Reactor Design of the Advanced Neutron Source

References

• C. D. WEST, “Overview of the ANS Project,” Trans. Am. Nucl. Soc., 57, 288 (1988).
   Google Scholar
• C. D. WEST, “The Advanced Neutron Source Facility: A New User Facility for Neutron Research,” Proc. Topl. Mtg. Reactor Physics, Jackson, Wyoming, September 18–22, 1988, Vol. II, p. 155, American Nuclear Society (1988).
   Google Scholar
• J. A. LAKE, D. K. PARSONS, J. L. LIEBENTHAL, J. M. RYSKAMP, G. N. FILLMORE, and D. R. DEBOISBLANC, “Ultrahigh Flux Reactor Design—Probing the Limits of Plate Fuel Technology,” EGG-EA-7116, Idaho National Engineering Laboratory (1985); see also
   Google Scholar
  Nucl. Instrum. Methods, A249, 41 (1986).
   Google Scholar
• F. C. DIFILIPPO, W. R. GAMBILL, R. M. MOON, R. T. PRIMM III, and C. D. WEST, “A Preliminary Reactor Design for the Center for Neutron Research,” Nucl. Instrum. Methods, A249, 58 (1986).
   Google Scholar
• G. L. COPELAND, W. R. GAMBILL, R. M. HARRINGTON, J. A. JOHNSON, F. J. PERETZ, H. REUTLER, J. M. RYSKAMP, D. L. SELBY, C. D. WEST, and G. L. YODER, “Advanced Neutron Source Final Preconceptual Reference Core Design,” ORNL/TM-11234, Oak Ridge National Laboratory (1989).
   Google Scholar
• W. W. ENGLE, Jr., R. A. LILLIE, and C. O. SLATER, “Radiation Transport Calculations for the ANS Beam Tubes,” Trans. Am. Nucl. Soc., 57, 294 (1988).
   Google Scholar
• J. M. RYSKAMP, “Irradiation Capabilities of the Advanced Neutron Source,” Trans. Am. Nucl. Soc., 60, 207 (1989).
   Google Scholar
• E. H. HONEYCUTT, Jr., “Erosion of Aluminum,” DP-214, Du Pont de Nemours and Company (1957).
   Google Scholar
• V. H. RANSOM, J. A. TRAPP, G. W. JOHNSEN, C. S. MILLER, D. M. KISER, and R. A. RIEMKE, “RELAP5/MOD2 Code Manual,” NUREG/CR-4312, EGG-2396, Rev. 1, U.S. Nuclear Regulatory Commission (1987).
   Google Scholar
• C. D. FLETCHER and L. S. GHAN, “Analysis of Loss-of-Coolant Accidents in the Advanced Neutron Source,” EGG-EAST-8700, Idaho National Engineering Laboratory (1990).
   Google Scholar
• B. H. MONTGOMERY, R. E. PAWEL, and G. L. YODER, “Advanced Neutron Source Corrosion Test Loop Facility,” Trans. Am. Nucl. Soc., 57, 300 (1988).
   Google Scholar
• G. H. HANSON, G. W. GIBSON, J. C. GRIESS, N. E. PACE, R. E. PAWEL, and J. M. RYSKAMP, “Aluminum Cladding Corrosion Workshop Summary,” CONF-8811203, Oak Ridge National Laboratory (1989).
   Google Scholar
• J. C. GRIESS, H. C. SAVAGE, and J. L. ENGLISH, “Effect of Heat Flux on the Corrosion of Aluminum by Water, Part IV—Tests Relative to the Advanced Test Reactor and Correlation with Previous Results,” ORNL-3541, Oak Ridge National Laboratory (1964).
   Google Scholar
• J. M. RYSKAMP, E. L. REDMOND II, S. S. KIM, and C. D. FLETCHER, “Reactivity Studies on the Final Preconceptual Reference Design of the Advanced Neutron Source,” EGG-NE-8940, Idaho National Engineering Laboratory (1990).
   Google Scholar
• R. M. MOON, Ed., Proc. Workshop Instrumentation for the Advanced High-Flux Reactor, CONF-8405192, Oak Ridge National Laboratory (1984).
