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OKBM 1
International conference
“VVER-2010, Experience and Perspectives“
November 01-03, 2010, Prague
TVSA-T fuel assembly for “Temelin” NPP.
Main results of design and safety analyses.
Trends of development
O.B. Samoilov, V.B. Kaidalov, A.A. Falkov, V.A. Bolnov, O.N. Morozkin
JSC “Afrikantov OKBM”, N. Novgorod
V.L. Molchanov, A.V. Ugryumov JSC “TVEL”, Moscow
OKBM 22
INTRODUCTION
 TVSA is a fuel assembly with rigid skeleton formed by 6 angle
pieces and SG is successfully operated at 17 VVER-1000 power
units of Kalinin NPP, as well as, at the Ukraine and Bulgaria NPPs
 Within the contract for fuel supply for “Temelin” NPP, TVSA-T fuel
assembly was developed based on proven solutions confirmed by
operation of TVSA modifications during 4-6 years and by the
results of post-irradiation examination
 TVSA-T design is characterized by using of combined spacer grids
(SG+MG) and by fuel column elongation by 150 mm
 A set of analyses and experiments was performed to validate
TVSA-T design, including thermohydraulic tests, validation of
critical heat flux correlation for TVSA-T, integrated mechanical,
vibration and lifetime tests
 TVSA-T design was successfully licensed in SONS.
Now the TVSA-T core in operation at “Temelin” NPP unit 1.
OKBM 33
 Operational reliability and safety of fuel in
view of operation conditions as per operator
requirements
 Compatibility with reference fuel, in-reactor
structures and “Temelin” NPP equipment
 Elimination of fuel rod fretting damage
 Bending resistance – sufficient stiffness of
FA design (sags in homogeneous core ≤ 6
mm)
 Effective fuel consumption with high burnup
to 72 MW·day/kgU, flexible fuel cycle
 Structure dismountability to ensure leaky
fuel rod replacement
TVSA-T DESIGN BASIS
головка
ДР
хвостовик
Fuel rod
cluster
Top nozzle
SG
TVSA-T
Fuel rod
cluster
Bottom nozzle
OKBM 44
 6 angle pieces
 6 combined SG
 Lower antivibration assembly
 Fuel rods with increased uranium content and fuel
column elongated by 150 mm
 Enrichment for U235 – up to 4.95%
 Design dismountability and maintainability
 Debris filter
 Application of mixing grids - heat exchange
intensifiers (MG)
TVSA-T DESIGN DECISIONS
OKBM 55
TVSA-T COMBINED GRID
- Decrease of temperature gradient over TVSA cross section and
local steam content
- Increase of DNBR
MG application permits to increase core power and power
peaking factors
 The combined two-level SG consists
of cell-type SG and mixing grid TVSA-
ALFA in a single shell
 MG is a plate-type grid with flow
deflectors (vanes) without fuel rod
spacing
 The combined SGs ensure:
OKBM 6
TOP NOZZLE
Top nozzle consists of:
 upper shell;
 spacer skeleton;
 spring assembly;
 connecting elements
The top nozzle is fixed to guide
thimbles by collets
Upper shell
Spring assembly
Spacer skeleton
OKBM 7
BOTTOM NOZZLE
Casing
Ribs
Locking element
Debris filter
Bottom nozzle consists of:
 casing;
 support ribs;
 locking element.
