Publications
J. Williams and L.E. Hochreiter, 2003, Large-Breal LOCA analysis Using Coupled COBRA-TF - RELAP5 3D Best-Estimate Computer Code Package- Simulation of the LOFT L2-5 Experiment (Draft), Submitted to Bettis Atomic Power Laboratory, Dec 2003.
L.E. Hochreiter, E.R. Rosal and J.S. Kaizer, 2003, Conceptual Design of a Laminar-to-Turbulent Flow Heat Transfer Experiment, Prepared for the Bettis Atomic Power Laboratory, June 2003.
R.L. Campbell, J.M. Cimbala, and L.E. Hochreiter, 2003, CFD Prediction of Grid Spacer Hydraulic Performance with Comparisons to Experimental Results, Submitted to ANS Nuclear Technology.
L.L. Pauley, R.E. Edwards and L.E. Hochreiter, 2003, The Nuclear Engineering and Mechanical Engineering Multiple Major Program at the Pennsylvania State University, American Society of Engineering Education, June 2003, meeting.
C. Frepoli, J.H. Mahaffy, and L.E. Hochreiter, 2003, A Moving Subgrid Model For Simulation of Reflood Heat Transfer, Nuclewar Engineering and Design, Vol 224, pg 131-148, (2003).
J.E. Chang, L.E. Hochreiter, T.F. Miller, and C.F. Sears, 2003, Numerical Simulation of the Pennsylvania State University Breazeale Nuclear Reactor (PSBR) during Steady-State Operation, Trnas. ANS, Vol 89, Pg 344-345, Nov 2003.
M.J. Holowach, L.E. Hochreiter, J.H. Mahaffy, F.B. Cheung, 2003, A Model for Predicting Droplet Entrainment at a Quench Front in Thermal Hydraulics Codes, Presented at ASME International Mechanical Engineering Congress and Exposition, Nov 20, 2003.
L.E. Hochreiter, F.B. Cheung, 2002, US NRC - PSU Rod Bundle Heat Transfer ProgramTransactions of the 2002 Nuclear Safety Research Conference, Washington, D.C. October 2002, NUREG/CP-0178, pp 39.
M.J. Holowach, L.E. Hochreiter, J.H. Mahaffy, F.B. Cheung, 2003, Modeling of Droplet Phenomena at a Quench Front, International Journal of Heat and Fluid Flow, Vol 24, Number 6, December 2003.
E.R. Rosal, T.F. Lin, I.S. McClellan, L.E. Hochreiter, F.B. Cheung, 2003, The Pennsylvania State University and US Nuclear Regulatory Commission Rod Bundle Heat Transfer Facility, The 6th ASME/JSME Joint Thermal Engineering Conference, Paper No. TED-AJ03-625, March 16-20, 2003.
A.J. Ireland, L.E. Hochreiter, F.B. Cheung, 2003, Droplet Size and Velocity Measurements in a Heated BundleThe 6th ASME/JSME Joint Thermal Engineering Conference, Paper No. TED-AJ03-624, March 16-20, 2003.
A. Sirdharan, L.E. Hochreiter, F.B. Cheung, 2003, The Behavior of Inverted Flow Film Boiling During the Reflood ProcessThe 6th ASME/JSME Joint Thermal Engineering Conference, Paper No. TED-AJ03-623, March 16-20, 2003.
M.J. Holowach, L.E. Hochreiter, F.B. Cheung, D.L.Aumiller, R.J. Houser, 2003, Scaling of Quench front and Entrainment-related PhenomenaNuclear Engineering and Design, Volume 223, Pgs 197-209 (2003).
M.J. Holowach, L.E. Hochreiter. F.B. Cheung, D.L. Aumiller, 2002, "Critical Heat Flux During Reflood Transient in Small Hydraulic Diameter Geometries", Nuclear Technology, Vol 140, No 1, pp 18-27, October 2002.
M.J. Holowach, L.E. Hochreiter, F.B. Cheung, 2002, A Model for Droplets Entrainment in Heated Annular Flow, International Journal of Heat and Fluid Flow, Vol 23, pp 807-822, December 2002.
