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Joseph S. Miller
Papers and Presentations
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"BWR Water Level
Modeling", Proceedings of Sixth International RETRAN Conference,
EPRI NP6949, August 1990
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"A Boron
Transport Simulation Using RETRAN-03 Control System Models for
Anticipated Transient Without SCRAM (ATWS) Event", October 1995
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"Alternatives
For Reducing Thermal/Hydraulic Loads on the Safety/Relief Valves
Discharging Piping", October-November 1983. PART I
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"Alternatives
For Reducing Thermal/Hydraulic Loads on the Safety/Relief Valves
Discharging Piping", October-November 1983. PART II
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"BWRSC:
An On-Line Stability Exclusion Region Calculator For BWRs",
September 1992
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"Developing Engineering Analysis Capabilities at a Nuclear Utility",
November 1992
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"Evaluation
of Vortex Formation in Tanks and Sumps", June 1998
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"Evaluation of APEX
SB-11 Test", June 1996
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"Implementation of an
Individual Plant Examination at a Nuclear Utility", April 1991
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"Instrument Sensing Line Anomalies in BWR's", 1986
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"A
Linear Programming Fuel Management Model for the HTGR", 1975
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"Natural
Circulation in a BWR"
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"PRA Applications at an Operating Nuclear Utility", October 1991
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"Using PRA
Methods at an Operating Nuclear Utility", April 1991
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"PRA Development
and Uses", November 1992
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"RELAP5
Simulation of Reactor Water Backflow Into the High Pressure Core
Spray (HPCS) System Piping
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"RETRAN
Simulation of a BWR/6 Load Rejection Transient", November 1989
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"Safety
Significance on Fire Induced Shorts on the 1E12*MOVF009 and
1B21*MOVF019 Valves", March 1990
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"Simulation of Coupled Primary System and Containment Response Using
RELAP5 and Contain on a Multiprocessor Computer"
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"Trace Large Break Loss-of-Coolant Accident Analyses Using Various
H.B. Robinson Plant Modeling Assumptions", July 2004
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"Validation of a Thermal Hydraulic Computer Code to Perform
Two-Phase Multi- Component Force Calculations for Structural
Evaluations", May 2005
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"Water-Level Backfill
Modification Evaluation Using RELAP 5", September 1995
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"Calculation of Forces on Reactor Containment Fan Cooler Piping",
April 2004
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"Conditions of the Fluid in the RHRS Pipe Line After the Loss and
Restart of the RHRS Pump", April 2007
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"Solving Reactor Water Clean-up System Anomalies Using RELAP5 MOD
3.3", April 2003
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"Conditions of Fluid in RHR Line After Loss and Restart of RHR Pump
at Turkey Point 3"
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"Improving Nuclear Power Plant's Operational Efficiencies in the
USA", May 2011
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"Dynamic Analysis of the M/S Heater Drain System", July 2007
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"Validation of a Thermal Hydraulic Computer Code to Perform
Two-Phase Multi-Component Force Calculations for Structural
Evaluations", May 2006
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"Fukushima Dia-itchi at
2 months", Presented at BYU, Provo, Utah,
May 10, 2011
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"Peach Bottom Drain Tank Dynamic Analysis Using RELAP5", May 31,
2007
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BWR/6
RELAP4 Model
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Power Uprate
Evaluation for NRC 1996
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