The nozzle includes debris filter
catching particles above 2 mm
OKBM 88
MAIN CHARACTERISTICS OF TVSA-T CORE
Maximum core power 3030 MW
Fuel column height 3680 mm
Fuel rod outer diameter / fuel rod pitch 9.1 / 12.75 mm
Maximum relative rating of fuel rod 1.63
Maximum relative rating of FA 1.45
Average linear loading of fuel rod 156.3 W/cm
Maximum linear loading of fuel rod
at the height of 0.5 Нcore / at the height of 0.8
Нcore
448 / 375 W/cm
Fuel rod maximum burnup 72 MW day/kgU
Reference fuel cycle 5х320 EPPD
TVSA-T characteristics ensure operation in the conditions of
flexible fuel cycle with reduced neutron leak and possibility to
change lifetime duration within 230-500 EPPD
TVSA-T reference fuel cycle is five-year cycle with 36 makeup
FAs, duration is 320 EPPD
OKBM 99
 Mechanical tests of FA components, fragments and mockups to
determine bending and torsion stiffness, load bearing capacity
and stability
 Study of seismic stability and loading during LOCA
 Vibration tests of 3-span fragment in transverse-longitudinal
coolant flow
 Tests for RCCA drop
 Life tests of full-scale TVSA-T mockup under actual coolant
parameters
 Transport tests of full-scale FA mockup
To validate TVSA-T, the results of TVSA designs and its
modifications test results were also used
MAIN EXPERIMENTS TO VALIDATE THE MECHANICAL DESIGN
OKBM 10
THERMOHYDRAULIC TESTS
10
 Hydraulic tests of FA fragments and mockups including testing of
two full-scale TVSA-T mockups at OKBM RGS and LKP Skoda test
facilities under actual coolant parameters
 Testing of debris filter to determine hydraulic loss and effectiveness
of debris entrapping
 Investigations of local flow hydrodynamics using 57-rod TVSA
model
 Investigations and optimization of mixing grids
 Investigations of thermohydraulic characteristics and CHF on 19-rod
TVSA models at two thermophysical tests facilities in OKBM and
IPPE
 Validation of DNB correlation for TVSA-T
OKBM 1111
CHF COMPARISON FOR TVSA-T MODELS WITH CALCULATION
USING CORRELATION CRT-1
0 5 0 0 1 0 0 0 1 5 0 0 2 0 0 0 2 5 0 0 3 0 0 0
C H F c a lc u la t e d v a lu e s , k W /m 2
0
5 0 0
1 0 0 0
1 5 0 0
2 0 0 0
2 5 0 0
3 0 0 0
CHFexperimentalvalues,kW/m2
OKBM 12
MAIN ACTIVITIES FOR TVSA-T DESIGN
 TVSA-T design was validated by OKBM together with RRC
“Kurchatov Institute”, VNIINM and IPPE
Main activities for the design included the following:
- Design methodologies as per Customer requirements
- Development of the neutronic part of the design
- Development of the thermohydraulic part of the design
- Fuel rod and gadolinium fuel rod design development
- FA mechanical design development
- TVSA-T design validation by experiments
- Provision of TVSA-T compatibility with “Temelin” NPP design
- Development of safety analysis report (Chapter 4 and 15 SAR)
 The design was validated, and the accidents were analyzed using
the procedures based on VVER safety validation methodology
applied in Russia, Rostekhnadzor regulatory documentation in
view of Czech regulatory documentation requirements fulfillment
 The computer codes certified it Rostekhnadzor and licensed in
Czech regulatory body were used for design validation
12
OKBM 13
COMPUTER CODES FOR MECHANICS, THERMOHYDRAULICS AND
SAFETY ANALYSES
13
KANAL
FA and core subchannel
thermohydraulic analysis
Thermohydraulic Analysis
Non LOCA (RIA, LOFA)
TIGR
3-D neutron kinetics model
and subchannel TH model
LOCA
RELAP5/MOD3.2
Best estimate integral
thermohydraulic code
RAPTA-5
Fuel rod analysis
in accidents
Safety Analysis in Accidents
Thermomechanical Analysis
ANSYS
FA stress-strained state analysis.
Static and cyclic strength validation
OKBM 1414
SAFETY ANALYSIS
 Analysis of acceptance criteria sensitivity for main parameters and
substantiation of selection of conservative initial state and normal
operation system actuation scenario
 Safety analysis at PRPS operation
 Safety analysis when PRPS fails and DPS operates
 The analysis of LOCA was performed in co-operation with UJV Rez
OKBM 1515
LIST OF CRITERIA (CONDITION I - IV)
 Departure from nuclear boiling ratio
 Maximum temperature of fuel rod cladding
 Equivalent oxidation level of fuel rod cladding
 Oxidized zirconium quantity
 Maximum temperature of fuel
 Maximum average-radial enthalpy of fuel
