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Bringing Engineering Analysis Codes
Into Real-Time Full-Scope Simulators
info@gses.com
Outline
I.

Full-scope simulator evolution

II. High-definition simulator platform
III. MAAP in full-scope simulators
IV. Support integrated training of NOP, EOP and
SAMGs

2
Real-Time Simulator
• Real-time simulators came to the nuclear industry as
training tools in the 1970s
– Full plant modeled, but models often “hand crafted”
– Analog controls, traditional hard-panel control panels

• Today’s nuclear power plant simulator is high fidelity
– Same scope, but
– High-definition predictive models used to model plant systems
– Digital controls and modern HSIs: detailed view of systems

• Today the real-time simulator is an engineering tool
– Holistic dynamic plant model

3
Real-Time Simulator
• Broad or full-scope plant model
– Includes primary, secondary, BOP and safety system and at
least a high-fidelity main loop

• All models integrated and synchronized (coupling)
• One second of problem time = One second of real time
(feels like the real plant)
• Models are interactive
– Observe and operate like the real plant
– Can be integrated with real control systems

4
New Missions of Simulator
• Holistic engineering V&V platform

− Validation of system design issue in integrated “plant”

• Controls system design and V&V

− Validation and refinement of logic and controls strategies
as a development tool for new control strategies

• Human factors engineering platform

− Support design of DCS interface, alarms, procedures, etc.
− Support design of digital control rooms and information layout
− Demonstrate viability of these designs to regulator

• Develop and validate operating procedures
• Address post-Fukushima challenges

5
GSE High-Definition (HD) Platform
• Running third-party best estimate or safety analysis
codes as integral parts of full-scope simulators
• Enforce synchronization between multiple systems
through client and server architecture
• Maintain integrity of original code

• Ensure repeatability
• Allow users to have access to model internal memory
and variables
• Advanced 2D & 3D visualization interfaces

6
GSE HD Platform Architecture
Client

Customized
plug-in
interface
client

Standard HD
server
configuration

Simulator Host
Executive
(GSE or non-GSE)
HD Client
Executive #1

Input

Server

Output

Client C
module

Control
Status request

Server
input/output

7
Multiple HD Servers
BWR Configuration
•

•

HD Server #1

Simulator

Server #1 (CPU #1): RELAP for
BWR vessel

(GSE or
other)

Server #2 (CPU #2): Neutron
Kinetics Code (ex. REMARK)

HD Server #2
HD
Client

PWR Configuration
•
•
•

Server #1 (CPU #1): RELAP for
primary loops

HD Server #3
HD Server #4

SMR Configuration

Server #2 (CPU #2): RELAP for
steam generators

•

Server #1 (CPU #1): RELAP for module #1

Server #3 (CPU #3) Neutron
kinetics code (ex. REMARK)

•

Server #2 (CPU #2): RELAP for module #2

•

Server #3 (CPU #3): S3R for module #1

•

Server #4 (CPU #4): S3R for module #2

8
Data-Centric System
MAAP
MAAP
4.06

MAAP
4.08

MAAP
5.01

MAAP
5.02

MAAP
5.03

RELAP5
-3D

9
Graphical SAMGs

Computer-based procedures that help automate the SAMG control the
sequence of events in PSA-HD simulation

10
V&V Tool

reference data
simulator data

11
Extensible Platform
• Servers may include GSE or third-party models, such as:
− GSE’s Topmeret, REMARK
− MAAP5, MAAP4
− INL’s RELAP5-3D v2.4 & v4.0
− Studsvik’s S3R (neutronics) and thermal margin codes
− MELCOR
− SPICE – analog circuit board
− Russian VVER Neutronic modes

• Flexible configuration
− Multiple computers
− Multiple processors/cores
− Varied frame rates

12
RELAP5-HD Installations
Reactor Type
BWR, GE
PWR, WE
PWR, WE
PWR, WE
Small Modular Reactor,
B&W
PWR, WE
CANDU
PWR, RUS
Naval Reactor
PWR, WE
BWR, GE
Small Modular Reactor,
NuScale

