DOCSLIB.ORG

PSAM10-Program-LR.Pdf

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
PSAM10-Program-LR.Pdf PSAM 10 - 10th International Probabilistic Safety Assessment & Management Conference June 7-11, 2010 Foreword Dear Colleagues, It’s our pleasure to welcome you to PSAM10. We hope the conference provides you with ample opportunities for learning and technical discourse. Your attendance directly supports achieving the mission of IAPSAM to provide educational op- portunities, and support the development and advancement of risk assessment methods helping to make the world a safer and more productive place to live. Your contributions are appreciated and valued. This year our program includes 400 papers in 18 technical tracks covering all of the major areas of risk assessment includ- ing methods, uncertainty, space and aviation, nuclear power, human reliability and risk management just to name a few. The diversity of organizations participating in this meeting and topics that will be discussed underscore the interest and importance in the technical issues that shape our activities. We encourage you to take some time and attend a session or two outside of your area of specialty and learn about the diversity of applications of Probabilistic Safety Assessment and risk management. Build new bridges; help to broaden our fields thinking while making some new colleagues. Challenge one another, and enter into substantive dialogue! As is our custom with this meeting, you will have a number of opportunities to renew old acquaintances and to develop new ones. We also encourage you to visit the dedicated sponsor area at the meeting to learn about new commercial products and services. Beyond the borders of the meetings lies one of the most vibrant and unique American cities. Our local hosts and we en- courage you to enjoy the Seattle area including its many restaurants and nightspots. You’re never far from a bookstore or a coffee shop in this city that is known for its relaxed and eclectic atmosphere. Experience Seattle and enjoy what this fine city has to offer. Thank you for your attendance and participation in this meeting and welcome to Seattle! Bruce and Harold and 1 PSAM 10 - 10th International Probabilistic Safety Assessment & Management Conference June 7-11, 2010 Acknowledgement The PSAM 10 Conference Organizing Committee wish to express our gratitude to the many people and organizations that have contributed to ensuring the success of this conference. It is the conference participants that provide the true value and generate the most significant and lasting effects of the interactive exchanges that occur during the week of meetings. Thank you for your interest, technical contributions, and willingness to actively participate. There were numerous organiza- tions and individuals that helped to disseminate notice of this meeting and encourage submission of technical papers. This form of support facilitated a very strong performance by the Technical Program Committee with nearly 360 papers from 32 countries in over 100 sessions will be presented and are included in the Conference Proceedings. In addition, the conference experience has been enhanced through the financial and logistical support provided by the sev- eral contributing sponsors. The PSAM 10 Conference organizers would like to thank our sponsors, IAPSAM, Idaho National Laboratory, The Center for Advanced Energy Studies, Scandpower, and Scientech for their support. Mrs. Hanna Shapira of Techno-Info Comprehensive Solutions (TICSs) provided the conference Web Site design and Online Software and we would also like to express our appreciation for the professionalism, technical skill and patience she has provided. We would like to acknowledge the many efforts on behalf of IAPSAM by the Technical Program Committee for PSAM 10. In particular the conference organizers