The reactor vessel assembly of SMART contains its major primary systems such as fuel and core, eight SGs, a PZR, four RCPs and 25 CRDMs in a single pressurized reactor vessel (PRV) as shown in Figure 15.5. The integrated arrangement of these components enables the removal of the large size pipe connections between major reactor coolant systems, and thus fundamentally eliminates the possibility of LB LOCAs. This feature, in turn, becomes a contributing factor for the safety enhancement of SMART. The reactor coolant forced by RCPs installed horizontally at the upper shell of the reactor pressure vessel (RPV) flows upward through the core, and enters the shell side of the SG from the top of the SG. The secondary side feedwater enters the helically coiled tube side from the bottom of the SG and flows upward to remove the heat from the shell side, eventually exiting the SG in a superheated steam condition. The large free volume in the top part of the RPV located above the reactor water level is used as a PZR region. As the steam volume of a PZR is designed to be sufficiently large, a spray is not required for a load maneuvering operation. The primary system pressure is maintained constant due
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Table 15.1 iPWR SMART technical data
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Description
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Value
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General plant data
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Reactor thermal output
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330 MWth
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Power plant output
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gross 100 MWe
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Power plant output
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net 90 MWe
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Power plant efficiency
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net 30.3%
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Mode of operation
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Load follow
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Plant design life
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60 years
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Plant availability target
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> 95%
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Seismic design, safe shutdown earthquake in g scale (SSE(g))
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0.3
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Primary coolant material
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Light water
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Moderator material
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Light water
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Thermodynamic cycle
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Rankin
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Type of cycle
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Indirect
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Non-electric applications
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Desalination, district heat
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Safety goals
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Core damage frequency/reactor-year
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< 1E-6
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Large early release frequency/reactor-year
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< 1E-7
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Occupational radiation exposure (Person Sievert/reactor year (Sv/RY))
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< 1.0
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Operator action time
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36 hours
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Economic goals
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Levelized unit electricity cost for nth-of-a-kind (NOAK) plant
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0.06
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Levelized unit cost of a non-electrical product for NOAK plant
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0.7
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Reactor core
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Active core height
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2.00 m
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Equivalent core diameter
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1.832 m
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Average linear heat rate
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10.97 KW/m
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Average core power density
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62.60 MW/m3
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Fuel material
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UO2
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Cladding material
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Zircaloy-4
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Lattice geometry
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Square
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Number of fuel assemblies
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57
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Enrichment of reload fuel at equilibrium core
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4.80 wt%
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Fuel cycle length
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36 months
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Average discharge burn-up of fuel
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36.1 MWd/kg
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Burnable absorber (strategy/material)
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Gd2O3-UO2
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Control rod absorber material
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Ag-In-Cd
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Mode of reactor shut-down control rods
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Soluble boron
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Primary coolant system
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Primary coolant flow rate
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2090 kg/s
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Reactor operating pressure
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15 MPa
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Core coolant inlet temperature
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295.7 °C
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Core coolant outlet temperature
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323 °C
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Table 15.1 Continued
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Description
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Value
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Power conversion system
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Working medium
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Steam
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Working medium flow rate at nominal conditions
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160.8 kg/s
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Working medium supply flow rate at nominal conditions
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13.4 kg/s
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Working medium supply temperature
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200 °C
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Reactor pressure vessel
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|
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Inner diameter of cylindrical shell
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5332 mm
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Design pressure
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17 MPa
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Design temperature
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360 °C
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Base material
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SA508, Class 3
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Total height
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15.5 m
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Steam generator or heat exchanger
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Number
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8
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Tube outside diameter
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17 mm
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Tube material
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Inconel 690
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Reactor coolant pump (primary circulation system)
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Circulation type
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Forced
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Number of pumps
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4
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Head at rated conditions
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27 m
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Flow at rated conditions
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0.89 m3/s
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Pressurizer
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Total volume
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61 m3
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Residual heat removal systems
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Active/passive systems
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Passive
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Safety injection systems
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Active/passive systems
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Active
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Primary containment
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Overall form (spherical/cylindrical)
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Cylindrical
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Dimensions — diameter
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44 m
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Design pressure
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0.42 MPa
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Turbine
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Number of turbine sections per unit (e. g. HP/MP/LP)
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1/0/1
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Turbine speed
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1800 rpm
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HP turbine inlet pressure
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5.2 MPa
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HP turbine inlet temperature
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296.4 °C
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Generator
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Number
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1
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Rated power
|
111 MV A
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Active power
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105 MW
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Voltage
|
18.0 kV
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Frequency
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60 Hz
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(Continued)
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Table 15.1 Continued
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Description
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Value
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Plant configuration and layout Plant configuration options
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Ground-based
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Surface area of the plant site
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99 800 ha
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Elevation or underground embedding of the nuclear island
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11.7 m
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Core catcher
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None/in Vessel retention-
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Protection against aircraft crash
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ex-reactor vessell cooling (IVR-ERVC) applied Yes
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Figure 15.5 SMART reactor vessel assembly.
to the large PZR steam volume and a heater control. The core exit temperature is programmed to maintain the primary system pressure constant during a load change. In this way, the reactor always operates at its own operating pressure range matched with the system condition. Eight SGs are located at the circumferential periphery
with an equal spacing inside the RPV and relatively high above the core to provide a driving force for a natural circulation of the coolant.
