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IAEA-TECDOC--690: The status of graphite development for gas cooled reactors.

Specialists' meeting on the status of graphite development for gas cooled reactors. Tokai, Ibaraki (Japan). 9-12 Sep 1991

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--690

Abstract

The meeting was convened by the IAEA on the recommendation of the International Working Group on Gas Cooled Reactors. It was attended by 61 participants from 6 countries. The meeting covered the following subjects: overview of national programs. Design criteria, fracture mechanisms and component test. Materials development and properties. Non-destructive examination, inspection and surveillance. The participants presented 33 papers on behalf of their countries.

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Articles

A microstructurally based fracture model for nuclear graphite
Burchell, T.D. (Oak Ridge National Lab., TN (United States))

Burst tests to measure the tangential strength of CFC tubes
Roedig, M.; Woschek, B. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer Reaktorwerkstoffe); Baur, W. (SIGRI GmbH, Meitingen (Germany))

Spatial variability in the tensile strength of an extruded nuclear-grade graphite
Strizak, J.P. (Oak Ridge National Lab., TN (United States))

Evaluations of the fracture mechanical properties of fuel compacts for the HTTR, with emphasis on thermal shock resistances and neutron irradiation effects
Sato, S.; Kurumada, A.; Kawamata, K. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering); Suzuki, N.; Kaneko, M. (Nuclear Fuels Industries, Ltd, Tokai (Japan). Tokai Works); Fukuda, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)

A method for assessing the effects of graphite property variability on core structural integrity criteria
Judge, R.C.B. (AEA Reactor Services, Risley (United Kingdom). Gas Cooled Reactor Assessments Dept.)

Bending fatigue behavior of nuclear-grade graphite under impact loading
Futakawa, M.; Kikuchi, K.; Muto, Y. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of High Temperature Engineering); Shibata, H. (Tokyo Univ. (Japan). Inst. of Industrial Science)

Component test of the core support post of the HTTR
Ishihara, M.; Iyoku, T.; Takikawa, N.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Jinza, K.; Tsuji, N.; Miki, T. (Fuji Electric Co. Ltd., Kawasaki, Kanagawa (Japan))

Assessment of the load capacity of the dowel and socket system in the HTTR hexagonal block
Takikawa, N.; Ishihara, M.; Iyoku, T.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Tokumitsu, M.; Koe, S.; Uno, M. (Kawasaki Heavy Industries (Japan))

The vibrational characteristics of the keyed graphite components in the HTTR
Futakawa, M.; Iyoku, T.; Shiozawa, S.; Takada, S. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment); Shirai, H. (CSK Co., Tokyo (Japan))

Fabrication of HTGR core components by the method of volume gas-phase impregnation of porous media with pyrocarbon - main characteristics of the materials and products
Zelenskij, V.F.; Gurin, V.A.; Konotop, Yu.F.; Deryuga, Yu.A.; Kolosenko, V.V. (AN Ukrainskoj SSR, Kharkov (Ukraine). Fiziko-Tekhnicheskij Inst.)

Development of graphite for fuel element sleeves in advanced gas cooled reactors
Burridge, D.P.; Naylor, J.E. (British Nuclear Fuels plc, Salwick (United Kingdom). Fuel Engineering Dept.)

Mechanical properties and thermal shock resistances of recently developed high performance graphites
Sato, S.; Kawamata, K.; Kurumada, A.; Chiba, A. (Ibaraki Univ., Hitachi (Japan). Faculty of Engineering)

Behavior of gas desorption and gas permeability of carbon materials
Okada, M.; Sogabe, T. (Toyo Tanso Co., Ltd, Mitoyo, Kagawa (Japan))

Relation between gasification rates and gas desorption behavior with metallic impurities of carbon and graphite materials for the HTTR
Nomura, S.; Fujii, K.; Shindo, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki, (Japan). Dept. of Fuels and Materials Research); Imai, H. (Research Association for Nuclear Facilities Decommissioning, Tokai, Ibaraki (Japan))

