Выпуск №34 (pdf, 3.18 Mb)
132
Transcript of Выпуск №34 (pdf, 3.18 Mb)
-
( )
( )
- . .. ( )
2014
:
-
34
-
:.. , .. ( ); .. , ..., - ( ); .. , ..., . (. ); .. (. ); .. ; .. , ...; .. , ...; .. , ...; .. , ...; .. , ...; .. , ...; .. , ...; .. ; .. ; .. , ...; .. , ...; ..; .. ; .. .
:.. , .. ( ); .. , ..., . (. ); .. (. ); .. .
:... .. , ..., . .. ; .. .
ISSN 2224-0853
- . : ../ [. .. , .. ]. - : , 2014. - 128 . (. : .. (. .) [ .]; . 34. )ISSN 2224-0853
- - - - - , , .
- (www.elibrary.ru).
621.039
AO
2002
621.039
, 2014 , 2014
-
.., .., .., .. -. . ....................................5
.., .., .., .., .., .., .., .., .., .. . .............................................. 11
.., .., .., .. . ...............................................................18
.., .., .., .., .. 68 80 ....................................................................................27
..; .., .., ., .., .., .. -1200. ............................................................................................................33
.., .., ..- - SAF 2507 (X2CrNiMoN 2574). ...........42
.., .., .., .., .., .., .., .., .. ...................... ...53
.., .., .., .., .. .. ........60
.., .., .., .., .., .. .. ........................................................................................................................................................67
.., .., .., .., .., .. () ....................................................................................................................................76
.., .., .., .., .., .., .., .., .. - -.. .................................................84
.., .. Rainbow-TPP 3- 1 .. .............................................................93
.., .., .., .. .. ..............................................................99
.., .. 1- .. .............................................................................................................. 110
.., .., .., .., .., ., .., .. -1200... .................................................................................... 113
3
-
4
CONTENTSMokhov V.A., Zubchenko A.S., Akbashev I.F., Semishkin V.P.WWER-TOI reactor vessel. Design and structural materials.. ..................................................................................5
Dub A.V., Levkov L.Ya., Shurygin D.A., Kriger Yu.N., Markov S.I., Orlov S.V., Dub V.S., Volobuev Yu.S., Kuznetsova K.N., Kisselman M.A.Prospects for production of NPP equipment using electroslag refining .................................................................. 11
Zubchenko A.S., Shary N.V., Davydova N.V., Fedorov A.V.High-alloy heat-treatable chromium steel ................................................................................................................18
Klauch D.N., Ponomarev A.A., Petrov O.M., Kotov I.V., TerekhovV.M.Improvement of manufacturing process and assembly of threaded joints M68 and M80 for high-duty heat exchangers ................................................................................................................................................................27
Karsonov V.I., Lyakishev S.L., Denisov V.V., Chaban V.A., Lyakisheva M.D., Zharov N.V., Ostretsov I.N.Manufacture and tests of multilevel bellows expansion joint for BN-1200 RP steam generator vessel .................33
Zubchenko A.S., Shary N.V., Rabinovich V.P.Sea-water corrosion-resistant austenitic-ferritic steel SAF 2507 (X2CrNiMoN 2574).. .........................................42
Artemieva D.A., Karzov G.P., Kudryavtsev A.S., Markov V.G., Suvorov S.A., Brykov S.I., Denisov V.V., Korolev S.Yu., Metalnikov M.S.Selection of steam generator structural material using criteria of corrosion resistance under different operating conditions of high power sodium reactor.. ...............................................................................................................53
Kozlachkov A.N., Bykov M.A., Siryapin V.N., Shein V.P., Tribelev A.A.Application of statistic analysis methods in reliability study of emergency protection.. ........................................60
Vasilchenko I.N., Kurakin K.Yu., Kushmanov S.A., Makhin V.M., Zakharov A.V., Risovanny V.D.Set of operability criteria of CPS absorber rod for new WWER reactors and capabilities of their lifetime extension.. ................................................................................................................................................................ .67
Bogachev A.V., Berkovich V.Ya., Semishkin V.P., Merkun A.V., Muravin D.B., Nagorny A.O.Implementation of residual life automated control system (SACOR) during lifetime extension of NPP.. ........... ...76
Mokhov V.A., Berkovich V.Ya., Nikitenko M.P., Makhin V.M., Churkin A.N., Lapin A.V., Kirillov P.L., Baranaev Yu.D., Glebov A.P.Conceptual proposals on VVER-SCP reactor prototype.. .......................................................................................84
Kavun O.Yu., Popykin A.I.Rainbow-TPP code verification based on the first three fuel cycles of Rostov NPP Unit 1..... ...............................93
Bezrukov Yu.A., Schekoldin V.I., Zaitsev S.I., Churkin A.N.Analysis of phenomena during reflood of the VVER reactor core... .......................................................................99
Kavun O.Yu., Popykin A.I.Simulation of axial xenon oscillation experiment at Rostov NPP Unit 1...... ......................................................... 110
S.L. Lyakishev, V.V. Denisov, M.D. Lyakisheva, V.A. Chaban, A.A. Khalutin, A.N. Blokhina, N.V. Zharov, V.A. UsachevCalculation justification of BN-1200 RP steam generator... .................................................................................. 113
-
- , -- - . - - - , .
- () -440 (-230 -213) -1000 (-320). , - -, , - . 1000 -440, . 1000 -, . -1000 .
1990- . , - . - - -2006, - [1]. - - -, , - , , - .
- - -1000 -1200. , - -2006 - . - - - .
- -
621.039.53
.., ...([email protected]); .., ... . ([email protected]); .. ([email protected]); .., ... ([email protected])
( )
-.
( 07.08.2014 .)
- -, . . 152, 152- 152 1 0893-013-00212179 152 . 152- . 5.961-11060. 60 .
5
-
. - , 3d- . - . 3d- - . , , , 3d- .
- 1. -2006 . , , ( 2). - - - . C . , 60 , f=1018 /c2. - -, -. -320 - . - - . - , : 152 (Ni=1,01,5 %), 152- (Ni=1,01,5 %), 152 1 ((Ni=1,0 1,3 %) 152- . (Ni = 0,2 0,4 %). - ,
-440 -1000. - 152 -. -440, 152 - -40. - - ( -).
- , -440/213. - -1000, - 152 ( -45) . - -1000 , - 152 . - - ( ) 1 .
- 152,
.1.
6
-
152-, 152 1 152- . - . - -1000 - (Cu, P, As, Sn, Sb), - (Ni, Si, Mn). - 152, 152- 152 1 , . 152 1 ( ): 0,08 %; 0,012 %, 0,010 %, 0,010 %, 0,005 %, 0,005 %. - , 0,015 %. - 152 1 1,01,3 %. , - 152, 152- 152 1 - 0,03 %.
- - , . - - . , 500 , 850, - . - , .
- 152, 152- 152 1 - -1000, , 152 . 152- . -45, -440 152 152- -40. , - 152 . , - , : - 0,10 %; - 0,02 %, - - 0,02 %, -0,04 %. , 152 . 0,015 %. -45 - 0,05 % , , 0,2 0,4 %.
- , ,
.2. - -2006
7
-
. . , , . , - . , . - . - , - , - . . 3. - . , , - , () , ( - , , ).
, - -, .
- - (). ( ). - , , . - - . .
. , - , - . , , . - . , - , .
. - - - . , . , - , - . -
3.
