Specialists' Meeting on Heat Exchanging Components of Gas-Cooled Reactors
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International Atomic Energy Agency IWGGCR-9 International Working Group on Gas-Cooled Reactors Specialists' Meeting on Heat Exchanging Components of Gas-Cooled Reactors Dusseldorf Federal Republic of Germany 16-19 April 1984 hosted by Bundesministerium fur Forschung und Technologie 31/42 Please be aware that all of the Missing Pages in this document were originally blank pages Introduction The Specialists' Meeting on "Heat Exchanging Components of Gas- cooled Reactors" was held at the Ministry of Economic and Trans- port of the State North Rhine Westphalia, Diisseldorf, FRG 16-19 April 1984. The meeting was sponsored by the IAEA on the recommendation of the International Working Group on Gas-Cooled Reactors and was hosted by the Federal Ministry of Research and Technology of the Federal Rebublic of Germany. The meeting was attended by 62 participants from Austria, France, Federal Republic of Germany, Japan, Poland, Sweden, Switzerland, United Kingdom of Great Britain and Northern Ireland and the United States of America. The objective of the meeting was to provide a forum, both formal and informal, for the exchange and discussion of technical infor- mation relating to heat exchanging and heat conducting components for gas-cooled reactors. The technical part of the meeting was divided into eight subject sessions: I. Heat exchanging components for process heat application - design requirements and r/d programmes II. Status of the design and construction of intermediate He/He heat exchangers III. Design, construction and performance of steam generators - 2 - 3 V. Metallic materials and design codes VI. Design and construction of valves and hot gas ducts VII. Description of component test facilities and test results VIII. Manufacturing of heat exchanging components A total of 38 papers were presented by the participants on behalf of their organizations during the meeting, and an opportunity for open discussion of the paper topic followed each presentation. Session I Heat exchanging components for process heat application - design requirements and R & D programmes No 1 Status of the R&D program in the field of the heat carrying and heat transfer components of the PNP- project H. Mausbeck, W. Jansing; Interatom GbmH; FRG No 2 Design requirements on HTR main components for process heat application K. Dumm; Interatom GmbH; FRG No 3 Helium/helium heat exchangers and hot-gas ducts for the PNP-project according to the BBC/HRB-concept H. Schmitt, B. Jiirgens, J. Knaul; Hochtemperatur-Reak- torbau GmbH; FRG Session II Status of the design and construction of intermediate He/He heat exchangers No 4 Recent research and development of intermediate heat exchanger for VHTR plant A. Shimizu, N. Matsumura, H. Nishikawa, S. Yamada; Industries, LTD; Japan No 5 Development of a helium/helium intermediate heat ex- changer (He/He-IHX) with helical coil tube bundle A. Czimczik; L. & C. Steinmuller GmbH; FRG G. Hirschle; Gebr. Sulzer AG; Switzerland No 6 Improved spacers for high temperature gas-cooled heat exchangers L. A. Nordstrom; Swiss Federal Institute for Reactor Research; Switzerland - 1 - r No 7 Life time test of a partial model of HTGR helium-helium heat exchanger M. Kitagawa, H. Hattori, A. Ohtomo, T. Teramae, J. Hamanaka, M. Itoh, S. Urabe; Ishikawajima-Harima Heavy Industrie Co., LtD.; Japan No 8 Development, construction and analysis of the URKO intermediate heat exchanger, R. Exner, M. Podhorskiy; Balcke-Durr AG; FRG No 9 Development of a new type of high-temperature-insula- tion-material and its application in the PNP-project R. Burger, R. Ganz; Didier-Werke AG, FRG No 10 Seismic analysis of a helical coil type heat exchanger I. Nishiguchi, 0. Baba, H. Yatabe; Japan Atomic Energy Research Institute; Babcock Hitachi K. K.; Japan Session III Design, construction and performance of steam generator No 11 Design and development of steam generators for the AGR power stations at Heysham II/Torness A. N. Charcharos, A. G. Jones; National Nuclear Corpo- rat ion Ltd.; UK No 12 Monitoring and performance analysis of AGR boilers during commissioning and power raising M. El-Nagdy, R. M. Harrison; Nuclear Engineering Department; Babcock Power Ltd.; UK No 13 Experience with the commissioning of helically coiled advanced gas-cooled reactor boilers D. B. Kettle; CEGB-Generation Development and Construc- tion Division; UK - 2 - No 14 Investigations of the gas-side heat transfer and flow characteristics of the AGR steam generators J. Lis; Central Electricity Research Laboratories; UK No 15 Effect on inlet and outlet shell side flow and heat transfer on the performance of HTGR straight tube heat exchangers D.P. Carosella; GA Technologies; USA Session IV Design, development and fabrication of steam reformers No 16 Status of an in-line reformer design for modular HTGR R. Gluck, W. H. Whitling, A. J. Lipps; General Electric Company; USA No 17 Development and fabrication of a helium heated steam reformer W. Panknin, W. Nowak; L. & C. Steinmuller GmbH; FRG No 18 Assembly and operation experience of the