1. Materials of equipment
for reactor plants
V-320 and V-491
Banyuk G.F., Ryzhov S.B.,
Mokhov V.А., Piminov V.А.
International Topical Meeting
VVER 2010. Experience & Perspectives
01 – 03 November 2010
Prague, Czech Republic

2. Units with VVER-1000
02
Country Number of Units
Russian
Federation
7 (VVER-1000/320) + 3 (VVER-1000/small
series)
Czech
Republic
2 (VVER-1000/320)
Bulgaria 2 (VVER-1000/320)
Ukraine
11 (VVER-1000/320)+ 2 (VVER-1000/small
series)
China 2 (VVER-1000/V-428)

3. Units of AES-2006 design under construction
03
NPP Number of Units
Novovoronezh-2 (V-392М) 2
Leningrad-2 (V-491) 2
Baltic NPP (V-491) (preparation
for construction)
2

4. Main equipment of reactor plant
04
Reactor pressure vessel and top head
Stream generator
Pressurizer
ECCS hydroaccumulator
Pipelines (MCP)

5. Reactor plant
05

6. Reactor pressure vessel
06
Parameter
Value
V-320 V-491
Length, mm 10897 11185
Inner diameter, mm 4150 4250
Wall thickness in the belt
line region, mm
192,5 197,5
Mass, t 320 330

7. Reactor pressure vessel
07
Additional requirements for materials are caused by:
the stronger requirements for equipment and high thermal power as
compared with those for a commercial Unit:
 service life (60 years) and life (fuel cycle 8400 h) are extended;
 primary and secondary coolant (pressure and temperature) parameters
are increased

8. Reactor pressure vessel
08
Implementation of the measures aimed at improvement of brittle
fracture
resistance (BFR) of reactor vessels:
 decrease in radiation embrittlement of RPV materials;
 decrease in loads onto RPV under pressurized thermal shocks;
 improved monitoring of changes in RPV material properties.

9. Reactor pressure vessel
09
Component
Grade of steel
RP V-320 RP V-491
Supporting shell.
Cylindrical upper and lower shells
15Х2НМФА-А 15Х2НМФА class 1
Shells of nozzle area 15Х2НМФА-А
Bottom head, flange 15Х2НМФА

10. Ni influence on radiation embrittlement of reactor
pressure vessel steel
Surveillance testing results and the results of research programs for
VVER-1000 RPV materials have shown, that radiation embrittlement
essentially depends on the nickel and manganese content
010

11. Decrease in radiation embrittlement of RPV
materials
011
Chemical composition of RPV base metal (supporting and core shells)
Grade of steel
(RP type)
Chemical composition, %
C Si Mn Cr Ni Mo
V
Calc.
15Х2НМФА-А
(В-320)
0.13-0.18 0.17-0.37 0.30-0.60 1.8-2.3
1.0 – 1.5
0.5-0.7 0.10-0.12
15Х2НМФА
class 1 (В-491)
1.0 – 1.3
Grade of steel
(RP type)
Chemical composition, %
Cu S P As Co Sb Sn Р + Sb + Sn
No more than
15Х2НМФА-А
(В-320)
0.10
0.006
0.008
0.010 0.03 0.005 0.005
-
15Х2НМФА
class 1 (В-491)
0.06 0.007 0,012

12. Decrease in radiation embrittlement of RPV
materials
012
Chemical composition of RPV welds metal (welds of core range)
Welding wire, flux
(RP type)
Chemical composition, %
C Si Mn Cr Ni Mo Ti
Св-12Х2Н2МАА,
flux ФЦ-16А (В-320)
0.04-0.10 0.15-0.45
0.65-1.10 1.4-2.1 1.2 – 1.9 0.45-0.75
-
0.45-1.10 1.2-2.0 1.0 – 1.3 0.40-0.75 0.01-0.06
Св-09ХГНМТАА-ВИ,
flux НФ-18М (В-491)
Welding wire, flux
(RP type)
Chemical composition, %
Co S P Cu Sb Sn As
No more than
Св-12Х2Н2МАА,
flux ФЦ-16А (В-320)
0.02 0.015 0.012
0.10
0.008 0.001 0.010
Св-09ХГНМТАА-ВИ,
flux НФ-18М (В-491) 0.08
Тко
of core weld metal: В-320 ≤ 0 0
С
В-491 ≤ minus 15 0
С

13. Decrease in radiation embrittlement of RPV
materials
013
Decrease in neutron fluence
Fluence decrease is implemented due to increase in the RPV diameter
and core arrangement (FA placing) with reduced neutron leakage
Maximum values of neutron fluence with an energy above 0.5 MeV for various
points
Location
Design data of neutron fluence (F ∗ 1023
), n/m2
В-320 (40 years) В-491 (60 years)
Core top (supporting shell) 2.44 1.28
Base metal in the place of max.
neutron fluence
5.7 4.22
Weld No. 2 5.7 4.06
Weld No. 3 4.5 3.58

14. Decrease in radiation embrittlement of RPV
materials
014
Tk calculation results
Location
Tk, 0
C
В-320 (40 years) В-491 (60 years)
Core top (supporting shell) 42 29
Base metal in point of max neutron fluence 64 55
Weld No. 2 77 69*
Weld No. 3 71 66*
* - without regard for Тко
≤ minus 15°С