M.J. Holowach, L.E. Hochreiter, F.B. Cheung, 2002, Improved Flow Modeling in Transient Reactor Safety Analysis Computer Codes, Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10), Paper No. ICONE 10 - 22651, April 2002.
M.J. Holowach, L.E. Hochreiter, F.B. Cheung, 2002", A Physical Model for Predicting Annular Film Flow Droplet Entrainment in Heat Transfer Systems", Proceedings of 2002 IMECE, Session NE-1, New Orleans, LA, November 2002.
R.K. Ratnayake, L.E. Hochreiter, J.M. Cimbala, K.N. Ivanov, 2002, Experimental Study of Two-Phase Flow behavior Past BWR Spacer Grids, Proeedings of 10th International Conference on Nuclear Engineering (ICONE 10), Paper ICONE 10 - 22198, April 2002.
R. K. Ratnayake, L.E. Hochreiter, S. Ergun, A.J. Baratta, 2002, Identification and Ranking of Phenomena Leading to Peak Cladding Temperatures in Boiling Water Reactors during Large-Break Loss of Coolant Accident transients, Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10), Paper No. ICONE 10 - 22288, April 2002.
C. Frepoli, J.M. Mahaffy, L.E. Hochreiter, 2002, "A Moving Subgrid Model for Simulation of Reflood Heat Transfer", Proceedings of the 10th International conference on Nuclear Engineering (ICONE 10), Paper No. ICONE 10 - 22774, April 2002.
B.J. Heidrich, L.E. Hochreiter, C.F. Sears, 2002, "Improvements to the Penn State TRIGA Reactor Thermal Power Calibration", American Nuclear Society Transactions, Vol 87, pp 200-201, November 2002.
M.N. Avramova, K.N. Ivanov, L.E. Hochreiter, S. Balzus, R. Mueller, 2002, Comparative Analysis of PWR Core Wide and Hot Channel Calculations, American Nuclear society Transactions, Vol 87, pp 208-210 November 2002.
K.N. Ivaonv, L.E. Hochreiter, B.Beebe, E. Jackson, L.Mayhue, J. Prichett, D. Robinson, R. Wiley, 2002, Innovations in Nuclear Engineering Education Through Improved University/Industry Partnership, American Nuclear Society Transactions, Vol 87, pp 261-262, November 2002.
J. Sinha, L.E. Hochreiter, F.B. Cheung, 2002, "Effects of Surface Roughness, Oxidation and Liquid Subcooling on the Minimum Film Boiling Temperature", Accepted for publication in Experimental Heat Transfer, Vol 16.
M.J. Holowach, L.E. Hochreiter, F.B. Cheung, D.L.Aumiller, R.J. Houser, 2002, "Scaling of Quench Front and Entrainment-Related Phenomena", Accepted for publication in Nuclear Engineering and Design.
A. Sirdharan, L.E. Hochreiter, F.B. Cheung, 2002, "The Behavior of Inverted Flow Film Boiling During the Reflood Process", Accepted for Presentation and Publication at the 6th ASME/JSME Joint Thermal Engineering Conference, Paper No. TED-AJ03-623, September 2002.
A.J. Ireland, L.E. Hochreiter, F.B. Cheung, 2002, "Droplet Size and Velocity Measurements in a Heated Rod Bundle", Accepted for Publication and Presentation at the 6th ASME/JSME Joint Thermal Engineering Conference, Paper No. TED-AJ03-624, September 2002.
E.R. Rosal, T.F. Lin, I.S. McClellan, L.E. Hochreiter, F.B. Cheung, 2002, "The Pennsylvania State University and U.E. Nucleawr Regulatory Commission Rod Bundle Heat Transfer Facility", Accepted for Publication and Presentation at the 6th ASME/JSME Joint Thermal Engineering Conference, Paper No. TED-AJ03-625, September 2002.
R. Maccan, J.H. Mahaffy, G.E. Robinson, S.M. Bajorek, L.E. Hochreiter, L.C. Smith, 2002, "Modelling the LOCA and Post-LOCA Steam Generator Heat Release with COBRA/TRAC", Accepted for publication in Journal of Nuclear Technology.