Country

Status

Japan
United States
United States
United States
United States

On-going
On-going
On-going
On-going
On-going

United States
Canada
Ukraine
UK
Netherlands
United States
United States

On-going
On-going
On-going
On-going
On-going
RFT
RFT

RELAP5-3D requires US
DOE export license

Reactor Type
PWR, WE
PWR, WE
PWR, CE
PWR, WE
PWR, ASEA
PWR, ASEA
BWR, ASEA
PWR, ASEA
BWR, ASEA
BWR, ASEA
BWR, ABB
BWR, GE
PWR, RUS
PWR, RUS
JMTR
PWR, WE
BWR, GE

Country
South Korea
South Korea
South Korea
South Korea
Germany
Germany
Germany
Germany
Sweden
Sweden
Sweden
Switzerland
Bulgaria
Ukraine
Japan
Japan
Japan

Status
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT
RFT

13
MAAP4 & 5 Installations
Reactor Type
BWR, GE

Plants, Country
K5, Japan

3-Loop PWR, WE
4-Loop PWR, WE (ice
condenser)
BWR, GE

KTN2, Japan
KON1, Japan

BWR, GE
BWR, GE

2F2, Japan
TS1, Japan
(Same design as 1F1)
TS2, Japan

4-Loop, PWR,
Mitsubishi
PWR, WE
PWR, WE
PWR, WE
BWR, ASEA

TK2, Japan

Status
MAAP 3.0, 1994
MAAP 4.0, 2013
MAAP4, 2006
MAAP4, 2006
MAAP 3.0, 1998
MAAP 4.0, 2013
MAAP3, 2001
MAAP3, 1997

R2, Sweden
United States
United States

MAAP 3.0, 1998
MAAP 4.0, 2013
MAAP5, on-going
MAAP5, on-going
MAAP5, on-going

Sweden

MAAP5, on-going

MAAP code requires
US EPRI user license
14
GSE First-of-a-Kind Engineering Simulator
Experience

Westinghouse AP1000
NuScale Power

Pebble Bed
Modular Reactor

HYH CPR-1000
HFE and Control
V&V Platform

Ultra Supercritical
Korea

IGCC China

SMART
Korea Atomic
Energy
Research
Institute

B&W
mPower
Engineering
and HFE
Simulator
15
HD Interfaces
•
•
•
•
•
•
•
•
•
•

Interface functions
BOP to HD fluid interface (BOP calculates flows)
BOP to HD fluid interface (HD calculates flows)
HD to HD fluid interface (typically only used for U-tube
rupture)
BOP to HD heat structure interface
Standard interfaces
HD to HD heat structure interface
and automated
Core model interface
generation
Miscellaneous control interface
Instrumentation interface
Remote function / Fast time interfaces

16
MAAP5 in Full-Scope Simulator
Electrical System
JElectric

I&C
JControl

Ex-plant DOSE
Simulation
MAAP5

In-plant
DOSE simulation

In-plant
DOSE simulation

Unit 2
Containment
MAAP5

Unit 1
Containment
MAAP5

SG
TH
Code/
MAAP5

RCS
TH Code/
MAAP5
Core
S3R

Auxiliary
Building
MAAP5
Spent Fuel Pool

BOP
JTopMeret

RCS
TH Code/
MAAP5

SG
TH
Code/
MAAP5

Core
S3R

2-Unit Westinghouse 4-Loop PWR
17
MAAP5 in Full-Scope Simulator
0 Min.

~60 Min.

3 Hrs. 20
Min.

5 Hrs. 30
Min.

Scenario

Steady-state

LOCA, code
transition

LOCA, Core
melt-down

LOCA, Vessel
failed

Unit #1
RCS/SG

TH Code

Timeline

MAAP
Server #1

Transition
MAAP5.0

Shared Aux.
Building
(w/ SFP)

MAAP5.0

BOP

MAAP
Server #2

Unit #1
Containment

MAAP5.0

GSE JTopmeret

Simulator
Neutronics

Studsvik S3R

MAAP5.0

18
A More Reliable Engineering Code
Accumulation
of
Benchmarks

NQA (Future)

Documentation

Best
Estimate
Core Code
Code
Improvement

Verification &
Validation

New
Capabilities

19
Engineering Codes to Simulator
Training Simulator

Simulator
System
Dev. &
Test
Process

Engineering Codes

All
Simulato
r System
Models

Benchmarks
Eng.
Code

Simulation
System

System
Configuration

Eng. Code
Input
Deck

Various
Interfaces

NQA
(Future)

Documentation

Code
Improvement

V&V

New
Capabilities

20
Progressive Simulator Solutions
HD (MAAP,
RELAP, JADE,
etc..)

Desktop HD
(MAAP or
RELAP)

Fullscope
simulator
Desktop

simulator

Riskinformed
simulator
HD (MAAP, RELAP,
JADE, uncertainty,
database, etc..)

