DOCSLIB.ORG

Safety Analysis of a Compact Integral Small Light Water Reactor

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Safety Analysis of a Compact Integral Small Light Water Reactor Safety Analysis of a Compact Integral Small Light Water Reactor by Zhiyuan Cheng B. Eng. Nuclear Science and Engineering (2018) Fudan University 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 May 2020 © 2020 Massachusetts Institute of Technology. All rights reserved. Signature of Author……………………………………………………………... Zhiyuan Cheng Department of Nuclear Science and Engineering May 11, 2020 Certified by: …………………………………………………………………… Koroush Shirvan Assistant Professor of Nuclear Science and Engineering Thesis Supervisor Certified by: …………………………………………………………………… Emilio Baglietto Associate Professor of Nuclear Science and Engineering Thesis Reader Accepted by ...….….…….......………………………………………………………… Ju Li, Ph.D. Battelle Energy Alliance Professor of Nuclear Science and Engineering Professor of Materials Science and Engineering Chair Department Committee on Graduate Students Safety Analysis of a Compact Integral Small Light Water Reactor by Zhiyuan Cheng Submitted to the Department of Nuclear Science and Engineering on May 11, 2020 in Partial Fulfillment of the Requirements for the Degree of Master of Science in Nuclear Science and Engineering Abstract Small modular reactors (SMRs) hold great promise in meeting a diverse market while reducing the risk of delays during nuclear construction compared to large gigawatt-sized reactors. However, due to lack of economy of scale, their capital cost needs to be reduced. Increasing the compactness or power density of the nuclear island is one way to reduce capital cost. This work first assesses the transient analysis of a compact integral small light water reactor to examine its safety performance. Subsequently, a parametric optimization study with the goal of increasing its power density (i.e. improve its market competitiveness) while maintaining safety is performed. A model of the reactor is established using RELAP5/3.3gl, with reference to the features of Nuward SMR. Nuward is a compact 170 MWe Pressurized Water Reactor, whose key features include the use of Compact Steam Generators and a large water tank in which the containment submerges for passive heat removal. A transient analysis of the reference reactor after Loss of Flow Accident, Station Blackout, and Loss of Coolant Accident is carried out. Following all three accidents, the integrity of the fuel and the reactor is maintained. The passive cooling system is estimated to provide 12 – 13 days of grace period. The parametric optimization study indicates that the size of the tank can be reduced to half and still maintain sufficient margin to both short-term and long-term safety goals after all three transients with an estimated grace period of 7 – 8 days. In addition, the configuration of the passive safety system can be rearranged to reduce the size of the containment to 76% of the reference design without affecting its safety performance. By increasing the coolant enthalpy change, which also results in a higher thermal efficiency, the electrical output of the reference design can be enhanced by 44% without major design changes. If the number of pumps in the vessel are increased by 2, the electrical output can be enhanced by 102% while satisfying all safety criteria. The uprated power that satisfies a 72- hour grace period requires a tank size that is 32.5% of the reference design. Such compact and simplified nuclear steam supply system can partially address the lack of economy of scale for the reference SMR and improve its market competitiveness. Thesis supervisor: Koroush Shirvan Title: Assistant Professor of Nuclear Science and Engineering Acknowledgements I would like to thank Prof. Koroush Shirvan for the opportunity to work with him and his continuous guidance throughout my thesis, Prof. Emilio Baglietto and Prof. Jacopo Buongiorno for their support on this project, Dr. Xu Wu and Dr. Wei Li for the help on RELAP model development. I would also like to thank EDF for funding this project. I would also like to thank Laurent Amice and all the EDF staff who provided information and feedback throughout the project. Lastly, I would like to thank all my family and friends for their moral support and encouragement. Table of contents Abstract .......................................................................................................................... 2 Acknowledgements ........................................................................................................ 3 List of Figures ................................................................................................................ 6 List of Tables ................................................................................................................ 10 Chapter 1. Introduction ................................................................................................ 12 1.1 Motivation ................................................................................................. 12 1.2 Nuward reactor design ............................................................................... 15 1.3 Thesis objective and outline ...................................................................... 20 Chapter 2 Methodology ............................................................................................... 22 2.1 RELAP model development ...................................................................... 22 2.1.1 RELAP model of the core .......................................................................... 