Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative

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1 Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative IAEA Headquarters Vienna, Austria Vienna International Centre Building M, Room M0E December 2015 Ref. No. 622-I3-TM WORKING MATERIAL

2 CONTENTS BACKGROUND INFORMATION... 1 Introduction... 1 Objectives of this technical meeting... 4 OPENING REMARKS AND OBJECTIVES OF THE TECHNICAL MEETING... 4 STATUS OF DEVELOPMENT OF A NEW IAEA FAST REACTOR KNOWLEDGE PRESERVATION PORTAL (FRKP PORTAL)... 5 SESSION I: MEMBER STATES AND INTERNATIONAL ORGANIZATIONS PRESENTATIONS... 7 SESSION II: FAST REACTOR TAXONOMY Results of Consultancy Meeting on the Taxonomy of Fast Reactors held on 7-8 December ANNEX I: List of Participants ANNEX II: Meeting Agenda... 20

3 BACKGROUND INFORMATION Introduction In response to needs expressed by Member States and within a broader International Atomic Energy Agency (IAEA)-wide effort in nuclear knowledge preservation, the IAEA has been carrying out a dedicated initiative on fast reactor knowledge preservation (FRKP). The main objectives of the FRKP initiative are to: Halt the ongoing loss of information related to fast reactors; and Collect, retrieve, preserve and make accessible already existing data and information on fast reactors. These objectives require the implementation of activities supporting digital document archival, data exchange, search and retrieval, as well as facilitating by developing and using advanced information technology tools knowledge preservation over the next decades. To this end the IAEA is developing a new web-based application employing IAEA methodology to categorize knowledge of fast reactors, allowing the creation of a comprehensive and well-structured international inventory of fast reactor data and information provided by Member States. The resulting web portal is being established and will be maintained by the IAEA. The IAEA knowledge preservation initiatives and tools in the field of fast neutron systems which were presented and well received during the recent International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) are designed to be of interest to national nuclear authorities, regulators, scientific and research organizations, commercial companies and all other stakeholders involved in fast reactor activities at national or international level. Starting in 2003, a number of meetings have been convened by the IAEA to implement the FRKP initiative: Technical Meeting to Preserve Fast Reactor Physics Knowledge held on May 2003; Consultancy Meeting on the IAEA Initiative to Establish a Fast Reactor Knowledge Base, held on 8 10 December 2004; Back-to-back Technical Meetings of the Coordinated Research Project on Analyses of and Lessons Learned from the Operational Experience with Fast Reactor Equipment and Systems, and on Coordinating the Agency s Fast Reactor Knowledge Preservation International Project in Russia, held on January 2005; Technical Meeting on Implementation of the Fast Reactor Data Retrieval and Knowledge Preservation Initiative, held on 28 November 1 December 2006; Technical Meeting on the Implementation of the Fast Reactor Data Retrieval and Knowledge Preservation Activities, held on December 2007; Technical Meetings to Coordinate the IAEA Fast Reactor Knowledge Preservation Initiative, held in 2008, 2009, 2010 and 2011; Consultants Meeting on the IAEA Coordinated Research Project Analyses of and Lessons Learned from the Operational Experience with Fast Reactor Equipment and Systems, held on January 2012; Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative, held on 3 5 December 2013; 1

4 Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative held on 2 4 December 2014; Consultancy Meeting to Update the Taxonomy of Fast Reactors Used in the IAEA Fast Reactor Knowledge Preservation (FRKP) Portal held on 7 8 December Member States continue to express an interest in contributing to the IAEA FRKP initiative. Each country has different methods of organizing and disseminating fast reactor related information and knowledge within their existing fast reactor organizations. Most Member States have been contributing to this initiative through the IAEA International Nuclear Information System (INIS), which allows the collection, processing, preservation and dissemination of bibliographic data and full texts of the world s nuclear literature. In some cases, Member States have provided documentation to the former Fast Reactor Knowledge Organization System (FR-KOS) system. To guarantee the continuous development of the FRKP Portal and to foster the FRKP initiative, an IAEA Technical Meeting on Status of IAEA Fast Reactor Data Knowledge Preservation Initiative was held on 9 11 December 2015 at the IAEA s Headquarters in Vienna, Austria. Results of the previous technical meeting held in 2014 The previous meeting took note of the fact that the new FRKP Portal is being developed with improved features and capabilities, and participants stated that they would appreciate full implementation of the first version of the Portal as soon as possible in order to make it accessible to this community in Each country has different constraints and policies that define the documents and information that can be provided to the IAEA FRKP initiative. With this in view, Terms of reference and conditions for Member States to provide information and documents to the FRKP Portal were developed at the meeting. The participants recommended clarifying with the governmental bodies of Member States represented in the Technical Working Group on Fast Reactors any specific requirements or prerequisites that may be needed to fully support provision of information to the FRKP Portal (e.g. a bilateral agreement). Letters in this regard were sent by the Department of Nuclear Energy to Member States in May With respect to protected information, it is acceptable, where possible, to provide the IAEA with metadata about documents along with appropriate contact information, rather than the full text of those documents. This will allow the fast reactor community to know that a particular document exists, and to have appropriate contact information if further information is sought. Bilateral arrangements can be established to arrange for the sharing of protected documents. To promote mutually beneficial and equitable contributions and use of the portal, it was suggested that the system be capable of providing metrics to identify contributions and use by the various Member States. Given the rapidly evolving technology the participants recommended that the IAEA undertake a revision of the existing taxonomy, i.e. the one reported in Fast Reactor Knowledge Preservation System: Taxonomy and Basic Requirements (IAEA Nuclear Energy Series No. NG-T-6.3, Vienna, 2008). To address this recommendation a consultancy meeting to update the taxonomy of fast reactors used in the FRKP Portal was planned be held on 7 8 December 2015 in Vienna, just before the Technical Meeting which is the subject of this summary report. The FRKP Portal 2

