JOURNALS
Ruggles, A.E., Scarton, H.A., and Lahey, R.T., Jr., "An Investigation of Pressure Perturbations in Two-Phase Flows."Journal of Heat Transfer, Vol. 110, No. 2, pp. 494-499, 1988.
Ruggles, A.E., Drew, D.A., Lahey, R.T., Jr., and Scarton, H.A., "The Relationship Between Standing Waves, Pressure Pulse Propagation and the Critical Flow Rate in Two-Phase Mixtures." Journal of Heat Transfer, Vol. 111, No. 2, pp. 467-473, 1989.
Plaster, M.J., Basoglu, B., Bentley, C.L., Dunn, M.E., Ruggles, A.E., Wilkinson, A.D., Yamamoto, T., Dodds, H. L.,"Analysis of a Hypothetical Criticality Accident in a Waste Supercompacter.”Nuclear Technology, Vol. III, No. 2, August 1995.
Radcliff, T.D., Parsons, R.J., Johnson, S.W., and Ruggles, A.E.,"Use of Transport Delay to Avoid Compensatory Effects in Sonic Orifice-Based Gas Concentration Probes.” Review of Scientific Instruments, Vol. 67, No. 8, pp. 2837-2842, 1996.
Ruggles, A.E., Vasiliev, A.D., Brown, N.W., Wendel, M.W.,"Role of Heater Thermal Response in Reactor Thermal Limits During Oscillatory Two-Phase Flows.” Nuclear Science and Engineering, Vol. 125, No. 1, pp 75-83, 1997.
Ruggles, A.E., McDuffee, J.L., "Local Pressure Gradients Due to Incipience of Boiling in Subcooled Flows.” Nuclear Science and Engineering, Vol. 125, No. 2, pp. 232-242, 1997.
Meftah, K. and Ruggles, A. E., "Vapor Volume Fraction, Flow Regime, and Vapor Velocity Inference Using Fluid Conductivity Measurements." Review of Scientific Instruments, Vol. 69, No. 8, pp. 2948-2954, 1998.
Patent #5792362, “Method and Apparatus for Cleaning Swimming Pools.” Issued August 11, 1998.
Radcliff, T.D., Parsons, R.J., Ruggles, A.E., and Johnson, S.W.,"Experimental and Hybrid Computational Fluid Dynamic (CFD) - Stochastic Determination of In-Reactor Boron Transport.” Nuclear Science and Engineering, Vol. 131, pp. 426-438, March 1999.
Crye, J. M., Ruggles, A. E., Pointer W. D., Felde, D. K., Jallouk, P. A., McFee, M. T., Rendel, M. W., and Yoder, G. L., "Measurement of the Heat Transfer Coefficient for Mercury Flowing in a Narrow Channel." Journal of Heat Transfer, Vol. 124, No. 6, pp. 1034-1038, December 2002.
Pointer, W. D., and Ruggles, A. E., "An Approach for Selection of Flow
Regime and Models for Conservative Evaluation of a Vessel Integrity Monitoring
System for Water Cooled Vacuum Vessels." Nuclear Technology, Vol. 141,
No. 2, pp. 2002-2010, Feb., 2003.
BOOK CONTRIBUTIONS
Ruggles, A.E., Lahey, R.T. Jr., and Drew, D.A.,"Void Wave Propagation in Bubbly Flows.” Included in Multiphase Transport and Particulate Phenomena, edited by Nejat Veziroglu, Hemisphere, 1990.
Ruggles, A. E., “Conditions for Small Channel Effects in Subcooled Boiling Flows”. Convective Flow and Pool Boiling, Taylor and Francis, Edited by M. Lehner and F. Mayinger, 1999
REFEREED CONFERENCE PAPERS AND REPORTS
Ruggles, A. E., "The Propagation of Pressure Perturbations in Two-Phase Flows.” PhD Dissertation, Rensselaer Polytechnic Institute, May 1987.
