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Systems > Rx Vessel & Internals

Rx Vessel & Internals

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Rx Vessel & Internals

Function

The reactor vessel contains the reactor core, core support structures, control rods, thermal shield, and other parts directly associated with the core. It provides the primary pressure boundary at the core region. (UFSAR 5.1, 5.4)

The reactor core generates thermal energy through controlled nuclear fission. It consists of 193 fuel assemblies arranged in a 17x17 rod array, cooled and moderated by light water at 2250 psia. Boron dissolved in the coolant serves as a neutron absorber for slow reactivity control. Rod Cluster Control Assemblies (RCCAs) provide fast reactivity control and shutdown capability. (UFSAR 4.1)

Key Design Parameters

ParameterValueSource
Design/Operating Pressure2485 / 2235 psigUFSAR T5.2-3
Hydrostatic Test Pressure3107 psigUFSAR T5.2-3
Design Temperature650°FUFSAR T5.2-3
Overall Height (bottom head OD to top of CRDM adapter)43 ft 10 inUFSAR T5.2-3
ID at Shell173 inUFSAR T5.2-3
ID of Flange172.5 inUFSAR T5.2-3
OD of Flange205 inUFSAR T5.2-3
Inlet Nozzle ID27½ inUFSAR T5.2-3
Outlet Nozzle ID29 inUFSAR T5.2-3
Vessel Beltline Thickness (min, base metal)8.5 inUFSAR T5.2-3
Lower Head Thickness (min, base metal)5⅜ inUFSAR T5.2-3
Closure Head Thickness7 inUFSAR T5.2-3
Clad Thickness (min)5/32 inUFSAR T5.2-3
Number of Closure Head Studs54UFSAR T5.2-3
Diameter of Closure Head Studs7 inUFSAR T5.2-3
Minimum Insulation Thickness3 inUFSAR T5.2-3

Vessel Volumes

ParameterValueSource
Total Water Volume Below Core1050 ft³UFSAR T5.2-3
Water Volume in Active Core Region665 ft³UFSAR T5.2-3
Total Water Volume to Top of Core2164 ft³UFSAR T5.2-3
Total Water Volume to Nozzle Centerline2959 ft³UFSAR T5.2-3
Total Vessel Water Volume (with core and internals)4945 ft³UFSAR T5.2-3

Construction

  • Cylindrical vessel with welded hemispherical bottom head
  • Removable, flanged and gasketed, hemispherical upper head
  • Inlet and outlet nozzles in horizontal plane just below vessel flange, above top of core
  • Flow path: coolant enters inlet nozzles → flows down core barrel-vessel wall annulus → turns at bottom → flows up through core → exits outlet nozzles
  • Head adaptors (tubular members) attached by partial penetration welds to closure head underside, with acme threads for CRDM assembly
  • Seal arrangement: welded flexible canopy seal at upper end of head adaptors
  • Bottom head contains penetration nozzles for in-core instrumentation (partial penetration welds)
  • (UFSAR 5.1)

Closure Head

  • Replacement closure heads on both Unit 1 and Unit 2 (no CET column penetrations)
  • Original heads had 5 CET column penetrations (cut and capped)
  • Head vent tap adjacent to center penetration near top of dome
  • (UFSAR 5.1)

Vessel Surveillance Program

  • Surveillance capsules monitor neutron fluence and material property changes
  • Capsules contain Charpy impact, tensile, and compact tension specimens
  • Program complies with 10CFR50 Appendices G and H, and ASTM E185
  • (UFSAR 5.4.3, 5.2.4.4)

Core Parameters

ParameterValueSource
Reactor Core Heat Output3459 MWtUFSAR T4.1-1
Reactor Core Heat Output11844 x 10⁶ Btu/hrUFSAR T4.1-1
Heat Generated in Fuel97.4%UFSAR T4.1-1
Nominal System Pressure2250 psiaUFSAR T4.1-1
Equivalent Core Diameter132.7 inUFSAR T4.3-1
Core Average Active Fuel Height143.7 inUFSAR T4.3-1
Height-to-Diameter Ratio1.09UFSAR T4.3-1
Total Cross Section Area96.06 ft²UFSAR T4.3-1
H₂O/U Molecular Ratio (cold)2.41UFSAR T4.3-1

