Graphite Materials for Nuclear Reactors
Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of neutron. Graphite materials are used both as a moderator and as a reflector in the core of high temperature gas-cooled reactors, and both as a rad...
Saved in:
| Published in | TANSO Vol. 1991; no. 150; pp. 338 - 353 |
|---|---|
| Main Author | |
| Format | Journal Article |
| Language | English |
| Published |
THE CARBON SOCIETY OF JAPAN
1991
|
| Subjects | |
| Online Access | Get full text |
Cover
Loading…
| Abstract | Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of neutron. Graphite materials are used both as a moderator and as a reflector in the core of high temperature gas-cooled reactors, and both as a radiation shielding material and as a reflector in the sur-rounding of the core for the fast breeder reactor. On the other hand, graphite materials are being positively used as a first wall of plasma as it is known that low Z materials are useful for holding high temperature plasma in the nuclear fusion devices. In this paper the present status of the application of graphite materials to the nuclear fission reactors and fusion devices (reactors) is presented. In addition, a part of results on the related pro-perties to the structural design and safety evaluation and results examined on the subjects that should be done in the future are also described. |
|---|---|
| AbstractList | Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of neutron. Graphite materials are used both as a moderator and as a reflector in the core of high temperature gas-cooled reactors, and both as a radiation shielding material and as a reflector in the sur-rounding of the core for the fast breeder reactor. On the other hand, graphite materials are being positively used as a first wall of plasma as it is known that low Z materials are useful for holding high temperature plasma in the nuclear fusion devices. In this paper the present status of the application of graphite materials to the nuclear fission reactors and fusion devices (reactors) is presented. In addition, a part of results on the related pro-perties to the structural design and safety evaluation and results examined on the subjects that should be done in the future are also described. |
| Author | Oku, Tatsuo |
| Author_xml | – sequence: 1 fullname: Oku, Tatsuo organization: Department of Mechanical Engineering, Faculty of Engineering, Ibaraki University |
| BookMark | eNpFj01Lw0AQhhepYKy9es7NU-JOdifZHKVoFVoF0fMy2Q-bUpOyGw_-e1MjdS4z8L7PwHPJZl3fOcaugedVwevbgbrY51DXkAuhzlgCSskMZY0zlnBRQYZC4gVbxLjj40jOi7JM2M0q0GHbDi7d0OBCS_uY-j6kz19m7yikr47M0Id4xc79mLnF356z94f7t-Vjtn5ZPS3v1pkpeKkyBPRI3ivrJXfGAlIjK0OFsiVIY7FQUgriyBsLUqAE2diqaQrwAm0jxJzl018T-hiD8_oQ2k8K3xq4PprqX1N9NNWj6QhsJmAXB_pwpzqFoR0VpjrUsp4QQP5_jPypZ7YUtOvED0-BYsQ |
| ContentType | Journal Article |
| Copyright | The Carbon Society of Japan |
| Copyright_xml | – notice: The Carbon Society of Japan |
| DBID | AAYXX CITATION |
| DOI | 10.7209/tanso.1991.338 |
| DatabaseName | CrossRef |
| DatabaseTitle | CrossRef |
| DatabaseTitleList | |
| DeliveryMethod | fulltext_linktorsrc |
| Discipline | Engineering |
| EISSN | 1884-5495 |
| EndPage | 353 |
| ExternalDocumentID | 10_7209_tanso_1991_338 article_tanso1949_1991_150_1991_150_338_article_char_en |
| GroupedDBID | ACGFS ALMA_UNASSIGNED_HOLDINGS JSP KQ8 OK1 RJT AAYXX ABJNI CITATION |
| ID | FETCH-LOGICAL-c2068-515f5aff8df40ecd15ab47ca28d614cd528443a050bd1435414bd7bb21f35db33 |
| ISSN | 0371-5345 |
| IngestDate | Tue Jul 01 04:34:20 EDT 2025 Wed Apr 05 10:51:58 EDT 2023 |
| IsDoiOpenAccess | true |
| IsOpenAccess | true |
