NPP Simulators Workshop for Education - Passive PWR …€¦ · · 2011-10-19NPP Simulators...
Transcript of NPP Simulators Workshop for Education - Passive PWR …€¦ · · 2011-10-19NPP Simulators...
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NPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview
Wilson Lam ([email protected]) CTI Simulation International Corp. www.cti-simulation.com
Sponsored by IAEA Modified for 2011 Presentation by Larry Foulke (Univ of Pittsburgh)
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Learning Objectives
• Discuss the pros and cons of training with a desktop simulator versus a full-scale, replica simulator.
• Describe how the CTI desktop simulation of a AP1000 differs from an actual AP1000.
• Develop skill and familiarity with the CTI desktop simulation.
• Explain and interpret information provided on the CTI simulator screens
• Interpret the tracking of elapsed time on the CTI desktop simulation
• Change y-axis scales on trend plots of the CTI simulator.
• Understand the control strategy and control systems of the CTI desktop simulations.
• Describe the importance of monitoring the axial power distribution and relate how it is measured.
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NPP Manpower Training Issue – important for Nuclear Renaissance
• Manpower Training for NPP - challenging issues – takes years to train competent NPP personnel, about the same time to build NPP.
• Traditional means of training through classroom and textbooks inadequate for reactor operator.
• Full scope training simulator often not completely in service until NPP in commercial operation.
• Is it cost effective to use full scope training simulator to train engineers and new recruits?
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Scope of Simulator Types versus Training Items
• Replica Full Scope Simulators - – Plant operation in a control room environment – Procedure based, cognitive skill based, team work
• Classroom/Desktop Simulators - – Configuration suited to classroom & self - learning
tool as complement to textbooks and manuals. – Provides knowledge of dynamic behavior – Provides subsystem training, as well as overall
plant training (startup, shutdown, malfunctions).
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Role of Desktop Simulators
• Provides initial educational training to all NPP personnel before NPP is built & full scope simulator in service.
• Provides knowledge of system interfaces, integration and interactions.
• Complements training on a full scope, replica simulator.
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Desktop Simulator Characteristics
• Relatively low cost and affordable. • Can use highly portable, standard PC
platforms. • Math models are easily configurable and
provide flexibility of use. • Can use graphic icons, control pop-ups,
time trends for user interfaces instead of hardwired panels.
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Classroom Simulator Utilization - Education
• As educational training tool – can provide a realistic interactive tool for educational study of NPP’s dynamics, and accident scenarios.
• Can be integrated with multi-media tools to enhance learning and knowledge acquisition.
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Pressurized Light Water Reactor •Reactor heats water from 279 (534) to 315 deg. C (600 F) •Pressurizer keeps coolant pressure 15.5 Mpa (2248 psi); boiling is not allowed. Thermal efficiency ~ 32 %. •Use Gen III+ Passive PWR AP-1000 as example.
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Passive PWR Simulator
• AP-1000 process design is used as a reference. • Reactor Controls based on Korean Standardized
1000 MW PWR Design –Mode K • SG pressure control to maintain setpoint at 5.7
KPa • Overall Unit Control allows Reactor-Leading or
Turbine-Leading Mode • Passive Systems modeled to demonstrate LOCA
mitigation
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Reactor Model
SYSTEM SIMULATION SCOPE DISPLAYPAGES
OPERATORCONTROLS
MALFUNCTIONS
REACTOR • neutron flux levels overa range of 0.001 to110% full power, 6
delayed neutron groups• decay heat (3 groups)• all reactivity controldevices - “dark” rods;
“gray” rods; boroncontrol.
• Xenon/Iodine poison• reactor power control
system• reactor shutdown system
• PWR powercontrol
• PWR controlrods & SD
rods• PWR tripparameters
• reactor power andrate of change
(input to controlcomputer)
• manual control ofreactivity devices- control rods and
boronaddition/removal• reactor trip
• reactor setback• reactor stepback
• reactor setback andstepback fail
• one bank of Darkcontrol rods drop
into the reactor core
SAFETYSYSTEM
• PWR passivecore cooling
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Advanced PWR Reactor Control
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Mode K Reactor Control Strategy • Double closed loop control of (1) reactor
coolant temp (2) axial power difference. • Heavy-worth control rods bank dedicated to
axial shape control. • Light-worth control rods bank for controlling
coolant temp at setpoint. • Auto regulation of both the reactivity and
power distribution - permits load-follow operations (frequency control) to respond to grid conditions, with minimum use of Boron.
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Reference Paper for Mode K Reactor Controls
• Korean Standardized 1000 MW PWR Design - YGN-3 NSSS Design
• Paper - “Automatic Reactor Power Control for a Pressurized Water Reactor “ by Jung-In Choi et al, Kyungwon University, Korea (August 27, 1992) - Nuclear Technology, Volume 102, May 1993, p.277
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Mode K Reactor Control Scheme
Limit control diagram.Designating Flux Tilt error as FT (%) Average Coolant Temperature error as DT (deg.
