HTGR Knowledge Base
IAEA-TECDOC--1210: Safety related design and economic aspects of HTGR
Proceedings of a Technical Committee Meeting held in Beijing, People's Republic of China, 2-4 November 1998
International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria), IAEA-TECDOC--1210
Abstract
The HTGR, as a nuclear heat source for the safe, economic and efficient production of electricity and high temperature industrial processes has, within the past few years, become a significantly increasing influence in the future of nuclear power. Nuclear test facilities with the capability of achieving core outlet temperatures to 950 deg. C are presently under construction in the People's Republic of China and Japan. These plants will be utilized to support HTGR research and development activities including electricity generation via the gas turbine and validation of high temperature process heat applications. Also, major development programmes focusing on the generation of electricity through the direct cycle gas turbine are in progress by ESKOM, the state electric utility of South Africa, and by a consortium of organizations from the Russian Federation, USA, France and Japan. Other national programmes focusing on research and development of the HTGR are underway including the Netherlands, where an evaluation is being completed on a heat and power co-generation plant utilizing a small direct cycle HTR; in Germany, where the primary focus is centered on basic issues of reactor safety and innovative reactor technology; in Indonesia with the evaluation of process heat applications such as coal liquefaction, hydrogen production and high temperature reforming of methane; and in the USA with the recent reintroduction of national support for the HTGR specifically directed to the burning of weapons plutonium.
view the full text of this conference report (format: PDF, size= 13349kB, 254 pages)
see also:
- cover pages and foreword (4 pages, format: PDF, size= 95kB )
- summary of sessions (6 pages, format: PDF, size= 499kB )
- index of contents (2 pages, format: PDF, size= 73kB )
- list of participants (8 pages, format: PDF, size= 171kB )
Articles
Recommendations for the development of high temperature reactors
D. Bastien (CEA), A. Chevalier (NNC), B.R.W. Haverkate (ECN), D. Hittner (Framatome), J. Magill (JRC/ITU), G. Proto (Ansaldo), H. Reutler (HTR-GmbH), N. Taylor (JRC/IAM) and W. von Lensa (FZj)
GT-MHR as economical highly efficient inherently safe modular gas cooled reactor for electric power generation
A.G.Baydakov, N.G.Kodochigov, N.G.Kuzavkov, V.E.Vorontsov (OKBM, Nizhny Novgorod, Russia)
Relevant safety issues in designing the HTR-10 reactor
Y. Sun, Y. Xu (Institute of Nuclear Energy Technology, Beijing, China)
Present activity of the feasibility study of HTGR-GT system
Y. MUTO, Y. MIYAMOTO and S. SHIOZAWA (Department of Advanced Nuclear Heat Technology, Oarai Research Establishment, JAERI)
Fuel cycle related-parametric study considering long-lived actinide production, decay heat and fuel cycle performances
X. RAEPSAET, F. DAMIAN, R. LENAIN (CEA/DRN, CEN Saclay, France),M. LECOMTE (Framatome, France)
Activities of RAHP and problems to be cleared towards commercialization
S. AN (Chairman, RAHP; Professor Emeritus, Univ. of Tokyo),Y. TSUCHIE (Rep. Secretary, RAHP; The Japan Atomic Power Co.)
Safety evaluation during a depressurization accident of the SFHTR
S. Nakagawa, A. Saikusa and K. Kunitomi (Department of HTTR Project, JAERI, Japan)
Nuclear design code development for fuel management and safety analysis of HTGR in Indonesia
L. P. Hong (Center for Multipurpose Reactor, National Atomic Energy Agency (Batan), Indonesia)
PBMR-SA licensing project organization
Clapisson G.A., Metcalf P.E., Mysen A.(Council for Nuclear Safety,South Africa)
Transient analysis for the high temperature pebble-bed reactor coupled to the energy conversion system
E.C. Verkerk (Nuclear Research and Consultancy Group (NRG),The Netherlands)
Application study of the heat pipe to the passive decay heat removal system of the modular HTR
K. OHASHI, F. OKAMOTO, H. HAYAKAWA (Fuji Electric Co., Ltd.,Japan),T. HAYASHI (Tokai University, Japan)
Nuclear graphite ageing and turnaround
B.J.Marsden(AEA Technology plc, UK),G.N.Hall,J Smart(University of Manchester, UK)
A study on cost reduction effect due to changes of safety grade of HTGR
S. UCHIDA(Advanced Reactor Technology Co., Ltd.,Japan), I. MINATSUKI, M. TANIHIRA, S. YAMADA (Mitsubishi Heavy Industries Co., Ltd.,Japan)
Characteristics of DC electrical braking method of the gas circulator to limit the temperature rise at the heat transfer pipes in the HTTR
K. KAWASAKI, K. SAITO and T. IYOKU(JAERI, Department of HTTR Project, Japan)
Analysis of stress in reactor core vessel under effect of pressure lose shock wave
L. Yong, L. Baoting (Institute of Nuclear Energy Technology Tsinghua University, Beijing)
Fabrication of HTTR first loading fuel
S. KATO, S. YOSHIMUTA, T. HASUMI, K. SATO (Nuclear Fuel Industries, Ltd., Japan),K. SAWA, S. SUZUKI, H. MOGI, S. SHIOZAWA, T. TANAKA (Japan Atomic Energy Research Institute, Japan)
An HTR cogeneration system for industrial applications
B.R.W. Haverkate, A.I.van Heek (Netherlands Energy Research Foundation ECN, The Netherlands),J.F. Kikstra (Delft University of Technology, The Netherlands)
Development programme on hydrogen production in HTTR
Y.INAGAKI, T.NISHIHARA, T.TAKEDA, K.HADA, M.OGAWA, S.SHIOZAWA, Y.MIYAMOTO (JAERI, Japan)
Techno-economic analysis of seawater desalination using high temperature gas-cooled reactor
L. Wu, Z. Qin (Tsinghua University, Beijing, China)
Use of plutonium in pebble bed HTGRs
K.Kugeler, W.von Lensa, G. Haag, H.J. Rütten (Institute for Safety Research and Reactor Technology, Forschungszentrum Juelich GmbH, Germany)
Sustainability and acceptance - new challenges for nuclear energy
W. von Lensa (Institute for Safety Research and Reactor Technology, Forschungszentrum Juelich GmbH, Germany)