C.D. Fago, L.E. Hochreiter, G.E. Robinson, 2002, "Numerical simulation of the AP600 Core Make-up Tank Mixing and Draining Under Natural Circulation using FLOW3D", Accepted for publication in Nuclear Engineering and Design.
L.E. Hochreiter, J.P. Cunningham, R.F. Wright, 2002, "Analysis of the AP600 Core Makeup Tank Data", Accepted with revisions by Journal of Nuclear Technology.
L.E. Hochreiter, D.S.Aumiller, 2002, "Scaling Analysis of the AP600 Core Makeup Tank Experiments", Accepted with revisions by Nuclear Engineering and Design.
L.E. Hochreiter, A. Sridharan, C. Frepoli, 2002, "Application of the Two-Tier Scaling Methodology to the PSU/NRC Rod Bundle Heat Transfer Test Facility", Accepted for publication with revisions by Nuclear Engineering and Design.
D.C. Garner, L.E. Hochreiter, R.M. Kemper, 2002, "Analysis of the AP600 Long Term Cooling Transient using WCOBRA/TRAC", To be submitted to Nuclear Engineering and Design.
L.E. Hochreiter, F.E. Peters, D.L. Paulson, E.J. Piplica, 2002, "Analysis of the AP600 Passive Residual Heat Removal Heat Exchanger Test Data", To be submitted to Nuclear Engineering and Design.
M.J. Holowach, L.E. Hochreiter, J.H. Mahaffy, F.B. Cheung, 2002, "A Model for Predicting Droplet Entrainemnt at a Quench Front in Thermal-Hydraulic Analysis Codes"To be Submitted to 2003 IMECE.
M.J. Holowach, L.E. Hochreiter, J.H. Mahaffy, F.B. Cheung, 2002, "Modeling of Droplet Entrainment at a Quench Front", To be Submitted to International Journal of Heat and Fluid Flow.
L.E. Hochreiter, F.B. cheung, 2002, "U.S. NRC - PSU Rod Bundle Heat Transfer Program", Transactions of the 2002 Nucleawr Safety Research Conference, Washington, D.C. October 2002, NUREG/CP-0178, pp 39.
S.M. Cetiner, L.E. Hochreiter, 2002, "Low Pressure Integral Test Facility", Penn State UNiversity Radiation Science and Engineering Center, 47th Annual Progress Report, pp 34 - 45, December 2002.
J.E. Chang, L.E. Hochreiter, T.F. Miller, 2002, "Thermal-Hydraulic Behavior of the Penn State Breazeale Rreactor", Penn State University Radiation Science and Engineering Center, 47th Annual Progress Report, pp 73 - 82, December 2002.
B.J. Heidrich, L.E. Hochreiter, C.F. Sears, 2002, "Improvements to the Thermal Power Calibration of the Penn State Breazeale Reactor", Penn State University Radiation Science and Engineering Center, 47th annual Progress Report, pp 86 - 91, December 2002.
M.J. Holowach, L.E. Hochreiter, F.B. Cheung, A.J. Ireland, 2002, Scaling Study for the Penn State Small Hydraulic Diameter Entrainment Facility, Internal report submitted to Bettis Atomic Power Laboratory, Jan 2002.
M.J. Holowach, S.Ergun, L.E. Hochreiter, F.B. Cheung, 2002, Implementation of the RESTART capability in the Modular Memory Version of COBRA/TFInternal report submitted to Bettis Atomic Power Laboratory, May, 2002.
M.J. Holowach, L.E. Hochreiter, F.B. Cheung, 2002, Study of Laminar Forced and Natural Convection Heat Transfer in Smooth Vertical Ducts over a Range of Hydraulic DiametersInternal report prepared for Bettis Atomic Power Laboratory, March 2002.
Holowach, M.J., Hochreiter, L.E., Cheung, F-B, and D. Aumiller, “Critical heat Flux During Reflood Transients in Small Hydraulic Diameter Duct”, Presented at the 2001 ASME IMECE Conference, New York, New York, November 2001.
Sinha, J., Hochreiter, L.E., and F-B Cheung, “Effect of Subcooling on the Quenching of Simulated Nuclear Fuel Rod”, Presented at the 2001 ASME IMECE Conference New York, New York, November 2001.
