partnership with the most advanced OECD member countries in a project which will be carried out at the Kurchatov Institute in Russia. (author). 1 fig

Proceedings of a C.S.N.I. specialist meeting on instrumented pre-cracked Charpy testing

Energy Technology Data Exchange (ETDEWEB)

Wullaert, R A [Fracture Control Corp., 340 South Kellogg Avenue, Suite G, Goleta, California 93017 (United States)

1981-11-15

This report presents the status of the testing and data analysis procedures for the instrumented pre-cracked Charpy test with emphasis on the application of the test technique to the nuclear industry. The report (Proceedings) consist of invited technical papers by specialists in the field and a synopsis of the comments, conclusions, and recommendations reached in a workshop session. The CSNl-sponsored and EPRI-hosted meeting confirmed both the popularity of the test technique in the nuclear industry and the problems associated with the test technique due to the lack of a national or international consensus standard. Major emphasis in the meeting was devoted to evaluating the existing industry testing procedure (EPRI procedure) and proposed national standards (ASTM, ASK). The EPRI procedures were considered adequate by specialists concerned with engineering applications, but too restrictive by specialists concerned with research applications. As a result of the conference, a compilation of state-of-the-art papers is now available to code and standard committees. Specific comments concerning test and data analysis procedures, applications in the nuclear industry, and future research areas are also contained in the proceedings

IAEA/NEA Fuel Incident Notification and Analysis System (FINAS) guidelines

International Nuclear Information System (INIS)

2006-01-01

The Fuel Incident Notification and Analysis System (FINAS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development (OECD/NEA). The fundamental objective of FINAS is to contribute to improving the safety of fuel cycle facilities, which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance, which occur at these facilities. The purpose of these guidelines, which supersede the previous NEA FINAS guidelines is to describe the system and to give users the necessary background and guidance to enable them to produce FINAS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating FCFs. These guidelines have been jointly developed and approved by the NEA/IAEA

SOAR on Containment Thermal-hydraulics and Hydrogen Distribution - Prepared by an OECD/NEA Group of Experts

International Nuclear Information System (INIS)

Karwat, Helmut; Bardelay, Joel; Hashimoto, Takashi; Koroll, Grant W.; Krause, Matt; L'Heriteau, Jean-Pierre; Lundstroem, Petra; Notafrancesco, Allen; Royl, Peter; Schwinges, Bernd; Tezuka, Hiroko; Tills, Jack; Royen, Jacques

1999-06-01

During the course of severe accidents in water-cooled nuclear power plants, large amounts of hydrogen could be generated and released into the containment. The formation of hydrogen inevitably accompanies any core degradation process. The problem may be amplified by the less-likely core-concrete interaction during a subsequent basemat erosion. The integrity of the containment could be challenged by certain hydrogen combustion modes if no mitigative measures were available. International consensus is that a detailed knowledge of containment thermal-hydraulics is necessary to analyse the effectiveness of hydrogen mitigation methods, even though, at present, there are no generally accepted requirements for this purpose. During the last decade, considerable international efforts have been undertaken to better understand the associated problems by executing a large number of experiments and subjecting the test results to extensive analytical assessment. The CSNI Principal Working Group 4 at its meeting in September 1995 proposed to CSNI to draft a state-of-the-art-report (SOAR) on 'Containment Thermal-hydraulics and Hydrogen Distribution'. CSNI had endorsed the preparation of such a SOAR at its November 1995 meeting. The mandate for this SOAR can be best illustrated by several guiding questions that had been raised and discussed during earlier meetings of PWG4 and its Task Group on Severe Accident Phenomena in Containment (SAC): - What had been learnt from recent International Standard Problem (ISP) exercises on containment thermal-hydraulics and hydrogen distribution? - What could be concluded about the codes' abilities to predict the containment thermal behaviour from ISPs and from other related tests for plant application? - How should remaining uncertainties be best handled? - What more needs to be done, if anything? Consequently, the main objectives of this SOAR are: 1. to assess the current capabilities to make relevant predictions for the plant assessment of

DORT-TD/THERMIX solutions for the OECD/NEA/NSC PBMR400 MW coupled neutronics thermal hydraulics transient benchmark

International Nuclear Information System (INIS)

Tyobeka, Bismark; Pautz, Andreas; Ivanov, Kostadin

2008-01-01

In new reactor designs that are still under review such as the PBMR, not much experimental data exists to benchmark newly developed computer codes against. Such a situation requires that nuclear engineers and designers of this novel reactor design must resort to the validation of a newly developed code through a code-to-code benchmarking exercise because there are validated codes that are currently in use to analyze this reactor design, albeit very few of them. There are numerous HTR core physics benchmarks that are currently being pursued by different organizations, for different purposes. One such benchmark exercise is the PBMR-400 MW OECD/NEA/NSC coupled neutronics/thermal hydraulics transient benchmark. In this paper, a newly developed coupled neutronics thermal hydraulics code system, DORT-TD/THERMIX with both transport and diffusion theory options, is used to simulate the transient scenarios in the above-mentioned benchmark problem. Steady-state calculations results are compared with selected participants' results as well as transient models in which the diffusion and transport theory solutions of the same code system are directly compared. Several sensitivity studies are also shown in order to determine how much the change in certain parameters influences the overall behaviour of a given transient. It is shown in this paper that DORT-TD/THERMIX is a versatile tool which can be deployed for design and safety analyses of high temperature reactors of pebble-bed type. (authors)

Use and development of probabilistic safety assessment - CSNI WGRISK

International Nuclear Information System (INIS)

Siu, Nathan; Monninger, John; Gomez-Cobo, Ana; Kao, Tsu-Mu; Schoen, Gerhard; Gunsell, Lars; Nyman, Ralph; Jelinek, Tomas; Hultquist, Goeran; Rapp, Anders; Eriksson, Stefan; Lantaron, Alfredo; Vojnovic, Djordje; Husarcek, Jan; Kovacs, Zoltan; Versteeg, M.F.; Lopez Morones, Ramon; Lee, Chang-Ju; Fukuda, Mamoru; Burgazzi, Luciano; Caporali, Rino; RoeWEKAMP, Marina; MACSUGA, Geza; Bareith, Attila; Lanore, J.M.; Sorel, Vincent; Virolainen, Reino; Patrik, Milan; Mlady, Ondrej; Raducu, Gheorghe; De Gelder, Pieter; Hendrickx, Isabelle; Lanore, Jeanne-Marie; Murphy, Joseph A.; Shepherd, Charles; Pyy, Pekka T.; Mauny, Elisabeth

2007-01-01

The CSNI WGRISK produced a report in July 2002 on 'The Use and Development of Probabilistic Safety Assessment in NEA Member Countries'. This provides a description of the PSA programmes in the member countries at the time that the report was produced. However, there have been significant developments in PSA since 2002. Consequently, a decision was made at the WGRISK meeting in October 2005 to produce an updated version of the report. The aim was to produce an updated, stand alone version of the report that presents an analysis of the position on the use and development of PSA in the WGRISK member countries as of spring 2006. A detailed questionnaire was circulated to WGRISK members and to the IAEA to ascertain the state of the art in PSA use and development at the end of 2006. Detailed responses were prepared by 20 countries totalling several hundred pages of information. After first compilation of information, an updating round was organized by showing to the countries all the answers and the summary made of them by a small group of experts. The process led to some clarifications and more consistency in the report. The collected information was finally analyzed and summarized to reach the conclusions presented in this report. The set of section headings in the report is as follows: Executive summary. 1. Introduction. 2. PSA Framework and Environment. 3. Numerical Safety Criteria. 4. PSA Standards and Guidance. 5. Status and Scope of PSA Programmes. 6. PSA Methodology and Data. 7. PSA Applications. 8. Results and Insights from the PSAs. 9. Future Developments. Appendix A: Overview of the Status of PSA Programmes. Appendix B: Contact information. Appendix C: Questionnaire and Guidance to authors

Korea-France collaboration for the preparation of joint proposal for the OECD project on the steam explosion experiments

International Nuclear Information System (INIS)

Song, Jin Ho; Kim, H. D.; Kim, J. H.; Hong, S. W.; Min, B. T.; Park, I. K.

2004-07-01

There are some difficulties in design of the new reactor containment and in establishment of accident management strategy for operating reactors, since there exist a few phenomenological uncertainties in a steam explosion which occurs at the time of the interaction between the corium melt and coolant. So, the OECD/NEA recommended a research which could finalize the unsolved issues in a steam explosion and then an international collaborative research involving US, France, Germany, Japan and Korea, so called the SERENA (Steam Explosion Resolution for Nuclear Application) started in 2002. The first phase of this collaborative research is an analytical research and the second phase is planned to be an experimental research which will start in 2005. Korea and France agreed that both countries would cooperate in the second phase of the SERENA program at the specialist meetings and collaborative committee between the KAERI (Korea Atomic Energy Research Institute) and the CEA (Commissariat a l'Energie Atomique). This preparation research is performed in order to carry out the agreement between Korea and France and propose a collaborative research to the SERENA second phase. The contents of this research is to perform a collaborative research between Korea and France to propose an international collaborative research on a steam explosion research to the OECD. The scope includes the technical exchange for the construction of an international collaborative research and the preparation of a proposal for an international collaborative research for the OECD steam explosion program. Two steam explosion specialist meetings were held to discuss the technical issues in the TROI and KROTOS experiments. A formal accession and amendment agreement for the collaboration was contracted between the KAERI/KINS/CEA/IRSN. And the KAERI's capability to perform an international collaborative research was proved by advertizing the TROI test results to the USNRC/CSARP and JAERI. Also, the English

Human machine interaction research experience and perspectives as seen from the OECD Halden Reactor Project

International Nuclear Information System (INIS)

Oewre, F.

1999-01-01

In this paper a short review is given on important safety issues in the field of human machine interaction as expressed by important nuclear organisations such as USNRC, IAEA and the OECD NEA. Further on, a presentation is offered of research activities at the OECD Halden Reactor Project in the field of human machine interaction aiming to clarify some of the issues outlined by the above mentioned organisations. The OECD Halden Reactor Project is a joint undertaking of national nuclear organisations in 19 countries sponsoring a jointly financed research programme under the auspices of the OECD - Nuclear Energy Agency. One of the research areas is the man-machine systems research addressing the operator tasks in a control room environment. The overall objective is to provide a basis for improving today's control rooms through introduction of computer-based solutions for effective and safe execution of surveillance and control functions in normal as well as off-normal plant situations. (author)

NEA activities in 1992. 21. Annual report of the OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

1993-01-01

This annual report gives informations on OECD Nuclear Energy Agency activities in 1992. This report is divided into ten chapters: 1 Trends in nuclear power. 2 Nuclear development and the fuel cycle. 3 Reactor safety and regulation. 4 Radiation protection. 5 Radioactive waste management. 6 Nuclear science. 7 Joint projects. 8 Legal affairs. 9 Informations programs. 10 Relations with non-member countries

BWR stability analysis: methodology of the stability analysis and results of PSI for the NEA/NCR benchmark task; SWR Stabilitaetsanalyse: Methodik der Stabilitaetsanalyse und PSI-Ergebnisse zur NEA/NCR Benchmarkaufgabe

Energy Technology Data Exchange (ETDEWEB)

Hennig, D.; Nechvatal, L. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

1996-09-01

The report describes the PSI stability analysis methodology and the validation of this methodology based on the international OECD/NEA BWR stability benchmark task. In the frame of this work, the stability properties of some operation points of the NPP Ringhals 1 have been analysed and compared with the experimental results. (author) figs., tabs., 45 refs.

OECD-IAEA Paks Fuel Project. Final Report

International Nuclear Information System (INIS)

2010-05-01

It is important for nuclear power plant designers, operators and regulators to effectively use lessons learned from events occurring at nuclear power plants since, in general, it is impossible to reproduce the event using experimental facilities. In particular, evaluation of the event using accident analysis codes is expected to contribute to improving understanding of phenomena during the events and to facilitate the validation of computer codes through simulation analyses. The information presented in this publication will be of use in future revisions of safety guides on accident analysis. During a fuel crud removal operation on the Paks-2 unit of the Paks nuclear power plant, Hungary on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a special tank under deep water in a service pit connected to the spent fuel storage pool. The first sign of fuel failures was the detection of some fission gases released from the cleaning tank. Later, visual inspection revealed that most of the 30 fuel assemblies suffered heavy oxidation and fragmentation. The first evaluation of the event showed that the severe fuel damage had been caused by inadequate cooling. The Paks-2 event was discussed in various committees of the OECD Nuclear Energy Agency (OECD/NEA) and of the International Atomic Energy Agency (IAEA). Recommendations were made to undertake actions to improve the understanding of the incident sequence and of the consequence this had on the fuel. It was considered that the Paks-2 event may constitute a useful case for a comparative exercise on safety codes, in particular for models devised to predict fuel damage and potential releases under abnormal cooling conditions and the analyses of the Paks-2 event may provide information which is relevant for in-reactor and spent fuel storage safety evaluations. The OECD-IAEA Paks Fuel Project was established in 2005 as a joint project between the IAEA and the OECD/NEA. The IAEA

Fuel safety criteria technical review - Results of OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria

International Nuclear Information System (INIS)

Hollasky, N.; Valtonen, K.; Hache, G.; Gross, H.; Bakker, K.; Recio, M.; Bart, G.; Zimmermann, M.; Van Doesburg, W.; Killeen, J.; Meyer, R.O.; Speis, T.

2000-01-01

With the advent of advanced fuel and core designs, the adoption of more aggressive operational modes and the implementation of more accurate (best estimate or statistical) design and analysis methods, there is a concern if safety margins have remained adequate. Most - if not all - of the currently existing safety criteria were established during the 60's and early 70's, and verified against experiments with fuel that was available at that time, mostly with unirradiated specimens. Verification was of course performed as designs progressed in later years, however mostly with the aim to be able to prove that these designs adequately complied with existing criteria, and not to establish new limits. The OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria (TFFSC) was therefore given the mandate to technically review the existing fuel safety criteria, focusing on the 'new design' elements (new fuel and core design, cladding materials, manufacturing processes, high burnup, MOX, etc.) introduced by the industry. It should also identify if additional efforts may be required (experimental, analytical) to ensure that the basis for fuel safety criteria is adequate to address the relevant safety issues. In this report, fuel-related criteria are discussed without attempting to categorize them according to event type or risk significance. For each of these 20 criteria, we present a brief description of the criterion as it is used in several applications along with the rationale for having such a criterion. New design elements, such as different cladding materials, higher burnup, and the use of MOX fuels, can affect fuel-related margins and, in some cases, the criteria themselves. Some of the more important effects are mentioned in order to indicate whether the criteria need to be re-evaluated. The discussion may not cover all possible effects, but should be sufficient to identify those criteria that need to be addressed. A summary of these discussions is given in Section 7. As part

NEA Annual Report 2011

International Nuclear Information System (INIS)

2012-01-01

The Nuclear Energy Agency (NEA) is a semi-autonomous body within the Organisation for Economic Co-operation and Development (OECD), located in the Paris area in France. The objective of the Agency is to assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes. 2011 was a pivotal year for the NEA and its member countries. The 11 March Tohoku earthquake and tsunami were at the origin of the Fukushima Daiichi nuclear power plant accident, with the earthquake having resulted in the loss of offsite power and the tsunami in the loss of onsite emergency power necessary to keep the cooling systems functioning. While the accident itself was not responsible for any casualties, it has affected the lives of thousands of displaced Japanese citizens and caused considerable environmental damage in the surrounding area. At the NEA, monitoring of the accident began immediately as well as working with all members to fully ascertain the technical and regulatory lessons that could be learnt. In that context, on 7-8 June 2011, the NEA hosted in co-operation with the French Presidency of the G8, a ministerial seminar on nuclear safety and a regulatory forum to discuss insights and approaches. The insights gained during the forum have strongly influenced the work of the NEA and also provided valuable input to the IAEA ministerial conference and subsequent action plan. At present, the three NEA standing technical committees most involved in Fukushima follow-up work are the Committee on Nuclear Regulatory Activities, the Committee on Radiation Protection and Public Health, and the Committee on the Safety of Nuclear Installations. A number of activities are underway in the areas of nuclear regulation, nuclear safety and research, crisis communication, radiological protection, decontamination and

The programme of OECD-Nuclear Energy Agency Committee on the safety of nuclear installations principal working group no. 3 on reactor component integrity

International Nuclear Information System (INIS)

Schulz, H.; Miller, A.

1995-01-01

The programme of the OECD-NEA Principal Working Group No.3 on reactor component integrity is described including the following issues: regular Committee meetings; non-destructive testing; fracture analysis; aging; related activities

Uncertainty and sensitivity analysis in reactivity-initiated accident fuel modeling: synthesis of organisation for economic co-operation and development (OECD/nuclear energy agency (NEA benchmark on reactivity-initiated accident codes phase-II

Directory of Open Access Journals (Sweden)

Olivier Marchand

2018-03-01

Full Text Available In the framework of OECD/NEA Working Group on Fuel Safety, a RIA fuel-rod-code Benchmark Phase I was organized in 2010–2013. It consisted of four experiments on highly irradiated fuel rodlets tested under different experimental conditions. This benchmark revealed the need to better understand the basic models incorporated in each code for realistic simulation of the complicated integral RIA tests with high burnup fuel rods. A second phase of the benchmark (Phase II was thus launched early in 2014, which has been organized in two complementary activities: (1 comparison of the results of different simulations on simplified cases in order to provide additional bases for understanding the differences in modelling of the concerned phenomena; (2 assessment of the uncertainty of the results. The present paper provides a summary and conclusions of the second activity of the Benchmark Phase II, which is based on the input uncertainty propagation methodology. The main conclusion is that uncertainties cannot fully explain the difference between the code predictions. Finally, based on the RIA benchmark Phase-I and Phase-II conclusions, some recommendations are made. Keywords: RIA, Codes Benchmarking, Fuel Modelling, OECD

Evaluated Data Projects at the NEA

International Nuclear Information System (INIS)

Henriksson, H.; Rugama, Y.

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. The NEA offers easy access to the main nuclear databases with bibliographical information, evaluated libraries, e.g. the Joint Evaluated Fission and Fusion (JEFF) library, and experimental data in the EXFOR database, comprising published neutron induced as well as charged particle induced nuclear reaction data. 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 six major evaluation projects (BROND, CENDL, Endf, FENDL, JEFF and JENDL). The NEA Data Bank administrates the collection and validation as well as the distribution of the JEFF library. The latest version, JEFF-3.1, was released in May 2005 and it contains a neutron data library, a proton data library and thermal scattering law data. The special purpose library on activation data contains 774 nuclei with over 12600 neutron induced reactions. Included is also radioactive decay data, with 3852 isotopes, and spontaneous and neutron induced fission yield data. The full documentation of the library is being prepared for publication in 2006. Processed JEFF-3.1 data files in ACE format, mainly for reactor physics applications, have been prepared and were distributed in spring 2006 with documentation. The processed files have been validated for criticality calculations, as well as for radiation physics application. The detailed analysis of the validation results will be very useful for improving the accuracy of evaluated data libraries. The display program JANIS has been developed at the NEA, and the latest version (JANIS-2.21) was released in October 2005. JANIS is designed to facilitate the visualisation and

Summary of the 1st specialist meeting on simulators and plant analyzers held in Lappeenranta

International Nuclear Information System (INIS)

Miettinen, J.

1999-01-01

The first CSNI specialist meeting on simulators and plant analyzers was an attempt to find a new perspective to simulation of the nuclear power plant processes at a time when analytical calculation and operator training were quite much diversified. The speed of computers was limited for real time physical simulation but quite impressive computer graphics and simulator development tools had been developed. Systematic methodologies for simulator validation were under development. The human reliability was under study. This paper first describes the content and conclusions of the meeting. After that the visions presented in the meeting are compared to the development during past years. (author)

Re-analysis of CSNI standard problem, 8

International Nuclear Information System (INIS)

Sasaki, Shinobu; Araya, Fumimasa

1981-12-01

This report presents the results of computer runs which carried out with the use of ALARM-Pl code. The object of analyses is the Semiscale S-06-3 experiment accepted as the CSNI International Standard Problem 8. According to the preliminary results reported before, the agreement between ALARM-Pl and this experiment was very poor for the key parameters such as the break flow or fuel cladding surface temperature. Hence, much effort has been made to improve the disagreement. Through the re-examination of both the code and input-data, the agreement between the calculated and measured results for key parameters has been much better than that gained in the foregoing test run. (author)

CSNI/NEA RASPLAV Seminar 2000, 14-15 November 2000, Munich, Germany - Executive Summary

International Nuclear Information System (INIS)

Asmolov, V.; Behbahani, A.; Hache, G.; Nakamura, H.; Raj Sehgal, B.; Strizhov, V.; Trambauer, K.; Tuomisto, H.; Vitanza, C.

2000-11-01

various boundary conditions were investigated. The work involved a combination of integral and separate effect tests including molten-salt tests to investigate non-eutectic mixtures and the effects of stratification, extension of the material property database to allow interpretation and modelling of the experimental data. The CSNI decided to hold a seminar where the major outcome of the RASPLAV Project could be presented and discussed also in the context of other experienced activities on Severe Accidents. The objectives of the seminar are: - to review the experimental results of the RASPLAV Project; - to exchange information on complementary research; - to discuss the progress made on understanding severe accident progression; - to discuss the applicability to nuclear power plants and use of the results. The Seminar was intended to provide an in-depth review of the RASPLAV Project in terms of the technical capabilities, results and analyses produced during the project execution. The application of the results and their significance for power plant applications were addressed. Relevant results of the complementary research carried out at various laboratories were also presented. The seminar consisted of five sessions. The abstracts of the presentations are given in the appendix, as well as the list of participants and the conference program

Spanish collaboration in the OECD Halden Reactor Project research on Gadolinia Fuel

International Nuclear Information System (INIS)

Horvath, M. I.; Jenssen, H. K.; Munoz-Reja, C.; Tverberg, T.

2011-01-01

Safe and reliable operation of nuclear power plants benefit from research and development advances and related technical solutions. One research platform is the OECD Halden Reactor Project (HRP), HRP is a joint undertaking of national organisations in 18 countries sponsoring a jointly financed programme under the auspices of the OECD-Nuclear Energy Agency (NEA). As a member state, Spain is participating HRP research programs with ENUSA as partner in the fuel research programs. Various experiments are developed and performed also by providing materials, ENUSA collaborates with HRP on various experiments investigating the fuel behaviour, especially on Gd-bearing fuel. 20 years of successful collaboration between HRP and ENUSA is continuing with promising and results to ensure and enhance the safe operation of the Spanish and all other NPPs in the world. (Author) 12 refs.

New Multi-group Transport Neutronics (PHISICS) Capabilities for RELAP5-3D and its Application to Phase I of the OECD/NEA MHTGR-350 MW Benchmark

Energy Technology Data Exchange (ETDEWEB)

Gerhard Strydom; Cristian Rabiti; Andrea Alfonsi

2012-10-01

PHISICS is a neutronics code system currently under development at the Idaho National Laboratory (INL). Its goal is to provide state of the art simulation capability to reactor designers. The different modules for PHISICS currently under development are a nodal and semi-structured transport core solver (INSTANT), a depletion module (MRTAU) and a cross section interpolation (MIXER) module. The INSTANT module is the most developed of the mentioned above. Basic functionalities are ready to use, but the code is still in continuous development to extend its capabilities. This paper reports on the effort of coupling the nodal kinetics code package PHISICS (INSTANT/MRTAU/MIXER) to the thermal hydraulics system code RELAP5-3D, to enable full core and system modeling. This will enable the possibility to model coupled (thermal-hydraulics and neutronics) problems with more options for 3D neutron kinetics, compared to the existing diffusion theory neutron kinetics module in RELAP5-3D (NESTLE). In the second part of the paper, an overview of the OECD/NEA MHTGR-350 MW benchmark is given. This benchmark has been approved by the OECD, and is based on the General Atomics 350 MW Modular High Temperature Gas Reactor (MHTGR) design. The benchmark includes coupled neutronics thermal hydraulics exercises that require more capabilities than RELAP5-3D with NESTLE offers. Therefore, the MHTGR benchmark makes extensive use of the new PHISICS/RELAP5-3D coupling capabilities. The paper presents the preliminary results of the three steady state exercises specified in Phase I of the benchmark using PHISICS/RELAP5-3D.

NEA activities in 1996. Twenty-fifth annual report of the OECD Nuclear Energy Agency

International Nuclear Information System (INIS)

1997-01-01

The activity of NEA in 1996 is briefly summarised. The following issues are concerned: trends in nuclear power, nuclear development, reactor safety and regulations, radiation protection, waste management, nuclear science, legal affairs, co-operative projects, relation with non-member countries. (K.A.) (K.A.)

Thermal-hydraulic analysis of the Three Mile Island Unit 2 reactor accident with THALES code

International Nuclear Information System (INIS)

Hashimoto, Kazuichiro; Soda, Kunihisa

1991-10-01

The OECD Nuclear Energy Agency (NEA) has established a Task Group in the Committee on the Safety of Nuclear Installations (CSNI) to perform an analysis of Three Mile Island Unit 2 (TMI-2) accident as a standard problem to benchmark severe accident computer codes and to assess the capability of the codes. The TMI-2 Analysis Exercise was performed at the Japan Atomic Energy Research Institute (JAERI) using the THALES (Thermal-Hydraulic Analysis of Loss-of-Coolant, Emergency Core Cooling and Severe Core Damage) - PM1/TMI code. The purpose of the analysis is to verify the capability of THALES-PM1/TMI code to describe accident progression in the actual plant. The present paper describes the final result of the TMI-2 Analysis Exercise performed at JAERI. (author)

Classifying and quantifying human error in routine tasks in nuclear power plants

International Nuclear Information System (INIS)

Pederson, O.M.; Rasmussen, J.; Carnino, A.; Gagnolet, P.; Griffon, M.; Mancini, G.

1982-01-01

This paper results from the work of the OECD/NEA-CSNI Group of Experts on Human Error Data and Assessment. It proposes a classification system (or taxonomy) for use in reporting events involving human malfunction, especially those occurring during the execution of routine tasks. A set of data collection sheets based on this taxonomy has been designed. They include the information needed in order to ensure adequate quality and coherence of the raw data. The sources from which the various data should be obtainable are identified, as are the persons who should analyze them. Improving data collection systems is an iterative process. Therefore Group members are currently making trial applications of the taxonomy to previously analysed real incidents. Results from the initial round of trials are presented and discussed

Manual for IRS Coding. Joint IAEA/NEA International Reporting System for Operating Experience

International Nuclear Information System (INIS)

2011-01-01

The International Reporting System for Operating Experience (IRS) is jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). In early 2010, the IAEA and OECD/NEA jointly issued the IRS Guidelines, which described the reporting system and process and gave users the necessary elements to enable them to produce IRS reports to a high standard of quality while retaining the effectiveness of the system expected by all Member States operating nuclear power plants. The purpose of the present Manual for IRS Coding is to provide supplementary guidance specifically on the coding element of IRS reports to ensure uniform coding of events that are reported through IRS. This Coding Manual does not supersede the IRS Guidelines, but rather, supports users and preparers in achieving a consistent and high level of quality in their IRS reports. Consistency and high quality in the IRS reports allow stakeholders to search and retrieve specific event information with ease. In addition, well-structured reports also enhance the efficient management of the IRS database. This Coding Manual will give specific guidance on the application of each section of the IRS codes, with examples where necessary, of when and how these codes are to be applied. As this reporting system is owned by the Member States, this manual has been developed and approved by the IRS National Coordinators with the assistance of the IAEA and NEA secretariats

Progress report on the management of the NEA ISOE system

Energy Technology Data Exchange (ETDEWEB)

Lazo, E. [OECD Nuclear Energy Agency, Issy-les-Moulineaux (France)

1995-03-01

The Information System on Occupational Exposure (ISOE) was launched by the Organization for Economic Cooperation and Development (OECD), Nuclear Energy Agency (NEA) on 1 January, 1992, to facilitate the communication of dosimetric and ALARA implementation data among nuclear utilities around the world. After two years of operation the System has become a mature interactive network for transfer of data and experience. Currently, 37 utilities from 12 countries, representing 289 power plants, and 12 national regulatory authorities participate in ISOE. Agreements for cooperation also exist between the NEA and the Commission of the European Communities (CEC), and the Paris Center of the WOrld Association of Nuclear Operators (WANO-PC). In addition, the International Atomic Energy Agency (IAEA) is acting as a co-sponsor of ISOE for the participation of non-NEA member countries. Three Regional Technical Centres, Europe, Asia, and Non-NEA member countries, serve to administer the system. The ISOE Network is comprised of three data bases and a communications network at several levels. The three ISOE data bases include the following types of information: NEA1 - annual plant dosimetric information; NEA2 - plant operational characteristics for dose and dose rate reduction; and NEA3 - job specific ALARA practices and experiences. The ISOE communications network has matured greatly during 1992 and 1993. In addition to having access to the above mentioned data bases, participants may now solicit information on new subjects, through the Technical Centres, from all other participants on a real-time basis. Information Sheets on these studies are produced for distribution to all participants. In addition, Topical Reports on areas of interest are produced, and Topical Meetings are held annually.

Progress report on the management of the NEA ISOE system

International Nuclear Information System (INIS)

Lazo, E.

1995-01-01

The Information System on Occupational Exposure (ISOE) was launched by the Organization for Economic Cooperation and Development (OECD), Nuclear Energy Agency (NEA) on 1 January, 1992, to facilitate the communication of dosimetric and ALARA implementation data among nuclear utilities around the world. After two years of operation the System has become a mature interactive network for transfer of data and experience. Currently, 37 utilities from 12 countries, representing 289 power plants, and 12 national regulatory authorities participate in ISOE. Agreements for cooperation also exist between the NEA and the Commission of the European Communities (CEC), and the Paris Center of the WOrld Association of Nuclear Operators (WANO-PC). In addition, the International Atomic Energy Agency (IAEA) is acting as a co-sponsor of ISOE for the participation of non-NEA member countries. Three Regional Technical Centres, Europe, Asia, and Non-NEA member countries, serve to administer the system. The ISOE Network is comprised of three data bases and a communications network at several levels. The three ISOE data bases include the following types of information: NEA1 - annual plant dosimetric information; NEA2 - plant operational characteristics for dose and dose rate reduction; and NEA3 - job specific ALARA practices and experiences. The ISOE communications network has matured greatly during 1992 and 1993. In addition to having access to the above mentioned data bases, participants may now solicit information on new subjects, through the Technical Centres, from all other participants on a real-time basis. Information Sheets on these studies are produced for distribution to all participants. In addition, Topical Reports on areas of interest are produced, and Topical Meetings are held annually

Anomaly detection in OECD Benchmark data using co-variance methods

International Nuclear Information System (INIS)

Srinivasan, G.S.; Krinizs, K.; Por, G.

1993-02-01

OECD Benchmark data distributed for the SMORN VI Specialists Meeting in Reactor Noise were investigated for anomaly detection in artificially generated reactor noise benchmark analysis. It was observed that statistical features extracted from covariance matrix of frequency components are very sensitive in terms of the anomaly detection level. It is possible to create well defined alarm levels. (R.P.) 5 refs.; 23 figs.; 1 tab

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.

