Safety Features of New Reactor Designs
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A Comparison of Advanced Nuclear Technologies
A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D MARCH 2017 B | CHAPTER NAME ABOUT THE CENTER ON GLOBAL ENERGY POLICY The Center on Global Energy Policy provides independent, balanced, data-driven analysis to help policymakers navigate the complex world of energy. We approach energy as an economic, security, and environmental concern. And we draw on the resources of a world-class institution, faculty with real-world experience, and a location in the world’s finance and media capital. Visit us at energypolicy.columbia.edu facebook.com/ColumbiaUEnergy twitter.com/ColumbiaUEnergy ABOUT THE SCHOOL OF INTERNATIONAL AND PUBLIC AFFAIRS SIPA’s mission is to empower people to serve the global public interest. Our goal is to foster economic growth, sustainable development, social progress, and democratic governance by educating public policy professionals, producing policy-related research, and conveying the results to the world. Based in New York City, with a student body that is 50 percent international and educational partners in cities around the world, SIPA is the most global of public policy schools. For more information, please visit www.sipa.columbia.edu A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D* MARCH 2017 *Andrew C. Kadak is the former president of Yankee Atomic Electric Company and professor of the practice at the Massachusetts Institute of Technology. He continues to consult on nuclear operations, advanced nuclear power plants, and policy and regulatory matters in the United States. He also serves on senior nuclear safety oversight boards in China. He is a graduate of MIT from the Nuclear Science and Engineering Department. -
Core Melt Stabilization Concepts for Existing and Future Lwrs and Associated R&D Needs
Core melt stabilization concepts for existing and future LWRs and associated R&D needs Manfred Fischer (corresponding author) AREVA GmbH, Severe Accident Analysis Dept. Paul Gossen Str. 100, 91052 Erlangen, Germany [email protected] Sevostian V. Bechta KTH Royal Institute of Technology, Division of Nuclear Power Safety, Physics Dept. Roslagstullsbacken 21, S-106 91 Stockholm, Sweden [email protected] Vladimir V. Bezlepkin ATOMPROECT Enterprise of ROSATOM State Corporation 82, Savushkina St., Saint Petersburg, Russia 197183 [email protected] Ryoichi Hamazaki Toshiba Corporation, Nuclear Safety System Design & Engineering Dept. 8 ShinSugita-Cho, Isogo-Ku, Yokohama 235-8523, Japan [email protected] Alexei Miassoedov Karlsruhe Institute of Technology Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany [email protected] ABSTRACT In the event of a severe accident with core melting in a NPP the stabilization of the molten corium is an important mitigation issue, as it can avoid late containment failure caused by basemat penetration, overpressure, or severe damage of internal structures. The related failure modes may result in significant long-term radiological consequences and high related costs. Because of this, the licensing framework of several countries now includes the request to implement mitigative core melt stabilization measures. This does not only apply to new builds but also to existing LWR plants. The paper gives an overview of the ex-vessel core melt stabilization strategies developed during the last decades. These strategies are based on a variety of physical principles like: melt fragmentation in a deep water pool or during molten core concrete interaction with top-flooding, water injection from the bottom (COMET concept), and retention in an outside-cooled crucible structure. -
Design of Nuclear Plants
Design of nuclear plants Reactor technology Lecture 1 Ildikó Boros Assistant lecturer Budapest University of Technology and Economics Institute of Nuclear Techniques (BME NTI) 24/10/2018 Reactor technology 1 Contents Operation of nuclear reactors (lecturer: …. Mr. Szabolcs Czifrus) Reactor technology (lecturer: I. Boros) 1. Main NPP types, reactor generations. Advanced NPP types 2. Fuel, reactor core, pressure vessel 3. PWR main systems (primary, secondary systems), safety systems 4. Containment systems 5. Cooling of NPPs 6. BWR, PHWR, other types 7. exotic reactors (fast breeders, etc.) 24/10/2018 Reactor technology 2 Nuclear energy at present • Share of nuclear in electricity production (2011 -> 2014): world 16% → 11% EU 35% → 27% Hungary 36% → 53% • 448 NPP units operate worldwide Source: WNA • 57 units under construction • Design lifetime of most units expires between 2015 and 2030 24/10/2018 Reactor technology 3 Nuclear energy at present • Share of nuclear in electricity production (2011 -> 2014): world 16% → 11% 13% EU 35% → 27% Hungary 36% → 53% • 448 NPP units operate 51% worldwide Source: WNA • 57 units under construction • Design lifetime of most units expires between 2015 and 2030 24/10/2018 Reactor technology 4 Trends in nuclear industry 24/10/2018 Source: WNA Reactor technology 5 Trends in nuclear industry Source: IAEA Power reactors under construction 24/10/2018 Reactor technology 6 BASICS OF NUCLEAR TECHNOLOGY 24/10/2018 Reactor technology 7 Nuclear fission • In certain isotopes, spontaneous or induced fission of the nucleus -
