Joint Safety Research Index

(JSRI)

CO-ORDINATOR

A. BreestGesellschaft für Anlagen und Reaktorsicherheit (GRS)mbH Research Management DivisionSchwertebergasse 1PO Box 10 15 64DE – 50667 KÖLN

Tel : +49.221.2068.667Fax +49.221.2068.629Email : bre@grs.de

PARTNERS

Department of Nuclear Safety Research, Risoe National Laboratory (RISOE), DenmarkInstitut de Protection et de Surete Nucleaire (IPSN), FranceTechnical Research Centre of Finland (VTT), FinlandInstitute for Systems, Informatics and Safety (JRC-ISPRA), Italy (EU)Nuclear Research and Consultancy Group (NRG), NetherlandsCenter of Technology and Engineering for Nuclear Projects (CITON), RomaniaHealth and Safety Executive (HSE), United KingdomPaul Scherer Institut (PSI), SwitzerlandNuclear Services Ltd.(HUT), HungarySwedish Nuclear Power Inspectorate (SKI), SwedenEnte per le Nuove Tecnologie, l’Energia e l’Ambiente (ENEA), ItalyForschungszentrum Karlsruhe (FZK), GermanyCentro de Investigaciones Energeticas, Mediambientales y Tecnologicas (CIEMAT), SpainCentre d’Etude de l’Energie Nucleaire (SCK/CEN), BelgiumUstav Jederneho Vyzkumu Rez a.s. (UJV), Czech Republic

CONTRACT N : FIR1-CT2000-20089

EC Contribution : EUR 299 909Total Project Value : EUR 307 784Starting Date : 1 January 2001Duration : 30 months

Table of Contents

1. Table of contents

2. Executive publishable summary for CORDIS

3. Objectives and strategic aspects

4. Scientific and technical description of the results

4.1. Progress during the project phase

4.2. Main Achievements

4.3. Architecture of JSRI

5. Assessment of results and conclusions

5.1. Supports of cooperation in the Nuclear Community by JSRI

5.2. Get reports on Information in the JSRI-System

6. Acknowledgements

7. References

8. Annexes

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2. Executive publishable summary for CORDIS

The aim of the Joint Safety Research Index (JSRI) is to provide a principal source of most recent information on current light water reactor (LWR) safety research projects in participating EU member states and associated countries. These annual re-ports are to be implemented into a data base (the JSRI) which will be presented in the Internet for researchers in the field of reactor safety as well as other interested persons.

To increase the effectiveness and user friendliness of the data base, which used to be distributed on diskettes or CD-ROM respectively, JSRI is now set up in the inter-net with some innovative user friendly tools for data retrieval.

To achieve this, all participants are to deliver a collection as complete as pos-sible of their annual reports, written in English and set up according to a standard ques-tionnaire via the new JSRI Internet homepage:http://w2ksrvx.ike.uni-stuttgart.de/jsri/

The JSRI project consortium presently consists of 16 partners from 10 EU mem-ber states and 4 associated countries according to EC extension 3. The Joint Research Centre JRC-ISPRA (later in the project JRC-Petten) also takes part (see annex for de-tails). Every partner of the JSRI project nominated a contact person responsible for the national technical implementation of the project work and authorised to grant access to the data base in their respective country.

The actual number of reports within the internet released JSRI amounts to a total of 1402 and the official homepage was visited more than 27000 times during the refer-ence period. This information system combines the nuclear competence of 37 contribut-ors from 17 countries and contains information about 641 nuclear experts in Europe.

The „Forschungsinstitut für Kerntechnik und Energiewandlung (KE-Technolo-gie)“ (Stuttgart, Germany) which is associated to the University of Stuttgart is as sub-contractor responsible for the technical and organisational establishment and operation of the Internet based JSRI Index.

3. Objectives and strategic aspects

The project extends the JSRI project carried out under the 4th EU Framework Programme. The need for concentration of R&D competences at a specific location will be replaced by interdisciplinary interactions in broader thematic R&D Networks on na-tional and international levels.

The 'classical' documentation may be overruled by electronic systems allowing for 'Hyperlinks' between different sources of information additional to the usual refer-ences. Especially long-termed developments should be accompanied establish docu-mentation systems that allow for safe retrieving of existing know-how.

The safety issues to be addressed in the various countries are similar as are the reactor designs used, especially in EU member states, and international co-operation is practised in various fields of investigation to bundle research capacities, exchange in-formation, and to avoid duplication of work.

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To support such international information exchange and co-operation, an in-formation tool is intended to be provided by this project which facilitates an overview on light water reactor safety research currently performed in member countries and countries associated to the European Union.

It is the goal to prepare an annular updated Index (JSRI) to be presented in the internet containing brief reports on current research projects in participating countries. It will be updated once a year.

These reports describe the project objectives, work scope, approach and status. Finished projects will be dropped from the Index because there are numerous sources providing detailed information on these.

The JSRI index will be updated every year so that the information provided is closely linked to the research just performed in EU member and applicant countries.

The timely information on research work under way, recent results and activities planned for the immediate future qualifies this database to be a strategic tool for further development of reactor safety research programmes on the national as well as the inter-national level.