 Number of leaky fuel rods
 Pressure in reactor plant circuits
The analysis results confirm that the design criteria are satisfied
during operation of TVSA-T fuel loadings in “Temelin” NPP core
in Condition I - IV
OKBM 1616
IMPROVEMENT OF DNBR VALIDATION PROCEDURE
 Validation of CHF and heat exchange coefficients correlation as a
part of subchannel code KANAL, used in the design, based on the
results of experiments with TVSA-T models
 Revising of engineering coefficients for power peaking factors and
coolant heating factor
 Statistical recording of local parameters deviations (∆q, ∆h, ∆corr)
at DNBR calculation based on provision of one-sided confidence
probability of 95%
 DNBR calculation for Condition II-IV is similar to Condition I with
application of hot assembly subchannel model in TIGR-1 code
This approach is implemented in TVSA-T design and “Temelin”
safety analysis
OKBM 1717
TVSA-T DESIGN DEVELOPMENT LINE
TVSA-T TVSA-T2
2 SG
6 CSG (SG+MG)
8 SG
3 MG
510х6=3060
SGandCSGpitch
255
Reduction in consumption of materials and
fabrication labor input
Improved fuel handling conditions (refueling
rate, SPR duration)
Skeleton bending stiffness enhancement
MG optimized design
OKBM 18
Twist - type flow By-row cross flow
MIXING GRID OPTIMIZATION
 Optimization developments and studies were performed to improve MG
effectiveness – optimization of dimension, inclination and location of
deflectors. MG was optimized with deflector location as per by-row cross flow
scheme
 Optimized MG is characterized by higher mixing efficiency and CHF
increase
 Positive experience of twist - type MG of TVSA operated at Kalinin NPP
during two fuel load
OKBM 19
RESULTS OF CHF INVESTIGATION OF OPTIMIZED MG
0 1 2 3 4 5 6
M a s s f lo w , k g /s e c
8 0 0
1 2 0 0
1 6 0 0
2 0 0 0
2 4 0 0
2 8 0 0Power,kW
W it h o u t M G
3 M G
3 o p t im iz e d M G
5 o p t im iz e d M G
P=15.7 MPa, Tin=290 °C
Critical power of TVSA models increased by 10-20% due to MG
OKBM 20
 Intercell exchange increase. Decrease of temperature gradient
over TVSA cross section and local steam quality by ~3%
 Increase of CHF and DNBR by ~15 - 30%
 Additional mixing grid effects:
- weaker CHF as a function of steam quality increases DNBR in
limiting modes of Condition 2
- less influence of axial profile on CHF (form factor effect)
increases DNBR in actual axial profile
 Possibility to increase core power and power peaking factors,
implementation of effective fuel cycles with increased power in fuel
rods
MAIN RESULTS OF MIXING GRID EFFICIENCY STUDY
OKBM 21
TVSA-12 Fuel Assembly
12 SG height is 35mm
 SG optimized position
 Skeleton bending stiffness
enhancement
 Operation reliability improvement
 Designed to operate in 5х1, 4х1 and
3х1.5 fuel cycles
 TVSA advantages application:
 reparability
 debris filter
 thermocontrol tubes
 antivibration SG
 Fuel rods with increased uranium
content (thinned cladding and
7.8/0mm fuel pellet
 High thermal performance due to MG
optimization
OKBM 2222
Thermal power, MW 3120
Inlet core temperature, °С 293.8
Pressure, MPa 15.7
Reactor flow rate, m3
/h 82000
Average linear power, W/cm 162.5
Maximum relative power of fuel rods, F∆h 1.63
Maximum linear power ql, W/сm 448
Minimum DNBR 1.47
Thermohydraulic characteristics of TVSA allow the core uprating
to 104% with fuel rod power peaking preservation F∆h=1.63
CORE UPRATING UP TO 3120 MWt
OKBM 2323
THERMAL CHARACTERISTICS OF TVSA CORE FOR FUTURE VVER
Based on the analysis results TVSA with MG for future VVER (MIR-1200)
ensures necessary thermal characteristics at core power 3300 MW with
increased allowable fuel rod power of F∆h=1.63
Thermal power, MW 3200 3300
Inlet core temperature, °С 298.2 298.6
Pressure, MPa 16.2 16.2
Reactor flow rate, m3/h 86000 86000
Average linear power, W/cm 168.7 174.0
Maximum relative power of fuel rods, F∆h 1.63 1.63
Maximum relative local power, FQ 2.38 2.31
Maximum linear power ql, W/сm
- at height of 0.5 Hcore
- at height of 0.8 Hcore
448
370
448
380
Minimum DNBR 1.52 1.43
OKBM 2424
CONCLUSION
 TVSA-T fuel assembly for “Temelin” NPP was validated. TVSA-T
design is based on approved technical decisions and meets the
current requirements for lifetime, operational maneuverability
and safety
 The results of post-irradiation examination of TVSA-T operated at