8
-
. -, - , , - - . 4 - , . - - - 152 1 152- , - (P---2008), 5.
- , T - - 60 -. , . 152- . , 152 1
. 152- . 420 5.96711060 - T , -25 -35 ( T= 0). - , - , -. 152 1 T - T=-45. , ( -2006) T -80.
152 , . , -- 5 , 152 1, Af= 17,7C
4. ,
9
-
( 6), - Af=23C. , 152 1 - . - T , , 152 , - .
1. - -1000 -1200. , - -2006 - . - - .
2. - - .
- . . , - - 60 , f=1018/c2. - .
3. 152, 152- 152 1 152 . 152- . -. - 152 1 152 . - 60 . , .
1. .. -. , 4, 2011.
2. .. - . , 1, 2012.
3. .. . , 1, 2012.
5. -
(P---2008)
6. -
5 ( 152 -)
10
-
: , , , , , -, , , , , , .Keywords: reactor vessel, VVER, neutron fluence, welded joints, strength, surveillance specimens, steel, impurities, strength grade, brittle temperature, safe operation, service life.
Design of VVER-TOI reactor provides for reduction in the number of welded joints to reduce essentially con-sumption of metal for billets and manufacturing content. Welded joints are removed from the radiation zone. The following steel grades are chosen for manufacturing of the reactor vessel: 15Kh2NMFA, 15Kh2NMFA-A and 15Kh2NMFA of class 1 as per TU 0893-013-00212179 and 15Kh2MFA mod. and 15Kh2MFA-A mod. as per TU 5.961-11060. Application of low impurity content steel grades ensures the reactor vessel life under irradiation conditions within 60 years.
621.039:669
.., ..., . ([email protected]); .., ... ([email protected]); ..([email protected]); .. ([email protected]); .. ([email protected]);
.. ([email protected]); .., ..., . ([email protected]); .., ... ([email protected]); .. ([email protected])
( )
.., ... ([email protected])( )
( 06.12.2013 .)
(). - (), - 102 . .
- 2030., 1715- 13 2009., , , - , () -
-1000 (1200), - (-2006, - .). - , .. - .
11
-
- - . , , - -1000, -1200. , () - (), (-, , , ) ( ).
() - () . - -1000 1. -. () - 0,36. , - .
- - , - ,
, [1,2]. - 100 300 [3].
- , , , - [4]:
() - - - .
, , , - , .
- . 081810- [5], - [6]. ,
.1. -100012
-
, , , , - [7]. .
- .
- . . , .. - . - -15/30 ( 2) [8], , . -, , .
, , - (20-40 -) , , , , , . - ( 3). - .
- , , - -. .
- , -
, .
- 102- - . 102-, - , , , 2 4, 1 2.
102 - - 0=-20 - 40.
, ( 4). . - ,
.2. -15/30 -
13
-
- ( 1, 2 3).
102-, , , - .
( 1) 60% . 2 90%, - 5 (1-2 50%, 2-532%, 5-10 15%).
( 5) , . . - , 30, 50, 70, 90 120, 130 ( 5 ) 102-, - - 0893-014-00212179-2004. KCV 39 /2 - -10. KCV -20 248 /2.
- 96-98% 10. - 50% 20).
, -, , - .
- -
.3.
.4. 27555,
102-
14
-
, - , , - , , - ( 4).
- - - -1000 ( 5) - .
1
( ) 102- ( 2 4)
,
0,2,
,
5, %
, %
20 459,5 563,5 27,5 80350 432 572,5 25 71,5
, 2 20 580,5 647,5 24 79
350 499 599,5 22 76
, 4 20 570 645 24 78,5350 487,5 598 22,5 74,5
0893-014-00212179-2004
20 345-590 540-700 18 60350 295 490 15 55
2
102- ( 2 4)
, KCV,
/2
-10 181-20 171
, 2-10 193-20 176
, 4-10 188-20 176
0893-014-00212179-2004 -10 39
3
102-
5639-82 7 10 ( 2) 10 11 ( 4) 10 11 0893-014-00212179-2004 4
15
-
.5. ( ) () 102- (90 130) ()
4
- ( )
1
,
1
,
1
,
1
,
/
-150-200-250-300
081810-
385935
19031722
1775515552505250
0,070,070,120,13
0,320,400,350,40
1390422033473528
74312227268
-400
20- 1045 1924 0,24 0,45 879 212
; -500;
20-
081810-
15-
2200
2700
621
3850
1110
895
0,30
0,20
0,45
0,43
0,51
0,66
2600
1590
274
47
16
30
280-930, 40-110
20-15-16- - - 0,3 0,6
1
600 12,9
16
-
- - , :
- (102-);
(081810-);
- (.20-,15-, 16-, 109-);
- (081810-);
(121011-);
(121818-);
(102-);
(06123-);
(102-);
(-82-).
- - - .
:
1. Watkins E.J., Tihansky E.L. Production of a 304 stainless steel nuclear reactor forging from a very large electroslag refined ingot.// Steel Forgings, ASTM STP 903. p.439-449.
2. Kern T.-U., Scarlin B., Donth B.et al. The European COST 536 project for the development of new high temperature rotor materials.// 17th International Forgemasters meetings. 3-8 November 2008, Santander.
3. .., .., .., .., .. . -.//, 2011, 9, .2-8.
4. .., .., .., .., .., .. . - -. .// , 2012. 6, . 2-6.
5. 08.001.05015348-92. - 081810-.
6. . ../ . .., .., ... : . , 1983. 256 .
7. . .., .. , .. . .. , .. / . - . ... : . , 1990. 312 .
8. .., .., .., .., .., .., .., .., .. . - -15/30 -.// II - , . , 2011.
5
() 102-
.
,
. , .
1 696,8 0,33 0,5 60,02 40,0 0,33 0,65 8,03 273,4 0,23 0,6 33,6
4 157,8 0,30 0,6 41,0
5 DN 800, DN 1200 56,6 0,31 0,5 3,5
17
-
Global trends in manufacturing of metal products with high added value for the nuclear and thermal power engineering are associated with widespread use of technology of electroslag refining (ESR). The roadmap for introduction of ESR technology in nuclear power engineering (NPE) was developed by JSC SRPA NIITMASH. Implementation of ESR production technology for hollow billets from steel 10GN2MFA for main coolant pipes (MCP) was the first phase of the roadmap. Research results demonstrate the feasibility of using the ESR hollow billets in cast condition or after optimized forging for NPE products.
: , , , , , , .Keywords: electroslag refining, MCP pipe, roadmap, mock-up facility, quality, properties, cast and low-deformed metal.
669
.., ... . ([email protected]); .. , ... ([email protected]); ..
( )
.. , ...( )
( 27.12.2013 .)
13%- -, , - . .
- - , - , - , . ~12 %. -
. - , -, , - , - . 10-14 % - . , (Pb, Pb-Bi), , - .
18
-
12 % - . , - - .
, - . EN 10088-1:2005 () - [1]. Schaeffler-deLong FM, :
FM=(1,2):(F8), :
F=1,5Si+Cr+Mo+2Ti+0,5Nb (1)
=30+0,5Mn+30N+Ni+0,5Cu+0,5Co
FM - 0,00 - 0,30 Schaeffler-deLong. - - . .
FM 0,30 - 1,0 - - ()- () . - - Schaeffler-deLong. - ( - , EN 10088) - ( 5632).
