R. HÜPER Fast Breeder Project, Kernforschungszentrum Karlsruhe

Total Page:16

File Type:pdf, Size:1020Kb

R. HÜPER Fast Breeder Project, Kernforschungszentrum Karlsruhe STATUS OF FAST BREEDER REACTOR DEVELOPMENT 500 °C. After several years of operation with a thermal reactor core (KNK I), IN THE FEDERAL REPUBLIC OF GERMANY, the plant has been run with fast, i.e. unmoderated, reactor cores since 1978 (KNK II). BELGIUM AND THE NETHERLANDS February 1987* While the fuel assemblies of the first fast core, KNK II/l, were identical with those of the Mk.Ia first core of the SNR 300 in their key parameters, the fuel assemblies of the second core loading, KNK 11/2 , correspond to the SNR 300 Mk.II R. HÜPER type, which is characterized by a high fuel density, 7.6 mm fuel rod diameter, Fast Breeder Project, and spark eroded spacer grids which, in the fuel assemblies of the test zone, Kernforschungszentrum Karlsruhe GmbH, are attached to the wrapper tube by means of flow aprons. Karlsruhe, Federal Republic of Germany The first fast core had been unloaded in 1982 after a peak burnup of 100.000 MWd/te. The fuel assemblies of the second core, which was commissioned iri mid-1983, have meanwhile reached an average burnup of 47.000 MWd/te. One test Abstract fuel assembly transferred from the first to the second core has reached an average burnup of 125.000 MWd/te by late 1986. In 1967 and 1968, the Federal Republic of Germany, the Kingdom of Belgium, and the Kingdom of the Netherlands ("DeBeNe") agreed in a joint program to develop In the course of the burnup of the second core so far, a change in the outlet breeder reactors. The following research organizations have taken part in this effort: temperatures of the Mk.II fuel assemblies has been observed. Probably as a result of some redistribution of the coolant flow from the test zone to the driver zone due to increased pressure loss in all fuel assemblies, the outlet Kernforschungszentrum Karlsruhe (KfK), INTERATOM, Bergisch Gladbach, temperatures of the test zone fuel assemblies rise, while those of the driver ALKEM, Hanau, assemblies drop. An extensive program of research is being conducted to eluci­ date the causes of these temperature changes. SCK/CEN, Mol, Belgonucléaire, Brussels, Four fuel assembly failures have so far occurred in operation of the KNK 11/2 core. Two test assemblies and two driver assemblies were involved. Operation of ECN, Petten, three of the assemblies was continued up to 35 days at full load and part load, TNO, Apeldoorn, respectively, after the failure had been noticed. Spotting the failed fuel NERATOOM, The Hague. assemblies in KNK II is done by a combination of load tilting operation and a dry sipping test conducted by the fueling machine. The failed fuel assemblies are subjected to extensive post-irradiation examinations at the Hot Cells of The three institutions mentioned above have been associated since 1977 in the KfK. Entwicklungsgemeinschaft Schneller Brüter. KfK, INTERATOM, and the French Commissariat à l'Energie Atomique entered into contracts in 1977 about close cooperation in the fast breeder field, to which the Belgian and Dutch partners Irradiation and post-irradiation examinations of specimens of the 1.6770 type material of the KNK II reactor vessel, which had been loaded in the first acceded. materials test assembly, have been concluded. The integrity of the vessel wall has been found to be unimpaired by irradiation effects, even in the long term. The results of activities carried out by the DeBeNe partners in 1986 have been compiled in this report. The report begins with a survey of the fast reactor plants, followed by an R&D summary. In an additional chapter, a survey is given Post-irradiation examination of a KNK 11/2 absorber assembly has also been of international cooperation in 1986. completed. The absorber rods of the first core were filled with boron carbide granulate. Only some test rods contained B.C pellets of the kind used for KNK II follow-on loadings and for the SNR 300. I. SUMMARY An investigation is being carried out of the KNK II steam generator in order to see whether the noise of the water-sodium interaction, which would arise in a steam generator failure, can be detected. For this purpose, a leak simulation 1. Operating Experience of KNK II in Karlsruhe source and ten acoustic sensors have been installed. KNK, a compact sodium-cooled reactor, is an experimental nuclear power station of 20 megawatts electric power, whose core is cooled by liquid sodium at approx. 