Small and Medium Power Reactors 1987

Total Page:16

File Type:pdf, Size:1020Kb

Small and Medium Power Reactors 1987 IAEA-TECDOC-445 SMAL MEDIUD LAN M POWER REACTORS 1987 A TECHNICAL DOCUMENT ISSUED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1987 SMAL MEDIUD LAN M POWER REACTORS 1987 IAEA, VIENNA, 1987 IAEA-TECDOC-445 Printed by the IAEA in Austria December 1987 PLEAS AWARE EB E THAT ALL OF THE MISSING PAGES IN THIS DOCUMENT WERE ORIGINALLY BLANK The IAEA does not normally maintain stocks of reports in this series. However, microfiche copie f thesso e reportobtainee b n sca d from IN IS Clearinghouse International Atomic Energy Agency Wagramerstrasse5 0 10 P.Ox Bo . A-1400 Vienna, Austria Orders should be accompanied by prepayment of Austrian Schillings 100, fore for e chequa th th f m IAEf m o n o n i i r eAo microfiche service coupons orderee whicb y hdma separately fro INIe mth S Clearinghouse. FOREWORD This TEC-DOC follows the publication of TEC DOC 347 Small and Medium Power Reactors Project Initiation Study - Phase I published in 1985 and TEC-DOC 376 Small and Medium Power Reactors 1985 published in 1986. It is mainly intended for decision makers in Developing Member States interested in embarking on a nuclear power programme. It consists of two parts : Part I; Guidelines for the introduction of Small and Medium Power Reactors in Developing Countries. These Guidelines were established during n Advisoro y Group Meeting hel n Vienni d5 May 1 ao t ,fro 1 19871 m . Their purpose is to review key aspects relating to the introduction f Smalo d Mediuan l m Power Reactor developinn i s g countries. Par: Up-dateII t d Informatio n o SMPn R Concepts Contribute y b Supplied r Industries. e Accordinrecommendationth o t e gSecon th f do s Technical Committee Meeting on SMPRs held in Vienna in March 1985, this part contains the up-dated information formerly published in Annex I of the above mentioned TEC DOC 347. EDITORIAL NOTE In preparing this material for the press, staff of the International Atomic Energy Agency have mounted and paginated the original manuscripts and given some attention to presentation. The views expresseddo not necessarily reflect those of the governments of the Member States or organizations under whose auspices the manuscripts were produced. thisin The bookuse particularof designations countriesof territoriesor does implynot any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities institutions and delimitation the of or theirof boundaries. The mention of specific companies or of their products or brand names does not imply any endorsement recommendationor IAEA. partthe the of on CONTENTS PART I - GUIDELINES FOR THE INTRODUCTION OF SMALL AND MEDIUM POWER REACTOR DEVELOPINN SI G COUNTRIES 1.1. Introduction ..............................................................................9 . 1.2. SMPR considerations ................................................................... 9 1.3. National development and energy policy ........................................... 10 1.4. Government commitment to nuclear power ........................................ 10 1.5. Public acceptance of a nuclear power programme ................................ 11 1.6. National infrastructure .................................................................1 1 . 1.6.1. General ..........................................................................1 1 . 1.6.2. National legislation ............................................................. 12 1.6.3. Organizational infrastructure ................................................. 12 1.6.4. Manpower .......................................................................3 1 . 1.7. Siting ......................................................................................4 1 . 1.8. Electrical grid ............................................................................ 14 1.9. Industrial participatio e nucleath n ni r power programme .......................5 1 . 1.10. Contractual approach .................................................................... 15 1.11. Financing .................................................................................. 16 1.12. Fuel cycle ................................................................................. 16 1.13. Operational waste managemen disposad an t l ......................................7 1 . 1.14. Technical assistance ..................................................................... 17 BIBLIOGRAPHY ............................................................................................7 1 . LIST OF PARTICIPANTS .................................................................................. 19 PART II — UPDATED INFORMATION ON SMALL AND MEDIUM POWER REACTOR CONCEPTS CONTRIBUTED BY SUPPLIER COUNTRIES Introduction ..................................................................................... 23 11.1. ARGOS PHWR 380, ENACE, Argentina ...................................... 24 11.2. CANDU 300 - AECL, Canada .................................................. 31 FRAMATOME— 0 30 P 11.3N . , France .............................................5 3 . 11.4. BBC/HRB - HTR, FRG ........................................................... 39 11.5. INTERATOM - HTR Module, FRG ........................................... 51 11.6. KWU PHWR 300, FRG ............................................................ 58 11.7. ANSALDO NIR300R APW , Italy ..............................................0 6 . 11.8. ANSALDO NIRA CIRENE 300, Italy .......................................... 63 11.9. HITACHI BWR 500, Japan ........................................................ 67 11.10. HITACHI SBWR 200, Japan ...................................................... 