HTGR Knowledge Base

IWGGCR--11: Graphite component structural design

Specialists' meeting on graphite component structural design, JAERI Tokai (Japan), September 8-11, 1986

International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors, IWGGCR--11

Abstract

On the invitation of the Government of Japan the International Atomic Energy Agency (IAEA) convened on September 8-11, 1986, in Tokai the Specialists' Meeting on "Graphite Component Structural Design". The meeting was held in the framework of the IWGGCR (International Working Group on Gas-Cooled Reactors) and hosted by the Japan Atomic Energy Research Institute at the Tokai Research Establishment. The purpose of the meeting was to provide an international forum to compare and discuss the state of the art of the development of and experience with graphite components for gas-cooled reactors in order to define critical issues and to give directions for future R&D.

The sessions concentrated on the subjects:

This volume contains all paper presented at the meeting.

view the full text of this conference report (format: PDF, size= 16895kB, 256 pages)

see also:

Articles

The integrity of CAGR moderator bricks
Prince, N. (UKAEA Risley Nuclear Power Development establishment); Brocklehurst, J.E

The assessment of the integrity of AGR core during an earthquake
Smith, C.R. (National Nuclear Corp. Ltd., Risley (UK))

Mechanical design philosophy for the graphite components of the core structure of an HTGR
Bodmann, E. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))

HTGR fuel element structural design consideration
Alloway, R.; Gorholt, W.; Ho, F.; Vollman, R.; Yu, H. (GA Technologies, Inc., San Diego, CA (USA))

Structural design of reactor core and support graphite components for the experimental VHTR
Arai, T.; Mogi, H.; Iyoku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment); Ide, A.; Takikawa,N.

The statistical characterization of tensile strengths for a nuclear-type graphite
Kennedy, C.R.; Eatherly, W.P. (Oak Ridge National Lab., TN (USA))

Statistical considerations of graphite strength for assessing design allowable stresses
Ishihara, M.; Mogi, H.; Ioka, I.; Arai, T.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

Fracture criterion of reactor graphite under multiaxial stresses
Sato, S.; Kawamata, K.; Kurumada, A. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering); Awaji, H.; Oku, T

Structural assessment of prismatic blocks for pin-in-block fuel element
Takikawa, N.; Koike, H.; Tanaka, M. (Kawasaki Heavy Industries Ltd., Tokyo (Japan)); Arai, T.; Iyoku, T.; Ide, A

Experimental and theoretical evaluation of core alignment structures against a seismic load
Ide, A.; Miki, T. (Fuji Electric Co. Ltd., Tokyo (Japan)); Matsumura, M.; Mogi, H.; Ishihara, M.; Koike, H

Structural strength of core graphite bars
Kikuchi, K.; Futakawa, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

The experimental qualification of a mathematical model used to assess the AGR core seismic response
Shaw, D.C. (National Nuclear Corp. Ltd., Risley (UK))

Seismic response analysis of prismatic block cores of the experimental VHTR
Iyoku, T.; Motoki, Y.; Arai, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment); Miki, T.; Ide, A

Development and testing of nuclear graphite for the German pebble-bed high temperature reactor
Haag, G.; Delle, W.; Nickel, H. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)); Theymann, W.; Wilhelmi, G

High temperature Young's modulus of IG-110 graphite
Konishi, T.; Eto, M.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

Effects of high temperature neutron irradiation on the physical, chemical and mechanical properties of fine-grained isotropic graphite
Matsuo, H.; Nomura, S.; Imai, H.; Oku, T.; Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

Degradations of thermal shock resistance and the fracture toughness of reactor graphite subjected to neutron irradiation
Sato, S.; Kawamata, K.; Kurumada, A.; Ugachi, H. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering); Awaji, H

Application of ISRM testing methods to fracture toughness testing of graphite
Hashida, T.; Fukasawa, T.; Takahashi, H. (Tohoku Univ., Sendai (Japan)); Ishiyama, S.; Oku, T

Notch sensitivity of graphite materials for VHTR
Kawakami, Haruo (Fuji Electric Corp. Research and Development Ltd., Yokosuka, Kanagawa (Japan))

Nondestructive testing of HTGR graphites
Maruyama, T. (Tokyo Inst. of Tech. (Japan). Research Lab. of Nuclear Reactor); Uragaki, H.; Fujii, M.; Ooka, K.; Sakashita, T.; Suzuki, H.; Oku, T

Achieving optimum graphite performance in AGR core and fuel
Norfolk, D.J.; Johnston, G.O.; Tucker, M.O. (Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.)

Graphite corrosion under severe HTR accident conditions
Katscher, W.; Moormann, R. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))

Estimation of graphite materials corrosion with water-vapor in coolant of the VHTR and oxidation effect on the materials properties
Eto, M.; Kurosawa, T.; Imai, H.; Nomura, S.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

A graphite corrosion rate equation under high concentration water-vapor in helium and an estimation of the VHTR support post corrosion and strength
Nomura, S.; Kurosawa, T.; Imai, H.; Eto, M.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

Radiation effect on the graphite of HTGR
Platonov, P.A.; Strombach, Ya.I.; Karpukhin, V.I.; Gurovich, B.A.; Chugunov, O.K.; Trofimchuk, E.I. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)

Matrix graphite for HTGR spherical fuel elements some their properties
Chernikov, A.S.; Mozzherin, S.I.; Reshetnikov, V.A. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)

Irradiation dimensional stability of graphite containing green coke filler
Kalyagina, I.P.; Virgiliev, Yu.S

Elastic-plastic fracture toughness of HTGR graphites
Oku, T.; Ishiyama, S.; Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment); Inagaki, M.; Hashida, T.; Takahashi, H

Fatigue behavior of fine-grained isotropic graphite for HTGRs
Ishiyama, S.; Eto, M.; Oku, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

Acoustic emission from polycrystalline graphites
Ioka, I.; Yoda, S.; Oku, T.; Miyamoto, Y. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment)

Experience obtained from construction and preliminary test of in-core structure test section (T-2)
Kunitomi, K.; Inagaki, Y.; Ioka, I.; Kondo, Y.; Miyamoto, Y.; Shimomura, H. (Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment); Akisada, T.; Yamaguchi, S

Results of the visual in-pile inspection of the inner graphite reflector of the AVR
Haag, G.; Delle, W.; Kirch, N.; Nickel, H. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)); Reinhart, K.; Ziermann, E