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

Research and Activities of OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF) Project

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung Il; Ha, Kwang Soon; Song, JinHo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

The severe accident codes were used to analysis the Fukushima Daiichi accident and give valuable information. In addition, the insufficient part of the code could be revised by comparing the calculation result with the measured data. In this circumstance, working plans have been set up to conduct a Benchmark Study of the Accident progression for the Fukushima Daiichi nuclear power plant(BSAF) units 1-3 with the members of the OECD/NEA. The BSAF project was launched in November 2012 with the fifteen organizations of eight countries (France, Germany, Korea, Russia, Spain, Switzerland, the United States, and Japan). The objectives of the project are: - to analyze the Fukushima accident progression. - to raise the understanding of severe accident(SA) phenomena. - to contribute the improvement of methods and models of SA code. - to contribute the status of debris distribution to a future debris removal plan. BSAF phase 2 also has been implemented from April, 2015 and it will be continued to March, 2018. It is more focused on the fission product behavior and source term estimation in phase 2. The phase 2 project implementation period is 3 years from April 2015 to March 2018. The main topic of the BSAF 2 is the fission product behavior in the Fukushima nuclear power plant. In the process of calculation, it is important to know the insufficient models in the code. Furthermore, the model would be applied to the KAERI's severe accident code after making up for the insufficient part.

Nuclear power plant operating experiences from the IAEA / Nea incident reporting system 2002-2005

International Nuclear Information System (INIS)

2006-01-01

The Incident Reporting System (IRS) is an essential element of the international operating experience feedback system for nuclear power plants. The IRS is jointly operated and managed by the Nuclear Energy Agency (NEA), a semi-autonomous body within the Organisation for Economic Co-operation and Development (OECD), and the International Atomic Energy Agency (IAEA), a specialized agency within the United Nations System. (author)

OECD Nuclear Energy Agency Activities Related to Fast Reactor Development

International Nuclear Information System (INIS)

Dujardin, Thierry; Gulliford, Jim

2013-01-01

• Despite impact of Fukushima, there remains a high level of interest in continued development of advanced nuclear systems and fuel cycles: – better use of natural resources; – minimisation of waste and reduction of constraints on deep geological repositories. • Ambitious R&D programmes on-going at national level in many countries, also through international projects: – expected to lead to development of advanced reactors and fuel cycle facilities. • OECD/NEA will continue to support member countries in field of fast reactor development and related advanced fuel cycles: – forum for exchange of information; – collaborative activities

Classification of criticality calculations with correlation coefficient method and its application to OECD/NEA burnup credit benchmarks phase III-A and II-A

International Nuclear Information System (INIS)

Okuno, Hiroshi

2003-01-01

A method for classifying benchmark results of criticality calculations according to similarity was proposed in this paper. After formulation of the method utilizing correlation coefficients, it was applied to burnup credit criticality benchmarks Phase III-A and II-A, which were conducted by the Expert Group on Burnup Credit Criticality Safety under auspices of the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development (OECD/NEA). Phase III-A benchmark was a series of criticality calculations for irradiated Boiling Water Reactor (BWR) fuel assemblies, whereas Phase II-A benchmark was a suite of criticality calculations for irradiated Pressurized Water Reactor (PWR) fuel pins. These benchmark problems and their results were summarized. The correlation coefficients were calculated and sets of benchmark calculation results were classified according to the criterion that the values of the correlation coefficients were no less than 0.15 for Phase III-A and 0.10 for Phase II-A benchmarks. When a couple of benchmark calculation results belonged to the same group, one calculation result was found predictable from the other. An example was shown for each of the Benchmarks. While the evaluated nuclear data seemed the main factor for the classification, further investigations were required for finding other factors. (author)

Accomplishing the objectives of NEA in radioactive waste management

International Nuclear Information System (INIS)

Olivier, J.P.; Stadie, K.B.

1984-01-01

The objectives of the Nuclear Energy Agency of the OECD in the area of radioactive waste management are to promote studies and improve the data available to support national programmes, to co-ordinate national activities, to promote international projects, and to improve the general level of understanding of waste management issues. The NEA programme concentrates on the disposal of waste and responds to objectives at three levels: sharing of information and organization of joint analytical studies through expert meetings, preparation of technical reports and analysis and dissemination of data; establishment of joint research and development projects designed to support national programmes; and discussion of current issues and strategies, particularly through the Radioactive Waste Management Committee acting as a specialized internatonal forum. The paper discusses, through various specific examples, how the objectives are met. In addition, the paper describes current NEA activities which have not been reported in other papers during the Conference. (author)

Contribution of the Nea data bank in the field of calculation codes in radiation protection, radio physics and dosimetry

International Nuclear Information System (INIS)

Kodeli, I.; Sartori, E.

2003-01-01

The Nuclear energy agency is a specialised agency of OECD (organization economic co-operation and development). These missions are to help its members to keep and improve by international cooperation, the scientific, technological and legal bases necessary to a peaceful use of nuclear energy. Nea includes twenty eight countries. Nea works in collaboration with IAEA. The field of activities concerns the acquisition, validation and distribution of nuclear data, calculation codes and experiments. To help users, it organises conferences and training about the calculation codes that it shares out. (N.C.)

Safety considerations in design of fast spectrum ads for transuranic or minor actinide burning: a status report on activities of the OECD/Nea expert group

International Nuclear Information System (INIS)

Wade, D.C.

2001-01-01

The Nuclear Development Committee of the OECD/NEA convened an expert group for a 'Comparative Study of Accelerator Driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles'. The expert group has studied complexes (i.e. energy parks) of fission-based energy production and associated waste management facilities comprised of thermal and fast reactors, and ADS. With a goal to minimise transuranic (TRU) flows to the repository per unit of useful energy provided by the complex, the expert group has studied homogenous and heterogeneous recycle of TRU and minor actinides (MA) in the facilities of the complex using aqueous or dry recycle in single and double strata architectures. In the complexes considered by the expert group the ADS is always assigned a TRU or MA (and sometimes a LLFP) incineration mission - with useful energy production only as a secondary ADS goal to partially offset the cost of its construction and operation. Ancillary issues have also been considered - including ADS safety challenges and strategies for resolving them. This paper reports on the status of the expert group's considerations of ADS safety strategy. (author)

Operating Experience Insights into Pipe Failures for Electro-Hydraulic Control and Instrument Air Systems in Nuclear Power Plant. A Topical Report from the Component Operational Experience, Degradation and Ageing Programme

International Nuclear Information System (INIS)

2015-01-01

Structural integrity of piping systems is important for plant safety and operability. In recognition of this, information on degradation and failure of piping components and systems is collected and evaluated by regulatory agencies, international organisations (e.g. OECD/NEA and IAEA) and industry organisations worldwide to provide systematic feedback for example to reactor regulation and research and development programmes associated with non-destructive examination (NDE) technology, in-service inspection (ISI) programmes, leak-before-break evaluations, risk-informed ISI, and probabilistic safety assessment (PSA) applications involving passive component reliability. Several OECD member countries have agreed to establish the OECD/NEA 'Component Operational Experience, Degradation and Ageing Programme' (CODAP) to encourage multilateral co-operation in the collection and analysis of data relating to degradation and failure of metallic piping and non-piping metallic passive components in commercial nuclear power plants. The scope of the data collection includes service-induced wall thinning, part through-wall cracks, through-wall cracks with and without active leakage, and instances of significant degradation of metallic passive components, including piping pressure boundary integrity. The OECD/NEA Committee on the Safety of Nuclear Installations (CSNI) acts as an umbrella committee of the Project. CODAP is the continuation of the 2002-2011 'OECD/NEA Pipe Failure Data Exchange Project' (OPDE) and the Stress Corrosion Cracking Working Group of the 2006-2010 'OECD/NEA Stress Corrosion Cracking and Cable Ageing Project' (SCAP). OPDE was formally launched in May 2002. Upon completion of the third term (May 2011), the OPDE project was officially closed to be succeeded by CODAP. SCAP was enabled by a voluntary contribution from Japan. It was formally launched in June 2006 and officially closed with an international workshop held in Tokyo in May

Status Report on Activities of the Systems Assessment Task Force, OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs

Energy Technology Data Exchange (ETDEWEB)

Bragg-Sitton, Shannon Michelle [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-09-01

The Organization for Economic Cooperation and Development /Nuclear Energy Agency (OECD/NEA) Nuclear Science Committee approved the formation of an Expert Group on Accident Tolerant Fuel (ATF) for LWRs (EGATFL) in 2014. Chaired by Kemal Pasamehmetoglu, INL Associate Laboratory Director for Nuclear Science and Technology, the mandate for the EGATFL defines work under three task forces: (1) Systems Assessment, (2) Cladding and Core Materials, and (3) Fuel Concepts. Scope for the Systems Assessment task force includes definition of evaluation metrics for ATF, technology readiness level definition, definition of illustrative scenarios for ATF evaluation, parametric studies, and selection of system codes. The Cladding and Core Materials and Fuel Concepts task forces will identify gaps and needs for modeling and experimental demonstration; define key properties of interest; identify the data necessary to perform concept evaluation under normal conditions and illustrative scenarios; identify available infrastructure (internationally) to support experimental needs; and make recommendations on priorities. Where possible, considering proprietary and other export restrictions (e.g., International Traffic in Arms Regulations), the Expert Group will facilitate the sharing of data and lessons learned across the international group membership. The Systems Assessment Task Force is chaired by Shannon Bragg-Sitton (INL), while the Cladding Task Force will be chaired by a representative from France (Marie Moatti, Electricite de France [EdF]) and the Fuels Task Force will be chaired by a representative from Japan (Masaki Kurata, Japan Atomic Energy Agency [JAEA]). This report provides an overview of the Systems Assessment Task Force charter and status of work accomplishment.

Verification of NUREC Code Transient Calculation Capability Using OECD NEA/US NRC PWR MOX/UO2 Core Transient Benchmark Problem

International Nuclear Information System (INIS)

Joo, Hyung Kook; Noh, Jae Man; Lee, Hyung Chul; Yoo, Jae Woon

2006-01-01

In this report, we verified the NUREC code transient calculation capability using OECD NEA/US NRC PWR MOX/UO2 Core Transient Benchmark Problem. The benchmark problem consists of Part 1, a 2-D problem with given T/H conditions, Part 2, a 3-D problem at HFP condition, Part 3, a 3-D problem at HZP condition, and Part 4, a transient state initiated by a control rod ejection at HZP condition in Part 3. In Part 1, the results of NUREC code agreed well with the reference solution obtained from DeCART calculation except for the pin power distributions at the rodded assemblies. In Part 2, the results of NUREC code agreed well with the reference DeCART solutions. In Part 3, some results of NUREC code such as critical boron concentration and core averaged delayed neutron fraction agreed well with the reference PARCS 2G solutions. But the error of the assembly power at the core center was quite large. The pin power errors of NUREC code at the rodded assemblies was much smaller the those of PARCS code. The axial power distribution also agreed well with the reference solution. In Part 4, the results of NUREC code agreed well with those of PARCS 2G code which was taken as the reference solution. From the above results we can conclude that the results of NUREC code for steady states and transient states of the MOX loaded LWR core agree well with those of the other codes

The NEA data bank - an international service centre for computer programs and nuclear data

International Nuclear Information System (INIS)

Nordborg, C.

2000-01-01

The Nuclear Energy Agency (NEA) is a specialized agency of the Organization for Economic Co-operation and Development (OECD) based in Paris. The most important purpose of NEA is the promotion of international cooperation in the peaceful uses of nuclear power. Within the Agency a special unit, the so-called Database, allows the 21 member countries to have direct access to nuclear data, chemical data, and computer codes. These countries are Austria, Belgium, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Italy, Japan, Korea, Mexico, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey, and the United Kingdom. Special agreements cover exchanges of data and codes with Canada, the United States of America, and IAEA. The NEA Database - maintains those databases which contain basic experimental and evaluated nuclear data, integral nuclear data, computer codes, and chemical thermodynamic data, - uses procedures of assured quality to store and maintain data and codes, - supplies as products internationally validated and licensed data and codes, - offers direct access to these products to scientists and engineers in national laboratories, universities, and in the nuclear industry. The services are available free of charge, and the databases can be accessed via the NEA web site (http://www.nea.fr). (orig.) [de

FLUENT calculations of the hydrogen distribution in a containment during the OECD-NEA THAI HM-2 experiment

International Nuclear Information System (INIS)

Visser, D.C.; Komen, E.M.J.; Houkema, M.; Siccama, N.B.; Kyttaelae, Juha; Huhtanen, Risto; Takasuo, Eveliina

2009-01-01

Hydrogen may be released into the containment atmosphere of a nuclear power plant during a severe accident. Locally, high hydrogen concentrations may be reached that can possibly cause fast deflagration or even detonation and put the integrity of the containment at risk. Therefore, the distribution and mixing of hydrogen is an important safety issue for nuclear power plants. Computer codes can be applied to predict the hydrogen distribution in the containment within the course of a hypothetical severe accident and get an estimate of the local hydrogen concentration in the various zones of the containment. In this way the risk associated with the hydrogen safety issue can be determined, and safety related measurements and procedures could be assessed. In order to validate the existing computer codes in the context of hydrogen distribution in the containment of a nuclear power plant, experimental benchmark studies have been performed in the German Thermal-hydraulics, Hydrogen, Aerosols and Iodine (THAI) facility in the framework of the OECD-NEA THAI project. In order to demonstrate the capabilities of the commercial Computational Fluid Dynamics (CFD) code FLUENT the THAI HM-2 test was simulated independently by NRG and VTT. In the first phase of the HM-2 test a stratified hydrogen rich light gas layer was established in the upper part of the THAI containment. In the second phase steam was injected at a lower position inducing a rising plume that gradually dissolved the stratified hydrogen-rich layer from below. Thermo-dynamic phenomena like natural convection, mixing, condensation, heat transfer and distribution in different zones that are expected in severe accidents are involved. The calculated results by NRG and VTT (on hydrogen concentration, temperature, pressure and flow velocity) are compared to the experimental results. The most important differences between the CFD model of NRG and VTT are the computational mesh, condensation model and treatment of the solid

Experimental Results of A1.2 Test for OECD-ATLAS Project

Energy Technology Data Exchange (ETDEWEB)

Kang, Kyoung-Ho; Bae, Byoung-Uhn; Park, Yu-Sun; Kim, Jong-Rok; Choi, Nam-Hyun; Choi, Ki-Yong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

In order to meet the international interests in the multiple high-risk design extension conditions (DECs) raised after the Fukushima accident, KAERI (Korea Atomic Energy Research Institute) is operating an OECD/NEA project (hereafter, OECD-ATLAS project) by utilizing a thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation). As for a prolonged SBO transient of the OECD-ATLAS project, two tests, named A1.1 and A1.2, were determined to be performed. In particular, passive safety systems are considered as the most promising alternatives to reinforce the safety and reliability of an ultimate heat removal system without any operator actions in the SBO transients. As one of the new safety improvement concepts to mitigate an SBO accident efficiently, a cooling and operational performance of the passive auxiliary feedwater system (PAFS) is investigated in the framework of the OECD-ATLAS project to produce clearer knowledge of the actual phenomena and to provide the best guidelines for accident management. As the second test of the OECD-ATLAS project, the A1.2 test was conducted to simulate a prolonged SBO with asymmetric secondary cooling through the supply of passive auxiliary feedwater only to SG-2. When the collapsed water level of steam generator reached a wide range of 25%, PAFS was actuated. PAFS played a key role in cooling down the primary system by the heat transfer and the natural circulation. With the actuation of PAFS, the fluid temperatures at the core inlet and outlet started to decrease without any excursion of the maximum heater surface temperature in the core. This integral effect test data of A1.2 test can be used to evaluate the prediction capability of existing safety analysis codes and identify any code deficiency for an SBO simulation with an operation of a passive system such as PAFS.

Development of infrastructure for the regulatory authority to implement risk-informed regulation

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

It is important to assure the technical adequacy of probabilistic risk assessment (PRA) to implement risk-informed regulation of nuclear power plants (NPPs). JNES has been conducting various activities, such as development of PRA model, method, and data base, in order to assure the technical adequacy of PRA as development of the infrastructure for the regulatory authority to implement risk-informed regulation. In 2012, JNES updated the reliability data base used in PRA and improved PRA models to enhance the technical bases of PRA. In addition, JNES has been establishing the PRA model for fuel damage in the spent fuel storage pool in NPPs. As for improvement of PRA model for core damage in reactor, JNES conducted the study including feasibility of a simplified reliability model for digital I and C system developed by the digital I and C task group of OECD/NEA CSNI WGRISK by reproducing the sample calculation, and improvement of PRA models of individual NPPs in Japan. JNES is making effort to develop the procedures of internal fire PRA and internal flooding PRA. To improve the internal fire PRA, JNES is participating in OECD/NEA FIRE project to obtain the latest information and to validate and improve the fire propagation analysis codes and the parameters. JNES is establishing a method for analyzing internal influence due to flooding in NPPs, and this method is the base to develop the procedure of internal flooding PRA. (author)

Proceedings of a NEA workshop on probabilistic structure integrity analysis and its relationship to deterministic analysis

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

This workshop was hosted jointly by the Swedish Nuclear Power Inspectorate (SKi) and the Swedish Royal Institute of Technology (KTH). It was sponsored by the Principal Working Group 3 (PWG-3) of the NEA CSNI. PWG-3 deals with the integrity of structures and components, and has three sub-groups, dealing with the integrity of metal components and structures, ageing of concrete structures, and the seismic behaviour of structures. The sub-group dealing with metal components has three mains areas of activity: non-destructive examination; fracture mechanics; and material degradation. The topic of this workshop is primarily probabilistic fracture mechanics, but probabilistic integrity analysis includes NDE and materials degradation also. Session 1 (5 papers) was devoted to the development of probabilistic models; Session 2 (5 papers) to the random modelling of defects and material properties; Session 3 (8 papers) to the applications of probabilistic modelling to nuclear components; Sessions 4 is a concluding panel discussion

Proceedings of a NEA workshop on probabilistic structure integrity analysis and its relationship to deterministic analysis

International Nuclear Information System (INIS)

1996-01-01

This workshop was hosted jointly by the Swedish Nuclear Power Inspectorate (SKi) and the Swedish Royal Institute of Technology (KTH). It was sponsored by the Principal Working Group 3 (PWG-3) of the NEA CSNI. PWG-3 deals with the integrity of structures and components, and has three sub-groups, dealing with the integrity of metal components and structures, ageing of concrete structures, and the seismic behaviour of structures. The sub-group dealing with metal components has three mains areas of activity: non-destructive examination; fracture mechanics; and material degradation. The topic of this workshop is primarily probabilistic fracture mechanics, but probabilistic integrity analysis includes NDE and materials degradation also. Session 1 (5 papers) was devoted to the development of probabilistic models; Session 2 (5 papers) to the random modelling of defects and material properties; Session 3 (8 papers) to the applications of probabilistic modelling to nuclear components; Sessions 4 is a concluding panel discussion

NEA and its Role in Enhancing the Implementation of Defence in Depth (DiD) in Light of the Fukushima Dai-ichi Accident

Energy Technology Data Exchange (ETDEWEB)

Shimomura, K., E-mail: Kazuo.SHIMOMURA@oecd.org [OECD Nuclear Energy Agency (NEA), Issy-Les-Moulineaux (France)

2014-10-15

Full text: This keynote speech will give an overview of NEA Activities to Enhance Global Nuclear Safety both those core to its work and those that have been initiated after the Fukushima Accident. In particular it will highlight the outcomes of the recently published “NEA report on the Fukushima Daiichi Nuclear Power Plant Accident”. The speech will specifically point out those lessons learnt related to Defence in Depth, and how those were fed into the NEA’s one day workshop on “Challenges and Enhancements to DiD in light of the Fukushima Dai-ichi Accident”, that took place on 5th June 2013. A workshop that brought together the member countries represented on the NEA’s three major standing committees for safety to not only discuss the lessons learnt from the accident but also what the NEA members considered could be done to enhance the understanding and implementation of defence in depth within nuclear safety. Members of these three standing committees, the Committee for Nuclear Regulatory Activities (CNRA), The Committee for Safety of Nuclear Installations (CSNI) and the Committee on Radiation Protection and Public Health (CRPPH) represent a considerable body of knowledge on the application of DiD within the countries using nuclear energy. The outcome of the workshop was the identification of a number of key tasks that NEA would take forward to assist in harmonising and enhancing globally the implementation of the DiD philosophy. The speech will in addition detail how the discussions ranged across the whole of the nuclear safety framework, what conclusions were derived and the process the NEA followed to incorporate those tasks within its future programme of work either by enhancing current activities or creating new ones. (author)

Proceedings of the third specialist meeting on sodium/fuel interaction in fast reactors

International Nuclear Information System (INIS)

1976-01-01

This specialist meeting, sponsored by the OECD-NEA and organized by the Power Reactor and Nuclear Fuel Development Corporation, was attended by 56 delegates from 6 countries and the CEC (Commission of the European Communities). The purpose of the meeting was to bring together and discuss in depth the Fuel-Sodium Interaction, a phenomenon of major importance in the assessment of the Hypothetical Core Disruptive Accident in the Liquid Metal Fast Breeder Reactor. The meeting was essentially a follow-up of an earlier meeting held at Ispra in December 1973. In all, 29 papers were presented, covering the following topics: 1. Current perspective on sodium-fuel interaction in LMFBR safety; 2. Basic experimental and theoretical studies including other materials; 3. In-pile and out-of-pile experimental studies on sodium-fuel interaction; 4. Theoretical models for the interpretation of experiments and for application to reactor situations. The meeting is considered useful in narrowing down the chain of events necessary to get energetic interaction, large work potential, but many points are being clarified on the gap between the basic vapor explosions and the real fuel sodium interactions in the HCDA scenario of LMFBR. Finally another meeting of the same nature as this one has been recommended

BWR stability analysis: methodology of the stability analysis and results of PSI for the NEA/NCR benchmark task

International Nuclear Information System (INIS)

Hennig, D.; Nechvatal, L.

1996-09-01

The report describes the PSI stability analysis methodology and the validation of this methodology based on the international OECD/NEA BWR stability benchmark task. In the frame of this work, the stability properties of some operation points of the NPP Ringhals 1 have been analysed and compared with the experimental results. (author) figs., tabs., 45 refs

Performance of core exit thermocouple for PWR accident management action in vessel top break LOCA simulation experiment at OECD/NEA ROSA project

International Nuclear Information System (INIS)

Suzuki, Mitsuhiro; Takeda, Takeshi; Nakamura, Hideo

2009-01-01

Presented are experiment results of the Large Scale Test Facility (LSTF) conducted at the Japan Atomic Energy Agency (JAEA) with a focus on core exit thermocouple (CET) performance to detect core overheat during a vessel top break loss-of-coolant accident (LOCA) simulation experiment. The CET temperatures are used to start accident management (AM) action to quickly depressurize steam generator (SG) secondary side in case of core temperature excursion. Test 6-1 is first test of the OECD/NEA ROSA Project started in 2005, simulating withdraw of a control rod drive mechanism penetration nozzle at the vessel top head. The break size is equivalent to 1.9% cold leg break. The AM action was initiated when CET temperature rose up to 623K. There was no reflux water fallback onto the CETs during the core heat-up period. The core overheat, however, was detected with a time delay of about 230s. In addition, a large temperature discrepancy was observed between the CETs and the hottest core region. This paper clarifies the reason of time delay and temperature discrepancy between the CETs and heated core during boil-off including three-dimensional steam flows in the core and core exit. The paper discusses applicability of the LSTF CET performance to pressurized water reactor (PWR) conditions and a possibility of alternative indicators for earlier AM action than in Test 6-1 is studied by using symptom-based plant parameters such as a reactor vessel water level detection. (author)

The work of the OECD Nuclear Energy Agency on safety and licensing of nuclear installations

International Nuclear Information System (INIS)

Strohl, P.

1975-01-01

The acceleration of nuclear power programmes in OECD Member countries is reflected in the emphasis given by OECD/NEA to its activities in nuclear safety and regulatory matters. Particular effort is devoted to work on radiation protection and radioactive waste management, safety of nuclear installations and nuclear law development. A Committee on the Safety of Nuclear Installations reviews the state of the art and identifies areas for research and co-ordination of national programmes. A Sub-Committee on Licensing collates information and data on licensing standards and practices of different countries with a view to considering problems of common interest. Comparative studies of various licensing systems and discussions between licensing authorities should help to improve regulatory control of nuclear installations for which there appears to be a need for internationally accepted standards in the long run. (author)

Fuel safety criteria in NEA member countries - Compilation of responses received from member countries

International Nuclear Information System (INIS)

2003-03-01

In 2001 the Committee on the Safety of Nuclear Installations (CSNI) issued a report on Fuel Safety Criteria Technical Review. The objective was to review the present fuel safety criteria and judge to which extent they are affected by the 'new' design elements, such as different cladding materials, higher burnup, the use of MOX fuels, etc. The report stated that the current framework of fuel safety criteria remains generally applicable, being largely unaffected by the 'new' or modern design elements. The levels (numbers) in the individual safety criteria may, however, change in accordance with the particular fuel and core design features. Some of these levels have already been - or are continuously being - adjusted. The level adjustments of several other criteria (RIA, LOCA) also appears to be needed, on the basis of experimental data and the analysis thereof. As a follow-up, among its first tasks, the CSNI Special Expert Group on Fuel Safety Margins (SEG FSM) initiated the collection of information on the present fuel safety criteria used in NEA member states with the objective to solicit national practices in the use of fuel safety criteria, in particular to get information on their specific national levels/values, including their recent adjustments, and to identify the differences and commonalties between the different countries. Two sources of information were used to produce this report: a compilation of responses to a questionnaire prepared for the June 2000 CNRA meeting, and individual responses from the SEGFSM members to the new revised questionnaire issued by the task Force preparing this report. In accordance with the latter, the fuel safety criteria discussed in this report were divided into three categories: (A) safety criteria - criteria imposed by the regulator; (B) operational criteria - specific to the fuel design and provided by the fuel vendor as part of the licensing basis; (C) design criteria - limits employed by vendors and/or utilities for fuel

Research strategies for human performance

International Nuclear Information System (INIS)

1998-01-01

Knowledge about factors that influence Human Performance is essential for the safety of nuclear power plant operation. Through a number of tasks, workshops and projects, experience is shared among OECD countries. At its December 1996 meeting, the CSNI endorsed the SESAR/CAF report on 'Nuclear Safety Research in OECD Countries: Capabilities and Facilities' and requested that the Principal Working Groups (PWGs) review existing co-operative programmes and develop specifications for programmes which address the identified needs. Following discussions between the chairmen of these PWGs and the NEA Secretariat, it was concluded that, for this technical area, the development of programme specifications must be preceded by the development of a strategic document that further elaborates the conclusions of the SESAR/CAF report and set out the general orientation of the research over the medium and long term. Accordingly, a group of senior experts met in August 1997 to discuss possible strategies in the area of Human Performance. The objectives of this meeting were: - To exchange information on existing plans and strategies by different Member countries; - To determine relevant issues and realistic medium/long-term targets and expectations for their resolution, and - To determine, in general sense, possible research programmes, their priority and their likelihood for success. This document is the result of this meeting. Its objective is to present to the CSNI proposals for future work on Human Performance research. The proposals are built upon the work performed to date by PWG1 and PWG5. Carrying out these proposals will continue to require close coordination on joint activities between these two PWGs. Reinforced systematic networking activities are needed particularly in management and organisational performance research to initiate and manage comparison and benchmarking activities. Synchronising the availability of funding is a specific problem in many cases. Since most

How to access the Nea Data Bank Services

International Nuclear Information System (INIS)

Anon.

1995-01-01

The OECD/NEA data Bank collects, tests and distributes computer programs and numerical data in the field of nuclear energy applications. These codes cover: cross section and resonance integral calculations, spectrum calculations, generations of group constants and cell problems, static design studies, depletion, fuel management, cost analysis, and power plants economics, radiological safety, hazard and accident analysis, heat transfer and fluid flow, deformation and stress distributions, structural analysis and engineering design studies, gamma heating and shield design, reactor systems analysis, data preparation, processing and management, general mathematical and computing system routines, materials, environmental and earth sciences, electronics, engineering equipment and energy systems studies, chemistry, particles accelerators and high voltage machines, physics, magnetic fusion research

Establishing the Appropriate Attributes in Current Human Reliability Assessment Techniques for Nuclear Safety

International Nuclear Information System (INIS)

Bowie, Jane; Munley, Gary; Dang, Vinh; Wreathall, John; Bye, Andreas; Cooper, Susan; Marble, Julie; Peters, Sean; Xing, Jing; Fauchille, Veronique; Fiset, Jean Yves; Haage, Monica; Johanson, Gunnar; Jung, Won Dae; Kim, Jaewhan; Lee, Seung Jung; Kubicek, Jan; Le Bot, Pierre; Pesme, Helene; Preischl, Wolfgang; Salway, Alice; Amri, Abdallah; Lamarre, Greg; White, Andrew; )

2015-03-01

This report presents the results of a joint task of the Working Groups on Risk Assessment (WGRISK) and on Human and Organisational Factors (WGHOF) of the OECD/NEA CSNI, to identify desirable attributes of Human Reliability Assessment (HRA) methods, and to evaluate a range of HRA methods used in OECD member countries against those attributes. The purpose of this project is to provide information that will support regulators and operators of nuclear facilities when making judgements about the appropriateness of HRA methods for conducting assessments in support of Probabilistic Safety Assessments (PSA). The task was performed by an international team of Human Factors, HRA and PSA experts from a broad range of OECD member countries. As in other reviews of HRA methods, the study did not set out to recommend or promote the use of any particular HRA method. Rather the study aims to identify the strengths and limitations of commonly used and developing methods to aid those responsible for production of HRAs in selecting appropriate tools for specific HRA applications. The study also aims to assist regulators when making judgements on the appropriateness of the application of an HRA technique within nuclear-related probabilistic safety assessments. The report is aimed at practitioners in the field of human reliability assessment, human factors, and risk assessment more generally

FARO test L-14 on fuel coolant interaction and quenching. Comparison report, volume 1 + 2, analysis of the results

International Nuclear Information System (INIS)

Annunziato, A.; Addabbo, C.; Yerkess, A.; Silverii, R.; Brewka, W.; Leva, G.

1997-01-01

This report provides a comparative analysis of the results from the ISP-39 exercise promoted by OECD-CSNI in the frame of the NEA activities. ISP-39 has been conceived to benchmark the predictive capabilities of computer codes used in the evaluation of fuel-coolant interaction (FCI) and quenching phenomenologies of relevance in water cooled reactors severe accidents safety analysis. The ISP-39 reference case is FARO test L-14, a non-energetic FCI test performed under realistic melt composition and prototypical accident conditions in the FARO experimental installation (Ispra, Italy). Thirteen research organizations from ten countries participated in the exercise submitting 15 prediction calculations with 8 different codes or code versions (COMETA, MC3D, IVA, IFCI, JASMINE, TEXAS, THIRMAL, VAPEX). ISP-39 was conducted as an open exercise. Conclusions are given concerning code capabilities, users effect and sensitivity analyses, numerical accuracy quantification of the predictions, code improvements, general considerations

An overview on applied methods in the FRG to investigate human factors in control rooms of nuclear power plants

International Nuclear Information System (INIS)

Thomas, D.B.