C)Region A: FT > 4; -0.5 < DT < 0.5Region C: FT < -4; -0.5 < DT < 0.5Region B: -4 < FT < 4; DT < -0.5Region D: -4 < FT < 4; DT > 0.5
Region E: the four cornersFT > 4; DT < -0.5;FT > 4; DT > 0.5;
FT < -4; DT < -0.5;FT < -4; DT > 0.5
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Reactor Power (%) Average Gray Rods Position (average of
the rod positions for the individual fourbanks)
0 – 10 % 93 % - 87 % in core 10 – 20 % 87 % - 83 % in core 20 – 30 % 83 % - 70 % in core 30 – 40% 70 % - 60 % in core 40 – 50 % 60 % - 53 % in core 50 – 60 % 53 % - 48 % in core 60 – 70 % 48 % - 44 % in core 70 – 80% 44 % - 40 % in core 80 – 90 % 40 % - 35 % in core 90 – 100 % 35 % - 30 % in core
Boron will be used if Gray rods limiting position has been reached
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Reactor Coolant System
• 2 heat transfer circuits, or 2 loops. • Each loop has one Steam Generator, one hot
leg(31-inch inside diameter), and two cold legs (22-inch inside diameter) for circulating reactor coolant for primary heat transport.
• One Pressurizer in one of the loops
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Reactor Coolant Pump • Two canned motor pumps mounted directly
in the channel head of each Steam Generator.
• No seals - cannot cause seal failure LOCA. • Allows pumps and SG to use the same
structural support; eliminates the crossover leg of coolant loop piping; reduces loop pressure drop; eliminates a potential of core uncovery due to loop seal venting during small LOCA.
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Reactor Coolant Pump (canned motor)
Stator winding
Impeller
motor
Journal Bearing
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Pressurizer
• Standard Westinghouse Design used in existing PWRs.
• 1600 cubic feet; 30 % larger - increases transient margin and eliminates the need for relief valve actuation - eliminates one possible source of RCS leakage and maintenance.
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Pressurizer
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Reactor Coolant Model
REACTORCOOLANT
• main circuit coolantloop with four pumps,two steam generators,
four equivalent“lumped” reactorcoolant channels
• pressure and inventorycontrol which includes
pressurizer, coolantletdown condenser,charge & letdown
control, and pressurerelief
• operating range is fromzero power hot to full
power
• PWR reactorcoolant system• PWR coolant
inventory &pressurizer• PWRinventorycontrol
• PWR pressurecontrol
• reactor coolantpumps
• coolant makeuppumps
• pressurizerpressure control:heaters; spray;pressure relief
valve• pressurizer level
control byregulating coolantfeed & bleed flow• isolation valvesfor: coolant feed
and bleed
• Pressurizer pressurerelief valve fails
open• charging (feed)
valve fails open• letdown (bleed)
valve fails open• pressurizer heaters
#2 to # 6 turned"ON" by
malfunction• reactor header break
SYSTEM SIMULATION SCOPE DISPLAYPAGES
OPERATORCONTROLS
MALFUNCTIONS
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Steam Generators
• Based on standard Westinghouse Model F technology.
• U-tube SG design, using Inconel 690 for tube material - enhanced reliability - Westinghouse claims less than 1 tube plugged per SG per four years of operation.
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Steam Generator
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Steam & Feedwater SYSTEM SIMULATION SCOPE DISPLAY
PAGESOPERATORCONTROLS
MALFUNCTIONS
STEAM &FEEDWATER
• boiler dynamics,including shrink and
swell effects• steam supply to turbine
and reheater• turbine by-pass to
condenser• extraction steam to feed
heating• steam generator pressure
control• steam generator level
control• boiler feed system
• PWRfeedwater &extraction
steam
• feed pump on/offoperation
• boiler levelcontroller mode:Auto or manual• level controlsetpoint duringAuto operation
• level control valveopening during
manual operation• extraction steam
valves opening
• all level controlisolation valves fail
closed• one level control
valve fails open• one level control
valve fails closed• all feed pumps trip• all steam safety
valves open• steam header break
• steam flowtransmitter fails
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PWR Characteristics with constant SG pressure – This Simulator
Typical PWR Characteristics
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275
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285
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300
0% 20% 40% 60% 80% 100% 120%
Power (%)
Tem
o (D
eg. C
)
0
1
2
3
4
5
6
7
Boile
r Pre
ssur
e (M
Pa)
Sat Liquid Temp (C)Coolant TempBoiler Pressure (Mpa)
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German PWR Design German PWR Characteristics
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0% 20% 40% 60% 80% 100% 120%
Power (%)
Tem
p (d
eg. C
)
5.6
5.8
6
6.2
6.4
6.6
6.8
Boi
ler P
ress
ure
(MPa
)
Sat Liquid Temp (C)Coolant Temp (C)Boiler Pressure (Mpa)
Reference: Features of KWU Type NPPs and their Leittechnik System - IAEA Technical Reports Series 387, 1999
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Response Curves
From Schultz “Control of Nuclear Reactors and Power Plants (1961)
Constant Tav Program
Advantages:
•Least amount of external control
•Preferred by reactor
•Small pressurizer (minimum expansion of coolant volume as power changes)
Disadvantages
•Drop off of steam temperature and pressure
•Poor turbine efficiency
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Turbine Generator
SYSTEM SIMULATION SCOPE DISPLAYPAGES
OPERATORCONTROLS
MALFUNCTIONS
TURBINE-GENERATO
R
• simple turbine model• mechanical power and
generator output areproportional to steam flow
• speeder gear and governorvalve allow synchronized
and non-synchronizedoperation
• PWR turbinegenerator
• turbine trip• turbine run-back• turbine run-up and
synchronization• condenser steam
discharge valves
• turbine spurious trip• turbine spurious
run-back
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Overall Unit
OVERALLUNIT
• fully dynamic interactionbetween all simulated
systems• overall unit power control
with reactor leading mode;or turbine leading mode
• unit annunciation & timetrends
• computer control of allmajor system functions
• PWR plantoverview
• PWR controlloops
• PWR MWdemand SP &
SGPC
SYSTEM SIMULATION SCOPE DISPLAYPAGES
OPERATORCONTROLS
MALFUNCTIONS
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Reactor Lead Control
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Reactor Lead Power Change
• Demonstrate power change using reactor lead
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Turbine Lead Power Change
• Demonstrate power change using turbine lead
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Passive Safety Systems
• Requires no operator actions to mitigate design basis accidents.