5 The FRKP Portal under development the previous version is known as the Fast Reactor Knowledge Organization System (FR-KOS) is currently located on the IAEA server and contains approximately articles. The FRKP Portal is accessible through registration with the IAEA NUCLEUS, the common access point to the IAEA's scientific, technical and regulatory information resources, along with access to the INIS library. The FRKP Portal, currently based on SharePoint2013, has been positively evaluated by the IAEA Division of Information Technology, but is still under development and will be fully implemented in It is envisioned that the Portal will enable control and management of both publicly available as well as restricted forms of information. It is expected that the target audience of the FRKP Portal will be experts and general users of fast reactor data and documentation. At previous consultancies it was recommended that the Users group should include several categories of users, including: Data providers; Taxonomy users; Readers. The FRKP Portal will provide users with authorized access to: Any fast reactor related documentation that Member States wish to share; Full papers and other materials of consultancies and technical meetings; Documentation from Coordinated Research Projects including the public and working materials; Old reports (which will remain available through the INIS repository); Document repositories on SharePoint. The end-users (typically the Member States that have a fast reactor programme) can upload their documents into the system with full control as far as setting permissions to access and download the documents. Control of the data security of the system will be the same as that already in place in the IAEA. In this regard the Member States are expected to trust the classified users. However, the Member States will, as noted, have the power to define the level of access for various users (e.g. definition of rights for other parties). Taxonomy for fast reactors The current taxonomy of fast reactors was developed in and needs revision. Currently the system uses the taxonomy developed about 10 years ago within the IAEA (see Nuclear Energy Series publication No. NG-T-6.3, published in 2008). However, in future it will be possible to install any taxonomy in the system, and perform a document search based on that particular taxonomy. The new IAEA taxonomy is based on international standards. The system allows searches to be conducted through the taxonomy. The future version will also allow auto- tagging of documents on the basis of the adopted taxonomy. A consultancy meeting to revise the taxonomy and obtain commitments to undertake this work by relevant stakeholders in the future occurred, as noted above, on 7 8 December at IAEA Headquarters in Vienna. 3

6 Objectives of this technical meeting The objectives of the technical meeting are to: Exchange information among Member States/international organizations on national and international initiatives that address knowledge preservation and data retrieval/collection in the field of fast neutron systems; Present and discuss the status of development of the new IAEA Fast Reactor Knowledge Preservation Portal (FRKP Portal); Present the results of the consultancy meeting on the taxonomy of fast reactors held on 7 8 December 2015; Present and discuss Member States and organizations policies and conditions for releasing to the IAEA both publicly available and confidential information on fast neutron systems resulting from the MS responses to the IAEA letter of May 2015; Establish the FRKP users group; Agree on further steps for development of the FRKP Portal. In particular, obtain commitments on provision of data to the FRKP Portal by the relevant stakeholders of the FRKP users group; Provide recommendations to further develop the FRKP initiative in the field of fast reactor knowledge preservation. OPENING REMARKS AND OBJECTIVES OF THE TECHNICAL MEETING The Scientific Secretary of the meeting and head of IAEA Nuclear Power Technology Development Section (NPTDS) Mr. Stefano Monti welcomed participants and opened the meeting. The list of meeting participants is reported in Annex I. Mr. Monti also introduced the co-scientific secretary of the meeting, Mr. Mikhail Khoroshev. Mr. Monti reminded that the FRKP initiative is a joint effort between the NPTD Section and the Nuclear Knowledge Management Section (NKMS) of the Department of Nuclear Energy which, among other, is in charge of developing and maintaining the knowledge management tools and platforms in the different nuclear technology fields and in particular in the area of fast reactors. The interest for this initiative was reconfirmed by the participants of the last FRKP meeting, as well as by the Technical Working Group on Fast Reactors (TWG-FR) in its last meeting in May this year. As a consequence, NKMS has been requested to continue allocating resources to this initiative. The NPTD section has been requested to continue organizing this meeting as an opportunity to exchange information among MSs interested in preserving knowledge in FR technology, as well as providing status of development of the available KP tools. Mr. Monti reminded meeting participants that IAEA developed the old FR-KOS system because of the interest of member states. However, the NKMS identified a number of issues with the FR-KOS system such as; maintenance, dependence on a single vendor, required training by vendor, lacked functionality, no support from IAEA IT office, user management issues, and lack of sustainability. For this reason NKM Section decided to shift to a new platform, based upon SharePoint 2103 server, which in particular can be more easily interfaced and linked to the NE INIS library. Mr Monti informed the participants that the new FR Portal will be presented by colleagues of NKMS after his introduction. 4