Ireland, A.J., Rosal, E.R., Hochreiter, L.E., and F-B Cheung, “Experimental Verification of the Performance of a Droplet Injection System for use in a Rod Bundle Test Facility”, Presented at the 2001 ASME IMECE Conference, New York, New York, November 2001.
Frepoli, C., Ireland, A.J., Hochreiter, L.E., F-B Cheung, “RBHT Steam cooling and Droplet Injection Pre-Test Analysis using COBRA-TF”, Presented at the 2001 ASME IMECE Conference, New York, New York, November 2001.
Frepoli, C., Ireland, A.J., Hochreiter, L.E., Ivanov, K., and R. Velten, “COBRA-TF Simulation of BWR Dryout Experiments”, Presented at the International Conference on Nuclear Engineering, ICONE 9, Nice, France, and April 2001.
Frepoli, C., Hochreiter, L.E., Ireland, A.J., and K. Ivanov, “Modeling of Annular Film Dryout with COBRA-TF”, Presented at the International Conference on Nuclear Engineering, ICONE 9, Nice, France, April 2001.
Frepoli, C. Hochreiter, L.E. , Mahaffy, J. H. and Cheung, F-B, “A Noding Sensitivity using COBRA-TF and the Effects of Spacer Grids During Reflood” , International Conference on Nuclear Engineering, ICONE –8, Baltimore, MD April 2000.
Wang, G, and L.E. Hochreiter, “Natural Circulation Behavior analysis of the Penn State Low Pressure Integral Test Facility”, International Conference on Nuclear Engineering, ICONE-8, Baltimore, MD, April, 2000.
Wang, G. Mahaffy, J.M., and L.E. Hochreiter, “Investigation of BWR LOCA Behavior using the USNRC Consolidated Code”, International Meeting on “Best-Estimate “ Methods in Nuclear Installations Safety Analysis (BE-2000), Sponsored by American Nuclear Society, Nov 2000.
Hochreiter, L.E. “Best-Estimate Methods Licensing Procedure: Simplification or Complication ? “ , Invited paper, International Meeting on “Best-Estimate” Methods in Nuclear Installations Safety Analysis (BE-2000), Sponsored by American Nuclear Society, Nov 2000.
Bajorek, S.M., Yeh, H.C., MacName, K. and L.E. Hochreiter, “Two-Phase, Three-Dimensional Thermal-Hydraulic Analysis of a Waste Heat Boiler”. Proceedings of the 34 th National Heat Transfer Conference, Pittsburgh, PA.
Solis-Rodarte, J. , Ivanov, K., Baratta, A., Hochreiter, L.E., and C. Frepoli, “Parallel Coupling Methodology for Evaluation of Local Safety Parameters in a BWR”, PHYSOR 2000 Conference, Pittsburgh, PA, May 2000.
Ziabletsev, D., Ivanov, K., Baratta, A., Hochreiter, L.E., and C. Frepoli, “Multi-Level Coupled Methodology for Local Evaluation of Safety Parameters in PWRs”, PHYSOR 2000 Conference, Pittsburgh, PA, May 2000.
T.M. Beam, L.E. Hochreiter, A.J. Baratta, and K. Ivanov. Best-Estimate Simulation of AP600 Rod Ejection Transient at Natural Circulation and Hot Zero Power, Post-SMIRT 14 Seminar, Passive Safety Features in Nuclear Installations, Pisa, Italy, (1997).
J. Zhang, S.M. Bajorek, R.M. Kemper, and L.E. Hochreiter. WCOBRA/TRAC Analysis of ORNL High Flow Rod Bundle Film Boiling Tests, 1997 National Heat Transfer conference, ANS HTC-Vol 10, Baltimore, MD, 1997.
J. Zhang, S.M. Bajorek, R.M. Kemper, M.E. Nissley, N. Petkov, and L.E. Hochreiter. Application of the WCOBRA/TRAC Best Estimate Methodology to the AP600 Large-Break LOCA analysis, Proceedings of ASME Nuclear Engineering Division NE-Vol. 21, 1997.
L.E. Hochreiter, Metodos Best Estimate Para Analysis de Seguridad, Sociedad Nuclear Espanola, No. 153, May 1996.