Title: GENERATION III AND III+ NUCLEAR POWER PLANT DESIGNS
1GENERATION 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
2Outline
- VVER Concept
- VVER Development
- VVER-1000
- VVER-1200
- Technical Description
- Conclusion
3Pressurized Water Reactor Type (Water-Water
Energetic Reactor)
4VVER 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)
5VVER 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
-
6VVER 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
7VVER-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
8VVER-1000
1.Horizontal steam generator 2.Reactor coolant
pump 3.Containment building 4. Refueling
crane 5.Control rod assemblies 6.Reactor vessel
9VVER-1000
Parameter V-320 Heat capacity, MW
3000 Pressure, MPa 15.7 Mean fuel
burn-up,(MW days)/kgU gt40.2 Lifetime, years 30
10VVER-1000
11VVER-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.
12ADVANCED 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.
13VVER-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?
14VVER-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
15VVER-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.
16VVER-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
17VVER-1200
frequency of limiting accident release less than
10-7 (1/year).
18VVER-1200
19VVER-1200
20Conclusion
- 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