Corrosion behavior of sintered pellet of graphite and boron carbide in helium containing water vapor
Fujii, K.; Nomura, S.; Shindo, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research); Imai, H. (Research Association for Nuclear Facilities Decommissioning, Tokai, Ibaraki (Japan))

Effect of atmosphere on the bend strength of nuclear graphite
Maruyama, T. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)

Corrosion tests of matrix graphites
Vavilin, A.I.; Kulikov, E.T.; Mozzherin, S.I.; Chernikov, A.S. (Scientific and Industrial Association 'Lutch', Podol'sk (Russian Federation))

Engineering thermomechanics of nuclear graphites under neutron irradiation, oxidation and transient heat up: A review
Arai, T. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)

A review of irradiation creep in reactor graphite
Kelly, B.T. (AEA Technology, Salwick (United Kingdom))

Specific behavior of reflector and matrix graphite under high temperature irradiation
Platonov, P.A.; Karpukhin, V.I.; Shtrombakh, Ya.I.; Alekseev, V.M.; Chugunov, O.K.; Gurovich, B.A.; Trofimchuk, E.I. (I.V. Kurchatov Inst. of Atomic Energy, Moscow (Russian Federation). Dept. of Research Reactors and Technology)

Irradiation behavior of boronated graphite for the HTTR
Matsuo, H. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment); Kobayashi, F.; Sawa, K. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)

Capsule design, fabrication and irradiation for tensile creep test on HTGR graphites at 1200 deg. C in the JMTR
Saito, T. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Kikuchi, T.; Arai, T.; Ugachi, H. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)

Strength analysis code for graphite structural components in uranium-graphite nuclear reactors
Rodchenkov, B.S.; Platonov, P.A.; Manevskij, V.N.; Kashirin, B.A.; Chugunov, O.K. (Research and Development Inst. of Power Engineering (Russian Federation))

The effect of volume on the tensile strength of several nuclear-grade graphites
Strizak, J.P. (Oak Ridge National Lab., TN (United States))

The effects of specimen geometry and size on the fracture toughness of nuclear graphites
Romanoski, G.R.; Burchell, T.D. (Oak Ridge National Lab., TN (United States))

Cumulative fatigue damage on HTGR graphite
Ishiyama, S.; Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of High Temperature Engineering)

Fracture behavior of nuclear graphites under compressive impact loading
Ugachi, H.; Ishihara, M.; Ishiyama, S.; Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of High Temperature Engineering)

Radiolytic corrosion of graphite surveillance and lessons drawn from the operation of the BUGEY-1 reactor
Petit, A. (Electricite de France (EDF), 01 - Loyettes (France). Centrale de Bugey); Phalippou, C.; Brie, M. (CEA Centre d'Etudes de Saclay, 91 - Gif-sur-Yvette (France))

Graphite surveillance in N Reactor
Woodruff, E.M. (Westinghouse Hanford Co., Richland, WA (United States). N Reactor Facility and Operation Assurance)

Non-destructive testing and acceptance test for HTTR graphite components
Takikawa, N.; Iyoku, T.; Shiozawa, S.; Ooka, N. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Kambe, M.; Ide, A. (Fuji Electric Co. Ltd., Kawasaki, Kanagawa (Japan))

Non-destructive test of HTGR graphite components
Ishihara, M.; Ishii, T.; Ishiyama, S.; Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of High Temperature Engineering)

The correlation of hardness with Young's modulus and strengths of nuclear carbon materials
Oku, T.; Ohta, S. (Ibaraki Univ., Hitachi, Ibaraki (Japan). Dept. of Mechanical Engineering); Eto, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)

Quantitative analysis of trace amounts of impurities contaminating pure graphite with ICP-MS and metal atomizer FLAAS
Miyatani, T.; Suzuki, H.; Yoshimoto, O. (Toyo Tanso Co., Ltd, Mitoyo, Kagawa (Japan))