4. Scientific and technical description of the results

4.1 Progress during the project phase

The co-ordinated JSRI start-up was supported by a kick-off meeting on February 19./20., 2001 right at the beginning of the project. The first annual progress meeting was held in Bologna on November 22./23., 2001. The second annual progress meeting was held in Prague on September 12./13., 2002. The third and final annual progress meeting was held in London on June 23, 2003. In the final meeting the experiences with the Joint Safety Research Index were summarized and recommendations are given for a possible future continuation.The first issue of the JSRI was successfully released officially by the end of 2001. This issue is based on the standards agreed upon in the previous project and incorporates the input of all 16 partners. The number of reports within the first internet released JSRI amounts to 353 and the official homepage was visited more than 4000 times during 2001.The second issue of the JSRI was released officially in autumn 2002. This issue is based on the standards agreed upon in the previous project and incorporates actions defined during the first annual JSRI meeting in Bologna. The number of reports within the JSRI-2002 release amounts to 300 and the official homepage was visited more than 16000 times during 2002.The third issue of the JSRI was released officially in spring 2003. It is based on the standards agreed upon during the second annual JSRI meeting in Prague. The number of reports within the JSRI-2003 release amounts to 304 and the official homepage was visited more than 27000 times.

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4.2 Main Achievements

The major progress steps which were achieved during this project are as follows:

JSRI now has its own internet homepage.

Every JSRI partner delivered links provided to national research organisations and industry. These links were integrated within the JSRI homepage.

It is now possible to add pictures and tables to JSRI reports (see annex).

A new entry field called „Funds“ was installed by using a special classification key.

All JSRI reports (even the ones from FP-4) were made free for users without re-gistration.

The JSRI classification list was simplified.

More than one classification is available for one JSRI project.

Item 7 „Others“ was added to the classification index.

A new link was put to the IAEA Waste Management Research Abstracts to be found under the new JSRI classification index under item 7.2.

The link to the EC CORDIS website was activated.

The searching potentials of JSRI were even improved by the implementation of a full text search engine with the release 2003.

Six “standard JSRI plots” were defined which are available as Excel-files (see annex):

1. Summary of projects over all classifications and all years2. Summary of projects distributed over classifications for year and country3. Summary of projects distributed over main classifications for year4. Summary of experts distributed over classifications for year and country5. Summary of funding size for year and all countries6. Summary of funding size for year and each country

By the „project leader selector“ the family names of the project leaders were sorted alphabetically.

Copies of JSRI projects from the previous year are available.

4.3 Architecture of JSRI

The project extends the JSRI project carried out under the 4th Framework Pro-gramme of the EU. This JSRI Phase II is meant to start the ”Internet-Phase” of the In-dex to make use of the advantages of this medium supporting international information exchange.

To increase the effectiveness and user friendliness of the data base, which used to be distributed on diskettes or CD-ROM respectively, JSRI was now set up in the in-ternet with some innovative user friendly tools for data retrieval.Therefore the main advantage of the Joint Safety Research Index (JSRI) is its free ac-cess to valuable and state-of-the-art information by participating research institutions,

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technical support organisations as well as technical advisory and regulatory bodies without time consuming release and transfer procedures.

For more global evaluations the information provided by the JSRI may be suffi-cient. If, however, more detailed information might be required the Index also provides for the appropriate contact addresses to apply for comprehensive exchange or collabora-tion.

As reactor safety research covers a wide spectrum of technological disciplines, spin-offs into non-nuclear research and application and vice versa can be expected by making ongoing research activities and programmes transparent.JSRI facilitates the most recent overview on LWR safety research currently performed in member countries and countries associated to the EU. Therefore JSRI could become the ”European address book dedicated to ongoing European LWR research (Yellow Pages)”.

The “heart” of all these approaches is a database based on a relational database management system (presently MS-ACCESS). The user works with the data in the database by utilising a standard Browser (Netscape-Navigator or Internet-Explorer) and can export data into tools like MS Word or MS EXCEL.

This is achieved by two special layers between the user interface and the data-base. The first one contains a Web server and connects the system with the user inter-face. The second one manages the dynamic generation of HTML pages and allows the export of data into various applications.

This four layer architecture enables the high flexibility and the easy adaptability of the system. Each layer can be modified separately.A further consequence of this architecture is that the system can be either operated on a single computer or in a distributed environment. No special installations are necessary as long as a browser and the MS office tools needed for a specific application are avail-able.

Finally, the whole system can be made available in a static version on CD-ROM. Such a version would offer all advantages of the system. However, it will not allow to modify the content of the underlying data base in a permanent way.

5. Assessment of Results and Conclusions

5.1. Supports of cooperation in the Nuclear Community by JSRI

The first release of JSRI aims to support cooperation among the nuclear com-munity. To do this it offers various kinds of support in principle. This includes:

a data base with information including the coordinates of all partners of the inform-ation system,

a data base for the collection of information structured through questionnaires. One such questionnaire is the form to collect annual reports on ongoing projects,

a data base to describe documents inserted in the archive of the system, a repository which serves as archive for documents, figures and tables, a platform to announce meetings and to report meeting results,

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a platform to provide access to systems of interest to the partners of the JSRI-pro-ject,

a collection of links which are of interest to the partners of the JSRI-project.