wish to acknowledge the following for their assistance, dedication and technical expertise in helping to bring about the technical program and this conference. Tunc Aldemir Bruce Hallbert Sitakanta Mohanty Ben Ale Joan Harvey Bill Nelson George Apostolakis Philippe Hessel Luiz Oliveira Piero Baraldi Stefan Hirschberg Todd Paulos James Battles Vincent Ho Osvaldo Pensado Harold Blackman Elod Hollo Helene Pesme Emanuele Bogonovo Feng Hsu Kurt Petersen Nattasha Freeman Moosung Jae Jerry Phillips Sandro Bologna David Johnson Luca Podofillini Ron Boring Peter Kafka Pekka Pyy Roger Boyer Tsu-Mu Kao Alan Roe Radim Bris Dana Kelly Budhi Sagar Mario Brito Soli Khericha Oliver Salvi Andreas Bye Inn Seock Kim Yoshinobu Sato James Chang James Lambert Martin Sattison Simone Colombo Jeanne-Marie Lanore Zdenko Simic Wan Ki Chow Tim Leahy Nathan Siu Valerio Cozzani James C. Lin Cornelia Spitzer Vinh Dang Antoly Lisniasky Andreas Strohm Homayoon Dezfuli Erasmia Lois Peter Swift Enrique Lopez-Droguett Gaspare Maggio Magdy (Samy) Tawfik Andrew Dykes Davide Manca Paolo Trucco Chester Everline Sebastian Martorell Jan Erik Vinnem Terri Flores Giuseppe Mashchio Reino Virolainen Adrian Gheorghe Xie Min Joon-Eon Yang Ching Guey Krishna Misra Jonathan Young Andrew Hale Zahra Mohaghegh Bob Youngblood 2 PSAM 10 - 10th International Probabilistic Safety Assessment & Management Conference June 7-11, 2010 Previous PSAM Conferences PSAM 1 Beverly Hills, CA, USA, February 1991 General and Technical Program Chair: G. E. Apostolakis PSAM 2 San Diego, CA, USA, March 1994 General Chair: M. G. Stamatelatos Technical Program Chair: G. E. Apostolakis PSAM 3 (Held in conjunction with ESREL’96) Crete, Greece, June 1996 General Chair: I. A. Papazoglou Technical Chair: P. C. Cacciabue PSAM 4 New York, New York, USA, September 1998 General Chair: R. A. Bari Technical Program Chair: A. Mosleh PSAM 5 Osaka, Japan, November 2000 Honorary Chair: H. Uchida General Chair: S. Kondo Technical Program Chairs: S. Kondo and K. Furuta PSAM 6 San Juan, Puerto Rico, USA, June 2002 General Chair: E. J. Bonano Technical Program Chair: A. L. Camp Technical Program C-Chair: A. Ghassemi PSAM 7 (held in conjunction with ESREL’04) Berlin, Germany, June 2004 General Chair: C. Spitzer Technical Program Chair: U. Schmocker Associate General Chair: E. Zio Technical Program C-Chairs: S. Chakraborty, M. Faber, and S. Hirschberg PSAM 8 New Orleans, USA, May 2006 General Co-Chairs: D. Johnson and L. J. Steinberg Technical Program Co-Chairs: H. Blackman and M. Stamatelatos PSAM 9 Hong Kong, China, May 2008 General Chair: V. Ho Technical Program Chair: Tsu-Mu Kao Associate Technical Program Chair: E. Zio 3 PSAM 10 - 10th International Probabilistic Safety Assessment & Management Conference June 7-11, 2010 Welcome 4 PSAM 10 - 10th International Probabilistic Safety Assessment & Management Conference June 7-11, 2010 Welcome 5 PSAM 10 - 10th International Probabilistic Safety Assessment & Management Conference June 7-11, 2010 Committees Technical Program Committee Piero Baraldi Anatoly Lisniansky James Battles Erasmia Lois Sandro Bologna Gaspare Maggio Ron Boring Xie Min Roger Boyer Zahra Mohaghegh Mario P. Brito Sitakanta Mohanty Wan Ki Chow Bill Nelson Valerio Cozzani Todd Paulos Vinh Dang Helene Pesme Adrian Gheorghe Alan Roe Ching Guey Budhi Sagar Feng Hsu Marty Sattison Moosung Jae Zdenko Simic David Johnson Joon-Eon Yang Tsu-Mu Kao Jonathan Young Soli Khericha Bob Youngblood Tim Leahy Technical Program Committee Members At Large Tunc Aldemir Jeanne-Marie Lanore Ben Ale James C. Lin George Apostolakis Davide Manca Harold Blackman Sebastian Martorell Emanuele Bogonovo Giuseppe Mashchio Radim Bris Krishna Misra Andreas Bye Luiz Oliveira James Chang Todd Paulos Simone Colombo Osvaldo Pensado Homayoon Dezfuli Kurt Petersen Enrique Lopez Droguett Jerry Phillips Andrew Dykes Luca Podofillini