1. Curriculum VITA as Professor
5/10/2012
Name Robert M. Edwards January 15, 1950
Academic Rank:Professor, full-time; retired July1 ,2012 as Professor Emeritus of Nuclear Engineering.
Date of Initial Appointment: January 1987
Degrees BS (1971) – Nuclear Engineering, The Pennsylvania State University
MS (1972)- Nuclear Engineering, University of Wisconsin
Ph.D. (1991) – Nuclear Engineering, The Pennsylvania State University
Field of Specialization and Current Areas of Interest: The applications of advanced control, monitoring, and
simulation to nuclear reactors and power plants. Current interests include: Hybrid simulation using the Penn State
TRIGA reactor and Low-pressure Thermal-Hydraulic Test-Loop coupled to real-time simulations of power plant
dynamics; optimal, robust and fault-accommodating control and monitoring systems; optimization and control of
balance-of-plant for efficiency improvement; and real-time power-plant simulator development.
Previous Employment Summary:
1977 to 1987: Director of Software Development, LeMont Scientific Incorporated, State College, Pennsylvania.
Responsible for the refinement and continuing evolution of the company's image analysis systems product line. The
LeMont image analysis system interfaced DEC LSI 11 computers to scanning electron microscopes (SEM) and Energy
Dispersive Spectrometers (EDS) with hardware manufactured by LeMont. The analysis system included chemical
composition identification.
1976 to 1977: Senior Nuclear Engineer, Combustion Engineering Incorporated, Windsor, Connecticut. Responsible
for the computer programming, testing, and documentation for a nuclear reactor core digital protection system.
Programming and testing was performed using FORTRAN simulations on a mainframe computer.
1972 to 1976: Engineer, General Atomic Company, San Diego, California. Assignments at General Atomic as
follows: 1974 to 1976: Core Performance Branch. Responsible for conducting nuclear reactor fuel performance
evaluations during transient conditions such as reactor start-up, load following, and accident conditions. 1973 to
1974: Systems Analysis Branch. Responsible for control systems analysis of the HTGR steam cycle power plant.
1972 to 1973: Computer Applications Branch. Responsible for developing application programs for on-line power
plant computers, primarily that of a reactivity surveillance program.
Courses Taught at Penn State:
designation credits Times
taught
Title level
NucE 505 3 15 Reactor Instrumentation and Control graduate
NucE 451 3 17 Experiments in Reactor Physics (lab) senior
NucE 497E 3 6 Simulator Design junior/senior
ChE 450 3 4 Process Dynamics and Control (Chemical Engr.) senior
NucE 003s 1 3 Power Plants & their Simulation (freshman seminar) freshman
NucE 597E 3 2 Power Plant Dynamics and Control graduate
NucE 597I 3 1 Power Plant Intelligent Distributed Control graduate
ME 462 3 1 Microcomputer Interfacing junior/senior
NucE 301 4 3 Fundamentals of Reactor Physics junior

2. 2
Graduate Theses Supervised.
Student Name
Type of
Degree
Granted
(Mo/Yr)
Title of Thesis
Shian-shing Shyu Ph.D. NucE 5/01 A Robust Multivariable Feedforward/Feedback Controller
Design for Integrated Power Control of Nuclear Power
Plant
Zhengyu Huang M.S. E.E. 8/01 Fuzzy Logic Controller Design for Overall Control of a
Nuclear Power Plant
Zhengyu Huang Ph.D. NucE 5/02 Fuzzy Adapted Sliding Mode Controller Design for a
Nuclear Power Plant
David Werkheiser M.S. NucE 12/02 Modeling of the Integrated Control System for the Three
Mile Island Pressurized Water Reactor
Hans Gougar Ph.D. NucE 5/04 Advanced In-Core Fuel management for Recirculating
Pebble-Bed Reactors
Weidong He Ph.D. NucE 8/09 Stability and Design of Low-Pressure Two-Phase Natural
Circulation
Yin Guo Ph.D. NucE 8/12 Reliable LQG Controller Design with Sensor Failure for
Nuclear Power Plant with IRIS Demonstration
A Service to the Profession
American Nuclear Society Penn State Student Chapter Advisor, 1999 to present.
Organization of Technical Sessions at National and International Meetings:
Session chairman of The Eight Power Plant Dynamics, Control, and Testing, Symposium, session on
"Control and Diagnostics Applications for Liquid-Metal Reactors," (May 1992).