Emphasis has also been put on the use of recent telecommunication tools as they seemed to be essential for R&D networking with a multi-partner, multi-topical and multi-national structure.Internet was chosen as the main communication platform for the JSRI-project as it is assumed that Internet will be broadly accepted for information exchange and for inter-active use.

This database approach now offers not only the possibility to search on a flex-ible basis for information needed but also allows to implement an elaborated role concept, which helps to distribute information both to restricted groups or the public of the JSRI-Information-System.

A restricted group is called FORUM. Everybody registered to the JSRI-Informa-tion-System is allowed to install a FORUM. Each FORUM offers an "Information Mar-ketplace" for information exchange among the members selected.This feature has turned out to be rather essential for the acceptance of the information system as it allows to insert e.g. drafts only restricted to the supplier of information, then circulating the information in limited groups or only within the department etc. This also allows to make internal use of the system by all registered organisations by in-stalling an organisation dependent FORUM.

5.2. Get reports on Information in the JSRI-System

The information from the database is offered by ‘reports’. You can choose dif-ferent reports after having activated Data Reports. The frame at the right side gives the options available. After choosing the area several selections are offered to find specific information.

Information available in the system can be searched for under various criteria. To do this various selectors are available. Usually these are fixed selectors. But also free selectors are offered. The searching potentials were even improved by the imple-mentation of a full text search engine with the release 2003.The information selected is presented in form of reports. Therefore reports in the con-text of the JSRI-Information-System means special forms to present query results. Usu-ally reports are presented as Web pages, but also Word documents or Excel sheets are possible where appropriate.

JSRI Phase II is meant to become an important strategic tool for the 6th Frame-work Programme of the EU for further development of reactor safety research.6. Acknowledgements

The co-ordinator wants to thank the JSRI consortium and the EC for a fruitful and dedicated work within the project.

7. References

Euratom Framework Programme 1998-2002 for Community Research and Training Activities Key action "Nuclear Fission "

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Operational safety of Existing Installations; MID-TERM SYMPOSIUM ON SHARED-COST AND CONCERTED ACTIONS

FISA 2001 – EU RESEARCH IN REACTOR SAFETY Luxembourg12 - 14 November 2001

8. Annexes

8.1 Description of the JSRI consortium

The project consortium consists of 16 partners from 10 EU member states and 4 associated countries according to EC extension 3. The Joint Research Centre (JRC) IS-PRA (later in the project JRC-Petten) applies for participation without requesting funds for their activities.

GRS applies for the overall co-ordination of the project. To pursue the duties the project manager will be supported by technical and administrational staff of the com-pany.

All partners are directly or indirectly involved in reactor safety research in their countries, experienced in international co-operation and stand for reliable provision of JSRI input as well as for pertinent use of the Index.

The Table below characterises the types of partner organisations:

Type of organisation Partner

Applied research GRS, ENEA, FZK, JRC (Ispra, Petten)

PSI, SCK/CEN, VTT, CIEMAT

Research close to utilities NRI, HUT

Support for utilities CITON, NRG

Support for licensing authorities and

R & D

IPSN (IRSN), RISOE

Licensing authority HSE, SKI

8.1.1. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbHGRS is Germany's central scientific-technical expert organisation for all issues

related to nuclear safety and nuclear waste management. Its task is to provide scientific results and methods and develop them further for the purpose of protecting man and en-vironment from technical hazards and risks. The work of GRS is based on the interna-tional state of the art.The technical competence of GRS is founded on the organisation's own research and development activities, technical analysis and the evaluation of operating experience of

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technical plants and facilities as well as on co-operation with numerous international or-ganisations. Among the staff of GRS there are specialists for all relevant technical fields, enabling the organisation to make comprehensive safety assessments of complex systems.The work of GRS serves for the benefit of general public. GRS is therefore recognised as a non-profit organisation.It is the company policy of GRS that all parts shall implement effective and efficient quality management systems especially consistent with the requirements of DIN EN ISO 9000, and in July 1997 the company was certified by TÜV CERT.

8.1.2 Research Centre for Energy, Environment and Technology (CIEMAT)

Over the past years CIEMAT has been involved in domestic and international research programmes in the field of nuclear safety, such as: OECD-LOFT, LACE, ACE, PHEBUS-CD, PHEBUS-FP, HALDEN and others. Likewise, CIEMAT has been contributing to EU Framework Programmes on the area of nuclear safety since middle eighties with both analytical and experimental kinds of work. Recently, and under the sponsorship of the 1994 - 1998 Euratom Programme, CIEMAT has contributed to the analysis of heat transfer in passive safety system through projects such a TEPSS and CONGA, to the validation of acknowledge nuclear safety tools, such as CONTAIN, through PHEBUS-FP experiments within the PHEBEN project, to the study of fuel thermal conductivity change with burn-up within HALDEN project, etc. Particularly relevant to this proposal is the CIEMAT contribution to the previous edition of the JSRI project. In addition, CIEMAT is being supported by the Spanish Nuclear Safety Au-thority to assess uncertainties in PSA-2 results obtained with MAAP.