Chester Everline Pekka Pyy Nattasha Freeman Oliver Salvi Andrew Hale Yoshinobu Sato Bruce Hallbert Nathan Siu Joan Harvey Cornelia Spitzer Philippe Hessel Andreas Strohm Stefan Hirschberg Peter Swift Vincent Ho Magdy (Samy) Tawfik Elod Hollo Paolo Trucco David Johnson Jan Erik Vinnem Peter Kafka Reino Virolainen Dana Kelly Inn Seock Kim James Lambert 6 PSAM 10 - 10th International Probabilistic Safety Assessment & Management Conference June 7-11, 2010 General Information Registration Registration is required for all attendees and presenters. The meeting registration desk is at Courtyard Foyer Badges are required for admission to all events. Sunday 8:00 AM – 3:00 PM Monday 7:30 AM – 4:00 PM The Full Conference Registration Fee includes: Welcome Tuesday 7:30 AM – 4:00 PM Reception, Tillicum Village Dinner Excursion, Conference Wednesday 7:30 AM – 4:00 PM Luncheon, proceedings, and admittance to technical ses- Thursday 7:30 AM – 4:00 PM sions. Conference Proceedings The Student Registration Fee includes: Welcome Reception, Conference Proceedings, in CD-ROM format, are included Tillicum Village Dinner Excursion, Conference Luncheon, with the program book. Please check the vinyl pocket inside proceedings, and admittance to technical sessions. the back cover of the program book. Spouse/Guest: Registrants can purchase extra tickets for guests to Welcome Reception ($-50.00/ ticket) on June 7, 2010 or to the Tillicum Village Dinner Excursion ($-50.00/ ticket) on June 9, 2010 Speaker Information Session Chair Information Please sign the “Speaker Sign-in Form” at the registration Please complete and return a “Session Chair Sign-in Form” desk. Please be sure to bring your presentation in MicroSoft to the Registration Desk the morning you are scheduled PowerPoint format. Note that the total time available for to Chair a Session(s). Please be present at your session presentations (other than the plenary) varies from 18 to
Load more

Recommended publications
  • Analysis on the Thermal Striping and Thermal Shock of the Lower Head of Central Measuring Shroud in a Fast Reactor
    Transactions, SMiRT-25 Charlotte, NC, USA, August 4-9, 2019 Division III Analysis on the Thermal Striping and Thermal Shock of the Lower Head of Central Measuring Shroud in a Fast Reactor Zheng Shu 1, Lu Daogang 1, Cao Qiong 1 1School of Nuclear Science and Engineering, Beijing Key Laboratory of Passive Nuclear Safety Technology for Nuclear Energy, North China Electric Power University, Beijing 102206, China ([email protected]) ABSTRACT The central measuring shroud, as an important in-vessel component, contains the conduits of control rod and a variety of measuring equipment. The distance between the core outlet and the lower head of central measuring shroud (LHCMS), which is located above the core outlet, is only 500mm. Therefore, the LHCMS is affected by the core coolant for a long period, especially the temperature effects of the following two types. Firstly, under the operating condition of the sodium-cooled fast reactor, the uneven distribution of the core power causes the phenomenon of thermal striping, which may cause large stress. In addition, under the scram condition, the coolant temperature at the core outlet is sharply reduced due to the decrease of the core power, inducing the phenomenon of thermal shock that may induce large stress. Therefore, stress analysis of the LHCMS under the operating condition and scram condition is very necessary. In the paper, the simulation first established the finite element model of the LHCMS, and then calculated the thermal stress of the LHCMS according to the temperature fluctuation curve and the scram temperature curve. The results show that the temperature field under thermal shock changes dramatically with time, while the temperature field under thermal striping changes relatively slowly with time.