   Google Scholar
• “Safety of Department of Energy-Owned Nuclear Reactors,” DOE Order 5480.6, U.S. Department of Energy (Sep. 23, 1987).
   Google Scholar
• J. R. BUCHANAN, J. N. DUMONT, C. M. KENDRICK, T. H. ROW, P. B. THOMPSON, C. D. WEST, J. F. MARCHATERRE, and M. D. MUHLHEIM, “Report of the Advanced Neutron Source (ANS) Safety Workshop,” CONF-8810193, Oak Ridge National Laboratory (1988).
   Google Scholar
• R. A. GRIMESEY, D. W. NIGG, and R. L. CURTIS, “COMBINE/PC—A Portable ENDF/B Version 5 Neutron Spectrum and Cross-Section Generation Program,” EGG-2589, Idaho National Engineering Laboratory (1989).
   Google Scholar
• W. E. FORD III, B. R. DIGGS, L. M. PETRIE, C. C. WEBSTER, and R. M. WESTFALL, “CSRL-V: Processed ENDF/B-V 227-Neutron Group and Pointwise Cross-Section Libraries for Criticality Safety, Reactor and Shielding Studies,” NUREG/CR-2306, ORNL/CSD/TM-160, U.S. Nuclear Regulatory Commission (1982).
   Google Scholar
• N. M. GREENE and L. M. PETRIE, “XSDRNPM-S: A One-Dimensional Discrete-Ordinates Code for Transport Analysis,” SCALE, Book IV, NUREG/CR-0200, Vol. 2, Sec. F3, ORNL/NUREG/CSD-2/V2/R1, U.S. Nuclear Regulatory Commission (1983).
   Google Scholar
• R. T. PRIMM III, “Cross-Section Processing Methodology Used to Design the Advanced Neutron Source Reactor,” Trans. Am. Nucl. Soc., 57, 292 (1988).
   Google Scholar
• C. J. PFEIFER, “PDQ-7 Reference Manual II,” WAPD-TM-947(2), Westinghouse Atomic Power Division (1971).
   Google Scholar
• D. R. VONDY, T. B. FOWLER, and G. W. CUNNINGHAM III, “The Bold Venture Computation System for Nuclear Reactor Core Analysis, Version III,” ORNL-5711, Oak Ridge National Laboratory (1981).
   Google Scholar
• Y. Y. AZMY and F. C. DIFILIPPO, “Comparison of the Diffusion and Transport Calculations for the Advanced Neutron Source Reactor,” Proc. Topl. Mtg. Reactor Physics, Jackson, Wyoming, September 18–22, 1988, Vol. II, p. 183 (1988).
   Google Scholar
• J. M. RYSKAMP, F. C. DIFILIPPO, and R. T. PRIMM III, “Reactor Physics Methods for the Preconceptual Core Design of the Advanced Neutron Source,” Trans. Am. Nucl. Soc., 57, 290 (1988).
   Google Scholar
• E. L. REDMOND II and J. M. RYSKAMP, “Monte Carlo Methods, Models, and Applications for the Advanced Neutron Source,” Trans. Am. Nucl. Soc., 61, 377 (1990).
   Google Scholar
• E. L. REDMOND II, “Monte Carlo Methods, Models, and Applications for the Advanced Neutron Source,” Master’s Thesis, Massachusetts Institute of Technology (1990).
   Google Scholar
• J. F. BRIESMEISTER, Ed., “MCNP—A General Monte Carlo Code for Neutron and Photon Transport,” LA-7396-M, Rev. 2, Los Alamos National Laboratory (1986).
   Google Scholar
• J. A. McCLURE, “A Two-Dimensional, Time-Dependent Heat Conduction Program,” IDO-17227, Idaho National Engineering Laboratory (1967).
   Google Scholar
• M. L. GRIEBENOW and K. D. RICHERT, “MACA-BRE II,” IN-1107, Idaho National Engineering Laboratory (1967).
   Google Scholar
• H. A. McLAIN, “HFIR Fuel Element Steady State Heat Transfer Analysis, Revised Version,” ORNL/TM-1904, Oak Ridge National Laboratory (1967).