7 He mentioned that the success of this initiative is very much depending upon the MSs contribution to the FRKP Portal; the IAEA is very well aware that there are constraints and issues to be solved to make this happen. As a consequence there is the need to establish clear rules under which MSs are in the position to deliver FR data and documents to populate the FRKP Portal. A slot of time in the agenda was therefore allocated in order to discuss this point. Mr. Monti closed his remarks with an acknowledgement of the consultancy meeting on update the FR taxonomy, IAEA, 7-8 December He provided an overview of the taxonomy meeting. After a self-introduction of each participant, Mr. C. Grandy from Argonne, U.S.A., was appointed to chair the meeting. The meeting participants agreed with the meeting agenda prepared by the secretariat, which is reported in Annex II with the exception that the demonstration of the FRKP Portal would be conducted after the agenda activity, status of the development of a new IAEA Fast Reactor Knowledge Preservation Portal (FRKP Portal). In addition, the presentation by MS Ukraine was skipped because the Ukraine representative could not make the meeting. STATUS OF DEVELOPMENT OF A NEW IAEA FAST REACTOR KNOWLEDGE PRESERVATION PORTAL (FRKP PORTAL) Mr. D. Beraha, IAEA-NKMS, presented the status of the new IAEA Fast Reactor Knowledge Preservation Portal. The objectives of the FRKP portal as developed by the Nuclear Knowledge Management Section of the IAEA are: knowledge sharing; knowledge preservation; knowledge development; search and discovery; collaboration and communication. Knowledge bases user interfaces include Portals, Wikis, Web Sites and other applications. Rapidly increasing number of documents and limitation on free text search motivated the development of new tools and Portals. In particular, the following solutions and ongoing activities of NKMS were discussed: The establishment of a SharePoint development platform for NKMS; Installing Poolparty Server and Power Tagging including enhancement of taxonomies and thesauri with ontology features (classes, relations, attributes) and automatic tagging (manual intervention possible); Providing Semantic Search (enhance search with synonyms, relations, facets,...); Knowledge Base navigation and discovery: Webpart in SharePoint; External applications (API available); Development of several Knowledge Portals in addition to the FRKP, such as the severe accident management portal. The new pilot FRKP Portal that has been developed allows for: Document repositories on SharePoint 2013; Uploads by MS users themselves; Principle for Rights Management: Documents provided by MS will be in control of MS (e.g. definition of rights for other parties) ; Taxonomy to improve choice search terms; 5

8 Links for searching into other collections of information such as INIS, OSTI s Science.gov, etc. ; Designing the portal pages to improve functionality; Uploading and auto-tagging documents from IAEA and MS. Mr. M. Khoroshev provided a live demonstration on how to search and retrieve documents from the pilot FRKP Portal. The discussion which followed the presentation and live demonstration highlighted and clarified the following points and issues: The FRKP portal is envisioned to control and manage both publically available as well as restricted forms of information, unlike INIS which manages just publically available information; The new FRKP Portal replaces the FR-KOS system and has been upgraded from SharePoint 2010 to SharePoint The FRKP Portal will be administered by the MTIT (i.e. central IT office of the IAEA); Currently the system uses the taxonomy developed about 10 years ago within the IAEA (see NES No. NG-T-6.3 published in 2008). However, the taxonomy will be upgraded to the new taxonomy which is expected to be available in 2016; The new IAEA taxonomy will be based on international standards; The FRKP Portal is able to access the INIS library using the fast reactor descriptor, but also other databases; The system also allows to search through the taxonomy; The new FRKP portal allows for auto-tagging of the documents on the basis of the adopted taxonomy; Wiki-pages can be created; The end-users (typically the MSs with a FR programme) can upload their documents into the system having full control as far as setting the permissions to access and download the documents, although the rights permission policy needs to be developed by IAEA; The new FRKP has the capability of uploading a single document, multiple documents, and documents in folder structures. In case of uploading of a huge amount of documents from an external database (for instance from the FRKP system of a MS) a specific interface script can be written and used; All searchable document formats can be uploaded; As for any SharePoint application, there is the possibility to automatically inform the users of any new uploading (this is an optional feature); Once the system will be populated with documents from MSs, it is possible to implement a feature to categorize the documents by supplying country; The system is under the control of the IAEA MTIT and therefore the level of security will be the same as for any other IAEA IT system; The FRKP Portal will be accessible through registration by the IAEA NUCLEUS; The system is designed for the use by a specific community; however in principle webpages providing general information about the FRKP portal can be also created and published. 6

9 SESSION I: MEMBER STATES AND INTERNATIONAL ORGANIZATIONS PRESENTATIONS Presentations on current initiatives on fast reactors knowledge management and preservation were given by Member States representatives. Summaries of the given presentations are provided below. Belarus Mr. Y. Fokov (Joint Institute for Power and Nuclear Research-Sosny) Mr. Fokov, on behalf of the Joint Institute for Power and Nuclear Research-Sosny, National Academy of Sciences of Belarus, gave a presentation on the research in the field of subcritical systems with fast neutron spectrum. His presentation covered the research of his institute, the investigation in the field of accelerator driven systems at the subcritical assembly YALINA-Booster, and the development of an advanced concept of a subcritical facility with a fast neutron spectrum. The JIPNR-Sosny s research of nuclear power plants is going on since the 1960 s. A lot of zero power critical assemblies with both thermal and fast-thermal spectra have been set up. The research also included the development and creation of the mobile nuclear power plant, PAMIR, and working out the concept of a gas-cooled fast reactor. The scientific research in the field of nuclear reactor physics started in the 1960 s with the 1000kWt research reactor, IRT. This reactor was later upgraded to 4000kWt. The research at this reactor was stopped in In the 1990 s, Belarus initiated research of accelerator driven system (ADS). The potential was proved to use low energy ion accelerators to study ADS neutronics, kinetics, and transmutation technologies. ADS experiments were performed at the YALINA facility, specifically, at two zero power subcritical assemblies, YALINA-Thermal and YALINA-Booster. The YALINA facility is used for developing experimental techniques for monitoring of sub-criticality levels, to study the spatial kinetics of ADS systems, to gain experience in the maintenance and operating performance of ADS and to measure the transmutation reaction rates of minor actinides and fission products. The YALINA-Booster facility was put into operation in 2005 for fast-thermal neutron spectrum research. The research conducted has shown that the application of reciprocal counting method allows to run fuel loading in a safe manner. Pulse neutron source technique has an advantage that both reactivity and the prompt decay constant is obtained from same set of experimental data. In addition, the reliability of subcritical level estimation by PNS method goes up with rise of assembly s k eff. The research at the YALINA facility is being continued by using different fuel compositions and geometry. These configurations have a k eff ~ The assembly could be used to develop experimental techniques for monitoring of sub-criticality, neutron spectra measurements, to study of spatial kinetics of sub-critical systems with fast neutron spectra, and to measure transmutation reaction rates of minor-actinides, among others. Mr. Fokov will verify the conditions for supplying information and documentation on their research and development to the FRKP Portal. China Mr. Y. Xu (CIAE) Mr. Xu, on behalf of China Institute of Atomic Energy (CIAE), gave a presentation on fast reactor knowledge preservation and data collection activities in China. As a fast reactor developing country, China has a strong desire to develop fast reactor technologies to realize its national nuclear development strategy. In this process, fast reactor knowledge preservation and management plays an 7