    [Show full text]
  • Security Operational Skills 2 (Tracing).P65
    Unit - 4 K Operating Skill for handling Natural Disasters Structure 4.1 Objectives 4.2 Introduction 4.3 Operating Skill for natural and nuclear disasters 4.4 Accident Categories 4.5 Nuclear and radiation accidents and incidents 4.6 Geological disasters 4.7 Operating Skills for handling Mines and other Explosive Devices 4.8 Operating Skills for handing hijacking situation (other than an airline hijacking 4.9 Operating skills for antivehicle theft operations 4.10 Operating skills for facing a kidnapping or hostage situation 4.11 Operating Skill for handling coal mines and other explosive devices 4.12 Hostage Rights : Law and Practice in Throes of Evolution 4.12.1 Terminology 4.13 Relative Value of Rights 4.14 Conflict of Rights and Obligations 4.15 Hong Kong mourns victims of bus hijacking in the Philoppines 4.16 Rules for Successful Threat Intelligence Teams 4.16.1 Tailor Your Talent 4.16.2 Architect Your Infrastructure 4.16.3 Enable Business Profitability 4.16.4 Communicate Continuously 4.17 Construction Safety Practices 4.17.1 Excavation 4.17.2 Drilling and Blasting 4.17.3 Piling and deep foundations 234 4.18 Planning 4.18.1 Steps in Planning Function 4.18.2 Characteristics of planning 4.18.3 Advantages of planning 4.18.4 Disadvantages of planning 4.1 Objectives The following is a list of general objectives departments should consider when creating an Information Disaster Prevention and Recovery Plan: O Ensure the safety of all employees and visitors at the site/facility O Protect vital information and records O Secure business sites
    [Show full text]
  • Licensing Small Modular Reactors an Overview of Regulatory and Policy Issues
    Reinventing Nuclear Power Licensing Small Modular Reactors An Overview of Regulatory and Policy Issues William C. Ostendorff Amy E. Cubbage Hoover Institution Press Stanford University Stanford, California 2015 Ostendorff_LicensingSMRs_2Rs.indd i 6/10/15 11:15 AM The Hoover Institution on War, Revolution and Peace, founded at Stanford University in 1919 by Herbert Hoover, who went on to become the thirty-first president of the United States, is an interdisciplinary research center for advanced study on domestic and international affairs. The views expressed in its publications are entirely those of the authors and do not necessarily reflect the views of the staff, officers, or Board of Overseers of the Hoover Institution. www.hoover.org Hoover Institution Press Publication Hoover Institution at Leland Stanford Junior University, Stanford, California 94305-6003. Copyright © 2015 by the Board of Trustees of the Leland Stanford Junior University The publisher has made this work available under a Creative Commons Attribution-NoDerivs license 3.0. To view a copy of this license, visit http://creativecommons.org/licenses/by-nd/3.0. Efforts have been made to locate the original sources, determine the current rights holders, and, if needed, obtain reproduction permissions. On verification of any such claims to rights in illustrations or other elements reproduced in this essay, any required corrections or clarifications will be made in subsequent printings/editions. Hoover Institution Press assumes no responsibility for the persistence or accuracy of URLs for external or third-party Internet websites referred to in this publication, and does not guarantee that any content on such websites is, or will remain, accurate or appropriate.
