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Technical Paper

Neutronic Space-Time Effects with Thermal-Hydraulic Feedback in Large Homogeneous and Heterogeneous Liquid-Metal Fast Breeder Reactors

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Pages 370-382 | Published online: 12 May 2017

References

  • W. M. STACEY, Jr., “Space- and Energy-Dependent Neutronics in Reactor Transient Analysis,” React. Technol., 14, 2, 169 (1971).
  • R. A. SHOBER, T. A. DALY, and D. R. FERGUSON, “FX2-TH, A Two-Dimensional Nuclear Reactor, Kinetics Code with Thermal-Hydraulic Feedback,” ANL-78-97, Argonne National Laboratory (1978).
  • D. A. MENELY et al., “A Kinetics Model for Fast Reactor Analysis in Two Dimensions,” in Dynamics of Nuclear Systems, p. 483, The University of Arizona Press, Tucson, Arizona (1972).
  • D. C. WADE and R. A. RYDIN, “An Experimentally Measurable Relationship Between Asymptotic Flux Tilts and Eigenvalue Separation,” Symp. Dynamics of Nuclear Systems, Tucson, Arizona, 1970, University of Arizona Press, Tucson, Arizona (1970).
  • “Preliminary Safety Analysis Report: Clinch River Reactor Project,” Project Management Corporation.
  • R. J. HENNINGER et al., “An Analysis of Unprotected Loss-of-Flow Accidents for the CRBRP with a Radial Parfait Core,” Trans. Am. Nucl. Soc., 24, 260 (1976).

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