Active Participation on Societies Committees:
ANS Human Factors Division Vice Chair/Chair Elect, 2002 to 2003
ANS Human Factors Division Chairman, 2003 to 2004
ANS Operations and Power Division Program Committee, 1997 to 2004
B. Research and/or Scholarly Publications
a. Articles published in refereed journals.
Ceceñas-Falcón, M., and R.M. Edwards. 2001. Application of a Reduced Order Model to BWR Corewide
Stability Analysis. Annals of Nuclear Energy. 28:1219-1235.
Shyu, S., and R.M. Edwards. 2002. A Robust Multivariable Feedforward/Feedback Controller Design for an
Integrated Power Control of Boiling Water Reactor Power Plants. Nuclear Technology. 140:129-146.
Ceceñas-Falcón, M., and R.M. Edwards. 2003. Out-of-Phase BWR Stability Monitoring. Nuclear
Technology. 143: 125-131.
Huang, Z., and R.M. Edwards. 2003. Hybrid Reactor Simulation of BWR Power Oscillations. Nuclear
Technology. 143:132-143.
Huang, Z., and R.M. Edwards, 2003. "Power Generation Efficiency Improvement through Auxiliary System
Modifications," IEEE Transactions on Energy Conversion. 18:525-529 (First author supervised by
candidate).
Huang, Z., R.M. Edwards, and K.Y. Lee, 2004. "Fuzzy Adapted Recursive Sliding Mode Controller Design
for a Nuclear Power Plant Overall Contol," IEEE Transactions on Nuclear Science, 51:256-266. (First Author
supervised by candidate.)

3. 3
Shaffer, R., W. He, and R.M. Edwards, 2004. "Design And Validation Of Optimized Feedforward With
Robust Feedback Control Of A Nuclear Reactor," Nuclear Technology, 147:240-257. (First Author
supervised by candidate.)
Shaffer, R.A., R.M. Edards, and K.Y. Lee., 2005. "Design and Validation of Robust and Autonomous
Control for Nuclear Reactors," Nuclear Engineering and Technology.
Turso, J.A., R.M. Edwards, and B.E Turso. 2007 Accommodating Power Plant Anomalies via Artificial
Neural Network-Based Reconfigurable Control. Journal of Intelligent Systems. Vol. 16, No 1:75:91(First
author supervised by candidate)
He, W., and R.M. Edwards, 2008 "Stability Analysis and Design of a Low Pressure Two-Phase Testloop.,
"Annals of Nuclear Energy. (First author supervised by candidate)
Xin Jin, Asok Ray, amd Robert M. Edwards, 2009. "Integrated Robust & Resilient Control of Nuclear Power
Plants for Operational Safety and High Performance," IEEE
Xin Jin, Robert M. Edwards and Asok Ray, 2009. " Calibration and Estimation of Redundant Sensors for On-
Line Monitoring and Control of Nuclear Power Plants," for submisssion to Nuclear Science and Engineering
Xin Jin, Robert M. Edwards, and Asok Ray 2009. "Transient Identifiication in Nuclear Power Plants Using
Support Vector Machines," for publication in Nuclear Science and Engineering
Xin Jin, Asok Ray, and R.M. Edwards ,2009. " Optimal Feature Extraction for Fault Diagnosis in Nuclear
Power Plants in the Presene of Sensor Degradation", to be submitted to IEEE
Yin Guo and Robert M. Edwards, 2009. "Pressure Control for Helical-Coil Steam Generator of IRIS Based
on Nonlinear Observer-Based Feedback Dissipation," accepted for publication in Nuclear Science and
Engineering
X. Jin, A. Ray and R. M. Edwards,2010. "Integrated Robust and Resilient Control of Nuclear Power Plants
for Operational Safety and High Performance," IEEE Transactions on Nuclear Science, vol. 57, no. 2, part 2,
pp. 807-817
X. Jin, Y. Guo, S. Sarkar, A. Ray and R. M. Edwards, 2011. "Anomaly Detection in Nuclear Power Plant via
Symbolic Dynamic Filtering," IEEE Transaction on Nuclear Science.
b. Articles published in refereed proceedings
He, W., Z. Huang, and R.M. Edwards. 2002. Advanced BWR Stability Monitoring Tests with a Hybrid
Reactor Facility. Proceedings of American Nuclear Society Topical Meeting, International Congress on
Advanced Nuclear Power Plants (ICAPP), 6 pages on CD ROM.
Huang, Z., and R.M. Edwards. 2002. Sliding Mode Control Application in ABWR Plant Pressure Regulation.