    [Show full text]
  • Uncertainty and Sensitivity Analysis for Long-Running Computer Codes: a Critical Review
    UNCERTAINTY AND SENSITIVITY ANALYSIS FOR LONG-RUNNING COMPUTER CODES: A CRITICAL REVIEW By MASSACHUSE~s INSTrTUTE' Dustin R. Langewisch OF TECHNOLOGY B.S. Mechanical Engineering and B.S. Mathematics MAR 122010 University of Missouri-Columbia, 2007 L A [ LIBRARIES SUBMITTED TO THE DEPARTMENT OF NUCLEAR SCIENCE AND ENGINEERING IN PARTIAL FULFILLMENT OF THE REQUIREMENTS FOR THE DEGREE OF ARCHIVES MASTER OF SCIENCE IN NUCLEAR SCIENCE AND ENGINEERING AT THE MASSACHUSETTS INSTITUTE OF TECHNOLOGY FEBRUARY 2010 The author hereby grants MIT permission to reproduce and distribute publicly paper and electronic copies of this thesis document in whole or in part in any medium now known or hereafter created. Copyright 0 Massachusetts Institute of Technology All rights reserved. Signature of Author: "-1epartment of Nuclear Science and Engineering January 28, 2010 Certified by: Dr. Gofge E p-p'stolakis, Thesis Supervisor KEPCO Professor of Nuclear Science and Engineering Professor of Engineering Systems Certified by: Don d Helton, Thesis Reader of ear Regulatory Research a. Regulatory Commission Accepted by: Dr. Jacquelyn C. Yanch Chair, Department Committee on Graduate Students UNCERTAINTY AND SENSITIVITY ANALYSIS FOR LONG-RUNNING COMPUTER CODES: A CRITICAL REVIEW Dustin R. Langewisch SUBMITTED TO THE DEPARTMENT OF NUCLEAR SCIENCE AND ENGINEERING IN PARTIAL FULFILLMENT OF THE REQUIREMENTS FOR THE DEGREE OF MASTER OF SCIENCE IN NUCLEAR SCIENCE AND ENGINEERING AT THE MASSACHUSETTS INSTITUTE OF TECHNOLOGY FEBRUARY 2010 Abstract This thesis presents a critical review of existing methods for performing probabilistic uncertainty and sensitivity analysis for complex, computationally expensive simulation models. Uncertainty analysis (UA) methods reviewed include standard Monte Carlo simulation, Latin Hypercube sampling, importance sampling, line sampling, and subset simulation.
    [Show full text]
  • The Nuclear Illustrative Programme of the Commission (PINC), and Is a Collection of Factual Data Gathered from Several Sources
    EUROPEAN COMMISSION Brussels, 4.4.2016 SWD(2016) 102 final COMMISSION STAFF WORKING DOCUMENT Accompanying the document Communication from the Commission Nuclear Illustrative Programme presented under Article 40 of the Euratom Treaty for the opinion of the European Economic and Social Committee {COM(2016) 177 final} EN EN Table of figures ...................................................................................................................................... 3 1 Introduction ................................................................................................................................... 4 1.1 Overview of the European nuclear industry ............................................................................ 4 2 The front-end of the nuclear fuel cycle ........................................................................................ 6 2.1 Demand for natural uranium .................................................................................................... 6 2.2 Conversion ............................................................................................................................... 7 2.3 Enrichment .............................................................................................................................. 7 2.4 Fuel fabrication ........................................................................................................................ 8 3 Nuclear new build .......................................................................................................................
