HTGR Knowledge Base

IAEA-TECDOC--901: Graphite moderator lifecycle behaviour.

Specialists meeting on graphite moderator lifecycle behaviour. Bath (United Kingdom). 24-27 Sep 1995.

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--901

Abstract

The meeting provided the forum for graphite specialists representing operating and research organizations worldwide to exchange information in the following areas: the status of graphite development. Operation and safety procedures for existing and future graphite moderated reactors. Graphite testing techniques. Review of the experiences gained and data acquired on the influence of neutron irradiation and oxidizing conditions on key graphite properties. And to exchange information useful for decommissioning activities. The participants provided twenty-seven papers on behalf of their countries and respective technical organizations. An open discussion followed each of the presentations. A consistently reoccurring theme throughout the specialists meeting was the noticeable reduction in the number of graphite experts remaining the nuclear power industry. Graphite moderated power reactors have provided a significant contribution to the generation of electricity throughout the past forty years and will continue to be a prominent energy source for the future. Yet, many of the renowned experts in the field of nuclear graphites are nearing the end of their careers without apparent replacement. This, coupled with changes in the focus on nuclear power by some industrialized countries, has prompted the IAEA to initiate an evaluation on the feasibility and interest by Member States of establishing a central archive facility for the storage of data on irradiated graphites.

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Articles

Irradiation damage in graphite. The works of Professor B.T. Kelly
Marsden, B.J. (AEA Technology, Risley (United Kingdom). Graphite Section)

Graphite core design in UK reactors
Davies, M.W. (NNC Ltd, Knutsford, Cheshire (United Kingdom). Nuclear Engineering Div.)

The high temperature reactor (HTR) and the new German safety concept for future nuclear power plants
Haag, G.; Kugeler, K.; Philippen, P.W. (Forschungszentrum Juelich GmbH (Germany))

Nuclear graphite development, operational problems, and resolution of these problems at the Hanford production reactors
Morgan, W.C. (Pacific Northwest Lab., Richland, WA (United States))

Radiation damage and life-time evaluation of RBMK graphite stack
Platonov, P.A.; Chugunov, O.K.; Manevsky, V.N.; Karpukhin, V.I. (Russian Research Centre Kurchatov Inst., Moscow (Russian Federation). Reactor Material Div.)

The development of direct core monitoring in Nuclear Electric plc
Curtis, R.F.; Jones, S. (Berkeley Technology Centre, Nuclear Electric plc., Berkeley (United Kingdom). Remote Operation Section) Reed, J.; Wickham, A.J. (Berkeley Technology Centre, Nuclear Electric plc., Berkeley (United Kingdom). Fuel and Core Section)

Results of assembly test of HTTR reactor internals
Maruyama, S.; Saikusa, A.; Shiozawa, S. (Japan Atomic Energy Research Inst., Ibaraki (Japan)); Tsuji, N.; Miki, T. (Fuji Electric Co. Ltd., Kawasaki, Kanagawa (Japan))

Application of a method for assessing probability of graphite core brick failure
Judge, R.C.B. (AEA Technology, Harwell (United Kingdom))

AGR core safety assessment methodologies
McLachlan, N.; Reed, J.; Metcalfe, M.P. (Nuclear Electric plc, Berkeley (United Kingdom). Berkeley Technology Centre)

Assessments of the stresses and deformations in an RBMK graphite moderator brick
Jones, C.J.; Davies, M.A.; Marsden, B.J. (AEA Technology, Risley (United Kingdom)); Bougaenko, S.E.; Baldin, V.D.; Demintievski, V.N.; Rodtchenkov, B.S.; Sinitsyn, E.N. (Research and Development Inst. of Power Engineering (RDIPE), Moscow (Russian Federation))

The seismic assessment of radially keyed graphite moderator cores
Steer, A.G.; Payne, J.F.B. (Nuclear Electric plc, Berkeley (United Kingdom). Berkeley Technology Centre)

The state of the graphite stack at Leningrad NPP, unit 2, after 16.5 years of operation
Baldin, V.D.; Rodtchenkov, B.S. (Research and Development Inst. of Power Engineering (RDIPE), Moscow (Russian Federation)); Platonov, P.A.; Chugunov, O.K. (Russian Research Centre, Kurchatov Inst. Moscow (Russian Federation))

Graphite stack corrosion of BUGEY-1 reactor (synthesis)
Petit, A. (EDF, Cedex (France)); Brie, M. (CEA, DRN-DMT-CEA Saclay, Cedex (France))

Radiolytic graphite oxidation revisited
Minshall, P.C.; Sadler, I.A.; Wickham, A.J. (Nuclear Electric plc, Berkeley (United Kingdom). Berkeley Technology Centre)

Graphite waste incineration in a fluidized bed
Guiroy, J.J. (FRAMATOME, Dismantling and Waste Management Dept., Cedex (France). Nuclear Projects Div.)

