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GENERATION III AND III+ NUCLEAR POWER PLANT DESIGNS

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GENERATION III AND III+ NUCLEAR POWER PLANT DESIGNS VVER-1200 (Vodo-Vodyanoi Energetichesky Reactor) Dr. ule Erg n Hacettepe University Department of Nuclear ... – PowerPoint PPT presentation

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Title: GENERATION III AND III+ NUCLEAR POWER PLANT DESIGNS


1
GENERATION III AND III NUCLEAR POWER PLANT
DESIGNS
VVER-1200 (Vodo-Vodyanoi Energetichesky Reactor)
Dr. Sule Ergün Hacettepe University Department of
Nuclear Engineering March 2008, Istanbul
2
Outline
  • VVER Concept
  • VVER Development
  • VVER-1000
  • VVER-1200
  • Technical Description
  • Conclusion

3
Pressurized Water Reactor Type (Water-Water
Energetic Reactor)
4
VVER Development
  • VVER-440
  • VVER-440/230
  • VVER-440/213
  • VVER-1000
  • VVER-1000 RP ?-320
  • VVER-1000 RP ?-428 (NPP-91)
  • VVER-1000 RP ?-466 (NPP-91/99)

5
VVER Development
  • Power Unit
  • Electric capacity (gross), MW 417 1000
  • Thermal capacity, MW 1375 3000
  • Efficiency (gross) 29.7 33.0
  • Number of primary coolant loops 6 4
  • Flow rate through reactor, m3/h 42110 88900

6
VVER Development
  • Reactor
  • Average coolant warm-up, C 28.9 29.5
  • Heat transfer surface area, m2 3150 4850
  • Mass of UO2 in the core, t 47.2 70
  • Number of fuel assemblies, pcs. 349 151
  • Reactor pressure vessel height m 11.80 10.88
  • Max. pressure vessel diameter, m 4.27 4.57
  • Core power density, kW/l 84.0 111.1
  • Fuel enrichment, (max.) 3.82 4.4

7
VVER-1000
  • Steel-lined, pre-stressed, large-volume concrete
    containment structure
  • "Evolutionary" design incorporating safety
    improvements over VVER-440 Model V213 plants.
  • Use of four coolant loops and horizontal steam
    generators--both considered improvements by
    Soviet designers.
  • Redesigned fuel assemblies that allow better flow
    of coolant, and improved control rods.
  • Plant worker radiation levels reportedly lower
    than in many Western plants

8
VVER-1000
1.Horizontal steam generator 2.Reactor coolant
pump 3.Containment building 4. Refueling
crane 5.Control rod assemblies 6.Reactor vessel
9
VVER-1000
Parameter V-320 Heat capacity, MW
3000 Pressure, MPa 15.7 Mean fuel
burn-up,(MW days)/kgU gt40.2 Lifetime, years 30
10
VVER-1000
11
VVER-1000
  • Substandard plant instrumentation and controls.
  • Fire-protection systems that do not appear to
    differ substantially from earlier VVER models,
    which do not meet Western standards.
  • Quality-control, design and construction
    significantly deficient by U.S. standards.
  • Higher power densities and smaller volume of
    primary and secondary systems result in a
    somewhat less forgiving and stable reactor.

12
ADVANCED REACTOR VVER-1200
  • NPP-2006 nominal electric powershall be at least
    1200 MW (gross)
  • Design service life of NPP main equipment without
    replacement 60 years
  • Usage factor averaged over the whole NPP service
    life 92
  • Annual load factor averaged over the whole NPP
    service life 90.

13
VVER-1200
  • Gross power unit efficiency increased
  • Improved heat flow diagram of steam turbine
    plant
  • - Steam pressure at steam generator outlet
    increased to 7.0 ?P?

14
VVER-1200
  • Reliability goals
  • frequency of trips - not more than 1 per a year
    of operation
  • average unavailability within the design service
    life of a Unit less than 1,4 (less than 5 days
    per a year)
  • Maximum fuel burnup over FAs 70 MWday/kg
  • Fuel cycle length up to 24 months

15
VVER-1200
  • Reaching the safe shutdown state for any
    anticipated operational occurrences, for design
    basis accidents and beyond design basis accidents
    within 24 hours
  • it is allowed to be increased up to 72 hours for
    design basis accident and beyond design basis
    accident
  • Feedwater inventory at Unit shall be sufficient
    for decay heat removal within 24 hours
  • Total frequency of the core degradation less then
    10-6 per reactor-year.

16
VVER-1200
  • RPV inner diameter extension by 100 mm as
    compared to V-320 RPV
  • Core baffle height increased by 200 mm
  • Extended guiding frame for CPS CRs in the
    protective tube unit

17
VVER-1200
frequency of limiting accident release less than
10-7 (1/year).
18
VVER-1200
19
VVER-1200
20
Conclusion
  • Technical approaches taken in developing design
    NPP-2006 meet the requirements of applicable
    Russian, EUR and IAEA codes and standards.
  • The cost of feasibility study for new solutions
    is decreased and project development /
    implementation period is reduced.
  • Achieving the design economic and safety targets
    is ensured by
  • design solutions being similar to those used in
    existing designs and operating plants
  • Licensability
  • proven construction technology
  • using mostly serial and standard equipment
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