    [Show full text]
  • Tổng Luận: Năng Lượng Hạt Nhân
    TỔNG LUẬN THÁNG 04/2011 LỘ TRÌNH PHÁT TRIỂN CÔNG NGHỆ NĂNG LƢỢNG HẠT NHÂN VÀ DỰ BÁO TRIỂN VỌNG TRONG TƢƠNG LAI 1 CỤC THÔNG TIN KHOA HỌC VÀ CÔNG NGHỆ QUỐC GIA Địa chỉ: 24, Lý Thƣờng Kiệt. Tel: 8262718, Fax: 9349127 Ban Biên tập: TS. Tạ Bá Hưng (Trƣởng ban), ThS. Cao Minh Kiểm (Phó trƣởng ban), ThS. Đặng Bảo Hà, Nguyễn Mạnh Quân, ThS. Nguyễn Phương Anh, Phùng Anh Tiến. MỤC LỤC Trang LỜI GIỚI THIỆU 1 I. I. NĂNG LƢỢNG HẠT NHÂN: MỘT SỐ KHÁI NIỆM CƠ BẢN 3 1. Năng lượng hạt nhân: tổng hợp, phân hạch hạt nhân 3 2. Công nghệ lò phản ứng hạt nhân, chu trình 6 3. Chất thải 8 4. An toàn hạt nhân, sự cố hạt nhân và phóng xạ 10 5. Điều phối quốc tế về năng lượng hạt nhân 18 II. SỰ PHÁT TRIỂN CÔNG NGHỆ NĂNG LƢỢNG HẠT NHÂN 22 1. Công nghệ lò phản ứng hạt nhân thế hệ I, II và III 22 21 2. Công nghệ năng lượng hạt nhân thế hệ IV và lộ trình phát triển 33 30 3. Công nghệ chu trình nhiên liệu hạt nhân 48 III. HIỆN TRẠNG VÀ DỰ BÁO TRIỂN VỌNG NĂNG LƢỢNG HẠT 51 NHÂN THẾ GIỚI 1. Hiện trạng năng lượng hạt nhân thế giới 51 2. Dự báo về triển vọng năng lượng hạt nhân toàn cầu 56 KẾT LUẬN 61 TÀI LIỆU THAM KHẢO 64 2 LỜI GIỚI THIỆU Dân số thế giới được cho là sẽ tăng từ 6 tỷ người hiện nay lên mức 9 tỷ vào năm 2050, và mọi người đều ra sức nỗ lực để có được chất lượng cuộc sống tốt hơn.
    [Show full text]
  • Strategic Environmental Assessment Report for the Polish Nuclear Programme
    1 NON-TECHNICAL SUMMARY AUTHORS: Łukasz Szkudlarek, Dominika Lewicka-Szczebak, Marek Kasprzak TABLE OF CONTENTS: 1 NON-TECHNICAL SUMMARY ........................................................................................................ 1-1 1.1 Introduction .......................................................................................................................... 1-2 1.2 About the Report .................................................................................................................. 1-3 1.3 References to other strategic documents .............................................................................. 1-6 1.4 Current state of the natural environment in Poland .............................................................. 1-6 1.5 No-action alternative – impact on the natural environment in Poland ............................... 1-14 1.6 Nuclear energy – background information ......................................................................... 1-15 1.7 Analysis and evaluation of the impact of radioactive emissions from nuclear power plants .................................................................................................................................. 1-23 1.8 Analysis and evaluation of other expected significant impacts related to the operation of nuclear power plants ...................................................................................... 1-31 1.9 Identification and description of the expected environmental impacts of the Programme ........................................................................................................................
    [Show full text]
  • Egypt Research and Nuclear Power Reactors Design Safety Approach
    Nuclear and Radiological Regulatory Authority Egypt - ENRRA Egypt Research and Nuclear Power Reactors Design Safety Approach Technical Meeting on the Evaluation of Nuclear Power plant Design Safety In the Aftermath of the Fukushima Daiichi Accident 26-29 August 2013 Vienna, Austria EL-MESSIRY Ahmed Egypt Nuclear and Radiological Regulatory Authority ENRRA [email protected] 29 August 2013 1 Nuclear and Radiological Regulatory Authority Egypt - ENRRA AUTHER RESUME B.Sc., M.SC., Ph. D. in Nuclear Engineering, Prof. of nuclear installation safety, Board Member of Egypt Nuclear and Radiological Regulatory Authority ,(2012- now), Sharing in editing Egypt nuclear law and its executive regulation, Member of Review & Assessment of nuclear installations committee, and Nuclear installation Operators licensing committees, Reactor operator of Egypt Test and Research Reactor # 1, (1969-1982). 29 August 2013 2 Nuclear and Radiological PAPER OUTLINE: Regulatory Authority Egypt - ENRRA 1- INTRODUCTION 2- EGYPT NUCLEAR SAFETY APPROACH OF NUCLEAR REACTORS 3- GENERAL DESIGN SAFETY ASPECTS OF NUCLEAR REACTORS 4-FUKUSHIMA ACCIDENT ANALYSES 5- DIFFERENT IMPOVMENTS IN PLANT SYSTEM AS A RESULT OF FUKUSHIMA ACCIDENT 6- FEEDBACK OF FUKUSHIMA ACCIDENT ON SAFETY OF NUCLEAR REACTORS IN EGYPT 29 August 2013 3 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA The main articles relating to the nuclear platform (infrastructures) of Egypt are: 1.1 Nuclear Organizations, 1.2 Regulatory Body, 1.3 Nuclear power program, 1.4 Nuclear reactors, 1.5 Regulation used in licensing nuclear reactors. 29 August 2013 4 Nuclear and Radiological 1. INTRODUCTION Regulatory Authority Egypt - ENRRA 1.1. Nuclear Organizations in Egypt i. Atomic Energy Authority AEA (Operates two research reactors), ii.
