1. Integration of GPWR Simulation Laboratory in Teaching, Research & Outreach
Jason Hou, Lisa Marshall & Kostadin Ivanov Department of Nuclear Engineering NC State University
Sean Fuller & Jay Umholtz GSE System

2. Introduction
The Nuclear Engineering (NE) Department at North Carolina State University (NCSU) renovated its simulation lab recently
GSE’s Generic Pressurized Water Reactor (GPWR) simulator is being used to support nuclear power related educational curricula as well as analytical studies
NCSU is planning to cooperate in the future with GSE, IFE, and other partners on enhanced and efficient simulator utilization for
Education,
Research,
Outreach; and,
Training purposes.

3. GPWR Introduction
GPWR is well suited to the uses that we may envision.
As a full nuclear simulator, it allows for the entire range of operations experienced in a commercial nuclear power plant.
Additionally, the supporting documentation will assist NCSU in understanding the systems and processes needed for normal and emergency operations.
GSE’s GPWR has a large research and educational user base that will allow for collaboration between different organizations.

4. Renovated NE Simulation Lab
Generic PWR simulator
1 instructor station
10 student stations
Various modes of simulation available, allowing students to
work together to finish an operational task
run simulation independently

5. Current lab configuration
VPanel glass-top control panel
Touch screen that enables control operations
Panel and simulator are embedded in a JClassRoom
IFE designed DCS style screens
Displayed on 3 HD monitors allowing for real-time display of key system parameters

6. Teaching: Motivation
The simulation software we are currently using runs fast, and is flexible in terms of altering system parameters, controller and sensor behavior, etc.
The GSE GPWR simulation software is an important supplement to the existing simulation capabilities we already have in the Department.
The primary advantage of the GPWR is its inclusion of expanded auxiliary and safety system models and enhanced graphics.

7. Teaching: Addition to Existing Courses
Supplement existing simulation capabilities in
NE 405/505 Reactor Systems
Primary, secondary and tertiary loops
Auxiliary systems
Reactor response to standard operational maneuvers
Accident behaviors and safety system response
NE 418 Nuclear Reactor Instrumentation
Reactor instrumentation needs
Impact of instrumentation response on reactor control
NE 722 Reactor Kinetics and Control
Development and optimization of control methods

8. Challenge: Effort is Required to Tailor GPWR Simulator to Our Education Needs
The simulator is designed primarily for training purposes
Students should not be required to memorize location of every meter, switch, and annunciator etc.
Students are encouraged to work independently using PC in the student station
In the classroom, it is more important to demonstrate the system design than to learn the operational procedures
Consequently, the well documented operating procedures need to be converted to the format that is suitable for teaching
Highlight the key-points and identify the most important steps that’s relevant to student
Time-dependent events for the experiments need to be carefully selected, such that
They meet the curriculum requirement
They can complete within a reasonable time frame (~1 hour)
Parameters for students to monitor and analyze will be selected

9. Progress in reactor system course
Parameter
Explanation 
Case 1
Case 2
Unit
REACTOR POWER
99.7
53.7 %
TURBINE SPEED RPM
1800.0
RPM
GENERATOR OUTPUT MW
968.0
439.6 MW
REFERENCE MW
936
400
DEMAND MW
RCS Boron Conc.
Boron Concentration
795.9
796.29
PPM
T-COLD 1
557.7
553.7
degF
T-COLD 2
T-COLD 3
T-HOT 1
620.2
587.3
T-HOT 2
T-HOT 3
RCS AVERAGE TEMP
588.9
573.09
PRZ LEVEL
60.0
39.8
PRZ PRESS
2236
2235
psig
RCS PI 403
RCS Pressure Indicator 403
2230
2228
psi
DELTA-T SG
62.5
33.5 F
SG STEAM FLOW
4.25
2.01
MPPH
SG FW FLOW
4.29
2.04
NR SG
Steam Generator Narrow Range
56.8
57.0
WR SG
Steam Generator Wide Range
53.3
53.6
Example of critical parameters for students to track
Fast time mode of simulation
Allows up to 8x faster than otherwise

10. Progress in reactor system course (cont.)
Lab module in preparation
Normal procedure (being tested, will be incorporated later this semester)
Power maneuver: ramp down
Power maneuver: ramp up
Automatic operation of rod control system: ramp down
Manual operation of rod control system: ramp down
Transients
Feedwater control system malfunction
Turbine control valves fails to open
Loss of feedwater pump
Design basis accidents (DBA)
Large/small break loss-of-coolant accident (LOCA)
Main steam line break (MSLB)

11. Example: Power Maneuver: Ramp Down
Simplified lab procedure
Reset Initial condition
Reduce turbine power by using the DEH Panel
Press the LOAD RATE MW/MIN push-button
Enter desire rate
Press the ENTER push-button
Press the REF push-button
Enter the desire load (power) in the DEMAND display
Press the ENTER push-button. The HOLD push-button should illuminate
Press the GO push-button to start the load reduction
Verify the number in the REFERENCE display decreases

12. Example: Power maneuver: ramp down (cont.)
Simplified lab procedure
When the Turbine 1st State pressure < 60% (~340 psig)
Stop one Main FW Pump (Location: Drawing B1, at the bottom of the FEEDWATER section)
Place MFW PUMP B RECIRC CONTROL 1FW-39 in the SHUT position
Place MAIN FW PUMP B in the STOP position
When the reactor power is between 40% to 45%
Place HEATER DRAIN PUMP A and HEATER DRAIN PUMP B in the STOP position
And more…
Lecture will be given on why certain equipment has to be secured or started during power maneuvering in respect of reactor design and operation

13. Example: Power Maneuver: Ramp Down (cont.)
Data acquisition
Students can load pre-defined trend file and record/export important parameters during simulations

14. Research: Strengthen Research Capability of NE Department
Reactor dynamics and control
Human factor research
Incorporating high-fidelity core simulation to the simulator environment for on-line tracking of local safety parameters
Extending the simulator capabilities to severe accident analysis
Research platform to meet the growing demands for improved nuclear plant performance

15. Training Program Development of training program
In collaboration with industry and other academic institutions
With addition of courses offered in NC State NE Department
Short courses/workshops
Combination with PULSTAR
1-MW pool-type research reactor
Full-scale simulation of PWR
Integrate hands-on PULSTAR operations with GPWR simulations
In combination with the PULSTAR research reactor the simulator will provide unique opportunities to nuclear engineering students and professionals
Future: reactor operation training via internet
Allows distance learning participants to interact with GPWR instructors through video and audio communications
On-line data representation

16. Extension Pre-College Outreach Prospective Student Outreach
Integrate into overall outreach programming, for example, High School Science Class Visits, Science Teachers’ Workshop in Nuclear Engineering, Young Investigators’ Summer Program in Nuclear Engineering
Prospective Student Outreach
In addition to other labs/facilities, provide prospective (under)graduate students and their stakeholders with general understanding of nuclear power and plant operation
Provide an introduction to engineering freshman students through new student orientation and introduction to Engineering & Problem Solving course
Provide an introduction to nuclear engineering lower classmen through student organizations
Integration into College of Engineering Open House & Other Recruitment Initiatives
Demonstrate reactor safety features
Assist in the demystification of nuclear science & technology
Assessment of impact of simulator technology
Use data to better outreach initiatives
Presentation at engineering education conference(s)

17. Acknowledgement
Authors would like to thank Huang Yeh and Juan Castaneda from GSE for their technical assistance in developing the lab procedure for reactor system course.