1985-01-01

In the first half of 1984 a feasibility study was carried out with respect to the CSNI of the OECD/NEA inventory of methods for the analysis and evaluation of human factors in the control room of nuclear power plants. In order to enable an analysis of the methods to be made, an elementary categorization of the methods under field studies, laboratory studies and theoretical studies was performed. A further differentiation of these categories was used as the basis for a critical analysis and interpretation of the methods employed in the research plan. In the following sections, an explanation is given of the method categories used and the plans included in the investigation. A short representation is given of the breakdown of the applied methods into categories and an analysis is made of the results. Implications for research programs are discussed. (orig./GL) [de

Committee on the safety of nuclear installations - Operating plan (2006 - 2009)

International Nuclear Information System (INIS)

2007-01-01

In 2004, NEA issued its Strategic Plan covering the period 2005-2009, addressing the NEA activities associated with nuclear safety and regulation. Committee on the Safety of Nuclear Installations (CSNI) and Committee on Nuclear Regulatory Activities (CNRA), which have the primary responsibility for activities in this area, have developed and issued a joint strategic plan covering this same time period. As requested in the Joint Strategic Plan, each committee is to prepare an operating plan which describes in more detail the committee's organisation, planned activities, priorities and operating procedures to be used to implement the Joint Strategic Plan. In effect, the Joint Strategic Plan defines what type of work CSNI should do, whereas the Operating Plan describes the overall work scope and how to accomplish it to meet the joint CSNI/CNRA Strategic Plan objectives and mission. The present Operating Plan follows and takes into account the outcome of a CSNI assessment group, which has evaluated the CSNI activities. The assessment group expressed appreciation for the CSNI role and activity, while making recommendations with regards to scope of work and way to operate in order to further improve efficiency. The main objectives of CSNI are to: - Keep all member countries involved in and abreast of developments in safety technology. - Review operating experience with the objective to identify safety issues that need to be addressed by new research. - Review the state-of-knowledge on selected topics of nuclear safety technology and safety assessment. - Promote training and research projects that serve to maintain competence in nuclear safety matters. - Promote research as needed to reach consensus on nuclear safety issues of common interest. - Consider the safety implications of scientific and technical developments. To accomplish these objectives, CSNI is organised into six permanent working groups (as described in Section II), each covering a different set of

Second Specialist Meeting on operator aids for severe accident management: summary and conclusions

International Nuclear Information System (INIS)

1997-01-01

The second OECD Specialist Meeting on operator aids for severe accident management (SAMOA-2) was held in Lyon, France (1997), and was attended by 33 specialists representing ten OECD member countries. As for SAMOA-1, the scope of SAMOA-2 was limited to operator aids for accident management which were in operation or could be soon. The meeting concentrated on the management of accidents beyond the design basis, including tools which might be extended from the design basis range into the severe accident area. Relevant simulation tools for operator training were also part of the scope of the meeting. 20 papers were presented; there were two demonstrations of computerized systems (the ATLAS analysis simulator developed by GRS, and EDF's 'Simulateur Post Accidentels' (SIPA). The three sessions dealt with operator aids for control rooms, operator aids for technical support centres, and simulation tools for operator training. The various papers for each session are summarized

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)

OECD - HRP Summer School on Nuclear Fuel

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

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

OECD - HRP Summer School on Nuclear Fuel

International Nuclear Information System (INIS)

2000-01-01

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

The International Experimental Thermal Hydraulic Systems database – TIETHYS: A new NEA validation tool

Energy Technology Data Exchange (ETDEWEB)

Rohatgi, Upendra S.

2018-07-22

Nuclear reactor codes require validation with appropriate data representing the plant for specific scenarios. The thermal-hydraulic data is scattered in different locations and in different formats. Some of the data is in danger of being lost. A relational database is being developed to organize the international thermal hydraulic test data for various reactor concepts and different scenarios. At the reactor system level, that data is organized to include separate effect tests and integral effect tests for specific scenarios and corresponding phenomena. The database relies on the phenomena identification sections of expert developed PIRTs. The database will provide a summary of appropriate data, review of facility information, test description, instrumentation, references for the experimental data and some examples of application of the data for validation. The current database platform includes scenarios for PWR, BWR, VVER, and specific benchmarks for CFD modelling data and is to be expanded to include references for molten salt reactors. There are place holders for high temperature gas cooled reactors, CANDU and liquid metal reactors. This relational database is called The International Experimental Thermal Hydraulic Systems (TIETHYS) database and currently resides at Nuclear Energy Agency (NEA) of the OECD and is freely open to public access. Going forward the database will be extended to include additional links and data as they become available. https://www.oecd-nea.org/tiethysweb/

Status Report on Activities of the Systems Assessment Task Force, OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs

Energy Technology Data Exchange (ETDEWEB)

Bragg-Sitton, Shannon Michelle [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-09-01

The Organization for Economic Cooperation and Development /Nuclear Energy Agency (OECD/NEA) Nuclear Science Committee approved the formation of an Expert Group on Accident Tolerant Fuel (ATF) for LWRs (EGATFL) in 2014. Chaired by Kemal Pasamehmetoglu, INL Associate Laboratory Director for Nuclear Science and Technology, the mandate for the EGATFL defines work under three task forces: (1) Systems Assessment, (2) Cladding and Core Materials, and (3) Fuel Concepts. Scope for the Systems Assessment task force (TF1) includes definition of evaluation metrics for ATF, technology readiness level definition, definition of illustrative scenarios for ATF evaluation, and identification of fuel performance and system codes applicable to ATF evaluation. The Cladding and Core Materials (TF2) and Fuel Concepts (TF3) task forces will identify gaps and needs for modeling and experimental demonstration; define key properties of interest; identify the data necessary to perform concept evaluation under normal conditions and illustrative scenarios; identify available infrastructure (internationally) to support experimental needs; and make recommendations on priorities. Where possible, considering proprietary and other export restrictions (e.g., International Traffic in Arms Regulations), the Expert Group will facilitate the sharing of data and lessons learned across the international group membership. The Systems Assessment task force is chaired by Shannon Bragg-Sitton (Idaho National Laboratory [INL], U.S.), the Cladding Task Force is chaired by Marie Moatti (Electricite de France [EdF], France), and the Fuels Task Force is chaired by a Masaki Kurata (Japan Atomic Energy Agency [JAEA], Japan). The original Expert Group mandate was established for June 2014 to June 2016. In April 2016 the Expert Group voted to extend the mandate one additional year to June 2017 in order to complete the task force deliverables; this request was subsequently approved by the Nuclear Science Committee. This

Status Report on Activities of the Systems Assessment Task Force, OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs

International Nuclear Information System (INIS)

Bragg-Sitton, Shannon Michelle

2016-01-01

The Organization for Economic Cooperation and Development /Nuclear Energy Agency (OECD/NEA) Nuclear Science Committee approved the formation of an Expert Group on Accident Tolerant Fuel (ATF) for LWRs (EGATFL) in 2014. Chaired by Kemal Pasamehmetoglu, INL Associate Laboratory Director for Nuclear Science and Technology, the mandate for the EGATFL defines work under three task forces: (1) Systems Assessment, (2) Cladding and Core Materials, and (3) Fuel Concepts. Scope for the Systems Assessment task force (TF1) includes definition of evaluation metrics for ATF, technology readiness level definition, definition of illustrative scenarios for ATF evaluation, and identification of fuel performance and system codes applicable to ATF evaluation. The Cladding and Core Materials (TF2) and Fuel Concepts (TF3) task forces will identify gaps and needs for modeling and experimental demonstration; define key properties of interest; identify the data necessary to perform concept evaluation under normal conditions and illustrative scenarios; identify available infrastructure (internationally) to support experimental needs; and make recommendations on priorities. Where possible, considering proprietary and other export restrictions (e.g., International Traffic in Arms Regulations), the Expert Group will facilitate the sharing of data and lessons learned across the international group membership. The Systems Assessment task force is chaired by Shannon Bragg-Sitton (Idaho National Laboratory [INL], U.S.), the Cladding Task Force is chaired by Marie Moatti (Electricite de France [EdF], France), and the Fuels Task Force is chaired by a Masaki Kurata (Japan Atomic Energy Agency [JAEA], Japan). The original Expert Group mandate was established for June 2014 to June 2016. In April 2016 the Expert Group voted to extend the mandate one additional year to June 2017 in order to complete the task force deliverables; this request was subsequently approved by the Nuclear Science Committee. This

Nuclear legislation. Analytical study. Regulatory and Institutional framework for nuclear activities in OECD Member countries. Volume I

International Nuclear Information System (INIS)

1983-01-01

This study is part of a series of analytical studies of the major aspects of nuclear legislation in OECD Member countries and is published in two volumes. This Volume I of the study is a revision and an expansion of a 1969 study concerning the organisation and general regime governing nuclear activities. The national studies were prepared, to the extent possible, following a standard plan for all countries to facilitate information retrieval and comparison. (NEA) [fr

The work and perspective of the OECD/NEA in decommissioning

International Nuclear Information System (INIS)

O'Sullivan, P.; Pescatore, C.

2008-01-01

OECD member countries are increasingly faced with the need to make provisions for dealing with all aspects of dealing with the management of legacy nuclear installations, especially in terms of having in place adequate policies and regulatory frameworks for ensuring both safety and the efficient implementation of the decommissioning projects. Efficiency also requires that funding schemes are capable of providing adequate funds when required, even in the event that issues arise during implementation that were not anticipated during the planning phase. Waste management arrangements may encompass separate disposal routes for different categories of waste, including Very Low Level Waste, and may also include provisions for clearance and recycling. Recent moves in several countries towards establishing new nuclear programmes are bringing decommissioning activities into fresh focus, for reasons of public confidence (i.e. demonstrating that decommissioning can be done). In some instances existing nuclear sites will be used for the construction of new installations, but stakeholder issues are important for these sites as well. Maturing decommissioning experience should also provide lessons that would help in the reduction of lifetime costs for nuclear plants and other facilities. The challenge lying ahead is to establish a framework that will account for growing nuclear industrial activities in competitive, globalized markets, while maintaining and assuring the safety of decommissioning for the public and for workers. Within this context, institutional arrangements, stakeholder issues, costs and funding, waste management and release policies, as well as availability of technologies and skills, need to be kept under review. (authors)

Radiation shielding activities at the OECD/Nuclear Energy Agency

International Nuclear Information System (INIS)

Sartori, Enrico; Vaz, Pedro

2000-01-01

The OECD Nuclear Energy Agency (NEA) has devoted considerable effort over the years to radiation shielding issues. The issues are addressed through international working groups. These activities are carried out in close co-ordination and co-operation with the Radiation Safety Information Computational Center (RSICC). The areas of work include: basic nuclear data activities in support of radiation shielding, computer codes, shipping cask shielding applications, reactor pressure vessel dosimetry, shielding experiments database. The method of work includes organising international code comparison exercises and benchmark studies. Training courses on radiation shielding computer codes are organised regularly including hands-on experience in modelling skills. The scope of the activity covers mainly reactor shields and spent fuel transportation packages, but also fusion neutronics and in particular shielding of accelerators and irradiation facilities. (author)

International report to validate criticality safety calculations for fissile material transport

International Nuclear Information System (INIS)

Whitesides, G.E.

1984-01-01

During the past three years a Working Group established by the Organization for Economic Co-operation and Development's Nuclear Energy Agency (OECD-NEA) in Paris, France, has been studying the validity and applicability of a variety of criticality safety computer programs and their associated nuclear data for the computation of the neutron multiplication factor, k/sub eff/, for various transport packages used in the fuel cycle. The principal objective of this work has been to provide an internationally acceptable basis for the licensing authorities in a country to honor licensing approvals granted by other participating countries. Eleven countries participated in the initial study which consisted of examining criticality safety calculations for packages designed for spent light water reactor fuel transport. This paper presents a summary of this study which has been completed and reported in an OECD-NEA Report No. CSNI-71. The basic goal of this study was to outline a satisfactory validation procedure for this particular application. First, a set of actual critical experiments were chosen which contained the various material and geometric properties present in typical LWR transport containers. Secondly, calculations were made by each of the methods in order to determine how accurately each method reproduced the experimental values. This successful effort in developing a benchmark procedure for validating criticality calculations for spent LWR transport packages along with the successful intercomparison of a number of methods should provide increased confidence by licensing authorities in the use of these methods for this area of application. 4 references, 2 figures

Renewable energy and macroeconomic efficiency of OECD and non-OECD economies

International Nuclear Information System (INIS)

Chien, Taichen; Hu, Jin-Li

2007-01-01

This article analyzes the effects of renewable energy on the technical efficiency of 45 economies during the 2001-2002 period through data envelopment analysis (DEA). In our DEA model, labor, capital stock, and energy consumption are the three inputs and real GDP is the single output. Increasing the use of renewable energy improves an economy's technical efficiency. Conversely, increasing the input of traditional energy decreases technical efficiency. Compared to non-OECD economies, OECD economies have higher technical efficiency and a higher share of geothermal, solar, tide, and wind fuels in renewable energy. However, non-OECD economies have a higher share of renewable energy in their total energy supply than OECD economies

OECD-FIRE PR02. OECD-FIRE database record structure

International Nuclear Information System (INIS)

Kolar, L.

2005-12-01

In the coding guidelines, the scope, format, and details of any record required to input a real fire event at a nuclear reactor unit to the international OECD-FIRE database are described in detail. The database was set up in the OECD-FIRE-PR02 code

Containment severe accident management - selected strategies

International Nuclear Information System (INIS)

Duco, J.; Royen, J.; Rohde, J.; Frid, W.; De Boeck, B.

1994-01-01

The OECD Nuclear Energy Agency (NEA) organized in June 1994, in collaboration with the Swedish Nuclear Power Inspectorate (SKI), a Specialist Meeting on Selected Containment Severe Accident Management Strategies, to discuss their feasibility, effectiveness, benefits and drawbacks, and long-term impact. The meeting focused on water reactors, mainly on existing systems. The technical content covered topics such as general aspects of accident management strategies in OECD Member countries, hydrogen management techniques and other containment accident management strategies, surveillance and protection of the containment function. The main conclusions of the meeting are summarized in the paper. (author)

The Nuclear Energy Agency of the OECD through its history; La Agencia de Energia Nuclear de la OCDE, a traves de su historia

Energy Technology Data Exchange (ETDEWEB)

Echavarri, L.

2008-07-01

This year, 2008, marks the 50th Anniversary of the OECD Nuclear Energy Agency (NEA). During these years the Agency has adapted to the evolution of the world energy situation. At the beginning the Agency launches international collaboration projects to establish the technological bases required for nuclear energy, then helps member countries in the construction of nuclear power plants and later analyzes the safety criteria as a consequence of the Three Miles Island and Chernobyl accidents. Based on this experience, the NEA faces the X XI Century prepared to contribute, even more, to a better international collaboration for a safe, environmentally friendly and economical use of the nuclear energy. (Author)

Links with NEA activities: Nuclear Data services and WPs

International Nuclear Information System (INIS)

Cabellos, O.

2016-01-01

During the last three years a significant number of international activities have been undertaken on Primary Radiation Damage (PRD): the Expert Group on Primary Radiation Damage belonging to the Working Party on Multi-scale Modelling of Fuels and Structural Materials for Nuclear Systems (WPMM- OECD/NEA/NSC), Coordinated Research Project (CRP) on “Primary Radiation Damage Cross Sections” (IAEA/NDS) and the activities of the European Consortium on Nuclear Data Development and Analysis for Fusion within the Fusion for Energy (F4E) Program. NEA activities related to fuels and structural materials are coordinated by the Working Party on Multi-scale Modelling of Fuels and Structural Materials for Nuclear Systems, WPMM. In May 2015, the Expert Group on “Primary Radiation Damage” reviewed the limitation of the NRT-dpa standard, and recommended a new improved standard of primary damage characteristics, the arc-dpa. Recently, the new Expert Group on Structural Materials Modelling (SMM) has been created to enhance efforts on the multiscale modelling approach applied to structural materials, in order to investigate phenomena that can not be studied experimentally, predicting how the nanostructure and the microchemistry changes under irradiation

Fast burner reactor benchmark results from the NEA working party on physics of plutonium recycle

International Nuclear Information System (INIS)

Hill, R.N.; Wade, D.C.; Palmiotti, G.

1995-01-01

As part of a program proposed by the OECD/NEA Working Party on Physics of Plutonium Recycling (WPPR) to evaluate different scenarios for the use of plutonium, fast reactor physics benchmarks were developed; fuel cycle scenarios using either PUREX/TRUEX (oxide fuel) or pyrometallurgical (metal fuel) separation technologies were specified. These benchmarks were designed to evaluate the nuclear performance and radiotoxicity impact of a transuranic-burning fast reactor system. International benchmark results are summarized in this paper; and key conclusions are highlighted

IAEA/NEA incident reporting system (IRS). Reporting guidelines. Feedback from safety related operating experience for nuclear power plants

International Nuclear Information System (INIS)

1998-01-01

The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants. These guidelines have been jointly developed and approved by the NEA/IAEA

Nuclear Energy and Renewables: System Effects in Low-carbon Electricity Systems : Method comments to a NEA report

OpenAIRE

Söder, Lennart

2012-01-01

OECD Nuclear Energy Agency (NEA) released a new report on 29 November 2012. The study recommends that decision-makers should take full electricity system costs into account in energy choices and that such costs should be internalised according to a “generator pays” principle. The study, entitled Nuclear Energy and Renewables: System Effects in Low-carbon Electricity Systems, addresses the increasingly important interactions of variable renewables and dispatchable energy technologies, such as ...

Summary report for the second TUV-workshop proceedings on living PSA application

International Nuclear Information System (INIS)

1991-01-01

This workshop on living PSA Application was organized to support the OECD/NEA CSNI-Principal Working Group No.5 on Risk Assessment for an international exchange of experience on living PSA application. The first session was devoted to Living PSA Applications and the second session to Tools for Living PSA. Living PSA Applications: Reasons for performing PSA (regulatory requirement, targets; corporate requirement, targets; safety related activity prioritization; other); Logistic of Living PSA Management (Corporate management involvement, Decision making levels and guidance, Plant level involvement, Required personnel commitment, Frequency and extent of re-quantification of PSA, Types of safety/risk parameters to be monitored, Quality assurance on maintaining Living PSA); Examples of Application (Experiences of application, State of Living PSA/e.g. all accident sequences involved, Details of component level involvement). Tools for Living PSA: Data Collection Systems and Codes (Source and type of data collected, Probabilistic parameter quantification, Interface to basic event data, Data code systems). An executive summary of the workshop is given

Reactivity measurements on an experimental assembly of 4.31 wt % 235U enriched UO2 fuel rods arranged in a shipping cask geometry

International Nuclear Information System (INIS)

Bierman, S.R.

1989-10-01

A research program was initiated for the US Department of Energy (DOE) Sandia National Laboratory Transportation Systems Development Department in 1982 to provide benchmark type experimental criticality data in support of the design and safe operations of nuclear fuel transportation systems. The overall objective of the program is to identify and provide the experimental data needed to form a consistent, firm, and complete data base for verifying calculational models used in the criticality analyses of nuclear transport and related systems. A report, PNL-6205, issued in June 1988 (Bierman 1988) covered measurement results obtained from a series of experimental assemblies (TIC-1, 2, 3 and 4) involving neutron flux traps. The results obtained on a fifth experimental assembly (TIC-5), modeled after a calculational problem of the Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group, are covered in this report. 10 refs., 10 figs., 7 tabs

Use of decision analytic methods in nuclear safety. An international survey

International Nuclear Information System (INIS)

Holmberg, J.; Pulkkinen, U.

1996-12-01

This report reviews applications of formal decision analysis methods in resolving nuclear safety related issues. The review is based on selected published reports and a questionnaire sent to the members of the Principal Working Group 5 on risk analysis (PWG5) of OECD/NEA/CSNI. In the report, decision analysis methodology is shortly described. The applications discussed in this review are related to probabilistic safety goals of safety criteria, operational safety management, nuclear waste management and emergency management. The experiences from the application decision analysis methodology have been mainly positive. The advantages provided by the decision analytical thinking are the structured view over the problem under consideration and the explicit statements on uncertainties, values and preferences. The decision analysis methodology is rather mature to be applied in solution of nuclear safety issues. Although the applications have been mainly research oriented, it can be expected that the practical use of the methodology shall be more common in future. (orig.) (27 refs.)

Use of decision analytic methods in nuclear safety. An international survey

Energy Technology Data Exchange (ETDEWEB)

Holmberg, J.; Pulkkinen, U. [VTT Automation, Espoo (Finland). Industrial Automation

1996-12-01

This report reviews applications of formal decision analysis methods in resolving nuclear safety related issues. The review is based on selected published reports and a questionnaire sent to the members of the Principal Working Group 5 on risk analysis (PWG5) of OECD/NEA/CSNI. In the report, decision analysis methodology is shortly described. The applications discussed in this review are related to probabilistic safety goals of safety criteria, operational safety management, nuclear waste management and emergency management. The experiences from the application decision analysis methodology have been mainly positive. The advantages provided by the decision analytical thinking are the structured view over the problem under consideration and the explicit statements on uncertainties, values and preferences. The decision analysis methodology is rather mature to be applied in solution of nuclear safety issues. Although the applications have been mainly research oriented, it can be expected that the practical use of the methodology shall be more common in future. (orig.) (27 refs.).

PREMIUM - Benchmark on the quantification of the uncertainty of the physical models in the system thermal-hydraulic codes

International Nuclear Information System (INIS)

Skorek, Tomasz; Crecy, Agnes de

2013-01-01

PREMIUM (Post BEMUSE Reflood Models Input Uncertainty Methods) is an activity launched with the aim to push forward the methods of quantification of physical models uncertainties in thermal-hydraulic codes. It is endorsed by OECD/NEA/CSNI/WGAMA. The benchmark PREMIUM is addressed to all who applies uncertainty evaluation methods based on input uncertainties quantification and propagation. The benchmark is based on a selected case of uncertainty analysis application to the simulation of quench front propagation in an experimental test facility. Application to an experiment enables evaluation and confirmation of the quantified probability distribution functions on the basis of experimental data. The scope of the benchmark comprises a review of the existing methods, selection of potentially important uncertain input parameters, preliminary quantification of the ranges and distributions of the identified parameters, evaluation of the probability density function using experimental results of tests performed on FEBA test facility and confirmation/validation of the performed quantification on the basis of blind calculation of Reflood 2-D PERICLES experiment. (authors)

OECD/NEZ Main Steam Line Break Benchmark Problem Exercise I Simulation Using the SPACE Code with the Point Kinetics Model

International Nuclear Information System (INIS)

Kim, Yohan; Kim, Seyun; Ha, Sangjun

2014-01-01

The Safety and Performance Analysis Code for Nuclear Power Plants (SPACE) has been developed in recent years by the Korea Nuclear Hydro and Nuclear Power Co. (KHNP) through collaborative works with other Korean nuclear industries. The SPACE is a best-estimated two-phase three-field thermal-hydraulic analysis code to analyze the safety and performance of pressurized water reactors (PWRs). The SPACE code has sufficient features to replace outdated vendor supplied codes and to be used for the safety analysis of operating PWRs and the design of advanced reactors. As a result of the second phase of the development, the 2.14 version of the code was released through the successive various V and V works. The topical reports on the code and related safety analysis methodologies have been prepared for license works. In this study, the OECD/NEA Main Steam Line Break (MSLB) Benchmark Problem Exercise I was simulated as a V and V work. The results were compared with those of the participants in the benchmark project. The OECD/NEA MSLB Benchmark Problem Exercise I was simulated using the SPACE code. The results were compared with those of the participants in the benchmark project. Through the simulation, it was concluded that the SPACE code can effectively simulate PWR MSLB accidents

OECD/NEA Ongoing activities related to the nuclear fuel cycle

International Nuclear Information System (INIS)

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

2013-01-01

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

First-term Status Report for the Component Operational Experience Degradation and Ageing Programme (CODAP) - 2011-2014

International Nuclear Information System (INIS)

2015-04-01

Structural integrity of piping systems is important for plant safety and operability. In recognition of this, information on degradation and failure of piping components and systems is collected and evaluated by regulatory agencies, international organisations (e.g., OECD/NEA and IAEA) and industry organisations worldwide to provide systematic feedback to reactor regulation and research and development programmes associated with non-destructive examination (NDE) technology, in-service inspection (ISI) programmes, leak-before-break evaluations, risk-informed ISI, and probabilistic safety assessment (PSA) applications involving passive component reliability. Several OECD Member Countries have agreed to establish the OECD/NEA 'Component Operational Experience, Degradation and Ageing Programme' (CODAP) to encourage multilateral co-operation in the collection and analysis of data relating to degradation and failure of metallic piping and non-piping metallic passive components in commercial nuclear power plants. The scope of the data collection includes service-induced wall thinning, part through-wall cracks, through-wall cracks with and without active leakage, and instances of significant degradation of metallic passive components, including piping pressure boundary integrity. The Project is organised under the OECD/NEA Committee on the Safety of Nuclear Installations (CSNI). CODAP is the continuation of the 2002-2011 'OECD/NEA Pipe Failure Data Exchange Project' (OPDE) and the Stress Corrosion Cracking Working Group of the 2006-2010 'OECD/NEA SCC and Cable Ageing project' (SCAP). OPDE was formally launched in May 2002. Upon completion of the 3. Term (May 2011), the OPDE project was officially closed to be succeeded by CODAP. SCAP was enabled by a voluntary contribution from Japan. It was formally launched in June 2006 and officially closed with an international workshop held in Tokyo in May 2010. Majority of the member organizations of the

International assessment of PCA codes

International Nuclear Information System (INIS)

Neymotin, L.; Lui, C.; Glynn, J.; Archarya, S.

1993-11-01

Over the past three years (1991-1993), an extensive international exercise for intercomparison of a group of six Probabilistic Consequence Assessment (PCA) codes was undertaken. The exercise was jointly sponsored by the Commission of European Communities (CEC) and OECD Nuclear Energy Agency. This exercise was a logical continuation of a similar effort undertaken by OECD/NEA/CSNI in 1979-1981. The PCA codes are currently used by different countries for predicting radiological health and economic consequences of severe accidents at nuclear power plants (and certain types of non-reactor nuclear facilities) resulting in releases of radioactive materials into the atmosphere. The codes participating in the exercise were: ARANO (Finland), CONDOR (UK), COSYMA (CEC), LENA (Sweden), MACCS (USA), and OSCAAR (Japan). In parallel with this inter-code comparison effort, two separate groups performed a similar set of calculations using two of the participating codes, MACCS and COSYMA. Results of the intercode and inter-MACCS comparisons are presented in this paper. The MACCS group included four participants: GREECE: Institute of Nuclear Technology and Radiation Protection, NCSR Demokritos; ITALY: ENEL, ENEA/DISP, and ENEA/NUC-RIN; SPAIN: Universidad Politecnica de Madrid (UPM) and Consejo de Seguridad Nuclear; USA: Brookhaven National Laboratory, US NRC and DOE

No evidence for larger leaf trait plasticity in ecological generalists compared to specialists

Czech Academy of Sciences Publication Activity Database

Dostál, Petr; Fischer, M.; Chytrý, M.; Prati, D.

2017-01-01

Roč. 44, č. 3 (2017), s. 511-521 ISSN 0305-0270 R&D Projects: GA ČR GA15-09119S; GA ČR GB14-36079G Institutional support: RVO:67985939 Keywords : ecological generalists and specialists * phenotypic plasticity * multispecies experiments Subject RIV: EH - Ecology, Behaviour OBOR OECD: Ecology Impact factor: 4.248, year: 2016

International co-operation on decommissioning - Achievements of the NEA Co-operative programme 1985-1990

International Nuclear Information System (INIS)

1992-01-01

Decommissioning of nuclear facilities is attracting a growing interest in all countries where an increasing number of plants are reaching the end of their operational life and will have to be decommissioned in the next few years. In response to this interest, the NEA set up in 1985 an international programme of technical co-operation between decommissioning projects in eight OECD countries. This report describes the programme and the participating projects, reviews the experiences accumulated during the first five-year term of this international undertaking, and discusses what remains to be done

Fundamentals of the NEA Thermochemical Database and its influence over national nuclear programs on the performance assessment of deep geological repositories.

Science.gov (United States)

Ragoussi, Maria-Eleni; Costa, Davide

2017-03-14

For the last 30 years, the NEA Thermochemical Database (TDB) Project (www.oecd-nea.org/dbtdb/) has been developing a chemical thermodynamic database for elements relevant to the safety of radioactive waste repositories, providing data that are vital to support the geochemical modeling of such systems. The recommended data are selected on the basis of strict review procedures and are characterized by their consistency. The results of these efforts are freely available, and have become an international point of reference in the field. As a result, a number of important national initiatives with regard to waste management programs have used the NEA TDB as their basis, both in terms of recommended data and guidelines. In this article we describe the fundamentals and achievements of the project together with the characteristics of some databases developed in national nuclear waste disposal programs that have been influenced by the NEA TDB. We also give some insights on how this work could be seen as an approach to be used in broader areas of environmental interest. Copyright © 2017 Elsevier Ltd. All rights reserved.