10 important role neither for the development of the organization nor the research level improvement of the CIAE staff. After the brief introduction of the CFR-600 design progress and the status of CEFR operation in 2015, the fast reactor knowledge preservation and management was the focus in the presentation. China have set up a preliminary fast reactor knowledge preservation and data collection system, which mainly covers the FR design,operation and R&D activities, but with the development of the IT technology and the need of knowledge management, it is a long term to update it well and perfect. The main characteristics of the FR knowledge management can be concluded here: MatrixOne system, which is mainly used for the new reactor design CFR-600, has the documentary management function as well as the design project management function. All the design activities and the results can be finely controlled through this system. CEFR Operation and Maintenance Management Platform, which is updated according the need of reactor operation, maintenance and experience feedback, can realize the functions to record all the real time operation data of CEFR and all the equipment maintenance administration activities. Fast Reactor Intellectual Property Rights Information Platform, as the important supporting tool for fast reactor R&D activities in CIAE, provides the latest patents and science and technology literature retrieval information in the world which is useful for the CEFR staff. As a new platform, it is also under construction to fulfill the future need. At last, it is pointed out that the digitization of FRKP provides an efficient way of information store, duplication, transfer and utilization. As a fast reactor developing country, China will strongly support the FRKP initiative and give more contributions to the new-generation FRKP portal construction. Of course, it is better for CIAE to be national focal points for the new FRKP portal. CIAE has the capabilities to do it well and this will enhance the communication among the FR community on FRKP. Germany: Knowledge Preservation and Data Collection at KIT Mr.K. Litfin (KIT) K. Litfin from the Karlsruhe Institute of Technology gave a presentation on the German contribution to the Fast Reactor Knowledge Preservation Initiative. In the past, two fast research reactors operated in Germany, KNK I from and KNK II from After the decline of fast reactor programs in Germany, data from KNK I and KNK II was transferred to the IAEA in 2003 and used as one cornerstone of the Fast Reactor Knowledge Preservation Initiative. Most of the data is also hosted by the KIT library. Besides that, new Fast Reactor related knowledge is produced in the framework of national and international programmes and projects involving topics as safety research or transmutation. It was emphasized that this data is also very valuable for Fast Reactor research and should also be addressed by this initiative. The question of intellectual property indeed is an open question that has to be discussed. Italy: Mr. G. Grasso (ENEA) In the field of Fast Reactors, the Italian background is concentrated upon two experiences. The first one ending up in the late 1980s was focused on the sodium-cooled fast reactors technology, 8

11 encompassing the participation to the Superphénix-I consortium and the commitment to the realization of the PEC (Fuel Element Testing in Italian acronym) reactor. The second one, relaunched since early 2000s, is focused on the lead-cooled fast reactor technology, through the design of ALFRED as European demonstrator of this technology. The preservation, sharing and continuous update of the knowledge accumulated and being continuously generated on fast reactor entered the spotlight of ENEA, as main responsible for the activities related to the Italian experiences in fast reactors. A priority program to recover, secure and transform in electronic form the entire archive of the PEC reactor which includes information on supporting experiments, design activities (from conceptual to construction), plant construction and project management has been approved recently, and will be implemented starting Following this work, the archive shall be extended to the whole documentation generated in the context of the present experience on lead-cooled fast reactors. Italy acknowledges the relevant role of the IAEA in supporting knowledge preservation initiatives, and confirms its intention to share, through the FRKP Portal, the information that will be recovered along with the creation of the new digital archive of ENEA dedicated to fast reactors. During the population of the archive, the classification level of each document will be re-evaluated (notably to what concerns the PEC documentation), considering as strategic the possibility to provide a relevant contribution to the Portal. For documents that will still need classification, information sheets containing bibliographic and meta-data will be anyway produced and released to IAEA for inclusion on the Portal, in the perspective that disclosure of this information will still be possible upon proper bilateral agreements with interested parties. Japan: Mr. H. Ohira (JAEA) In this technical meeting, JAEA mainly explained the structure of Japanese contribution to IAEA/INIS, and the methods of data provided, preserved and collected by other means. The data provided form JAEA to INIS as the National Center of Japan, by collecting data from IMIC, JST and JAEA, are approximately more than 5,000 in every year. The brief search results of INIS indicated that Japan had made a great contribution to supplying documents about FR area, and further detail search results of INIS by using keywords of JOYO, MONJU and JSFR indicated that documents concerning these reactors had been well issued in countries/organizations out of Japan and these results implied a great deal of global interests in Japanese FRs. Other providing, preserving and collecting methods were also introduced in the presentation, which were Web-based information concerning JOPSS and Training and education for the sodium handling and training, International cooperation concerning IAEA s CRPs and TMs, and knowledge management system in JAEA concerning Design & Maintenance Documents for MONJU, Data Acquisition Systems of MONJU and JOYO, and Component Reliability Database for PSA. JAEA explained the requirements and prerequisite for FRKP Portal to IAEA, which were already replied from Japan s government, and required the reply from IAEA. Then JAEA also explained the outline of providing information from Japan based on the present status of SFR development of Japan, i.e. The possibility of loss of information related fast reactors is quite low since JOYO and MONJU are respectively in operational preparation and under construction phase. Finally, JAEA summarized the JAEA s knowledge preservation activities as follows; Japanese FRs are stepping up from JOYO to MONJU and JSFR with efforts to overcome the 9