Lahey, R.T., Jr., and Ruggles, A.E.,"The Dispersion and Attenuation of Small Amplitude Standing Waves and the Propagation of Acoustic Pressure Pulses in Bubbly Air/Water Two-Phase Mixtures.” Physical Benchmark, DOE/EPRI Second International Workshop of Two-Phase Flow Fundamentals, Rensselaer Polytechnic Institute, Troy, NY, March 1987.
Ruggles, A. E., and Lahey, R. T., Jr.,"An Analysis of Void Wave Propagation in Bubbly Flows.” Session on Multi-Phase Flow Instabilities, 5th Miami International Symposium on Multiphase Transport and Particulate Phenomena, Miami Beach, Florida, December 12-14, 1988.
Morris, D.G., Wendel, M.W., Chen, N.C.J., Ruggles, A.E., and Cook, D.H., "Thermal-Hydraulic Simulation of Natural Convection Decay Heat Removal in the High Flux Isotope Reactor Using RELAP5 and TEMPEST, Part 1: Models and Simulation Results.” RELAP5 User Seminar, College Station, TX, January 31-February 2, 1989.
Ruggles, A.E., and Morris, D.G.,"Thermal-Hydraulic Simulation of Natural Convection Decay Heat Removal in the High Flux Isotope Reactor Using RELAP5 and TEMPEST, Part 2: Interpretation and Validation of Results.” RELAP5 User Seminar, College Station, TX, January 31-February 2, 1989.
Ruggles, A.E.,"Flow Excursion Considerations in the Advanced Neutron Source and High Flux Isotope Reactor.” Proc. ANS Workshop on Safety of Uranium-Aluminum Fueled Reactors, Idaho Falls, Idaho, March 14-16, 1989.
Ruggles, A.E., and Williams, P.T.,"RELAP5-MOD2 Benchmarking Study: Critical Heat Flux Under Low Flow Conditions.” Proc. ANS Annual Meeting, Nashville TN, June 10-14, 1990. Full documentation as calculation to support Safety Analysis Report for the High Flux Isotope Reactor, Calculation ID: C-HFIR-92-026, ORNL, August 31, 1992.
Morris, D.G., Ruggles, A.E., and Wendel, M.W.,"Thermal-Hydraulic Analysis of the High Flux Isotope Reactor.” Proc. ANS Annual Meeting, Nashville, TN, June 10-14, 1990.
Fletcher, C.D., Ruggles, A.E., and Chen, N.C.J.,"Advanced Neutron Source System Modeling Using RELAP5.” Proc. ANS Annual Meeting, Nashville, TN, June 10-14, 1990.
Ruggles, A.E.,"Applicability of RELAP5 to Water-Cooled Research Reactor Designs.” Proc. ANS Annual Meeting, Nashville, TN, June 10-14, 1990.
Ruggles, A.E., "Countercurrent Flow in Systems of Parallel Narrow Rectangular Channels.” Proc. of Advances in Gas-Liquid Flows, pp. 243-250, ASME Winter Annual Meeting, Dallas, TX, November 25-30, 1990.
Ruggles, A.E., "Countercurrent Flow Limited (CCFL) Heat Flux in the High Flux Isotope Reactor (HFIR) Fuel Element.” ORNL/TM -11638, 1990.
Bentley, C.B., and Ruggles, A.E., "Phase Distribution Measurements in Narrow Rectangular Channels Using Image Processing Techniques.” Proc. of Experimental Techniques in Multiphase Flows, ASME Winter Annual Meeting, Atlanta, GA, December 1-6, 1991.Also ORNL/TM-12011, 1991.
Siman-Tov, M., Gambill, W.R., Nelson, W.R., Ruggles, A.E., and Yoder, G.L., "Thermal-Hydraulic Correlations for the Advanced Neutron Source Reactor Fuel Element Design and Analysis.” Proc. of Symposium on Nuclear Reactor Thermal-Hydraulics-II, ASME Winter Annual Meeting, Atlanta, GA, December 1-6, 1991.
