XXXX第15届国际核安全与仿真大会会议日程

1、THE 60TH ANNIVERSARY CEREMONY OF HARBIN ENGINEERING UNIVERSITYTHE 15TH INTERNATIONAL WORKSHOP ON NUCLEAR SAFETY AND SIMULATION TECHNOLOGY(IWNSST2013)August 30th - September 1st, 2013Harbin Engineering UniversityProgram Overviewn Date: August 30th -September 1st , 2013n Place: Meeting Room 370, 31#Bl

2、dg, Harbin Engineering Universityn Organizer: Harbin Engineering University (HEU)n Cooperating with:111 Project on Nuclear Power Safety and SimulationInternational Journal of Nuclear Safety and Simulation (IJNS)n Topics：(1) Lessons learned from the Fukushima Dai-ichi Accident(2) Progress in the deve

3、lopment of advanced technologies for improving nuclear safetyn Hotel Information: Hotel Name: ZhengMing JinJiang HotelHomepage: http:/www.zmjj-Address: 278 Dongdazhi Street,Nangang District,Harbin,P.R.ChinaTel: (86-451)-53618888 Fax: (86-451)-53618899n Airport Pick UpThe workshop organizer will arra

4、nge airport pick up service for invited speakers. n Contact Prof. Ming YangEmail: myang.heuMobile: List of Invited SpeakersSpeakerTitle/Affiliation1Hidekazu YOSHIKAWAProfessor Emeritus/Kyoto University, JapanPresident/Symbio Community Society, Japan Master Professor/Harbin Engineering U

5、niversity, China2Takeshi MATSUOKAProfessor/Utsunomiya University, JapanProfessor/Harbin Engineering University, China3Takashi NITTAAdviser/ The Japan Atomic Power Company4Jun SUGIMOTO Professor/Kyoto University, Japan5Poong Hyun SEONGProfessor/Korea Advanced Institute of Science and Technology, Kore

6、a6Morten LINDProfessor Emeritus/Technical University of Denmark, DenmarkProfessor/Harbin Engineering University, China7Terje JOHNSEN Department Head/OECD Halden Reactor Project, Norway8Ming YANGProfessor/Harbin Engineering University, Chinan AudiencesTotally ca. 30 audiences including senior master

7、course students, Ph.D students and young teachers at College of Nuclear Science and Technology (CNST), HEU, are expected to attend. n Workshop ScheduleDateTimePresentationsAugust 3008:45-09:00Opening Address by Prof. Puzhen GAO09:00-10:20Lecture 1: Perspective on Post-Fukushima Severe Accident Resea

8、rchSpeaker: Sugimoto JunChair: Professor Xinrong Cao10:20-10:50Group Picture /Coffee Break10:50-12:10Lecture 2: Lessons learned from the Fukushima Dai-ichi AccidentSpeaker: Takashi NittaChair: Professor Xinrong Cao12:10-14:00Lunch at HEU International Exchange Center14:00-15:20Lecture 3: Bayes Theor

9、em and its Application to Nuclear Power Plant safetySpeaker: Takeshi MatsuokaChair: Professor Poong Hyun Seong15:20-15:40Coffee Break15:40-17:00Lecture 4: Approaches at KAIST NICIE Lab to Quantifying Situation Awareness in Nuclear Power Plant MCRs.Speaker: Poong Hyun SeongChair: Professor Terje John

10、sen17:30-20:30Dinner at at HEU International Exchange CenterAugust 3109:00-10:20Lecture 5: Overview and Status of Functional ModelingSpeaker: Morten LindChair: Professor Ming Yang10:20-10:40Coffee Break10:40-12:00Lecture 6: A New Functional Modeling Framework of Risk Monitor SystemSpeaker: Hidekazu

11、YoshikawaChair: Professor Takeshi Matsuoka12:00-14:00Lunch at HEU International Exchange Center14:00-15:20Lecture 7: Reliability Analysis of Digital I&C Systems by a Functional Modeling ApproachSpeaker: Ming YangChair: Professor Morten Lind15:20-15:40Coffee Break15:40-17:00Lecture 8: Radiologica

