{"title":"A hybrid model to deal with missing values in nuclear safeguards’ evaluation","authors":"Rosa M. Rodríguez, D. Ruan, Jun Liu, L. Martínez","doi":"10.1504/IJNKM.2011.040942","DOIUrl":"https://doi.org/10.1504/IJNKM.2011.040942","url":null,"abstract":"Nuclear safeguards’ evaluation aims to verify countries not misusing nuclear programmes for nuclear weapon purposes. This is a complex process in which the International Atomic Energy Agency (IAEA) uses information from different available sources. Initially, the research was focused on developing the evaluation framework to handle the complexity of the safeguards’ evaluation and the uncertainty inherent to the information involved. Consequently, different models were obtained to cope with the complexity by means of a multi-level hierarchical process, and the uncertainty managed by modelling the information linguistically. However, another challenge in nuclear safeguards is to handle the incomplete information due to the missing values that could bias the final evaluation results. There exist different strategies to treat missing values in nuclear safeguards. This paper presents a new approach for dealing with missing values that hybridises the previous ones to increase the trustworthiness of nuclear safe...","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"33 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130866931","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Failure possibilities for nuclear safety assessment by fault tree analysis","authors":"J. H. Purba, Jie Lu, Guangquan Zhang, D. Ruan","doi":"10.1504/IJNKM.2011.040940","DOIUrl":"https://doi.org/10.1504/IJNKM.2011.040940","url":null,"abstract":"Fault tree analysis (FTA) is a deductive tool to assess the safety of nuclear power plants. This analysis can only be implemented if all basic events in the tree have their corresponding failure rates. Therefore, safety analysts have to provide those failure rates well in advance. However, it is often difficult to obtain those failure rates due to insufficient data, changing environment or new components. This paper proposes a failure possibility based FTA approach to overcome the limitation of the conventional FTA for nuclear safety assessment. It utilises the concept of failure possibilities to evaluate basic event failure without historical data, fuzzy numbers to map component failure possibilities into mathematical form and defuzzification algorithms to convert fuzzy numbers into component failure rates. A case study on evaluating a typical high pressure core spray system of a boiling water reactor illustrates the applicability of the proposed approach.","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"91 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"134085353","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Mechanical property changes of VVER RPV materials embrittlement (tensile-Charpy properties)","authors":"D. Erak","doi":"10.1504/IJNKM.2011.040154","DOIUrl":"https://doi.org/10.1504/IJNKM.2011.040154","url":null,"abstract":"Tensile strength and Ductile-Brittle Transition Temperature (DBTT) are the essential parameters for the strength analysis of reactor pressure vessels at various stages of operation, as well as for the validation of the lifetime extension. This paper reviews the changes in yield strength and DBTT under irradiation on the example of the Russian RPV steels: VVER-440 (15KhMFA steel and welds) and VVER-1000 (15Kh2NMFA steel and welds) as well as the functional dependences, developed in the last 10–15 years, to determine the DBTT of VVER RPV steels. The review is based on papers selected by a group of experts under the EC Project ‘Nuclear Knowledge Preservation and Consolidation’, coordinated by JRC Petten.","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"118 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-05-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123093508","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Hitoshi Makino, K. Hioki, H. Umeki, H. Takase, I. McKinley
{"title":"Knowledge management for radioactive waste disposal: moving from theory to practice","authors":"Hitoshi Makino, K. Hioki, H. Umeki, H. Takase, I. McKinley","doi":"10.1504/IJNKM.2011.040157","DOIUrl":"https://doi.org/10.1504/IJNKM.2011.040157","url":null,"abstract":"The exponential growth in the knowledge base for radioactive waste management is a cause for concern in many national programmes. In Japan, this problem is exacerbated by a volunteering approach to siting of a deep geological repository, which requires particular flexibility in the tailoring of site characterisation plans, repository concepts and associated Performance Assessments (PAs). Recognition of this situation led, in 2005, to initiation by Japan Atomic Energy Agency (JAEA) of an ambitious project to develop an advanced Knowledge Management System (KMS) aimed to facilitate its role as the supplier of background R&D support to both regulators and implementers of geological disposal. The paper will review progress to date in this work, with emphasis on tailoring of existing Knowledge Engineering tools and methods to radioactive waste management requirements, and outline future developments and challenges.","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"126 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-05-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132055077","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"A historical review of WWER RPV embrittlement issues","authors":"M. Brumovsky, V. Nikolaev","doi":"10.1504/IJNKM.2011.040155","DOIUrl":"https://doi.org/10.1504/IJNKM.2011.040155","url":null,"abstract":"The paper tries to describe the history of the radiation effects study in WWER type reactor pressure vessels – from their design, manufacturing and operation point of view. The paper shows the time evolution and also institutions that were and are included in this research and development study. Main effort has been concentrated on development and realisation of steels and welding joint with low susceptibility to radiation damage as neutron fluences on reactor pressure wall in WWER type reactors are relatively high.","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"184 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-05-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124664207","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"WWER RPV embrittlement: start of life toughness","authors":"M. Serrano, J. Lapeña","doi":"10.1504/IJNKM.2011.040153","DOIUrl":"https://doi.org/10.1504/IJNKM.2011.040153","url":null,"abstract":"It is well known that neutron irradiation affects the properties of reactor pressure vessel material. The methodologies to assess the embrittlement of LWR (PWR, BWR