69 11.11. MITSUBISHI PWR 300, Japan ................................................... 71 11.12. TOSHIBA BWR 500, Japan ....................................................... 72 11.13. TOSHIBA BWR 300, Japan ....................................................... 73 11.14. ASEA ATO M- PIUS , Sweden .................................................7 7 . 11.15. GEC Magnox, UK ................................................................... 82 11.16. NNC Magnox 300, UK ............................................................. 83 11.17. ROLLS-ROYCE Prefabricated PWR 300, UK ................................. 87 11.18. B&W CNSG, USA .................................................................. 91 11.19. B&W CNSS, USA ................................................................... 95 11.20. G.E. Future Small BWR ..................................................A ,US 9 9 . 11.21. G.E. HTGR ..................................................................A US , 4 10 . 11.22. G.E. PRISM, USA .................................................................. 104 11.23. ATOMENERGOEXPORT WER 440, USSR ................................. 109 PART I GUIDELINE INTRODUCTIOE TH R SFO N SMALF O MEDIUD LAN M POWER REACTORS IN DEVELOPING COUNTRIES I.I. INTRODUCTION e e purposguidelineTh th f o revieo t e s y aspecti ske w s relatine th o t g introductio f o Smald nMediu an l m Power Reactors (SMPRs n i developin) g countries. Accordin e Agency'th o t g s definitio n electricita n SMP a ns i R y producing nuclear powe r e capacit 0 MWeplanth 50 n ,o i t TEC-DO y0 rang10 Cf o e 347, (see bibliography). These guidelines are mainly intended for decision makers in developing countries interested in embarking on a nuclear power programme. The various SMPR studies implemented by the Agency have shown that nuclear energy is a viable alternative in many developing countries to face electricity consumption increase. SMPRs present interesting featuree th r fo s introductio f nucleao n r energ n thosi y e countries t thiBu .s introductios ha n to be analyzed under country specific conditions. The Agency upon request will assist Member State undertakinn i s g such studies. 1.2. SMPR CONSIDERATIONS Particularly for developing countries, it is clearly recognized that the utilization of nuclear power is necessary for diversification of energy resources. In considering the choice between SMPRs and larger power reactors, a numberther e f ar factoreo s which ten o favout d e SMPth rR concept e maiTh .n factors are summarized as follows: recognizing that a single unit should not exceed a given fraction of the grid size ,e introduceb SMPR y n earliesma a t a d r date than larger units, therefore SMPRs allo r earliefo w r introductio f nucleao n r power programme wit n earliea h r realizatio e resultinth f o n g potential benefits, in considering grid characteristics, SMPRs provide a better fit in terms of grid size and demand growth rate, and generally result in less requirements for grid adaptation and additional reserve margins, e morb SMPR ey ma ssimila n siz i ro othe t e r industrial projects existing in developing countries, there is the potential that, relative to larger reactors, overall management of an SMPR project may be easier, lead times may be shorter, siting could be less restrictive, smaller demands may be placed on the transportation syste t earliea m r dates d thaan , t financin e morb ey ma g easily obtained. s importani t I e abovo notth t t ef o factorthal al t se assesseb hav o t e d on a country specific basis. s describeA f thi o n Par i dI s I t publication, presently ther e severaar e l SMPR alternatives under various stages of development, thereby allowing flexibility for developing countries in their plant and/or programme selection. Notwithstandin e perceiveth g d advantage s listea s d above,e b ther y ma e certain
Recommended publications
  • KERNFORSCHUNGSANLA JULICH Gmbh
    KERNFORSCHUNGSANLA JULICH GmbH Proceedings of the Workshop on Structural Design Criteria for HTR Jiilich, 31. January - 1. February 1989 Editors: G. Breitbach F. Schubert H. Nickel Jiil-Conf-71 April 1989 ISSN 0344-5798 Als Manuskript gedruckt Berichte der Kernforschungsanlage Jülich - Jül-Conf-71 Zu beziehen durch: ZENTRALBIBLIOTHEK der Kernforschungsanlage Jülich GmbH Postfach 1913 • D-5170 Jülich (Bundesrepublik Deutschland) Telefon: 02461/610 • Telex: 833556-0 kf d Proceedings of the Workshop on Structural Design Criteria for HTR Jiilich, 31. January - 1. February 1989 Editors: G. Breitbach F. Schubert H. Nickel Workshop on Structural Design Criteria for HTR Introductural remarks Most of the presentations given in this workshop are based on the German research and development project "HTR Design Criteria" carried out under the sponsorship of the Federal Ministry of Research and Technology. The main emphasis of this work was to acquire the fundamental principles and basic data for the establishment of German KTA-rules (KTA: Nuclear Safety Standards Commission) for the design of HTR-structural components. The project began in 1984 and the research work divided among several working groups and task forces, with participation from several institutions and companies. The role of coordination has been carried out by the Institute for Reactor Materials, Nuclear Research Centre Julien, headed by Prof. Dr. H. Nickel. The work has been organized into four working groups: a) Technical safety boundary conditions; b) Metallic structural components; c) Prestressed concrete pressure vessel; d) Graphitic structural components. The required work in each group was divided between a number of task forces. The membership of each group and task force is given in the appendix.