24 2.1.2 RELAP model of the steam generators ..................................................... 28 2.1.3 RELAP model of the pumps ...................................................................... 31 2.1.4 RELAP model of the pressurizer ............................................................... 33 2.1.5 RELAP model of the pipes and pressure vessel ........................................ 34 2.1.6 RELAP model of the secondary side ......................................................... 35 2.1.7 RELAP model of the containment ............................................................. 35 2.1.8 RELAP model of the safety system ........................................................... 36 2.2 Steady-state simulation result .................................................................... 43 Chapter 3. Transient analysis ....................................................................................... 46 3.1 Overview of transient analysis .................................................................. 46 3.2 LOFA transient analysis ............................................................................. 46 3.3 SBO transient analysis ............................................................................... 51 3.4 LOCA transient analysis ............................................................................ 56 Chapter 4 Optimization study ...................................................................................... 65 4.1 General description .................................................................................... 65 4.2 Passive safety system optimization ........................................................... 66 4.3 Steam generator alternative ....................................................................... 78 4.4 Power uprating ........................................................................................... 86 4 4.4.1 Power uprating approaches ........................................................................ 86 4.4.2 Transient analysis with uprated power ...................................................... 90 Chapter 5 Conclusion and future work ........................................................................ 99 5.1 Conclusion ................................................................................................. 99 5.2 Future work.............................................................................................. 100 Appendix .................................................................................................................... 102 PCHE benchmarking in RELAP ......................................................................... 102 References .................................................................................................................. 110 5 List of Figures Figure 1-1 Design concept for one unit of the Nuward SMR Figure 1-2 Four-reactor configuration of the Nuward SMR Figure 1-3 Cross section of the Nuward reactor pressure vessel Figure 2-1 Simplified schematic of Nuward SMR for RELAP model development Figure 2-2 RELAP model of the Nuward SMR Figure 2-3 Heat flux along fuel rod of the average core, the hottest assembly and the hottest pin Figure 2-4 RELAP model of the core Figure 2-5 SCRAM reactivity feedback in the RELAP model Figure 2-6 Channel geometry compact steam generators (a) Areva design; (b) PCHE Figure 2-7 Example of spool-type pump with mixed flow hydraulics Figure 2-8 Volumes of steam and liquid in the RELAP model of the pressurizer Figure 2-9 Equivalent water tank RELAP model with only one ANNULUS component Figure 2-10 Simulation result over 2000 seconds of the model shown in Figure 2-9 Figure 2-11 Equivalent water tank RELAP model with two ANNULUS components Figure 2-12 Simulation result over 2000 seconds of the model shown in Figure 2-11 Figure 2-13 Schematic of the reactor vessel, safety
Load more

Recommended publications
  • Survey of Design and Regulatory Requirements for New Small Reactors, Contract No
    Canadian Nuclear Safety Commission - R550.1 Survey of Design and Regulatory Requirements for New Small Reactors, Contract No. 87055-13-0356 Final Report - July 3, 2014 RSP-0299 Canadian Nuclear Safety Commission R550.1 Survey of Design and Regulatory Requirements for New Small Reactors, Contract No. 87055-13-0356 Final Report July 3, Released for Brian Gihm 0 Victor Snell Jim Sarvinis Milan Ducic 2014 Use Victor Snell Date Rev. Status Prepared By Checked By Approved By Approved By Client - CNSC H346105-0000-00-124-0002, Rev. 0 Page i © Hatch 2015 All rights reserved, including all rights relating to the use of this document or its contents. Canadian Nuclear Safety Commission - R550.1 Survey of Design and Regulatory Requirements for New Small Reactors, Contract No. 87055-13-0356 Final Report - July 3, 2014 Executive Summary The objectives of this report are to perform a design survey of small modular reactors (SMRs) with near-term deployment potential, with a particular emphasis on identifying their innovative safety features, and to review the Canadian nuclear regulatory framework to assess whether the current and proposed regulatory documents adequately address SMR licensing challenges. SMRs are being designed to lower the initial financing cost of a nuclear power plant or to supply electricity in small grids (often in remote areas) which cannot accommodate large nuclear power plants (NPPs). The majority of the advanced SMR designs is based on pressurized water reactor (PWR) technology, while some non-PWR Generation IV technologies (e.g., gas-cooled reactor, lead-cooled reactor, sodium-cooled fast reactor, etc.) are also being pursued.