Proceedings of American Nuclear Society Topical Meeting, International Congress on Advanced Nuclear
Power Plants (ICAPP), June 2002. 8 pages on CD ROM.
Cetiner, S.M., and R.M. Edwards. 2002. Results of Coupling a Thermal-Hydraulic Test Loop and University
Research Reactor. Proceedings of American Nuclear Society Topical Meeting, International Congress on
Advanced Nuclear Power Plants (ICAPP). 7 pages on CD ROM.
Huang, Z., K.Y. Lee, and R.M. Edwards. 2002. Fuzzy Logic Control for Nuclear Power Plant Overall
Control. Proceedings of 15th IFAC World Congress. Barcelona, Spain. 6 pages on CD ROM.
Pauley, L.L., R.M. Edwards, and L.E. Hochreiter. 2003. The Nuclear Engineering and Mechanical
Engineering Multiple Majors Program at the Pennsylvania State University. Proceedings of the 2003 ASEE
Annual Conference and Exhibition. Nashville, TN. 9 pages on CD ROM.

4. 4
Pauley, L.L., R.M. Edwards, and L.E. Hochreiter, 2003. "The Nuclear Engineering and Mechanical
Engineering Multiple Majors Program at the Pennsylvania State University," Proceedings of the 2003 ASEE
Annual Conference and Exhibition. Nashville, TN. 9 pages on CD ROM. (Equal contributions by authors.).
Xin Jin, Robert M. Edwards and Asok Ray, 2008. "Integrated Robust and Resilient Control for Nuclear
Power Plants" Proceedings of The sixth Nuclear Plant Instrumentation Control and Human Machine Interface
Technologies. (First author supervised by candidate)
X. Jin, R. M. Edwards, and A. Ray, 2008. "Integrated Robust and Resilient Control for Nuclear Power
Plants", in Proceedings of 6th ANS International Topical Meeting on NPIC & HMIT, Knoxville, TN.
Y. Guo, X. Jin and R. M. Edwards, 2010. "State Observer Design for IRIS Reactor based on Dissipation-
based High Gain Filter," in the Proceeding of 7th NPIC & HMIT Topical Meeting, Las Vegas, NV, Nov. 7-
11, 2010.
X. Jin, Y. Guo, R. M. Edwards and A. Ray, 2010. "Data-driven Fault Detection in Nuclear Power Plants
under Sensor Degradation," in the Proceeding of 7th NPIC & HMIT Topical Meeting, Las Vegas, NV, Nov.
7-11.
c. Papers refereed by abstract
Huang, Z., and R.M. Edwards. 2001. Simulation of BWR Out-of-Phase Oscillation Using a University
Research Reactor. Trans. of the Amer. Nucl. Soc. Student Conference. College Station, TX. 7 pages on CD
ROM.
He, W., and R.M. Edwards. 2001. Robust Design an Evaluation of On-line Uncertainty Monitoring System
on a Reactor. Trans. of the Amer. Nucl. Soc. Student Conference. College Station, TX. 6 pages on CD ROM.
Cetiner, M., and R.M. Edwards. 2001. The Pennsylvania State University Low Pressure Integral Test Facility
Data Acquisition System and User Interface. Trans. of the Amer. Nucl. Soc. Student Conference. College
Station, TX. 7 pages on CD ROM.
Erhard, R.P, D.L. Werkheiser, and R.M. Edwards. 2001. Simulator Design and Man / Machine Interfacing.
Trans. of the Amer. Nucl. Soc. Student Conference. College Station, TX. 6 pages on CD ROM.
Erhard, R.P., and R.M. Edwards. 2001. Web Based Reactor Experiments. Trans. of the Amer. Nucl. Soc.
Student Conference. College Station, TX. 6 pages on CD ROM.
Huang, Z., and R.M. Edwards. 2001. Hybrid Reactor Simulation and 3-D Information Display of BWE Out-
of-Phase Oscillation. Trans. of the Amer. Nucl. Soc. 84:99-100. Milwaukee, WI.
He, W., and R.M. Edwards. 2001. Evaluation of a Reactor On-Line Uncertainty Monitoring System. Trans.
of the Amer. Nucl. Soc. 84:111-112. Milwaukee, WI.
Cetiner, S.M., L.E. Hochreiter, R.M. Edwards, W. He, and Z. Huang. 2001. Two-Phase Natural Circulation
Experiments in The Penn State Low-Pressure Integral Test Facility. Trans. of the Amer. Nucl. Soc. 85:311-
333. Reno, NV.
Huang, Z., and R.M. Edwards. 2002. ABWR Plant Overall Control Using Fuzzy Logic Control Technique.