Proceedings (slides) of the OECD/NEA Workshop on Innovations in Water-cooled Reactor Technologies

International Nuclear Information System (INIS)

Spiler, Joze; Kim, Sang-Baik; ); Feron, Fabien; Jaervinen, Marja-Leena; Husse, Julien; ); Ferraro, Giovanni; Bertels, Frank; Denk, Wolfgang; Tuomisto, Harri; Golay, Michael; Buongiorno, J.; Todreas, N.; Adams, E.; Briccetti, A.; Jurewicz, J.; Kindfuller, V.; Srinivasan, G.; Strother, M.; Minelli, P.; Fasil, E.; Zhang, J.; Genzman, G.; Epinois, Bertrand de l'; Kim, Shin Whan; Laaksonen, Jukka; Maltsev, Mikhail; Yu, CHongxing; Powell, David; Gorgemans, Julie; Hopwood, Jerry; Bylov, Igor; Bakhmetyev, Alexander M.; Lepekhin, Andrey N.; Fadeev, Yuriy P.; Bruna, Giovanni; Gulliford, Jim; ); Ham-Su, Rosaura; Thevenot, Caroline; GAUTIER, Guy-Marie; MARSAULT, Philippe; PIGNATEL, Jean-Francois; White, Andrew; )

2015-02-01

Hitachi's ABWR and ESBWR: safer, simpler, smarter(D. Powell); 17 - Innovations in Reactor Designs (J. Gorgemans); 18 - Innovations in Water-Cooled Technologies: Candu Energy Perspective ( J. Hopwood); 19 - OKBM AFRIKANTOV small modular reactors engineering solutions for safety provision (I. Bylov, A.M. Bakhmetyev, A.N. Lepekhin, Y.P. Fadeev); 20 - NUGENIA Association For GEN II / GEN III R and D (G. Bruna); 21 - Status of NEA Nuclear Science activities related to accident tolerant fuels (J. Gulliford); 22 - Advanced Fuel and Fuel Cycles S and T (R. Ham-Su); 23 - Main results and lessons of the 10 years innovation research program dedicated to LWR ( C. Thevenot, G.M. Gautier, P. Marsault, J.F. Pignatel); 24 - Offshore Floating Nuclear Power Plant (OFNP) (M. Golay, J. Buongiorno, N. Todreas, E. Adams, A. Briccetti, J. Jurewicz, V. Kindfuller, G. Srinivasan, M. Strother, P. Minelli, E. Fasil, J. Zhang, G. Genzman); 25 - CSNI Research on Safety of Water-Cooled Reactors (A. White)

Nuclear legislation analytical study. Regulatory and institutional framework for nuclear activities in OECD member countries. Volume II

International Nuclear Information System (INIS)

1984-01-01

This study is part of a series of analytical studies of the major aspects of nuclear legislation in OECD Member countries and is published in two volumes. This volume II of the study is a revision and an expansion of a 1969 study concerning the organisation and general regime governing nuclear activities. The national studies were prepared, to the extent possible, following a standard plan for all countries to facilitate information retrieval and comparison. This volume also contains tables of international conventions of relevance to the nuclear field. (NEA) [fr

Protective measures adopted in OECD member countries in response to the Chernobyl accident

International Nuclear Information System (INIS)

Yoshida, Yoshikazu

1988-01-01

The report outlines the measures for exposure prevention taken in West European countries following the Chernobyl power plant accident. In particular, the radioactivity regulation levels for foods (derived intervention levels) adopted in these countries are described in detail, citing from the reports of the Committee on Radiation Protection and Public Health of OECD/NEA (The Radiological Impact of the Chernobyl Accident in OECD Countries) and an scientific seminar held by EC (International Scientific Seminar on Foodstuffs Intervention Levels Following a Nuclear Accident). It is pointed out that these countries rather largely vary in measures taken and the derived intervention levels adopted although the principles for radiation protection which provide the basis for emergency protection measures must be nearly the same in all of the countries. It is necessary to establish consistent standards in each country in consideration of an accident, like the one at Chernobyl, that may have global effects. The ICRP recommendations and IAEA safety guidelines so far are centered on ''near-field'' measures to be taken in areas near an accident site. Thus, studies should be made to establish measures to be taken in areas far from the site. (Nogami, K.)

Comparison report of the OECD/CSNI international standard problem 21 (Piper-one experiment PO-SB-7). Volume 1 comparison report. Volume 2 evaluation of code accuracy in the prediction of ISP 21

International Nuclear Information System (INIS)

1989-11-01

The present report deals with the comparison of 6 blind predictions, submitted by 5 participants, and the experimental results measured during the test PO-SB-7 performed in PIPER-ONE facility. The PIPER-ONE apparatus is an experimental simulator of a General Electric BWR. The test PO-SB-7 simulates a SB-LOCA originated by a break in one recirculation line of the reference BWR-6 plant, without intervention of high pressure ECCS. The overall activity constitutes the CSNI ISP-21. The main parts of the report are: a) outline of the test facility and of the PO-SB-7 experiment; b) overview of input models used by participants; c) evaluation of participant predictions on the basis of one-by-one comparison with selected experimental trends; d) evaluation of present code capabilities and accuracy, on the basis of the overall comparison between measured data and participants double blind predictions. Finally, a judgement is given in relation to the overall value of the activity

Proceedings of the specialist meeting on severe accident management implementation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

The Niantic Specialist meeting was structured around three main themes, one for each session. During the first session, papers from regulators, research groups, designers/owners groups and some utilities discussed the critical decisions in Severe Accident Management (SAM), how these decisions were addressed and implemented in generic SAM guidelines, what equipment and instrumentation was used, what are the differences in national approaches, etc. During the second session, papers were presented by utility specialists that described approaches chosen to specific implementation of the generic guidelines, the difficulties encountered in the implementation process and the perceived likelihood of success of their SAM program in dealing with severe accidents. The third session was dedicated to discussing what are the remaining uncertainties and open questions in SAM. Experts from several OECD countries presented significant perspectives on remaining open issues

Proceedings of the specialist meeting on severe accident management implementation

International Nuclear Information System (INIS)

1995-01-01

The Niantic Specialist meeting was structured around three main themes, one for each session. During the first session, papers from regulators, research groups, designers/owners groups and some utilities discussed the critical decisions in Severe Accident Management (SAM), how these decisions were addressed and implemented in generic SAM guidelines, what equipment and instrumentation was used, what are the differences in national approaches, etc. During the second session, papers were presented by utility specialists that described approaches chosen to specific implementation of the generic guidelines, the difficulties encountered in the implementation process and the perceived likelihood of success of their SAM program in dealing with severe accidents. The third session was dedicated to discussing what are the remaining uncertainties and open questions in SAM. Experts from several OECD countries presented significant perspectives on remaining open issues

The OECD FIRE database

International Nuclear Information System (INIS)

Angner, A.; Berg, H.P.; Roewekamp, M.; Werner, W.; Gauvain, J.

2007-01-01

Realistic modelling of fire scenarios is still difficult due to the scarcity of reliable data needed for deterministic and probabilistic fire safety analysis. Therefore, it has been recognized as highly important to establish a fire event database on an international level. In consequence, several member countries of the Nuclear Energy Agency of the OECD have decided in 2000 to establish the International Fire Data Exchange Project (OECD FIRE) to encourage multilateral co-operation in the collection and analysis of data related to fire events at nuclear power plants. This paper presents the OECD FIRE project objectives, work scope and current status of the OECD FIRE database after 3 years of operation as well as first preliminary statistical insights gained from the collected data. (orig.)

OECD-NEA’s New Approach to Human Aspects of Nuclear Safety

International Nuclear Information System (INIS)

Hah, Y.

2016-01-01

Fukushima Daiichi accident in 2011 in Japan has brought us new challenge to deal with “human” aspects of nuclear safety which have always been crucial elements of safety, but which often receive less attention than technical and equipment issues. The key factors that led to the accident were not only a huge tsunami following a massive earthquake, but also a variety of human failures: organizational decision-making, safety culture of the plant staff and the regulator, training to assure that operators are well prepared for a wide range of possible challenges. In order to fully understand and respond to the lessons learned from the Fukushima accident, the OECD-NEA created a new Division of Human Aspects of Nuclear Safety (HANS) which is focusing on the human issues related to nuclear safety. The Division of HANS is responsible for supporting the relevant work programmes of the NEA; fostering greater focus and building expertise in areas vital to effective nuclear safety such as safety culture, personnel training policies and practices; and safety-related public communication and stakeholder engagement. In 2014, NEA produced the Green Booklet on the Characteristics of an Effective Nuclear Regulator noting that the characteristic of “safety focus and safety culture” was one of the four fundamental principles from which all regulatory body actions should be derived. Based on this understanding, in 2015, NEA published the follow up Green Booklet, Safety Culture of an Effective Nuclear Regulatory Body, providing main principles and attributes to be benchmarked for the regulatory bodies to encourage them to enhance their effectiveness as they fulfil their mission to protect public health and safety. Many challenges exist to regulatory bodies’ safety culture which must be recognised, understood and overcome. Continuing collective efforts could help turn these challenges into opportunities to further strengthen the overall health of the safety culture of regulatory

The contribution of nuclear energy co-operation to a new global age, OECD Headquarters, Paris, 30 September 1998

International Nuclear Information System (INIS)

ElBaradei, M.

1998-01-01

The document reproduces the text of the conference given by the Director General of the IAEA at the Special Session to mark the Fortieth Anniversary of the OECD Nuclear Energy Agency (NEA), held at the OECD Headquarters in Paris, on 30 September 1998. The conference emphasizes the role of the IAEA in enlarging the contribution of nuclear energy for peace and development, and ensuring that atomic energy is used at a high level of security and exclusively for peaceful purposes. The Agency was never intended to 'promote' nuclear energy in any commercial sense. Its role is to be an objective institution that serves as a centre for international norm development, standard setting, independent analysis, expert advice, technology transfer, and impartial oversight and verification. From this perspective, the Director General offers some views on why the international nuclear co-operation, complemented by regional and national activities, is an indispensable part of way forward, highlighting the following areas: energy, safety, verification, and technology transfer

The NEA benchmark study of the accident at the Fukushima Daiichi NPP

International Nuclear Information System (INIS)

Koganeya, Toshiyuki

2015-01-01

In November 2012, the NEA, under the aegis of the Committee on the Safety of Nuclear Installations (CSNI), initiated a joint research project called the Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF). Objectives of this project include supporting Fukushima Daiichi decommissioning by analysing accident progression and the current status of the reactors, such as fuel debris distribution in the reactor pressure vessels and primary containment vessels in preparation for fuel debris removal. A second objective of the project is to improve SA (severe analysis) codes through comparisons with data from the Fukushima reactors. So as to enhance communication between analysts and those involved in decommissioning activities, participants in the project have been discussing the remaining uncertainties in relation to understanding the accident and the data needs from the viewpoint of the analysts. Since the accident sequences at the Fukushima Daiichi site include a wide range of phenomena, a phased approach is being applied in this benchmark exercise while awaiting more detailed information on debris examination and other factors. This article provides an overview of the project (scope, input data and boundary conditions, participants (from eight countries), analytical approach - common case and best estimate case) as well as an outline of the project's next phase (BASF phase 2) that begins in June 2015

Estonia to join OECD / Ella Karapetyan

Index Scriptorium Estoniae

Karapetyan, Ella

2010-01-01

2010. aasta kevadel tehakse otsus Eesti liitumise kohta OECD-ga. Välisminister Urmas Paet ja OECD peasekretär Angel Gurria allkirjastasid Pariisis privileegide ja immuniteetide lepingu. OECD liikmed

Unbundling payments for radioisotopes from radiopharmaceuticals and from diagnostic procedures: A tool to support the implementation of full-cost recovery. NEA discussion document

International Nuclear Information System (INIS)

2012-01-01

The objective of the NEA's HLG-MR policy approach is to ensure a long-term secure supply. The HLG-MR has determined that to attain that objective, a necessary (but not sufficient) requirement is that irradiation services in the 99 Mo/ 99m Tc supply chain must be provided on a full-cost recovery (FCR) basis (OECD-NEA, 2011). The HLG-MR policy approach also recommended that supply chain participants should implement payment reforms that promote full-cost recovery within their reimbursement systems. Reforms might include separate radioisotope pricing or auditing, separate radioisotope payment, differential radioisotope payment for FCR, or other approaches to promote a complete transition to full-cost recovery

International Expert - OECD/NEA

International Nuclear Information System (INIS)

Yi, Yong Sun

2009-11-01

This report was prepared to describe the activities of Yongsun Yi as a technical secretary for the Generation IV VHTR (Very High Temperature Reactor) system. The contents of the report are; i) the GIF (Generation IV International Forum); ii) the GIF governance and technical secretariat; iii) the brief description of the VHTR system iv) the activities of Yongsun Yi as the technical secretary for the VHTR system

Eesti loodab peagi OECD liikmekutset / Sirje Rank

Index Scriptorium Estoniae

Rank, Sirje, 1966-

2010-01-01

OECD on Eesti hindamisel jõudnud lõppjärku, liitumiskutset on oodata maikuus. OECD-le pakub huvi Eesti reformikogemus, e-valitsusega seonduv, oodatud on Eesti seisukohad OECD liitumiskõnelustel Venemaaga. OECD tegevusest

CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (FALSIRE II)

Energy Technology Data Exchange (ETDEWEB)

Bass, B.R.; Pugh, C.E.; Keeney, J. [Oak Ridge National Lab., TN (United States); Schulz, H.; Sievers, J. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Gemany)

1996-11-01

A summary of Phase II of the Project for FALSIRE is presented. FALSIRE was created by the Fracture Assessment Group (FAG) of the OECD/NEA`s Committee on the Safety of Nuclear Installations (CNSI) Principal Working Group No. 3. FALSIRE I in 1988 assessed fracture methods through interpretive analyses of 6 large-scale fracture experiments in reactor pressure vessel (RPV) steels under pressurized- thermal-shock (PTS) loading. In FALSIRE II, experiments examined cleavage fracture in RPV steels for a wide range of materials, crack geometries, and constraint and loading conditions. The cracks were relatively shallow, in the transition temperature region. Included were cracks showing either unstable extension or two stages of extensions under transient thermal and mechanical loads. Crack initiation was also investigated in connection with clad surfaces and with biaxial load. Within FALSIRE II, comparative assessments were performed for 7 reference fracture experiments based on 45 analyses received from 22 organizations representing 12 countries. Temperature distributions in thermal shock loaded samples were approximated with high accuracy and small scatter bands. Structural response was predicted reasonably well; discrepancies could usually be traced to the assumed material models and approximated material properties. Almost all participants elected to use the finite element method.

CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (FALSIRE II)

International Nuclear Information System (INIS)

Bass, B.R.; Pugh, C.E.; Keeney, J.; Schulz, H.; Sievers, J.

1996-11-01

A summary of Phase II of the Project for FALSIRE is presented. FALSIRE was created by the Fracture Assessment Group (FAG) of the OECD/NEA's Committee on the Safety of Nuclear Installations (CNSI) Principal Working Group No. 3. FALSIRE I in 1988 assessed fracture methods through interpretive analyses of 6 large-scale fracture experiments in reactor pressure vessel (RPV) steels under pressurized- thermal-shock (PTS) loading. In FALSIRE II, experiments examined cleavage fracture in RPV steels for a wide range of materials, crack geometries, and constraint and loading conditions. The cracks were relatively shallow, in the transition temperature region. Included were cracks showing either unstable extension or two stages of extensions under transient thermal and mechanical loads. Crack initiation was also investigated in connection with clad surfaces and with biaxial load. Within FALSIRE II, comparative assessments were performed for 7 reference fracture experiments based on 45 analyses received from 22 organizations representing 12 countries. Temperature distributions in thermal shock loaded samples were approximated with high accuracy and small scatter bands. Structural response was predicted reasonably well; discrepancies could usually be traced to the assumed material models and approximated material properties. Almost all participants elected to use the finite element method

Principal working group No. 1 on operating experience and human factors (PWG1). Report of the task group on reviewing the activities

International Nuclear Information System (INIS)

2001-02-01

annual meetings of the working group. In addition there has been a large number of workshops, specialists' meetings, and other meetings focused on particular topics. Many reports of a special nature have been published. In 1999 the CSNI has directed some changes in its existing working groups and this has prompted the reexamination of the processes by which PWG-1 discharges its functions. This re-examination is a consequence of the adoption of a Strategic Plan by the Nuclear Energy Agency and some conforming strategic plans by the CSNI and CNRA. In response to CSNI direction, PWG1 formed a Task Group to consider the directions contained in these strategic plans and propose the necessary changes in the working group mandate. As a point of departure the Task Group reviewed the accomplishments of PWG1 since 1994. It was thought that this review might help guide any changes to the group mandate. It was observed that for the most part PWG1 had been discharging its mandate in a careful and efficient manner. The formal guidance from CSNI with respect to review and modification of the PWG1 mandate is contained in the Strategic Plan of the CSNI. One significant aspect of the Strategic Plan was to reassign the Human Factors aspects of PWG1, as embodied in the Extended Task Force (ETF), to a Special Expert Group which will report directly to CSNI. Further, the CSNI decided to embed the Fuel Cycle Task Group within WGOE. Some structural changes characteristic of strategic planning, including prioritization duties, adoption of success criteria (or performance measures), consideration of customer needs, and consideration of the need to review operating experience for possible future research projects were part of the work of the Task Group. This report provides an analysis of recent progress of PWG1, and also proposes changes to the group mandate, in response to the strategic plans of NEA and CSNI. The mandate is quite brief and lists some broad areas of work

The OECD/NEA/NSC PBMR400 MW coupled neutronics thermal hydraulics transient benchmark - Steady-state results and status

International Nuclear Information System (INIS)

Reitsma, F.; Han, J.; Ivanov, K.; Sartori, E.

2008-01-01

The PBMR is a High-Temperature Gas-cooled Reactor (HTGR) concept developed to be built in South Africa. The analysis tools used for core neutronic design and core safety analysis need to be verified and validated. Since only a few pebble-bed HTR experimental facilities or plant data are available the use of code-to-code comparisons are an essential part of the V and V plans. As part of this plan the PBMR 400 MW design and a representative set of transient cases is defined as an OECD benchmark. The scope of the benchmark is to establish a series of well-defined multi-dimensional computational benchmark problems with a common given set of cross-sections, to compare methods and tools in coupled neutronics and thermal hydraulics analysis with a specific focus on transient events. The OECD benchmark includes steady-state and transients cases. Although the focus of the benchmark is on the modelling of the transient behaviour of the PBMR core, it was also necessary to define some steady-state cases to ensure consistency between the different approaches before results of transient cases could be compared. This paper describes the status of the benchmark project and shows the results for the three steady state exercises defined as a standalone neutronics calculation, a standalone thermal-hydraulic core calculation, and a coupled neutronics/thermal-hydraulic simulation. (authors)

Experimental Results of A1.1 Test for OECD-ATLAS Project

Energy Technology Data Exchange (ETDEWEB)

Kang, Kyoung-Ho; Bae, Byoung-Uhn; Park, Yu-Sun; Kim, Jong-Rok; Choi, Nam-Hyun; Choi, Ki-Yong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

KAERI (Korea Atomic Energy Research Institute) is operating an OECD/NEA project (hereafter, OECD-ATLAS project) by utilizing a thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation). Considering the importance of the SBO scenario and the related accident mitigation measures, a prolonged SBO scenario was selected as the first test subject worthy of investigation in the OECD-ATLAS project as summarized in Table 1. After the Fukushima accident, design extension conditions (DECs) such as an SBO and a total loss of feed water (TLOFW) attracted wide international attention in that such high-risk multiple failure accidents should be revisited from the viewpoint of the reinforcement of the 'defense in depth' concept. In particular, an SBO is one of the most important DECs because a total loss of heat sink can lead to a core melt-down scenario under high pressure without any proper operator action. As for a prolonged SBO transient of the OECD-ATLAS project, two tests, named A1.1 and A1.2, were determined to be performed. In most nuclear power plants (NPPs), a turbine-driven auxiliary feedwater system was designed to remove the decay heat during the early period of an SBO transient. From a conservative point of view, however, it is necessary to investigate the thermal-hydraulic behaviors of the NPP when a turbine-driven auxiliary feedwater supply is not available during the initial period of an SBO transient and moreover a mobile pump-driven auxiliary feedwater supply can only become realized in the later period of the scenario. In particular, asymmetric heat removal characteristic through the supply of auxiliary feedwater only to one steam generator has its own peculiar importance in terms of safety analysis code validation. With an aim of considering these safety importance, in the A1.1 test, a prolonged SBO transient was simulated with two temporal phases: Phase (I) for a conservative SBO transient

OECD/NRC Benchmark Based on NUPEC PWR Sub-channel and Bundle Test (PSBT). Volume I: Experimental Database and Final Problem Specifications

International Nuclear Information System (INIS)

Rubin, A.; Schoedel, A.; Avramova, M.; Utsuno, H.; Bajorek, S.; Velazquez-Lozada, A.

2012-01-01

The need to refine models for best-estimate calculations, based on good-quality experimental data, has been expressed in many recent meetings in the field of nuclear applications. The needs arising in this respect should not be limited to the currently available macroscopic methods but should be extended to next-generation analysis techniques that focus on more microscopic processes. One of the most valuable databases identified for the thermal-hydraulics modelling was developed by the Nuclear Power Engineering Corporation (NUPEC), Japan, which includes sub-channel void fraction and departure from nucleate boiling (DNB) measurements in a representative Pressurised Water Reactor (PWR) fuel assembly. Part of this database has been made available for this international benchmark activity entitled 'NUPEC PWR Sub-channel and Bundle Tests (PSBT) benchmark'. This international project has been officially approved by the Japanese Ministry of Economy, Trade, and Industry (METI), the US Nuclear Regulatory Commission (NRC) and endorsed by the OECD/NEA. The benchmark team has been organised based on the collaboration between Japan and the USA. A large number of international experts have agreed to participate in this programme. The fine-mesh high-quality sub-channel void fraction and departure from nucleate boiling data encourages advancement in understanding and modelling complex flow behaviour in real bundles. Considering that the present theoretical approach is relatively immature, the benchmark specification is designed so that it will systematically assess and compare the participants' analytical models on the prediction of detailed void distributions and DNB. The development of truly mechanistic models for DNB prediction is currently underway. The benchmark problem includes both macroscopic and microscopic measurement data. In this context, the sub-channel grade void fraction data are regarded as the macroscopic data and the digitised computer graphic images are the

PACTEL OECD project planning (PACO). PACTEL OECD project planning

Energy Technology Data Exchange (ETDEWEB)

Kouhia, V.; Purhonen, H. [Lappeenranta University of Technology (Finland)

2004-07-01

OECD launched the SETH project to investigate issues relevant for accident prevention and management and to ensure the existence of integral thermal hydraulic test facilities. The facilities included in the SETH project are PKL from Germany and PANDA from Switzerland. At the early stages of the SETH project an idea was raised to exploit the PACTEL facility in a similar OECD project. Without any external funding the analytical work in the required extent would not be possible within Lappeenranta University of Technology, the party responsible of operating PACTEL. This fact directed the PACO project proposal to be conducted for the SAFIR programme. The aim of the PACO project is to prepare a project proposal to OECD of a PACTEL related project. To attain this objective some preliminary analyses have to be performed to ensure the relevancy of the proposed topic. The low power situation, i.e. midloop state was chosen to be the topic in the PACO studies and project planning basis. The plan is to use PACTEL to examine vertical steam generator behaviour during the midloop operation and the following loss of residual heat removal system transient. Such a possibility is acknowledged with special alterations to PACTEL. The APROS code version 5.04.07 was selected as a tool for the preanalyses. The virtual simulation of the chosen experimental situation would give a preconception on the phenomena to be expected and the progression of the transient. Originally the PACO project was planned to continue only for a few months, ending up with the project proposal to OECD during the summer time 2004. During the pre-calculation process it became obvious that the time expected was not enough to establish good pre-calculation results. The reasons for this relates to time used to learn and adapt the use of the chosen code, improvements and corrections in modelling as well as the code ability to manage the special conditions defined for the project topic. Another aspect on completing a

OECD:s multilaterala BEPS-konvention – Ärdubbelbeskattning tillbaka på menyn?OECD:s multilateral BEPS-convention – Is double Taxation back on the menu?

OpenAIRE

Bender, Lars-Ole

2017-01-01

Uppsatsen behandlar OECD:s multilaterala BEPS-konvention för vilken i skrivande stund OECD om några dagar ska hålla en signeringscermoni. Uppsatsen innefattar en redogörelse för bakomliggande traktatsrätt, en redogörelse för konventionen i sig samt hänvisningar till relevant nationell rätt där denna är aktuell för konveentionens tillämpning.

Report on the CSNI workshop on nuclear power plant transition from operation into decommissioning: human factors and organisation considerations

International Nuclear Information System (INIS)

2000-01-01

The Senior Expert Group of the Committee on the Safety of Nuclear Installations (CSNI) proposed to Principal Working Group 1 (PWG1) of CSNI that a workshop be held to identify and discuss issues related to the impact of human factors and organisational aspects on decommissioning. This workshop was held in May 1999 in conjunction with the Joint NEA/IAEA/EC workshop on The Regulatory Aspects of Decommissioning. The workshop goals, as stated in the NEA Research Strategies for Human Performance, were 'to convene an information exchange meeting with interested Member countries in order to discuss areas of concern in this respect and identify possible areas that merit further research and their priorities'. The workshop highlighted a comparative lack of developed work in this area concerning the way in which organisational weaknesses can manifest themselves and how best to prevent or mitigate their effects. Eight key issues were identified and discussed by the participants. For each of the eight issues discussed by working groups, the potential risks of failing to address the Issue were identified. These potential risks formed a focal point for generating discussion about current experience and for drawing out gaps in current knowledge and understanding. From this base, participants then focused on specific types of information and questions that need further research in order to improve understanding and successful implementation of the transition from operations to decommissioning. The eight issues and suggested high priority needs are: - Creating a system to share international experience: Establish improved methods for obtaining and sharing information and experience on a regular basis in order to identify organisational and human factors issues, good practices and lessons learned as regulators and utilities deal with decommissioning. - Organisational memory and competence: Identify effective approaches to retain expertise during the transition from operations to

Overview of the NEA/OECD Seabed Working Group. An international programme for assessment of the feasibility of disposal of high-level waste in geological formations beneath the ocean

International Nuclear Information System (INIS)

Anderson, D.R.; Boyer, D.G.; Rueegger, B.; Olivier, J.P.

1984-01-01

The NEA/OECD Seabed Working Group, a subcommittee of the Radioactive Waste Management Committee (whose present membership includes Canada, the CEC, the Federal Republic of Germany, France, Japan, the Netherlands, the United Kingdom and the USA), is addressing the questions of how best to utilize the resources of the ocean. Since the beginning of time, the oceans have been the 'garbage dumps' of the land masses. Erosional processes continuously tear down mountains and the land and move them into the oceans. Most of the elements in nuclear waste are chemically identical to those being eroded, cycled and deposited in the ocean. Could the ocean's geological formations be used for the disposal of these radioactive wastes. The Seabed Working Group is divided into eight task groups: System Analysis, Site Selection, Sediment and Rock, Engineering Studies, Biology, Physical Oceanography, Waste Form and Canister, and Institutional. Within each of the groups a set of predictive models is being developed, the appropriate properties acquired, and predictions made. Laboratory and in-situ field tests will be conducted to verify the accuracy of the model predictions. The model sections will then be combined into a systems model to yield an estimate of the feasibility, risk and cost of this waste disposal option. The results to date of the technical and environmental feasibility studies of seabed disposal appear to be leading to a conclusion that this is technically feasible. Institutional feasibility is just beginning to be considered. (author)

Coal Consumption and Economic Growth: Panel Cointegration and Causality Evidence from OECD and Non-OECD Countries

Directory of Open Access Journals (Sweden)

Taeyoung Jin

2018-03-01

Full Text Available This paper examines the relationship between coal consumption and economic growth for 30 OECD (Organisation for Economic Co-operation and Development countries and 32 non-OECD countries for 1990–2013 using a multivariate dependent panel analysis. For the analysis, we conducted the common factor defactorization process, unit root test, cointegration test, long-run cointegrating vector, and Granger causality test. Our results suggest the following: First, there is no long-run relationship between coal consumption and economic growth in OECD countries; however, in non-OECD countries, the relationship does exist. Second, excessive coal usage may hinder economic growth in the long run. Lastly, the growth hypothesis (coal consumption affects economic growth positively is supported in the short run for non-OECD countries. As coal consumption has a positive effect on economic growth in the short run and a negative effect in the long run, energy conservation policies may have adverse effects only in the short run. Thus, non-OECD countries should gradually switch their energy mix to become less coal-dependent as they consider climate change. Moreover, a transfer of technology and financial resources from developed to developing countries must be encouraged at a global level.

The international probabilistic system assessment group. Background and results 1990

International Nuclear Information System (INIS)

1991-01-01

The OECD Nuclear Energy Agency (NEA) devotes considerable effort to the further development of methodologies to assess the performance of radioactive waste disposal systems, and to increase confidence in their application and results. The NEA provides an international forum for the exchange of information and experience among national experts of its twenty-three Member countries and conducts joint studies of issues important for safety assessment. In 1985, the NEA Radioactive Waste Management Committee set up the Probabilistic System Assessment Code User Group (PSAC), in order to help coordinate the development of probabilistic system assessment codes. The activities of the Group include exchange of information, code and experience, discussion of relevant technical issues, and the conduct of code comparison (PSACOIN) exercises designed to build confidence in the correct operation of these tools for safety assessment. The Group is now known simply as the Probabilistic System Assessment Group (PSAG). This report has been prepared to inform interested parties, beyond the group of specialists directly involved, about probabilistic system assessment techniques as used for performance assessment of waste disposal systems, and to give a summary of the objectives and achievements of PSAG. The report is published under the responsibility of the Secretary General of the OECD

Near-surface non-destructive examination of reactor steels: a state-of-the-art report

International Nuclear Information System (INIS)

Launay, J.P.

1985-06-01

A Working Group has been set up to deal with nondestructive testing reliability within the OECD/CSNI framework. One of its activities was to initiate consideration on near surface defect inspection, especially inner surfaces of reactors. The purpose of the survey was to clarify the three following points: present regulations of safety authorities and implementation of these regulations concerning manufacturing examinations and in-service inspection; results of R and D work already performed in this field; R and D work in progress and proposal for an expansion within the framework of the CSNI Special Working Group. This document summarizes information received from the following countries: USA, Spain, the Netherlands, France, United Kingdom, Belgium, Switzerland

Participation in benchmark MATIS-H of NEA/OCDE: uses CFD codes applied to nuclear safety. Study of the spacer grids in the fuel elements

International Nuclear Information System (INIS)

Pena-Monferrer, C.; Chiva, S.; Munoz-cobo, J. L.; Vela, E.

2012-01-01

This paper develops participation in benchmark MATIS-H, promoted by the NEA / OECD-KAERI, involving the study of turbulent flow in a rod beam with spacers in an experimental installation. Its aim is the analysis of hydraulic behavior of turbulent flow in the subchannels of the fuel elements, essential for the improvement of safety margins in normal and transient operations and to maximize the use of nuclear energy through an optimal design of grids.

Human Performance under Extreme Conditions with Respect to a Resilient Organisation. Proceedings of a CSNI International Workshop, 24-26 February 2015, Brugg, Switzerland

International Nuclear Information System (INIS)

2015-01-01

After the Fukushima Daiichi accident a number of initiatives have been undertaken internationally to learn from the accident and to implement lessons learned to improve nuclear safety. The accident has shown in particular the challenges in supporting reliable human performance under extreme conditions. Acknowledging that further work is needed to be better prepared for the HOF (Human and Organisational Factors) challenges of the extreme conditions that may be present in severe accidents, the NEA's Working Group on Human and Organisational Factors (WGHOF), one of the working groups for the Committee on the Safety of Nuclear Installations (CSNI) initiated a new task with the objectives to: - share experiences and knowledge of human and organisational performance under extreme conditions, - identify specific currently applied HOF principles in nuclear and other high risk industries and compare them with the available knowledge, - provide a basis for improvements and necessary research taking into account HOF issues in the design and use of measures, and - make recommendations with the aim to achieve the best level of human and organisational performance as possible under extreme conditions. In order to move those issues forward WGHOF hosted together with the Swiss Federal Nuclear Safety Inspectorate ENSI a workshop entitled 'Human Performance under Extreme Conditions with respect to a Resilient Organization'. The workshop was conducted with participation of a number of invited key speakers from academic research and a range of industries, including nuclear. Thirty-four experts from 12 countries, the IAEA and OECD/Halden participated. Experts came from nuclear authorities, research centres, technical support organisations, training simulator centres, utilities and from non-nuclear field (aircraft accident investigation, fire fighting, military, design of resilient organisations). From the discussions at the workshop, it is clear that the accident at Fukushima has

The OECD/NEA programme on radon and thoron dosimetry and monitoring: its contribution to the assessment of public exposure to natural radiation

International Nuclear Information System (INIS)

Ilari, O.; Steinhaeusler, F.