A Joint Report on PSA for New and Advanced Reactors
Nuclear Safety NEA/CSNI/R(2012)17 www.oecd-nea.org A Joint Report on PSA for New and Advanced Reactors NUCLEAR ENERGY AGENCY Unclassified NEA/CSNI/R(2012)17 Organisation de Coopération et de Développement Économiques Organisation for Economic Co-operation and Development 19-Feb-2013 ___________________________________________________________________________________________ English text only NUCLEAR ENERGY AGENCY COMMITTEE ON THE SAFETY OF NUCLEAR INSTALLATIONS Unclassified NEA/CSNI/R(2012)17 A Joint Report on PSA for New and Advanced Reactors JT03334892 English text only Complete document available on OLIS in its original format This document and any map included herein are without prejudice to the status of or sovereignty over any territory, to the delimitation of international frontiers and boundaries and to the name of any territory, city or area. NEA/CSNI/R(2012)17 ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT The OECD is a unique forum where the governments of 34 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies. The OECD member countries are: Australia, Austria, Belgium, Canada, Chile, the Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Israel, Italy, Japan, Luxembourg, Mexico, the Netherlands, New Zealand, Norway, Poland, Portugal, the Republic of Korea, the Slovak Republic, Slovenia, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. -
Nuclear Reactor Technology Assessments
UxC Special Report April 2008 Nuclear Reactor Technology Assessments Table of Contents A service of Ux Consulting 1401 Macy Drive Roswell, GA 30076 (770) 642-7745 www.uxc.com – NOTICE – The Ux Consulting Company, LLC (“UxC”) shall have title to, ownership of, and all proprietary rights in this Report. Under United States federal copyright law (17 USC 101 et seq.) it is illegal to reproduce this Report by any means without written permission from UxC. The information contained in this Report is obtained from sources that UxC believes to be reliable. UxC makes no warranty or representation, express or implied, with respect to the accuracy, completeness or usefulness of the information contained in this Report and UxC, to the maximum extent permitted by law, assumes no liability for the use or effects of any of the information or data contained in this Report. It is UxC’s strict policy not to endorse, promote, or recommend any particular securities, currencies, or other finan- cial products or instruments. Nothing contained in this Report is intended to constitute investment, legal, tax, ac- counting or other professional advice and the reader should not rely on the information provided in this Report for making financial decisions. Nuclear Reactor Technology Assessments - Apr 2008 Table of Contents Table of Contents 1 – Introduction __________________________________________________________________________ 7 Why Buy this Report ....................................................................................................................................................8 -
Generation III of Nuclear Reactors
Generation III of nuclear reactors Generation III The nuclear reactors technology Summary of the generation III of nuclear reactors technology Actual status of realization Ing. Martin Titka, AREVA NP Controls, Bratislava for Young Generation at NUSIM 2008 in Častá Papierni čka This figures are not authorized by AREVA. All data have beenCopyright compiled © AREVA from official NP Controls, sources s.r.o. l ike2007. internet All rights, by including the author rights created by patent grant or registration of a utility model or design, are reserved. Any reproduction, transmission or use of this document or its contents wholly or in part is not permitted without express written authority. Any violation may result in liability for damages. Copyright © AREVA NP Controls, s.r.o. 2008. All rights, including rights created by patent grant or registration of a utility model or design, are reserved. Any reproduction, transmission or use of this document or its contents wholly or in part is not permitted without express written authority. Any violation may result in liability for damages. AREVA NP Controls Martin Titka, 2008 Nuclear power plant generations EPR AP 1000 VVER 1200 APR 1400 APWR ABWR ESBWR ACR-1000 > Enhanced safety (4 safety trains, core catcher, protection against aircraft crash…) > Enhanced construction (modular systems, new technology) > Simplification and optimization of System/Equipment design and construction > Digital I&C > Enhanced economical aspects… AREVA NP Controls Martin Titka, 2008 All rights reserved. See copyright notice on cover sheet. 2 Perspective for New Nuclear Plants EPR (AREVA) AP 1000 (Westinghouse) VVER 1200 (ASE) PWR APR 1400 (Doosan) APWR (MHI) LWR VBER 300 (ASE) VVER 1000 (ASE) CNP-1000 (CNNC) CPR-1000 (CGNPC) CNP-600 (CNNC) Nuclear reactors BWR ABWR (GE, Hitachi) ESBWR (GE) AB 1600 (Toshiba) SWR 1000 (AREVA) HWR ACR 1000 (AECL) Indian Department of Atomic Energy AREVA NP Controls Martin Titka, 2008 All rights reserved. -