12 Fukushima #1 NPP accidents, including focus on ensuring and enhancing safety of these FRs, Japan (JAEA) has made continuous and considerable efforts to supply FR information to IAEA/INIS, JAEA has also contributed to a global dissemination of its R&D activities through JOPSS English version, which will be beneficial to worldwide FR development, IAEA s CRPs and TMs, and other international collaborations, and Database of design, operation and licensing data of JOYO, MONJU, JSFR and other test facilities should be consolidated in the future. The collection of components reliability data will be continued. Requirements for FRKP Portal to IAEA were already replied by Japan s government, and the outline procedure for providing data was also explained in this presentation. The FRKP users in Japan will be decided soon after the reply from IAEA. Republic of Korea: Mr. Y. I. Kim (KAERI) Mr. Kim presented knowledge preservation and data/retrieval activities on fast reactors in Korea. First, He presented the overview of main achievements in the SFR technology development in Korea. The SFR technology development was commenced in The KALIMER-600 concept, selected as one of the Gen-IV SFR concepts, is given as a remarkable technological achievement. Based on the experiences gained through the development of KALIMER conceptual designs, the prototype SFR, PGSFR is being developed by KAERI from 2012, aiming at its design approval in 2020, with its target deployment in He briefly presented the INIS information collection and related service. KAERI, as a national INIS Center, has made a continuous contribution to providing fast reactor information to IAEA/INIS. He presented the nuclear knowledge management activities at KAERI. KAERI commenced the nuclear knowledge management project in 2011, carrying out the Nuclear Technology Archives Project as the main activity. Through the Archives Project, whole historical and technological items from background to achievement in KAERI are to be archived, and a comprehensive knowledge transfer system and R&D base are to be established. Total 96 projects are archived for documenting the experience and know-how acquired until SFR knowledge, as a valuable intellectual asset, was archived, retrieved and preserved in 2012 through the institutional knowledge management system DADAMS at KAERI.SFR knowledge mainly on the PGSFR design development is being collected and managed through ANSIM and S-RIMS under the PGSFR Development Project in KAERI. At present PGSFR design documents and data are produced, stored and managed in ANSIM according to QA requirements, which will contribute to the specific design and design licensing. The other documents and data are stored in S-RIMS, which serves the process management system. Romania: Ms. D. Gugiu (RATEN ICN) Since 2007 Romania is actively involved in various European Projects dedicated to innovative fast reactors technology with a focus on Lead-cooled Fast Reactors. The accumulated expertise of RATEN ICN (Institute for Nuclear Research) as well as the interest of various European organizations (ANSALDO (Italy), ENEA (Italy), RATEN (Romania), CVR (Czech Republic), SCK*CEN (Belgium), KTH (Sweden) led to the initiative to build the ALFRED Demonstrator in Romania. 10

13 As a result, a significant number of scientists from RATEN ICN are involved in the on-going European projects related to fast reactors (ESNII+, MAXSIMA, MATTER, ARCADIA ) as well as in a large number of R&D activities developed under the National Program Advanced Nuclear Reactors and Fuel Cycles. Recognizing the importance of IAEA s initiative regarding the development of Fast Reactors Knowledge Preservation Portal, Romania through its Governmental Representative Nuclear Agency and for Radioactive Waste agreed (by an Official Letter sent to IAEA) to preserve and make accessible the existing information on Fast Reactors within the framework proposed by IAEA. The contribution to FRKP Portal will consist mainly in documents related to FRs activities developed in the frame of bilateral and international projects/cooperation and the National program (R&D and experimental activities in support of fast reactors technologies). Moreover, a knowledge management portal is developing in RATEN ICN being designed to allow: simple exchange of information, search in structured/unstructured document compilations, archiving and distributing information, support for management, access to all relevant documents, (e.g. databases, archives), discussions/forums, etc. The portal is based on Windows Server 2008 R2, Windows SharePoint Foundation 2010, Windows SQL Server It consists on two servers one with database server role and the other with SharePoint server role, both coupled to the internal RATEN ICN INTRANET. The structure consists in libraries, folders and sub-folders based on the type of activities (one of them being represented by fast reactors field). Documents are open with the appropriate software tool depending on the document format. Some documents are available in image format only (e.g. procedures, drawings etc.), and some are available in fully searchable PDF format (e.g. technical specifications, research reports etc.). Search and retrieval functions are also implemented. The portal has a defined access rights system based on the facilities offered by Windows SharePoint Foundation 2010, anonymous access being prevented. Based on the level of access of various group of users the following operations are allowed: only read, read or download documents and read, download and upload. A team of scientists (having expertise in various fields of fast reactors technologies) has been created (based on an Official Decision of the General Director of RATEN ICN) having as responsibilities the analysis, selection and preparation in the appropriate format of the most representative documents related to fast reactors activities performed in the organization in order to be stored in the IAEA FRKP Portal. Russia:ROSATOM knowledge management approach: preservation of knowledge on fast reactors Mr. S. Iugai (Rosatom) At present, management of data, information and experience gained is an integral part of the successful development of any company just like management of finances, property and human resources. In the Russian Federation the State Atomic Energy Corporation «Rosatom» is in charge of safe and continuous operation of NPPs and electricity generation as well as of development and deployment of non-power applications of radiation technologies. In course of its operation ROSATOM establishes the common logic of managing the knowledge resources through the all life cycle stages of nuclear facilities and technologies, including the fast reactor domain. 11