21
Integrated EOPs, SAMGs, etc.

NOPs

EOPs

SAMGs

Postulated Actions

Exercises

Full-scope Simulator (RELAP5-HD)
Realistic Training
Main Control Room

Local Field
Personnel

Expanded Training

Technical Support
Center

Radiological
Center

Emergency Director
(Plant Manager)

22
Next-Generation Simulation
Multi-scale, multi-physics modeling
Wide-scale data processing
Large-scale numerical computation
Multi-variant, multi‐response and multi-dimensional
problems
• Total data model integration
• Data, computations, systems, uncertainty
quantification and knowledge management
•
•
•
•

23
EPRI MAAP Code
•

''MAAP 5.0 is an Electric Power Research Institute (EPRI) software program
that performs severe accident analysis for nuclear power plants including
assessments of core damage and radiological transport. A valid license to
MAAP 5.0 from EPRI for customer's use of MAAP 5.0 is required prior to a
customer being able to use MAAP 5.0 with [LICENSEE PRODUCT].

•

EPRI (www.epri.com) conducts research and development relating to the
generation, delivery and use of electricity for the benefit of the public. An
independent, nonprofit organization, EPRI brings together its scientists
and engineers as well as experts from academia and industry to help
address challenges in electricity, including reliability, efficiency, health,
safety and the environment. EPRI does not endorse products or services,
and specifically does not endorse [NEW PRODUCT NAME] or GSE.
Interested vendors may contact EPRI for a license to MAAP 5.0."

24
GSE Systems, Inc.

Thank you!

25
For more information:
Go to:

www.GSES.com

Follow us on:

Call:

+1 800.638.7912

Twitter @GSESystems

Email:

info@gses.com

Facebook.com/GSESystems

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Bringing Engineering Analysis Codes Into Real-Time Full-Scope Simulators