FM 1,0-4 Schaeffler-deLong. - ()- -.
, - , , - , .
1. 13 %-
1 Fe Cr [2]. - - . ()- - - - . - - Fe-Cr, - +()+. 12-14 % . 13 %- ~0,25 %, 2013 1.4021 (X20Cr13), - ().
, - - ( 2).
1 - EN 10088-1:2005 () FM 13 %- 0813, 1213, 2013 . - 5632. 0813
.1.
19
-
1.4000 (X6Cr13), EN 10088-1 5632 , - - ()-.
- -- 1213, 2013 1.4005 (X12CrS13) 1.4021 (X20Cr13). - 2013 1.4021 (X20Cr13) FM, 1,0. 0,22 %, 5632 EN 10088-1.
13 %- , , -, - 500 . -, - , 2.
13 %- - . 0813 . ~12 % , - ,
, , . , 1.4512 (X2Ti12) - , 10,5-12,5%, 6 0,65%. 1.4512 (X2Ti12) - , - , .
0813, 1213, 2013 - , , - , -. 13%- -
.2. 0813,1213,2013
1
13 %-
,
,
, % FM
C Si Mn S P Cr
0813
1.4000(X6Cr13)
5632EN 10088-1
0,08
0,08
0,80
1,00
0,80
1,00
0,025
0,015
0,030
0,040
12-14
12-14
0,03-0,35
0,03-0,37
1213
1.4005 (X12CrS13
5632EN 10088-1
0,09-0,150,08-0,15
0,80
1,00
0,80
1,50
0,025
0,015
0,030
0,040
12-14
12-14
0,10-0,80
0,20-0,88
2013
1.4021 (X20Cr13)
5632EN 10088-1
0,16-0,250,16-0,25
0,80
1,00
0,80
1,50
0,025
0,015
0,030
0,040
12-14
12-14
0,56-1,46
0,57-1,48
20
-
- -7-008-89 ( 5582-75, 25054).
2.
13 %- - . 600-650 , , , , ( 3).
- , .
-, - - - . (, - ) - , . ,
2
13 %-
, ,
Rpo,2, Rm, 5, % Z, %
KCU(V), /2
0813
9940-81 9941-81 372 22
() 18968-3 410 580 20 60 KCV98 187-217
7350-77 295 420 23
25054-81 392 539 17 50 KCU83 187-229
1.4000 (X6Cr13) EN 10088-3 230 400- 630 20 200
1213
9940-81 9941-81 3922122
() 18968-3 440-610 620 20 60 KCV78 192-229
5582-75 440 21
25054-81 392 539 16 50 KCU74 187-229
1.4005 (X12CrS13) EN 10088-3 450 650- 850 12 220
2013
() 18968-3 490- 655 670 18 50 KCV69 207-241
25054-81 441 647 16 50 KCU64 197-248
1.4021 (X20Cr13) EN 10088-3 600 800- 950 12 KCV20
21
-
. 13 %- - -. 13 %- - - , -, , [3].
- - Pb, Bi 44,5 % Pb 55,5 % Bi - . - - - - . - - .
- - . - - , , . 3 121322 ( 852), 101223 ( 549) 1612 ( 823) , -, 1 % . - , - -, [4].
FM 0,48-0,81. , 1511, 2012 1811, 5632-72 , - - .
, - ~ 0,2 %.
-- - 4.
3. -
- . . , - , (), . - - () . - . - .
5 , , , - , , , - .
1.4027 (20r14) ( 5) - . - .
. - - 0,75-2 %.
22
-
3
,
, %
.
CSi
Mn
SP
Cr
Ni
Mo
WV
Nb
BC
eA
l F
M
15
11
0,
12-0
,19
0,5
0,7
0,0
250
,030
10,0
-11,
5
0,6-
0,8
0,
25-0
,40
0,
48-1
,87
15
12
0,12
-0,18
0,4
0,5-
0,9
0,0
250
,030
11,0
-13,
00,
4-0,
80,
5-0,
70,
7-1,
10,
15-0
,30
0,
48-1
,56
20
12
0,17
-0,2
30
,60,
5-0,
90
,025
0,0
3010
,5-1
2,5
0,5-
0,9
0,5-
0,7
0,7-
1,1
0,15
-0,3
0
0,76
-2,3
5
18
11
0,
15-0
,21
0,6
0,6-
1,0
0,0
250
,030
10,0
-11,
50,
5-1,
00,
8-1,
1
0,20
-0,4
00,
20-0
,45
0,69
-2.3
5
13
11
22
0,
10-0
,160
,6
0,6
0,0
250
,030
10,5
-12,
01,
5-1,
80,
36-0
,50
1,6-
2,0
0,18
-0,3
0
0,61
-2,0
0
10
13
0,
07-0
,12
1,2-
2,0
0,8
0,0
250
,030
12,0
-14,
01,
0-1.
80,
10-0
,48
12
13
22
(
852
)0,
10-0
,15
1,4-
2,1
0,6
0,0
200
,030
12,0
-14,
00
,30
1,2-
2,0
0,16
-0,5
3
10
12
2
3
(
549
)0,
09-0
,12
1,2-
1,8
0,6
0,0
200
,030
11,0
-12,
01,
0-1,
52,
6-3,
30,
2-0,
50
,1
16
12
(
8
23)
0,14
-0,18
1,0-
1,3
0,5-
0,8
0,0
100
,015
10,0
-12,
00,
5-0,
80,
6-,
90,
5-0,
80,
2-0,
40,
2-0,
40
,006
0,1
0.55
-1,0
6
23
-
4
, Rpo,2, Rm, 5, % Z, %KCU(V), /2
1511 18968-73, 5949-72590-755 490
740 690 15 15
50 35
KCV 59 KCU 59
229- 269 229
1512 18968-73, 5949-72590-735 490
740 740 15 15
50 45
KCV 59 KCU 59
229-269 229
2012 18968-73, 5949-72590- 755 450
740 740 15 15
50 50
KCV 59 KCU 59
229-269 229
1811 18968-73, 5949-72590-735 590-735
740 740 15 15
50 50
KCV 59 KCU 59
229-269 255
131122 5949-72 735 930 880 1080 15 13
55 55
KCU 88 KCU 88
269 269
1013 5949-72 345 490 15 60
131322 ( 852) 14-1-1992-76 400 600 15 50
101223 ( 549) 14-3-76-72 520 700 15 50
1612 ( 823) 14-1-1135-74, 8009. 00.044 590 588
780 735
16 12 50
5
-
,
,
, % FM
C Si Mn S P Cr Ni u V
1012 977-88 0,10 0,17-0,400,2- 0,6 0,025 0,025 12-13
1,0-1,5
0,8- 1,1 0,05-0,97
0814 977-88 0,08 0,40 0,5-0,8 0,025 0,02513,0-14,5
1,2-1,6
0,8- 1,2 0,09-0,76
1.4006 (12Cr13) EN 10088-3 0,08-0,15 1,0 1,5 0,030 0,04011,5-13,5 0,75 0,17-1,37
1.4008 (GX7CrNiMo12-1) EN 10283:2010 0,10 1,0 1,0 0,025 0,035
12,0-13,5
0,2-0,5
1,0-2,0 0,00-0,98
1.4027 (20Cr14) EN 10302:2008 0,16-0,23 1,0 1,0 0,035 0,04512,0-14,5 1,0 0,45-1,80
06123 108.1425-86 0,06 0,30 0,60 0,025 0,025 12,0-13,52,80-3,20
0,50-1,10 0,31-1,16
1.6982 (GX3CrNi 13-4) EN 10213:2007 0,05 1,0 1,0 0,015 0,035
12,0-13,5 0,7
3,5- 5,0 0,3 0,08 0,30-1,14
1.4313 (X3CrNiMo 13-4) EN 10088-3 0,05 0,7 1,5 0,015 0,040
12,0-14,0
0,3-0,7
3,5-4,5 0,30-1,18
08154 977-88 0,08 0,40 1,0-1,5 0,025 0,02514,0-16,0
0,30-0,45
3,5-3,9 1,0-1,4 0,08 0,36-1,04
06145 24.11.029-91 0,06 0,40 0,8 0,025 0,025 13,5-14,70,35-0,50
5,0-5,5 0,8-1,3 0,08 0,54-1,22
24
-
, , - . FM , - (~ 0,05 %) 1012, 0814 1.4008 (GXCrNiMo12-1) . 0,16-0,23 % - - - 1.4027 (X20Cr14). 1.4027 (X20Cr14) , - - .