| IsPeerReviewed | false |
| IsScholarly | true |
| Issue | 150 |
| Language | English |
| LinkModel | OpenURL |
| MergedId | FETCHMERGED-LOGICAL-c2068-515f5aff8df40ecd15ab47ca28d614cd528443a050bd1435414bd7bb21f35db33 |
| OpenAccessLink | https://www.jstage.jst.go.jp/article/tanso1949/1991/150/1991_150_338/_article/-char/en |
| PageCount | 16 |
| ParticipantIDs | crossref_primary_10_7209_tanso_1991_338 jstage_primary_article_tanso1949_1991_150_1991_150_338_article_char_en |
| ProviderPackageCode | CITATION AAYXX |
| PublicationCentury | 1900 |
| PublicationDate | 1991 |
| PublicationDateYYYYMMDD | 1991-01-01 |
| PublicationDate_xml | – year: 1991 text: 1991 |
| PublicationDecade | 1990 |
| PublicationTitle | TANSO |
| PublicationTitleAlternate | TANSO |
| PublicationYear | 1991 |
| Publisher | THE CARBON SOCIETY OF JAPAN |
| Publisher_xml | – name: THE CARBON SOCIETY OF JAPAN |
| References | 6) 高温ガス炉研究開発の現状, 日本原子力研究所 (1989). 12) 荒井, 西山, 三木, 奥, 「材料力学シンポジウム」, 日本機械学会, 1990. 28) Birch, M., Brocklehurst, J.E., ND-R-1434 (s), 1987. 17) Sato, S. et al., Proc. 15th Symp. on Fusion Tech., Utrecht (1988) F39, 231. 13) 淡路, 佐藤, 材料, 28 (1978) 522. 21) Dinwiddie, R.B., Sapp, J.W., Bowers, D.A., Extended Abstracts, 20th Biennial Conf. Carbon, p.620,(1991). 27) Kennedy, C.R., Mindermann, D., Proc. 4th Mt. Carbon Conf., Baden-Baden, FRG, June 30 July 4, 1986. 15) Ando, T., et al., J. Nucl. Mater. 179-181 (1991) 339. 3) 日野友明, 山科俊郎, 炭素, 1987 (No.130) 118 (1987). 5) 多目的高温ガス炉研究開発の現状, 日本原子力研究所 (1984). 18) Sato, S., Kurumada, A., et al., J. Nucl. Sci. and Tech., 24 (1987) 547. 26) Kasten, P.R., et al., Nucl Eng. Design, 9 (1969) 157. 25) Kelly, B.T., Fusion Technology 16 (1989) 96. 30) Cundy, M.R., O'Connor, M.F., Kleist, G., Carbon, 80, 569 (1980). 31) Kennedy, C.R., Cundy, M.R., Kleist, G., Proc. of an Mt. Conf. on Carbon, Univ. of Newcastle upon Tyne, UK, 1988, p.443. 2) 高津英幸, 奥達雄, 炭素, 1988 (No.135) 286 (1988). 7) 高温ガス炉研究会実行委員会, JAERI-M90-087 (1990). 14) 安東ほか, 核融合研究第65巻別冊P.27 (1991). 22) Sato, S., Kurumada, A., Kawamata, K., Ishida, R., Fusion Eng. and Design 13 (1990) 159. 24) Kobayashi, H., et al., Mechanical Behavior of Materials-VI', p.117 (1991). 10) Oku, T., Eto M., Ishiyama, S., J. Nuclear Mater. 172 (1990) 77. 4) 奥達雄, 「炭素素原料の有効利用」, CPC研究会, p.186 (1984). 11) 高温工学試験研究の現状, 日本原子力研究所 (1987). 29) Burchell, T.D., et al., Extended Abstracts, 20th Biennial Conf. Carbon, p.598 (1991). 23) 小林, 荒居, 荒木, 奥, 材料39 (1990) 1076. 9) 荒井長利, 佐藤貞夫, JAERI-M5513 (1974). 19) Seki, M., et al., Proc. of Japan-U.S. Work-shop P134 (1989) p.164. 20) Davis, J.W., Proc. of Japan-U.S. Workshop P134 (1989) p.194. 1) 奥達雄, 原子力工業, 34 (10号) 29 (1988). 8) Arai, T., Mogi, H., Iyoku, T., Ide, A., Takikawa, N., JAERI-M86-192 (1986) p.58. |
| References_xml | – reference: 17) Sato, S. et al., Proc. 15th Symp. on Fusion Tech., Utrecht (1988) F39, 231. – reference: 3) 日野友明, 山科俊郎, 炭素, 1987 (No.130) 118 (1987). – reference: 5) 多目的高温ガス炉研究開発の現状, 日本原子力研究所 (1984). – reference: 24) Kobayashi, H., et al., Mechanical Behavior of Materials-VI', p.117 (1991). – reference: 4) 奥達雄, 「炭素素原料の有効利用」, CPC研究会, p.186 (1984). – reference: 11) 高温工学試験研究の現状, 日本原子力研究所 (1987). – reference: 30) Cundy, M.R., O'Connor, M.F., Kleist, G., Carbon, 80, 569 (1980). – reference: 28) Birch, M., Brocklehurst, J.E., ND-R-1434 (s), 1987. – reference: 21) Dinwiddie, R.B., Sapp, J.W., Bowers, D.A., Extended Abstracts, 20th Biennial Conf. Carbon, p.620,(1991). – reference: 8) Arai, T., Mogi, H., Iyoku, T., Ide, A., Takikawa, N., JAERI-M86-192 (1986) p.58. – reference: 2) 高津英幸, 奥達雄, 炭素, 1988 (No.135) 286 (1988). – reference: 22) Sato, S., Kurumada, A., Kawamata, K., Ishida, R., Fusion