    [Show full text]
  • Nuclear and Energy Independence
    Meetings ANS WINTER MEETING Nuclear and energy independence HILE ORGANIZATIONS HAVE canceled or altered conferences in W the wake of the events of Sep- Major themes of the plenary: tember 11, the American Nuclear Society at- tracted more than 1100 attendants to its Win- N ter Meeting in November in Reno, Nev. “In H2 power can be an application light of recent events, that is a remarkable ac- complishment,” ANS President Gail Marcus of nuclear commented during the opening plenary. The large gathering was due perhaps to the upbeat mood of the industry in general, thanks N 50 years since first electricity with EBR-I in part to the Bush administration’s support of the continued use and further deployment of N nuclear power, and because any hope for re- A proposal for a continental supergrid ducing greenhouse gas emissions likely would include nuclear power in a national energy policy. oring the EBR-I and the nuclear pioneers who was associate project director of the EBR-I During the plenary Marcus paraphrased developed it. The proclamation recognized the and project manager for another reactor, the Charles Dickens by saying, “It is the best of environmental benefits of nuclear power and EBR-II. He later became director of the Re- times, it is the worst of times,” in reference feted those who worked to provide the world actor Engineering Division at Argonne Na- to the terrorist attacks on the United States with “clean, sustainable energy for the bene- tional Laboratory before moving on to Illinois and the opportunity for nuclear power to fit of humankind for centuries by making use Power Company.
    [Show full text]
  • HTGR Dust Safety Issues and Needs for Research and Development
    INL/EXT-11-21097 HTGR Dust Safety Issues and Needs for Research and Development P. W. Humrickhouse June 2011 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. INL/EXT-11-21097 HTGR Dust Safety Issues and Needs for Research and Development P. W. Humrickhouse June 2011 Idaho National Laboratory Next Generation Nuclear Plant Project Idaho Falls, Idaho 83415 http://www.inl.gov Prepared for the U.S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 ABSTRACT This report presents a summary of high temperature gas-cooled reactor dust safety issues. It draws upon a literature review and the proceedings of the Very High Temperature Reactor Dust Assessment Meeting held in Rockville, MD in March 2011 to identify and prioritize the phenomena and issues that characterize the effect of carbonaceous dust on high temperature reactor safety.
    [Show full text]
  • Reactor Technology Safety and Siting
    XA0101477-5/I5* IAEA-TC-389.26 LIMITED DISTRIBUTION REACTOR TECHNOLOGY SAFETY AND SITING REPORT OF A TECHNICAL COMMITTEE MEETING ORGANIZED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY AND HELD IN DIMITROVGRAD, USSR, 21-23 JUNE 1989 Reproduced by the IAEA Vienna, Austria, 1990 NOTE The material in this document has been supplied by the authors and has not been edited by the IAEA. The views expressed remain the responsibility of the named authors and do not necessarily reflect those of the govern- ments) of the designating Member State(s). In particular, neither the IAEA nor any other organization or body sponsoring this meeting can be held responsible for any material reproduced in this document. FOREWORD On the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The meetings complemented each other. Due to the large worldwide interest, the conference attracted approximately 60 participants from 18 countries and 130 Soviet delegates. About 50 foreign participants and 100 Soviet delegates stayed over for the Technical Committee Meeting. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGR's to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: - The diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors.
