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ORIGINAL PAPER

Preliminary Safety Analysis on Depressurization Accident without Scram of a Molten Salt Reactor

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Pages 720-730 | Received 06 Apr 2005, Accepted 10 Mar 2006, Published online: 05 Jan 2012

References

  • Robertson , R. C. 1971 . Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor , ORNL-4541 Oak Ridge , TN : Oak Ridge National Laboratory .
  • Mitachi , K. , Suzuki , T. , Nakanishi , Y. Okabayashi , D. 1999 . “A preliminary design study of a Small Molten Salt Reactor for effective use of thorium resource” . In 7th Int. Conf. on Nuclear Engineering Tokyo , , Japan 7144
  • Mitachi , K. , Suzuki , T. , Nakanishi , Y. , Okabayashi , D. and Yoshioka , R. 2000 . “Re-estimation of nuclear characteristics of a Small Molten Salt Power Reactor” . Nihon-Genshiryoku-Gakkai Shi (J. At. Energy Soc. Jpn.) , 42 ( 9 ) : 99 [in Japanese]
  • Yoshioka , R. Private communication
  • Chao , Y. A. and Huang , P. 1989 . “Theory and performance of the Fast-Running Multidimensional Pressurized Water Reactor Kinetics Code, SPNOVA-K” . Nucl. Sci. Eng. , 103 : 415
  • Okumura , K. , Kaneko , K. and Tsuchihashi , K. 1996 . SRAC95; General Purpose Neutronic Code System , JAERI-Data/Code 96–015 [In Japanese]
  • http://www.haynesintl.com Haynes International, Inc

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