12、l software tools supporting improved nuclear safetySpeaker: Terje JohnsenChair: Professor Yoshikawa Hidekazu17:30-20:30Dinner at Portman Western RestaurantSeptember 108:40-09:30Option1: Technical Tour at Automation College, HEUOption 2: HEU Exhibition Tour09:30-11:30 The 60th Anniversary Ceremony of

13、 HEU11:40-12:50Lunch at the Faculty Saloon, Qihang Center13:00-17:00International Forum for University Presidents on Information and Communication Technology Education (IFUP-ICT13)17:10-18:30Closing Ceremony and Banquet, Faculty Saloon19:00-21:00The 60th Anniversarys Evening Party, Qihang TheaterPro

14、gram Day-by-DayAugust 30, 201308:00- Assembling at the lobby of ZhengMing JinJiang Hotel (Invited speakers only)08:45-09:00Opening address09:00-10:20 Lecture 1 Chaired by Professor Xinrong CAOPerspective on Post-Fukushima Severe Accident ResearchJun SUGIMOTO, Ph.DProfessor, Kyoto University, Japansu

15、gimoto.jun.8ukyoto-u.ac.jpAfter the accident at Fukushima Daiichi Nuclear Power Station several investigation committees issued reports with lessons learned from the accident in Japan. Among those lessons, some recommendations have been made on severe accident research. Similar to the EURSAFE effort

16、s under EU Program, review of specific severe accident research items was started before Fukushima accident in working group of Atomic Energy Society of Japan (AESJ) in terms of significance of consequences, uncertainties of phenomena and maturity of assessment methodology. Re-investigation has been

17、 started after the Fukushima accident in this working group. Additional effects of Fukushima accident, such as core degradation behaviors, sea water injection, containment failure/leakage and re-criticality have been covered. The review results are categorized in nine major fields; core degradation

18、behavior, core melt coolability/retention in containment vessel, function of containment vessel, source term, hydrogen behavior, fuel-coolant interaction, molten core concrete interaction, recriticality and instrumentation in severe accident conditions. In January 2012, Research Expert Committee on

19、Evaluation of Severe Accident was established in AESJ in order to investigate severe accident related issues for future LWR development and to propose action plans for future severe accident research, in collaboration with this working group. Based on these activities and also authors personal view,

20、 the present paper describes the perspective of important severe accident research issues after Fukushima accident. Specifically those are investigation of damaged core and components, advanced severe accident analysis capabilities and associated experimental investigations, development of reliable

21、passive cooling system for core/containment, analysis of hydrogen behavior and investigation of hydrogen measures, enhancement of removal function of radioactive materials of containment venting, advanced instrumentation for the diagnosis of severe accident and assessment of advanced containment des

22、ign which excludes long-term evacuation in any severe accident situations. Lastly severe accident research conducted at Kyoto University is briefly introduced.Biographical Sketches -Doctor of Engineering, Professor of Department of Nuclear Engineering,Graduate School of Engineering, Kyoto University

23、, Japan(B. Physics, 1973, Ms. Eng. 1975, Dr. Eng. 1989, Kyoto University)He joined Japan Atomic Energy Agency in 1975. He was Head of Severe Accident Research Laboratory, Director of Vienna Office and Director of Nuclear Human Resource Development Center. He served as Vice Chairperson of OECD RASPLA

24、V Program Review Group (1996-1999), Member of IAEA Standing Advisory Group on Technical Assistance and Cooperation (2007, 2010, 2012-2013), Project Leader of Japan on Human Resources Development Project in Forum on Nuclear Cooperation in Asia (2007-2011) and Chairperson of Scientific Advisory Commit

25、tee of International Science and Technology Center (2008-2011).He is involved in the research fields of Nuclear Reactor Safety, especially Severe Accident Research for Advanced Nuclear Energy Systems.(Awards)-He received the Best Paper Award of Atomic Energy Society of Japan in1986.-He received Tech

26、nical Award of Atomic Energy Society of Japan in 1999.10:20-10:50: Group Picture /Coffee BreakMEMO10:50-12:10: Lecture 2 Chaired by Professor Xinrong CAOLessons learned from the Fukushima Dai-ichi Accident(based on the Report by Nuclear Safety Division of Atomic Energy Society of Japan) Mr. Takashi

