References
- P. A. GNADT et al., “THORS-A High Temperature Sodium Test Facility Rated at 2.0 MW,” Proc. Int. Conf. Fast Reactor Safety Technology, Seattle, Washington, Vol. V, p. 2311 (Aug. 1979).
- P. A. GNADT et al., “Fuel Pin Simulators Tested in the THORS Facility,” Proc. Int. Symp. Fuel Rod Simulators-Development and Application, Gatlinburg, Tennessee, CONF-80191 (Oct. 1980).
- P. A. GNADT et al., “Sodium Boiling Experiments in the THORS Facility,” Nucl. Eng. Des. (to be published).
- M. H. FONTANA et al., “Temperature Distribution and Flow Mixing in a 19-Rod Simulated LMFBR Fuel Assembly,” Trans. Am. Nucl. Soc., 14, 2, 719 (1971).
- M. H. FONTANA et al., “Temperature Distribution in the Duct Wall and at the Exit of a 19-Rod Simulated LMFBR Fuel Assembly (FFM Bundle 2A),” Nucl. Technol., 24, 176 (1974).
- M. H. FONTANA et al., “Effect of Inlet Blockages in 19-Rod Simulated LMFBR Fuel Subassemblies,” Trans. Am. Nucl. Soc., 17, 345 (1973).
- J. T. HAN and M. H. FONTANA, “Blockages in LMFBR Fuel Assemblies,” Proc. Symp. Thermal and Hydraulic Aspects of Nuclear Reactor Safety, V.2: Liquid Metal Fast Breeder Reactors, American Society of Mechanical Engineers (1977).
- M. H. FONTANA et al., “Effect of Partial Blockages in Simulated LMFBR Fuel Assemblies,” Proc. ANS Topi.Mtg. Fast Reactor Safety, Los Angeles, California, CONF-740401-P3, p. 1139 (1974).
- A. E. LEVIN and J. L. WANTLAND, “Reproducibility of Data in Steady State Testing of Simulated LMFBR Fuel Assemblies,” Trans. Am. Nucl. Soc., 41, 706 (1982).
- J. F. DEARING, “Calculated vs Experimental Temperature Distribution Behind a Six-Channel Central Blockage,” Trans. Am. Nucl. Soc., 27, 566 (1977).
- J. T. HAN et al., “Thermal Hydraulic Correlations of a Six-Channel Blockage in a Sodium-Cooled Simulated LMFBR Fuel Assembly,” Proc. ANS Topl. Mtg. Fast Reactor Safety and Related Physics, Chicago, Illinois, CONF-761001, p. 1541 (1976).
- N. HANUS et al., “Quasi-Steady State Boiling Downstream of a Six-Channel Central Blockage in a 19-Rod Simulated LMFBR Subassembly,” Proc. ANS Topi.Mtg. Fast Reactor Safety and Related Physics, Chicago, Illinois, CONF-76001, p. 1550 (1976).
- J. F. DEARING et al., “A Comparison of COBRA III-C and SABRE-I (Wire-Wrap Version) Computational Results with Steady-State Data from a 19-Pin Internally Guard Heated Sodium-Cooled Bundle with a Six-Channel Central Blockage (THORS Bundle 3C),” Proc. Int. Conf. Fast Reactor Safety Technology, Seattle, Washington, Vol. IV, p. 1706 (1979).
- J. T. HAN et al., “Edge Blockages in 19-Pin Sodium-Cooled Bundles,” Trans. Am. Nucl. Soc., 26, 335 (1977).
- J. L. WANTLAND et al., “Flow-Controlled Coast-down Tests to Boiling in a Sodium-Cooled 19-Rod Bundle,” Trans. Am. Nucl. Soc., 21, 300 (1975).
- J. L. WANTLAND et al., “Dynamic Boiling Tests in a 19-Pin Simulated LMFBR Fuel Assembly,” Trans. Am. Nucl. Soc., 27, 567 (1977).
- J. L. WANTLAND et al., “Sodium Boiling Incoherence in a 19-Pin Wire-Wrapped Bundle,” Proc. Int. Conf. Fast Reactor Safety Technology, Seattle, Washington, Vol. IV, p. 1678 (1979).
- S. D. ROSE et al., “Experimental and Numerical Thermal-Hydraulic Results from a 61-Pin Simulated LMFBR Subassembly,” Trans. Am. Nucl. Soc., 34, 880 (1980).
- G. E. P. BOX, W. G. HUNTER and J. S. HUNTER, Statistics for Experimenters, John Wiley & Sons, New York (1978).