Kalinin NPP unit 1 during 4 years confirm the assembly
operability, skeleton stiffness, TVSA-T geometric stability and
normal fuel rod cladding condition
 Characteristics of TVSA with MG make possible core power
increase up to 3300 MW according to future VVER (MIR-1200)
design perspectives, providing allowable fuel rod power
F∆h =1.63 (to implement effective fuel cycles)

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TVSA-T fuel assembly for “Temelin” NPP. Main results of design and safety analyses. Trends of development

  • 1. OKBM 1 International conference “VVER-2010, Experience and Perspectives“ November 01-03, 2010, Prague TVSA-T fuel assembly for “Temelin” NPP. Main results of design and safety analyses. Trends of development O.B. Samoilov, V.B. Kaidalov, A.A. Falkov, V.A. Bolnov, O.N. Morozkin JSC “Afrikantov OKBM”, N. Novgorod V.L. Molchanov, A.V. Ugryumov JSC “TVEL”, Moscow
  • 2. OKBM 22 INTRODUCTION  TVSA is a fuel assembly with rigid skeleton formed by 6 angle pieces and SG is successfully operated at 17 VVER-1000 power units of Kalinin NPP, as well as, at the Ukraine and Bulgaria NPPs  Within the contract for fuel supply for “Temelin” NPP, TVSA-T fuel assembly was developed based on proven solutions confirmed by operation of TVSA modifications during 4-6 years and by the results of post-irradiation examination  TVSA-T design is characterized by using of combined spacer grids (SG+MG) and by fuel column elongation by 150 mm  A set of analyses and experiments was performed to validate TVSA-T design, including thermohydraulic tests, validation of critical heat flux correlation for TVSA-T, integrated mechanical, vibration and lifetime tests  TVSA-T design was successfully licensed in SONS. Now the TVSA-T core in operation at “Temelin” NPP unit 1.
  • 3. OKBM 33  Operational reliability and safety of fuel in view of operation conditions as per operator requirements  Compatibility with reference fuel, in-reactor structures and “Temelin” NPP equipment  Elimination of fuel rod fretting damage  Bending resistance – sufficient stiffness of FA design (sags in homogeneous core ≤ 6 mm)  Effective fuel consumption with high burnup to 72 MW·day/kgU, flexible fuel cycle  Structure dismountability to ensure leaky fuel rod replacement TVSA-T DESIGN BASIS головка ДР хвостовик Fuel rod cluster Top nozzle SG TVSA-T Fuel rod cluster Bottom nozzle
  • 4. OKBM 44  6 angle pieces  6 combined SG  Lower antivibration assembly  Fuel rods with increased uranium content and fuel column elongated by 150 mm  Enrichment for U235 – up to 4.95%  Design dismountability and maintainability  Debris filter  Application of mixing grids - heat exchange intensifiers (MG) TVSA-T DESIGN DECISIONS
  • 5. OKBM 55 TVSA-T COMBINED GRID - Decrease of temperature gradient over TVSA cross section and local steam content - Increase of DNBR MG application permits to increase core power and power peaking factors  The combined two-level SG consists of cell-type SG and mixing grid TVSA- ALFA in a single shell  MG is a plate-type grid with flow deflectors (vanes) without fuel rod spacing  The combined SGs ensure:
  • 6. OKBM 6 TOP NOZZLE Top nozzle consists of:  upper shell;  spacer skeleton;  spring assembly;  connecting elements The top nozzle is fixed to guide thimbles by collets Upper shell Spring assembly Spacer skeleton
  • 7. OKBM 7 BOTTOM NOZZLE Casing Ribs Locking element Debris filter Bottom nozzle consists of:  casing;  support ribs;  locking element. The nozzle includes debris filter catching particles above 2 mm
  • 8. OKBM 88 MAIN CHARACTERISTICS OF TVSA-T CORE Maximum core power 3030 MW Fuel column height 3680 mm Fuel rod outer diameter / fuel rod pitch 9.1 / 12.75 mm Maximum relative rating of fuel rod 1.63 Maximum relative rating of FA 1.45 Average linear loading of fuel rod 156.3 W/cm Maximum linear loading of fuel rod at the height of 0.5 Нcore / at the height of 0.8 Нcore 448 / 375 W/cm Fuel rod maximum burnup 72 MW day/kgU Reference fuel cycle 5х320 EPPD TVSA-T characteristics ensure operation in the conditions of flexible fuel cycle with reduced neutron leak and possibility to change lifetime duration within 230-500 EPPD TVSA-T reference fuel cycle is five-year cycle with 36 makeup FAs, duration is 320 EPPD