Reflector

LocationCompositionThicknessSource
TopWater plus steel~10 inUFSAR T4.3-1
BottomWater plus steel~10 inUFSAR T4.3-1
SideWater plus steel~15 inUFSAR T4.3-1

Fuel Assemblies

ParameterValueSource
Number of Fuel Assemblies193UFSAR T4.3-1
Rod Array17 x 17UFSAR T4.3-1
Rods per Assembly264UFSAR T4.3-1
Rod Pitch0.496 inUFSAR T4.3-1
Overall Dimensions8.426 x 8.426 inUFSAR T4.3-1
Guide Thimbles per Assembly24UFSAR T4.3-1
Loading Technique3 Region Non-uniformUFSAR T4.1-1
DesignRCC CanlessUFSAR T4.1-1

Fuel Assembly Types

Salem cores may use any combination of: Vantage 5H, Vantage+, and Robust Fuel Assembly (RFA/RFA-2). The most significant difference is the use of ZIRLO cladding in Vantage+ and RFA designs. (UFSAR 4.1)

Grid Assemblies

Fuel TypeGridsSource
V5H2 Inconel (top/bottom) + 6 Zircaloy-4 (mid)UFSAR T4.3-1
V+2 Inconel (top/bottom) + 6 ZIRLO (mid)UFSAR T4.3-1
RFA2 Inconel (top/bottom) + 1 Inconel (protective) + 6 ZIRLO (mid) + 3 ZIRLO (IFM)UFSAR T4.3-1

Fuel Rods

ParameterValueSource
Number in Core50952UFSAR T4.3-1
Outside Diameter0.374 inUFSAR T4.3-1
Diametral Gap0.0065 inUFSAR T4.3-1
Clad Thickness0.0225 inUFSAR T4.3-1
Clad Material (V5H)Zircaloy-4UFSAR T4.3-1
Clad Material (V+, RFA)ZIRLOUFSAR T4.3-1

Fuel Pellets

ParameterValueSource
MaterialUO₂ SinteredUFSAR T4.3-1
Density95.5% theoreticalUFSAR T4.3-1
Diameter0.3225 inUFSAR T4.3-1
Length (STD)0.530 inUFSAR T4.3-1
Length (V5H, V+, RFA solid)0.387 inUFSAR T4.3-1
RFA Annular Pellet ID0.155 inUFSAR T4.3-1
Mass of UO₂ per Foot (V5H, V+)0.364 lb/ftUFSAR T4.3-1
Mass of UO₂ per Foot (RFA)0.355 lb/ftUFSAR T4.3-1

All fuel rods are pressurized with helium during fabrication to reduce stresses/strains and increase fatigue life. RFA fuel rods use annular pellets at the top and bottom 6 inches for lower rod internal pressures. ZIRLO fuel rods may be oxide coated at the lower end for fretting protection. (UFSAR 4.1)

Rod Cluster Control Assemblies (RCCAs)

ParameterValueSource
Neutron AbsorberAg-In-Cd (80-15-5%)UFSAR T4.3-1
Absorber Diameter0.381 inUFSAR T4.3-1
Absorber Density0.367 lb/inUFSAR T4.3-1
Cladding MaterialType 316L SS, Ionnitride surfaceUFSAR T4.3-1
Clad Thickness0.0185 inUFSAR T4.3-1
Number of Full-Length Clusters53UFSAR T4.3-1
Absorber Rods per Cluster24UFSAR T4.3-1
Full Length Assembly Weight (dry)149 lbUFSAR T4.3-1

Each RCCA consists of individual absorber rods fastened to a common spider assembly. The control rod drive mechanisms are magnetic latch type — upon loss of power to the coils, the RCCA releases and falls by gravity to shut down the reactor. (UFSAR 4.1)

Burnable Absorbers

TypeMaterialKey ParameterSource
PYREXBorosilicate glass12.5 w/o B₂O₃UFSAR T4.3-1
WABAAl₂O₃-B₄C compound0.7 fraction theoretical densityUFSAR T4.3-1
IFBAZrB₂ coating1.570–2.355 mg B-10/inUFSAR T4.3-1

