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Design and Development of Gas Cooled Reactors with Closed Cycle Turbinesgas IAEA-TECDOC-899 Design and development of gas cooled reactors with closed cycle turbinesgas Proceedings of a Technical Committee meeting held in Bei/ing, China, 30 October - 2 November 1995 INTERNATIONAL ATOMIC ENERGY AGENCA / Y The IAEA does not normally maintain stocks of reports in this series. However, microfiche copies of these reports can be obtained from IN IS Clearinghouse International Atomic Energy Agency Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna, Austria Orders shoul accompaniee db prepaymeny db f Austriao t n Schillings 100,- in the form of a cheque or in the form of IAEA microfiche service coupons which may be ordered separately from the IN IS Clearinghouse. originatine Th g Sectio f thino s publicatio IAEe th An i was- Nuclear Power Technology Development Section International Atomic Energy Agency Wagramerstrasse 5 0 10 x P.OBo . A-1400 Vienna, Austria DESIG DEVELOPMEND NAN COOLES GA F TDO REACTORS WITH CLOSED CYCL TURBINES EGA S IAEA, VIENNA, 1996 IAEA-TECDOC-899 ISSN 1011-4289 IAEA© , 1996 Printed by the IAEA in Austria August 1996 FOREWORD lons Iha tg been recognized that substantial generatioe gainth n si f electricitno y from nuclear e obtainefissiob n ca nd throug e directh h t s turbincouplin ga a hig a o t ehf o g temperature helium cooled reactor. This advanced nuclear power plant is unique in its use of the Brayton cycle to achieve a net electrical efficiency approaching 50% combined with the attendant features of low initial capital costs due to plant simplification, public acceptance from the safety attributes of the high temperature gas cooled reactor (HTGR), and reduced radioactive wastes. e TechnicaTh l Committee Meeting (TCM d Worksho an )e Desig th d n o an pn Developmen Cooles Ga f o dt Reactors with Closed Cycl Turbines eGa convenes swa d within the frame of the International Working Group on Gas Cooled Reactors as part of the IAEA nuclear power technology development programme. Technological advances over the past fifteen years in the design of turbomachinery, recuperator d magnetian s c bearings provid e potentiath e quantua r fo l m improvemenn i t nuclear power generation economic HTGe th f so R throug e witus closeha e hth d cycls ega turbine. Enhanced international co-operation among nationa cooles ga l d reactor programmes in these common technology areas could facilitate the development of this nuclear power concept thereby achieving safety, environmental and economic benefits with overall reduced development costs Workshod an . ThiM convenes psTC wa provido dt opportunite eth o yt review and examine the status of design activities and technology development in national HTGR programmes with specific emphasi closee th n dso cycl turbines identifo et ga d an ,y pathways which take advantage of the opportunity for international co-operation in the developmen f thio t s concept. EDITORIAL NOTE preparingIn this publication press,for IAEAthe staffof have pages madethe up fromthe original manuscripts submittedas authors.the viewsby The expressed necessarilynot do reflect those governmentsofthe nominating ofthe Member nominating the States of or organizations. Throughout textthe names Memberof States retainedare theyas were when textthe was compiled. Theof use particular designations countriesof territoriesor does imply judgementnot any 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 pan of the IAEA. The authors responsibleare havingfor obtained necessarythe permission IAEAthe to for reproduce, translate or use material from sources already protected by copyrights. CONTENTS 7 SUMMARY SUMMARY OF NATIONAL AND INTERNATIONAL ACTIVITIES IN GAS COOLED REACTORS (Session 1) Construction of the HTTR and its testing program for advanced 5 1 HTGR development T. Tanaka, O. Baba, S. Shiozawa, M. Okubo, K. Kumtomi Progress of the HTR-10 project 25 D. Zhong, Y. Xu State of HTGR development in Russia 31 V.F Golovko, Kiryushtn,I. A N.G. Kodochigov, N.G. Kuzavkov High temperature reactor development in the Netherlands 47 Heekvan .1. A French activities on gas cooled reactors 51 D. Bastten Status of GT-MHR with emphasis on the power conversion system 55 A.J. Neylan, F.A. Silady, B.P. Kohler, Lomba,D. RoseR. HTR plus modern turbine technology for higher efficiencies 67 H. Bamert, K. Kugeler DESIG HTGRF NO s WITH CLOSED CYCL TURBINES EGA S (Sessio) n2 Design of indirect gas turbine cycle for a modular high temperature 5 8 s coolega d reactor Z. Zhang, Z. Jiang Conceptua5 9 l desig heliuf no turbins mga r MHTGR-Gefo T Matsuo,E. Tsutsumi,M. Ogata,K. NomuraS. Investigation of GT-ST combined cycle in HTR-10 reactor 111 Z. Gao, Z. Zhang, D. Wang HTG turbine-moduls Rga 1 12 e demonstration tesproposaa - t l E