Trans. of the Amer. Nucl. Soc. 86:180-182. Hollywood, FL.
Cetiner, S.M., and R.M. Edwards. Integration of a Thermal-Hydraulic Test Loop and University Research
Reactor For Advanced Control. 2002. Trans. of the Amer. Nucl. Soc. 86:195-196. Hollywood, FL.
He, W., and R.M. Edwards. 2002. Evaluation of in-phase BWR Stability Monitor with a Hybrid Reactor
Facility. Trans. of the Amer. Nucl. Soc. 86:242-243. Hollywood, FL.
Meyers, G.L., and R.M. Edwards. 2004. Internet Access to Reactor Control Experiments. Proceedings of
the American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control and

5. 5
Human-Machine Interface Technologies, NPIC&HMIT'2004, 8 pages on CDROM. (First author supervised
by candidate.)
He, W., and R.M. Edwards. 2004. Stability Analysis Results for a Two-Phase Test Loop. Proceedings of
the American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control and
Human-Machine Interface Technologies, NPIC&HMIT'2004, 11 pages on CDROM. (First author supervised
by candidate.)
Edwards, R.M., R.A. Shaffer, and S.A. Arndt, 2006. “Modeling Digital Control Systems in TRACE.,
Proceedings of the American Nuclear Society International Topical Meeting on Nuclear Plant
Instrumentation, Control and Human-Machine Interface Technologies, NPIC&HMIT'2006, 12 pages on
CDROM.
Xin Jin, Asok Ray, and Robert Edwards, 2009. "Integrated Robust and Resilient Control for Nuclear Power
Plants", Proceedings of the 2009 ANS Winter Meeting, Washington, DC
Yin Guo, Robert M. Edwards, 2009. "Reliable LQG Controller Design with Sensor Failure for Nuclear
Power Plant with IRIS Demonstration, " Proceedings of the 2009 ANS Winter Meeting, November 2009,
Washington DC.
Xin Jin, Asok Ray and Robert M. Edwards, 2009. "Redundant Sensor Calibration and Estimation for
Monitoring and Control of Nuclear Power Plants,", Proceedings of the ANS Winter Meeting, November,
2009
X. Jin, A. Ray and R. M. Edwards, 2010. "Feature Extraction for Data-driven Fault Detection in Nuclear
Power Plants," in Transactions of American Nuclear Society, vol. 102, pp. 163-164, June 2010
d. Research projects completed.
July 1999 – July 2003
Title: Monitoring and Control Research Using a University Reactor and SBWR Test-loop
Submitted to: Department of Energy Nuclear Engineering Education and Research
Amount: $380,791
PI
100%
July 1998 – June 2003
Title: Simulator Design
Submitted to: Penn State College of Engineering, PECO Energy Gift funds, and Tuition Surcharge
Amount: $56,000
PI
100%
October 2007-December 2010
Title: Advanced Instrumentation and Control Methods for Small Export Reactors with IRIS
Demonstration
Submitted to: DOE
Amount: $471,017
PI
100%

6. 6
C. Research reports to sponsor.
Edwards, R.M., December 2000. Monitoring and Control Research Using a University Research Reactor and
SBWR Test-Loop, Phase 2 Topical Report. Report to: U.S. Department of Energy. 7 pages.
Edwards, R.M., January 2002. Monitoring and Control Research Using a University Research Reactor and
SBWR Test-Loop, Phase 3 Topical Report. Report to: U.S. Department of Energy. 18 pages.
Edwards, R.M., February 2003. Monitoring and Control Research Using a University Research Reactor and
SBWR Test-Loop, Annual Report. Report to: U.S. Department of Energy. 4 pages
Edwards, R.M., August 2003. External Interface to SIMULINK. Report to U.S. Nuclear Regulatory
Commission. 29 pages.
Edwards, R.M., January 2011, Advanced Instrumentation and Control Methods for Small Export Reactors
with IRIS Demonstration, Report to the U.S. Department of Energy.
D. Participation in, and description of, seminars and workshops
Seminar/Workshop
Title _ Dates Sponsor Role
Instrumentation, Control
and Human Machine
Interface Workshop
5/15/02- 5/17/02 Department of Energy Participant
I&C HMI Technology
Working Group Meeting
11/16/02 Department of Energy and
Electric Power Research Institute
Invited Presenter