EVA II - steam reforming bundle H. F. NieBen, R. Harth; Kernforschungsanlage Julich GmbH; W. Kessel; Rheinische Braunkohlenwerke AG; FRG Session V Metallic materials and design codes No 19 Evaluation of materials for heat exchanging components in advanced helium-cooled reactors F. Schubert; Kernforschungsanlage Julich GmbH; FRG No 20a Pressure vessel design codes: A review of their applica- bility to HTGR components at temperatures above 800°C P. T. Hughes; General Electric Company; USA K. Bieniussa; Gesellschaft fur Reaktorsicherheit GmbH, H. H. Over; Kernforschungsanlage Julich GmbH; FRG - 3 - No 20b Status of design code work for metallic high temperature components K. Bieniussa; Gesellschaft fur Reaktorsicherheit; FRG H. J. Seehafer; Interatom? FRG H. H. Over; Kernforschungsanlage Jiilich GmbH; FRG P. Hughes; General Electric Company; USA No 21 Oxide films on austenitic HTR heat exchanger materials as a tritium barrier H. P. Buchkremer, R. Hecker, H. Jonas, H. J. Leyers, D. Stover; Kernf orschungsanlage Jiilich GmbH; FRG No 22 Effect of creep-fatigue damage relationships upon HTGR heat exchanging design D. P. Carosella, M. M. Kozina, J. H. King, M. Basol; GA Technologies; Combustion Engineering Inc.; USA Session VI Design and construction of valves and hot gas ducts No 23 The Klinger hot gas double axial valve J. Kruschik; Klinger Engineering; Austria; H. Hiltgen; Interatom GmbH; FRG No 24 Two layers thermal insulations tests for designing of hot gas ducts T. Nakase, S. Midoriyama, K. Roko, A. Yoshizaki; Kawasaki Heavy Industries, Ltd.; Japan No 25 Status of the development on hot gas ducts for HTRs H. Stehle, E. Klas; Interatom GmbH; FRG No 26 Graphite and carbon-carbon components for hot gas ducts in the HTR G. Popp, U. Gruber, H. Boder, K. Janssen? Sigri Elektrographit GmbH; FRG - 4 - f No 27 Research on thermal insulation for hot gas ducts P. Brockerhoff; Kernforschungsanlage Jiilich GmbH; FRG Session VII Description of component test facilities and test results No 28 Facility for endurance tests of thermal insulations R. Mauersberger; Hochtemperatur-Reaktorbau GmbH; FRG No 29 Construction and performance tests of helium engineering demonstration loop (HENDEL) for VHTR M. Hishida, T. Tanaka, H. Shimomura, K. Sanokawa; Japan Atomic Energy Research Institute; Japan No 30 Testing of high-temperature components in the KVK W. Jansing; Interatom GmbH; FRG No 31 WKV-operation experiences with heat exchanging compo- nents of a nuclear gasification pilot plant R. Kirchhoff, K. H. van Heek; Bergbau-Forschung GmbH; FRG No 32 The test facility EVA II/ADAM II - Description and operational results R. Harth, H. F. Niessen, V. Vau; Kernforschungsanlage Jiilich GmbH; FRG No 33 Modification of the AVR to a versatile nuclear test facility for high temperature components H. Barnert, N. Kirch, E. Ziermann; Kernforschungsanlage Jiilich GmbH; Arbeitsgemeinschaft Versuchsreaktor GmbH; FRG No 34 Heat removal by natural circulation in gas-cooled rod- bundles M. Hudina; Swiss Federal Institute for Reactor Research; Switzerland 5 - Session VIII Manufacturing of heat exchanging components No 35 Manufacture of steam generator units and components for the AGR power stations at Heysham II/Torness J. R. Glasgow, K. Parkin? Nuclear Systems Limited; UK No 36 The use of bimetallic welds in the THTR steam genera- tors U. Blumer, H. Fricker, S, Amacker; Sulzer Brothers Ltd.; Switzerland No 37 GMA-narrow gap welding of PNP-hot gas collectors K. Iversen, A. Palussek; Interatom GmbH; FRG No 38 Forged hollows (alloy 617) for PNP-project F. Hofmann; Vereinigte Deutsche Metallwerke AG; FRG SUMMARY Session I: Heat exchanging components for process heat application - design requirements and R & D programmes Session Chairman: E. Balthesen KFA-Jiilich - PTH -, FRG The first session of the Specialist's Meeting comprised survey papers describing the application of heat exchanging components in nuclear process heat plant concepts in the Federal Republic of Germany. These concepts are based on He-cooled high tempe- rature reactors as nuclear heat sources for steam gasification and hydrogasification of coal and for a thermochemical heat pipe system. The consideration of the strong interaction between nuclear heat source and application process illuminated the func- tion and the main design requirements for the heat ducting and exchanging components. The component designs are partially de- pending on different reactor designs. INTERATOM presented the HTR modular concept consisting of a number of independent small pebble bed reactor units with a thermal output of 170 MW each. Each modul can be combined either with a steam reformer in the primary circuit or with a He/He heat exchanger. The system company HRB presented a modified THTR pebble bed reactor embedded in PCRV. This concept fundamentally applies an intermediate heat transfer circuit with a tandem heat ex- changer design consisting of a high temperature and a low tempe- rature unit each. The process requirements, the gaseous media, the high temperatures and the necessary application of new materials mean a great techni- cal challenge for the development, design work as well as testing.