[Document Title]
[EHNUR WP 4] ADVANCED NUCLEAR POWER PLANT CONCEPTS AND TIMETABLES FOR THEIR COMMERCIAL DEPLOYMENT Steven C. Sholly1 VIENNA, June 2013 1 Institute of Safety/Security and Risk Sciences, University of Natural Resources and Life Sciences Copyright Vienna, June 2013 Media owner and editor: University of Natural Resources and Life Sciences Vienna, Department of Water, Atmosphere and Environment, Institute of Safety and Risk Sciences, Borkowskigasse 4, 1190 Wien, Austria URL: http://www.risk.boku.ac.at ReportWP4 – Advanced Nuclear Power Plant Concepts and Timetables EHNUR EXECUTIVE SUMMARY Most currently operating nuclear power plants are Generation II reactors (except for a few remaining Generation I units and a few Generation III units). Generation III and Generation III+ nuclear power plant concepts are widely recognized to be significant improvements over Generation II reactor designs. Both Generation III designs (standardized designs safer than Generation II) and Generation III+ designs (standardized designs safer than Generation II and with the expectation of greater economy of scale) are available for immediate deployment. The absolute minimum schedule for a Generation III or III+ nuclear power plant project is 10 years from feasibility study to completion of startup testing. Such a schedule is only achievable by: (a) an experienced utility, (b) with the reactor sited at an existing nuclear power plant site, and (c) with a design for which first-of-a-kind engineering (FOAKE) is complete. Under other circumstances (e.g. a utility new to nuclear generation, a greenfield site, a utility in a country without significant nuclear infrastructure, a nuclear power plant design where FOAKE has not yet been accomplished), the schedule would extend from fifteen to seventeen years and perhaps more. -
Current Reactor Technology, A.K.A. GENERATION III
Current reactor technology, a.k.a. GENERATION III: Radek Škoda Texas A&M WNU SI 2011 Christ Church, Oxford RS, Texas A&M WNU SI 2011 Overview 1. ANALOGY: Old does not mean bad but… 2. GenII/III: How are they different ? 3. Resulting types… RS, Texas A&M WNU SI 2011 Nuclear reactors « Generations » Future Advanced Operating Nuclear Systems Reactors Reactors Pionner Facilities 1950 1970 1990 2010 2030 2050 2070 2090 Generation I Generation II Generation III Generation I V Nuclear Policies ± B. Barré WNUSI 2011 p.81 RS, Texas A&M WNU SI 2011 FORD Thunderbird 1964 6.4 l 300 bhp (224 kW) V8 petrol engine 0 to 60 mph in 11seconds top speed 120 mph (200 km/h) economy 11 mpg ( 21 l/100km) RS, Texas A&M WNU SI 2011 FORD Mondeo 2008 FORD: changes in 45 years ELECTRONICS NEW TECHNOLOGY Track control Turbocharger LED lights lambda sensor Cruise control multizone A/C Electric mirror/window disk brakes GPS navigation progressive shock absorbers CD player 6-speed gearbox Tape player common rail USB radial tubeless tires … … SAFETY: “In Love With My Car” 5 STAR crash test ISOFIX ABS Crash zones Air bags Standard safety belts Analogy not perfect as Gen II reactors have had many upgrades/uprates which is not true for T-birds… RS, Texas A&M WNU SI 2011 Historical development of nuclear power Back to reactors: Gen III still evolve LWR with enhanced safety Fast reactors with Commercial and performance closed fuel cycle power reactors First reactors 1950 1970 1990 2010 2030 2050 2070 2090 Atoms for Peace TMI-2 Chernobyl Generation I • Shippingport Generation -
NATIONAL REPORT To