  • 9. OKBM 99  Mechanical tests of FA components, fragments and mockups to determine bending and torsion stiffness, load bearing capacity and stability  Study of seismic stability and loading during LOCA  Vibration tests of 3-span fragment in transverse-longitudinal coolant flow  Tests for RCCA drop  Life tests of full-scale TVSA-T mockup under actual coolant parameters  Transport tests of full-scale FA mockup To validate TVSA-T, the results of TVSA designs and its modifications test results were also used MAIN EXPERIMENTS TO VALIDATE THE MECHANICAL DESIGN
  • 10. OKBM 10 THERMOHYDRAULIC TESTS 10  Hydraulic tests of FA fragments and mockups including testing of two full-scale TVSA-T mockups at OKBM RGS and LKP Skoda test facilities under actual coolant parameters  Testing of debris filter to determine hydraulic loss and effectiveness of debris entrapping  Investigations of local flow hydrodynamics using 57-rod TVSA model  Investigations and optimization of mixing grids  Investigations of thermohydraulic characteristics and CHF on 19-rod TVSA models at two thermophysical tests facilities in OKBM and IPPE  Validation of DNB correlation for TVSA-T
  • 11. OKBM 1111 CHF COMPARISON FOR TVSA-T MODELS WITH CALCULATION USING CORRELATION CRT-1 0 5 0 0 1 0 0 0 1 5 0 0 2 0 0 0 2 5 0 0 3 0 0 0 C H F c a lc u la t e d v a lu e s , k W /m 2 0 5 0 0 1 0 0 0 1 5 0 0 2 0 0 0 2 5 0 0 3 0 0 0 CHFexperimentalvalues,kW/m2
  • 12. OKBM 12 MAIN ACTIVITIES FOR TVSA-T DESIGN  TVSA-T design was validated by OKBM together with RRC “Kurchatov Institute”, VNIINM and IPPE Main activities for the design included the following: - Design methodologies as per Customer requirements - Development of the neutronic part of the design - Development of the thermohydraulic part of the design - Fuel rod and gadolinium fuel rod design development - FA mechanical design development - TVSA-T design validation by experiments - Provision of TVSA-T compatibility with “Temelin” NPP design - Development of safety analysis report (Chapter 4 and 15 SAR)  The design was validated, and the accidents were analyzed using the procedures based on VVER safety validation methodology applied in Russia, Rostekhnadzor regulatory documentation in view of Czech regulatory documentation requirements fulfillment  The computer codes certified it Rostekhnadzor and licensed in Czech regulatory body were used for design validation 12
  • 13. OKBM 13 COMPUTER CODES FOR MECHANICS, THERMOHYDRAULICS AND SAFETY ANALYSES 13 KANAL FA and core subchannel thermohydraulic analysis Thermohydraulic Analysis Non LOCA (RIA, LOFA) TIGR 3-D neutron kinetics model and subchannel TH model LOCA RELAP5/MOD3.2 Best estimate integral thermohydraulic code RAPTA-5 Fuel rod analysis in accidents Safety Analysis in Accidents Thermomechanical Analysis ANSYS FA stress-strained state analysis. Static and cyclic strength validation
  • 14. OKBM 1414 SAFETY ANALYSIS  Analysis of acceptance criteria sensitivity for main parameters and substantiation of selection of conservative initial state and normal operation system actuation scenario  Safety analysis at PRPS operation  Safety analysis when PRPS fails and DPS operates  The analysis of LOCA was performed in co-operation with UJV Rez
  • 15. OKBM 1515 LIST OF CRITERIA (CONDITION I - IV)  Departure from nuclear boiling ratio  Maximum temperature of fuel rod cladding  Equivalent oxidation level of fuel rod cladding  Oxidized zirconium quantity  Maximum temperature of fuel  Maximum average-radial enthalpy of fuel  Number of leaky fuel rods  Pressure in reactor plant circuits The analysis results confirm that the design criteria are satisfied during operation of TVSA-T fuel loadings in “Temelin” NPP core in Condition I - IV
  • 16. OKBM 1616 IMPROVEMENT OF DNBR VALIDATION PROCEDURE  Validation of CHF and heat exchange coefficients correlation as a part of subchannel code KANAL, used in the design, based on the results of experiments with TVSA-T models  Revising of engineering coefficients for power peaking factors and coolant heating factor  Statistical recording of local parameters deviations (∆q, ∆h, ∆corr) at DNBR calculation based on provision of one-sided confidence probability of 95%  DNBR calculation for Condition II-IV is similar to Condition I with application of hot assembly subchannel model in TIGR-1 code This approach is implemented in TVSA-T design and “Temelin” safety analysis