8.1.3 Center of Technology and Engineering for Nuclear Projects (CITON)

With its almost 500 employees the Center mainly deals with engineering activit-ies in the field of nuclear, and thermal energy co-generation projects or other industrial and non-industrial activities. Our specialists have got a vast experience in designing, guiding and checking up all the activities required by the nuclear program experience certified by 20 years of co-operation with Canadian, Italian and American companies.

The Center of Technology and Engineering for Nuclear Projects (CITON) has got an excellent reputation. It is well recognized as one of the best engineering institutes in Romania, being able to develop a wide range of activities, in the field of producing energy. Under different denominations (IRNE, ISPE-DN) CITON has participated in the elaboration of all the nuclear projects in Romania.

The Center of Technology and Engineering for Nuclear Projects (CITON) is the only one specialized and certified to perform Nuclear Projects in Romania, acting as General Designer responsible for overhaul engineering work.

8.1.4 Nulear Research and Consultancy Group (NRG)NRG is a science and engineering services company providing solutions on the

safe, ecologically sound and efficient use of nuclear installations. NRG was established in 1998 through the merger of ECN's and KEMA's nuclear science and technology activities. NRG's product groups have executed nuclear R&D-programmes for the joint Dutch utilities and government for over 40 years. NRG has broad expertise in design and safety issues of existing nuclear installations, and has participated in technology de-velopment programmes for evolutionary and advanced nuclear power reactor designs

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such as PBMHTR, GTMHR, SBWR, SWR-1000, EPR, and accelerator driven reactor concepts. NRG operates the HFR at Petten.

NRG is registered to the quality assurance standard ISO-9001 for the validity range of nuclear research, development and services in the field of nuclear energy. NRG staff have participated in various nuclear safety projects for the European Com-mission, involving co-ordination, numerical analysis and experimental work. NRG's nu-merical analyses capabilities combine considerable experience in nuclear analyses, ex-perience with a variety of internationally renown codes, and a powerful infrastructure of multiprocessor computers. NRG applies leading codes for nuclear system, computa-tional fluid dynamics (CFD) and finite element method (FEM) analyses, such as RE-LAP/SCDAP, TRAC, MELCOR, MAAP, CFX, STAR-CD, TASCFlow, ANSYS and MARC.

8.1.5. National Agency for New Technology, Energy and Environment (ENEA)ENEA has in Italy eleven centres and several support offices. The ENEA staff is

about 3000 Persons; 1500 of them are scientists and engineers involved in R&D and co-ordination activities. The ENEA is organised in three Departments: Energy, Environ-ment and New Technology.This proposal is originated by ENEA's Department of Energy and in particular by the ERG-SIEC Division, that is "Divisione Sistemi Energetici Ecosostenibili". The director, Dr. Renzo Tavoni and the scientific responsible Dr. Felice de Rosa are the reference persons inside ENEA for this proposal.The research programme of ERG-SIEC is mainly finalised at maintaining knowledge on the most relevant methods, solutions and issues linked to nuclear fisson safety. On this regard ERG-SIEC promotes and participates in research actions with national and international organisations to contribute to the development of a new nuclear reactor concept, characterised by safety requirements under definition by the main European Electric Utilities.

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8.1.6. Forschungszentrum Karlsruhe (FZK)Forschungszentrum Karlsruhe (FZK), Technik und Umwelt (Research Center

Karlsruhe, Technique and Environment) is one of the largest research centres in Ger-many, it employs about 3.200 persons. Since several decades it has a profound know-ledge and experience in R&D of nuclear reactor safety and in national and international co-operation. Actual research for light water reactor safety covers experimental and analytical work with respect to severe accidents, including model development, for in- and ex-vessel safety behaviour in severe accidents, fuel-water interaction, steam explo-sion, core melt retention and containment risks. Based on its broad national and interna-tional co-operation, FZK is especially qualified by its scientific and technical staff to solve complex problems requiring input from various fields and to perform and evalu-ate large scale experiments with complicated measurement techniques.The R&D-program for reactor safety is mainly centred around the comprehensive ex-perimental facilities operating since several years, some were newly designed for in-vestigation of arising additional questions.FZK has close contacts and is in co-operation with many national and international in-stitutions, like research centres, industries and licensing authorities and universities. FZK was a reliable partner in many projects in the 4th Frame Work Program of the EC.

8.1.7. Health and Safety Directorate (HSE) - Nuclear Safety DivisionThe Health and Safety Directorate is an independent public corporate body and

has the responsibility to make arrangements to enforce health and safety legislation in the UK. It reports to, and is the executive arm of, the Health and Safety Commission (HSC).

The Nuclear Safety Division (NSD) of HSE - which incorporates the Nuclear Installations Inspectorate, set up under the 1960 Nuclear Installations Act - is the divi-sion of HSE which provides the regulatory function for the civil nuclear industry in the UK. It employs around 280 staff, sixty percent of which are technical staff qualified to honours degree level or higher and are corporate members of senior professional engin-eering or scientific institutions, or have equivalent status. Most of the other staff are professional administrative civil servants and have experience in other areas of HSE's activity such as policy and administration.