Government of India NATIONAL REPORT to THE CONVENTION ON NUCLEAR SAFETY Seventh Review Meeting of Contracting Parties, March 2017 August 2016 Government of India NATIONAL REPORT to THE CONVENTION ON NUCLEAR SAFETY Seventh Review Meeting of Contracting Parties, March 2017 August 2016 This page is intentionally left blank ii Foreword The Government of India ratified the Convention on Nuclear Safety on March 31, 2005. India started presenting its national reports from the 4th Review Meeting of the Contracting Parties of the CNS in 2008. The present national report for the 7th Review Meeting is the fourth one being submitted by India. The Report updates how Government of India continues to fulfill its obligations under Articles 6 through 19 of the Convention. The National Report was prepared in line with the guidelines contained in information circular INFCIRC/572/Rev.5 on “Guidelines regarding National Reports under the Convention on Nuclear Safety”, the summary report of the 6th Review Meeting, additional recommendations for the preparation of national reports for the 7th Review Meeting dated October 8, 2015, and the letter written by President of 7th Review Meeting of CNS to the Contracting Parties in February 2016. All land-based nuclear power plants including storage, handling and treatment facilities for radioactive materials attached to the NPP and directly related to the operation of nuclear power plants are covered in the national report. This report also addresses the national position with regard to the Vienna Declaration on Nuclear Safety for the implementation of the objectives of the CNS. iii This page is intentionally left blank iv CONTENTS Foreword ................................................................................................................................................................. -
A Global Review of PWR Nuclear Power Plants
applied sciences Review A Global Review of PWR Nuclear Power Plants Pablo Fernández-Arias 1,*, Diego Vergara 1 and José A. Orosa 2 1 Department of Mechanical Engineering, Catholic University of Ávila, C/Canteros, s/n, 05005 Avila, Spain; [email protected] 2 Department of N. S. and Marine Engineering, Universidade da Coruña, Paseo de Ronda, 51, 15011 A Coruña, Spain; [email protected] * Correspondence: [email protected]; Tel.: +34-920-251-020 Received: 3 June 2020; Accepted: 25 June 2020; Published: 27 June 2020 Featured Application: This work shows a global review with three analyses of the PWR nuclear design: (i) technical evolution; (ii) level of implementation in the world, and (iii) life extension scenario. Abstract: Nuclear energy is presented as a real option in the face of the current problem of climate change and the need to reduce CO2 emissions. The nuclear reactor design with the greatest global impact throughout history and which has the most ambitious development plans is the Pressurized Water Reactor (PWR). Thus, a global review of such a reactor design is presented in this paper, utilizing the analysis of (i) technical aspects of the different variants of the PWR design implemented over the past eight years, (ii) the level of implementation of PWR nuclear power plants in the world, and (iii) a life extension scenario and future trends in PWR design based on current research and development (R&D) activity. To develop the second analysis, a statistical study of the implementation of the different PWR variants has been carried out. -
Incorporation of Severe Accidents in the Licensing of Nuclear Power Plants
2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 INCORPORATION OF SEVERE ACCIDENTS IN THE LICENSING OF NUCLEAR POWER PLANTS 1 1 Marco Antonio Bayout Alvarenga , Sidney Luiz Rabello 1 Comissão Nacional de Energia Nuclear (CNEN) Rua General Severiano, 90 22294-900 Rio de Janeiro, RJ [email protected] [email protected] ABSTRACT Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. -
Nuclear Reactor Types
http://www.theiet.org/cpd Nuclear Reactor Types A Factfile provided by the Institution ofEngineering and Technology www.theiet.org/factfiles About This Factfile Contents The Institution of Engineering and Technology acts as a voice Nuclear Reactor Types ........................................................... 3 for the engineering and technology professions by providing Gas Cooled, Graphite Moderated ........................................... 3 independent, reliable and factual information to the public Heavy Water Cooled and Moderated ...................................... 3 and policy makers. This Factfile aims to provide an accessible Water Cooled and Moderated ................................................ 3 guide to current technologies and scientific facts of interest to Water Cooled, Graphite Moderated ........................................ 4 the public. Current Developments ............................................................ 6 For more Position Statements and Factfiles on engineering Next-Generation (NG) CANDU .............................................. 6 and technology topics please visit http://www.theiet.org/ Advanced Pressurised Water Reactor AP1000 ....................... 6 factfiles. Evolutionary Power Reactor/European Pressurised-Water Reactor (EPR) ....................................................................... 6 The Institution of Engineering and Technology EPR Construction Projects ..................................................... 7 Economic Simplified Boiling Water Reactor (ES BWR) ..........