    [Show full text]
  • Small Reactors with Simplified Design
    XA9745920 IAEA-TECDOC-962 Small reactors with simplified design Proceedings Technicala of Committee meeting held in Mississauga, Ontario, Canada, 15-19 May 1995 INTERNATIONAL ATOMIC ENERGY AGENCY November 1997 t 29 The IAEA doe t normallsno y maintain stock f reportso thin si s series. However, microfiche copie f thesso e reportobtainee b n sca d from ClearinghousS I N I e International Atomic Energy Agency Wagramerstrasse5 0 10 x P.OBo . A-1400 Vienna, Austria Orders should be accompanied by prepayment of Austrian Schillings 100,- fore for e chequa th mf th IAEmf o n o i n i r Aeo microfiche service coupons orderee whicb y dhma separatel ClearinghouseS I y N froI e mth . IAEA-TECDOC-962 Small reactors with simplified design Proceedings Technicala of Committee meeting held in Mississauga, Ontario, Canada, 15-19 May 1995 W INTERNATIONAL ATOMIC ENERGY AGENCY originatine Th g Sectio thif no s publicatio IAEe th Ann i was: Nuclear Power Technology Development Section International Atomic Energy Agency Wagramerstrasse5 P.O. Box 100 A-1400 Vienna, Austria SMALL REACTORS WITH SIMPLIFIED DESIGN IAEA, VIENNA, 1997 IAEA-TECDOC-962 ISSN 1011-4289 ©IAEA, 1997 Printe IAEe th AustriAn y i d b a November 1997 FOREWORD There is a potential future need for small reactors for applications such as district heating, electricity productio t remotna e location desalinationd an s . Nuclear energn ca y provide an environmentally benign alternative to meet these needs. For successful deployment, small reactors must satisf e requirementth y f userso s , regulatore th d an s general public.
    [Show full text]
  • ICARO Final Report on the Round Tables
    CHERNE Cooperation for Higher Education on Radiological and Nuclear Engineering Erasmus Intensive Programme Project (IP) ICARO Intensive Course on Accelerator and Reactor Operation 01/03/09 – 14/03/09 – Lisboa, Portugal – Alma Mater Studiorum Universita’ di Bologna, Italy Czech Technical University, Prague, Czech Republic Fachhochschule Aachen, Jülich, Germany Haute Ecole Paul Henri Spaak ISIB, Brussels, Belgium Instituto Tecnológico e Nuclear ITN, Lisboa, Portugal Politecnico di Milano, Milano, Italy Universidade de Coimbra, Coimbra, Portugal Universita’ degli Studi di Catania, Italy Universitad Politecnica de Valencia, Valencia, Spain XIOS Hogeschool Limburg, Diepenbeek, Belgium Final report on the Round tables: 1. Nuclear and Sustainable Development 2. Ethics and the Principle of Justification – the case of Nuclear Technology Assessment – Herwig Janssens - editor XIOS Hogeschool Limburg, dptm. Nuclear Technology, Diepenbeek, Belgium – 2009 – Icaro 2009: Round tables Contents 1. Nuclear and Sustainable Development: an Introduction Herwig Janssens XIOS Hogeschool Limburg, Diepenbeek, Belgium 2. Ethics and the Principle of Justification - the case of Nuclear Technology Assessment Gaston Meskens SCK•CEN, Mol, Belgium 3. The concept of sustainable development in general and the implication for the energy sector in particular Lara Marwaha, Francois Tondeur Haute Ecole Paul Henri Spaak ISIB, Brussels, Belgium 4. Comparison of nuclear energy and alternatives in view of sustainable development (excluding competitiveness) Griet D’hollander,
    [Show full text]
  • Download Article (PDF)