2. Commissioning of the Kalkar Nuclear Power Station (SNR 300) In 1973, construction near Kalkar was begun of the 300 MWe SNR 300 prototype * Translated by R. Friese. breeder power plant by Internationale Natrium-Brutreaktor Bau GmbH (INB). The plant owner is Schnellbrüter-Kernkraftwerksgesellschaft mbH (SBK). Both firms 3. Planning of the SNR 2 are joint German-Belgian-Netherlands enterprises; in addition, the state-owned British CEGB holds an interest in SBK. The company awarding the contracts for planning and construction of the SNR 2 (1.500 MWe pool type facility) will be the Europaische Schnellbrüter-Kernkraft- Construction of the plant was largely completed in 1985 after lengthy delays, werksgesellschaft (ESK). Its shareholders are SBK, the Italian ENEL, and the most of them caused by political conditions. After the sodium systems had been French EdF. The project is based on the Breeder Convention agreed upon in 1973, filled, functional tests were carried out within the framework of pre-nuclear under which construction of the SPX 1 in France, now commissioned, was to come commissioning. A number of problems were overcome in this phase in 1986: first. Because of a number of leaks observed, the welds of the four dump tanks and Planning work for the SNR 2 is to provide an assured development status re­ leakage interception vessels on the secondary side were redone. As a consequence presenting an attractive basis on which to decide about the next European of similar technological, design and welding conditions as in the sodium dump breeder. Points of primary interest are engineered safeguards (passive safety and leakage interception vessels, also the partly loaded cold traps were re­ concept) and economic considerations. paired and regenerated. On the basis of the well-known inherent properties of breeder facilities, the To reject the higher-than-rated heat load, new blowers were installed in the safety potential is to be exploited further, e.g., by passive natural cir­ reactor closure head cavity. Additional tanks designed to collect leakage oil culation systems for decay heat removal. Studies of the component design va­ were installed near the primary pumps. riants of decay heat removal systems performed so far, and also the arrangements of these components, are at present being evaluated in detail by the French and Labor-intensive rerouting of cables took until mid-February 1986; it had become Italian partners. Also the British side contributes to this effort. necessary in order to meet the tighter redundancy requirements in the decay heat removal trains. Passive day heat removal is one of the key features of an accident management concept designed to minimize active measures. The studies devoted to this In January 1986, a vibration measurement lance introduced into the reactor complex of problems are intended to result in a new kind of emergency power vessel was ruptured in an attempt to dismantle it for reworking. The disrupted supply concept and a consistent control panel concept. part of the lance and several small parts which had stuck in the reactor vessel were retrieved. In March 1986, the primary system and the reactor vessel were The concept for handling core assemblies has been advanced far enough to allow again filled with sodium. consistent handling under sodium of irradiated core assemblies and, hence, solutions for passive decay heat removal to be defined. Conceptual proposals An abnormally high moisture content was measured in the cover gas of the re­ have been made for the layouts of the secondary systems and the handling de­ actor. It came from the basalt granulate used to shield the reactor closure vices. head. The basalt was dehumidified at a sodium temperature of about 240 °C. Breeder plants achieve clearly higher burnups than light water reactors. One of The tests of the emergency power supply system were completed. The systems the targets in planning for the SNR 2 ist a considerably higher burnup also designed for decay heat removal (decay heat removal specifically for each leg relative to the SNR 300. Besides this point, which is important especially with through the heat sink in the water/steam system and the emergency core cooling regard to fuel cycle costs, lower construction costs are expected to arise from system) were tested successfully. the passive safety concept. Since the end of 1986, the Kalkar facility has been ready for acceptance of the The SNR 2 allows cost reductions to be achieved especially for the following fuel assemblies. reasons : In July 1986, the North-Rhine-Westphalian State Minister of Economics, who is No safety related decay heat removal through the "balance-of-plant" sy­ responsible for issuing reactor permits, surprised everyone with the announce­ stems; consequently, conventional components and process engineering ment of reservations against further permits, because of his new assessment of simplifications are possible. facts well-known for quite a time. The German Advisory Committees on Reactor Safeguards (RSK) and Radiological Protection (SSK) as well as the Rhineland Absence of extensive emergency power supply installations because the Technical Inspectorate (TQV) had not raised any objections on grounds of tech­ sodium systems can be used for passive decay heat removal. nical safety against loading the fuel assemblies and conducting zero power tests in the SNR 300.
