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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. Foreign participants in the workshop had the opportunity to present the status of the HTR-related structural design code work being carried out in their own countries. Ill Table of contents Objective of the workshop Objective of the Workshop on Structural Design Criteria for HTR; Survey of the Research Activities in the Federal Republic of Germany H. Nickel KFA-Jülich, Institut für Reaktorwerkstoffe Section I: HTR Projects and status of licensing principles Chairman; H. Schuster, KFA-Jüüch Present Status of MHTGR program in USA 15 P.L Rittenhouse Oak Ridge National Laboratory, Oak Ridge Present status of HTTR project in Japan 33 T. Tanaka, S. Saito Japan Atomic Energy Research Institute HTR situation in China 48 D. Wang, S. Xu Institute of Nuclear Energy, Tsinghua University, Peking Present status of HTR in FRG 59 H. Nickel KFA Jülich, Institut für Reaktorwerkstoffe Section II: Technical safety boundary conditions Chairman: R. Trumpfheller, Essen HTR Safety Features and the Integrity Concept • ,. * 83 J. Wolters - - KFA Jülich, Institut für Nukleare Sicherheitsforschung . .-~ • IV Classification of systems and components into safety classes and quality standard classes 97 M. Dette Rheinisch-Westfälischer Technischer Überwachungs-Verein e. V., Essen Section III: Metallic high temperature components Section 111.1 Chairman: H. Clausmeyer, MAN-GHH, Oberhausen Metallurgical and physical fundamentals for the design of high temperature components 113 F. Schubert KFA Jülich, Institut für Reaktorwerkstoffe Load levels, stresses, failure modes and design criteria 133 K. Bieniussa Gesellschaft für Reaktorsicherheit (GRS) mbH, Köln Basic requirements relating to quality assurance of safety related HTR materials and components 159 J. Just Rheinisch Westfälischer Technischer Überwachungs-Verein e. V.,Essen Non-destructive detection of flaws during manufacture and operation of components 171 F.Walte Fraunhofer-Institut für zerstörungsfreie Prüfverfahren, Saarbrücken Section III.2 Chairman: W. Dahl, RWTH-Aachen Material Data and Constitutive Equations 185 HJ. Penkalla KFA Jülich, Institut für Reaktorwerkstoffe Methods for very high temperature design 206 J. J. Blass, J. M. Corum and S. J. Chang Oak Ridge National Laboratory, Oak Ridge Life fraction rules 228 K. Maile Staatliche Materialprüfungsanstalt, Stuttgart The present status of research and development works for the preparation of the high temperature design code 243 Y.-Muto Japan Atomic Energy Research Institute (JAERI), Japan Creep rupture characteristics in the HTGR simulated helium gas environment and their relevance to structural design 275 Y. Kurata, Y. Ogawa, H. Nakajima, T. Kondo Japan Atomic Research Institute (JAERI), Japan • Section III.3 Chairman: H. P. Alder, PSI-WCirenlingen Assessment of primary and secondary stresses for component design , 293 E. Bodmann Hochtemperatur-Reaktorbau GmbH, Mannheim Elastic and inelastic analysis for component behaviour . 309 H.-J. Seehafer Interatom GmbH, Bensberg Significance of Fracture Mechanics 32g K. .Schneider - i ASEA Brown Boveri AG, Mannheim Section IV: Reactor pressure vessels Chairman: J. Altes, KFA-Jülich Design criteria for prestressed concrete pressure vessels 34g K. Schimmelpfennig. Stangenberg, Schnellenbach & Partner, Bochum Design criteria for liners of concrete vessels 370 R. Oberpichler ... ' •• ' Stangenberg, Schnellenbach & Partner, Bochum VI Special features of the design of pressure vessel closures and heat inulations 385 J. Pschowski Hochtemperatur-Reaktorbau GmbH, Mannheim The HTR-module pressure vessel unit; design criteria and safety philosophy 404 G. Neumann, Siemens AG, Unternehmensbereich KWU, Erlangen K. Dumm, Interatom GmbH, Bensberg Design principles for MHTGR pressure vessels 442 C. Hoffmann Combustion Engineering, Windsor, Connecticut Section V: Structural graphite components Chairman: G. Wintermann, RWTÜV-Essen Materials behaviour and design values 467 G. Haag KFA JCilich, Institut für Reaktorwerkstoffe Design Methods and Criteria for Graphite Components 480 A. Schmidt Hochtemperatur-Reaktorbau GmbH, Mannheim Analysis of the graphite side reflector block of the HTR-Module 493 P. Rathjen Interatom GmbH, Bensberg Design criteria for graphite components of HTTR 506 T. lyoku, S. Shiozawa Japan Atomic Energy Research Institute (JAERI), Japan Section VI: General Summary Chairman: R. Schulten, KFA-Jülich Statements on current HTR structure design criteria 527 R. Trumpfheller vii Comments concerning the "Workshop on Structural Design Criteria for HTR" 535 W. von Lensa Summary of the final discussion 539 Appendix 541 Members of working groups and task forces of the German Design Criteria project Objective of the workshop Objective of the Workshop on Structural Design Criteria for HTR Survey of the Research Activities in the Federal Republic of Germany H. Nickel Kernforschungsanlage Jülich GmbH, Institut für Reaktorwerkstoffe, Fed. Rep. of Germany Abstract Technical guidelines and design codes for nuclear plants in the Federal Republic of Germany are tailored to the light water reactor (LWR) systems, so that a design code for the helium-cooled high temperature reactor (HTR) has to be formulated. In an extensive research project, the underlying principles for such a design code have been worked out. The aim of the workshop is to present the current status of the work. 1. Introduction The purpose of this meeting is the presentation of the results of a nine-year effort to set out the fundamental principles and basic data for a nuclear design code covering high temperature reactor components. At the beginning, work was concentrated on metallic heat exchanger components, but, on completion of the preliminary work about five years ago, it was decided to increase the scope to include all structural components of an HTR plant. This was not least from the plant con- structors desired, who wished to move away from the often time-con- suming methods applied for the THTR licensing and control procedures. Instead they wanted to build on the good results of and positive experience with the methods of the specialists' working party 'HTR design criteria'.. The advantage of cooperation between materials scientists, plant constructors, stress analysts and safety engineers of the different organisations should be further utilized and transferred to the basic work for the establishment of guidelines and design rules for the HTR. There are two aspects which are of particular significance in the drafting of guidelines and rules: - adherence to the established status of science and technology; - formulation of generally accepted rules and regulations in such a form that their development for technical systems remains transparent and comprehensible for all concerned. With regard to a complicated technology such as nuclear reactors, which involves the participation of different institutions and organizations, it. is the second aspect that plays a crucial role. Clearly defined procedures and regulations simplify and ease the carrying out of appropriate steps in which many participants are involved. In the end, the regulations ensure that everyone speaks the 'same language1. Appropriate guidelines and procedures have been laid down for the light water reactors, an established and commercially marketed system. For the advanced reactor types that have not yet been commercially established such guidelines are not available. The HTR suffers a deficit in this respect. 2. Legal basis for the use of nuclear reactors in the FRG In this section, the standard framework within which the use of nuclear technology, including of course the HTR, is controlled in the Federal Republic of Germany will be described. 2.1 Highest level of control hierarchy The planning, construction, commissioning
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