Status of the research and development at JAERI on the C/C composite control rod for HTGR
Eto, M.; Ishiyama, S.; Ugachi, H. (Japan Atomic Energy Research Inst., Ibaraki (Japan))

Influence of air oxidation on thermal shock resistances of nuclear carbon materials
Kurumada, A.; Oku, T. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering); Harada, K. (Japan Atomic Energy Research Inst., Ibaraki (Japan)); Kawamata, K. (Ibaraki Univ., Ibaraki (Japan). Faculty Engineering); Sato, S. (Iwaki Meisei Univ., Fukushima (Japan)); Hiraoka, T. (Tokyo Tanso Co. Ltd., Kagawa (Japan)); McEnaney, B. (Bath Univ. (United Kingdom). School of Materials Science)

An analytical study on porosity changes of nuclear graphites under high temperature irradiations
Arai, T. (Japan Atomic Energy Research Inst., Ibaraki (Japan). Dept. of High Temperature Engineering)

Acceptance test for graphite components and construction status of HTTR
Iyoku, T.; Ishihara, M.; Maruyama, S.; Shiozawa, S. (Japan Atomic Energy Research Inst., Ibaraki (Japan)); Tsuji, N.; Miki, T. (Fuji Electric Co. Ltd., Kawasaki, Kanagawa (Japan))

Radiation behaviour of graphite for HTGR
Shtrombakh, Ya.I.; Platonov, P.A.; Gurovich, B.A.; Alekseev, V.M. (Russian Research Centre Kurchatov Inst., Moscow (Russian Federation))

Blunt indentation of core graphite
Hartley, M.; McEnaney, B. (Bath Univ. (United Kingdom). School of Materials Science)

Effect of compressive prestress on the Young's modulus and strength of isotropic graphite
Oku, T.; Ota, S. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering); Shiraishi, M. (National Inst. for Pollution and Resources, Ibaraki (Japan)); Eto, M. (Japan Atomic Energy Research Inst., Ibaraki (Japan)); Gotoh, Y. (Hitachi Research Lab., Hitachi (Japan))

Preliminary study on application of eddy current testing as monitoring technique for graphite components in HTTR
Ishihara, M.; Iyoku, T. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)

A systematic study of acoustic emission from nuclear graphites
Neighbour, G.B.; McEnaney, B. (Bath Univ. (United Kingdom). School of Materials Science)

The interaction of strain, the coefficient of thermal expansion and dimensional changes in graphite
Marsden, B.J.; Preston, S.D.; Davies, M.A. (AEA Technology, Risley (United Kingdom)); McLachlan, N. (Nuclear Electric plc, Berkeley (United Kingdom). Berkeley Technology Centre)

In situ studies of the kinetics of surface topography development during ion irradiation
Levinskas, R. (Lthuanian Energy Inst., Kaunas (Lithuania). Material Research and Testing Lab.); Pranevicius, L. (Vytautas Magnus Univ., Kaunas (Lithuania). Dept. of Physics)

Gaseous diffusion and pore structure in nuclear graphites
Mays, T.J.; McEnaney, B.; Kelly, B.T. (Bath Univ. (United Kingdom). School of Materials Science)

Development of the graphite matrix materials of the fuel elements for the 10 MW HTR test module
Qiu Xueliang; He Jun; Guo Guiju; Zuo Kaifer; Zhang Shuangxi (Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy Technology)

Oxidation behaviour of the matrix materials
Qiu Xueliang; He Jun; Ma Changwen (Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy Technology); Zhang Shichao (Beijing Univ. of Aeronautics and Astronautics, Beijing (China). Dept. of Materials Science and Engineering)