Takada, Ohashi,K. Hayakawa,H. Kawata,O. KobayashiO. LICENSING, FUEL AND FISSION PRODUCT BEHAVIOUR (Session 3) A study of silver behavior in gas-turbine high temperature gas-cooled reactor 131 K. Sawa, S. Shiozawa, K. Kumtomi, T. Tanaka COMEDIE BD1 experiment Fission product behaviour during depressunzation transients 145 R. Gillet, D. Brenet, D.L. Hanson, O.F. Kimball 7 15 Licensing experienc HTR-1e th f eo 0 test reactor Y. Sun, Y. Xu GAS-TURBINE POWER CONVERSION SYSTEM DEVELOPMENT (Session 4) Development of compact heat exchanger with diffusion welding 165 K Kumtomi, T. Takeda, T. Hone, K. Iwata Summary repor technican o t l experiences from high-temperature helium 7 17 turbomachinery testin Germann gi y WeisbrodtLA WORKSHOP (Sessio) n5 Pebble bed modular reactor - South Africa 251 M. Fox, E. Mulder IAEe Rolth f gas-cooleAn ei o d reacto7 r developmen25 applicatiod an t n J. Cleveland, L. Brey, J. Kupitz List of Participants 271 SUMMARY The Technical Committee Meeting (TCM) and Workshop on Design and Development s CooleoGa f d Reactors with Closed Cycl s TurbineGa e s hel Beijingn wa i sd , People's Republic of China, from 30 October to 2 November 1995. The meeting was convened by the recommendatioe IAEth n Ao Internationas it f no l Working Cooles GrouGa n dpo Reactors (IWGGCR Instituthostes e th wa y dd b Nucleaf e)o an r Energy Technology (INET), Tsinghua University. The meeting was organized to review the status and technology development activities for high temperature gas cooled reactors with closed cycle gas turbines (HTGR-GT), an identifo dt y pathway opportunitf so r internationayfo l co-operatio developmene th n i f o t common systems and components. It was attended by twenty-three participants and observers from eight countries (China, France, Germany, Japan, the Netherlands, the Russian Federation, South Africa and the United States of America). Sixteen papers were presented by the participants on behalf of their respective countries. Professor Z. Wu, Director of INET, chaired the meeting. Each presentation was followed by general discussion within the area covere papere th y db . INEToure th f To s research facilitieHige th hd Temperaturan s e Reactor (HTR-10) construction site followed the meeting and workshop. Recent advance turbomachineryn si , magnetic bearing head san t exchanger technology provid potentiae eth r significanfo l t improvemen nuclean i t r power generation economics through use of the HTGR with closed cycle gas turbines. This TCM was used as a forum to share the recent advances in this technology and to explore those technical areas where international co-operation woul e beneficiadb e HTGR-GTth o t l . Area f investigatioo s n included materials development, component fabrication, qualification of the coated fuel particles and fission product behaviour hi the power conversion system, national HTGR development and testing programmes including gas turbine related systems and components. Summarie f nationaso internationad an l cooles ga l d reactor development programmes included presentations from representatives of Japan, China, the Russian Federation, the Netherlands, France, the United States of America and Germany. The Japanese High Temperature Engineering Test Reactor (HTTR) is currently under construction at the Japan Atomic Energy Research Institute (JAERI), Oarai Research Establishment site. This is a 30 MWth reactor with a maximum outlet temperature of 950°C. Construction of the HTTR began in March, 1991, with initial reactor criticality scheduled for lat reactoe e 1997Th . r buildin containmend gan t vessel, includin maie gth n components such as the reactor vessel, intermediate heat exchanger, hot gas piping and the reactor support structure are now installed. The HTTR project is intended to establish and upgrade the technology basis necessar advancer yfo d HTGR development heae Th .t utilization systems planned for demonstration with this reactor are currently under consideration as part of the IAEA Co-ordinated Research Programm Desige th Evaluatiod n eo nan f Heano t Utilization Systems for the HTTR. The gas turbine and CO2 and steam reforming of methane are considered as first priority heat utilization system candidates. Safety demonstration tests on the HTTR are also planned to confirm the inherent safety features of the HTGR. Construction continue HTR-1e th INE e n th so t T0a site outsid f Beijingeo , China. This pebble-bed helium cooled test reacto beins i r g supporte governmene th y db f Chinao t e Th . construction permit for this plant was issued by the national safety authority at the end of 1994 and construction bega Junen i , 1995. First criticalit schedules yi r 1999dfo . maie Mosth nf o t components, including the spherical fuel elements, are to be manufactured in China.
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