14 ROSATOM distinguishes the following stages of the knowledge lifecycle: Knowledge Creation and Capture, Knowledge Formalization and Preservation, Intellectual Property Rights Identification and Protection, followed by Knowledge Commercialization which is beyond the scope of the present Technical Meeting. For every stage mentioned, specific methodologies and tools are developed to enable Management of the Communities of Practices, Management of the Scientific and Technical Content, and Management of the Intellectual Property Rights. Under the Management of the Communities of Practices activity ROSATOM makes use of the methodology to capture and preserve the critical knowledge based on the risk analysis of potential knowledge loss, knowledge and competence mapping, and to develop relevant multimedia products, as well as of the crowd sourcing technologies; the dedicated tool for this stage is the Corporate Expert Network deployed using the MS SharePoint Management of the Scientific and Technical Content methodologically is based on the corporate taxonomy, which in turn relied upon the IAEA Fast Reactor taxonomy; mobile digitizing centers are used to convert paper documents into the electronic format and to incorporate them to the electronic library being an integral part of the Corporate Portal of Scientific and Technology Information. The Corporate Portal also provides access to the IAEA INIS documents. Management of the Intellectual Property Rights encompasses the technologies of capturing, accounting and protection of Intellectual Property Rights with regard to the results of R&D; creating the Technology IPR Portfolios enabling protection of rights according to the national and international legislations; special Information System for Management of IPR is in place. The above described knowledge resources management concept is applied to both research organizations and universities, and the divisions of ROSATOM s principal business such as electricity generation, uranium mining and production, and fuel fabrication. To facilitate involvement of personnel into the critical knowledge preservation activities, and to promote the knowledge management culture ROSATOM set up a series of regular educational courses, business simulation modules, publications related to nuclear knowledge management. ROSATOM actively cooperates with the IAEA on nuclear knowledge management both in methodological aspects and various practical activities. To further strengthen cooperation with the IAEA in the nuclear knowledge management, including fast reactor knowledge preservation, ROSATOM intends to elaborate corporate rules of information exchange with respect to fast reactors domain. U.S.A.: Fast Reactor Knowledge Preservation Efforts - Overview Mr. C. Grandy (ANL) Mr. Grandy, Argonne National Laboratory, provided an overview of the U.S. fast reactor research elements being performed under the Department of Energy's Office of Nuclear Energy. The R&D program is guided by the goals outlined in the current Nuclear Energy R&D Roadmap. The components of the Advanced Reactor Technology program, with particular focus on fast reactor topics were described. Knowledge management in this area is extremely important in the U.S. recognizing that the U.S. investment in fast reactor research and technology development, the fact that the U.S. has not operated a domestic fast reactor for roughly 20 years, and does not currently have a domestic fast reactor project. The knowledge management program has been on-going for over 10 years. 12

15 DOE's activities in the fast reactor domain are currently part of a long-term research, development and demonstration program that is intended to provide long-term fuel cycle options and further improve the long-term sustainability of nuclear energy, as well as to provide safe, cost effective and improved future reactor technologies to facilitate the expansion of nuclear power. In the U.S. in some areas there is a limited window of opportunity to capture tacit knowledge and "know how" from the older generation of individuals with actual "hands on" experience. This limited pool of individuals is rapidly retiring or becoming unavailable. The recovery and evaluation of TREAT experimental and FFTF operational data is a good example of this. Mr. Grandy provided an update on several activities that are underway to recover technical information and data from previous operations and experiments and to digitize this information to make it more easily disseminated. Specific examples include EBR-II and FFTF reactor tests, TREAT reactor experimental data, data from fuels and materials irradiation tests, and component reliability data. These activities also include the recovery of plant data from old magnetic data tapes that require special handling to recover and use their information. Currently, data recovery from these tapes is predominantly being performed by colleagues at Pacific Northwest National Laboratory. In some cases specific actions were needed to capture, protect and preserve valuable historical information that was at risk of being irretrievably lost. In other cases it was clear that expert knowledge was required to properly interpret or clarify historical data. The historical information and data also supports the development, validation and verification of improved models and high performance computer simulations, and would be very difficult and costly, if not impossible to recreate. The IAEA Coordinated Research Project on EBR-II Benchmarks is a current example of how the historical data can be used to improve current and future fast reactor design and safety methods and predictive tools. The fast reactor knowledge preservation efforts are also targeting collections of documents with a current and sustained focus on DOE s Office of Scientific and Technical Information (OSTI). The mission of the DOE Office of Scientific and Technical Information (OSTI) was described. OSTI (and its predecessors) was established in 1947 in Oak Ridge, Tennessee and is responsible for ensuring access to the results of DOE R&D to the appropriate stakeholders. OSTI collects and controls access for unrestricted (publically available) information as well as "restricted" information (either classified or limited in some other way). OSTI also serves as a portal for linking scientific information across, DOE, across government or scientific institutions, or across international organizations. There is a strong foundational relationship between OSTI and INIS, for example. These efforts, along with international cooperation and the Nuclear Energy University Program, are supporting the development of the next generation of subject matter experts and helping to assure that future nuclear technologies are informed and improved based on the experiences of the past. SESSION II: FAST REACTOR TAXONOMY Results of Consultancy Meeting on the Taxonomy of Fast Reactors held on 7-8 December 2015 Mr. Liftin provided a summary of the taxonomy meeting and Mr. Grandy reviewed the revised taxonomy. The consultancy meeting on development of a revised taxonomy of fast reactors was held on 7-8 December 2015 just before this technical meeting. 13