    Advances in Computer Science Research (ACSR), volume 76 7th International Conference on Education, Management, Information and Mechanical Engineering (EMIM 2017) New Nuclear Power Technology Research Progress in China and Abroad Mingqi Wu North China Electric Power University, Baoding, 071003, China [email protected] Keywords: Application of nuclear energy; Nuclear energy research Abstract. Nuclear power is a clean, safe and mature technology, strong supply capacity, to large-scale application way of generating international technology development leveled off in 2015, the Chinese reactors construction accounted for 40% of the world. International nuclear energy application of the third generation of nuclear power units continue to improve, at present, in all kinds of fourth-generation nuclear power systems research, China's fourth generation nuclear power in air cooled fast reactor (GFR) and lead cooled fast reactor (LFR) into the reactor construction stage, China's nuclear power development in the spring. The Preface-world Nuclear Power Development Characteristics According to the independent energy and environmental policy experts Mycle Schneider and other cooperation wrote "the world nuclear industry status report 2015", by the mid - 2015, 30 countries operating nuclear power plants, there is only one than in previous years (Japan).[1] Nuclear power plant to produce 2.41 trillion KWH of surfing the Internet, compared with 2013 growth of 2.2%, but still 9.4% lower than the peak in 2006. A total of 31 countries around the world are running nuclear reactors, nuclear reactor with a total of 391 seats, launched in 2014, compared to the same five reactors, closed 2 reactors, with a total installed capacity of 337 gigawatts (GW), political influence by fukushima, Japan has not been running nuclear power unit.
    [Show full text]
  • Comparative Assessment of Small Modular Reactor Passive Safety System Design Via Integration of Dynamic Methods of Analyses
    Comparative Assessment of Small Modular Reactor Passive Safety System Design via Integration of Dynamic Methods of Analyses by Yi Mi A thesis submitted to the School of Graduate and Postdoctoral Studies in partial fulfillment of the requirements for the degree of Master of Applied Science in Nuclear Engineering Faculty of Energy Systems and Nuclear Science Ontario Tech University Oshawa, Ontario, Canada December 2019 © Yi Mi, 2019 THESIS EXAMINATION INFORMATION Submitted by: Yi Mi Master of Applied Science in The Faculty of Energy Systems and Nuclear Science Thesis title: Comparative Assessment of Small Modular Reactor Passive Safety System Design via Integration of Dynamic Methods of Analyses An oral defense of this thesis took place on 28 November, 2019 in front of the following examining committee: Examining Committee: Chair of Examining Committee Hossam Gaber Research Supervisor Akira Tokuhiro Research Co-supervisor Lixuan Lu Examining Committee Member Glenn Harvel Thesis Examiner Muhammad Aamir, Manager, SMR Engineering, OPG The above committee determined that the thesis is acceptable in form and content and that a satisfactory knowledge of the field covered by the thesis was demonstrated by the candidate during an oral examination. A signed copy of the Certificate of Approval is available from the School of Graduate and Postdoctoral Studies. ii ABSTRACT Integral Pressurized Water Reactor (iPWR) type SMR designs were studied featuring Passive Safety Systems (PSS) in all cases. As many as 11 current SMR designs use PSS to remove decay heat. Variations in PSS designs were studied and compared using evaluation metrics and a proposed weighting method. This resulted in classification of iPWRs designs based on the methodology presented.
    [Show full text]