1.4027 (X20Cr14) ( 5) - 0,05-0,08 %. -. - ~3 % . - - - ( 6) - .
4. -
- - .
-
[5]. - 82 - 7 8.
1. -- 13 %- . , , --, 500 . 0813, 1213 2013, , - , . .
2. 13 %- - , (Pb, Bi, Pb + Bi), - .
.
3. -- 3% Ni. - .
4. , , - .
1. BS EN 10088:2005. Stainless steels. Part 1: List of stainless steels. Annex C. Empirical formulae for steel grade classification by microstructure.
2. .. - , - .
7
, , %
FMC Si Mn S P Cr i Ni V
04143114-1-4599-89 0,02-0,06 0,5 0,5 0,020 0,030 13-16 1,3-1,8 2,3-3,5 0,5 0,15-0,30
14-1-5591-2010 0,02-0,06 0,5 0,5 0,015 0,025 13-16 1,3-1,8 2,3-3,5 0,5 0,15-0,30
041452 14-1-5591-2010 0,02-0,05 0,5 0,5 0,015 0,025 13-16 2,0-3,0 3,8-6,6 0,5 0,15-0,35
8
,
,
Rpo,2, Rm, 5, %
041431-041431 041431-041451-
2572,237-0,3
257
14-3-1630-89
14-3-1630-89 441 245 10
26
-
(). .2. . . 1978.
3. .., .. -. - ( .. .. ). . -. 1997.
4. .., .., .. . -
. . . .2. . 1999.
5. - . 11, 2011.
The paper presents overview of a variety of multipurpose 3%-chromium steel grades used in mechanical engineering for components and subassemblies of equipment operating under effects of corrosive and high-tem-perature environment. Analysis of structure of the widely applicable domestic and foreign steel grades is provided depending on their chemical composition.
: , , - , , , .Keywords: chromium steel, martensite, ferritic-martensitic structure, high-temperature strength, cavitation, neu-tron absorption.
621.7
.. , ... ([email protected]); .. ([email protected]); .. ([email protected])
( )
.. ([email protected]); .. , ... ([email protected])( -)
68 80
( 05.12.2013 .)
- , . - ( )
27
-
- -, , , , - .
, - , - -, , .
- - 686 806 .
, - , , -, 400, , :
;
; ; .
- , - , - .
- :
- ,
- - ( , , 100%- - );
( ) ;
- -, , , - Dcp ;
- ;
- - .
686 806 8g/7H, .. 8g, 7. , 0,02 - .
, , . - .
28
-
- min 0,03-0,04 - , - , - ( ), - .
- - - 0,1 - 0,15 .
, 0,1 - 0,15 , , Dcp 0,1 - 0,2 0,475 7 (64,4...64,57 686 74,4...74,57 806) 0,1- 0,2 0,450 - 8g ( 63,57...63,67 686 75,57.. .75,67 806).
-, , Dcp - - , Dcp .
.
- .
- - , ,
- 68 80 ~ 130 .
- - - .
: -, - - .
. 0,1 . , . 163 1-2 . .
3 251.
, - Dcp, , - - . - Ra 0,5 , - Ra 2,5...5 .
, - . - R 10... 15 0,1 - Ra 1...2 . ~0,15...0,2 (2 ) - Ra 0,5... 1 .
Dcp 0,1...0,15 - 7 (64,4- 64,45 686 74,4 - 74,45 806).
29
-
Dcp 64,2...64,3 686 76,2.. .76,3 806.
(0,15 ) (>95 686 806), - , Dcp 686 64,4...64,57 , 806 Dcp 76,4...76,57 , 686 dcp 63,57...63,67 , 806 dcp - 75,57...75,67 .
0,03 0,15...0,17 . - 8g/7H (0,2-0,25 ) 686 0,03 0,05...0,1 . 0,03 . .
0,04...0,05 .
.
- - - () -, . - . , - .
- . ,
0,04 0,15 .
- , , .. - .
- -100. (0,4 ) - .
- :
4 8295-73 - 40% ;
6259-75 - 60% .
() . 48 430500.
100. - - .
- > 0,4 , .
:
S=0.2887(D..-d.. )-S1-S2,
:S - ;D - ;d - ;S1 - - ;S2 - - - (30).
30
-
- 0,03 .
- , 020' - 030', - , , 0,02 - 0,03 . S1 S2 0,06 .
-, - ().
0,06 - 68 (100%) . 0,06-0,11 - 30-50 %. 0,11 (0 %). - 80 () 0,06 .
-, >0,1 , .
96 , - - - - ( - , 200 , ).
, - 686 806 - 7 7G.
- - - 20.
: (-), ( ), , - .
, - - 600.
- .
- (, ..). (t=400, 1 ).
, , , .
- - 540 - 580 1-3 .
( ) , - , .
20 , , - , .
300400 - -, 500600 - .
-, .
- , 10001100.
, - , - .
31
-
-- 686 806 - - - ( , ..) ~0,10,15 .
, - 0,03 . 8g/7H ( 686-Dcp=64,4-64,57 , 806 -Dcp=76,4-76,57 ; 686 - dcp= 63,57-63,67 , 806-dcp=75,57-75,67 ), - .
~0,10,2 Dcp (~0,1 ). .
- - (, - 100).
, -, , - . 30-40 (5-7 ) 70-80 (11-13 ).
- , (, -), .
The paper deals with the issue on enhancement of quality and accuracy of manufacturing of high-loaded threaded joints, provision for their assembly in accordance with the required conditions and defect-free disas-sembly. To perform the specified tasks a number of studies were performed to investigate the effect of geometric parameter errors in threads (by correction of average size tolerances) on threaded joint reliability, manufactu- ring processes and tools providing the required manufacturing accuracy, roughness and mechanical properties of thread surface, were developed. Tests were performed and a number of antifriction coatings and lubricants were chosen to reduce a possibility of adhesion of threaded surfaces at high operating temperatures.
: , , , .Keywords: process, high-loaded threaded joints, accuracy of manufacturing, reliability.
32
-
- , - .
-1200 , , .
- -, - . , - .
, -600 -800, -. -, , - .
- -. , ,
. , , .
- - .
1 - -1200 , -, . () -1200 - .
- , , . () . (-) - .