G L. Yoder, et al., "Steady State Thermal-Hydraulic Design Analysis of the Advanced Neutron Source Reactor." ORNL/TM-12398, May 1994.
Ruggles, A.E., Griffith, P., Dimenna, R.A., Wilson, G. and Cheng, L.Y.,"Phenomena Identification and Ranking for the Advanced Neutron Source Reactor during Large Break Loss of Coolant Accidents.” ORNL/TM-12496, 1994.
Plaster, M.J., Basoglu, B., Bentley, C.L., Dunn, M.E., Ruggles, A.E., Wilkinson, A.E., Yamamoto, T., and Dodds, H. L.,"Analysis of a Hypothetical Criticality Accident in a Waste Supercompacter.” Transactions of the American Nuclear Society, pp. 189-191, June 1994.
Bentley, C.L., Basoglu, B., Dunn, M.E., Ruggles, A.E., Wilkinson, A.E., Yamamoto, T., and Dodds, H.L.,"Shutdown Mechanisms for a Hypothetical Criticality Accident Involving HEU Powder.”Transactions of the American Nuclear Society, pp. 188-189, June 1994.
Siman-Tov, M., Felde D.K., Farquharson, G., Kaminaga, M., McDuffee, J.L., McFee, M.T., Robinson, J.J., Ruggles, A. E., Wendel, M.W., and Yoder, G.L., "FY 1993 Progress Report on the Advanced Neutron Source Thermal-Hydraulic Test Loop Operation and Results.” ORNL/ANS/INT-52, 1994.
McDuffee, J. and Ruggles, A.E.,"Prediction of the Local Pressure Gradient in Partially Developed Subcooled Boiling.” Fourth ASME/JSME Joint Thermal Engineering Conference, Maui, March 1995.
Vasiliev, A. and Ruggles, A.E.,"Sensitivity Studies of Reactor Thermal Limits During Two-Phase Natural Circulation Conditions.” ICONE-3, Kyoto, Japan, April 23-27, 1995.
Ruggles, A.E., McDuffee, J.L.,"Local Pressure Gradients Due to Incipience of Boiling in Subcooled Flows.” NUREG/CP-0142, Vol 1, pp.131-140, NURETH7, Saratoga, NY, September 10-15, 1995.
Ruggles, A.E., Vasiliev, A.D., Brown, N.W., Wendel, M.W.,"Role of Heater Thermal Response in Reactor Thermal Limits During Oscillatory Two-Phase Flows.”NUREG/CP-0142, Vol IV, pp. 2470-2479, NURETH7, Saratoga, NY, September 10-15, 1995.
Lemure, N., Olvera, J.R., Ruggles, A.E., "Bulk Temperature Measurement in Thermally Striped Pipe Flows.” NUREG/GR-0015, November 1995.
Ruggles, A. E., “Conditions for Small Channel Effects in Subcooled Boiling Flows”. Engineering Foundation Convective Flow and Pool Boiling Conference, Kloister Irsee, Germany, May 18-23, 1997.
Gulec, K. and Ruggles, A.E.,"Stability of a Liquid Lithium Jet over a Concave Surface.” Fourth World Conference on Experimental Heat Transfer, Fluid Mechanics, and Thermodynamics, Vol. III, pp. 1823-1828, Brussels, June 2-6, 1997.
Ruggles, A.E., "Thermal-Hydraulic Considerations for Flux Perturbations due to Fuel Manufacturing Tolerances in Plate Fueled Research Reactors.” NURETH-8, Vol. III, pp. 1823-1830, Kyoto, Sept. 30-Oct. 4, 1997.
Meftah, K., and Ruggles, A.E., “A Low Pressure Scale Model Boiling Water Reactor with Simulated Void-Reactivity Feedback.” NURETH-8, Vol. 1, pp. 405-412, Kyoto, Sept. 30-Oct. 4, 1997.