16 As reported by Mr. Litfin, the primary objectives of the taxonomy meeting were to revise and update the FR taxonomy / ontology developed almost 10 years ago and provide recommendations for further update of FR taxonomy used in the IAEA tools including the FRKP portal. The reasons for restructuring the FR taxonomy are manifold: the newly organized taxonomy should be able to support improved search functionality, provide the foundations for developing a comprehensive knowledge base, and be applicable within the SharePoint Portal. The original taxonomy does not lend itself to these tasks, since it lacks some of the features such as a consistent hierarchy; also, the frequent repetition of concepts presents difficulties when interpreted by machines. The taxonomy of fast reactors is a key element of designing the FRKP portal, while it allows using the new capabilities of semantic search in the Agency wide tools developed jointly by nuclear knowledge management section and NPTDS. Seven experts from seven countries prepared the first draft of the updated taxonomy. Preparatory work done by the NKMS (re-structured FR taxonomy) facilitated this work, because it took into account the new software allowing extended capabilities in tagging and searching documents allocated in the portals. At this meeting modifications and extensions to the re-structured FR Taxonomy were introduced. During the discussions definitions of the taxonomic concepts, links between related concepts within the taxonomy have been considered and incorporated as appropriate. The FR taxonomy should be further elaborated. For the completeness of the FR taxonomy it is recommended to further enhance the basic taxonomy with relevant links to FRKP and external information resources, e.g. other relevant websites. Connection to the most relevant documents and concepts should be incorporated, and collection of any other information assisting in characterizing the given concept should be continued. Mr. Liftin reviewed the list of proposed actions from the Taxonomy meeting as follows: Use the glossary provided by the IAEA for proper definition of the items Modifications and extensions of concepts Add definitions to the taxonomic concepts Links between related concepts within the taxonomy Provide additional information o Links to external information resources relevant to the concepts, e.g. other relevant websites o Connection of the most relevant documents and concepts o Collection of any other information assisting in characterizing the given concepts Consultants recommended that another consultancy meeting be held in the March 2016 timeframe to elaborate on the FR taxonomy document and prepare the related NES publication. This timing was discussed in detail by Mr. Monti and others. The taxonomy may also be shared with other MS through the TWGFR. Mr. Grandy provided an overview of the new draft taxonomy. The new taxonomy is created by listing high level concepts related to fast reactors and then breaking down those high level (parent) concepts into finer and finer concepts that allow for the organization of documents and information into finer detail. In addition, Mr. Grandy discussed that concepts can be linked where appropriate to 14

17 establish relationships between concepts and to avoid duplication of concepts within the taxonomy. The software adopted by IAEA is most effective at organizing collections of documents by a particular taxonomy if the concept terms are not replicated in the taxonomy. One of the future efforts will be to provide definitions of the concepts using standard definitions where available. IAEA Secretariat plans to submit in January 2016 a Document Preparation Proposal (DPP) for an updated NES publication on fast reactor taxonomy. The revised fast reactor taxonomy will be sent to the members of the TWG-FR with request to provide comments and feedback to be reported at the next TWG-FR meeting in May The results of the comments and feedback will be taken into consideration during the second consultancy meeting to update and finalize the taxonomy targeted for June At the second consultancy meeting, the final NES publication will be drafted. CONCLUSIONS AND RECOMMENDATIONS 1. There continues to be interest by the Member States in contributing to the IAEA FRKP initiative. Each country has different methods of organizing and disseminating their fast reactor related information and knowledge within their existing fast reactor organizations. 2. Most Member States have been contributing to this initiative through the IAEA INIS system which allows to collect, process, preserve and disseminate bibliographic data and full texts of the world s nuclear literature. In some cases, Member States have provided specific documentation to the former FR-KOS system. 3. The meeting reviewed the details of the new FRKP Portal being developed with improved features and capabilities. Participants appreciate that IAEA has fully implemented the first version of the FRKP portal in Sharepoint The portal is based upon MS Sharepoint Services and has all the functionality of a Sharepoint site. The portal is distinct from INIS and other repositories, but can search into these repositories via a click of a button. 4. It is strongly recommended that the connection between FRKP, INIS, and other large collections be strengthened to ensure full semantic search capability of FRKP is utilized. 5. Each country has different constraints and policies that define the documents and information that can be provided to the IAEA FRKP initiative. Some countries have responded to the IAEA Member States letter dated May 2015 and some have not yet. It is important for Member States to communicate any special requirements for providing limited access documents into FRKP. Each MS needs to provide the assigned country point of contact for the Portal. 6. Japan has sent a letter in response to the May 2015 letter with request for additional requirements. IAEA will prepare a response to Japan s request after consultation with appropriate sections within IAEA and clarification of the requirements from Japan. 7. As discussed in the meeting, there are still collections of documents and other information that is considered at risk of being lost or destroyed. This documentation is typically in countries and locations that don t currently have active fast reactor projects. As already noted on the occasion of the previous TM, examples of at-risk collections are the PEC reactor documentation in Italy (although this is nearing resolution), the fast reactor program information in Karlsruhe, Germany, the DFR and PFR reactor information in the U.K., and BN-350 reactor and decommissioning information in Kazakhstan. 8. As discussed previously, with respect to protected information, it is acceptable, where possible, to provide IAEA with metadata about the document and appropriate contact information rather than the full text document. This will allow for the FR community to know 15