621.18
.. ; .. , ... ([email protected]); .. ; .. ; .. ; .. ; .. , ..., .
( )
-1200( 15.12.2013 .)
- () -1200. , . - -1200.
33
-
- :
, ;
- ;
, - ;
1303 - 162 ;
;
, - - - .
- 09189 ( )
( 2 - 5). .
=400 =0,6 30 30 - N=150 2,4105 1,96 .
- - 30 , 1,0 . - 3000. () t=20.
.1. -1200
.2.
.3.
34
-
, , .
, - - , 7 0,1
10 450. -, , . -. .
.4.
.5.
35
-
- . .
6 -, 7 - .
8 09189 - , .
- - ( 9).
- - - .
, 10. .
-. 5 8. - 6 4. - 4 3, 8 7.
.6.
.7.
.8. ,
.9.
36
-
6 9 - 2, - - 1. - 6 5 4. 6 - 4 5.
- . .
- -- .
, - 11. 12 - .
-, :
- ;
= 4,0 - , , ;
3000 ;
- 5640 , .
.=1,0 , - 85 ( .=1,0 , 30 ) -. 3482 , . , - , .
- -
.10.
.11.
37
-
. - [1] - , -1200. -: 350 ; 20 .
- ANSYS [2]. - - 13. 30 . - Y.
-. 0,13. - - 14 15.
16 -. 30 .
- - ( A, B, D 17) , ( D-2 17).
.12.
.13.
38
-
85 1 , , - .
09189 - , - -7-002-86 [1]. , - .
09189 - -7-002-86 : - =20, n=2; nN=10; - =20, n=1; nN=1; - =400, n=2; nN=10; - =400, n=1; nN=1; - =20, ; - n=1; nN=1,
n- -, nN .
- [3]. - .
. 14. - .
.15. - .
.16. , 39
-
.
, :
09189 , -7-002-86, - 85 =5,1310-1. [N]=290, 3482 ;
09189 85
=1,2310-1. - ( ) [N]=1200, 3482 ;
-7-002-86 [1] . , 85 (=1) - ;
=20 30 5640 - 85 3482 - -1200 =400.
1. - - -1200 - 09189.
2. , -1200, , . - -7-002-86
(N)
30 (N=150) 85 (N=150) 30 (N=5600) 85 (N=3200)
()
1 3,8110-2 5,13
2 3,2310-3 5,1310-1 11,4
3 2,1910-1 16,8
4 2,1910-2 1,68 38,1
5 2,1610-4 1,2310-1 2,66
.17.
40
-
, 2,4105 .
1. - - . -7-002-86, , , 1989.
2. . - -. ANSYS Mechanical, v.7.1, CAD-FEM, Gmbh, 2003.
3. . - . 86-2002, 08624607.00418, , 2002.
The paper deals with the design features and manufacture of a multilevel bellows expansion joint for steam generator (SG) vessel of sodium-cooled fast reactor plant BN-1200. The steam generator manufacturing process, strength tests and their results are shown. In the paper issues are considered regarding calculation-based strength analysis of the bellows and verification of their operability under operating conditions as a part of BN-1200 SG vessel.
: , , -1200, , , , .Key words: multilevel bellows, steam generator, BN-1200, tests, manufacture, analysis, cyclic strength.
-- .
, - : , , , .
.
, , , , .
-
www.gidropress.podolsk.ru.
41
-
- () , 0,03% , 25% , 3% , ~7% - (~0,3%), - - , [1, 2]. X2CrNiMoN 2574, - , [3].
- -, , , - X2CrNiMoN 2574 2000 - , - 1 2 . SANDVIK () , , SAF 2507, 25.10.4.LR 25.10.4.L. 10 - .
- -350 . () 032463 (-130),
X2CrNiMoN 2574. - - - .
SAF 2507 :
; ; ,
/; , ; ,
; -
. SAF 2507
-- (ASME) - ASME -, VIII, 1, 2047, ASME 31.3 -, Vd TUV - Werkstoffblatt 508, NACE MR 01-75 , , - .
: X2CrNiMoN 2574, S 32750, SS 2238, SAF 2507.
SAF 2507 : .
669
.. , ..., .([email protected]); .. , ...; .. , ...( )
- -
SAF 2507 (X2CrNiMoN 2574)( 30.12.2013)
SAF 2507 (X2CrNiMoN 2574), .
42
-
. - , - . , - . 30- - , -, , 40% 60% .
SAF 2507 - , . , - , - . 1 - ( - , - ).
SAF 2507 - , . 1.
1050...1125 , ( 2). , - - .
- -7-008-89 20 Tmax 50, Tmax+25 Tmax+50.
SAF 2507, - - Rm, Rp0,2, A Z.
3 - SAF 2507 - 20 . 4 - Rm Rp0,2 20, .
SAF 2507 , , 4.
( 600).1.
SAF 2507
1 SAF 2507, . %
C Si Mn S P Cr Ni Mo N , % ()
2198 0,021 0,64 0,89 0,012 0,024 25,0 7,3 3,8 0,29 48
= 20 0,028 0,58 0,94 0,015 0,030 24,8 6,9 4,3 0,30 50SAF 2507,
max 0,03 max 0,8 max 1,2 max 0,015max 0,030
24,026,0
6,06,8
3,05,0
0,240,32
3555
43
-
2
SAF 2507
., Rm, Rp0.2, ,% Z,% Hv
( )
20855860863
563570570
424039
424448
290292298
50850858864
549560571
454042
464450
100852860870
554560572
434045
525250
300690703712
470482490
404449
505049
325704712720
480491499
424140
394950
350683699699
466471483
474648
505051
400680688693
454463460
464840
384553
( )
20890890890
593584590
464339
485050
50873881890
563560569
394140
474859
100850870870
568572570
424446
555250
300720730738
505512518
475049
505152
325709712722
498490493
504241
474746
350671683699
503490496
425153
396151
400682694701
483480494
313943
396151
( )
20893902902
604602599
434547
393835
50868890892
590592588
474942
454750
100855870870
577602599
434239
525264
300746750751
512517504
463940
504141
325722730736
503499507
393735
394253
350699702710
485503500
444840
354049
400673682688
479482490
384240
324550
44
-
~200 . , . SAF 2507 - . . 4 - , - SAF 2507 , , -50,
-, .
SAF 2507
- 300 SAF 2507 , - . - ,
2
., Rm, Rp0.2, ,% Z,% Hv
( )
20893902902
604602599
434547
393835
50868890892
590592588
474942
454750
100855870870
577602599
434239
525264
300746750751
512517504
463940
504141
325722730736
503499507
393735
394253
350699702710
485503500
444840
354049
400673682688
479482490
384240
324550
3 SAF 2507
, Rm, MPa Rp0,2, MPa A, % Z, %
20 800-1000 550 25 40
100 710 480 25 40200 665 420 25 40250 650 405 25 40300 645 395 25 40350 645 395 25 40400 645 395 25 40
45
-
, SAF 2507. , -, 250.
SAF 2507 30. 5
100 200 - .
SAF 2507
20 - 7,85 /3. (W/) -
(/)
4 SAF 2507, (V-)
,
,
-100253248
303539
194243
-75505869
424463
505055
-505998190
8288120
737979
-25156173210
135135148
139142144
0220229260
189240253
150183198
20225260270
202270271
222229231
50235269301
195264271
189213250
5
SAF 2507 ,
100 200
500 3000 500 3000
20 -50 20 -50 20 -50 20 -50
,
220228240
100112123
218240255
94120122
231249250
889494
227252273
79120133
,
232239239
101125142
209220224
112118130
217229241
101120121
220244259
9191
120
46
-
20...400C 6 7. 6 AISI 316L.