Eng. and Design 13 (1990) 159. – reference: 25) Kelly, B.T., Fusion Technology 16 (1989) 96. – reference: 14) 安東ほか, 核融合研究第65巻別冊P.27 (1991). – reference: 31) Kennedy, C.R., Cundy, M.R., Kleist, G., Proc. of an Mt. Conf. on Carbon, Univ. of Newcastle upon Tyne, UK, 1988, p.443. – reference: 29) Burchell, T.D., et al., Extended Abstracts, 20th Biennial Conf. Carbon, p.598 (1991). – reference: 7) 高温ガス炉研究会実行委員会, JAERI-M90-087 (1990). – reference: 20) Davis, J.W., Proc. of Japan-U.S. Workshop P134 (1989) p.194. – reference: 27) Kennedy, C.R., Mindermann, D., Proc. 4th Mt. Carbon Conf., Baden-Baden, FRG, June 30 July 4, 1986. – reference: 1) 奥達雄, 原子力工業, 34 (10号) 29 (1988). – reference: 26) Kasten, P.R., et al., Nucl Eng. Design, 9 (1969) 157. – reference: 18) Sato, S., Kurumada, A., et al., J. Nucl. Sci. and Tech., 24 (1987) 547. – reference: 9) 荒井長利, 佐藤貞夫, JAERI-M5513 (1974). – reference: 12) 荒井, 西山, 三木, 奥, 「材料力学シンポジウム」, 日本機械学会, 1990. – reference: 10) Oku, T., Eto M., Ishiyama, S., J. Nuclear Mater. 172 (1990) 77. – reference: 19) Seki, M., et al., Proc. of Japan-U.S. Work-shop P134 (1989) p.164. – reference: 6) 高温ガス炉研究開発の現状, 日本原子力研究所 (1989). – reference: 15) Ando, T., et al., J. Nucl. Mater. 179-181 (1991) 339. – reference: 23) 小林, 荒居, 荒木, 奥, 材料39 (1990) 1076. – reference: 13) 淡路, 佐藤, 材料, 28 (1978) 522. |
| SSID | ssj0000400266 |
| Score | 1.2965302 |
| Snippet | Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of... |
| SourceID | crossref jstage |
| SourceType | Index Database Publisher |
| StartPage | 338 |
| SubjectTerms | Fission Reactor Fusion Reactor HTGR Mechanical Properties Nuclear Graphite Physical Properties Radiation Damage Structural Design Thermal Shock |
| Title | Graphite Materials for Nuclear Reactors |
| URI | https://www.jstage.jst.go.jp/article/tanso1949/1991/150/1991_150_338/_article/-char/en |
| Volume | 1991 |
| hasFullText | 1 |
| inHoldings | 1 |
| isFullTextHit | |
| isPrint | |
| ispartofPNX | TANSO, 1991/12/25, Vol.1991(150), pp.338-353 |
| link | http://utb.summon.serialssolutions.com/2.0.0/link/0/eLvHCXMwnV3PS8MwFA46PehB_Im_6UHwIJ1JmpjuKKIORUHYYLeSNMlBYZPZXfzrfa_puk52mEIppeQlbb_05Uv63ldCLqinKrdSxRomA7Fwysa641hsrcq1MzTnGtchX15vun3xNJCDmfJumV1SmHb-vTCv5D-owjnAFbNk_4BsXSmcgGPAF_aAMOyXwvgR1aaBM1696CK0V0YNvqJGsR5jgHz5M50mAe3B0DSqV1Y_JiVeuviajGbzf4xTajiIRLFYJkGOse2CA0tTEcOcT855uIYZYhmkXiuXlQR1lWr0S4J072_HqnipS1rgNWKCI2vXZk0F618jSx3vBzMNrCEr7TO0z8B-laxxIPfoTp_f0nplDN0Krz4yVzcY1Daxiuv5S5hjE-vvQKinwXglP-htk62K2Ee3AaUdsuKGu2SzIfe4Ry6neEU1XhHgFVV4RVO89kn_4b53142rH1XEOaeYucakl9r71HpBXW6Z1EZAX-epBfYDrwJwAJFoKqmxyE8FE8YqYzjzibQmSQ5IazgaukMSMa2AQFkD1lrccNWBOhk1znHvqU_pEbmc3nD2GfRIssVP94g8hOdRl6v6aSjHOqITykJ3mB2AYV0O8_7gNTteuskTshEi6XA7Ja1iPHFnwNkKc15C_AM49kFZ |
| linkProvider | Colorado Alliance of Research Libraries |
| openUrl | ctx_ver=Z39.88-2004&ctx_enc=info%3Aofi%2Fenc%3AUTF-8&rfr_id=info%3Asid%2Fsummon.serialssolutions.com&rft_val_fmt=info%3Aofi%2Ffmt%3Akev%3Amtx%3Ajournal&rft.genre=article&rft.atitle=Graphite+Materials+for+Nuclear+Reactors&rft.jtitle=Tanso&rft.au=Oku%2C+Tatsuo&rft.date=1991&rft.issn=0371-5345&rft.eissn=1884-5495&rft.volume=1991&rft.issue=150&rft.spage=338&rft.epage=353&rft_id=info:doi/10.7209%2Ftanso.1991.338&rft.externalDBID=n%2Fa&rft.externalDocID=10_7209_tanso_1991_338 |
| thumbnail_l | http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/lc.gif&issn=0371-5345&client=summon |
| thumbnail_m | http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/mc.gif&issn=0371-5345&client=summon |
| thumbnail_s | http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/sc.gif&issn=0371-5345&client=summon |