Core Structure

ParameterValueSource
Core Barrel ID/OD148.0 / 152.5 inUFSAR T4.1-1
Thermal Shield ID/OD158.5 / 164.0 inUFSAR T4.1-1

Reactor Internals

Three main components:

  1. Lower core support structure — includes entire core barrel and thermal shield
  2. Upper core support structure — maintains alignment between fuel assemblies and CRDMs
  3. In-core instrumentation support structure — provides guides for in-core instruments

Functions: support core, maintain fuel alignment, limit fuel assembly movement, direct coolant flow, provide gamma/neutron shielding, guide in-core instrumentation. (UFSAR 4.1)

Core Average Linear Power and Hot Channel Factors

ParameterValueSource
Core Average Linear Power5.52 kW/ftUFSAR T4.3-2
Total Heat Flux Hot Channel Factor (FQ)2.40UFSAR T4.3-2
Nuclear Enthalpy Rise Hot Channel Factor (F-delta-H, RFA)1.65UFSAR T4.3-2
Nuclear Enthalpy Rise Hot Channel Factor (F-delta-H, V5H)1.57UFSAR T4.3-2
Maximum Heat Flux (normal operation)461930 Btu/hr-ft²UFSAR T4.4-1
Maximum Thermal Output (normal operation)13.3 kW/ftUFSAR T4.4-1
Peak Linear Power for Protection Setpoints≤22.4 kW/ftUFSAR T4.1-1
Peak Fuel Center Temp at Max Overpower Trip<4700°FUFSAR T4.1-1

Reactivity Coefficients

ParameterValueSource
Moderator Temperature Coefficient (operating)0 to -44 pcm/°FUFSAR T4.3-2
Boron Coefficient-16 to -6 pcm/ppmUFSAR T4.3-2
Rodded Moderator Density Coefficient (operating)≤ +0.52 x 10⁵ pcm/gm/ccUFSAR T4.3-2
Doppler CoefficientSee UFSAR Figures 4.3-17/18UFSAR T4.3-2
Moderator Void Coefficient (BOL, low temp)50 pcm/% voidUFSAR 4.3.2.3
Moderator Void Coefficient (EOL, operating temp)-250 pcm/% voidUFSAR 4.3.2.3

Note: 1 pcm = 10⁻⁵ delta-rho. The MTC becomes more negative with fuel burnup as boron concentration decreases. The power coefficient (combined moderator + Doppler) also becomes more negative with burnup. (UFSAR 4.3.2.3)

Delayed Neutron Fraction

ParameterBOLEOLSource
Beta-effective0.00750.0044UFSAR T4.3-2

Control Rod Worths

ParameterValueSource
Maximum Bank Worth<2000 pcmUFSAR T4.3-2
Total Rod Worth (53 RCCAs, all in) BOL8.595 %delta-rhoUFSAR T4.3-3
Total Rod Worth (53 RCCAs, all in) EOL8.00 %delta-rhoUFSAR T4.3-3
N-1 Rod Worth (highest worth stuck out) BOL6.85 %delta-rhoUFSAR T4.3-3
N-1 Rod Worth (highest worth stuck out) EOL6.30 %delta-rhoUFSAR T4.3-3
Available with 10% uncertainty (N-1 - 10%) BOL6.17 %delta-rhoUFSAR T4.3-3
Available with 10% uncertainty (N-1 - 10%) EOL5.67 %delta-rhoUFSAR T4.3-3

Reactivity Requirements (Control Rod Rack-up)

Reactivity EffectBOL (%delta-rho)EOL (%delta-rho)Source
Fuel Temperature (Doppler)1.321.30UFSAR T4.3-3
Moderator Temperature0.111.25UFSAR T4.3-3
Void0.010.05UFSAR T4.3-3
Redistribution0.500.85UFSAR T4.3-3
Rod Insertion Allowance0.500.50UFSAR T4.3-3
Rod Misalignment Relaxation0.120.12UFSAR T4.3-3
Total Control Required2.564.07UFSAR T4.3-3
Shutdown Margin Available3.611.60UFSAR T4.3-3

Design basis minimum shutdown margin: 1.3 %delta-rho. The largest control requirement is at EOL when the MTC is most negative. (UFSAR T4.3-3)