15. Decrease in loads onto RPV under PTS
015
Decrease in loads is achieved due to limitation of the minimum water
temperature in the emergency core cooling system
Decrease in loads on RPV under PTS
Reactor plant type
Temperature of ECCS water, 0
C,
not less than
V-320 10
V-491 20

16. Improved monitoring of changes in RPV material
properties
016
Improvement is achieved due to change in location of surveillance
specimen casks.
In RP V-320 the surveillance specimen casks were located in the
channels of the reactor core baffle.
In RP V-491 the casks are placed directly on the inside wall of the
reactor pressure vessel in the place of maximum fluence

17. Monitoring of RPV metal state during operation
(surveillance program)
Irradiated surveillance sets are located opposite to the core and fixed
directly on the RPV wall.
017

18. Surveillance specimens
Surveillance specimen program for RPV of RP V-491 defines:
1.Irradiated sets (materials, number and date of removal).
2.Temperature sets (материалы, number and date of removal).
3.Test sets.
4.Scheme for cutting of specimens.
5.Number of specimens for each type of tests.
6.Type of specimens.
7.Quality Assurance Program.
018

19. Surveillance specimens
019
Basic requirements for fabrication of surveillance specimens
Surveillance specimens for in-service inspection of change in RPV metal
properties shall be fabricated from:
 base metal;
 weld metal;
 HAZ metal.
Billets of the base metal surveillance specimens shall be cut out of the test
ring of the standard shells after basic heat treatment.
The billets shall be subject to heat treatments under the modes identical to
heat treatment modes of the shell, from which the test ring is cut out, in the
course of the vessel manufacture.

20. Surveillance specimens
020
Basic requirements for fabrication of surveillance specimens
Billets of specimens of weld metal and HAZ metal shall be cut out of the
circular welded sample, made of metal cut from one of the RPV shells.
The sample shall be of the same thickness and the same grooving as
the RPV welds.
The circular welded sample shall be made under the same modes and
using the same welding process and welding materials of the same lots
as the tested RPV welds.
The sample shall be subject to the same complex of heat treatments as
the RPV welds to be tested.

21. The first AES-2006 RPV for Novovoronezh-2 NPP was manufactured at the
Izhora plant in this year
The second AES-2006 RPV for Novovoronezh-2 is planned in the next year
021

22. Main coolant pipeline
022
Tubes for manufacture of MCP
Technical conditions TU 108.1197-83 (the Manufacturer - «EUROTUBE
GmbH»)
Outer diameter,
mm
Inner diameter,
mm
Wall thickness,
mm
Maximum length,
mm
Thickness of
cladding layer,
mm
990 850 70 8400 5
1130 990 70 8400 5

23. Main coolant pipeline
023
Materials
Chemical composition of the base metal of MCP tubes
Grade of
steel
Content of elements, %
C Si Mn Ni Mo V S P Cr Cu
10ГН2МФА
0.08-
0.12
0.17-
0.37
0.70-
0.90
1.70-
2.00
0.40-
0.60
not more than
0.04 0.020 0.020 0.30 0.30

24. Main coolant pipeline
024
Materials
Chemical composition of deposited corrosion-resistant coating 03Х22Н11Г2Б
Content of element, %
C Si S P Cu Co N Mn Cr Ni Nb
not more than
1.00-
2.50
17.50-
20.50
8.50-
11.0
0.70-
1.000.05 1.00 0.02 0.03 0.30 0.02 0.05

25. Regulatory requirements
025
Regulations for design and safe operation of nuclear plant equipment
and pipings (PNAE G -7-008-89).
Regulations for strength calculation of equipment and pipings of nuclear
power plants (PNAE G -7-002-86).
Equipment and pipings of nuclear power plants. Welding and cladding.
General provisions (PNAE G -7-009-89).
Equipment and pipings of nuclear power plants. Welded joints and
claddings. Rules of inspection (PNAE G -7-010-89).

26. Regulatory requirements
026
Guiding technological document. Equipment and pipings of nuclear power plants.
Welding, cladding and heat treatment of welded joints of components of steels of
grades 10ГН2МФА, 10ГН2МФАЛ, 15Х2НМФА, 15Х2НМФА-А, 15Х2НМФА class
1 (RTD 2730.300.02.91).
Standardized control procedures for inspection of base materials (semi-products),
welded joints and claddings of nuclear power plant equipment and pipings:
Ultrasonic test. Inspection of base materials (semi-products) (PNAE G -7-014-89).
Magnetic particle test (PNAE G -7-015-89).
Visual and measurement check (PNAE G -7-016-89).

27. Regulatory requirements
027
Radiographic examination (PNAE G -7-017-89).
Penetrant test (PNAE G -7-018-89).
Check of leak-tightness. Gas and liquid methods (PNAE G -7-019-89).
Ultrasonic test. Part II. Inspection of welded joints and claddings (PNAE G -7-030-
91).
Standardized control procedures for inspection of base materials (semi-products),
welded joints and claddings of nuclear power plant equipment and pipings
Ultrasonic test. Part III. Measurement of thickness of monometals, bimetals and
corrosion-resistant coatings (PNAE G -7-031-91).
Ultrasonic test. Part IV. Inspection of welded joints of austenitic steels (PNAE G
-7-032-91).

28. Welcome to the 7th
International Scientific and Technical Conference
“Safety Assurance of NPP with VVER” which will take place at
OKB “GIDROPRESS”, Podolsk, Russia on 17-20 May, 2011
More details at www.gidropress.podolsk.ru
028

29. THANK YOU FOR YOUR ATTENTION
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