SAF 2507 - ( 8). - SAF 2507 - . SAF 2507 - .
SAF 2507, , - .
SAF 2507
SAF 2507 - (-, )
(), , , - . SAF 2507 - , .
, - 304L, 081810 . , . AISI 316L, 904L, 0317143 - .
, , . - - , , -, , - .
6
(W/) SAF 2507 AISI 316L
, 20 100 200 300 400
SAF 2507 14 15 16 18 20
AISI 316L 14 15 17 18 20
7
(/) SAF 2507
, 20 100 200 300 400
480 500 530 550 580
8
(10-6)1/
, 30...100 30...200 30...300 30...400
SAF 2507 13,5 14,0 14,0 14,5
12,5 13,0 13,5 14,0
AISI 316L 16,5 17,0 17,5 18,0
47
-
, PRE (Pitting Resistance Equivalent) :
PRE = % Cr + 3,3% Mo + 16% N
10 - PRE.
PRE , . SAF 2507 - , PRE 41. 10 PRE SAF 2507.
6 %- FeCl3, ASTM G48
, - SAF 2507 , . - SAF 2507 90 64. SAF 2507 -. U- 1000 . 100 25%- NaCl . , 40%- CaCl2 100 =6,5 , - SAF 2507, 90% . 42%- MgCl2 155 SAF 2507
9
()
, 20 100 200 300
SAF 2507 200 194 186 180
AISI 316L 198 193 189 185
10
, %
(-, -)
PRECr Ni Mo N
304L 18,5 10 - - A 18
08X18H10T 18 10 - - A 18
316L 17,5 13 2,6 - A 26
08X17H15M3T 17 13 3 - A 27
03216 21 6 - - 50%+50% 21
SAF 2304 23 4,5 - 0,1 50%+50% 24
08X21H6M2T 21 6 2 - 50%+50% 27
SAF 2205 22 5,5 3,2 0,18 50%+50% 35
03X25H6AM ( 130) 25 6 3 0,2 50%+50% 38
SAF 2507 25 7 4 0,3 50%+50% 41
48
-
-, 50% Rm. 1,5 - - SAF 2507. SAF 2507 . - 11.
SAF 2507
SAF 2507 - -, . -
. - SAF 2507 :
TIG - ;
MIG - ;
- - ;
SAW - . : TIG MIG -
Sandvik 25.10.4.L; - -
Sandvik 25.10.4.L.R; SAW - Sandvik
25.10.4.L Sandvik 15W.
25.10.4.L - TIG, MIG, MMA SAW 12.
11
SAF 2507
C PRE
, , SCC
6% FeCl3 (ASTM G48)25% NaCl, 108, 1000 ,
U-40% aCl2,
100C, pH=6,5, 0,9 Rp
41 >90 >64
- ; - ;SCC - -.
12
, %
C Si Mn P S Cr Ni Mo N
TIG. 25.10.4.L
0,020 0,2-0,4 0,3...0,5 0,020 0,015 24...26 9,0...10,5 3,8...4,2 0,20
0,020 0,2...0,4 0,3...0,5
-
- 2198 20 , 1. - TIG , - TIG, MMA SAW.
: - V-
70; - -
70 TIG , 90 - SAW.
, 6 , 5 . . , - q=0,2..1,5 / - 150. , :
(U- , ; J - , ; V- , /) q=1,1 /, U=11 J=100 , 60 /. :
TIG: 25.10.4.L, , J=100 , U=11 ;
MMA: 25.10.4.LR, 3,2 , J=80 , U=22 ;
SAW: 25.10.4.L, 3,2 , J=300 , U=30 .
- 13.
- 6 , 816150 81065 . - - 10 , 2040200 101065 , - 6 . 14 15.
- - . 16. - .
, - TIG, MMA SAW, .
- - SAF 2507 - , ,
13
C Si Mn P S Cr Ni Mo N
25.10.4.L TIG 0,015 0,30 0,42 0,015 0,012 25,0 9,6 4,2 0,25
25.10.4.LR 0,025 0,5 0,7 0,015 0,010 25,0 9,6 4,1 0,26
25.10.4.L 15W 0,012 0,56 0,31 0,016 0,011 24,5 9,5 4,2 0,21
50
-
, - - .
SAF 2507 - .
14
, Rm,
,
.
219,08
TIG 20845850861
120120120
20840845852
120120120
= 20
TIG 20851862862
120120120
20839848852
120120120
SAW 20849862874
120120120
15
, Rm, Rp0,2, 5, % Z, %
TIG
20849852858
638640640
282726
464849
100854855862
629639639
313227
474953
200848850855
635639641
353432
454349
MMA
20850852858
642650650
303035
454650
100854855861
638645651
293133
495153
200839845854
630633645
323838
535553
SAW
20875880880
675680685
282729
434647
100875879879
680681699
303029
444849
200859863870
650653660
374040
505352
51
-
, , - , , , TIG, MMA SAW - - , .
1. Bertil Walden and J. Michael Nicolls Applications of duplex stainless steels in the
Chemical and Petrochemical Industry//R&D Centre, AB Sandvik Steel. S-51-55-ENG, April 1994.
2. Per A. Olsson and Mark B. Newman SAF 2507 for sea water cooled heat exchangers // R&D Centre, AB Sandvik Steel. S-51-57-ENG,Feb. 1998.
3. .., .. - - // . : . 25. . 2009 . . 106-112.
Results of testing the mechanical properties and corrosion resistance of steel SAF 2507 (X2CrNiMoN 2574) approved by Gosatomnadzor of Russia for manufacturing of sea water pipelines at nuclear power plants are presented.
: - , , . , , , , .Key words: austenitic-ferritic steel, duplex steel, pitting corrosion, sea water, chemical composition, mechanical properties, fracture energy, welding process.
16
SAF 2507,
,
-40 -30 -20 -10 0 20
TIG
106109115
107108119
108112122
115122130
120130133
130140145
828493
112114118
125150150
153155157
164168168
180189195
MMA
323744
454545
505253
555860
636464
656872
828889
110116117
120129142
155163163
155163163
190196196
SAW
576069
606468
707073
757883
757883
110112118
798399
110120121
106132136
138145171
180183200
173199201
52
-
620.193:621.18
.. ; .. , ... ([email protected]); .. ; . , ...; ..( )
.. ; .. ; .. ([email protected]); .. ( )
( 21.04.2014 .)
- . , - 0712 - .
, - () , , - .
- - , , , - -- .
, , , - .
-600 3 ()
102. 125 . 102 - 500 -600. , , 102 . ( ) . - , , . , 505 - 510, - - , 102 .
- -600, 09189 (10189), , - 515 . - ,
53
-
, - -. - , , , - 09189 .
- 0321323 (-33). - - .
- - - , - , , . - - 9 12 %.
.
- , - .
, - , ,
- .
-600, - 100 , .
. , -, - /1, 2/.
- ( 1).
-
.1. -
54
-
- [3]. - (), ( 2).
- - ( ) , - . - , [1]. , (Na+, Cl-, SO42- Ca2+ ).
- , .
, , - , , . , .
- kp,
is ciw [4].
kp - 3.
