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Technical Paper

Development of a New Measurement Method for Fast Breeder Reactor Fuel Burnup Using a Shielded lon Microprobe Analyzer

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Pages 107-113 | Published online: 13 May 2017

References

  • “Standard Test Method for at. Vo Fission in U and Pu Fuel (Nd-148 Method),” Annual Book of ASTM Standards, E321-79, American Society for Testing and Materials (1982).
  • Y. ENOKIDO et al., “Development of a Shielded Ion Microprobe Analyzer (SIMA) and Its Application to Fast Reactor Fuel Element,” Nucl. Technol., 63, 164 (1983). Y. ENOKIDO et al., ‘‘Development of a Shielded Ion Microprobe Analyzer for Irradiated Fast Reactor Fuel and Material Examination, “ Secondary Ion Mass Spectrometry-SIMS IV, p. 147, Springer Verlag, Tokyo (1984).
  • B. F. RIDER and M. E. MEEK, “Compilation of Fission Product Yields,” NEDO-12154-2(D), Class 1, Valle-citos Nuclear Center (1977).
  • M. CONTE et al., “Study of the Thermal Behavior of LMFBR Fuel,” Proc. Int. Conf. FBR Fuel Performance, Monterey, California, p. 301 (1979).

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