1984-01-01

Inhalation of radon, thoron and their daughters is recognised to be the most important pathway to exposure of mankind to natural radiation sources. The progressive understanding of the increasing role of this exposure in the overall radiation detriment to the public and the workers produced an increasing concern in several countries about the problems of dosimetry and measurement of these nuclides. This trend was readily appreciated by NEA, which began an active programme in this field in 1976. The effort of NEA focussed on two main areas, namely (a) development of dosimetric models and study of correlation between exposure and dose (Phase I), and (b) review of principles and techniques of metrology and development of guidance on monitoring (Phase II). (author)

International Standard Problems and Small Break Loss-Of-Coolant Accident (SBLOCA)

International Nuclear Information System (INIS)

Aksan, N.

2008-01-01

Best-estimate thermalhydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors. Evaluation of the capabilities and the performance of these codes can be accomplished by comparing the code predictions with measured experimental data obtained on different test facilities. In this respect, parallel to other national and international programs, OECD/Nea (OECD Nuclear Energy Agency) Committee on the Safety of Nuclear Installations (CSNI) has promoted, over the last twenty-nine years some forty-eight International Standard Problems (ISPs). These ISPs were performed in different fields as in-vessel thermalhydraulic behaviour, fuel behaviour under accident conditions, fission product release and transport, core/concrete interactions, hydrogen distribution and mixing, containment thermalhydraulic behaviour. 80% of these ISPs were related to the working domain of Principal Working Group no. 2 on Coolant System Behaviour (PWG2). The ISPs have been one of the major PWG2 activities for many years. The individual ISP comparison reports include the analysis and conclusions of the specific ISP exercises. A global review and synthesis on the contribution that ISPs have made to address nuclear reactor safety issues was initiated by CSNI-PWG2 and an overview on the subject of small break LOCA ISP's is given in this paper based on a report prepared by a CSNI-PWG2 writing group. In addition, the relevance of small break LOCA in a PWR with relation to nuclear reactor safety and the reorientation of the reactor safety program after TMI-2 accident, specifically small break LOCA, are shortly summarized. Five small break LOCA related ISP's are considered, since these were used for the assessment of the advanced best-estimate codes. The considered ISP's deal with the phenomenon typical of small break LOCAs in Western design PWRs. The experiments in four integral test facilities, LOBI, SPES, BETHSY

Erosion of a confined stratified layer by a vertical jet – Detailed assessment of a CFD approach against the OECD/NEA PSI benchmark

Energy Technology Data Exchange (ETDEWEB)

Kelm, S., E-mail: s.kelm@fz-juelich.de [Forschungszentrum Jülich GmbH, 52425 Jülich (Germany); Kapulla, R., E-mail: ralf.kapulla@psi.ch [Paul Scherrer Institute, 5232 Villigen PSI (Switzerland); Allelein, H.-J., E-mail: allelein@lrst.rwth-aachen.de [Forschungszentrum Jülich GmbH, 52425 Jülich (Germany); RWTH Aachen University, 52080 Aachen (Germany)

2017-02-15

Highlights: • Systematic of a U-RANS approach, capable to be applied at containment scale. • Validation against measured and derived point-wise and field data. • Validation by means of transported quantities (concentration) but also underlying flow field and turbulent kinetic energy. • U-RANS approach yields in overall consistent and plausible results. • But unexpected difference in SST and k–ε identified for free-stream flow. - Abstract: Recently, a blind CFD benchmark exercise was conducted by the OECD/NEA (2013–2014) based on an experiment in the PANDA facility at the Paul Scherrer Institute (PSI) in Switzerland, investigating the turbulent erosion of a stratified helium rich layer in the upper region of the test vessel by means of a vertical air-helium jet impinging from below. In addition to the ‘classical’ pointwise measurements available for similar experiments conducted in the past, significant additional efforts were spent on the experimental characterization of the underlying flow field and turbulent quantities by means of particle image velocimetry (PIV) for the benchmark. This data is well suited for a detailed assessment of the driving jet flow and its interaction with the stratified layer. Both are essential in order to avoid elimination of different errors, which is possible if validation is performed in a global manner. Different impacts on the simulation results, in particular on the jet profile and on the mixing progress, are discussed in this paper. A systematic validation is carried out based on measured and derived quantities. It is identified that e.g. the mesh resolution in the jet and mixing zone has only a minor impact, while small changes in turbulence modeling strategy or the chosen model constants, like Sc{sub t}, significantly affect the simulation results. Finally, the chosen unsteady RANS model represents mixing process consistently in the transient progression and instantaneous flow variables, while an unexpected

SCAP: the Nea project on stress corrosion cracking and cable ageing

International Nuclear Information System (INIS)

Yamamoto, A.; Huerta, A.; Gott, K.; Koshy, T.

2007-01-01

Two subjects - stress corrosion cracking (SCC) and degradation of cable insulation - were selected as the focus of the SCC and Cable Ageing Project (SCAP) due to their relevance for plant ageing assessments and their implication on inspection practices. Fourteen NEA member countries agreed to contribute to the project. The main SCAP objectives are to: establish a complete database with regard to major ageing phenomena for SCC and degradation of cable insulation through collective efforts by OECD/NEA members; establish a knowledge base in these areas by compiling and evaluating the collected data and information systematically; perform an assessment of the data and identify the basis for commendable practices which would help regulators and operators to enhance ageing management. The aim of the knowledge base is to provide a state-of-the-art description of the degradation mechanisms, the main influencing factors, the most susceptible materials and locations, and common strategies available for mitigation and repair. The SCAP project is currently in the development phase, defining and refining the database performance requirements, data format and coding guidelines. The project is scheduled to last four years. It is anticipated that the database definition and the collection of data from member countries will take approximately two years. The subsequent assessment and the commendable practices report are expected to take one year each

Reserve requirement systems in OECD countries

OpenAIRE

Yueh-Yun C. O’Brien

2007-01-01

This paper compares the reserve requirements of OECD countries. Reserve requirements are the minimum percentages or amounts of liabilities that depository institutions are required to keep in cash or as deposits with their central banks. To facilitate monetary policy implementation, twenty-four of the thirty OECD countries impose reserve requirements to influence their banking systems’ demand for liquidity. These include twelve OECD countries that are also members of the European Economic and...

NEA Activities in Preserving, Evaluating and Applying Data from Fast Reactor Experiments

International Nuclear Information System (INIS)

Gulliford, N.T.; Cornet, S.M.; Hill, I.; Yamaji, A.

2015-01-01

The goal of the OECD Nuclear Energy Agency (NEA) in the area of nuclear science is to help member countries identify, collate, develop and disseminate the basic scientific and technical knowledge required to ensure safe and reliable operation of current nuclear systems and to develop next generation technologies. Within these general goals, the current nuclear science programme has three key objectives: (i) to help advance the existing scientific knowledge needed to enhance the performance and safety of current nuclear systems, (ii) to contribute to building a solid scientific and technical basis for the development of future generation nuclear systems and (iii) to support the preservation of essential knowledge in the field of nuclear science. As part of the second and third of these objectives, an extensive programme of work to preserve and evaluate data from integral experiments has been established, including reactor physics, shielding and criticality safety experiments on fast reactor systems. Data from experimental facilities are reviewed and, if necessary, archives of information are made safe. This may typically involve the indexing and scanning of key documents and archiving of logbooks, for example. Selected experiments go through a detailed evaluation process and where deemed appropriate, a benchmark description is created in a standardized format for inclusion in one of the NEA Data Bank international databases. This information is used extensively by the international nuclear science community to validate their modelling and simulation tools. The process can be viewed as part of a broader knowledge management function, where information is gathered, evaluated, linked and made accessible to a wide range of users. The presentation gives details of the main databases maintained and developed by the NEA, focusing on those related to fast reactor applications. The status of recent preservation activities for fast reactor archives in the United Kingdom is

NEA 2015 Annual Report

International Nuclear Information System (INIS)

Magwood, William D. IV; Ha, Jaejoo; Nieh, Ho; Hah, Yeonhee; Siemann, Michael; Gulliford, Jim; Matsumoto, Kiyoshi; Vasquez-Maignan, Ximena; Gannon-Picot, Cynthia

2016-01-01

The year 2015 continued to be one of significant change, both in relation to the Agency and the global context within which it operates. As countries around the world plan aggressive nuclear power plant construction programmes, prepare to phase out and decommission plants, or to both build and retire plants simultaneously, issues of economics, waste management, public communication and nuclear safety continue to dominate the global discussion regarding nuclear power. As many countries work to absorb the outcome of the COP21 negotiations at the end of 2015, it is becoming increasingly likely that the future of nuclear power will be determined in great respect by non-traditional suppliers and new entrant countries. As reflected in this year's Annual Report, the NEA completed a significant revision of its management structure, which, it is hoped, will enable it to be more flexible, more efficient and more focused on the issues of greatest concern to its member countries. Our members provided input via the process of developing the new Strategic Plan of the Nuclear Energy Agency: 2017-2022, reaffirming their desire to maintain a sharp focus on nuclear safety as our most important mission area, while also reaffirming the vital importance of the NEA as a leading forum for technology cooperation, economic analysis and scientific investigation. In that respect, the NEA's new role as the institutional home of the International Framework for Nuclear Energy Cooperation (IFNEC) continues the Agency's coverage of complex issues associated with the deployment of new nuclear power plants. The NEA also launched the Nuclear Innovation 2050 initiative in 2015, through which NEA hopes to develop a coordinated international agenda for priority nuclear technology research and development on issues ranging from advanced fuel cycles to improved technology and methods for decommissioning retired plants. In all, 2015 was a year of both continued success for the NEA and a

NEA perspectives on timescales and criteria in post-closure safety of geological disposal

International Nuclear Information System (INIS)

Preter, P. de; Smith, P.; Pescatore, C.; Forinash, B.

2006-01-01

A key challenge in the development of safety cases for geological repositories is associated with the long periods of time over which radioactive wastes that are disposed of in repositories remain hazardous. The OECD Nuclear Energy Agency (NEA) has recently examined issues related to timescales in the context of two projects under the auspices of the Radioactive Waste Management Committee (RWMC): the Timescales Initiative and the Long-Term Safety Criteria (LTSC) Initiative. These projects examine, respectively, the treatment of timescales in actual safety cases and in the development of radiological protection criteria for geological disposal. They treat different aspects of timescales but have some overlap and have shown some convergence of the results achieved to date. Based on these projects, this paper examines general considerations in the handling of timescales, including ethical principles, evolution of the hazards of radioactive waste over time, and uncertainty in the evolution of repository systems (including geological features). The implications of these considerations are examined in terms of repository siting; levels of protection in regulations; planning for pre-closure and post-closure actions; and development and presentation of safety cases. A comparison is made with previous NEA work related to timescales, in order to show evolutions in current understanding. (authors)

NEA perspectives on timescales and criteria in post-closure safety of geological disposal

Energy Technology Data Exchange (ETDEWEB)

Preter, P. de [ONDRAF/NIRAS, Brussels (Belgium); Smith, P. [Safety Assessment Management Ltd, SAM Ltd. (United Kingdom); Pescatore, C.; Forinash, B. [OECD/NEA, Nuclear Energy Agency, 92 - Issy les Moulineaux (France)

2006-07-01

A key challenge in the development of safety cases for geological repositories is associated with the long periods of time over which radioactive wastes that are disposed of in repositories remain hazardous. The OECD Nuclear Energy Agency (NEA) has recently examined issues related to timescales in the context of two projects under the auspices of the Radioactive Waste Management Committee (RWMC): the Timescales Initiative and the Long-Term Safety Criteria (LTSC) Initiative. These projects examine, respectively, the treatment of timescales in actual safety cases and in the development of radiological protection criteria for geological disposal. They treat different aspects of timescales but have some overlap and have shown some convergence of the results achieved to date. Based on these projects, this paper examines general considerations in the handling of timescales, including ethical principles, evolution of the hazards of radioactive waste over time, and uncertainty in the evolution of repository systems (including geological features). The implications of these considerations are examined in terms of repository siting; levels of protection in regulations; planning for pre-closure and post-closure actions; and development and presentation of safety cases. A comparison is made with previous NEA work related to timescales, in order to show evolutions in current understanding. (authors)

CSNI Technical Opinion Papers No. 14 - Nuclear Licensee Organisational Structures, Resources and Competencies: Determining their Suitability

International Nuclear Information System (INIS)

2012-01-01

The way in which nuclear licensees' organisations are structured and resourced clearly has a potential impact on nuclear safety. As experience has continually demonstrated, operating organisations with a strong training programme for personnel, adequate resourcing and overall effective leadership and management perform more effectively in times of crisis than those lacking in one or more of these areas. In parallel, the nuclear industry is developing new resource deployment strategies which are making increased use of contractors and leading to changes in organisational structure, which in turn create challenges for the continued safe operation of nuclear facilities. This technical opinion paper represents the consensus among human and organisational factor specialists in NEA member and associated countries on the methods, approaches and good practices to be followed in designing an organisation with a strong safety focus while meeting business needs. It also considers some of the attributes that an organisation which is effectively managing its resources and capabilities might demonstrate

Contribution of the Nea data bank in the field of calculation codes in radiation protection, radio physics and dosimetry; Role de la banque de donnees de l'AEN dans le domaine des codes de calcul en radioprotection, radiophysique et dosimetrie

Energy Technology Data Exchange (ETDEWEB)

Kodeli, I; Sartori, E [Organization for Econimic Co-Operation and Development (OECD NEA DB), 91 - Issy les Moulineaux (France)

2003-07-01

The Nuclear energy agency is a specialised agency of OECD (organization economic co-operation and development). These missions are to help its members to keep and improve by international cooperation, the scientific, technological and legal bases necessary to a peaceful use of nuclear energy. Nea includes twenty eight countries. Nea works in collaboration with IAEA. The field of activities concerns the acquisition, validation and distribution of nuclear data, calculation codes and experiments. To help users, it organises conferences and training about the calculation codes that it shares out. (N.C.)

Energy balances of OECD countries 1970/1982

International Nuclear Information System (INIS)

Anon.

1984-01-01

The present volume provides standardized energy balance sheets expressed in a common unit of tons of oil equivalent for all OECD Countries. It covers the years 1970 to 1982 year by year and includes many revisions and additions to data previously published. The balances in the present volume are based on data published in OECD Energy Statistics 1971-1981 and OECD Energy Statistics 1981-1982. Tables for each OECD Country include production, import, export, consumption by the different industries, transportation, agriculture, residential sector of the different energies: solid fuels, petroleum, gas, nuclear power and hydroelectricity [fr

International OECD NEA Workshop: Implementation of the EGIRM methodology for presenting of national RW and SF management programmes - Workshop proceedings

International Nuclear Information System (INIS)

Froment, Ludovic; Volckaert, Geert; Garamszeghy, Mike; Lahodova, Zdena; Ilvonen, Mikko; Petry, Elodie; Matuzas, Vaidas; ); KUGEL, Karin; LaZaR, Istvan; Dionisi, Mario; Kinam, Kwon; De Nood, Michiel; Bennett, Peter; Vahr, Henning R.; Grzegrzolka, Andrzej; Madaj, Krzysztof; Virtopeanu, Cornelia Sabina; Samoylov, Andrey; Vedernikova, Marina; Garcia Neri, Emilio; Quiros Gracian, Maria; Gimholt, Eva; Hedberg, Bengt; Stein, Mario; Garrs, Gareth; James, Martin; Heath, Maurice; Lust, Merle; ); Zaccai, Henri; Ciambrella, Massimo; Kwong, Gloria; Lebedev, Vladimir; Smadja, Lisa; )

2018-03-01

The NEA, having developed the methodology with the purpose to harmonize the RW and SF inventories reporting within the presentation of the national RW/SF management strategies and disposal routes proposes wide discussion and practical application of the methodology. The methodology was presented by the EGIRM representatives to invited workshop participants. Four topical sessions were held: Session 1 - RW/SF inventory, management strategy and disposal routes - need to harmonise reporting and presenting. This session aimed at providing an understanding why the methodology development and other relevant activities were started and what is the status of international efforts. Reporting needs for the various international programmes and benefits of a common presentation format were discussed in the session. Session 2 - EGIRM methodology - history of development, background, EGIRM objectives, requirements to the methodology. This session aimed at providing an overview of the methodology development process, objectives achieved and requirements addressed. Session 3 - The methodology in details. This session focussed on all details of the developed methodology explaining the role of each element of the presenting scheme with wide provision of examples. Implementation of the methodology for reporting to different programmes were demonstrated. Session 4 - Practical exercises on the methodology application on prosed examples. This session focussed on practical exercises on the methodology application with examples of hypothetical and some national RW/SF inventories proposed by workshop organisers. This document gathers the available presentations given at this workshop: 1.1 - Review of existing programmes requiring/requesting national SF/RW inventory reporting; requirements to reports; supporting documents (NEA Secretariat, V. LEBEDEV); 1.2 - 'Status and Trends' initiative. Status of project and format of SF/RW inventory reporting (IAEA, M. LUST); 1.3 - Joint

Improving regulatory practices through the OECD-NEA Stress Corrosion Cracking and Cable Ageing Project (SCAP)

International Nuclear Information System (INIS)

Yamamoto, A.; Huerta, A.; Sekimura, N.; Gott, K.; Koshy, T.

2012-01-01

For regulatory authorities, it is important to verify the adequacy of ageing management methods applied by the licensees, based on reliable technical evidence. In order to achieve that goal, 14 NEA member countries joined the SCAP (Project) in 2006 to share knowledge and three more countries joined during the course of the project. The project focused on two important safety issues, the stress corrosion cracking (SCC) and the degradation of cable insulation, due to their relevance for plant ageing assessments and their implication on inspection practices. The commendable practices identified in the project are intended to strengthen technical approaches to optimize ageing management in the areas of SCC and cable ageing. The SCAP SCC and Cable data- and knowledge bases provided extensive information to benefit all stakeholders in designing, constructing, operating and regulating Nuclear Power Plants and also provide commendable practices applicable to new reactors. The paper presents the product of SCAP work resulting from 4 years of technical interactions and shared knowledge from all participants from June 2006 to June 2010. (author)

Estonia ready to contribute to OECD / Ella Karapetyan

Index Scriptorium Estoniae

Karapetyan, Ella

2010-01-01

Eestis visiidil viibinud OECD peasekretär Angel Gurria kohtus president Toomas Hendrik Ilvese ja peaminister Andrus Ansipiga. Kohtumistel räägiti Eesti liitumisest OECD-ga. Andrus Ansip ja Angel Gurria kirjutasid alla Eesti ühinemislepingule OECD-ga

International symposium concluded that uranium supply for nuclear power is secure

International Nuclear Information System (INIS)

2000-01-01

The document informs that stable uranium supply to fuel nuclear power plants will continue to be available according to the conclusion reached at the International Symposium on the Uranium Production Cycle and the Environment held from 2 to 6 October 2000 at the IAEA in Vienna. The meeting included specialists from about 40 countries, in addition to the Arab Atomic Energy Agency, European Commission, OECD/Nuclear Energy Agency (NEA), Office of Supervising Scientist (OSS)/Environment Australia, United Nations, Uranium Institute, World Bank, the World Energy Council and the Nuclear Energy Institute (NEI)

Strategies for competitive nuclear power plants

International Nuclear Information System (INIS)

1999-11-01

This technical publication on competitive strategies for nuclear power plants (NPPs) is part of an ongoing project on management of NPP operations in a competitive environment. The overall objective of this project is to assist the management of operating organizations and NPPs in identifying and implementing appropriate measures to remain competitive in a rapidly changing business environment. Other documents that have been written on this topic have focused on how the environment in which NPPs operate is changing. This report instead focuses on strategies and techniques that operating organization and NPP managers can use to succeed in this environment. Of particular note is ongoing OECD/NEA work to describe the environment for nuclear power in competitive electricity markets. The main objective of the OECD/NEA study is to review the impacts of increasing market competition on the nuclear power sectors in OECD Member countries. The OECD/NEA study is identifying various nuclear aspects which have to be considered in relation to the regulatory reform of the electricity sector in OECD Member States. The OECD/NEA work was co-ordinated with the development of this IAEA report; staff members from the two organizations participated in the development and review of the associated documents. Thus, the strategies and techniques identified in this report are consistent with the impacts of increasing market competition identified in the OECD/NEA study

The OECD expert meeting on ecotoxicology and environmental fate--towards the development of improved OECD guidelines for the testing of nanomaterials.

Science.gov (United States)

Kühnel, Dana; Nickel, Carmen

2014-02-15

On behalf of the OECD Working Party on Manufactured Nanomaterials (WPMN) an expert meeting on ecotoxicology and environmental fate of nanomaterials (NMs) took place in January 2013 in Berlin. At this meeting experts from science, industry and regulatory bodies discussed the applicability of OECD test guidelines (TGs) for chemicals to nanomaterials. The objective was to discuss the current state of the relevant science and provide recommendations to the OECD WPMN on (1) the need for updating current OECD TGs and the need for developing new ones specific to nanomaterials; and (2) guidance needed for the appropriate and valid testing of environmental fate and ecotoxicity endpoints for NMs. Experts at the workshop agreed that the majority of the OECD TG for chemicals were generally applicable for the testing of NM, with the exception of TG 105 (water solubility) and 106 (adsorption-desorption). Additionally, the workshop also highlighted considerations when conducting OECD chemical TG on nanomaterials (e.g., sample preparation, dispersion, analysis, dosimetry and characterisation). These considerations will lead to the future development of proposals for new TG and guidance documents (GDs) to ensure that OECD TG give meaningful, repeatable, and accurate results when used for nanomaterials. This report provides a short overview of topics discussed during the meeting and the main outcomes. A more detailed report of the workshop will become available through the OECD, however, due to the urgency of having OECD TG relevant for nanomaterials, this brief report is being shared with the scientific community through this communication. Copyright © 2013. Published by Elsevier B.V.

The OECD expert meeting on ecotoxicology and environmental fate — Towards the development of improved OECD guidelines for the testing of nanomaterials

International Nuclear Information System (INIS)

Kühnel, Dana; Nickel, Carmen

2014-01-01

On behalf of the OECD Working Party on Manufactured Nanomaterials (WPMN) an expert meeting on ecotoxicology and environmental fate of nanomaterials (NMs) took place in January 2013 in Berlin. At this meeting experts from science, industry and regulatory bodies discussed the applicability of OECD test guidelines (TGs) for chemicals to nanomaterials. The objective was to discuss the current state of the relevant science and provide recommendations to the OECD WPMN on (1) the need for updating current OECD TGs and the need for developing new ones specific to nanomaterials; and (2) guidance needed for the appropriate and valid testing of environmental fate and ecotoxicity endpoints for NMs. Experts at the workshop agreed that the majority of the OECD TG for chemicals were generally applicable for the testing of NM, with the exception of TG 105 (water solubility) and 106 (adsorption-desorption). Additionally, the workshop also highlighted considerations when conducting OECD chemical TG on nanomaterials (e.g., sample preparation, dispersion, analysis, dosimetry and characterisation). These considerations will lead to the future development of proposals for new TG and guidance documents (GDs) to ensure that OECD TG give meaningful, repeatable, and accurate results when used for nanomaterials. This report provides a short overview of topics discussed during the meeting and the main outcomes. A more detailed report of the workshop will become available through the OECD, however, due to the urgency of having OECD TG relevant for nanomaterials, this brief report is being shared with the scientific community through this communication. - Highlights: • OECD test guidelines (TGs) were developed for the testing of conventional chemicals. • Need for discussion on applicability of current TGs to nanomaterials • An expert meeting addressing this issue was held. • The focus was on TGs covering ecotoxicology and environmental fate. • Recommendations for updating current OECD

OECD sarjab II samba peatamist / Erik Müürsepp

Index Scriptorium Estoniae

Müürsepp, Erik

2009-01-01

OECD peab II pensionisamba maksete peatamist taunitavaks. OECD dokumendist, milles vaadeldakse praegu kriisiolukorda sattunud riikide käitumist pensionisüsteemi kujundamisel. Sotsiaalminister Hanno Pevkuri arvamus OECD soovituste kohta

The OECD/NEA/NSC PBMR 400 MW coupled neutronics thermal hydraulics transient benchmark: transient results - 290

International Nuclear Information System (INIS)

Strydom, G.; Reitsma, F.; Ngeleka, P.T.; Ivanov, K.N.

2010-01-01

The PBMR is a High-Temperature Gas-cooled Reactor (HTGR) concept developed to be built in South Africa. The analysis tools used for core neutronic design and core safety analysis need to be verified and validated, and code-to-code comparisons are an essential part of the V and V plans. As part of this plan the PBMR 400 MWth design and a representative set of transient exercises are defined as an OECD benchmark. The scope of the benchmark is to establish a series of well defined multi-dimensional computational benchmark problems with a common given set of cross sections, to compare methods and tools in coupled neutronics and thermal hydraulics analysis with a specific focus on transient events. This paper describes the current status of the benchmark project and shows the results for the six transient exercises, consisting of three Loss of Cooling Accidents, two Control Rod Withdrawal transients, a power load-follow transient, and a Helium over-cooling Accident. The participants' results are compared using a statistical method and possible areas of future code improvement are identified. (authors)

A critical study on the irradiated fuel transport containers

International Nuclear Information System (INIS)

Gualdrini, G.F.; Mancioppi, S.

1987-01-01

The report summarizes the work done by a NEA-CSNI Working Group devoted to the analysis of large arrays of Fissible Class II transport containers in order to assess: 1) codes validation criteria and safety margins; 2) large arrays and mixed arrays computations. The results have been obtained using several neutronic codes and various cross section libraries, available at ENEA

The long-term radiological safety of a surface disposal facility for low-level waste in Belgium - An international Peer review of key aspects of ONDRAF/NIRAS' safety report of November 2011 in preparation for the license

International Nuclear Information System (INIS)

2012-01-01

An important activity of the OECD Nuclear Energy Agency (NEA) in the field of radioactive waste management is the organisation of independent, international peer reviews of national studies and projects. This report provides an international peer review of the long-term safety strategy and assessment being developed by the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, ONDRAF/NIRAS, as part of the licence application for the construction and operation of a surface disposal facility for short-lived, low- and intermediate-level radioactive waste in the municipality of Dessel, Belgium. The review was carried out by an International Review Team comprised of seven international specialists, all of whom were free of conflict of interest and chosen to bring complementary expertise to the review. To be accessible to both specialist and non-specialist readers, the review findings are provided at several levels of detail

The strategic plan for the Committee on the Safety of Nuclear Installations

International Nuclear Information System (INIS)

2000-01-01

Following the request from the NEA that all the committees should develop Strategic Plans and the report of the Effectiveness Review Group (ERG) on the effectiveness of CSNI's activities, CSNI created a Strategic Planning Group to review their working processes. In developing a five year rolling Strategic Plan, the Group has considered the need for more top-down direction by CSNI, stricter control on time limited Task Groups and improved communications including timely review and publication of reports. The Strategic Planning Group, after reviewing the current work structure of CSNI and the current technical issues as laid out in the SESAR series of reports and the CNRA report on Regulatory Effectiveness, have made the following recommendations. The basic elements of the CSNI will continue to be the Principal Working Groups, which will be known in future simply as Working Groups. The number of Working Groups and their areas of expertise will be reviewed periodically when the strategic plan undergoes a review. It is recommended that this Plan be reviewed every five years. In order to provide better top-down direction by the CSNI, it is recommended that a small Programme Review Group (PRG) be created. The PRG will assist the CSNI Bureau to review proposals from the Working Groups, and enable the review of major reports to ensure high quality. To ensure timely management of projects and reviews of proposals and reports it is recommended that CSNI have a second full meeting in early summer. It is recommended that Special Expert Groups (SEGs) be created reporting directly to CSNI. These Groups would deal with issues that cut across the disciplines of more than one Working Group and be assigned clear time-limited mandates. The creation of SEGs on Fuel Safety Margins and on Human and Organisational Factors is proposed at this time. Restructuring of the five Principal Working Groups into four Working Groups is recommended. This would be accomplished by merging the former

Comparison report on OECD-CSNI containment standard problem N.1

International Nuclear Information System (INIS)

Winkler, W.

1980-05-01

The technical purpose of this containment standard problem N.1 was to compare experimental results of history of pressure, temperature, pressure difference and water mass after a steam line rupture within a chain of six subsequent compartments (simplified integral test) with the corresponding results of best-estimate post-test calculations from computer codes for three different time intervals. 11 countries took part in the comparison, using 11 different computer codes and several versions

Climate change policies in the OECD

International Nuclear Information System (INIS)

Staahle, C.

1993-01-01

The author focuses on the United Nations Conference on the Environment and Development (UNCED), held in 1992 in Rio de Janeiro, Brasil, and on carbon taxation. At the UNCED the Framework Convention on Climate Change was signed by 154 countries. This convention is intended to guide policy makers, and takes into account the great differences that exist between countries with regard to their ability to cater and pay for greenhouse gas emission reductions. It is pointed out that since 1985 the share of CO 2 emissions from non-OECD countries has exceeded that of OECD countries. An overview is given of stated OECD targets on CO 2 emission reductions. The global impact of reductions in OECD countries alone will be limited: if all targets are met, global emissions will be growing with 19% in the coming ten years, compared to 22% in a 'business-as-usual' scenario. It was noted that only very few OECD countries have developed action plans or implemented carbon taxes that could make their targets attainable. Details were given on carbon taxes now in place. It is concluded that no progress will be made if developing countries are not included in climate change policies. Also much work remains to be done in developed countries to meet emission reduction or stabilization targets. 3 figs., 4 tabs

NEA activities in preserving, evaluating and applying data from fast reactor experiments

International Nuclear Information System (INIS)

Gulliford, Jim; Cornet, S.M.; Hill, I.; Yamaji, A.

2013-01-01

Conclusions: Progress to date: • Extensive programme of work to preserve and evaluate data from integral experiments has been established since the mid 1990s. • NEA Data Bank maintains and distributes several databases of these integral experiments, notably through the ICSBEP and IRPhE projects. • More recently programmes of work have been established to help preserve data from the UK Fast Reactor Programme and from various experiments related to minor actinide management. • Data obtained from these programmes are made available to the nuclear science community to provide high quality benchmarks against which modelling methods can be validated. • Involvement of younger scientists and engineers to work alongside well-established experts in the process of evaluating the information is a highly efficient means of transmitting tacit knowledge to the new generation of nuclear specialists. Conclusions: Looking ahead - • Further development of Databases and Database tools, e.g. – improved coverage of fast reactor experiments, MAs; – improved treatment of correlations in uncertainties between experiments; – production of sensitivities to facilitate identification of similar experiments. • Continuation securing UK archives and creating framework for information: – Start identifying suitable integral experiments for inclusion in NEA databases

OECD Reviews of School Resources: Kazakhstan

Science.gov (United States)

Pons, Anna; Amoroso, Jeremie; Herczynski, Jan; Kheyfets, Igor; Lockheed, Marlaine; Santiago, Paulo

2015-01-01

This joint OECD-World Bank report for Kazakhstan forms part of the OECD Review of Policies to Improve the Effectiveness of Resource Use in Schools. The purpose of the Review is to explore how resources can be governed, distributed, utilised and managed to improve the quality, equity and efficiency of school education. School resources are…

Improving of health and safety contribution of OECD/NEA Radiation Protection Committee and Public Health

International Nuclear Information System (INIS)

Lazo, T.