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]
  • 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]
  • Core Physics of Pebble Bed High Temperature Nuclear Reactors
    Core Physics of High Temperature Pebble Bed Nuclear Reactors Pebble of High Temperature Physics Core Uitnodiging Voor het bijwonen van de openbare Core Physics of Pebble Bed verdediging van het proefschrift High Temperature Core Physics of Nuclear Reactors Pebble Bed High Temperature Nuclear Reactors Gert Jan Auwerda door Gert Jan Auwerda 22 december 12:30 Aula, TU Delft, Mekelweg 5 Gert Jan Auwerda Voorafgaand, om 12:00, is een presentatie over het onderzoek Faculty of Applied Sciences Department of Radiation Science & Technology Faculty: Applied Sciences Department: RS&T ISBN 978-94-6295-047-4 Group: NERA Propositions accompanying the dissertation CORE PHYSICSOF PEBBLE BED HIGH TEMPERATURE NUCLEAR REACTORS by Gert Jan AUWERDA 1. Non-isotropic models are required to accurately simulate heat and mass transfer next to the wall in a pebble bed reactor. (This thesis.) 2. In a pebble bed reactor, the higher porosity near the boundaries than in the centre of the randomly stacked pebble bed can be ignored when calculating the neutron flux distribution, but cannot be ignored when calculating the ke f f or the power distribution. (This thesis.) 3. In annular pebble bed designs, the wall-channelling effect results in a significantly lower maximum fuel temperature during both normal operation and during a pres- surized loss of forced cooling accident. (This thesis.) 4. A grid convergence study based on Richardson extrapolation to evaluate the grid convergence index (GCI) should be mandatory to evaluate the mesh quality when solving equations using numerical analysis. (P.J.Roache. Verification and validation in com- putational science and engineering, Hermosa Publishers, USA, 1998.) 5.
    [Show full text]
  • Nuclear Energy of the Future: What Research for Which Objectives?
    MonoCEA GB 5/04/06 15:30 Page 3 Commissariat à l’énergie atomique e-den A monograph of the Nuclear Energy Directorate Nuclear energy of the future: what research for which objectives? Éditions techniques MonoCEA GB 5/04/06 15:30 Page 2 DEN monographs A monograph of the Nuclear Energy Directorate Commissariat à l’énergie atomique, 31-33, rue de la Fédération 75752 Paris Cedex 15 Tél. : +33-1 40 56 10 00 Scientific comitee Michel Alexandre, Michel Beauvy, Georges Berthoud, Mireille Defranceschi, Gérard Ducros, Yannick Guérin, Yves Limoge, Charles Madic, Gérard Santarini, Jean-Marie Seiler, Pierre Sollogoub, Étienne Vernaz, Research Directors. The following people participated in this work: Fanny Bazile, Patrice Bernard, Bernard Bonin, Jacques Bouchard, Jean-Claude Bouchter, Bernard Boullis, Franck Carré, Jean Cazalet, Alain Marvy, Valérie Moulin, Emmanuel Touron, Yves Terrien. Publishing Supervisor: Philippe Pradel. Editorial Board: Bernard Bonin (Managing Editor), Bernard Bouquin, Martine Dozol, Michel Jorda, Jean-Pierre Moncouyoux, Alain Vallée. Administrator: Fanny Bazile. Editor: Jean-François Parisot. Graphic concept: Pierre Finot. Cover illustration: Véronique Frouard. Correspondence: all correspondence can be addressed to the Editor or to CEA / DEN Direction scientifique, CEA Saclay 91191 Gif-sur-Yvette Cedex. Tél. : + 33-1 69 08 16 75. © CEA Saclay and Groupe Moniteur (Éditions du Moniteur), Paris, 2006 The information contained in this document can be freely reproduced, with the agreement of the Editorial Board and due mention of its origin. MonoCEA GB 5/04/06 15:30 Page 5 Preface After a dazzling start in the 1950s as a promising, inexhaustible, cost-effective energy source, nuclear energy was rejected by majority opinion in several countries in North America and Western Europe three to four decades later, suddenly bringing its development to a halt.
    [Show full text]