    [Show full text]
  • IMT Atlantique, Orano, Naval Group Et L'irsn Reconduisent La Chaire
    Le 15/05/2018 Communiqué de presse IMT Atlantique, Orano, Naval Group et l’IRSN reconduisent la chaire RESOH avec l’Andra pour nouveau partenaire Lancée en 2012, par IMT Atlantique et ses trois partenaires Orano, Naval Group et l’IRSN, la chaire de recherche et d’enseignement RESOH « REcherche en Sûreté Organisation Hommes » constitue une démarche innovante. Elle réunit des exploitants du nucléaire et l’institut d’expertise d’appui de l’Autorité de sûreté autour d’une volonté commune de réfléchir et d’agir au service d’une performance industrielle « sûre ». La convention signée au début de l’année 2018 reconduit la chaire RESOH jusqu’en octobre 2022 et marque l’arrivée d’un nouveau partenaire, l’Andra (Agence nationale pour la gestion des déchets radioactifs). La chaire RESOH-2 s’appuiera sur les acquis et l’originalité de RESOH-1, qui a permis d’initier des collaborations inédites en matière de recherche et des discussions entre les acteurs de la sûreté nucléaire. Ce projet met l’accent sur les relations inter-organisationnelles et marque la volonté de ne pas isoler la sûreté nucléaire des autres formes de performance industrielle, faisant ainsi émerger le concept de « performance industrielle sûre ». RESOH-2 reprend et approfondit les 3 axes de recherche initialement définis, avec la volonté de renforcer les liens transversaux entre ces différents domaines : • Gestion des projets complexes, • Pilotage de la valeur des relations de sous-traitance (engagements contractuels, travailler ensemble). • Relations contrôleur-contrôlé et gestion de l’équilibre entre sécurité réglée et sécurité gérée. Cette seconde étape est aussi l’occasion de capitaliser sur la connaissance des sites des partenaires industriels et de valider l’investissement de terrain effectué pour appréhender la complexité d’équipements tels que La Hague, le chantier de construction des sous-marins nucléaires d’attaque de classe Barracuda, ou des activités d’expertise de l’IRSN (Institut de Radioprotection et de Sûreté Nucléaire).
    [Show full text]
  • Recueil Des Actes Administratifs De La Manche
    PREFET DE LA MANCHE RECUEIL DES ACTES ADMINISTRATIFS DE LA MANCHE DOCUMENTATION ET INFORMATIONS JANVIER 2020 Le contenu intégral des textes et/ou les documents et plans annexés peut être consulté auprès du service sous le timbre duquel la publication est réalisée et sur le site Internet de la préfecture : http://www.manche.gouv.fr Rubrique : Publications - Annonces et avis - Recueil des actes administratifs 2 SOMMAIRE CABINET DU PREFET ..................................................................................................................................................................................... 3 Arrêté n° 19-588 du 20 décembre 2019 portant attribution de la médaille d’honneur du Travail - Promotion du 01 janvier 2020 .................... 3 Arrêté n° 20-001 du 6 janvier 2020 modifiant l’arrêté préfectoral accordant la médaille d’honneur Agricole, promotion du 1er janvier 2020 ..................................................................................................................................................................................................... 14 Arrêté n° 20-002 du 6 janvier 2020 modifiant l’arrêté préfectoral portant attribution de la médaille d’honneur Régionale, Départementale et Communale, promotion du 1er janvier 2020 ...................................................................................................................... 14 SOUS-PREFECTURE DE CHERBOURG ......................................................................................................................................................