  • 1. Bringing Engineering Analysis Codes Into Real-Time Full-Scope Simulators info@gses.com
  • 2. Outline I. Full-scope simulator evolution II. High-definition simulator platform III. MAAP in full-scope simulators IV. Support integrated training of NOP, EOP and SAMGs 2
  • 3. Real-Time Simulator • Real-time simulators came to the nuclear industry as training tools in the 1970s – Full plant modeled, but models often “hand crafted” – Analog controls, traditional hard-panel control panels • Today’s nuclear power plant simulator is high fidelity – Same scope, but – High-definition predictive models used to model plant systems – Digital controls and modern HSIs: detailed view of systems • Today the real-time simulator is an engineering tool – Holistic dynamic plant model 3
  • 4. Real-Time Simulator • Broad or full-scope plant model – Includes primary, secondary, BOP and safety system and at least a high-fidelity main loop • All models integrated and synchronized (coupling) • One second of problem time = One second of real time (feels like the real plant) • Models are interactive – Observe and operate like the real plant – Can be integrated with real control systems 4
  • 5. New Missions of Simulator • Holistic engineering V&V platform − Validation of system design issue in integrated “plant” • Controls system design and V&V − Validation and refinement of logic and controls strategies as a development tool for new control strategies • Human factors engineering platform − Support design of DCS interface, alarms, procedures, etc. − Support design of digital control rooms and information layout − Demonstrate viability of these designs to regulator • Develop and validate operating procedures • Address post-Fukushima challenges 5
  • 6. GSE High-Definition (HD) Platform • Running third-party best estimate or safety analysis codes as integral parts of full-scope simulators • Enforce synchronization between multiple systems through client and server architecture • Maintain integrity of original code • Ensure repeatability • Allow users to have access to model internal memory and variables • Advanced 2D & 3D visualization interfaces 6
  • 7. GSE HD Platform Architecture Client Customized plug-in interface client Standard HD server configuration Simulator Host Executive (GSE or non-GSE) HD Client Executive #1 Input Server Output Client C module Control Status request Server input/output 7
  • 8. Multiple HD Servers BWR Configuration • • HD Server #1 Simulator Server #1 (CPU #1): RELAP for BWR vessel (GSE or other) Server #2 (CPU #2): Neutron Kinetics Code (ex. REMARK) HD Server #2 HD Client PWR Configuration • • • Server #1 (CPU #1): RELAP for primary loops HD Server #3 HD Server #4 SMR Configuration Server #2 (CPU #2): RELAP for steam generators • Server #1 (CPU #1): RELAP for module #1 Server #3 (CPU #3) Neutron kinetics code (ex. REMARK) • Server #2 (CPU #2): RELAP for module #2 • Server #3 (CPU #3): S3R for module #1 • Server #4 (CPU #4): S3R for module #2 8
  • 10. Graphical SAMGs Computer-based procedures that help automate the SAMG control the sequence of events in PSA-HD simulation 10
  • 12. Extensible Platform • Servers may include GSE or third-party models, such as: − GSE’s Topmeret, REMARK − MAAP5, MAAP4 − INL’s RELAP5-3D v2.4 & v4.0 − Studsvik’s S3R (neutronics) and thermal margin codes − MELCOR − SPICE – analog circuit board − Russian VVER Neutronic modes • Flexible configuration − Multiple computers − Multiple processors/cores − Varied frame rates 12
  • 13. RELAP5-HD Installations Reactor Type BWR, GE PWR, WE PWR, WE PWR, WE Small Modular Reactor, B&W PWR, WE CANDU PWR, RUS Naval Reactor PWR, WE BWR, GE Small Modular Reactor, NuScale Country Status Japan United States United States United States United States On-going On-going On-going On-going On-going United States Canada Ukraine UK Netherlands United States United States On-going On-going On-going On-going On-going RFT RFT RELAP5-3D requires US DOE export license Reactor Type PWR, WE PWR, WE PWR, CE PWR, WE PWR, ASEA PWR, ASEA BWR, ASEA PWR, ASEA BWR, ASEA BWR, ASEA BWR, ABB BWR, GE PWR, RUS PWR, RUS JMTR PWR, WE BWR, GE Country South Korea South Korea South Korea South Korea Germany Germany Germany Germany Sweden Sweden Sweden Switzerland Bulgaria Ukraine Japan Japan Japan Status RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT RFT 13
  • 14. MAAP4 & 5 Installations Reactor Type BWR, GE Plants, Country K5, Japan 3-Loop PWR, WE 4-Loop PWR, WE (ice condenser) BWR, GE KTN2, Japan KON1, Japan BWR, GE BWR, GE 2F2, Japan TS1, Japan (Same design as 1F1) TS2, Japan 4-Loop, PWR, Mitsubishi PWR, WE PWR, WE PWR, WE BWR, ASEA TK2, Japan Status MAAP 3.0, 1994 MAAP 4.0, 2013 MAAP4, 2006 MAAP4, 2006 MAAP 3.0, 1998 MAAP 4.0, 2013 MAAP3, 2001 MAAP3, 1997 R2, Sweden United States United States MAAP 3.0, 1998 MAAP 4.0, 2013 MAAP5, on-going MAAP5, on-going MAAP5, on-going Sweden MAAP5, on-going MAAP code requires US EPRI user license 14
  • 15. GSE First-of-a-Kind Engineering Simulator Experience Westinghouse AP1000 NuScale Power Pebble Bed Modular Reactor HYH CPR-1000 HFE and Control V&V Platform Ultra Supercritical Korea IGCC China SMART Korea Atomic Energy Research Institute B&W mPower Engineering and HFE Simulator 15
  • 16. HD Interfaces • • • • • • • • • • Interface functions BOP to HD fluid interface (BOP calculates flows) BOP to HD fluid interface (HD calculates flows) HD to HD fluid interface (typically only used for U-tube rupture) BOP to HD heat structure interface Standard interfaces HD to HD heat structure interface and automated Core model interface generation Miscellaneous control interface Instrumentation interface Remote function / Fast time interfaces 16
  • 17. MAAP5 in Full-Scope Simulator Electrical System JElectric I&C JControl Ex-plant DOSE Simulation MAAP5 In-plant DOSE simulation In-plant DOSE simulation Unit 2 Containment MAAP5 Unit 1 Containment MAAP5 SG TH Code/ MAAP5 RCS TH Code/ MAAP5 Core S3R Auxiliary Building MAAP5 Spent Fuel Pool BOP JTopMeret RCS TH Code/ MAAP5 SG TH Code/ MAAP5 Core S3R 2-Unit Westinghouse 4-Loop PWR 17
  • 18. MAAP5 in Full-Scope Simulator 0 Min. ~60 Min. 3 Hrs. 20 Min. 5 Hrs. 30 Min. Scenario Steady-state LOCA, code transition LOCA, Core melt-down LOCA, Vessel failed Unit #1 RCS/SG TH Code Timeline MAAP Server #1 Transition MAAP5.0 Shared Aux. Building (w/ SFP) MAAP5.0 BOP MAAP Server #2 Unit #1 Containment MAAP5.0 GSE JTopmeret Simulator Neutronics Studsvik S3R MAAP5.0 18
  • 19. A More Reliable Engineering Code Accumulation of Benchmarks NQA (Future) Documentation Best Estimate Core Code Code Improvement Verification & Validation New Capabilities 19
  • 20. Engineering Codes to Simulator Training Simulator Simulator System Dev. & Test Process Engineering Codes All Simulato r System Models Benchmarks Eng. Code Simulation System System Configuration Eng. Code Input Deck Various Interfaces NQA (Future) Documentation Code Improvement V&V New Capabilities 20
  • 21. Progressive Simulator Solutions HD (MAAP, RELAP, JADE, etc..) Desktop HD (MAAP or RELAP) Fullscope simulator Desktop simulator Riskinformed simulator HD (MAAP, RELAP, JADE, uncertainty, database, etc..) 21
  • 22. Integrated EOPs, SAMGs, etc. NOPs EOPs SAMGs Postulated Actions Exercises Full-scope Simulator (RELAP5-HD) Realistic Training Main Control Room Local Field Personnel Expanded Training Technical Support Center Radiological Center Emergency Director (Plant Manager) 22
  • 23. Next-Generation Simulation Multi-scale, multi-physics modeling Wide-scale data processing Large-scale numerical computation Multi-variant, multi‐response and multi-dimensional problems • Total data model integration • Data, computations, systems, uncertainty quantification and knowledge management • • • • 23
  • 24. EPRI MAAP Code • ''MAAP 5.0 is an Electric Power Research Institute (EPRI) software program that performs severe accident analysis for nuclear power plants including assessments of core damage and radiological transport. A valid license to MAAP 5.0 from EPRI for customer's use of MAAP 5.0 is required prior to a customer being able to use MAAP 5.0 with [LICENSEE PRODUCT]. • EPRI (www.epri.com) conducts research and development relating to the generation, delivery and use of electricity for the benefit of the public. An independent, nonprofit organization, EPRI brings together its scientists and engineers as well as experts from academia and industry to help address challenges in electricity, including reliability, efficiency, health, safety and the environment. EPRI does not endorse products or services, and specifically does not endorse [NEW PRODUCT NAME] or GSE. Interested vendors may contact EPRI for a license to MAAP 5.0." 24
  • 26. For more information: Go to: www.GSES.com Follow us on: Call: +1 800.638.7912 Twitter @GSESystems Email: info@gses.com Facebook.com/GSESystems