    [Show full text]
  • Deployability of Small Modular Nuclear Reactors for Alberta Applications Report Prepared for Alberta Innovates
    PNNL-25978 Deployability of Small Modular Nuclear Reactors for Alberta Applications Report Prepared for Alberta Innovates November 2016 SM Short B Olateju (AI) SD Unwin S Singh (AI) A Meisen (AI) DISCLAIMER NOTICE This report was prepared under contract with the U.S. Department of Energy (DOE), as an account of work sponsored by Alberta Innovates (“AI”). Neither AI, Pacific Northwest National Laboratory (PNNL), DOE, the U.S. Government, nor any person acting on their behalf makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by AI, PNNL, DOE, or the U.S. Government. The views and opinions of authors expressed herein do not necessarily state or reflect those of AI, PNNL, DOE or the U.S. Government. Deployability of Small Modular Nuclear Reactors for Alberta Applications SM Short B Olateju (AI) SD Unwin S Singh (AI) A Meisen (AI) November 2016 Prepared for Alberta Innovates (AI) Pacific Northwest National Laboratory Richland, Washington 99352 Executive Summary At present, the steam requirements of Alberta’s heavy oil industry and the Province’s electricity requirements are predominantly met by natural gas and coal, respectively. On November 22, 2015 the Government of Alberta announced its Climate Change Leadership Plan to 1) phase out all pollution created by burning coal and transition to more renewable energy and natural gas generation by 2030 and 2) limit greenhouse gas (GHG) emissions from oil sands operations.
    [Show full text]
  • Exelon Generation Introduction to the Pebble Bed Modular Reactor
    Exekn.m Exelon Generation Telephone 610.765.5661 Generati on 200 Exelon Way Fax 610.765.5545 KSA3-N www.exeloncorp.com Kennett Square, PA 19348 Project No.: 713 August 30, 2001 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Subject: "Introduction to the Pebble Bed Modular Reactor" Dear Sir/Madam, a general Transmitted here with is a copy of the subject document, which provides presents an description of the Pebble Bed Modular Reactor (PBMR). This document safety analysis, and overview of the PBMR; the concept, the basic principles of design, operation. It is not intended to be used (or maintained) as a design document. Sincerely, Manager, Licensing PBMR Introduction to the Pebble Bed Modular Reactor (PBMR) Doc. No. 009949-185 PBMR Introduction to the Pebble Bed Modular Reactor (PBMR) Doc. No. 009949-1 85 INTRODUCTION TO THE PEBBLE BED MODULAR REACTOR (PBMR) DOCUMENT No.: 009949-185 Revision: 1 Document Status: Approved 1 Page 1 0179 ©@ Copyright 20012001 by PBMR 22/08/200122108/2001 Revision 1 Page 1 of 79 PBMVR Introduction to the Pebble Bed Modular Reactor (PBMR) Doc. No. 009949-185 CHANGE HISTORY Configuration Control Project: PBMR Title: Introduction to the Pebble Bed Modular Reactor (PBMR) Doc. Reference: 009949-185 Created By: A P George Creation Date: August 2001 Classification: Confidential Document History Revision History Revision Date Changes A August 2001 New document 1 August 2001 Document updated after review I Page 2of79 Q© Copyright 2001 byby PB3MRPBMR 22/08/200122108/2001 Revision I Page 2 of 79 PBMVR Introduction to the Pebble Bed Modular Reactor (PBMVR) Doc.
    [Show full text]
  • Granular Dynamics in Pebble Bed Reactor Cores
    Granular Dynamics in Pebble Bed Reactor Cores by Michael Robert Laufer A dissertation submitted in partial satisfaction of the requirements for the degree of Doctor of Philosophy in Engineering – Nuclear Engineering in the Graduate Division of the University of California, Berkeley Committee in Charge: Professor Per Peterson, Chair Professor Brian Wirth Professor Tarek Zohdi Dr. Robert Budnitz Spring 2013 Granular Dynamics in Pebble Bed Reactor Cores Copyright 2013 by Michael Robert Laufer Abstract Granular Dynamics in Pebble Bed Reactor Cores by Michael Robert Laufer Doctor of Philosophy in Engineering – Nuclear Engineering University of California, Berkeley Professor Per F. Peterson, Chair This study focused on developing a better understanding of granular dynamics in pebble bed reactor cores through experimental work and computer simulations. The work completed includes analysis of pebble motion data from three scaled experiments based on the annular core of the Pebble Bed Fluoride Salt-Cooled High- Temperature Reactor (PB-FHR). The experiments are accompanied by the development of a new discrete element simulation code, GRECO, which is designed to offer a simple user interface and simplified two-dimensional system that can be used for iterative purposes in the preliminary phases of core design. The results of this study are focused on the PB-FHR, but can easily be extended for gas-cooled reactor designs. Experimental results are presented for three Pebble Recirculation Experiments (PREX). PREX 2 and 3.0 are conventional gravity-dominated granular systems based on the annular PB-FHR core design for a 900 MWth commercial prototype plant and a 16 MWth test reactor, respectively. Detailed results are presented for the pebble velocity field, mixing at the radial zone interfaces, and pebble residence times.