2004-01-01

The OECD Nuclear energy Agency, has, since 1957, been addressing issues in radiological protection through its Committee on Radiation Protection and Public Health (CRPPH). The Committee is made up of regulators and radiation protection experts, with the broad mission to provide timely identification of new and emerging issues, to analyse their possible implications and to recommend or take action to address these issues to further enhance radiation protection regulation and implementation. The regulatory and operational consensus developed by the CRPPH on these emerging issues supports policy and regulation development in Member countries, and disseminates good practice. To best serve the needs of its Member countries, the CRPPH has been focusing its work in recent years on a few key topic areas. These induce the evolution of the system of radiological protection, the advancement of preparedness for nuclear emergency accidents, and the improvement of occupational exposure management at nuclear power plants. With the International Commission on Radiological Protection about to issue new recommendations, due out in 2005, the CRPPH will take advantage of the radiological protection community's recent focus on emerging policy and strategic issues to develop a new CRPPH Collective Opinion. This document, to be published in 2005, will serve the Committee as a guide for its programme of work for the coming 5 to 10 years. (Author) 13 refs

Over a decade of nuclear emergency management at the Nea

International Nuclear Information System (INIS)

Ahier, B.

2005-01-01

The OECD Nuclear Energy Agency has a long tradition of expertise in the area of nuclear emergency policy, planning, preparedness and management. Through its activities in this field, the Agency offers its member countries unbiased assistance on nuclear preparedness matters, with a view to facilitating improvements in nuclear emergency preparedness strategies and response at the international level. The 1986 Chernobyl accident demonstrated that nuclear accidents can have international consequences, highlighting the need for international co-operation, and leading to improvements in the areas of international communication, information exchange and harmonization of response actions between countries. From its inception, the NEA Working Party on Nuclear Emergency Matters has focused on improving the effectiveness of international nuclear emergency preparedness and management. Part of its work programme is set on exploring and developing new concepts and future procedures to enhance national and international preparedness and response management. A central approach to this has been the preparation and conduct of the International Nuclear Emergency Exercise (INEX) series. The role and strategies of exercises and future directions are discussed in this presentation. (A.L.B.)

Improving of health and safety contribution of OECD/NEA Radiation Protection Committee and Public Health; Mejora de la salud publica y la seguridad. contribuciones de la OECD/NEA, comite de Proteccion Radiologia y Salud Publica

Energy Technology Data Exchange (ETDEWEB)

Lazo, T.

2004-07-01

The OECD Nuclear energy Agency, has, since 1957, been addressing issues in radiological protection through its Committee on Radiation Protection and Public Health (CRPPH). The Committee is made up of regulators and radiation protection experts, with the broad mission to provide timely identification of new and emerging issues, to analyse their possible implications and to recommend or take action to address these issues to further enhance radiation protection regulation and implementation. The regulatory and operational consensus developed by the CRPPH on these emerging issues supports policy and regulation development in Member countries, and disseminates good practice. To best serve the needs of its Member countries, the CRPPH has been focusing its work in recent years on a few key topic areas. These induce the evolution of the system of radiological protection, the advancement of preparedness for nuclear emergency accidents, and the improvement of occupational exposure management at nuclear power plants. With the International Commission on Radiological Protection about to issue new recommendations, due out in 2005, the CRPPH will take advantage of the radiological protection community's recent focus on emerging policy and strategic issues to develop a new CRPPH Collective Opinion. This document, to be published in 2005, will serve the Committee as a guide for its programme of work for the coming 5 to 10 years. (Author) 13 refs.

Application examples of the reports of the NEA Incident Reporting System of the OECD and evolution of the system

International Nuclear Information System (INIS)

Libmann, J.

1989-06-01

Some reports of the work group no. 1 of the Nuclear Installations Security Committee of NEA, are summarized. An example of the report coding system concerning human factors, is given. The aim of the study is to improve the report contents as well as the coding system. In this case, a fast data selection is possible, and allows an efficient analysis of a particular situation. Moreover, the corrective procedures of the nuclear installation conception or operation can be easily modified, by the national organisations. Due to the improvements in quality, the opinion of the member countries on the incident reporting systems efficiency was enhanced [fr

OECD - kvaliteedimärk kogu riigile / Keit Kasemets

Index Scriptorium Estoniae

Kasemets, Keit

2010-01-01

Majanduskoostöö ja Arengu Organisatsiooni (OECD) liikme staatus loob Eesti majanduspoliitika ja teiste oluliste poliitikate arendamisel uusi võimalusi. OECD faktides, praegused liikmesriigid ja nende liitumisaeg

Summary and conclusions: Specialist Meeting on Severe Accident Management Implementation

International Nuclear Information System (INIS)

1995-01-01

During the first session of this meeting, regulators, research groups, designers/owners' groups and some utilities discussed the critical decisions in SAM (Severe Accident Management), how these decisions were addressed and implemented in generic SAM guidelines, what equipment and instrumentation was used, what are the differences in national approaches, etc. During the second session, papers were presented by utility specialists that described approaches chosen for specific implementation of the generic guidelines, the difficulties encountered in the implementation process and the perceived likelihood of success of their SAM programme in dealing with severe accidents. The third and final sessions was dedicated to discussing what are the remaining uncertainties and open questions in SAM. Experts from several OECD countries presented significant perspectives on remaining open issues

International seminar on the safety research needs for Russian-designed reactors: material presented at the international seminar 1997

International Nuclear Information System (INIS)

1997-01-01

This seminar on international, national and bilateral cooperation programmes on the safety research needs for Russian-designed reactors was held in Tokyo, Japan (1997) and hosted by the OECD Nuclear Energy Agency and the Science and Technology Agency (STA) of Japan. More than 70 participants attended the seminar. Represented were experts from OECD/NEA member countries and Russia, the International Atomic Energy Agency (IAEA), the ISTC, the INSC and the Russian INSC. Eighteen papers were presented in five sessions. The seminar was structured around four main areas of cooperation: cooperative programmes of the OECD/NEA, programmes of international organisations, bi-lateral programmes, and national programmes of OECD/NEA member countries having reactors of the VVER type. General conclusions, followed by specific technical conclusions are included

OECD environmental performance reviews: United States

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-01-15

This book presents OECD assessments and recommendations regarding the United States' efforts to manage its environment including air, water, nature, and biodiversity; to do this in a sustainable manner; and to do this in co-operation with its global neighbours. In particular, it assesses progress made since 1996, when OECD's previous review on the US was done. 47 figs., 20 tabs.

Nye OECD-retningslinjer for transfer pricing dokumentation

DEFF Research Database (Denmark)

Rossing, Christian Plesner

2015-01-01

er vedtaget, erstatte det nuværende kapitel V om transfer pricing dokumentation i ‘OECD Transfer Pricing Guidelines for Multinational Enterprises and Tax Administrations’. De gældende danske regler for transfer pricing dokumentation baserer sig på de eksisterende OECD-retningslinjer, og det må...

Pediatric Specialists

Science.gov (United States)

... Healthy Children > Family Life > Medical Home > Pediatric Specialists Pediatric Specialists Article Body ​Your pediatrician may refer your child to a pediatric specialist for further evaluation and treatment. Pediatric specialists ...

NEA activities in 1986

International Nuclear Information System (INIS)

1987-01-01

This report presents the main features of the Agency work during 1986. It deals with the response of NEA to the Chernobyl Accident; trends in Nuclear Power; Nuclear development and the fuel cycle; Nuclear safety research and licensing; radiation protection and waste management; legal affairs, nuclear science; joint undertakings and other NEA joint projects; information programmes; organization and administration

OECD ukse avamine tooks siia raha / Harry Tuul

Index Scriptorium Estoniae

Tuul, Harry

2007-01-01

Poola pensionifondid ei taha Eestisse investeerida, sest Eesti ei kuulu Majandusliku Koostöö ja Arengu Organisatsiooni. Vt. samas: OECD liikmeskond; Romet Kreek. OECD ukse avamine tooks siia raha. Kommenteerib Andre Nõmm

A review of the IEA/NEA Projected Costs of Electricity – 2015 edition

International Nuclear Information System (INIS)

Khatib, Hisham

2016-01-01

The IEA/NEA recently issued their eighth edition of the Study on the “Projected Costs of Generating Electricity” – 2015 edition. The Study is mainly concerned with calculating the levelised cost of electricity (LCOE). The LCOE calculations are based on a levelised average life time cost approach using the discounted cash flow (DCF) method. The analysis was this year, and for the first time, performed using three discount rates (3%, 7%, and 10%). The LCOE can serve as a tool for calculating the cost of different generation technologies. However the Study's usefulness is affected by its narrow base of a limited set of countries that are not necessarily representative. It ignored the negative role of subsidies and did not provide a methodology for selective application of the discount rates and costing of carbon. The global power generation scene is changing. Generation growth in OECD countries has become very limited; simultaneously there is rapid growth of varying renewables (VRE) generation which needs special criteria for assessing its system cost. All this demands a rethinking of the application and usefulness of the LCOE in future generation planning. - Highlights: • LCOE is a useful tool for economics of generation technologies. • The IEA/NEA study did not cover fully the required criteria for assessment. • It ignored interpretation of: the discount rate, carbon costing and subsidies. • The world energy scene is changing, this requires reassessment of LCOE.

The OECD and Global Governance in Education

Science.gov (United States)

Sellar, Sam; Lingard, Bob

2013-01-01

This review essay discusses the history, evolution and development of the Organisation for Economic Co-operation and Development (OECD) and traces the growing impact of its education work. The essay is in four main sections. The first discusses Carrol and Kellow's "The OECD: A Study of Organizational Adaptation" (Edward Elgar) and…

Education at a Glance 2010: OECD Indicators

Science.gov (United States)

OECD Publishing (NJ1), 2010

2010-01-01

Across OECD countries, governments are seeking policies to make education more effective while searching for additional resources to meet the increasing demand for education. The 2010 edition of "Education at a Glance: OECD Indicators" enables countries to see themselves in the light of other countries' performance. It provides a rich, comparable…

NEA Annual report 1997

International Nuclear Information System (INIS)

1998-01-01

The following issues are dealt with: 1997 in perspective. Trends in nuclear power. Technical programmes: Nuclear development and fuel cycle, nuclear safety and regulation, radiation protection, radioactive waste management, nuclear science, data bank, legal affairs, joint projects and other cooperative projects. General information: information programme, NEA publications produced in 1997, organization chart of NEA, workshops and meetings held in 1997. (R.P.)

OECD/NEA International Common Cause Failure Data Exchange (ICDE) project - insights and lessons learnt

International Nuclear Information System (INIS)

Johanson, G.; Kreuser, A.; Pyy, P.; Rasmuson, D.; Werner, W.

2006-01-01

Events initiated by common-cause-failure (CCF) can significantly affect the availability and reliability of nuclear power plant safety systems. In recognition of this, CCF data are systematically collected and analysed in the International Common-Cause Data Exchange (ICDE) Project, which was initiated in August 1994. Since April 1998, the NEA has formally operated the project. Currently eleven countries participate in the project. The ICDE collects all events where two or more identical, redundant components of a group, fulfilling the same function, have failed or were impaired due to a shared cause (ICDE events). Complete CCFs, i. e. failure of all identical, redundant components in the group due to a shared cause are an important subset of the collected data. Currently, data exchange and analysis covers the following components: centrifugal pumps, diesel generators, motor-operated valves, safety and relief valves, check valves, reactor protection system components (level measurement, control rod drives, etc), circuit breakers, and batteries. The main findings of the ICDE reports issued by 2005 show averaged over all components that about two thirds of all complete CCF events involve faulty actions by plant personnel and contractors. The single largest contribution is from faulty testing and maintenance work due to deficient and/or incomplete procedures. Other important causes are insufficient testing and requalification of components or systems after maintenance, repair, modifications or backfitting work, as well as operator errors of commission. The probability that a reported ICDE event is a complete CCF decreases strongly with increasing number of redundant components, demonstrating the effectiveness of redundancy as a powerful defence against CCFs. However, complete CCFs cannot be completely prevented by high redundancy only. (orig.)

Vabariigi president kohtus OECD peasekretäriga

Index Scriptorium Estoniae

2008-01-01

President Toomas Hendrik Ilves kohtus 12. veebruaril 2008 Tallinnas Majandusliku Koostöö ja Arengu Organisatsiooni (OECD) peasekretäri Angel Gurria'ga, tänades teda panuse eest organisatsiooni laienemispoliitika edendamisel. Ilmunud ka: Meie Kodu 20. veebr. 2008, lk. 3, pealk.: President Ilves kohtus OECD peasekretäriga (Allk. Kristel Peterson)

Nuclear Education and training: addressing a global need

International Nuclear Information System (INIS)

Dunn Lee, Janice

2008-01-01

There is growing concern about the difficulties nuclear institutions in many OECD/NEA member countries are experiencing in recruiting qualified specialists. Recent studies have also shown that nuclear education and training have been suffering declines of various degrees. If no action is taken on this issue, the nuclear sector risks facing a shortage of qualified human resources to ensure the appropriate regulation and operation of existing nuclear facilities as well as the construction of new ones in those countries wishing to do so. The NEA Steering Committee for Nuclear Energy issued a statement on this subject in October 2007, the complete text of which is available at: www.nea.fr/html/general/press/2007/2007-05.html. The NEA has for many years been involved in efforts to define and address the need for qualified human resources. In this regard, the Agency: 1- carries out assessments of requirements and availability of qualified human resources in the nuclear field, 2- enhances nuclear education programmes, such as the International School of Nuclear Law, and 3- encourages large, high-profile international research and development programmes. These areas are addressed in the NEA Strategic Plan as well as in the specific NEA programmes discussed below. The presentation will focus on ways to address the issue of qualified human resources, share information about what others are doing, and discuss what we might do collectively. (author)

Summary record of the experts meeting on the proposed OECD-IRSN STLOC project

International Nuclear Information System (INIS)

2004-01-01

The purpose of this meeting was to determine the interest in member countries for the types of LOCA tests envisaged in the STLOC programme proposed by IRSN. The IRSN proposal was circulated among this Group in advance of the meeting. After the presentations and discussions, the Group recommendations were as follows: different views were expressed as to the need to perform the LOCA integral tests; there was an understanding that the results of separate effect tests (ANL, JAERI, Halden) would need to be obtained before deciding on the intended LOCA tests proposed in STLOC; IRSN and the OECD-NEA should explore the possibility to run the first ST test with air ingress (STLOC1), for which partial funding already exists (this test is foreseen for 2008); the need of LOCA tests as envisaged in STLOC should be re-assessed in about three years time (2006); analytical and experimental progress on LOCA tests should be monitored until then, through for instance the SEGFSM. An executive summary of the IRSN Source term LOCA program LOCA part is given in an appendix

Safety, safety case and society - Lessons from the experience of the Forum on Stakeholder Confidence and other NEA initiatives

International Nuclear Information System (INIS)

Pescatore, Claudio

2014-01-01

A vast amount of literature on radioactive waste management (RWM) and its governance is available on the web page of the Radioactive Waste Management Committee of the OECD Nuclear Energy Agency (NEA), in particular on the pages of the Forum on Stakeholder Confidence (FSC), the Reversibility and Retrievability (R and R) Project and the Project on Records, Knowledge and Memory (RK and M) Preservation across Generations. The FSC literature alone likely represents the largest collection of literature on RWM governance presently available on any single site. The safety case developed for any deep geological repository project deals with technical safety. A license is to be granted based on the repository being, after closure, safe 'by itself', i.e. without the need to watch it, independent of the existence of the implementer, regulator and others. The main legal requirement of the safety case is that it needs to show convincingly that the technical regulatory criteria are met. The latter are both qualitative and quantitative. Qualitative criteria are technical, but not in a strong sense, e.g. one requirement may simply be the use of 'sound technical and managerial principles'. The safety case also needs to argue robustness upon human intrusion. The human intrusion analyses, however, are only used to make a qualitative judgement on the robustness of the system. The international guidance suggests that their results need not be tested, by the authorities, for compliance against a numerical yardstick. The technical regulator will have an important role in decision making, but others aside from the technical regulator will also play a decision-making role in the development of a repository project and with regard to its safety. For instance, the technical regulator is largely removed from the initial choice of site. Safety nowadays is brought about by a system of actors comprising the implementer, technical regulators, specialist groups in various advisory roles and the

Organisation of safety research programmes and infrastructure for existing reactors

International Nuclear Information System (INIS)

Micaelli, J.C.

2008-01-01

The author reviewed the main drivers of safety research, noting that challenging research is an excellent means to preserve know-how and professional skills. International efforts such the NEA-CSNI joint projects are an efficient means to support experimental infrastructure for safety research, while providing useful experimental results. Other initiatives, e.g. within the EU, aimed at developing networks of international expertise and infrastructure were also mentioned. (author)

Swedish analysis of NEA/CSNI benchmark problems for criticality codes

International Nuclear Information System (INIS)

Mennerdahl, D.

1984-08-01

The Monte Carlo methods used by the members of the working group are adequate for calculations on large arrays. The differences in the results from different codes are probably caused by the differences in cross sections. The previous difficulties in obtaining good results for bare arrays of UNH-solution are, at least to some extent, explained by incomplete information. The neutron reflection from walls, ceiling and floor has earlier been neglected. The inclusion of these in the input to the Monte Carlo codes appears to lead to adequate results. The basis for the IAEA rules of calculating allowable numbers of fissile packages mixed with other packages (fissile or not) during transport, does not seem justified. This has been demonstrated for theoretical package designs. It has not been confirmed by the other members of the working group and no conclusion was drawn by the group. It is very likely that a mix of real packages can be found that supports the mentioned theoretical demonstration. (author)

NEA Workshop on Stakeholder Involvement in Nuclear Decision Making, 17-19 January 2017, OECD Conference Centre, Paris, Room CC9

International Nuclear Information System (INIS)

Burns, Stephen G.; Yanush, Maryna; Jendroska, Jerzy; Beyens, Marc; Emmerechts, Sam; Touitou-Durand, Florence; Crosland, Martha; Ziakova, Marta; Nuclear Regulatory Authority of the Slovak Republic; Nuclear Regulation Authority; Ferapontov, Alexey; Hayano, Ryugo; Boyd, Mike; Mayall, Andrew; Tomkiv, Yevgeniya; Kawabuchi, Hideo; Kuenzi, Pascale; Shaver, Kathryn; Yngve Toernqvist, Johanna; Bjoerklund, Sara; Gerhardsson, Ansi; Kuenzi, Pascale; Birkhaeuser, Philip; Smith, Katherine; Katz, Sharonne; Vanhatalo, Hanna; Thome-Jassaud, Pierre-Franck; Bae, Su Hwan; Straub, Ralf; Gadano, Julian; Wolsink, Maarten; Komendantova, Nadejda; Kalaydjian, Francois; Harrington, Holly; Bouchot, Emmanuel; Runyon, Timothy; Gonzalez Herrero, Eva; Maclachlan, Ann

2017-01-01

Nuclear issues are embedded with broader societal issues such as the environment, risk management, energy and health policies, and sustainability. As such, nuclear projects often generate considerable interest and concern from stakeholders. In this context 'stakeholder' is intended to be taken in its broadest sense and should include concerned public, businesses, economic actors, NGOs, local, regional and national authorities, nuclear regulators, etc. Anyone who has relevant information, experience or concerns may seek to participate in the decision making process, and to interact with other stakeholders. Nuclear regulators, governments, operators, and other decision makers have a responsibility to ensure a high degree of transparency and to make clear and well-reasoned decisions. In this respect, there is an increasing demand for stakeholder involvement, participation and engagement. Across NEA member countries, many different approaches are taken to stakeholder involvement as decisions are made and implemented. Well-informed decisions broadly reflect the input of stakeholder views in a balanced fashion, the achievement of which can be difficult to assess. Attempts to achieve such broad understanding of views and acceptance of resulting decisions are an important part of building public confidence. Additionally, interested citizens, other stakeholders, and non-governmental organisations often call upon decision processes to be conducted in a manner that maintains public confidence. This workshop was not about what decision is made. Rather, it was about decision making processes used to reflect stakeholder concerns and input. How does one effectively involve stakeholders? How does one build and assess public confidence? How can broader stakeholder involvement help decision makers to make well-informed decisions that effectively address stakeholder views? On 17-19 January 2017, the NEA hosted a workshop on Stakeholder Involvement in Nuclear Decision Making

Review of OECD study into 'Projected costs of generating electricity-2010 Edition'

International Nuclear Information System (INIS)

Khatib, Hisham

2010-01-01

This joint report by the International Energy Agency (IEA) and the OECD Nuclear Energy Agency (NEA) is the seventh in the long established series of studies into electricity generating costs. It presents the main results of the work carried out in 2009 for calculating the costs of generating baseload electricity. The study is quite comprehensive in covering almost all financial aspects facing investors in the electricity generating system. Therefore this study although useful, its usefulness lies in explaining methodologies, mentioning factors that affect investment and cost, educating planners and improving investment evaluation and planning methodologies, its resulting figures and cost comparisons are however controversial. Generation planning and investments are case and country specific, and should be studied correspondingly and as close as possible to the timing of decision making to take account of trends. Most likely such case specific results will differ from figures calculated in the study. Therefore we need to emphasize a key conclusion of the study which is 'that country-specific circumstances determine the LCOE'; it is this that needs to be considered and not the results represented in the study.

10. national workshop of the NEA Forum on Stakeholder Confidence

International Nuclear Information System (INIS)

Martin, Kamishan; )

2017-01-01

The Forum on Stakeholder Confidence (FSC) was established by the NEA Radioactive Waste Management Committee (RWMC) in the year 2000. It fosters learning about stakeholder dialogue and ways to develop shared confidence, informed consent and acceptance of radioactive waste (RW) management solutions. A 'stakeholder' is defined as anyone with a role to play or an interest in the process of deciding about RW management. The FSC provides a setting for direct stakeholder exchange in an atmosphere of mutual respect and learning. Participating in this forum are government policy and regulatory officials, R and D specialists, implementers, and industry representatives from NEA member countries. Together they analyse, document and provide recommendations on today's and tomorrow's processes for embedding waste management programs into a socio-political decision-making context. The FSC convenes annually for a regular meeting and is often complemented by an FSC national workshop. The regular meetings include lectures and topical case study sessions to share experiences. FSC national workshops are organised in volunteer NEA member countries to bring together all the national stakeholders to provide a neutral ground for discussion, dialogue and advancement of knowledge on long-term radioactive waste management. FSC members and other international actors involved in RW management are invited to learn about the host country's waste management program and provide support by giving an external reflection built up on their own experience. They are often supplemented by a half a day devoted to a community visit (potential or selected site for a repository) or open event (public meeting or debate). 2016 marked the 10. national workshop of the FSC which took place in Switzerland. It focused on 'Bridging Gaps - Developing Sustainable Inter-generational Decision-making in Radioactive Waste Management'. The workshop provided a forum for the participants from around the world to learn from

NEA data bank

International Nuclear Information System (INIS)

1983-01-01

This paper is an introduction to the NEA data bank. The essential programs and data for nuclear energy calculations are available from the Data Bank. The Data Bank's role, in co-operation with other centers, is to protect the technological capital represented by the programs and data in its collection, which is unique in covering nearly the whole field of reactor physics at a single center (Saclay). The compilation and exchange of experimental and evaluated neutron and other nuclear data is carried out through a world-wide information network. The tasks now assigned to the Data Bank are in the areas of computer program packaging, neutron data compilation, assembly and benchmark testing of the Joint Evaluated File (JEF) of neutron cross-section data, and servicing the NEA scientific committees, as well as providing a computer service to the main NEA secretariat. In all areas the emphasis is on developing a ''value added'' element to the incoming data or computer codes, by validation documentation and presentation of information in a convenient standard form. The services offered by the Data Bank and the computers used by the Data Bank are presented

OECD Reviews of School Resources : Austria 2016

OpenAIRE

Theisens, Henno

2016-01-01

The effective use of school resources is a policy priority across OECD countries. The OECD Reviews of School Resources explore how resources can be governed, distributed, utilised and managed to improve the quality, equity and efficiency of school education. The series considers four types of resources: financial resources, such as public funding of individual schools; human resources, such as teachers, school leaders and education administrators; physical resources, such as location, buildin...

Analysis of differences in fuel safety criteria for WWER and western PWR nuclear power plants

International Nuclear Information System (INIS)

2003-11-01

In 2001 the OECD issued a report of the NEA/CSNI (Committee on the Safety of Nuclear Installations) Task Force on the existing safety criteria for reactor fuel for western LWR nuclear power plants (both for PWRs and BWRs) under new design elements. Likewise in 2001, the IAEA released a report by a Working Group on the existing safety criteria for reactor fuel for WWER nuclear power plants under new design requirements. However, it was found that it was not possible to compare the two sets of criteria on the basis upon which they had been established. Therefore, the IAEA initiated an assessment of the common features and differences in fuel safety criteria between plants of eastern and western design, focusing on western PWRs and eastern WWER reactors. Between October 2000 and November 2001, the IAEA organized several workshops with representatives from eastern and western European countries in which the current fuel safety related criteria for PWR and WWER reactors were reviewed and compared. The workshops brought together expert representatives from the Russian Federation, from the Ukraine and from western countries that operate PWRs. The first workshop focused on a general overview of the fuel safety criteria in order for all representatives to appreciate the various criteria and their respective bases. The second workshop (which involved one western and one eastern expert) concentrated on addressing and explaining the differences observed, and documenting all these results in preparation for a panel discussion. This panel discussion took place during the third workshop, where the previously obtained results were reviewed in detail and final recommendations were made. This report documents the findings of the workshops. It highlights the common features and differences between PWR and WWER fuel, and may serve as a general basis for the safety evaluation of these fuels. Therefore, it will be very beneficial for licensing activities for PWR and WWER plants, as it

The Nuclear Energy Agency: Strengthening Nuclear Safety Technology and Regulation Through Effective International Cooperation

International Nuclear Information System (INIS)

Nieh, H.

2016-01-01

The NEA provides an effective forum for international co-operation on nuclear safety and regulatory issues in its specific task groups, working parties and expert groups, as well as through joint international safety research projects. In these activities, NEA member countries work together to share and analyse data and experiences, gain consensus and develop approaches that can be applied within each country’s governmental processes. Through effective international co-operation, NEA member countries have worked together to develop actions for improving their regulatory frameworks and nuclear installation safety. As a result of these efforts, safety improvements and further harmonisation have been realized in the areas operating reactors, new reactors, human and organisational factors and nuclear safety research. At the NEA, technical and programmatic work under the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI), joint safety research projects and the Multinational Design Evaluation Programme (MDEP) have helped NEA member countries to ensure a high standard for nuclear safety and to further develop the technical knowledge base. (author)

FALSIRE. CSNI project for fracture analyses of large-scale international reference experiments. Phase 1

International Nuclear Information System (INIS)

Sievers, J.; Schulz, H.; Bass, B.R.; Pugh, C.E.; Keeney, J.

1994-04-01

The six experiments used in Project FALSIRE (performed in the Federal Republic of Germany, Japan, the United Kingdom, and the U.S.A.) were designed to examine various aspects of crack growth in reactor pressure vessel (RPV) steels under pressurized-thermal-shock (PTS) loading conditions. The CSNI/FAG established a common format for comprehensive statements of these experiments, including supporting information and available analysis results. For each experiment, analysis results provided estimates of variables such as crack growth, crack-mouth-opening displacement, temperature, stress, strain, and applied J and K values. A comparative assessment and discussion of the analysis results are presented; also, the current status of the entire results data base is summarized. Generally, these results highlight the importance of adequately modeling structural behavior of specimens before performing fracture mechanics evaluations. Applications of the various fracture methodologies were found to be partially successful in some cases but not in others. Based on these assessments, some conclusions concerning predictive capabilities of selected ductile fracture methodologies, as applied to RPVs subjected to PTS loading are given. (orig.)

The evolution of the system of radiological protection: the programme of the Nea committee on radiation protection and public health

International Nuclear Information System (INIS)

Mundigl, S.

2004-01-01

The primary aim of radiological protection has always been to provide an appropriate standard of protection for the public and workers without unduly limiting the beneficial practices giving rise to radiation exposure. Over the past few decades, many studies concerning the effects of ionising radiation have been conducted, ranging from those that examine the effects of radiation on individual cells, to epidemiological studies that examine the effects on large populations exposed to different radiation sources. Using information gained from these studies to estimate the consequences of radiation exposure, together with the necessary social and economic judgements, the International Commission on Radiological Protection (ICRP) has put forward a series of recommendations to structure an appropriate system for radiological protection, and to ensure a high standard of protection for the public and for occupational exposed workers. The ICRP system of radiological protection that has evolved over the years now covers many diverse radiological protection issues. Emerging issues have been dealt with more or less on an individual basis resulting in an overall system, which while very comprehensive, is also complex. With such a complex system it is not surprising that some perceived inconsistencies or incoherence may lead to concerns that radiation protection issues are not being adequately addressed. Different stakeholders in decisions involving radiological protection aspects tend to focus on different elements of this perceived incoherence. To advance solutions to these issues, the OECD Nuclear Energy Agency (NEA) has been working for some time to contribute to the evolution of a new radiological protection system, through its Committee on Radiation Protection and Public Health (CRPPH). This group of senior regulators and expert practitioners has, throughout its existence, been interested in the development of recommendations by the ICRP. Recently, this interest has

Eesti allkirjastas liitumislepingu OECD-ga

Index Scriptorium Estoniae

2010-01-01

Peaminister Andrus Ansip ja OECD peasekretär Angel Gurria allkirjastasid 3. juunil 2010. a. Stenbocki majas Eesti liitumislepingu. Samal päeval kohtus president Toomas Hendrik Ilves Angel Gurriaga Kadriorus

Safety research needs for Russian-designed reactors

International Nuclear Information System (INIS)

1998-01-01

In June 1995, an OECD Support Group was set up to perform a broad study of the safety research needs of Russian-designed reactors. This Support Group was endorsed by the CSNI. The Support Group, which is composed of senior experts on safety research from several OECD countries and from Russia, prepared this Report. The Group reviewed the safety research performed to support Russian-designed reactors and set down its views on future needs. The review concentrates on the following main topics: Thermal-Hydraulics/Plant Transients for VVERs; Integrity of Equipment and Structures for VVERs; Severe Accidents for VVERs; Operational Safety Issues; Thermal-Hydraulics/Plant Transients for RBMKs; Integrity of Equipment and Structures for RBMKs; Severe Accidents for RBMKs. (K.A.)

