Evolution of ACR Physics from CANDU 6 · Diameter = 760 cm ( 299 inches) ACR 731 MWe 284 channels...
Transcript of Evolution of ACR Physics from CANDU 6 · Diameter = 760 cm ( 299 inches) ACR 731 MWe 284 channels...
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Evolution of ACR Physics from CANDU 6
By Peter Chan, ACR Fuel & Physics Section Head
Presented to US Nuclear Regulatory CommissionOffice of Nuclear Reactor Regulation
December 4, 5, 2002 at CRL
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Outline
� Major differences between ACR and CANDU 6 CoreDesigns� Coolant� Fuel� Lattice Pitch
� Core Physics of ACR� High Power Output in a Compact Core� Negative Power Feedback Reactivity Coefficients� Negative Coolant Void Reactivity� Unique LOCA features
� Summary
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Major Differences betweenCANDU 6 and ACR
� Coolant� CANDU 6 (D2O )� ACR (H2O)
� Fuel� CANDU 6 (NU in 37-element bundle)� ACR (2.0 % SEU in 42 pins, Central Pin Dy/NU, CANFLEX
bundle)
� Lattice Pitch� CANDU 6 (28.575 cm, 11.25 inches)� ACR (22.0 cm, 8.66 inches)
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Comparison of CANDU 6 and ACR Lattices
CANDU 6 Lattice
ACR Lattice
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CANDU 6728 MWe380 channelsDiameter = 760 cm ( 299 inches)
ACR 731 MWe 284 channelsDiameter = 520 cm ( 205 inches)
Core Size Comparison
Calandria volume reducedby a factor of 2.5 (smallerlattice pitch).By using H2O coolant, lessthan 25% of D2O used in C6is required.
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Reactivity Effects in ACR-700 and CANDU 6(Equilibrium Core)
+10 to +15 mk-3.0 mkFull-Core Coolant-VoidReactivity
~ 0-0.07 mk/% powerPower Coefficient (95% -105% full power)
small negative-0.008 (mk/ �F)Fuel Temperature effect
positive-0.006 (mk/�F )Coolant Temperature(including density) effect
slightly positive-0.013 (mk/�F )Moderator Temperature(including density) effect
CANDU-6ACR-700
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Safety & Control Parameters in ACR-700 and CANDU 6
14 Controllers in7 Assemblies
18 Controllers in9 Assemblies
Bulk & Spatial Control
0.920.33Prompt Neutron Lifetime( millisecond)
6 Poison Nozzles(core region)
6 Poison Nozzles(reflector region)
Shutdown System (SDS2)
28 AbsorberRods
20 AbsorberRods
Shutdown System (SDS1)
4 MechanicalAbsorber rods
4 MechanicalAbsorber Rods
Fast Power Reduction
0.00580.0056Total Delayed NeutronFraction ( ß )
CANDU 6ACR-700
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Effect of Prompt Neutron Lifetime on Power Transients
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Time (second)
Rel
ativ
e Po
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l*=0.33 ms +1 mk Stepl*=0.90 ms +1 mk Stepl*=0.33 ms +3 mk Stepl*=0.90 ms +3 mk Stepl*=0.33 ms +0.5 mk Stepl*=0.90 ms +0.5 mk Stepl*=0.33 ms -3.0 mk Stepl*=0.90 ms -3.0 mk Step
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Characteristics of ACR-700 and CANDU 6
7.520.5Core-AveragedBurnup (MWd/kgU)
165.8Fueling Rate(Bundles per Day)
23Channel Visits/Day
37 NU pins2.0% in 42 pinsCentral NU/Dy pin
Fuel Enrichment
728731Gross ElectricalPower ( MW)
20641982Reactor ThermalPower ( MW)
380284Fuel Channels
CANDU 6ACR-700
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CANDU Fuel Bundle Designs
37-Element37-Element BundleBundleC6 Fuel ChannelC6 Fuel Channel
CANFLEXCANFLEXBundleBundle (43 elements) (43 elements)ACR Fuel ChannelACR Fuel Channel
Dy
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Effects of CANFLEX SEU Fuel in ACR� Enables the use of H2O Coolant� Allows the reduction of moderator to reduce Coolant Void
Reactivity ( CVR)� Allows the use of neutron absorber in the central fuel pin to
further reduce CVR to target of – 3 mk� High fuel burnup and high power output� Flat radial channel power profile ( 0.93 form factor)� Reduction in maximum fuel element rating� Inlet skewed axial power profile improves thermalhydraulic
margin
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Element Ratings ( ACR vs CANDU-6)for 900 kW bundle power at mid-burnup
-15.2 **57.248.5Ring 4
-18.546.537.9Ring 3
+ 6.141.343.8Ring 2
- 52.139.719.0Ring 1(Central)
% ChangeACR vs C-6
C-6 ( 37-el NU)(kW/m)
ACR (Canflex SEU) ( kW/m)
** lower element rating allows higher power and higher burnup
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End-View of ACR-700
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Pg 14 Schematic Face View of CANDU 6 Reactor
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Radial Thermal Flux Profiles
ACR-700 CANDU-6
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Axial Thermal Flux Profiles
ACR-700 CANDU 6
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Channel Power Profiles in ACR-700 and CANDU 6
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-12 -11 -10 -9 -8 -7 -6 -5 -4 -3 -2 -1 0 1 2 3 4 5 6 7 8 9 10 11 12
Channels from Centre of Reactor Core (Central Row)