    [Show full text]
  • Advanced Reactors
    © 2012 European Nuclear Society Rue Belliard 65 1040 Brussels, Belgium Phone + 32 2 505 30 54 Fax +32 2 502 39 02 E-mail [email protected] Internet www.euronuclear.org ISBN 978-92-95064-14-0 These transactions contain all contributions submitted by 7 December 2012. The content of contributions published in this book reflects solely the opinions of the authors concerned. The European Nuclear Society is not responsible for details published and the accuracy of data presented. 2 of 96 ENC2012-A0026 Development of a thermohydraulic model of the Lazaro Chueca, A. (1); Ammirabile, L. (1); European Sodium Fast Reactor (ESFR) using Martorell, S. (2) the system code TRACE. 1 - JRC-IET, Netherlands 2 - Universidad Politecnica de Valencia, Spain ENC2012-A0028 Generation IV Technology Status including Anderson, G. (1); Lillington, J. (1) recent R & D Activities in ANSWERS 1 - AMEC, United Kingdom ENC2012-A0053 Preliminary Design Assessment of the Molten Merle-Lucotte, E. (1); Allibert, M. (1); Salt Fast Reactor Brovchenko, M. (1); Ghetta, V. (1); Heuer, D. (1); Rubiolo, P. (1); Laureau, A. (1) 1 - LPSC-IN2P3-CNRS / UJF / Grenoble INP, France ENC2012-A0078 Development of materials to withstand the Shepherd, D. (1) extreme, irradiated environments in advanced 1 - National Nuclear Laboratory, United Kingdom nuclear fission reactors ENC2012-A0126 ARCHER:- Material and component challenges Buckthorpe, D. (1) for the Advanced High Temperature Reactor 1 - AMEC, United Kingdom ENC2012-A0258 Pressure Drop Analysis of a Pressure-Tube Type Peiman, W. (1); Saltanov, E. (1); Pioro, I. SuperCritical Water-Cooled Reactor (SCWR) (1); Gabriel, K. (1) 1 - University of Ontario Institute of Technology, Canada ENC2012-A0003 SPES3: THE INTEGRAL FACILITY FOR Ferri, R.
    [Show full text]
  • Financial Report 2016 —
    FINANCIAL REPORT 2016 — Ladies and gentlemen, We have called this ordinary Annual General Meeting in accordance with the provisions of the law and our company’s articles of association to report on business in the course of the fi nancial year ended December 31, 2016 and to submit for approval the company’s annual and consolidated fi nancial statements. At the meeting, the report of the Chairman of the Board of Directors, the general report of the company’s Statutory Auditors on the annual fi nancial statements for the fi nancial year ended December 31, 2016, the report of the Statutory Auditors on the consolidated fi nancial statements for the fi nancial year ended December 31, 2016 and the special report of the Statutory Auditors on related-party agreements will be presented to you. The required notices of the meeting have been duly sent to you. The Statutory Auditors’ reports, the management report, the company’s annual fi nancial statements, the consolidated fi nancial statements and all related documents required under the applicable laws and regulations have been sent to you or made available to you at the company’s registered offi ce in accordance with all legal requirements and within the required timeframes to allow you to familiarise yourselves with their content. The fi nancial statements presented to you have been drawn up in accordance with International Financial Reporting Standards (IFRS) as adopted in the European Union, and with the principles of prudence and fairness. Hervé Guillou Chairman & Chief Executive Offi cer DCNS Financial report ! MANAGEMENT REPORT I. Presentation of the Group and DCNS’ position during the year 5 II .
    [Show full text]
  • Rapport Responsabilité Sociétale De L'entreprise 2019
    NON SENSIBLE RAPPORT RESPONSABILITÉ SOCIÉTALE DE L’ENTREPRISE 2019 © Propriété Naval Group SA 2020 - tous droits réservés. Ce document/logiciel dans son contenu et dans sa forme est la propriété de Naval Group et/ou de tiers. Toute utilisation, reproduction, modification, traduction, communication ou représentation intégrale ou partielle du présent document/logiciel qui n’a pas été préalablement autorisée par écrit par Naval Group est formellement interdite. Une telle utilisation, reproduction, modification, traduction, communication ou représentation intégrale ou partielle non autorisée, par quelque moyen que ce soit, constituerait une contrefaçon sanctionnée par la loi au plan pénal et civil et d’une manière générale, une atteinte aux droits de Naval Group. NON SENSIBLE Table des matières I. GOUVERNANCE DU GROUPE ...................................................................................... 7 1. Les ambitions ........................................................................................................ 9 a. Profil de l’organisation ...................................................................................... 9 b. Stratégie et analyse .......................................................................................... 9 c. Aspects et périmètres pertinents identifiés ................................................ 11 2. La gouvernance .................................................................................................. 11 a. Administration et contrôle.............................................................................