In the UK, legal responsibility for the safe design and operation of nuclear plant is placed on the operator, but no one may build or operate a commercial nuclear install-ation without a license from HSE. The Nuclear Safety Division provides the expertise to assess all aspects of the relevant safety cases and to inspect and enforce compliance with the case and associated procedures and legislation.

HSE's Nuclear safety Division actively takes part in world-wide efforts to main-tain and improve nuclear safety through organisations like the International Atomic En-ergy Agency, the Nuclear Energy Agency of the Organisation for Economic Co-opera-tion and Development and through exchanges of technical information with nuclear safety inspectorates of other countries. The Division monitors and influences the UK nuclear safety research programme, managed by the industry to meet the HSC's require-ments, and sponsors its own research to address aspects perceived as requiring further knowledge to enhance safety.

8.1.8. Institute for Protection and Nuclear Safety IPSN (now IRSN)

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The mission of the IPSN (IRSN) is to contribute to the control of nuclear risks and their consequences on people and the environment. IPSN (IRSN) carries out re-search and expert appraisal concerning all aspects of risk.The Institute studies all aspects of the risk posed by nuclear power stations, laboratories and industrial facilities, and by natural radioactivity. The protection of people and the environment, and the safety and security of nuclear installations are analysed in normal and accident situations.

The research and expert appraisal are linked in order to have the best available level of knowledge to hand, and to answer the questions raised by risk analysis. The IPSN (IRSN) itself carries out research in nuclear safety, occupational safety, radiolo-gical protection and radioecology and is supported by the collaboration of its foreign counterparts.

8.1.9. Joint Research Centre (JRC)The Joint Research Centre in Ispra (now Petten), Italy, is the principal research

establishment of the EC in the field of nuclear energy and nuclear safety research.

8.1.10 Nuclear Research Institute (NRI)NRI is the immediate successor of the Nuclear Research Institute which was

founded back in 1955 as a part of R&D base for the Czechoslovak nuclear programme within the Czechoslovak Academy of Sciences. In December 1992 the Nuclear Re-search Institute has been transformed into joint-stock Company.

The actual mission of the NRI Rez plc is research and development activities, and implementation of the results in nuclear technologies, as well as radioactive waste management, with emphasis on support for the Czech Republic state authorities in the area of the strategic nuclear power planning and nuclear waste management, including the siting permits procedures, evaluation of the environmental impacts, establishing concept of the safety information systems, and support to State Inspectorate on Nuclear Safety, and performance of research and development activities related for various fields of nuclear energy and nuclear safety.NRI traditionally took part in such international activities as OECD, IAEA and PHARE projects.

8.1.11 Nuclear Services Ltd Hungary HUT)By Central Research Institute for Physics of the Hungarian Academy of Sci-

ences (KFKI) has been founded a private limited company; as definite by the VI. Hun-garian Law of 1988 and by the Court of Registration has been registered on 21/05/1991 No 74770. Its activities are research-development-application in the field of material testing and safeguards, safety investigations - first of all by visual inspection - of re-search and power reactor vessels and equipment, organisation of manufacturing and de-livering of nuclear electronic instruments and equipment, preparatory work in the full or limited reconstruction of research and teaching-reactor's and nuclear equipment or establishments, export-import in connection with the main activities, and publishing of educational material and making of video pictures connected to the main activities and their marketing

8.1.12 Paul Scherrer Institut (PSI)The Paul Scherrer Institute (PSI) is a multidisciplinary research institute for nat-

ural sciences and technology. In national and international collaboration with universit-

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ies, other research institutes and industry, PSI is active in elementary particle physics, life sciences, solid-state physics, material sciences, nuclear and non-nuclear energy re-search, and energy-related ecology.

PSI's priorities lie in research fields which are relevant to sustainable develop-ment, serve educational needs and are beyond the possibilities of a single university de-partment. PSI develops and operates complex research installations which call for espe-cially high standards of know-how, experience and professionalism. PSI is one of the world's leading user laboratories for the national and international scientific community. Through its research, PSI acquires new fundamental knowledge and promotes applica-tions in industry.

Nuclear energy research in Switzerland is lively, forward-looking and market-oriented! It provides important contributions to the safety of the domestic nuclear power plants and to the solution of the waste disposal issue! The Nuclear Energy and Safety Research Department (NES) of the PSI takes a particular position with regard to nuclear energy research, as it is practically the only organisation in the country active in this domain. The light water reactors presently in operation in Switzerland are in the foreground, but also safety characteristic of future reactor concepts are investigated. PSI contributes also to the disposal of radioactive waste from medicine, industry and re-search and through its research to the safety evaluation of future nuclear waste reposit-ories.

8.1.13. RISOE National LaboratoryRISOE is a national laboratory under the Danish Ministry of Research and In-

formation Technology. It carries out research in science and technology, providing Danish society new opportunities for technological development.

The research creates new opportunities for Danish industry. It contributes to the development of environmentally acceptable methods for agricultural and industrial pro-duction as well as for the generation of the energy necessary for modern society.

RISOE has a special responsibility for consolidating the knowledge base on nuc-lear issues and providing consultancy to governmental authorities in this area. It ollab-orates with universities, research institutes, technological institutes and the industrial sector on a national, European as well as on an international basis.Risoe places strong emphasis on the education of young researchers through PhD and post-doctorate programmes.