Cha
nnel
Pow
er (
MW
)
ACR-700CANDU-6
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Axial Power Profiles in ACR and in C6
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Bundle Position from Inlet End ( Channel Power = 7.5 MW)
Bun
dle
Pow
er (k
W)
ACR 2-bundle-shift
C6 8-bundle-shift
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Effect of Coolant Void in ACR� ACR lattice is under-moderated with normal H2O coolant� H2O acts as both coolant and moderator� LOCA further reduces moderation from the lattice� Coolant Void Reactivity (CVR) is a combined effect due to loss of
absorption (positive) and loss of moderation (negative) from H2O� Increase in fast flux and decrease in thermal flux upon LOCA� U238 and Pu239 generate negative components in CVR
� Increase in Resonance Absorption (1 eV to 100 keV) in U238� Decrease in Fission (0.3 eV resonance) in Pu239
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Physics Innovations to achieve slightlynegative CVR ( H2O Coolant)
� Large Moderator/Fuel ratio (Vm/Vf) means high CVR� Current Lattice Pitch ( LP) 28.575 cm ( 11.25 inches ) Vm/Vf =16.4 CVR = + 60 mk� Target CVR = -3 mk requires Vm/Vf < 6.0, 0 LP < 20 cm (7.87 inches)� Minimum LP = 22 cm ( 8.66 inches) required to provide space for feeders
between channels Vm/Vf = 8.4
� Use larger CT, OR =7.8 cm (3.07 inches) to displace more moderator� Vm/Vf = 7.1� Add Dy (4.6% ) to central NU pin CVR = - 3 mk
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Neutron Flux Averaged over Fuel and Coolant within thePressure Tube (MCNP Model)
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1.E-09 1.E-08 1.E-07 1.E-06 1.E-05 1.E-04 1.E-03 1.E-02 1.E-01 1.E+00 1.E+01 1.E+02
Neutron Energy, MeV
Nor
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ized
flux
per
uni
t let
harg
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normal void
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Absorption Cross Section of 238U
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Fission Cross Section of 239Pu
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Change in Power/Flux Profile due to LOCAfor 900 kW bundle power at mid-burnup of ACR CANFLEX Fuel
- 6.845.248.5Ring 42 % SEU
+ 4.039.437.9Ring 32 % SEU
+ 17.250.243.8Ring 22 % SEU
+ 21.1 **23.019.0Ring 1 (Central Pin)NU + 4.6 wt% Dy
% Changedue to LOCA
ACR Voided( kW/m)
ACR Cooled( kW/m)
** current CVR design target is – 3 mk -10 mk CVR can be achieved by using less than 10 wt% Dy in the central pin
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Typical Power Pulses in CANDU 6 for Individual Bundle and for Broken- &Intact-Loop Core Halves
• Fast power rise due to positive CVR
• Power transient quickly terminated by
• Fast response neutron detectors
• 2 independent fast acting shutdown systems
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Unique LOCA Features in ACR
• Power in reactor core region drops upon LOCA due tonegative void reactivity
• LOCA power transients not sensitive to trip time(relative to CANDU 6)
• Rapid rise in thermal neutron flux in the reflector regiondue to migration and subsequent thermalization of fastneutrons from the core region
• Fast neutronic trip is available from neutron detectors inthe reflector region
• Slower process trip is sufficient to terminate LOCA
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Effect of Trip Time on LOCA TransientACR 100% RIH LOCA Transient
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CVR -3 mk, Trip at 1 s, 1.36 FPS
CVR -3 mk, Trip at 2 s, 2.11 FPS
CVR -3 mk, Trip at 3 s, 2.81 FPS
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Distance from Edge of Reflector (cm)
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T=0.020s
T=0.030s
Thermal Neutron-Flux Distributionsin ACR-700 after LOCA
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Thermal Flux Profile upon LOCA at t=0 s
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Thermal Flux Profile upon LOCA at t=0.015 s
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Thermal Flux Profile upon LOCA at t=0.02 s
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Thermal Flux Profile upon LOCA at t=0.03 s
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Thermal Flux Profiles in ACR-700 upon LOCA( click picture to start animation )
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Thermal Flux Ratios in ACR-700 upon LOCA( click picture to start animation )
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Summary� ACR is an evolutionary design of current CANDUs
� Common features between ACR and current CANDUs:� Horizontal fuel channels� D2O moderator� On-power fueling� Simple fuel bundle design
� ACR specific features:� H2O coolant� Smaller lattice-pitch and compact reactor core� High burnup SEU fuel� High power output� Negative coolant void reactivity� Negative power feedback coefficients
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