  • 17. OKBM 1717 TVSA-T DESIGN DEVELOPMENT LINE TVSA-T TVSA-T2 2 SG 6 CSG (SG+MG) 8 SG 3 MG 510х6=3060 SGandCSGpitch 255 Reduction in consumption of materials and fabrication labor input Improved fuel handling conditions (refueling rate, SPR duration) Skeleton bending stiffness enhancement MG optimized design
  • 18. OKBM 18 Twist - type flow By-row cross flow MIXING GRID OPTIMIZATION  Optimization developments and studies were performed to improve MG effectiveness – optimization of dimension, inclination and location of deflectors. MG was optimized with deflector location as per by-row cross flow scheme  Optimized MG is characterized by higher mixing efficiency and CHF increase  Positive experience of twist - type MG of TVSA operated at Kalinin NPP during two fuel load
  • 19. OKBM 19 RESULTS OF CHF INVESTIGATION OF OPTIMIZED MG 0 1 2 3 4 5 6 M a s s f lo w , k g /s e c 8 0 0 1 2 0 0 1 6 0 0 2 0 0 0 2 4 0 0 2 8 0 0Power,kW W it h o u t M G 3 M G 3 o p t im iz e d M G 5 o p t im iz e d M G P=15.7 MPa, Tin=290 °C Critical power of TVSA models increased by 10-20% due to MG
  • 20. OKBM 20  Intercell exchange increase. Decrease of temperature gradient over TVSA cross section and local steam quality by ~3%  Increase of CHF and DNBR by ~15 - 30%  Additional mixing grid effects: - weaker CHF as a function of steam quality increases DNBR in limiting modes of Condition 2 - less influence of axial profile on CHF (form factor effect) increases DNBR in actual axial profile  Possibility to increase core power and power peaking factors, implementation of effective fuel cycles with increased power in fuel rods MAIN RESULTS OF MIXING GRID EFFICIENCY STUDY
  • 21. OKBM 21 TVSA-12 Fuel Assembly 12 SG height is 35mm  SG optimized position  Skeleton bending stiffness enhancement  Operation reliability improvement  Designed to operate in 5х1, 4х1 and 3х1.5 fuel cycles  TVSA advantages application:  reparability  debris filter  thermocontrol tubes  antivibration SG  Fuel rods with increased uranium content (thinned cladding and 7.8/0mm fuel pellet  High thermal performance due to MG optimization
  • 22. OKBM 2222 Thermal power, MW 3120 Inlet core temperature, °С 293.8 Pressure, MPa 15.7 Reactor flow rate, m3 /h 82000 Average linear power, W/cm 162.5 Maximum relative power of fuel rods, F∆h 1.63 Maximum linear power ql, W/сm 448 Minimum DNBR 1.47 Thermohydraulic characteristics of TVSA allow the core uprating to 104% with fuel rod power peaking preservation F∆h=1.63 CORE UPRATING UP TO 3120 MWt
  • 23. OKBM 2323 THERMAL CHARACTERISTICS OF TVSA CORE FOR FUTURE VVER Based on the analysis results TVSA with MG for future VVER (MIR-1200) ensures necessary thermal characteristics at core power 3300 MW with increased allowable fuel rod power of F∆h=1.63 Thermal power, MW 3200 3300 Inlet core temperature, °С 298.2 298.6 Pressure, MPa 16.2 16.2 Reactor flow rate, m3/h 86000 86000 Average linear power, W/cm 168.7 174.0 Maximum relative power of fuel rods, F∆h 1.63 1.63 Maximum relative local power, FQ 2.38 2.31 Maximum linear power ql, W/сm - at height of 0.5 Hcore - at height of 0.8 Hcore 448 370 448 380 Minimum DNBR 1.52 1.43
  • 24. OKBM 2424 CONCLUSION  TVSA-T fuel assembly for “Temelin” NPP was validated. TVSA-T design is based on approved technical decisions and meets the current requirements for lifetime, operational maneuverability and safety  The results of post-irradiation examination of TVSA-T operated at Kalinin NPP unit 1 during 4 years confirm the assembly operability, skeleton stiffness, TVSA-T geometric stability and normal fuel rod cladding condition  Characteristics of TVSA with MG make possible core power increase up to 3300 MW according to future VVER (MIR-1200) design perspectives, providing allowable fuel rod power F∆h =1.63 (to implement effective fuel cycles)

Notes de l'éditeur

  1. Иметь информацию по ходу головки, включая запас на радиационный рост, т.к. у Вестингауза он был практически выбран и витки почти сомкнулись. Привести подробную картинку как снимается головка.
  2. Рассказать про проектные основы.