    [Show full text]
  • Core Design and Optimization of the High Conversion Small Modular Reactor
    Technische Universität München Fakultät für Maschinenwesen Lehrstuhl für Nukleartechnik Core Design and Optimization of the High Conversion Small Modular Reactor Denis Janin Vollständiger Abdruck der von der Fakultät für Maschinenwesen der Technischen Universität München zur Erlangung des akademischen Grades eines Doktor-Ingenieurs (Dr.-Ing.) genehmigten Dissertation. Vorsitzender: Prof. Phaedon-Stelios Koutsourelakis, PhD Prüfer der Dissertation: 1. Prof. Rafael Macián-Juan, PhD 2. Prof. Dr. Jean-Baptiste Thomas Die Dissertation wurde am 08.05.2018 bei der Technischen Universität München eingereicht und durch die Fakultät für Maschinenwesen am 01.11.2018 angenommen. ABSTRACT This research work investigates the design and optimization of the high conversion small modular reactor (HCSMR) core. The HCSMR has a thermal output of 600 MW for 200 MW electrical. It is an integrated PWR with a tightened fuel assembly lattice. The rod-to-rod pitch is 1.15 cm in a hexagonal fuel assembly geometry. As a result the moderation ratio (1.0) is reduced compared to large PWRs (around 2.0) and the HCSMR has an improved ability to convert 238U into 239Pu and use plutonium isotopes more efficiently. The core is loaded with MOX fuel. The HCSMR concept finds its roots both in large high conversion light water reactors and small modular reactor (SMR) concepts. The reduced core size results in an increased neutron leakage rate compared to large cores. This intrinsically supports the core behavior in voided situations. The necessity to introduce fertile fuel materials in the core to keep negative void coefficients is reduced, contributing to the HCSMR safety and limited core heterogeneity.
    [Show full text]
  • 60 Years of Marine Nuclear Power: 1955
    Marine Nuclear Power: 1939 - 2018 Part 4: Europe & Canada Peter Lobner July 2018 1 Foreword In 2015, I compiled the first edition of this resource document to support a presentation I made in August 2015 to The Lyncean Group of San Diego (www.lynceans.org) commemorating the 60th anniversary of the world’s first “underway on nuclear power” by USS Nautilus on 17 January 1955. That presentation to the Lyncean Group, “60 years of Marine Nuclear Power: 1955 – 2015,” was my attempt to tell a complex story, starting from the early origins of the US Navy’s interest in marine nuclear propulsion in 1939, resetting the clock on 17 January 1955 with USS Nautilus’ historic first voyage, and then tracing the development and exploitation of marine nuclear power over the next 60 years in a remarkable variety of military and civilian vessels created by eight nations. In July 2018, I finished a complete update of the resource document and changed the title to, “Marine Nuclear Power: 1939 – 2018.” What you have here is Part 4: Europe & Canada. The other parts are: Part 1: Introduction Part 2A: United States - Submarines Part 2B: United States - Surface Ships Part 3A: Russia - Submarines Part 3B: Russia - Surface Ships & Non-propulsion Marine Nuclear Applications Part 5: China, India, Japan and Other Nations Part 6: Arctic Operations 2 Foreword This resource document was compiled from unclassified, open sources in the public domain. I acknowledge the great amount of work done by others who have published material in print or posted information on the internet pertaining to international marine nuclear propulsion programs, naval and civilian nuclear powered vessels, naval weapons systems, and other marine nuclear applications.
    [Show full text]
  • Specials Steels and Superalloys for Nuclear Industry
    Specials Steels and Superalloys for Nuclear Industry Enhancing your performance or almost 60 years Aubert & Duval has been a key partner for the development Aubert & Duval: Your partner F of forged and rolled products, especially those customized for the nuclear market. to energize your success With full vertical integration from melting, to remelting, hot converting and machining (rough machining through to near-net-shape parts), Aubert & Duval offers wide-ranging cutting edge capabilities for nuclear application. Equipment Process flow . MELTING Melting furnaces (EAF, AOD, LF) Melting up to 60 tons Vacuum Induction Melting (VIM) HPS NiSA up to 20 tons Remelting furnaces (ESR, VAR) up to 30 tons powder atomization (Gaz, VIM) . FORGING Open-die forging presses Remelting Powder atomization from 1,500 to 10,000 tons Closed-die forging presses from 4,500 to 65,000 tons . ROLLING MILL HPS 7-200 mm diameter bars High Performance Steels: Conversion . HEAT TREATMENT A range of alloyed steels with Solution and ageing furnaces tightly controlled characteristics HPS Ti NiSA AL PM Horizontal and vertical quenching offering optimum value for equipment customers. TESTING Forging Closed-die Hot Isostatic Immersion UT up to 13 tons and/or rolling Forging Forging Pressing (HIP) ©Valinox-Franck Dunouau (28,000 lbs) Automated contact UT up to 20 tons NiSA Aubert & Duval has also put in place over many decades dedicated skills to co-design re-engineered Nickel-base Superalloys: Nickel-based superalloys: materials metallurgical solutions with our clients. keeping high surface integrity while Sales of alloys and superalloys have progressively expanded across a broad spectrum of primary withstanding severe mechanical circuit contractors and their subcontractors.