8.1.14. SCK/CENThe Belgian Nuclear Research Centre (SCK/CEN) is an institute of public utility

under the tutorship of the Belgian minister in charge of energy. About 600 highly quali-fied researchers and technicians realize an annual turnover of three billion Belgian francs, 50% being covered by a governmental subsidy and 50% by contract work and services for the Belgian and foreign industry and for the European Union.

The primary mission of SCK/CEN is research and development in the fields of the safety of nuclear installations, the safe handling and disposal of radioactive waste, and radiation protection and safeguards. It is converted in concrete projects, based on the current priorities of the Belgian authorities and of our customers.

8.1.15. Statens Kärnkraft-inspektion (SKI)

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In Sweden, the nuclear power utilities are responsible for the safe operation of the nuclear power plants. The utilities are also responsible for the handling and final disposal of spent nuclear fuel and radioactive waste.

SKI, the Swedish Nuclear Power Inspectorate, (in Swedish, Statens Kärnkraft-inspektion) is the authority which ensures that the nuclear power utilities actually as-sume this responsibility.

SKI is the Swedish government regulatory body under the Nuclear Activities Act and the Act on the Financing of Future Expenses for the Spent Nuclear Fuel.

SKI finances research in the field of nuclear safety. The research mainly aims at providing a basis for SKI's supervisory work, maintaining a high level of competence within the field of nuclear safety within and outside SKI, and contributing to work re-lating to Swedish nuclear safety.

Examples of areas of research are severe accidents, reactor safety, nuclear fuel management, nuclear waste, safeguards, and safety issues related to the interaction between man, technology and organisation. A great deal of the research is conducted in the form of joint international projects.

8.1.16. VTT , Technical Research Centre of FinlandVTT, the Technical Research Centre of Finland is an impartial expert organisa-

tion employing 2.900 persons. VTT is a governmental contract research centre having nine research institutes. The total budget is 191 million Euros. Income from contract re-search is 73 million Euros, income from contract research with joint budget financing is 42 million Euros, and own-initiated budget financing is 60 million Euros. VTT's clients and co-operation partners are industrial enterprises, other companies and business, uni-versities, research institutes and governmental bodies. VTT produces new applied tech-nology in co-operation with foreign partners.

VTT Energy is one of the nine research institutes of Technical Research Centre of Finland (VTT). The mission of VTT Energy is to carry out high-quality and impar-tial research and product development work concerning the generation, transfer, distri-bution, and use of energy. The total staff of VTT Energy is 312, of which 70 % is hold-ing an academic degree. The total budget of VTT Energy is 27 million Euros.The work to be carried out for this project will be performed by VTT Energy, Nuclear Energy. The Nuclear Energy research field has group of experts in the following areas reactor analysis, accident management, nuclear waste, PACTEL-Group and fusion re-search.

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8.2 JSRI Classification List of Reactor Safety Research Areas (old)

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1 Integrity and Reliability1.1 Mechanical Components (Including Fuel Elements)1.1.1 Mechanical Components - Ageing1.1.2 Mechanical Components – Radiation Resistance1.1.3 Mechanical Components – Hazards Resistance1.1.4 Mechanical Components – Vibrations1.1.5 Mechanical Components . Non Destructive Test and Inspection1.1.6 Mechanical Components – Components failures1.2 Electrical and Electronical Components1.2.1 Electrical and Electronical Components – Ageing1.2.2 Electrical and Electronical Components – Resistance to Radiation1.2.3 Electrical and Electronical Components – Instrumentation and Control1.2.4 Electrical and Electronical Components – Hazards Resistance1.3 Concrete1.3.1 Concrete – Ageing1.3.2 Concrete Leak Tightness1.3.3 Concrete – Non Destructive Tests2 Controlled Faults (Design Basis Accidents)2.1 Reactor Physics and Fuel Behaviour2.2 Reactivity Insertion2.3 Loss of Coolant2.4 Loss of Heat Sink3 Severe Accidents3.1 Core Degradation3.2 Hydrogen3.3 Steam Explosions3.4 Reactor Pressure Vessel Behaviour3.5 Corium Behaviour in RPV and in the Containment3.5.1 Corium Flow3.5.2 Corium/Water Interaction3.5.3 Corium Coolability3.6 Explosion3.7 Fire3.8 Hurricanes and Tornadoes3.9 Floods4 Fission Products inside Primary Circuit and Containment4.1 Fission Products Inventory and Release4.2 Chemistry of Aerosols and Vapours4.3 Transport of Aerosols and Vapours4.4 Detection, Measurement4.5 Management of FP inside the Containment during an Accident5 Containment5.1 Hazards Resistance of Concrete Structures5.1.1 Explosion, Overpressure5.1.2 Missiles5.1.3 Earthquakes5.2 Containment Loss of Integrity5.3 Containment Management during an Accident5.3.1 Hydrogen Mitigation Measures5.3.2 Venting5.3.3 Spray6 Risk Analysis