27、NITTAAdviser, The Japan Atomic Power CompanyTwo years and five months have passed since the Fukushima Dai-ichi accident caused by extraordinary tsunami due to the Great East Japan Earthquake occurred on March 11, 2011.The Nuclear Safety Division of the Atomic Energy Society of Japan (AESJ/NSD) organ

28、ized a series of Seminars in 2012 to investigate the accident and published the final report at the end of March,2013. The issues identified during the seminar were defense-in-depth, safety design and severe accident management, nuclear safety regulation, emergency preparedness and response, probabi

29、listic risk assessment, operating experience feedback and safety research and so on.This presentation is to introduce the main conclusions of the report. Biographical Sketches -Education Kyoto University, Master Degree, Electrical Engineering CourseWork Experience -1972 2004: The Kansai Electric Pow

30、er Company -Nuclear safety analysis -Nuclear safety design -Electrical maintenance - 2004Present: The Japan Atomic Power Company - The TURUGA Units 3&4 (the first Advanced PWR s) Construction Project - Research and developmentMEMO12:10-14:00Lunch at HEU International Exchange Center14:00-15:20 L

31、ecture 3 chaired by Professor Poong Hyun SEONGBayes Theorem and its Application to Nuclear Power Plant safetyTakeshi MATSUOKA, Ph.DVisiting Professor, Harbin Engineering UniversityLecturer, Center for Fundamental Education, Utsunomiya UniversityVice chairman, Consumer Safety Investigation Commission

32、, Consumer Affairs Agencymatscc.utsunomiya-u.ac.jpProbabilistic safety assessment methods are widely used for the evaluation of nuclear power plant safety. It has been realized, however, the method has to deal with the rarity of events, that is, lack of meaningful statistical data. So, traditional s

33、tatistical method is not well applicable to PSA. Bayes theorem has been made much attention for its application to PSA. Analyst knowledge is changed when new evidence becomes available. Bayes theorem provides us the method to update data with a new evidence, coherently.In this paper, first discuss t

34、he types of probability, subjectivistic and frequentistic probabilities. Then Bayes theorem is explained in detail. How to interpret the Bayes equation. Explanation is also given for the concept of the pair of conjugate distributions between prior distribution and likelihood. It is also shown that s

35、equential evaluation, two or three steps evaluation, by Bayes theorem gives the same result with the summarized evaluation.Component failure data are evaluated by the Bayes theorem. Examples are demand probability of the start of diesel generator and failure of pressure sensor. Also the frequency of

36、 nuclear power plant accidents are evaluated. These are frequency of fires in reactor compartment and core meltdown frequency with the experience of Fukushima dai-ichi accidents.Bayes theorem is well incorporated into system reliability analysis with the use of Bayesian network. As an example of Bay

37、esian network, Hugin-light is taken up and some model analysis is shown. Still, there are many discussions between favorable and critical peoples to the Bayes methods. Their opinions are briefly introduced. Bayesian methods provide a logical framework for safety analysis of nuclear power plants. The

38、 frequentist methods are seems to be objective, but they limit the available evidence to the only statistical values. In actual situation, however, we have to make judgment to decide what the evidence is. Furthermore, our knowledge about nuclear power plant is formed not only by statistical data but

39、 also from design considerations, operating environment and so on. Bayesian methods can translate these beliefs into numbers, and assessors become coherent. Then the group of assessors has high chances to reach a common decision.Biographical Sketches -In 1973, he graduated the University of Tokyo, g

40、raduate school. After joining the Ship Research Institute, Ministry of Transport, he engaged in a research for the safety of nuclear propulsion ship. From 1979 to 1980, he studied at the Massachusetts Institute of Technology, Nuclear Engineering department.After that, he has been engaging in the Pro

41、babilistic Safety Assessment (PSA), system reliability analysis. Then, he developed a new system reliability analysis methodology GO-FLOW, which can easily analyze large, complex systems, such as a nuclear plant, a chemical plant, a network system. He also performed the application research of GO-FL

42、OW methodology. Now this GO-FLOW program package is widely supplied to a public with reasonable price. In 1993, he was awarded the prize of the Minister of Science and Technology Agency for the development of the GO-FLOW. He moves from the national Maritime Research Institute to the Utsunomiya Unive