   Google Scholar
• W. R. GAMBILL, “Thermal-Hydraulic Constraints on Water-Cooled Research Reactor Performance,” Nucl. Instrum. Methods, A249, 53 (1986).
   Google Scholar
• W. R. GAMBILL and T. MOCHIZUKI, “Advanced Neutron Source Design: Burnout Heat Flux Correlation Development,” Trans. Am. Nucl. Soc., 57, 298 (1988).
   Google Scholar
• R. M. BRUGGER, Ed., Proc. Workshop Advanced Steady-State Neutron Facility, Gaithersburg, Maryland, December 16–18, 1985, published in Nucl. Instrum. Methods, A249 (1986).
   Google Scholar
• J. A. LAKE and C. D. WEST, “Report on the Working Group on ‘Critique of Source Concepts,’” Nucl. Instrum. Methods, A249, 125 (1986).
   Google Scholar
• J. M. RYSKAMP, D. K. PARSONS, and J. A. LAKE, “Ultrahigh Flux Double Donut Research Reactor Design,” Proc. Topl. Mtg. Reactor Physics and Safety, Saratoga Springs, New York, September 17–19, 1986, NUREG/CP-0080, Vol. 2, p. 780, U.S. Nuclear Regulatory Commission (1986).
   Google Scholar
• J. M. RYSKAMP, C. H. OH, R. G. AMBROSEK, W. G. LUSSIE, J. A. LAKE, and R. P. WADKINS, “Parameter Trade-Off Studies for the Ultrahigh Flux Double Donut Reactor,” Trans. Am. Nucl. Soc., 55, 612 (1987).
   Google Scholar
• J. A. LAKE, R. L. HEATH, J. L. LIEBENTHAL, D. R. DEBOISBLANC, C. F. LEYSE, D. K. PARSONS, J. M. RYSKAMP, R. P. WADKINS, Y. D. HARKER, G. N. FILLMORE, and C. H. OH, “High Flux Reactor,” U.S. Patent 4764339 (1988).
   Google Scholar
• F. C. DIFILIPPO, W. R. GAMBILL, R. M. MOON, R. T. PRIMM III, and C. D. WEST, “An Intense Steady State Neutron Source—The CNR Reactor,” Proc. Topl. Mtg. Reactor Physics and Safety, Saratoga Springs, New York, September 17–19, 1986, NUREG/CP-0080, Vol. 2, p. 792, U.S. Nuclear Regulatory Commission (1986).
   Google Scholar
• F. C. DIFILIPPO, “Designing CNR, A Very High Thermal Neutron Flux Facility,” Proc. Topl. Mtg. Reactor Physics and Safety, Saratoga Springs, New York, September 17–19, 1986, NUREG/CP-0080, Vol. 2, p. 810, U.S. Nuclear Regulatory Commission (1986).
   Google Scholar
• J. M. RYSKAMP, C. H. OH, J. A. LAKE, W. G. LUSSIE, and R. P. WADKINS, “Comparison of Single and Split Core Concepts for the Advanced Neutron Source,” EGG-NERD-8131, Idaho National Engineering Laboratory (1988) (full report); see also
   Google Scholar
  Proc. Topl. Mtg. Reactor Physics, Jackson, Wyoming, September 18–22, 1988, Vol. II, p. 173 (1988).
   Google Scholar
• D. L. SELBY, R. M. HARRINGTON, and F. J. PERETZ, “Advanced Neutron Source (ANS) Project Annual Report April 1987–March 1988,” ORNL/TM-10860, Oak Ridge National Laboratory (1989).
   Google Scholar
• RIZWAN-UDDIN and J. J. DORNING, “Thermal-Hydraulic Mixing in the Split-Core ANS Reactor Design,” Trans. Am. Nucl. Soc., 57, 301 (1988).
   Google Scholar
• C. H. OH, B. J. MERRILL, and R. P. WADKINS, “Flow Distribution Analysis on the Advanced Neutron Source,” Am. Instrum. Chem. Eng. Heat Transfer Symp. 269, 85, 436 (1989).
   Google Scholar
• R. T. PRIMM III, “Reactor Physics Studies of Various Advanced Neutron Source Reactor Core Configurations,” Trans. Am. Nucl. Soc., 59, 346 (1989).
   Google Scholar