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6.1 PSA/PRA6.1.1 PSA/PRA – Level 16.1.2 SA/PRA - Level 26.2 Human Factor6.3 Man-Machine Interface6.4 Automation, Computerisation6.4.1 Hardware, Networks6.4.2 Software6.5 Instrumentation6.6 Simulators, Plant Analysers6.7 Code Quality Control7 Others

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8.2 JSRI Classification List of Reactor Safety Research Areas (new)

1. Integrity and Reliability1.1. Mechanical Components (Including Fuel Elements)1.2. Electrical and Electronical Components1.3. Concrete2. Controlled Faults (Design Basis Accidents)2.1. Reactor Physics and Fuel Behaviour2.2. Reactivity Insertion2.3. Loss of Coolant2.4. Loss of Heat Sink3. Severe Accidents3.1. Core Degradation3.2. Hydrogen3.3. Steam Explosions3.4. Reactor Pressure Vessel Behaviour3.5. Corium Behaviour in RPV and in the Containment3.6. Explosion3.7. Fire3.8. Hurricanes and Tornadoes3.9. Floods4. Fission Products inside Primary Circuit and Containment4.1. Fission Products Inventory and Release4.2. Chemistry of Aerosols and Vapours4.3. Transport of Aerosols and Vapours4.4. Detection, Measurement4.5. Management of FP inside the Containment during an Accident5. Containment5.1. Hazards Resistance of Concrete Structures5.2. Containment Loss of Integrity5.3. Containment Management during an Accident6. Risk Analysis6.1. PSA/PRA6.2. Human Factor6.3. Man-Machine Interface6.4. Automation, Computerisation6.5. Instrumentation6.6. Simulators, Plant Analysers6.7. Code Quality Control7. Others7.1. Fuel Storage Management7.2. Waste Management

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8.3 Example of a JSRI questionnaire:

Reporting Period: Classification: Project Number:

Project Title: Country:

Sponsor:

Contractor:

Initiated: Completed: Project Leader:

Last Updating: Funds:

1. General Aim:

2. Particular Objectives and Research Program:

3. Experimental Facilities:

4. Computer Codes:

5. Progress to Date:

6. Results:

7. Next Steps:

8. Relation with other Projects:

9. References:

10. Degree of Availability of the Reports:

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8.4 Sample JSRI Report as Document

Reporting Period:01.01.2001 31.12.2001

Classification:6.7

Project Number:026

Project Title:Preparation of the material inspection of the 4/1 bend

Country:HU - HungarySponsor:Paks NPPContractor:Paks NPP

Initiated:01.01.2000

Completed:31.12.2001

Project Leader:PINCZES, Janos

Last Updating: Funds:0

1. General Aim:The ultrasonic measurements performed on 4/1 bend of main circulating pipe-

line No. 1 of Unit 4 revealed that in the vicinity of the longitudinal welding seam on the short bend the wall thickness is by several millimeters less, than the design value. It is likely that during the manufacturing, the so called hard-facing welding being the part of the last phase, by which the part machined during preparation of the welding was to be filled, was not executed.

According to the strength calculations performed by HIDROPRESS in 1994 on the basis of the real values, the wall thickness is adequate, the conditions of the safe op-eration are not violated. During recent years the issue of the 4/1 bend was regularly raised between Paks Nuclear Power Plant and Nuclear Safety Directorate of the Hun-garian Atomic Energy Office, different possibilities were investigated seeking a long-term solution.

2. Particular Objectives and Research Program:The range of the solutions covered replacement of the bend, performance of

hard-facing welding for increase of the wall thickness, and regular inspections. The power plant has throughly analyzed all potential possibilities. As an outcome of the dis-cussions it became evident, that a reliable inspection, precisely revealing the condition of the welding seam and its vicinity shall be performed. It is possible that the final, ac-ceptable to both parties decision will be the regular mechanical ultrasonic inspection of the welding seams of the bend, which will be available by mechanizing the inspection of the primary circuit pipe-lines. The ultra-sonic inspection is the only possible solu-tion, since this is the method by means of which the full cross-section of the welding seam can be inspected with appropriate resolution. The mechanized inspection is neces-sary on one hand because the specifics of the complicated geometry and material struc-ture would make difficult the reliable manual execution of the inspection, while on the other hand the results of the mechanical inspection give more complete picture on the condition of the welding seam, and they can be re-evaluated at any time.

Characteristics of the bend, basic principles of the inspection

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The bend in question is a part of the coolant pipe-line. The bends were manufac-tured from 60 mm thick mark 08H18N10T plates. The vicinity of the location of the welding seams has been cut off under angle of 15° up to thickness value of 48-50 mm. The welding seams were prepared by means of protective powder welding. The bends were made with two welding seams. One seam was on the pressed side (shorter bend), while the other one on the stretched side (longer bend). In course of the wall thickness measurements performed in accordance with the inspection program it was revealed that in the direct vicinity of the welding seam on the shorter bend the wall thickness corresponds to the post-machining dimensions, i.e. the cut off part was not filled back during the welding process. According to the strength calculations this wall thickness is close to critical.

