178
Views
2
CrossRef citations to date
0
Altmetric
TECHNICAL REPORT

Technical Code Issues of ITER Vacuum Vessel and Their Resolutions

Pages 687-694 | Received 13 May 2003, Accepted 16 Jul 2003, Published online: 07 Feb 2012

References

  • Maruo , T. 2002 . “V. Safety features of ITER and Approach to Ensure its Safety” in “The Summary Report on Engineering Design Activities in the ITER Project,” . Nihon-Gensiryoku-Gakkai Shi (J. At. Energy Soc. Jpn.) , 44 ( l ) : 75 – 82 . [in Japanese]
  • Asada , Y. , Miya , K. , Hada , K. and Tada , E. “Code of a Tokamak Fusion Energy Facility ITER,” . Proc. 10th Int. Conf. on Nuclear Engineering . Apr. l4-l8 2002 , Arlington , U.S.A.. No. 22673 (CD-ROM)
  • 2002 . ITER Technical Basis , ITER EDA Documentation Series, No. 24 Vienna : IAEA .
  • l982 . Pressure Vessel and Piping: Design Technology—A Decade of Progress , ASME .
  • Neyatani , Y. , Tsuru , D. , Nakahira , M. , Araki , T. , Araya , F. and Nomoto , K. “Study of decay heat removal and structural assurance by LBB concept of tokamak components,” . Proc. 18th IAEA Fusion Energy Conf. Oct. 4-l0 2000 , Sorrento , Italy. IAEA-CN-77/SEP/0l
  • Koizumi , K. , Nakahira , M. , Itou , Y. , Kanamori , N. , Kitamura , K. , Tada , E. , Johnson , G. , Shimizu , K. , Sannazzaro , G. , Takahashi , K. , Utin , Y. and Ioki , K. “Development of full-scale sector model for ITER vacuum vessel,” . Fusion Technol. 1996 Proc. 19th Symp. on Fusion Technol. Sept. l6–20 1996 , Lisbon , Portugal. Vol. 2 , pp. l347 – l350 .
  • Koizumi , K. , Nakahira , M. , Itou , Y. , Takahashi , H. , Tada , E. , Ioki , K. , Johnson , G. , Onozuka , M. , Utin , Y. , Sannazzaro , G. , Elio , F. and Takahashi , K. “Fabrication of full-scale sector model for ITER vacuum vessel,” . Proc. 17th IEEE/NPSS Symp. Fusion Eng. Oct. 6-l0 1997 , San Diego , U.S.A.. Vol. 2 , pp. 933 – 936 .
  • Nishi , H. , Eto , M. , Tachibana , K. and Nakahira , M. “Fatigue strength reduction factor of partial penetration weldments for ITER vacuum vessel,” . Trans. 16th Int. Conf. on Structural Mech. in Reactor Technol. (SmiRT) . Aug. l2-l7 200l , Washington D.C. , U.S.A.. No. l626 (CD-ROM)
  • l969 . Criteria of the ASME Boiler and Pressure Vessel Code for Design by Analysis in Sections III and VIII, Division 2 , ASME .
  • 2001 . “Design Requirements and Guide-lines Level l (DRGl),” , ITER Joint Central Team . Private communication, provided by
  • Tsujikawa , S. and Hisamatsu , Y. l980 . Boshoku Gijutsu , 29 : 37 [in Japanese]
  • Asada , Y. , Tashimo , M. and Ueta , M. “System based code: Principal concept,” . Proc. 10th Int. Conf. on Nuclear Engineering . Apr. l4-l8 2002 , Arlington , U.S.A.. No. 22730 (CD-ROM)
  • Asada , Y. , Tashimo , M. and Ueta , M. “System based code: Basic structure,” . Proc. 10th Int. Conf. on Nuclear Engineering . Apr. l4-l8 2002 , Arlington , U.S.A.. No. 2273l (CD-ROM)

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.