- . - .
- -, - ,
.2.
. 3. kp
55
-
- , . .
, - ( 4).
- . . (CuO, Cu2O, CuFeO), . Cu2+, Cu+ . Fe3+ - .
[5]:
/ :2Cu + H2O Cu2O + 2H
+ + 2e-2Cu + OH- Cu2O + H
+ + 2e- :2Cu+ + 2e- 2CuFe + 2H2O Fe(OH)2 + 2H
+ + 2e-Fe + 2Cu+ + 2H2O Fe(OH)2 + 2H
+ + 2Cu3Cu2+ + 2Fe 3Cu + 2Fe2+ (/
):2Cu+ Cu2+ + Cu
.
- .
- .
, - - ( , , ) .
- , - -, 9 12 % - .
, - - .
- , - 3355 3000 9 % - 0,006 /, 12 % 0,004 /. (- 53010) - 9 % 0,06 /, 12 % 0,031 / , 2 .
( 240 000 ) - , () [6]. 5 - - 560 600.
6 - 9 12 % - 560 1,6 , 600 1,8 .
, 9 % 12 % -
. 4.
56
-
.
(- ) - - .
/7-12/ - 0,1 0,3 % [Cl-] 20 80C - 9 % 200- 400 mV , 12 % .
, 09189 200-300 mV - 10-20 . . - 9 % , 12 % . ( -) .
1500 9 % - 0,3 /, 12 % - - 0,01 /1000 ( 0,1 /).
- .
, - - . , - . , - , , -, . -600, 20600 , - . , , - .
- - , . 6 , - .
6, i I - i
I
. 5.
(1-2 %) (9-12 %)
. 6. ,
i (I) (II)
i57
-
I
- ia
I. II - II i
II-
- ia
II.
- ( 7).
8, - 10 12 % ( 0,5 ) .
() - [10]:
PRE = % Cr + 3,3 % + 16 % N. 109 PRE12, - 0712 PRE15. PRE 3 - () 5-7, () - .
12% ( 0712) 3% - NaCl 20 , 10000 .
- , - - - 9 12 % .
- () , - - 12 % .
, - - 0712.
1. .., .., .., .., .. - - . Proceeding of the Ninth International Conference on Material ISSUES in Design, Manufacturing and Operation of Nuclear Power Plants Equipment 6-8 June 2006, Pushkin-St-Petersburg, Russia.
2. .., .., .., .. ( , .-), .., .., .. ( , .). -
. 7.
4 % NaCl
[12]58
-
-1000. 7- , , , 3-5 , 2006.
3. .., .., .. ( ). - -1000. 11, 2001.
4. .., . .: , 1987, 384.
5. Interdependance of On-Load Corrosion, Creep-Rupture, and Copper Deposit in Augmenting Failure Processes of Boiler Tubes, S.C. Bose, S.V. Reddy, and K. Singh (Metallurgy Department, Corporate Research and Development, BHEL, Hyderabad-500093, India), Corrosion-Vol.56, No. 11, November 2000.
6. Sumitomo Metal Indusrees Ltd. Steam oxidation on Cr-Mo Steel Tubes. Paper No.805, 1443A, 1989.
7. .., , ., , 1969, 750 .
8. . - - -, - .: , 1988. 222 .
9. .., ... , .: , 1994.
10. -/ . ...: , 1989. 400 .
11. A.J. Bard, R. Parsons, J. Jordan, Standard Potentials in Aqueous Solution, Marcel Dekker, New York (1985) p.1833.
12. H.H. Uhlig, R.W. Revie, Corrosion and Corrosion Control, third edition, John Wiley, New York, (1985) p. 78-79.
The present paper deals with the issues on corrosion damage resistance of tubing systems of once-through steam generators. Approaches are offered for selection of structural materials of high-power sodium reactor steam generators by the criteria of corrosion stability. It is shown that complex alloy chromium steel of martensitic-ferritic grade 07Cr12NiMoVNb fully meets the requirements for operation of steam generator heat exchange tubing systems of the high-power sodium reactor.
: , - , , Keywords: high-power sodium reactor steam generators, corrosion-resistant steel, deposits, corrosion
2006 , - ().
- , - .
:
, , ;
, , -.
- 10 .
www.gidropress.podolsk.ru
59
-
- , - . [1] . - ( 2). - , - . ( 3). , , . . , - - . - [2].
- , 3]. ,
. - - - - , .
- . . .
[4] - - . - - .
- , , -, - . - 1 -
621.039.58
.. ([email protected]); .. , ...; .. , ...; .. ; ..
( )
( 04.08.2014 .)
- . . - . , . ( , , ) . - .
60
-
( 20 ). - . , , . .
-, - . - . ~50 . . - 2, 9 . - , . , - , - - (. . ).
[4] - , -. - . - 9
-1000 61 .
- [4]. . , . 2 100 30 , 1 100 - 20 1 100 40 . - , [4] (300 - 9 ). , , 700 .
- . , - .
3 : 20 , 30 40 . - . (20 ) 92 - . (30 ) 95 17 . - (40 ) 97 68.
, , . , ,
. 1.
.2.
61
-
, , -, - ( , ). - , - . 4 50 . (- 2).
5 - (
, ). 30 - - 1,589. 20 - 1,177. , , , - , , .
-
. 4. 50
.5. 30 20
30 ; 20
.3.
( 20, 30 40 )
62
-
- . , - , . - - [5] - -. 100 - 0,03 ( 0,95). , , .
, - [6]. - . - :
K(x1, x2x61)=a0+a1x1+a2x2+a3x3++ a61x61 (1)
- - - .
- , . , - . : . , :
(x1, x2x61)=b0+b1x1+b2x2+b3x3++b61x61 (2)
(x1, x2x61)=c0+c1x1+c2x2+c33x3++c61x61 (3)
, - (x1,x2x61)>(x1,x2x61), - ,
(x1, x2x61)
-
. - - :
QRPS = qTqc (4)
qT - 0, 1, 261 ;qc 0, 1, 261 .
- , - .
, qc . - , - . , 7, - -. , , - 7 ( ) 0. 9 100 - . - . -, - , 0,03.
, 8. 10 , . 2 - qc.
, 7 - , QRPS - (4) . .. .
- , , , , 300, -, 0,01.
- - . 6 - - . - (700 ).
(30 40) - . 6 - .
1
IN OUT
1 2 3 4 5 6 7 61 ( )
1 0 0 1 0 1 1 0 1 1.564 N2 0 1 1 0 1 0 0 0 0.895 CR3 1 0 0 0 1 1 0 0 2.378 N
4 1 0 0 1 0 1 0 1 1.189 N
5 0 1 0 0 1 0 1 0 0.987 CR
n 1 1 0 0 0 0 1 0 2.193 N
64
-
.
, - 7 . - - 7 , 6.
, - , (- ), . - - (700 ).
. . , , - , .
3 :1 -
100
9 ( 100 , );
2 100 , 9 20 ( 200 , );
3 100 , 9, 20 30 ( 300 , 17 , ).
, - . - . - , - . , - (9, 20 30).
7 - . , 9 - -. .
, 9, 20 30 ( 300 -) , 700 ( 6). ,
2
i qci0 0,0 7 0,08 0,039 0,0310 1,011 1,0 61 1,0
.6.
65
-
- 300 .
, , (30 40), - 7-20 . , , 9 - , . , - , - , .
