References
- “Final Safety Analysis Report,” GAT/GDP-1073, Portsmouth Gaseous Diffusion Plant (May 1990).
- R. G. TAYLOR, “Criticality Safety Analysis of a Uranium Hexafluoride Freezer/Sublimer,” K/DD-1003, Oak Ridge Gaseous Diffusion Plant (1978 May).
- W. T. MEE, D. A. REED, and R. G. TAYLOR, “Consequences of a Postulated Moderated Criticality Accident at the Oak Ridge Y-12 Plant,” Y/DD-384, Oak Ridge Y-12 Plant (Sep. 1988).
- G. E. HANSEN, “Assembly of Fissionable Material in the Presence of a Weak Neutron Source,” Nucl. Sci. Eng., 8, 709 (Dec. 1960).
- H. I. DODDS and R. M. WESTFALL, “SKINATH — A Computer Program for Solving the Reactor Point Kinetics Equations with Simple Thermal Hydraulic Feedback,” ORNL/CSD/TM-210, Oak Ridge National Laboratory (Sep. 1984).
- D. J. MATHER and P. M. SHAW, “CRITEX-A Computer Program to Calculate Criticality Excursions in Fissile Liquid Systems,” SRD R 380, U.K. Atomic Energy Authority (July 1984).
- R. KATO, “The Code CREST to Simulate Criticality Accident Power Excursions in Fuel Solution,” Mitsubishi Atomic Power Industries.
- W. D. NEWMYER, “The Analysis of a Hypothetical Criticality Accident Involving Dry Highly-Enriched Uranium Powder,” MS Thesis, The University of Tennessee, Knoxville (Dec. 1991).
- B. BASOGLU, “Analysis of a Hypothetical Criticality Accident Involving Damp Low Enriched UO2 Powder,” MS Thesis, The University of Tennessee, Knoxville (Aug. 1992).
- R. W. BREWER, “Analysis of a Hypothetical Array Criticality Accident Involving Units of Aqueous Uranyl Fluoride,” MS Thesis, The University of Tennessee, Knoxville (May 1993).
- P. LECORCHE and R. L. SEALE, “A Review of the Experiments Performed to Determine the Radiological Consequences of a Criticality Accident,” Y-CDC-12, Oak Ridge Y-12 Plant (Nov. 1973).
- R. E. MALENFANT and H. M. FOREHAND, “Facility Description of a Solution Critical Assembly: SHEBA,” Trans. Am. Nucl. Soc., 39, 555 (1981).
- “Uranium Hexafluoride: A Manual of Good Handling Practices,” ORO-651 (Rev. 6), U.S. Department of Energy (Oct. 1991).
- “SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation,” NUREG/CR-0200, Vol. II, Sec. F3, U.S. Nuclear Regulatory Commission (Jan. 1990).
- A. F. HENRY, Nuclear-Reactor Analysis, The MIT Press, Cambridge, Massachusetts (1975).
- N. E. TODREAS and M. S. KAZIMI, Thermal Hydraulic Fundamentals, Hemisphere Publishing Corp., New York (1990).
- C. F. HAUGHT, “Analyses of Hypothetical Nuclear Criticality Excursions in a 10-MW and 20-MW Freezer/Sublimer,” MS Engineering Practice Project Report, The University of Tennessee, Knoxville (May 1993).
- J. P. HOLMAN, Heat Transfer, McGraw-Hill Book Company, New York (1986).
- R. C. BINDER, Fluid Mechanics, Prentice-Hall, Englewood Cliffs, New Jersey (1962).
- L. HARR, J. GALLAGER, and G. KELL, NBS/NRC Steam Tables, Thermodynamic and Transport Properties, and Computer Programs for Vapor and Liquid States of Water in SI Units, Hemisphere Publishing Corp., New York, and McGraw-Hill International Book Company, New York (1984).
- I. KATAOKA and M. ISHII, “Drift Flux Model for Large Diameter Pipe and New Correlation for Pool Void raction,” Int. J. Heat Mass Transfer, 30, 9, 1928 (1987).
- A. C. HINDMARSH, “LSODE and LSODI-Two New Initial Value Ordinary Differential Equation Solvers,” ACM-Signum Newsletter, 15, 4 (1980).
- M. R. LAMBERT, Martin Marietta Energy Systems, Personal Communication (Feb. 1993).
- J. H. CLINTON, Martin Marietta Energy Systems, Personal Communication (Jan. 1992).
- D. J. MATHER and P. M. SHAW, “Calculations of Critical Excursions in Fissile Liquid Solutions,” SRD-308, U.K. Atomic Energy Authority (July 1984).