18 that a particular document exists with appropriate contact information for the protected document. Bilateral arrangements can then be established to arrange for the sharing of protected documents. 9. To promote mutually beneficial and equitable contributions and use of the portal, it is suggested that the system be capable of providing metrics identifying contributions and use by the various Member States. 10. IAEA should create a template for capturing document metadata for those documents, open or limited distribution, which will not be placed on FRKP portal. 11. IAEA needs to create an implementation policy for establishing how each member state will be allowed to enforce access rights to documents and/or collections of documents. 12. It is recommended that the FRKP portal allow for searching other fast reactor archives such as the JAEA Originated Papers Searching System (JOPSS) and the Transient Reactor Test Facility (TREAT) databases once available. 13. IAEA will create a procedure for access to the FRKP Portal sharepoint site. The access procedure should follow the following general guidelines: a. Each country will identify a contact person(s) (MS PROVIDER) who will be coordinating their countries contributions to the FRKP portal b. The provider will coordinate with IAEA the list of personnel who can access Nucleus who have access to the FRKP portal. These people will be the FRKP Portal General Users c. The IAEA will create two folders/subsites for each country an unrestricted folder and a restricted rights folder d. For restricted rights folder/subsite IAEA will create owners of folders/subsites and subfolders( Project Owners ) who will have permission to authorize personnel access (from the FRKP portal list) who have access to the restricted folders/subsites and subfolders. Each folder/subsites and/or subfolder can have individual access rights. IAEA needs to determine if folder owners will have access rights permissions or if IAEA personnel will grant owners authorization rights. Permission for granting access rights will be in consultation with MTIT. 14. The following personnel are considered the first set of MS PROVIDERS: a. Argentina O. Azpitarte (CNEA) b. Argentina J.Villanueva (CNEA) (alternate) c. Belarus Y. Fokov (JIPNR-Sosny) d. Belgium D. Couvreur (SCK CEN) e. China Y. XU (CIAE) f. China Ms Y. Xia (CIAE) (alternate) g. Germany A. Rineiski (KIT) h. Germany K. Litfin (KIT) (alternate) i. Germany A.Seubert (GRS) (alternate) j. India R. Jehadeesan (IGCAR) k. Italy G. Grasso (ENEA) l. Japan H. Ohira (JAEA) m. Korea Y.I. Kim (KAERI) n. Romania D. Gugiu (RATEN ICN) o. Russia S. Iugai (ROSATOM) p. Russia A.Sorokin (IPPE) (alternate) q. Switzerland K. Mikityuk (PSI) r. USA C. Grandy (ANL) 16

19 15. The current FRKP portal has already been populated with sites of the recent CRPs and recent studies such as the compendium of liquid metal testing facilities. It is also recommended that the site be populated with documentation from TWG-FR meetings, current and historical. 16. It was recommended that pdf format documents uploaded to the portal be in a searchable format. 17. The meeting participants acknowledged the work to develop the new FR taxonomy for FRKP portal. The next annual technical meeting of this initiative will take place in the 4 th quarter of 2016.Exact dates and information about the knowledge preservation activities and potential participants in this work will be provided by the IAEA secretariat to the TWG-FR at the next meeting. It was discussed that meeting may be held in October 2016 to facilitate finalization of the FR taxonomy to ensure resolution by December At the end of the meeting Mr. Grandy, chairman of the meeting, and Mr Monti thanked the delegates for their very appreciated contributions to the meeting, and the useful recommendations which the IAEA secretariat will try to implement in the forthcoming months. 17

20 ANNEX I: List of Participants Belarus Mr Fokov Yurii, China Mr Xu Yijun, Germany Mr Litfin Karsten, Japan Mr Ohira Hiroaki, Korea, Republic of Mr Kim Young In, Romania Ms Gugiu Daniela, Elena, o Russian Federation Mr Iugai Sergei, Joint Institute of Energy and Nuclear Research, SOSNY Academician A.K. Krasin, 99 MINSK BELARUS Tel: fokov@sosny.bas-net.by China Institute of Atomic Energy (CIAE) China National Nuclear Corp. (CNNC) P.O. Box Fangshan BEIJING CHINA juntaxu2008@163.com Karlsruhe Institute of Technology Hermann-von-Helmholtz-Platz EGGENSTEIN- LEOPOLDSHAFEN GERMANY Karsten.litfin@kit.edu JAEA 1 Shiraki TSURUGA JAPAN ohira.hiroaki@jaea.go.jp KAERI 111, Daedeok-daero 989 beon-gil Yuseong-gu DAEJEON KOREA, REPUBLIC OF yikim2@kaeri.re.kr Institute for Nuclear Research Pitesti Campului Street No. 1 PO Box MIOVENI ROMANIA daniela.gugiu@nuclear.ro State Atomic Energy Corporation "Rosatom" 24 BolshayaOrdynka St MOSCOW RUSSIAN FEDERATION SVYugay@rosatom.ru 18

21 Ukraine Mr Fomin Sergii, United States of America Mr Grandy Christopher, IAEA Scientific Secretary Mr Stefano Monti Akhiezer Institute for Theoretical Physics; National Science Center 1, Akademicheskaja Street KHARKIV UKRAINE Argonne National Laboratory (ANL) 9700 S. Cass Avenue ARGONNE, IL UNITED STATES OF AMERICA IAEA Mr Mikhail Khoroshev IAEA Mr Chirayu Batra IAEA Ms AtiehTagrid IAEA Mr David BerahaMenahem IAEA Mr Maxim Gladyshev 19

22 ANNEX II: Meeting Agenda TECHNICAL MEETING ON STATUS OF IAEA FAST REACTOR KNOWLEDGE PRESERVATION INITIATIVE 9 11 DECEMBER 2015 IAEA HQ, VIENNA. BUILDING M, MEETING ROOM M0E100 AGENDA Scientific Secretary: Stefano Monti 20

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