• Rely on natural forces - gravity, natural circulation, compressed gas; no pumps, fans diesels, chillers used. Only few simple valves, supported by reliable power sources
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Passive Core Cooling (PXS) The PXS uses three sources of water to
maintain core cooling: • Core Makeup Tanks (CMTs) • Accumulators • In-containment Refueling Water Storage
Tank (IRWST) • These injection sources are all connected to
two nozzles on the reactor vessel.
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In-containment refuelling water storage tank
Injection Sources
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Passive Core Cooling System
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High Pressure Safety Injection with CMTs
• Two Core Makeup Tanks (CMTs), filled with borated water, located above the RCS loop piping.
• Make up for small leaks following transients or whenever the normal makeup system is unavailable.
• Designed for full RCS pressure using gravity. • Poised to be in-service when water level in the pressurizer
reaches a low-low level: – reactor scrammed; the reactor coolant pumps tripped;
the CMT discharge isolation valves open automatically. – The relative elevations of the CMTs and the pressurizer
are such that if RCS level continued to decrease, the water in the CMTs would drain into the reactor vessel.
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Medium Pressure Safety Injection with Accumulators
• Accumulators for large LOCAs - for higher initial makeup flows to rapidly refill the reactor vessel lower plenum and downcomer following RCS blowdown.
• The gas pressure forces open check valves that normally isolate the accumulators from the RCS.
• Accumulators sized to respond to complete severance of the largest RCS pipe.
• The accumulators continue delivery to assist the CMTs in rapidly reflooding the core.
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In-containment refuelling water storage tank
Injection Sources
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Low Pressure Reactor Coolant Makeup from the IRWST - long Term Injection
• In-containment Refueling Water Storage Tank (IRWST) for long-term injection water located in the containment just above the RCS loops.
• IRWST normally isolated from the RCS by self-actuating check valves. This tank is designed for atmospheric pressure.
• The RCS must be depressurized before injection. The automatic depressurization system (ADS) made up of four stages of valves to permit a relatively slow, controlled RCS pressure reduction to 10 psig.
• The ADS stages are actuated by CMT level. The first three stages are connected to the pressurizer and discharge through spargers into the IRWST. The fourth stage is connected to a hot leg and discharges through redundant isolation valves to the containment.
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In-containment refuelling water storage tank
Injection Sources
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• Passive residual heat removal (PRHR) subsystem protects the plant against transients that upset the normal steam generator feedwater and steam systems - loss of feedwater, feedwater line breaks, and steam line breaks with a single failure.
Passive Core Cooling System - Residual Heat Removal
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Passive Residual Heat Removal System Enough water to absorb
decay heat > 1 hour before water begins to boil. Steam passes to containment, and condenses on steel containment vessel, and drains back to IRWST
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AP1000 Operating Characteristics Withstand the following operations without reactor
scram or actuation of safeguard systems - • From 15 % - 100 % FP, +/- 5 % /minute ramp load
change; • From 15 % - 100 %, +/- 10 % step load change • 100 % load rejection • Daily load following • Grid frequency changes 10 % peak-to-peak, at 2 %
per minute rate • 20 % power step increase or decrease in 10 minutes • loss of single feedwater pump.
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PWR Simulator
• Run the PWR Simulator • View all the Simulator Screens
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Answer to PWR Response to Boiler Press Changes Question
• At steady state: SG Q = Core Q • SG Q = UA (Tav -Ts); Tav = (To+Ti)/2 Ts - Sat Steam Temp.; To, Ti - coolant T’s • SG P Ts Q --> SG Q > Core Q Prim Coolant T --> positive reactivity feedback
• SG P Ts Q --> SG Q < Core Q Prim Coolant T --> negative reactivity feedback