Boron Concentrations

ConditionBoron (ppm)Source
Refueling (ARI, k<0.95)≥2050UFSAR T4.3-2
HZP, ARO (k=1.0)1700–1950UFSAR T4.3-2
HFP, ARO, 0 MWD/MTU, No Xenon1400–1700UFSAR T4.3-2
HFP, ARO, 150 MWD/MTU, Eq Xenon1000–1250UFSAR T4.3-2
HFP, ARO, 1000 MWD/MTU, Eq Xenon1000–1250UFSAR T4.3-2

Note: Values are typical reload values. Current cycle values are in the appropriate NDR or COLR. (UFSAR T4.3-2)

Maximum Core Reactivity

Maximum core reactivity (cold, zero power, BOC): 1.200 keff (typical reload). (UFSAR T4.3-1)

Reactivity Control Methods

  1. Chemical poison (boron): Dissolved in coolant, controlled by CVCS. Compensates for slow reactivity changes including fuel burnup, xenon/samarium transients, and moderator temperature changes.
  2. Rod Cluster Control Assemblies: 53 full-length clusters of Ag-In-Cd rods. Provide fast reactivity control and shutdown capability. Magnetic latch CRDMs release on loss of power.
  3. Burnable absorbers: PYREX, WABA, or IFBA rods placed in guide thimble positions to hold down excess BOL reactivity without increasing soluble boron beyond limits. (UFSAR 4.3.2.5)

Key Exam Concepts

  • The core is designed so that the highest worth stuck RCCA still allows adequate shutdown margin (≥1.3 %delta-rho)
  • MTC is required to be negative at power (TS limit) — verified by physics testing
  • FQ and F-delta-H limits are given in the COLR, not fixed in Tech Specs
  • The power coefficient becomes more negative with burnup (larger power defect at EOL)
Exam — 2023 Q71
Boron mixing during natural circulation vs forced circulation: more time is required to achieve complete mixing in the RCS during natural circulation (lower flow rate without RCPs). However, once mixing is complete, a 1 ppm increase in boron concentration produces the same change in reactivity regardless of whether the RCS is in forced or natural circulation. The reactivity effect of boron depends on concentration, not flow rate.
Exam — 2023 Q70
Xenon-135 following a reactor trip from 100% power: Xe-135 concentration peaks at approximately 4700 pcm at about 8-9 hours after the trip. After the peak, Xe-135 concentration decreases due to decay of I-135 and Xe-135. Decreasing Xe-135 inserts positive reactivity (Xe-135 is a fission product poison). At 12 hours post-trip with reactor at 5% power, Xe-135 is lowering — operator must add negative reactivity to maintain power and T-avg stable.
Exam — 2023 Q75
Axial peaking factor increase: with the core axial power distribution already peaked below the midplane, reducing RCS boron concentration (diluting) increases the maximum axial peaking factor. Dilution inserts positive reactivity, raising Tavg and hot leg temperature — hotter water in upper core regions is less dense (less moderation), shifting flux further toward the already flux-dense bottom half. Withdrawing control rods 4 steps reduces peaking (less flux depression). A dropped rod at the core edge affects radial peaking, not axial. A turbine load reduction lowers delta-T, pushing flux upward, also reducing axial peaking.

Tech Spec LCOs

  • TS 3/4.4 — Reactor Coolant System|TS 3/4.4.9 — RCS Specific Activity
  • Pressure-temperature limits governed by Appendix G analysis
  • TS 3/4.1TS 3/4.1.1 — Boration Control (shutdown margin, rod operability, rod insertion limits)
  • TS 3/4.2TS 3/4.2 — Power Distribution (FQ, F-delta-H, axial flux difference)
  • TS 3/4.1.1 — Shutdown Margin
  • TS 3/4.1.2 — Boration Systems (CVCS)
  • TS 3/4.1.3 — Movable Control Assemblies
  • TS 3/4.2.1 — Axial Flux Difference
  • TS 3/4.2.2 — Heat Flux Hot Channel Factor (FQ)
  • TS 3/4.2.3 — Nuclear Enthalpy Rise Hot Channel Factor (F-delta-H)

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