Líneas de Ensamble Auto-balanceables

OpenAIRE

Palomino Sánchez, José Manuel

2011-01-01

Este documento presenta una monografía de las líneas de ensamble auto-balanceables. Este tipo de líneas se han popularizado con la implementación de la manufactura esbelta en muchas empresas de diferentes ramos. Sin embargo, su estudio es aún incipiente, por lo que el objetivo de este proyecto es hacer una revisión de la literatura existente con el propósito de identificar posibles trabajos en esta área. Las líneas de ensamble auto-balanceables, también descritas en la literatura como Buck...

Regulatory inspection of nuclear power plants in NEA member countries

International Nuclear Information System (INIS)

Gronow, W.S.; Ilani, O.

1977-01-01

The increasing use of nuclear power and public interest in the safety controls led to the proposal by the sub-Committe on Licensing of the NEA Committee on the Safety of Nuclear Installations for a specialist meeting on regulatory inspection practices. This report which was prepared at the request of the sub-Committee to assist in the exchange of views and experience at the meeting reviews the response to a questionnaire on the systems employed, the scope and objectives and the effort involved in regulatory inspection throughout all stages of the life of a nuclear power plant. Other aspects of regulatory inspection activities are discussed including documentation, procedures for changes in technical specification and modifications to plant, powers and duties of regulatory inspection personnel and actions to be taken in the event of an accident or emergency. The report concludes with some comments on those aspects of regulatory inspection practices where further information and an exchange of experience might prove to be beneficial to Member countries. (author)

Looking Back, Looking Forward in Stakeholder Engagement. 10-year Anniversary Colloquium of the FSC, 15 September, OECD Conference Centre, Paris

International Nuclear Information System (INIS)

Pescatore, Claudio; Buser, Marcos; Kallenbach-Herbert, Beate; Brazier, David; Molina, Mariano; Blom, Catharina; Simic, Eva; Coadou, Jean; ); Beule, Karina de; Kotra, Janet P.; LE BARS, Yves; Gonzalez Hermosilla, Fernando; Heriard Dubreuil, Gilles; Zeleznik, Nadja; O'Connor, Martin; Lezaun, Javier; Hietanen, Leena; Koivisto, Katarina; Gas, Serge; Mathieu Carey; Massart, Cecile

2010-01-01

The OECD Nuclear Energy Agency (NEA) and its Radioactive Waste Management Committee (RWMC) proudly celebrate the 10. anniversary of the Forum on Stakeholder Confidence with a one-day open Colloquium in Paris. The Colloquium takes stock of FSC achievements, conducts a multi-stakeholder discussion of important themes in the governance of radioactive waste management, and gathers guidance on new directions to be taken by the FSC in coming years. The Colloquium welcomes some 80 participants: local and national opinion leaders and stakeholder representatives, government policy and regulatory officials, R and D specialists, implementers and industry representatives from 16 countries, and journalists. This report brings together the presentations (slides) given at this colloquium: 1 - Update since September 2009, The 10-year Anniversary Colloquium; Review of the RWMC and its working parties; Review of countries' input and RWMC project vision (C. Pescatore); 2 - State-of-the-art Report on Marker Systems for Radioactive Waste Repositories (M. Buser); 3 - Consideration of Social Scientific Aspects in a Safety Case for a Geological Repository in Germany, Results of a Research Project (B. Kallenbach-Herbert); 4 - Interplay Among Stakeholders for the Definition of the Detailed Geological Survey Zone in the Meuse/Haute-Marne (Andra); 5 - Regulatory Guidance on Retrievability (D. Brazier); 6 - Sogin engagement process 2010, Focus on involvement of economic operators as a part of the local community (Sogin); 7 - The role of the Government in territorial development of Meuse/Haute-Marne (Andra); 8 - Cooperating with regional elected authorities, some cases in Spain (M. Molina); 9 - Regional development and economic growth (C. Blom); 10 - Seeking transparency, Collective Action... (C. Pescatore); 11 - Introduction and overview of country responses to the transparency questionnaire (E. Simic); 12 - EC initiatives/support towards enhanced transparency and citizens participation

The SKI SITE-94 Project: An International Peer Review Carried out by an OECD/NEA Team of Experts

International Nuclear Information System (INIS)

Sagar, Budhi; Devillers, C.; Smith, Paul; Laliuex, P.; Pescatore, C.

1997-10-01

The recently completed SITE-94 project is an SKI effort directed at building competence and capacity in the assessment of safety of a spent-fuel geologic repository. Emphasis is given to the assimilation of site-specific data, with its associated uncertainties, into the performance assessment. Specific attention is also given to improving the understanding of mechanisms that might compromise canister integrity. This report represents the common views of an International Review Team (IRT) established by the NEA Secretariat, at the request of SKI, to perform a peer review of SITE-94. The basis for the report is the understanding of SITE-94 and its background obtained by IRT in the course of several months of study of SITE-94 documentation, internal discussions and a meeting with SKI in Stockholm. The report is limited to the main findings of IRT. The intended audience of the report is the staff of SKI and, accordingly, the style of the report is suited to a technical audience familiar with the contents of the SITE-94 project

NEA International Workshop on the Nuclear Innovation Road-map - NI2050. Workshop proceedings

International Nuclear Information System (INIS)

Ait Abderrahim, Hamid; Fernandez Fernandez, Alberto; Van Walle, Eric; Speranzini, Robert; Zezula, Lubor; Puska, Eija Karita; Tuomisto, Harri; Al Mazouzi, Abderrahim; Bazile, Fanny; Cordier, Pierre-Yves; Wahide, Carole; Tromm, Th. Walter; Horvath, Akos; Agostini, Pietro; Ambrosini, Walter; Kamide, Hideki; Nakatsuka, Toru; Sagayama, Yutaka; Tsujimoto, Kazufumi; Jeong, Ik; LEE, Gye Seok; Roelofs, Ferry; Van Der Lugt, Hermen; Wrochna, Grzegorz; Alekseev, Pavel; Andreeva-Andrievskaya, Lyudmila N.; Liska, Peter; Cizelj, Leon; Castelao Lopez, Carlos; Zimmermann, Martin; Rayment, Fiona; Pasamehmetoglu, Kemal; Martin Ramos, Manuel; Schmitz, Bruno; Monti, Stefano; Bignan, Gilles; Mcgrath, Margaret; Caron-Charles, Marylise; Magwood, William IV; Ha, Jaejoo; Deffrennes, Marc; Paillere, Henri; Noh, Jae Man; Gulliford, Jim; Breest, Axel; Matsumoto, Kiyoshi; Lebedev, Vladimir

2015-07-01

The two-day workshop held at the OECD Headquarters in Paris on 7-8 July 2015, brought together some of the leading experts in the field of nuclear fission research, development and demonstration. The purpose was to launch the NEA Nuclear Innovation 2050 Initiative, aiming, after a first survey phase, at producing a road-map of main priority research programs and infrastructures necessary to support the role nuclear energy may play in the low carbon power sector of the future. This might then further lead to some ad-hoc co-operation frameworks that help to effectively implement key priorities coming out of the road-mapping. The workshop was organised into the following five sessions: 1 - Opening session on NI2050: vision and main objectives; 2 - National presentations on nuclear fission research and innovation activities (programs, infrastructures, budgets); 3 - Presentations on some existing international nuclear fission road-maps and co-operation frameworks; 4 - Defining the way forward for NI2050: survey, road-mapping and priorities and co-operation; 5 - Open discussion. This document gathers the available presentations given at this workshop

Energy demand in seven OECD countries

International Nuclear Information System (INIS)

Patry, M.

1990-01-01

The intensity of utilization of energy has been declining in all OECD countries since the first oil price shock of 1973. In 1988, the OECD countries were consuming 1.7 billion tonnes of crude oil, that is two hundred million tonnes less than fifteen years ago. From 1974 to 1988, OECD oil consumption decreased at an average annual rate of 1.3% while the GDP of these countries rose by an average of 2.6% per annum. The authors present here a model of sectoral energy demand and interfuel substitution for the G-7 countries: Canada, France, Germany, Italy, Japan, the United Kingdom and the United States. The ultimate goal is to determine the relative importance of the contributing factors to the observed reversal in energy consumption per unit of production in these countries. The results they present should be viewed as preliminary. They point in the paper to a number of extensions that should improve the theoretical quality of the modeling effort and the statistical robustness of the results. They are presently expanding the data set to pinpoint more adequately the effects of structural change and conservation

Special Experts Meeting: Identifying and Overcoming Barriers to the Effective Consideration of Human and Organizational Factors in Event Analysis and Root Cause Analysis. Nuclear Energy Agency / Working Group on Human and Organizational Factors

International Nuclear Information System (INIS)

2011-01-01

The main mission of the Nuclear Energy Agency (NEA) Working Group on Human and Organisational Factors (WGHOF) is to improve the understanding and treatment of human and organisational factors (HOF) within the nuclear industry in order to support the continued safety performance of nuclear installations and improve the effectiveness of regulatory practices in member countries. WGHOF developed a CSNI (Committee on the Safety of Nuclear Installations) Activity Proposal Sheet (CAPS) outlining the work and milestones necessary towards achieving the following objectives: - Identify barriers to analyzing and correctly identifying the Human and Organisational Factors (HOF) causes of events; - Identify barriers to implementing lessons learned from these analyses; and - Develop recommendations for overcoming these barriers to: improve the identification of HOF causes of events and support the successful implementation of appropriate corrective actions The CAPS can be found in Appendix A. The first activity under the plan was the development of a questionnaire. This was distributed to WGHOF members and their counterparts from the Working Group on Operating Experience (WGOE). The questionnaire was comprised of 20 questions based on the objectives of the CSNI Activity Proposed Sheet. The intended survey participants were licensees with previous experience conducting root cause analyses. Responses were received from 26 respondents from 11 different countries. The results of the questionnaire were analyzed to identify themes for further discussion during a specialist meeting planned for September 2009. The following themes were presented during the WGHOF meeting in March of 2009 and endorsed for further work: - Roles and Influence of Senior Management, - Skills and Knowledge of the Investigators, - Qualitative Nature of HOF, - Influence of the Regulator, - Systematic Approach to Investigation. A summary of the questionnaire responses is provided in Appendix B

Practical Application of Art. 9 OECD Model Convention: the Czech Republic

Directory of Open Access Journals (Sweden)

Veronika Solilová

2014-01-01

Full Text Available All transfer prices determined between the associated enterprises must comply with the arm’s length principle. The arm’s length principle for associated enterprises is mentioned in Art. 9(1 of the OECD Model Convention, which was also adopted by the OECD Member states into their national law. However, not all OECD Member states adopted the next part of Art. 9, namely Art. 9(2, with the same way, some of them, like the Czech Republic, entered a reservation on Art. 9 (2 OECD Model Convention. In this paper the practical application of Art. 9 is analyzed from the point of view of the Czech Ministry of Finance, where the corresponding adjustment and time-limit issue are highlighted. On the basis of the results of analysis, where the history, context and purpose of Art. 9 OECD Model Convention have to be taken into account, are made some recommendations.

FDS5 Simulation for OECD PRISME Fire Test of DOOR PRSD5

International Nuclear Information System (INIS)

Lee, Kyu Bok; Park, Jong Seuk

2009-01-01

OECD/NEA PRISME Fire Project is an international co-operation project to investigate fire propagation by means of experiments and analyses for nuclear power plant applications. This project focuses on the generation of experimental data for fire and smoke propagation from the fire room to adjacent rooms under various conditions and room configurations. In addition, analyses using computer codes are performed to understand the phenomena of interest and to produce a consistent interpretation of the experimental results. The PRISME Project is composed of series of tests named as SOURCE, DOOR, LEAK and Global Tests. The SOURCE is composed of tests to characterize the fire source, and the DOOR is to study fire and smoke propagation through an open door, while the LEAK is to investigate hot gas leakages through other modes of openings such as holes, a slot, a duct, and a partially opened door. The Global test will be conducted as integral tests on the basis of the results of the previous separate effects tests. In this paper, simulations are performed with FDS5 computer code for the DOOR Test No.5 (PRS D 5) and the calculation results are compared with the corresponding experimental data to study the code capability to predict the phenomena of the hot gas propagation between two rooms

Energy statistics and balances of non-OECD countries 1991-1992

International Nuclear Information System (INIS)

1994-01-01

Contains a compilation of energy production and consumption statistics for 85 non-OECD countries and regions, including developing countries, Central and Eastern European countries and the former Soviet Union. Data are expressed in original units and in common units for coal, oil, gas, electricity and heat. Historical tables for both individual countries and regions summarize data on coal, gas and electricity production and consumption since 1971. Similar data for OECD are available in the IEA publications Energy Statistics and Energy Balances of OECD Countries

The NEA Nuclear Innovation 2050 Initiative

International Nuclear Information System (INIS)

Rayment, Fiona; ); Deffrennes, Marc; )

2017-01-01

The NEA launched its Nuclear Innovation 2050 (NI2050) Initiative with the aim of identifying research and development (R and D) strategies and associated priorities to achieve commercial readiness of innovative, sustainable nuclear fission technologies in a fast and cost-effective way. As defined at the beginning of the process, these R and D strategies would be elaborated with NEA stakeholders at large, in particular involving nearly all NEA committees, nuclear research organisations, industry, regulators and technical safety organisations. The NI2050 Initiative has evolved over the last year to become an NEA incubator for the selection and development of a number of large nuclear fission R and D programs (and infrastructures) that can support the role of nuclear energy in a low carbon future, mainly by accelerating innovation and the market deployment of technologies. This article provides a brief overview and the next steps of the initiative, which has reached the stage where more concrete outcomes might now be expected, in particular in terms of programs of action to be proposed for co-operative implementation

Overview of the OECD Halden reactor project

International Nuclear Information System (INIS)

Vitanza, C.

2000-01-01

The OECD Halden Reactor Project is an international network dedicated to enhancing the safety and reliability of nuclear power plants. The project operates under the auspices of the OECD Nuclear Energy Agency and aims at addressing and resolving issues relevant to safety as they emerge in the nuclear community. This paper gives a concise presentation of the project's goals and of its technical infrastructure. The paper also contains a brief overview of results from the ongoing programme and of the main issues contemplated for the next three-year programme period (2000-2002). (author)

Proceedings of the CSNI WGOE/SEGHOF workshop on modifications at nuclear power plants - Operating experience, safety significance and the role of human factors and organisation

International Nuclear Information System (INIS)

2004-01-01

Operating experience repeatedly shows that changes and modifications at nuclear power plants (NPPs) may lead to safety significant events. At the same time, modifications are necessary to ensure a safe and economic functioning of the NPPs. To ensure the continuing safety of NPPs it is important that processes for change and modification are given proper attention both by the NPPs and the regulators. The operability, maintainability and testability of every modification should be thoroughly assessed from different points of view to ensure that no safety problems are introduced. The OECD/NEA Committee on Safety of Nuclear Installations (CSNI) addressed the issue of modifications at a 'Workshop on Modifications at Nuclear Power Plants - Operating Experience, Safety Significance and Role of Human Factors' held at the OECD headquarters in Paris on October 6 to 8, 2003. This workshop was undertaken as a joint effort of the Working Group on Operating Experience (WGOE) and the Special Experts Group on Human and Organisational Factors (SEGHOF). During the workshop, WGOE focused on the theme of 'Minor Modifications and their Safety Significance', while SEGHOF focused on the topic 'Human and Organisational Factors in NPP Modifications'. The workshop was attended by 55 experts from the industry, regulators and technical support organizations in 15 countries. The workshop programme consisted of plenary and parallel sessions for presentations and discussions. One important part of the workshop was to discuss findings of the WGOE and SEGHOF surveys of utility and regulatory experience from modifications at the NPPs. Modifications at the NPPs are controlled by written procedures. The process varies depending on the type of the modification. Large modifications generally lead to fewer problems, because the projects are given both a great deal of attention and resources. In contrast, minor modifications seem to represent a generic challenge because they are less likely to be

OECD Halden Reactor Project

International Nuclear Information System (INIS)

1988-01-01

The OECD Halden Reactor project is an agreement between OECD member countries. It was first signed in 1958 and since then regularly renewed every third year. The activities at the Project is centred around the Halden heavy water rector, the HBWR. The reseach programme comprizes studies of fuel performance under various operating conditions, and the application of computers for process control. The HBWR is equipped for exposing fuel rods to temperatures and pressures, and at heat ratings met in modern BWR's and PWR's. A range of in-core instruments are available, permitting detailed measurements of the reactions of the fuel, including mechanical deformations, thermal behaviour, fission gas release, and corrosion. In the area of computer application, the studies of the communication between operator and process, and the surveillance and control of the reactor core, are of particular interst for reactor operation. 1988 represents the 30th year since the Project was started, and this publication is produced to mark this event. It gives and account of the activities and achievements of the Project through the years 1958-1988

International Standard Problems and Small Break Loss-of-Coolant Accident (SBLOCA

Directory of Open Access Journals (Sweden)

N. Aksan

2008-01-01

Full Text Available Best-estimate thermal-hydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors. Evaluation of the capabilities and the performance of these codes can be accomplished by comparing the code predictions with measured experimental data obtained on different test facilities. OECD/NEA Committee on the Safety of Nuclear Installations (CSNI has promoted, over the last twenty-nine years, some forty-eight international standard problems (ISPs. These ISPs were performed in different fields as in-vessel thermal-hydraulic behaviour, fuel behaviour under accident conditions, fission product release and transport, core/concrete interactions, hydrogen distribution and mixing, containment thermal-hydraulic behaviour. 80% of these ISPs were related to the working domain of principal working group no.2 on coolant system behaviour (PWG2 and were one of the major PWG2 activities for many years. A global review and synthesis on the contribution that ISPs have made to address nuclear reactor safety issues was initiated by CSNI-PWG2 and an overview on the subject of small break LOCA ISPs is given in this paper based on a report prepared by a writing group. In addition, the relevance of small break LOCA in a PWR with relation to nuclear reactor safety and the reorientation of the reactor safety program after TMI-2 accident are shortly summarized. The experiments in four integral test facilities, LOBI, SPES, BETHSY, ROSA IV/LSTF and the recorded data during a steam generator tube rupture transient in the DOEL-2 PWR (Belgium were the basis of the five small break LOCA related ISP exercises, which deal with the phenomenon typical of small break LOCAs in Western design PWRs. Some lessons learned from these small break LOCA ISPs are identified in relation to code deficiencies and capabilities, progress in the code capabilities, possibility of scaling, and various additional aspects

OECD - HRP Summer School on Light Water Reactor Structural Materials. August 26th - 30th, 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

In cooperation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on Light Water Reactor Structural Materials in the period August 26 - 30, 2002. The summer school was primarily intended for people who wanted to become acquainted with materials-related subjects and issues without being experts. It is especially hoped that the summer school served to transfer knowledge to the ''young generation'' in the field of nuclear. Experts from Halden Project member organisations were solicited for the following programme: (1) Overview of The Nuclear Community and Current Issues, (2) Regulatory Framework for Ensuring Structural Integrity, (3) Non-Destructive Testing for Detection of Cracks, (4) Part I - Basics of Radiation and Radiation Damage, (5) Part II - Radiation Effects on Reactor Internal Materials, (6) Water Chemistry and Radiolysis Effects in LWRs, (7) PWR and Fast Breeder Reactor Internals, (8) PWR and Fast Breeder Reactor Internals, (9) Secondary Side Corrosion Cracking of PWR Steam Generator Tubes, (10) BWR Materials and Their Interaction with the Environment, (11) Radiation Damage in Reactor Pressure Vessels.

OECD - HRP Summer School on Light Water Reactor Structural Materials. August 26th - 30th, 2002

International Nuclear Information System (INIS)

2002-01-01

In cooperation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on Light Water Reactor Structural Materials in the period August 26 - 30, 2002. The summer school was primarily intended for people who wanted to become acquainted with materials-related subjects and issues without being experts. It is especially hoped that the summer school served to transfer knowledge to the ''young generation'' in the field of nuclear. Experts from Halden Project member organisations were solicited for the following programme: (1) Overview of The Nuclear Community and Current Issues, (2) Regulatory Framework for Ensuring Structural Integrity, (3) Non-Destructive Testing for Detection of Cracks, (4) Part I - Basics of Radiation and Radiation Damage, (5) Part II - Radiation Effects on Reactor Internal Materials, (6) Water Chemistry and Radiolysis Effects in LWRs, (7) PWR and Fast Breeder Reactor Internals, (8) PWR and Fast Breeder Reactor Internals, (9) Secondary Side Corrosion Cracking of PWR Steam Generator Tubes, (10) BWR Materials and Their Interaction with the Environment, (11) Radiation Damage in Reactor Pressure Vessels

Nuevo método de sutura subcutánea percutánea continua New method of continuous percutaneous subcutaneous suture

Directory of Open Access Journals (Sweden)

Germán Brito Sosa

2012-06-01

Full Text Available Objetivos: realizar un método de sutura continua, en las personas operadas en el Hospital "Julio Trigo López", que disminuya los granulomas a nivel de la herida quirúrgica, y compararlas con el método tradicional. Métodos: se realizó un estudio experimental sobre la aplicación de un método de sutura subcutánea percutánea continua, en un grupo de pacientes operados de diversas enfermedades, ya sea de urgencia, electivo o ambulatorio, en el Hospital "Julio Trigo López", en los años 2008 y 2009. Resultados: con el método de sutura subcutánea percutánea continua con nylon no se forman granulomas, mientras que con el método tradicional, sí ocurre en un porcentaje no despreciable. Las ventajas del método de sutura subcutánea percutánea continua con nylon son: en el plano celular subcutáneo de la pared abdominal no queda sutura, no se producen granulomas y es más económica. Conclusiones: la sutura de nylon es menos rechazada que la del cromado, ya que no se producen granulomas. El método de sutura subcutánea percutánea continua es una sutura más hemostática que el método tradicional, ya que el por ciento de hematomas es menor. El gasto económico es menor con el método de sutura subcutánea percutánea continua. Con el método de sutura subcutánea percutánea continua la sutura es extraída al 10mo. día de haberla aplicado.Objectives: to apply a continuous suture method to reduce granulomas in surgical wounds in patients operated on at "Julio Trigo Lopez" hospital, and to compare the results with those of the traditional method. Methods: an experimental study was conducted on the application of a continuous percutaneous subcutaneous suture in a group of patients operated on from several diseases, either under emergency, elective or outpatient conditions at "Julio Trigo Lopez" hospital during 2008 and 2009. Results: the continuous percutaneous subcutaneous suture method with nylon prevents formation of granulomas, whereas

Education and Obesity in Four OECD Countries. OECD Education Working Papers, No. 39

Science.gov (United States)

Sassi, Franco; Devaux, Marion; Church, Jody; Cecchini, Michele; Borgonovi, Francesca

2009-01-01

An epidemic of obesity has been developing in virtually all OECD countries over the last 30 years. Existing evidence provides strong suggestions that such epidemic has affected certain social groups more than others. In particular, education appears to be associated with a lower likelihood of obesity, especially among women. A range of analyses of…

Improvements to SFCOMPO - a database on isotopic composition of spent nuclear fuel

International Nuclear Information System (INIS)

Suyama, Kenya; Nouri, Ali; Mochizuki, Hiroki; Nomura, Yasushi

2003-01-01

Isotopic composition is one of the most relevant data to be used in the calculation of burnup of irradiated nuclear fuel. Since autumn 2002, the Organisation for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA) has operated a database of isotopic composition - SFCOMPO, initially developed in Japan Atomic Energy Research Institute. This paper describes the latest version of SFCOMPO and the future development plan in OECD/NEA. (author)

The (New) OECD Jobs Study: Introduction and Assessment

OpenAIRE

Alfred Stiglbauer

2006-01-01

In 1994, the OECD presented the Jobs Study analyzing the causes of high unemployment in Europe. The study identified inappropriate labor market regulations and legislation as a key determinant of high unemployment. The OECD recommended deregulation and liberalization of labor market institutions as a remedy. Meanwhile, new empirical research has explored the influence of labor market institutions on unemployment and has only partly confirmed the recommendations of the Jobs Study. In a reevalu...

Japan and the OECD - a lesson for Romania

OpenAIRE

Iustina Luţan

2007-01-01

The Organisation for Economic Co-operation and Development (OECD) is a unique forum where the governments of 30 market democracies work together to address the economic, social and governance challenges of globalisation as well as to exploit its opportunities. One of the most important advantages of the OECD over other intergovernmental organizations or academia is the fact that the work, expertise, and know-how is transferred from a wide range of participants, like member countries, senior o...

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

International Nuclear Information System (INIS)

1983-03-01

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

Overview of the OECD-Halden reactor project

International Nuclear Information System (INIS)

Vitanza, Carlo

2001-01-01

The OECD Halden Reactor Project is an international network dedicated to enhanced safety and reliability of nuclear power plants. The Project operates under the auspices of the OECD Nuclear Energy Agency and aims at addressing and resolving issues relevant to safety as they emerge in the nuclear community. This paper gives a concise presentation of the Project goals and of its technical infrastructure. The paper contains also a brief overview of results from the programme carried out in the time period 1997-1999 and of the main issues contemplated for the 3-year programme period 2000-2002

Increased Accident Tolerance of Fuels for Light Water Reactors - Workshop Proceedings, OECD/NEA Headquarters, Issy-les-Moulineaux, France, 10-12 December 2012

International Nuclear Information System (INIS)

2013-01-01

The Fukushima accident in March 2011 raised concerns about the safety of current and future nuclear power plants both inside and outside the international nuclear energy community. With a view to learning lessons from this accident a large consensus emerged on the need to strengthen each level of Defence-In-Depth, reinforcing both prevention and mitigation. The fuel performance characteristics identified as being central to increased accident tolerance for long-term loss of coolant include reduced clad-steam reactions, reduced hydrogen production and improved fission product retention. New fuel designs which offered the potential to incorporate these characteristics, while retaining the operational performance of existing designs, would therefore be considered as suitable candidates for further investigation. Under the auspices of the NEA Nuclear Science Committee, a workshop has been organised to bring together international experts from the modelling, safety, operations and regulatory technical disciplines to discuss the various issues related to increased accident tolerance of fuels for Light Water Reactors and to help establish a co-ordinated international approach in this field. The organisation of this workshop was also supported by the NEA Committee on the Safety of Nuclear Installations. These proceedings include all the abstract papers presented at this workshop. The programme was comprised of 4 sessions: - Session 1: Lessons learned from the Fukushima accident; - Session 2: Accident-tolerant fuel design; - Session 3: Reactor operation, safety, fuel cycle constraints, economics and licensing; - Session 4: Synthesis and future programmes. A total of 55 participants from 16 countries attended the workshop, with 26 technical presentations and 2 breakout parallel sessions (one on safety issues, the other on reactor performance, R and D and technological issues). The attendees represented a broad spectrum of stakeholders involved in different nuclear energy

Infectious Disease Specialist: What Is an Infectious Disease Specialist?

Science.gov (United States)

... medical professionals? When do I need an ID specialist? Many common infections can be treated by your ... diseases. Back to Top How was my ID specialist trained? Your ID Physician has 9-10 years ...

OECD Trilog Plenary Symposium : public policy issues in global freight logistics

Science.gov (United States)

1998-01-01

This is the fifth plenary symposium on public policy issues in global freight logistics conducted by the Organization for Economic Cooperation and Development (OECD). OECD's Trilateral Logistics Project, Trilog Project, is aimed at clarifying the pub...

OECD BEPS: Reconciling global trade, taxation principles and the digital economy

OpenAIRE

Lee-Makiyama, Hosuk; Verschelde, Bert

2014-01-01

Following media reports on the low tax rates paid by some of the world's largest multinationals, international tax reform has moved to the top of policy-makers' agendas across the world. At the request of the G20, the OECD has designed an action plan to address what it calls base erosion and profit shifting (BEPS) - namely that the corporate tax base is eroding due to the internet. However OECD itself admits there is no evidence of base erosion in reality. Nonetheless, some OECD and EU Member...

Assessment of multi-dimensional analysis cacpacity of the MARS using the OECD-SETH PANDA tests

International Nuclear Information System (INIS)

Bae, S. W.; Jung, J. J.; Jung, B. D.

2004-01-01

The objectives of OECD/NEA-PANDA tests are to validate and assess computer codes that analyze the non-condensable gas concentrations and mixing phenomena in a reactor containment building. Especially, the main issue is multi-dimensional analysis capability which is involved in the mixing of non-condensable gases, i. e. hydrogen. The main tests consist of a superheated steam flow injection into a large vessel initially filled with air or air/helium mixtures. Then the temperature and concentration of noncondensable gases are measured. A pre-calculation has been performed with the MARS about PANDA Tests even though MARS is not a containment analysis code. Three cases among 25 PANDA Tests are selected and are modeled to simulate the jet plumes and air mixing in a large vessel. The dimensions of large vessel are 4 m diameter and 8 m height. For the conclusion of calculation, the cylindrical vessel which dimensions are 4 m diameter and 8 m height was simplified as rectangular geometry. It is revealed that the MARS code has the capability to distinguish the multi-dimensional distribution of the velocity and the temperature fields

OECD, "Key Competencies" and the New Challenges of Educational Inequality

Science.gov (United States)

Takayama, Keita

2013-01-01

In this paper, I develop a critique of the Organization for Economic Cooperation and Development (OECD)-based lifelong learning policy discourse with a particular focus on "key competencies" (KCs) and its equity implications for school curricular policies. First, I review the discussion of KCs in the writings by the OECD-affiliated…

Human exploration of NEA: why and how?

Science.gov (United States)

Viscio, M. A.; Casacci, C.; Ferro, C.

The human exploration of multiple deep space destinations, and among them Near Earth Asteroids (NEA), in view of the final challenge of sending astronauts to Mars, represents a current and consistent study domain. NEAs represent interesting targets, not only for the high level scientific return of such missions, but also for advanced technologies demonstration. Accordingly, the NEA mission described in this paper is conceived as an intermediate step before a human mission to the Red Planet and, in this regard, several technologies required for Mars are implemented, in order to test and validate them in significant environment, but at a closer and easier destination. Another crucial aspect to be considered, when dealing with asteroids, is related to planetary defense: even if the probability of an impact with the Earth is very low, this possibility does actually exist. A human mission as the one described in this paper would represent a chance for the development and test of technologies and techniques to be used for asteroid collision avoidance. The paper starts discussing the main objectives of a NEA mission, highlighting the benefits of the human presence. A reference human mission is then described, in terms of strategy, architecture and concept of operations, with particular attention to NEA collision avoidance issue. In the last part, the idea of exploiting virtual reality in support of the mission definition and execution is discussed.

Simulation codes and the impact of validation/uncertainty requirements

International Nuclear Information System (INIS)

Sills, H.E.