    [Show full text]
  • Advances in Small Modular Reactor Technology Developments
    Advances in Small Modular Reactor Technology Developments Advances in Small Modular Reactor Technology Developments Technology in Small Modular Reactor Advances A Supplement to: IAEA Advanced Reactors Information System (ARIS) 2018 Edition For further information: Nuclear Power Technology Development Section (NPTDS) Division of Nuclear Power IAEA Department of Nuclear Energy International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna, Austria Telephone: +43 1 2600-0 Fax: +43 1 2600-7 Email: [email protected] Internet: http://www.iaea.org Printed by IAEA in Austria September 2018 18-02989E ADVANCES IN SMALL MODULAR REACTOR TECHNOLOGY DEVELOPMENTS 2018 Edition A Supplement to: IAEA Advanced Reactors Information System (ARIS) http://aris.iaea.org DISCLAIMER This is not an official IAEA publication. The material has not undergone an official review by the IAEA. The views expressed do not necessarily reflect those of the International Atomic Energy Agency or its Member States and remain the responsibility of the contributors. Although great care has been taken to maintain the accuracy of information contained in this publication, neither the IAEA nor its Member States assume any responsibility for consequences which may arise from its use. The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA.
    [Show full text]
  • AIEA D”Pliant 2013
    The CEA is a leading IRSN is the public AREVA supplies ever DCNS designs, builds The EDF group is ASSYSTEM is an ANDRA (National AFNI (France I2EN: The mission of The INSTN stands public body in research, expert in nuclear and safer and more and supports French an integrated energy international Agency for Radioactive International Nuclear the International out as a specifically development and radiological risks for economical solutions Navy nuclear company with a Engineering and Waste Management) Agency) is your Institute of Nuclear nuclear oriented innovation. The CEA is all nuclear facilities. for power generation powered vessels for presence in a wide Innovation Consultancy ensures the sustainable partner to benefit from Energy (I2EN) is to higher education active in four main As a research and with less carbon: more than 50 years. range of electricity- representing 10,200 management of the experience and provide the best institution. As part of areas: low-carbon expert appraisal nuclear and With a large offer related businesses: people worldwide. radioactive waste know-how of France in training solutions for the CEA, the INSTN energies, defence and organisation, IRSN renewables. Ranked covering engineering, nuclear, renewable As a key participant produced in France the preparation of human resources draws on the scientific security, information works together with all first in the global manufacturing and and fossil-fuel fired in the nuclear industry and provides surface your nuclear project. development in potential of this technology and health the parties concerned nuclear power services, DCNS energy production; for 45 years, disposal solutions for AFNI will assist you to nuclear energy to leading institution in technology.
    [Show full text]
  • Nuclear Power: Is the Renaissance Real Or a Mirage? H-Holger Rogner & Alan Mcdonald International Atomic Energy Agency (IAEA) 1
    Nuclear Power: Is the Renaissance Real or a Mirage? H-Holger Rogner & Alan McDonald International Atomic Energy Agency (IAEA) 1 Keywords: Nuclear power status and projections, nuclear power economics, manufacturing capacity Summary In 2009, in the midst of the global financial and economic crises that began in 2008, and as the nuclear power industry posted its first two-year decline in installed capacity in history, the IAEA revised its projections for future nuclear power growth upwards. This paper summarizes the status of nuclear power in the world today and the status of all steps in the nuclear fuel cycle. It summarizes nuclear power’s prospects and important trends in key factors. It explains the reasons for optimism and rising expectations about nuclear power’s future, and it acknowledges that there is, nonetheless, much uncertainty. Conflicting indicators For nuclear power, 2009 was a second straight paradoxical year. In 2008, pprojections of future growth were revised upwards even though installed nuclear capacity actually declined during the year and no new reactors were connected to the grid. It was the first year since 1955 without at least one new reactor coming on-line. There were, however, ten construction starts, the most since 1987. In 2009 installed nuclear capacity dropped yet again, the first two-year drop in nuclear power’s history, with three reactors being retired and only two new ones connected to the grid. But the IAEA’s projections for nuclear power growth were again revised upward, by about 8%, even as the world was still dealing with the financial and economic crises that started in late 2008.
    [Show full text]