    [Show full text]
  • Annual Report 2015 Forschungszentrum Jülich at a Glance Contents
    Annual Report 2015 Forschungszentrum Jülich at a glance Contents U 2 Facts and Figures 0 2 Highlights 0 4 Board of Directors 0 5 Preface 0 6 60 Years of Research R e s e a r c h at the Centre 22 Climate Research Climate goals. Climate Records. Climate Models. 1 4 Chronology 28 Nanoelectronics Insights into the Resistance Generation 32 Energy Research Breaking New Ground in the Hydrogen World 36 Materials Research The Slipperiness Formula 38 Structural Biochemistry New Light Switch for Nerve Cells 40 Electron Tomography Nanoworld in 3D 42 Brain Research Changes in the Brain Caused by Depression 44 Climate Research A Chance Discovery for Climate Research 46 Computer Simulation The Birth of Elements 48 Materials Research New Steel for Energiewende 5 0 Research in Brief 5 2 Publications Cooperation 5 4 The Computer Diplomat 5 8 International Cooperations (EU) 59 National Cooperations 6 0 Collaborations with Industry 6 1 JARA – Combined Expertise 6 4 Cooperations in Brief 6 8 Research for Practical Applications 7 0 Patents and Licenses P e o p l e 7 2 The Tinkerer and the Networker 7 4 Promoting Young Talent 8 2 Personnel 8 4 Accolades 8 6 Professorial Appointments Campus 8 8 Strategy Process of Forschungszentrum Jülich 98 Finances 9 0 Jülich’s Sustainable Campus 1 0 2 Bodies and Committees 9 1 Excellent Platforms 1 0 4 Organization Chart 9 4 Work at Other Locations 1 0 6 Contact Information/ Publication Details U3 Impressions from 60 Years of Research Forschungszentrum Jülich Annual Report 2015 1 Highlights 2015 Forschungszentrum Jülich is focused on use-inspired basic research.
    [Show full text]
  • Heavy Water Reactors: Status and Projected Development Designed in the Russian Federation
    01-01915_TRS407.qxd 17.04.2002 14:04 Uhr Seite 1 Technical Reports Series No. This report commences with a review of the historical development of heavy water reactors (HWRs), detailing the various national efforts made in developing reactor concepts and taking them to the stage of prototype operation or commercial viability. Sections cover HWR economics, safety and fuel cycles. 4 0 7 Technical Reports Series No. 407 The future directions likely to be taken in the development of HWR technology are addressed through discussion of three national programmes: the Canadian CANDU design, the Advanced HWR currently under development in India, and an 'Ultimate Safe' reactor being Reactors: Status and Projected Development Heavy Water designed in the Russian Federation. Heavy Water Reactors: Status and Projected Development ISBN 92–0–111502–4 ISSN 0074–1914 €99.00 INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 2002 HEAVY WATER REACTORS: STATUS AND PROJECTED DEVELOPMENT The following States are Members of the International Atomic Energy Agency: AFGHANISTAN GREECE PARAGUAY ALBANIA GUATEMALA PERU ALGERIA HAITI PHILIPPINES ANGOLA HOLY SEE POLAND ARGENTINA HUNGARY PORTUGAL ARMENIA ICELAND QATAR AUSTRALIA INDIA REPUBLIC OF MOLDOVA AUSTRIA INDONESIA ROMANIA AZERBAIJAN IRAN, ISLAMIC REPUBLIC OF RUSSIAN FEDERATION BANGLADESH IRAQ SAUDI ARABIA BELARUS IRELAND SENEGAL BELGIUM ISRAEL SIERRA LEONE BENIN ITALY SINGAPORE BOLIVIA JAMAICA SLOVAKIA BOSNIA AND HERZEGOVINA JAPAN SLOVENIA BRAZIL JORDAN SOUTH AFRICA BULGARIA KAZAKHSTAN SPAIN BURKINA FASO KENYA SRI LANKA
    [Show full text]
  • Preliminary Failure Modes and Effects Analysis of the US DCLL Test Blanket Module
    INL/EXT-07-13115 Preliminary Failure Modes and Effects Analysis of the US DCLL Test Blanket Module Lee C. Cadwallader August 2007 The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-07-13115 Preliminary Failure Modes and Effects Analysis of the US DCLL Test Blanket Module Lee C. Cadwallader August 2007 Idaho National Laboratory Advanced Nuclear Energy Systems Department Idaho Falls, Idaho 83415 Prepared for the U.S. Department of Energy Office of Fusion Energy Sciences Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 ABSTRACT This report presents the results of a preliminary failure modes and effects analysis (FMEA) of a small tritium-breeding test blanket module design for the International Thermonuclear Experimental Reactor. The FMEA was quantified with “generic” component failure rate data, and the failure events are binned into postulated initiating event families and frequency categories for safety assessment. An appendix to this report contains repair time data to support an occupational radiation exposure assessment for test blanket module maintenance. iii iv CONTENTS ABSTRACT.................................................................................................................................................iii ACRONYMS................................................................................................................................................ 1 1. INTRODUCTION.............................................................................................................................