Meftah, K., and Ruggles, A.E., “Design and Construction of a Scaled Model Boiling Water Reactor Training Facility". Annual ASEE/GSW Conference, New Orleans, February 23-27, 1998.
W. David Pointer and Arthur E. Ruggles, “Preliminary Performance Evaluation of a Vessel Integrity Monitoring System for Water Cooled Vacuum Vessels in Cold Neutron Source Applications”. 6th International Conference on Nuclear Engineering, May 10-15, 1998.
Harvill, R., Ruggles, A. E., Taleyarkhan, R. P., and Kim, S., “Thermoacoustic Waves in Liquid Metal Targets for a High Power Spallation Neutron Source.” Second International Topical Meeting on Nuclear Applications of Accelerator Technology, American Nuclear Society, Gatlinburg, TN, September 20-23, 1998.
Pointer, D., Ruggles, A. E., Chae, S. M., Cox, D. F., Crye, J. M., Felde, D. K., Jallouk, P. A., “Characterization of Flow Patterns in the Nominal SNS Mercury Target through Flow Experiments in the Water Thermal Hydraulic Loop (WTHL).” SNS/TSR-194, May 2000.
Pointer, D., Ruggles, A. E., Felde, D. K., Chae, S. M., Cox, D. F., Crye, J. M., Jallouk, P. A., “Summary of Water Thermal Hydraulic Loop Experiments for Characterization of Flow Behavior in the SNS Mercury Target.” SNS/TSR-205, September, 2000.
Crye, J. M., Felde, D. K., Wendel, M., Yoder, G. L., Carbajo, J., Farquharson, G., Jallouk, P. A., McFee, M. T., Pointer, W. D., Ruggles, A. E., “Mercury Thermal Hydraulic Loop Electrically-Heated (Straight) Test Section Report.” SNS/TSR-200, August, 2000.
Pointer, D., Ruggles, A. E., Wendel, M., and Crye, J., “Investigation of Flow Asymmetry and Instability in the Liquid Mercury Target of the Spallation Neutron Source.” American Nuclear Society Summer Meeting, San Diego, CA, 2000.
Pointer, W. D., Crye, J. M., Wendel, M. W., Ruggles, A. E., Felde, D. K., Haines, J., Jallouk, P. A., Yoder, G. L., “Scaled Experiments and CFD Simulations Supporting the Design of the Spallation Neutron Source Mercury Target.” 2000 Mechanical Engineering Congress and Exposition, Orlando, FL, November 5-10, 2000.
Ruggles, A. E., and Alvord, C. W., “Thermal Performance of CTI, Inc. Enriched Water Targets.” 16th International Conference on the Application of Accelerators in Research and Industry (CAARI 2000), Denton, TX, November 1-4, 2000.
Lopez, M. and Ruggles, A. E., "Onset of Vapor Generation in Small Channels at Low Reynolds Number." Heat Transfer and Transport Phenomena in Microsystems, United Engineering Foundation Conference, Banff, Alberta, Canada, October 15-20, 2000.
Sawyer, A., Williamson, M., Zhau, K., and Ruggles, A. E., "RELAP5-3D Validation Study using MB-3 Prototypical Steam Generator Steady State Data." RELAP5 International Users Seminar, August 27-29, 2003, West Yellowstone, Montana.
Sawyer, A. Ruggles, A. E., Upadhyaya, B. R., Eryurek, E.,Kavaklioglu, K and Miller, J., "Development of a Data-Based Method for Performance Monitoring of Heat Exchangers." Heat Exchanger Fouling and Cleaning, ECI Conference, May 18-22, 2003, Santa Fe, New Mexico.
A. Sawyer, A. E. Ruggles, "Modeling Methods for Condenser Performance
Analysis." Proceedings of the Maintenance and Reliability Conference, MARCON
2003, Knoxville, TN, May 4-7, 2003.