Editor's Notes

  1. A popular term for describing the new role of the simulator is Simulator Assisted EngineeringFor many of these new plants, the simulator is their first view of the plant running. It provides an Integrated Environment testing out design assumptions.For years simulators have been used to test the DCS implementation in non-nuclear applications, finding issues with control strategies as well as bugs in implementing the DCS when it is less costly to fix.From a human factors perspective, operating a nuclear plant almost totally from computer screens versus panel boards is a “radical” change. Presenting the right level of information, determining the navigation and conduct of operations, and testing out new operator aids such as electronic procedures and alarm handling systems are all effective uses of the simulator.For many of the new plants, operating procedures just don’t exist and the simulator is a perfect tool for developing the procedures and corresponding training materialsFinally at the end of the day, you also have your ANS 3.5 simulator available for use in licensing operators
  2. SimultaneouslyCompare current trending with reference data.Statistical built-in functions to evaluate code performance, such as sensitivity & uncertainty study.Give insight to code users.Simultaneous code performance, do not need to wait until code to be terminated to know how code performs comparing with reference data.
  3. demo case was applied to both desktop psa-hd & full-scope simulator PSA-HD.Desktop PSA-HD does not include S3R & BOP. Has successfully run the different transient for 32 hours.Full-scope PSA-HD has interfaces built-in and integrated with full-scope simulator. Has successfully run LOCA for more than 8 hours.