    [Show full text]
  • The High Temperature Gas-Cooled Reactor
    The High Temperature Gas-cooled Reactor Safety considerations of the (V)HTR-Modul Kugeler, K., Nabielek, H., Buckthorpe, D. Editors: Scheuermann, W., Haneklaus, N., Fütterer, M. 2017 EUR 28712 EN KJ - NA - 28712 - EN - C This publication is a Book with editorship by the Joint Research Centre (JRC), the European Commission’s science and knowledge service. It aims to provide evidence-based scientific support to the European policymaking process. The scientific output expressed does not imply a policy position of the European Commission. Neither the European Commission nor any person acting on behalf of the Commission is responsible for the use that might be made of this publication. Contact information Name: Fütterer, M. Address: European Commission, DG Joint Research Centre – JRC, Directorate G, Unit G.I.4 – Nuclear Reactor Safety & Emergency Preparedness; P.O. Box 2, NL-1755 ZG Petten, Netherlands Email: [email protected] Tel.: +31 22456-5158 JRC Science Hub https://ec.europa.eu/jrc JRC107642 EUR 28712 EN PDF ISBN 978-92-79-71311-8 ISSN 1831-9424 doi:10.2760/270321 Print ISBN 978-92-79-71312-5 ISSN 1018-5593 doi:10.2760/970340 Luxembourg: Publications Office of the European Union, 2017 © European Atomic Energy Community, 2017 Reuse is authorised provided the source is acknowledged. The reuse policy of European Commission documents is regulated by Decision 2011/833/EU (OJ L 330, 14.12.2011, p. 39). For any use or reproduction of photos or other material that is not under the EU copyright, permission must be sought directly from the copyright holders.
    [Show full text]
  • General Conference ENGLISH Original: ENGLISH, FRENCH
    International Atomic Energy Agency GC(XI)/INF/97/Add.1 28 September 1967 GENERAL Distr. General Conference ENGLISH Original: ENGLISH, FRENCH ELEVENTH REGULAR SESSION PROGRESS IN PEACEFUL APPLICATIONS OF NUCLEAR ENERGY DURING THE YEAR 1966-67 Further Statements by Member States PROGRESS IN PEACEFUL APPLICATIONS OF JWUCLEAR ENERGY DURING THE YEAR 1966/67 1 CANADA The past year has been one of progress Another development in the past year was and expansion for the Canadian nuclear power the conclusion of an agreement between the programme. Probably the most significant develop­ Governments of India and Canada to build a ment was the decision by Canada's largest electric second 200-MW(e) CANDU unit at the Rajasthan utility company, the Hydro Electric Power Atomic Power Project in north-west India. The Commission of Ontario, to add two 540-megawatt first Rajasthan unit is under construction and is units to its Pickering nuclear power station, now expected to begin operation in 1970. In Pakistan being built near the City of Toronto. This will the Canadian General Electric Company Limited double the station's capacity to more than are building a 137-.\lW(e) heavy-water-moderated, 2000 MW(e) and make it the second largest natural-uranium-fuelled nuclear power plant. nuclear power plant under construction in North Completion is scheduled for 1970. America. Ontario Hydro's decision, involving an estimated outlay of $256 million, offers further confirmation of the confidence placed in the Thus there now are in operation or under nuclear power system developed by the Crown construction in Canada and abroad six nuclear company, Atomic Energy of Canada Limited.
    [Show full text]