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Technical Paper

Mechanical Behavior of SNR-300 Reactor Vessel Components Under Postaccident Heat Removal Conditions

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Pages 46-52 | Published online: 10 May 2017

References

  • W. MASCHEK and D. STRUWE, “Recriticality Considerations and Core Material Distribution in the Reactor Vessel of SNR-300 as Consequence of Unprotected Loss-of-Flow Transients in the MARK-IA-Core,” Proc. Int. Mtg. Fast Reactor Safety Technology, Seattle, Washington, August 19–23, 1979, Vol. II, p. 721, American Nuclear Society (1979).
  • H. VOSSEBRECKER and A. KELLNER, “Inherent Safety Characteristics of Loop-Type LMFBR’s,” Proc. Int. Mtg. Fast Reactor Safety Technology, Seattle, Washington, August 19–23, 1979, Vol. II, p. 554, American Nuclear Society (1979).
  • K.-J. BATHE, “ADINA, A Finite Element Programme for Automatic Dynamic Incremental Non-Linear Analysis,” Massachusetts Institute of Technology (Sep. 1975).

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