1995-01-01

Several of the OECD/CSNI members have adapted a proposed methodology for code validation and uncertainty assessment. Although the validation process adapted by members has a high degree of commonality, the uncertainty assessment processes selected are more variable, ranaing from subjective to formal. This paper describes the validation and uncertainty assessment process, the sources of uncertainty, methods of reducing uncertainty, and methods of assessing uncertainty.Examples are presented from the Ontario Hydro application of the validation methodology and uncertainty assessment to the system thermal hydraulics discipline and the TUF (1) system thermal hydraulics code. (author)

Quarterly coal statistics of OECD countries

Energy Technology Data Exchange (ETDEWEB)

1992-04-27

These quarterly statistics contain data from the fourth quarter 1990 to the fourth quarter 1991. The first set of tables (A1 to A30) show trends in production, trade, stock change and apparent consumption data for OECD countries. Tables B1 to B12 show detailed statistics for some major coal trade flows to and from OECD countries and average value in US dollars. A third set of tables, C1 to C12, show average import values and indices. The trade data have been extracted or derived from national and EEC customs statistics. An introductory section summarizes trends in coal supply and consumption, deliveries to thermal power stations; electricity production and final consumption of coal and tabulates EEC and Japanese steam coal and coking coal imports to major countries.

A survey of different regulatory practices

International Nuclear Information System (INIS)

1975-01-01

Draft survey of legislation governing the licensing of nuclear installations in OECD Member countries prepared by a Sub-Committee on Licensing for the OECD/NEA Committee on the Safety of Nuclear Installations. (author)

Occupational radiation exposure trends in the nuclear industry of NEA/IAEA Member States

International Nuclear Information System (INIS)

Ilari, O.; Horan, J.R.; Franzen, F.L.

1980-01-01

After various introductory statements on current occupational radiation exposure trends in nuclear facilities, the authors briefly discuss the problems involved in the application of the ICRP principle of optimization of radiological protection to the design and, in particular, the operation of nuclear plants, with the aim of comparing present exposure trends. To assemble an adequate data base for supporting the technical studies required to optimize radiological protection, the OECD Nuclear Energy Agency and the International Atomic Energy Agency have launched a survey aimed at collecting information on the levels and trends of occupational radiation exposure in the nuclear industry. The features of this study, based on the answers of NEA/IAEA Member States to a questionnaire, are described. The first results of the survey, regarding the situation and time trends of the average individual dose equivalents and collective dose equivalents for different plant types and for several countries, are also given. A preliminary analysis of the data collected allows certain considerations to be made relating to the influence of size, age and plant type, as well as of different national practices in plant operation and maintenance. (author)

A Simulation Study about OECD-SETH PANDA Tests by using MARS Code

International Nuclear Information System (INIS)

Bae, Sung Won; Chung, Bub Dong

2007-04-01

Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-Of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. In addition, the multi-D module component has been developed to meet the expand the multi-dimensional analysis capability of MARS. Participating in OECD-SETH, MARS provides and undergoes the assess procedure of comercial CFD codes, like FLUENT, CFX, etc. During the participation, MARS has been used to provide the system code results, which is made with the intermediate length scale, restricted analysis volume numbers. With these restrictions and shortcomings, MARS predicts well about the steam concentration distribution and mixture temperature in the large multi-comparted bulk spaces. After the SETH project, NEA has planned the SETH II, which deals with the multiple non-condensible gas stratification and mixing phenomena

Observations of NEAs at Arecibo Observatory and NASA's IRTF: Combining Radar and Thermal Measurements to Better Understand NEA Physical Properties

NARCIS (Netherlands)

Nolan, Michael C.; Vervack, R. J.; Howell, E. S.; Magri, C.; Fernandez, Y. R.; Taylor, P. A.; Mueller, M.; Rivkin, A. S.; Benner, L. A. M.

2010-01-01

As we sample ever-smaller sizes of near-Earth asteroids (NEAs), we see an increasing variation in the range of physical properties. Radar experiments show a diverse range of shapes, surface features, and rotation states among NEAs. Infrared observations of these objects are equally varied,

Generation 4 and the Nea

International Nuclear Information System (INIS)

Dujardin, T.

2002-01-01

In the previous edition of NEA News, W. D. Magwood of the US Department of Energy (DOE) outlined the future of nuclear energy in the context of the new US national energy policy. He cited the Generation IV initiative as a mechanism to implement a longer-term aspect of this policy. Although initiated in the US, the Generation IV initiative has quickly become an international effort and today ten countries are participating in the Generation IV International Forum (GIF). This article briefly reviews the context of Generation IV and describes NEA involvement in the Generation IV process. (author)

Budget reform in Ukraine and the OECD countries

Directory of Open Access Journals (Sweden)

Puchko Anna

2016-09-01

Full Text Available The article analyzes the fiscal reforms in Ukraine and the OECD countries. It has been proved that the main areas which should undergo changes are the tax reform, regulatory reform and restructuring policies to encourage entrepreneurship, reform of social protection and social security, reform of social sphere constituents, administrative reform, reform of the army and law enforcement, administrative and territorial reform. According to the analysis results, there has been drawn the conclusion about the need to introduce in Ukraine the successful experience of the OECD countries in implementing budget reforms.

Nuclear power: A competitive option? Annex 3

International Nuclear Information System (INIS)

Bertel, E.; Wilmer, P.

2002-01-01

Because the future development of nuclear power will depend largely on its economic performance compared to alternatives, the OECD Nuclear Energy Agency (NEA) investigates continuously the economic aspects of nuclear power. This paper provides key findings from a series of OECD studies on projected costs of generating electricity and other related NEA activities. It addresses the cost economics necessary for nuclear units to be competitive, and discusses the challenges and opportunities currently faced by nuclear power. (author)

Inequality in OECD countries.

Science.gov (United States)

Thévenot, Celine

2017-08-01

This article recalls the state of play of inequality levels and trends in OECD countries, with a special focus on Nordic countries. It sheds light on explaining the drivers of the rise in inequality and its economic consequences. It addresses in particular the issue of redistribution through taxes and transfers. It concludes with an overview of policy packages that should be considered to address the issue of rising inequalities.

Aspectos nutricionales de la dieta mediterránea

OpenAIRE

Mariné Font, Abel; Vidal, M. Carmen

1999-01-01

Se realiza un anàlisis de los orígenes de la dieta mediterránea, los cuales se remontan a las grandes culturas clásicas de la Edad Antigua. Además, se describe lo que hoy en dia cabe entender como dieta mediterránea y se analiza el valor nutritivo de los alimentos que integran los diversos tipos de dietas mediterrdneas. Finalmente, se realizan algunas consideraciones sobre la bondad de la dieta mediterránea, que, sin ser una panacea, es lo suficientemente equilibrada y agradable para consider...

JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Selection of thermodynamic data of selenium

International Nuclear Information System (INIS)

Doi, Reisuke; Kitamura, Akira; Yui, Mikazu

2010-02-01

Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level and TRU radioactive wastes, the selection of the thermodynamic data on the inorganic compounds and complexes of selenium was carried out. Selection of thermodynamic data of selenium was based on a thermodynamic database of selenium published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). The remarks of a thermodynamic database by OECD/NEA found by the authors were noted in this report and then thermodynamic data was reviewed after surveying latest literatures. Some thermodynamic values of iron selenides were not selected by the OECD/NEA due to low reliability. But they were important for the performance assessment of geological disposal of radioactive wastes, so we selected them as a tentative value with specifying reliability and needs of the value to be determined. (author)

Results from the Application of Uncertainty Methods in the CSNI Uncertainty Methods Study (UMS)

International Nuclear Information System (INIS)

Glaeser, H.

2008-01-01

Within licensing procedures there is the incentive to replace the conservative requirements for code application by a - best estimate - concept supplemented by an uncertainty analysis to account for predictive uncertainties of code results. Methods have been developed to quantify these uncertainties. The Uncertainty Methods Study (UMS) Group, following a mandate from CSNI, has compared five methods for calculating the uncertainty in the predictions of advanced -best estimate- thermal-hydraulic codes. Most of the methods identify and combine input uncertainties. The major differences between the predictions of the methods came from the choice of uncertain parameters and the quantification of the input uncertainties, i.e. the wideness of the uncertainty ranges. Therefore, suitable experimental and analytical information has to be selected to specify these uncertainty ranges or distributions. After the closure of the Uncertainty Method Study (UMS) and after the report was issued comparison calculations of experiment LSTF-SB-CL-18 were performed by University of Pisa using different versions of the RELAP 5 code. It turned out that the version used by two of the participants calculated a 170 K higher peak clad temperature compared with other versions using the same input deck. This may contribute to the differences of the upper limit of the uncertainty ranges.

NEA Activities in 1988

International Nuclear Information System (INIS)

Anon.

1989-01-01

The following topics are developed: trends in nuclear power; nuclear development and the fuel cycle; nuclear safety and licensing; radiation protection; radioactive waste management; legal affairs; nuclear science; NEA joint projects; information programmes

Specialist Bibliographic Databases

OpenAIRE

Gasparyan, Armen Yuri; Yessirkepov, Marlen; Voronov, Alexander A.; Trukhachev, Vladimir I.; Kostyukova, Elena I.; Gerasimov, Alexey N.; Kitas, George D.

2016-01-01

Specialist bibliographic databases offer essential online tools for researchers and authors who work on specific subjects and perform comprehensive and systematic syntheses of evidence. This article presents examples of the established specialist databases, which may be of interest to those engaged in multidisciplinary science communication. Access to most specialist databases is through subscription schemes and membership in professional associations. Several aggregators of information and d...

OECD Halden Reactor Project

International Nuclear Information System (INIS)

1983-01-01

The OECD Halden Reactor Project is both the oldest and the only one still in operation of the three major joint undertakings established at the inception of the OECD Nuclear Energy Agency. This publication has been printed in connection with its twenty-fifth anniversary as an international project. After presentation of the history and organization of the project, a thorough description of the past and present activities in the field of fuel performance and process control and surveillance is given. The projects's fuel testing programme is now focuessed on an investigation to define safety margins under normal operations as well as under various kinds of accident situations. Fuel research is also concerned with the characterisation of long term effects with regard to efficiency, operational safety and mapping of reliability and durability in the case of accidents with loss of coolant. In the field of process control and surveillance, research work is directly linked to the use of computers and colour graphics as tools in the control room. A fullscale simulator-based model and experimental control room has been constructed. The first experiments to be carried out in this laboratory will investigate the advantage of analysing alarms before they are presented to the operator. (RF)

OECD Policy Recommendations on Security for Biological Materials

International Nuclear Information System (INIS)

Radisch, J.

2007-01-01

Biomedical innovations derived from research on pathogenic micro-organisms promise astounding health and economic benefits. Some such biological resources employed in the RandD for diagnostic kits, vaccines and therapeutics, however, possess capacity for dual-use; they may be misused to develop biological weapons. Research facilities entrusted with possession of such dual-use materials have a responsibility to comply with biosecurity measures that are designed to prevent loss or theft and thereby reduce the probability of a bioterrorist attack. The OECD has provided a forum for its Member countries to engage in a dialogue of international co-operation with a view to produce policies that achieve a research environment fortified by biosecurity measures and capable of producing health innovations. In 2007, the OECD developed a risk assessment framework and risk management principles for Biological Resource Centres. Ongoing policy work at the OECD will look to design biosecurity guidelines appropriate to a broader range of facilities in possession of dual-use materials, such as university and industrial laboratories.(author)

First EURONEAR NEA discoveries from La Palma using the INT

Science.gov (United States)

Vaduvescu, O.; Hudin, L.; Tudor, V.; Char, F.; Mocnik, T.; Kwiatkowski, T.; de Leon, J.; Cabrera-Lavers, A.; Alvarez, C.; Popescu, M.; Cornea, R.; Díaz Alfaro, M.; Ordonez-Etxeberria, I.; Kamiński, K.; Stecklum, B.; Verdes-Montenegro, L.; Sota, A.; Casanova, V.; Martin Ruiz, S.; Duffard, R.; Zamora, O.; Gomez-Jimenez, M.; Micheli, M.; Koschny, D.; Busch, M.; Knofel, A.; Schwab, E.; Negueruela, I.; Dhillon, V.; Sahman, D.; Marchant, J.; Génova-Santos, R.; Rubiño-Martín, J. A.; Riddick, F. C.; Mendez, J.; Lopez-Martinez, F.; Gänsicke, B. T.; Hollands, M.; Kong, A. K. H.; Jin, R.; Hidalgo, S.; Murabito, S.; Font, J.; Bereciartua, A.; Abe, L.; Bendjoya, P.; Rivet, J. P.; Vernet, D.; Mihalea, S.; Inceu, V.; Gajdos, S.; Veres, P.; Serra-Ricart, M.; Abreu Rodriguez, D.

2015-05-01

Since 2006, the European Near Earth Asteroids Research (EURONEAR) project has been contributing to the research of near-Earth asteroids (NEAs) within a European network. One of the main aims is the amelioration of the orbits of NEAs, and starting in 2014 February we focus on the recovery of one-opposition NEAs using the Isaac Newton Telescope (INT) in La Palma in override mode. Part of this NEA recovery project, since 2014 June EURONEAR serendipitously started to discover and secure the first NEAs from La Palma and using the INT, thanks to the teamwork including amateurs and students who promptly reduce the data, report discoveries and secure new objects recovered with the INT and few other telescopes from the EURONEAR network. Five NEAs were discovered with the INT, including 2014 LU14, 2014 NL52 (one very fast rotator), 2014 OL339 (the fourth known Earth quasi-satellite), 2014 SG143 (a quite large NEA), and 2014 VP. Another very fast moving NEA was discovered but was unfortunately lost due to lack of follow-up time. Additionally, another 14 NEA candidates were identified based on two models, all being rapidly followed-up using the INT and another 11 telescopes within the EURONEAR network. They include one object discovered by Pan-STARRS, two Mars crossers, two Hungarias, one Jupiter trojan, and other few inner main belt asteroids (MBAs). Using the INT and Sierra Nevada 1.5 m for photometry, then the Gran Telescopio de Canarias for spectroscopy, we derived the very rapid rotation of 2014 NL52, then its albedo, magnitude, size, and its spectral class. Based on the total sky coverage in dark conditions, we evaluate the actual survey discovery rate using 2-m class telescopes. One NEA is possible to be discovered randomly within minimum 2.8 deg2 and maximum 5.5 deg2. These findings update our past statistics, being based on double sky coverage and taking into account the recent increase in discovery.

Spanish collaboration in the OECD Halden Reactor Project research on Gadolinia Fuel

International Nuclear Information System (INIS)

Horvath, M.; Munoz-Reja, C.; Tverberg, T.; Jenssen, H. K.

2010-01-01

Safe and reliable operation of nuclear power plants benefit from research and development advances and related technical solutions. One research platform is the OECD Halden Reactor Project (HRP). HRP is a joint undertaking of national organisations in 18 countries sponsoring a jointly financed programme under the auspices of the OECD - Nuclear Energy Agency (NEA). As a member state, Spain is participating HRP research programs with ENUSA as a partner in the fuel research programs. Improving the NPP operations, fuel cycles were designed to increase fuel burnup. Higher fuel burnup reduces the number of spent fuel assemblies and thus the costs of new fuel as well as the costs of back-end management. Higher burnup is reached either by prolonging the reactor cycles or by increasing the number of reactor cycles for the fuel in the core. Both ways entail additional requirements concerning fuel enrichment and burnable absorbers as additives and adjustments on the cladding material properties, such as mechanical treatment and chemical composition of the alloys. For these demands and needs ENUSA promotes the research on high burnup effects, gadolinium doped fuels and cladding material behaviour under irradiation. Various experiments, called IFA, are developed and performed also by providing materials. ENUSA collaborates with HRP on various experiments investigating the fuel densification and swelling, fission gas release, pressure limits on UO 2 and (U,Gd)O 2 fuels (IFA-504, -515, -636, -681); the cladding creep, lift-off, corrosion and hydrides on different tubing materials (IFA-567, -610, -638); instrumentation of the experiments, especially on pre-irradiated materials (IFA-533). These experiments are combined with model calculations to improve predictions for higher burnups and to maintain safety margins (IFA-515, -636, -681). Besides these unique in-pile experiments PIEs are performed as well on fuel and structural materials to complete the scope of these studies (IFA

The international hydrocoin project

International Nuclear Information System (INIS)

1987-01-01

The International HYDROCOIN (Hydrologic Code Intercomparison) Project was started in May 1984. Fourteen organizations participate in the Project, with the Swedish Nuclear Power Inspectorate (SKI) as managing participant and the OECD Nuclear Energy Agency (NEA) taking part as a member of the Project secretariat. HYDROCOIN is concerned with the assessment of groundwater movements at potential nuclear waste disposal sites with the help of mathematical models and computer codes. The Project is divided into three levels. The objective of HYDROCOIN Level 1 is to verify the accuracy of groundwater flow codes. HYDROCOIN Level 2 and Level 3 are concerned with validation of hydrological models and uncertainty/sensitivity analysis, respectively. This report, which has been prepared by the NEA Secretariat and SKI in consultation with the co-ordinating group of the HYDROCOIN Project summarizes the background and objectives of the Project and presents the results of the work performed up to the middle of 1987. It is intended to provide general information on HYDROCOIN to interested parties beyond the group of directly involved specialists

Kajian Perbandingan Tax Treaty Model: OECD, UN, dan US

OpenAIRE

Rachmawati, Dyna

2003-01-01

The needs of tax treaty arise as International trade growth rapidly due to advancement of information technology. Taxa imposed on income derived from International trade are double. Tax treaty or tax convention is bilateral agreement for the avoidance of double taxation. This agreement arranges taxation rights. There are 3 (three) tax treaty model, which is used as reference to make bilateral agreement for the avoidance of double taxation. The first one is OECD Model made by The OECD...

Adults, Computers and Problem Solving: "What's the Problem?" OECD Skills Studies

Science.gov (United States)

Chung, Ji Eun; Elliott, Stuart

2015-01-01

The "OECD Skills Studies" series aims to provide a strategic approach to skills policies. It presents OECD internationally comparable indicators and policy analysis covering issues such as: quality of education and curricula; transitions from school to work; vocational education and training (VET); employment and unemployment; innovative…

Maintenance and improvement of thermal hydraulic system codes using results of OCDE experiments (PKL, Rosa, Atlas) and application to Spanish Nuclear power plants. Camp-Spain project; Mejora y mantenimiento de codigos termohidraulicos de sistema de base a resultados de los experimentos OECD (PKL, ROSA y ATLAS) y su aplicacion a plantas espanolas, proyecto Camp-Espana

Energy Technology Data Exchange (ETDEWEB)

Sanchez, M.; Perez, J.; Martorell, S.; Carlos, S.; Villanueva, J. F.; Sanchez, F.; Queral, C.; Rebollo, M. J.; Rivas-Lewicky, J.; Verdu, G.; Gallardo, S.; Miro, R.; Querol, A.; Munoz-Cobo, J. L.; Escriva, A.; Berna, C.; Reventos, F.; Freixa, J.; Martinez, V.

2016-08-01

CSN involvement in different international NEA experimental TH programmes has outlined the scope for a new period of CAMP-Espana activities, currently focused on the: -Analysis, simulation and investigation of specific safety aspects of PKL3/OECD and ATLAS/OECD experiments. -Analysis of applicability and/or extension of the results in these projects to the safety, operation or availability of the Spanish nuclear power plants. Both objective are carried out by simulating experiments and plant application with the last available versions of NRC TH codes (RELAP5 or TRACE). A CAMP in kind contribution (NUREG/IA) is aimed as final result of both types of analyses. Five different national research groups (from Technical Universities of Madrid, Valencia and Cataluna) ate carrying out the development of these activities. (Author)

Energy statistics and balances of non-OECD countries 1993-1994

International Nuclear Information System (INIS)

1996-01-01

Contains a compilation of energy supply and consumption statistics for more than 100 non-OECD countries and regions, including developing countries Central and Eastern European countries and the former USSR. Data are expressed in original units and in common units for coal, oil, gas, electricity, heat and combustible renewable and waste. Historical tables for both individual countries and regions summarize data on coal, oil, gas and electricity production, trade and consumption as well as main energy and economic indicators since 1971. Each issue includes definitions of products and flows and notes on the individual countries as well as conversion factors from original units to common energy units. Similar data for OECD are available in the IEA Energy Statistics and Energy Balances of OECD Countries. (author)

Changes and events in uranium deposit development, exploration, resources, production and the world supply-demand relationship. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1997-09-01

This report consists of the proceedings of the Technical Committee Meeting on Recent Changes and Events in Uranium Deposit Development, Exploration, Resources, Production and the World Supply/Demand Relationship, held in co-operation with the OECD Nuclear Energy Agency (OECD/NEA) in Kiev, Ukraine, from 22 to 26 May 1995. Some of the information from this meeting was also used in preparation of the 1995 edition of ''Uranium - Resources, Production and Demand'' a joint report by the OECD/NEA and the IAEA. At the Beginning of 1995 there were 432 nuclear power plants in operation with a combined electricity generating capacity of 340 GW(e). This represents nearly a 100% increase over the last decade. In 1995 over 2228 TW·h of electricity were generated, equivalent to about 17% of the world's total electricity. To achieve this, about 61,000 t U were required as nuclear fuel. For about a decade and a half uranium production and related activities have been decreasing because of declining uranium prices. For many participants in the nuclear industry there has been little interest in uranium supply because of the oversupplied market condition. The declining production led to the development of a supply and demand balance were production is currently meeting a little over 50% of reactor requirements and the excess inventory is being rapidly drawn down. This very unstable relationship has resulted in great uncertainty about the future supply or uranium. One of the objectives of this Technical Committee meeting was to bring together specialists in the field of uranium supply and demand to collect information on new developments. This helps provide a better understanding of the current situation, as well as providing information to plan for the future. Refs, figs, tabs

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

NEA, Nuclear law and information processing

International Nuclear Information System (INIS)

Reyners, P.

1977-01-01

NEA has for many years now been collating information on, and analysing, laws and regulations on the peaceful uses of nuclear energy, and this work has resulted in a series of publications. However, as seen by the multiplication of computer-based legal information centres, both at national and international level, conventional information systems are no longer adequate to deal with the increasing volume of information and with users' needs. In view of the particular aspects of nuclear law and of its own availabilities, NEA has endeavoured to make the best possible use of existing structures by opting for participation in the IAEA International Nuclear Information System rather than by creating a specialised centre. Before becoming operational, the arrangements concluded between NEA and IAEA required that the INIS rules be altered somewhat to take account of the specific problems raised by treatment of legal literature and also to improve the quality of information provided to users. (auth.) [fr

The OECD and the Expansion of PISA: New Global Modes of Governance in Education

Science.gov (United States)

Sellar, Sam; Lingard, Bob

2014-01-01

This paper examines the expansion of the OECD's Programme for International Student Assessment (PISA) and associated growth in the influence of the OECD's education work. PISA has become one of the OECD's most successful "products" and has both strengthened the role of the Directorate for Education within the organization and enhanced…

Resource recovery and recycling in OECD countries

Energy Technology Data Exchange (ETDEWEB)

MacNeil, J.W.

It was the importance of the economic issues relevant to resource recovery and re-use that prompted OECD to become involved in this general area, and the author proposes in this talk to describe the principal features of the three main approaches to waste management from an economic perspective. These approaches are reduction of waste generation (i.e. birth control) resource recovery and materials recycling or re-use (reincarnation). Most of OECD's work in this area to date has been on the third of these approaches with particular emphasis on the economics of recycling, so somewhat more attention will be devoted to it. Then some conclusions will be drawn concerning possible policy actions to encourage a rational approach to management of this resource.

OECD Halden reactor project

International Nuclear Information System (INIS)

1978-01-01

This report summarizes the activities of the OECD Halden Reactor Project for the year 1976. The main items reported on are: a) the process supervision and control which have focused on core monitoring and control, and operator-process communication; b) the fuel performance and safety behavior which have provided data and analytical descriptions of the thermal, mechanical and chemical behavior of fuel under various operating conditions; c) the reactor operations and d) the administration and finance

International benchmark for coupled codes and uncertainty analysis in modelling: switching-Off of one of the four operating main circulation pumps at nominal reactor power at NPP Kalinin unit 3

International Nuclear Information System (INIS)

Tereshonok, V. A.; Nikonov, S. P.; Lizorkin, M. P.; Velkov, K; Pautz, A.; Ivanov, V.

2008-01-01

The paper briefly describes the Specification of an international NEA/OECD benchmark based on measured plant data. During the commissioning tests for nominal power at NPP Kalinin Unit 3 a lot of measurements of neutron and thermo-hydraulic parameters have been carried out in the reactor pressure vessel, primary and the secondary circuits. One of the measured data sets for the transient 'Switching-off of one Main Circulation Pump (MCP) at nominal power' has been chosen to be applied for validation of coupled thermal-hydraulic and neutron-kinetic system codes and additionally for performing of uncertainty analyses as a part of the NEA/OECD Uncertainty Analysis in Modeling Benchmark. The benchmark is opened for all countries and institutions. The experimental data and the final specification with the cross section libraries will be provided to the participants from NEA/OECD only after official declaration of real participation in the benchmark and delivery of the simulated results of the transient for comparison. (Author)

Specialist Bibliographic Databases.

Science.gov (United States)

Gasparyan, Armen Yuri; Yessirkepov, Marlen; Voronov, Alexander A; Trukhachev, Vladimir I; Kostyukova, Elena I; Gerasimov, Alexey N; Kitas, George D

2016-05-01

Specialist bibliographic databases offer essential online tools for researchers and authors who work on specific subjects and perform comprehensive and systematic syntheses of evidence. This article presents examples of the established specialist databases, which may be of interest to those engaged in multidisciplinary science communication. Access to most specialist databases is through subscription schemes and membership in professional associations. Several aggregators of information and database vendors, such as EBSCOhost and ProQuest, facilitate advanced searches supported by specialist keyword thesauri. Searches of items through specialist databases are complementary to those through multidisciplinary research platforms, such as PubMed, Web of Science, and Google Scholar. Familiarizing with the functional characteristics of biomedical and nonbiomedical bibliographic search tools is mandatory for researchers, authors, editors, and publishers. The database users are offered updates of the indexed journal lists, abstracts, author profiles, and links to other metadata. Editors and publishers may find particularly useful source selection criteria and apply for coverage of their peer-reviewed journals and grey literature sources. These criteria are aimed at accepting relevant sources with established editorial policies and quality controls.

Specialist Bibliographic Databases

Science.gov (United States)

2016-01-01

Specialist bibliographic databases offer essential online tools for researchers and authors who work on specific subjects and perform comprehensive and systematic syntheses of evidence. This article presents examples of the established specialist databases, which may be of interest to those engaged in multidisciplinary science communication. Access to most specialist databases is through subscription schemes and membership in professional associations. Several aggregators of information and database vendors, such as EBSCOhost and ProQuest, facilitate advanced searches supported by specialist keyword thesauri. Searches of items through specialist databases are complementary to those through multidisciplinary research platforms, such as PubMed, Web of Science, and Google Scholar. Familiarizing with the functional characteristics of biomedical and nonbiomedical bibliographic search tools is mandatory for researchers, authors, editors, and publishers. The database users are offered updates of the indexed journal lists, abstracts, author profiles, and links to other metadata. Editors and publishers may find particularly useful source selection criteria and apply for coverage of their peer-reviewed journals and grey literature sources. These criteria are aimed at accepting relevant sources with established editorial policies and quality controls. PMID:27134485

Peritonite bacteriana espontânea

Directory of Open Access Journals (Sweden)

Strauss Edna

2003-01-01

Full Text Available A peritonite bacteriana espontânea ocorre em 30% dos cirróticos com ascite e, neste grupo, apresenta altas taxas de morbidade e mortalidade. Os fatores predisponentes incluem a diminuição da defesa imunológica encontrada no homem nas fases avançadas da cirrose, o supercrescimento da flora intestinal e a translocação bacteriana da luz dos intestinos aos linfonodos mesentéricos. As manifestações clínicas variam de graves a leves ou ausentes, sendo sempre necessária a análise do líquido ascítico. O diagnóstico de peritonite bacteriana espontânea se faz pela contagem de neutrófilos > 250/mm³ no líquido ascítico associado ou não ao crescimento de bactéria na cultura. As enterobactérias predominam como causa da infecção, sendo a Echerichia coli a bactéria mais freqüentemente isolada. O diagnóstico precoce e o tratamento adequado provocaram a queda das taxas de mortalidade nas duas últimas décadas. O uso endovenoso de cefalosporinas de terceira geração mostra-se eficaz em 70% a 95% dos casos. A recorrência de peritonite bacteriana espontânea é comum e pode ser prevenida com norfloxacina oral, de uso contínuo. O surgimento de resistência bacteriana tem estimulado a procura de novas opções para a profilaxia da peritonite bacteriana espontânea; os probióticos constituem nova abordagem promissora, mas que necessita melhor avaliação. Recomenda-se a profilaxia primária de curta duração aos cirróticos com ascite que apresentem episódio de hemorragia digestiva alta.

OECD - Majandusliku Koostöö ja Arengu Organisatsioon / Kairi Saar, Jane Makke

Index Scriptorium Estoniae

Saar, Kairi, 1973-

2011-01-01

Ülevaade OECD ajaloost, tegevusest, liikmesuse kriteeriumitest (riikide sarnane mõtteviis) ning majandusprognoose, uuringuid ja statistikat sisaldavatest väljaannetest. Eesti liitumisest organisatsiooniga 2010. a., Eesti ja Balti riikide kohta avaldatud väljaanded. Rahvusraamatukogu kui OECD hoiuraamatukogu Eestis

In-vessel core degradation code validation matrix update 1996-1999. Report by an OECD/NEA group of experts

International Nuclear Information System (INIS)

2001-02-01

In 1991 the Committee on the Safety of Nuclear Installations (CSNI) issued a State-of-the-Art Report (SOAR) on In-Vessel Core Degradation in Light Water Reactor (LWR) Severe Accidents. Based on the recommendations of this report a Validation Matrix for severe accident modelling codes was produced. Experiments performed up to the end of 1993 were considered for this validation matrix. To include recent experiments and to enlarge the scope, an update was formally inaugurated in January 1999 by the Task Group on Degraded Core Cooling, a sub-group of Principal Working Group 2 (PWG-2) on Coolant System Behaviour, and a selection of writing group members was commissioned. The present report documents the results of this study. The objective of the Validation Matrix is to define a basic set of experiments, for which comparison of the measured and calculated parameters forms a basis for establishing the accuracy of test predictions, covering the full range of in-vessel core degradation phenomena expected in light water reactor severe accident transients. The emphasis is on integral experiments, where interactions amongst key phenomena as well as the phenomena themselves are explored; however separate-effects experiments are also considered especially where these extend the parameter ranges to cover those expected in postulated LWR severe accident transients. As well as covering PWR and BWR designs of Western origin, the scope of the review has been extended to Eastern European (VVER) types. Similarly, the coverage of phenomena has been extended, starting as before from the initial heat-up but now proceeding through the in-core stage to include introduction of melt into the lower plenum and further to core coolability and retention to the lower plenum, with possible external cooling. Items of a purely thermal hydraulic nature involving no core degradation are excluded, having been covered in other validation matrix studies. Concerning fission product behaviour, the effect