43、rsity, Professor of the Faculty of Engineering, in 2006.In 2009, he has presented the method to solve the reliability of loop structured system, and he was awarded Takagi prize of the Reliability Engineering Association of Japan, in 2013.He was a technical committee member of Nuclear Safety Commissi

44、on, for long time. From 2011, he is a member of the Science Council of Japan. From 2012, he is a Vice chairman, Consumer Safety Investigation Commission, Consumer Affairs Agency. 15:20-15:40Coffee BreakMEMO15:40-17:00Lecture 4 chaired by Mr. Terje JOHNSENApproaches at KAIST NICIE Lab to Quantifying

45、Situation Awareness in Nuclear Power Plant MCRs.Poong Hyun SEONG, Ph.DProfessor, Department of Nuclear and Quantum Engineering, KAISTIn this presentation, some empirical efforts which are made at the KAIST NICIE (Nuclear I&C and Information Engineering) Lab to quantify Situation Awareness (SA) i

46、n NPP Control Rooms will be introduced. The presentation will be in two parts. First part will be on quantifying individual situation awareness by using eye tracking system. Second part will be on quantifying team situation awareness analyzing the team members conversation. Besides these, some attem

47、pts to quantify SA in analytical ways will also be presented. For the first analytical approach, Bayesian inference method is used with the assumption of ideal operator and for the second analytical approach, real operators characteristics such as working memory decay, imperfect mental models were a

48、lso included. An effort to develop a tool will be also presented. Biographical Sketches -Dr. Poong Hyun SEONG is currently a Professor in Nuclear Engineering at KAIST, Korea. Prof. Poong Hyun SEONG had his BS degree from Seoul National University in 1977, and MS and Ph D degrees in nuclear engineeri

49、ng from Massachusetts Institute of Technology (MIT) in 1984 and 1987, respectively. He worked as the chief editor of “Nuclear Engineering and Technology” from 2003 to 2008. He was a commissioner of the Korea Nuclear Safety Commission from 2006 to 2009. He was the chair of the HFICD (Human Factors an

50、d Instrumentation and Control Division) of the ANS (American Nuclear Society) from 2006 to 2007. He is now an editorial board member of “Reliability Engineering and System Safety”. His research interest includes Digital Instrumentation and Control systems developments for Nuclear Power Plants, Softw

51、are V/V, Human Reliability Analysis, and Cognitive Systems Engineering. He published numerous technical papers (http:/niclab.kaist.ac.kr) and he published a book “Reliability and Risk Issues in Large Scale Safety-critical Digital Control Systems”, Springer in 2009.17:30-20:30Dinner at at HEU Interna

52、tional Exchange CenterMEMOAugust 31, 201308:30- Assembling at the lobby of ZhengMing JinJiang Hotel (Invited speakers only)09:00-10:20Lecture 5 Chaired by Prof. Ming YANGOverview and Status of Functional ModelingMorten Lind, Ph.DProfessor Emeritus , Technical University of DenmarkVisiting Professor,

53、 Harbin Engineering University Functional modeling is an exciting research field which is highly relevant for the engineering disciplines. It addresses basic questions about the relations between means and ends or purposes and our understanding of complex physical artifacts like industrial systems a

54、nd infrastructures. Functional modeling is currently applied to Nuclear Power Plants in projects in Europe and Asia.Functional modeling has its roots in AI research and is reaching a promising level of maturity. Modeling tools are becoming available (such as Multilevel Flow Modeling).Functional mode

55、ling has therefore the potential to play a central role in future advancements of systems engineering.The presentation will give an overview of the current status and challenges of functional modeling and present a summary of the international workshop on functional modeling IWFM hosted by DTU in 20

56、12. Biographical Sketches -Personal information and professional career:Prof. Lind was born in Copenhagen, Denmark 28 May, 1944 and received his MScE in electrical engineering 1969 and his PhD (Selforganizing Control Systems) in 1977 from Technical University of Denmark. He was employed as a research scientist at Risø National Laboratory (now DTU-Risø) from 1969-1984 where he worked at department of electronics (1969-1973, 1977-1984) and reactor technology (1973-77). In 1984 he was appointed Full Professor of Digital Systems at University of Aalborg, De