From material inspection point of view the close to critical condition means that the full cross-section of the welding seam shall be reliably inspected, in order to avoid unexpected failures. From point of view of the inspections beyond the complicated geo-metry the main problem is caused by the fact that the presence of the seam-crown pre-vents the direct inspection of the crown and its close vicinity. There is no possibility to access the anticipated errors (cracks) in accordance with the requirements for direct de-tection. It means that the seam inspection shall be actually divided into two parts, i.e. the inspection of the seam root and of the middle part of the seam can be performed by direct irradiation, while the inspection of the seam-crown by indirect (waves reflecting from the inner surface) irradiation.

Since the ultrasonic inspection cannot be deemed as an absolute inspection method, in order to get prepared for the inspections and analyses of the revealed defects it is un-ambiguously necessary to have such specimens one which contain artificial defects of known size and type. In course of preparation for the inspections the calculations relev-ant to the probably defects on the given equipment are prepared and on the basis of them a set of requirements is prepared, which include the types and sizes of the defects which are to be obligatory revealed during the inspections. On the basis of the criteria system, if necessary specimen (specimens) shall be made, by means of which the ad-equacy of the inspections can be proved, as well as certain parameters of the inspection system can be adjusted.

1. Experimental Facilities:

Preparation of the manual ultrasonic inspectionSince the tool needs and time required for preparation in case of manual ultra-

sonic inspections is only a fraction of similar needs of mechanical inspections it was deemed appropriate in the first phase to solve the issue of manual inspectability of the welding seams. An appropriate specimen was needed. Due to shortage of the time the power plant made a decision to borrow a qualification specimen, and though in late 1999 a "Finnish specimen" came to Paks for two months. This loop section with weight of almost 1 ton has several artificial defects (cuts) in the root of the short bend and is perfectly suitable for preparation of the inspection of the critical from professional point of view root range.

After time-consuming calculations and test-measurements it has been precisely determined from which positions might be the different parts of the welding seam in-spected. On the basis of the results such an inspection program was developed the exe-cution of which assures the reliable and adequate sensitivity inspection of significant part of the welding seam (with exception of the seam crown).Following preparation of the inspection technology a team, set up from specialists, who did not participate in the preparation has performed trial measurements on the Finnish specimen. The purpose of the trial measurements was to explore the weak points of the

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technology, as well as to determine what preparatory training was required for adequate execution of the inspection. The inspections executed during the year 2000 outages on the basis of the inspection technology did not reveal any, significant from operational point of view deviations in the welding seam.

Preparation of the mechanical inspectionsNaturally the Finnish specimen was used not only for analysis of questions re-

lated to the preparation of the manual inspection, but also the possibility of the mechan-ical inspection.

The performed measurements proved, that in spite of the geometrical difficulties the welding seam can be inspected with high accuracy.The report on the mechanical preparatory ultrasonic inspections performed on the Finnish specimen and on possibilities of execution of mechanical inspections was ac-knowledged by the Nuclear Safety Directorate of the Hungarian Atomic Energy Office, and they have prescribed for Paks NPP to prepare the relevant technology by November 30, 2000.

The analysis continued during the year 2000 outages as well indicated unam-biguously, that even the seam crown might be inspected. In order to assure the neces-sary level inspectability such a specimen was required on which there was a cut in the crown. The company decided to buy that loop piece from Greifswald, which includes the bend in question and practically is suitable for the preparation of the mechanical in-spection of the whole NA 500 nominal dimension pipe-line. Following arrival of the specimen in early autumn using the techniques proved on the reactor vessel of the Maintenance Training Center cuts were made on the external surface of the welding seam, in order to be able to calibrate the measuring heads by means of the known sized defects.On simplified models all such possibilities were investigated, by means of which the more delicate (or accessible with difficulties, or critical from the point of view of the anticipated defects) parts of the welding seams could be properly analyzed. The gained and deemed to be applicable possibilities were tested on the specimen as well, the actual geometry was limited, as well as the limits of the presently used mechanics. In spite of the relatively narrow traditional inspection head park the necessary level inspections were planned, as well as the inspection technology based on this was developed. A case of interest was for us, that with an inspection head, which was a bit bigger than appro-priate and had counter direction metallographic section we were able unambiguously indicate a tiny, approximately 2 mm deep cut from one-jump distance, about which we thought at the beginning that it will not be possible with this method.

All this means for us that the inspection of the 4/1 bend can be performed tem-porary with the presently available tools, though such inspections require very careful scanning. In practical sense it means that the inspection can be executed slowly, with several repetitions, but provides such information on the condition of the welding seam from which can be determined if further safe operation is possible or not.The authority approval of the developed inspection technology is in progress.We are convinced that during the outages in 2002 we will be able to use also phase con-trolled inspection heads as well during the inspections, furthermore that we will be able to work with such technology, that has been specially developed for inspection of pipe-lines and bends.

4. Computer Codes:

5. Progress to Date:

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The inspection of the 4/1 bend can be performed temporary.

6. Results:

7. Next Steps:

8. Relation with other Projects:

9. References:

10. Degree of Availability of the Reports:Paks NPP, H-7031 Paks, P.O.B. 71.

Images:

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(Image 1) Specimen from Loviisa

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(Image 2) Mechanical trial inspection on the Finnish specimen

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8.5. JSRI plots

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