and WWER types) are all based on the shift induced by irradiation of a reference transition temperature. This shift is obviously defined as the transition temperature (RTNDT or T k ) for the irradiated material minus the transition temperature for the non-irradiated material. This shift is measured by Charpy impact tests and applied to the fracture toughness reference curves. The main objective of this paper is to review the available literature on fracture toughness data of non-irradiated material, which is start of life fracture toughness for WWER reactor pressure vessels.","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"79 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-05-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125840862","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Post-irradiation annealing and re-irradiation review","authors":"A. Chernobaeva","doi":"10.1504/IJNKM.2011.040152","DOIUrl":"https://doi.org/10.1504/IJNKM.2011.040152","url":null,"abstract":"This paper summarises the review of 92 papers most of them selected from the ODIN database made within the framework of the project ‘Nuclear Knowledge Preservation & Consolidation, WWER – WS2’ managed by JRC EC. The papers contain the experimental results concerning postirradiation annealing and re-irradiation of WWER RPV materials. The results published in these papers have been obtained in RRC KI, VTT, NRI Rez, Forschungszentrum Dresden-Rossendorf, with the international cooperation between RRC KI, VTT-Fortum, JRC EC and ITEP, RRC KI and ORNL, and IAEA International Project. The following problems are examined in the review: evolution of RPV materials properties and structure under irradiation; recovery of irradiated RPV materials properties and structure under annealing; chemical composition effect on transition temperature of irradiated RPV materials recovery; effect of fluence on WWER RPV materials mechanical properties recovery due to annealing; microstructure evolution due to postirradiation annealing; effect of post-irradiation annealing on mechanical properties of irradiated WWER-1000 RPV materials; re-irradiation behaviour; surveillance programme for the post-annealing operation; assessment of the RPV state; technical problems concerning annealing; and licensing problems for annealing.","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"34 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-05-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131863709","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Problems and challenges of teaching nuclear energy physics in a small university","authors":"T. Lönnroth","doi":"10.1504/IJNKM.2011.040156","DOIUrl":"https://doi.org/10.1504/IJNKM.2011.040156","url":null,"abstract":"Internationally, new (classical) power plants are again being built, and a strong increase in the construction of new plants is expected in the future. In addition, there will soon be a demand for construction of more efficient ones, any of the six so-called Generation IV units, in an increasing number. On the contrary, the education of nuclear energy physics and techniques has stagnated, since little construction has been done over the last decades, and thus there has been little need of this kind of education. The paper presents the situation in Finland, especially the development that has been done over thelast 5 years at Abo Akademi University in Turku, south-western Finland. It shows that it is possible to set up a strong educational programme in nuclear energy and provides some guidelines as how to do it.","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"66 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-05-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114497968","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Environmental factors influence on RPV","authors":"Krassimira Ilieva","doi":"10.1504/IJNKM.2010.037072","DOIUrl":"https://doi.org/10.1504/IJNKM.2010.037072","url":null,"abstract":"Review of the results of research in the last decade on the influence of environmental factors on the materials of Reactor Pressure Vessels (RPV) of Russian WWER type of power reactors is presented. The reviewed papers are collected and electronically stored in a nuclear database ODIN.JRC.NL dedicated to knowledge preservation and consolidation. The open issues allow identifying future research activities needed in the area. The way of influence of the environmental factors as neutron fluence, neutron fluence rate, gamma rays and temperature, and their contribution on measured effects is summarised. The investigations attempt to fit an empirical presentation of the factors' dependence. The radiation field parameters are used for non-destructive evaluation of the radiation damage of reactor vessel and its internals and claddings, and therefore for planning ways for improving both operation and plant life extension. Harmonisation of calculation and measurement methods for use in WWER, PWR and BWR design and structural integrity assessments will help to maintain reliable and verified knowledge.","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"38 4 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2010-11-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"117250885","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Knowledge communication in internet age and its impacts on public perception of nuclear risk","authors":"Xingquan Wang","doi":"10.1504/IJNKM.2010.037076","DOIUrl":"https://doi.org/10.1504/IJNKM.2010.037076","url":null,"abstract":"The public perception of nuclear risk can sensibly sway political decision and policy making related to nuclear energy. Knowledge is generally considered as an important variable to change public perception, so to promote knowledge communication is a rational choice for all stakeholders in the political game. The era of internet knowledge communication is marked by the emergence of three models, namely network community, media convergence and cloud computing. By mapping of relations between these three models of communication and three versions of nuclear knowledge communicated by pro-nuclear, anti-nuclear and scientific stakeholders, some significant correlations can be identified: network community contributes to further self-organisation of anti-nuclear individuals; media convergence helps to optimise the communication efficiency of pro-nuclear groups; cloud computing facilitates the communication of scientific nuclear knowledge.","PeriodicalId":188437,"journal":{"name":"International Journal of Nuclear Knowledge Management","volume":"67 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2010-11-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115716150","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}