1. - . - . . - , - .
2.
, . , - .
3. - , - - . - , - - , .
1. Deterministic Safety Analysis for Nuclear Power Plants, International Atomic Energy Agency, SSG-2, Vienna, 2009.
2. SUSA, Version 3.3, User's Guide and Tutorial, Gesellschaft fur Anlagen-und Reaktorsicherheit (GRS) mbH, 2001.
3. Boyack, B. et al., Quantifying Reactor Safety Margins, Application of Code Scaling, Applicability, and Uncertainty Evaluation Methodology to a Large-Break, Loss-of-Coolant Accident, NUREG/CR-5249, US Nuclear Regulatory Commission (1989).
4. .., .., .. - - , 8 - , , , . 2013.
5. .., .., .., -, , ., 1965.
6. .., , , 2008.
The problem of multiple control rod failures at reactor scram during the initiating event of main steam line break was considered. Probability of scram function failure was assessed in the view of safety criteria. Cases with a different number of control rods failed were studied. The input data were generated for multivariant calculations.
.7.
66
-
-1000 104% N , , , 18- , -2 - ( ) [1].
- -1000 -1200 - 10 , 3 7 - . - -
15 , - .
-1000 . . -, . - , , -
: , , , , , , , , .Keywords: reactor, VVER, calculation, scram, reliability analysis, main steam line break, probability, response surface, safety.
621.039.56
.. , ...; .. ; .. ([email protected]); .. , ... ([email protected])
( )
.. , ...; .. , ...( )
( 12.08.2014 .)
, - .
Control rods failures were chosen in a random way. Different statistical methods for post-processing were tested (by frequency of events, multiple linear regression, discriminant functional analysis) which enabled to find out some laws.
67
-
.
- - , .
-1000, -1200 - ( 1) - - , [1]:
;
- - .
18 (), - . 2000 , -1000 , - - n, - (- 2). - :
- -;
- 10 (75 600 . ), 3 (25 500 . ) ;
- 4 .;
.
- -1000 -1200 -. - 15 , - - .
-
.1.
68
-
- -1000, . 5 [2,3]:
:
- ;
( , );
- .
- :
, ( );
:
() - ;
;
n,-;
- :
- ( , , );
- (, , -);
( -);
( , -, ) - ( ).
:
- ( );
( );
- () - ( ).
- - , - - . - .
-
.2.
69
-
, - . - - .
.
- , . 49 121. 3 - -320 (61 ).
- - . - .
- . , , -320 5%.
-320 6- , - . - - - ( ) . - ( - ) . - -320 18- - 104% N 4. , -1000, -2006 -, , - - .
.3. -1000
.4.
70
-
- , , - . - . -1000 5. - - , - . -1000 0,5%.
- , , , - . , . 6 - . - , - -. -1000, -2006 - , , 4 , ( - ) 1,2 .
, -1000 , , , ( 2). , -, ,
, - . -1000 - 42. . - . - -1000 18- - 104% N 7. -
.5. -1000
.6.
71
-
(3,41022 -2 >0,1 ) - , 42 . - , .
. . - - (45%) 10. - -1000 104%N 18- 8.
- , , - (n,)- - . - - 4,01022 -2 >0,1 7,01022 -2.
-1000 - . - .
- , - . :
(-) ;
(, , ) (, , );
- (, , - ).
, , - .
.7. -
1000 18- 104% N
.8. 10 -1000 18-
104%N
72
-
. - - - . , - .
, - - . - , . , - . .
- :
-;
, ;
- - - .
- , - . , -
- .
- - . - .
- .
- - . -- , , - . - . .
- . - , , - . -
73
-
, .
- , - :
- -95&RC;
- , -;
- MARC ( ).
- , - .
- - - . - - .
- - - , , , .
- 2010 . -
- . , , , - .
(n,) - - , , - [4].
- (n,) 300 700-900 ( - ). - - , , 10B.
, - , -1000.
(70 % ) 10B. .
- - . - -. . - 42 - - 51022 -2 (>0,1 ).
74
-
, , - . 700 42. - 42, 550 [5].
- >0,1 ~ 51022 -2.
- , - -1200 -.
1. - , - , - .
2. - - , -- -, .
3. (
) . - - - .
4. - - , - - 15 .
1. .., .., .. -1200. , - , 25, - , 2009, . 44-49.
2. .. . - , -, .4, , 1996, .37-52.
3. .., .. . - , -, ( CD-), , 2013.
4. Zakharov A.V., Risovany V.D., Muraleva Y.E., Sokolov V.F. Development and mastering of production of dysprosium hafnate as absorbing material for control rods of promising thermal neutron reactors Fontevraud-7. Contribution of Materials Investigations to Improve the Safety and Performance of LWRs, 26-30 September 2010.
Acceptance criteria of control and protection system absorber rods (CPS AR) are proposed to be introduced into the practice of designing for substantiation of CPS AR functioning within the specified service life.
: , , , , , , , .Keywords: acceptance criteria, reactor plant, VVER, physical efficiency, dynamic parameters, radiation resis-tance, core, absorber.
75
-
- .
, , - [1,2]. - , - [3].
:
1) 3- - , - / .
2) - , - .
3) , , - / - , ( ).
4) ,
- .
5) - , ( , //- ).
6) , :
- ();
- - ;
;
. ,
() -, . - - . ,
621.039.56
.., .. ([email protected]); ..; .., ..; ..; ..; ..
( )
()
( 30.10.2014 .)
. , , -. . , , - .
76
-
- . , , , .. .
, , /-/ , , -, - .
- ().
, , - :
- ;
(, , - . .);
;
- (- 111 ).
- . -, , , - , . -
, - . , . , - . - , [4].
, - - .
- [5]. - . - , - , - - . - - ( - ) .
- .
,
- - - . ,
77
-
. - - .
, - - . , . , , - .
- - - . [6].
- - , - , , . - [7].
- ( ) - - (FAMOS, , , ). , - .
- - , .
-338 -338 , . - -338 1. - .
- -, . , - , , - , . - - . . 2 - . - , , .
- , - , .
, , - , - .
1 - - , - FAMOS.
78
-
.2. -338
.1. -338
79
-
FAMOS -338. 3 - FAMOS.
-338 FAMOS - , - .
, 200 1-4 , - - .
, - 200 , - .
(- ) -
.
- -1 ~ 200 1-4 , , - - .
- , ~ 200 1-4 , - - .
.
.3. FAMOS80
-
-, 2- , , - , - .
- . , , - .
- - . . , . , ( - ), - .
- , , , - - 400 . , - .
- , - ,
-. - . , , , . - , -, -.
- - 2 , 2004 [8]. 4 - 2004 .
, - - . , . . - .
- - ,
.4. 2004
81
-
, .
-, - 1 2001 , - ( ) -. , 161. - 10.11.2001 . . , , , -, .
- 2003 1 - . . - 1 . - . , , - - .
() , :
1. - -, .
2. - - .
3. - , , .
4. ( ) verlife - - .
, , - .
1. -017-2000 -
1 01.01 2004 .
1.01.04
1.01.04
Y00 1 850 1 0,000479 0,000927 0,185
YA11 1 . : . 850 1 0.006853 0,009805 0,957
YA41 13 . . . 4 0.005440 0,01104 0,51
YB10 2 3 0,001139 0,00289 0,590
YC00 16 . 0.004451 - 0,994
82
-
2. 1.1.1.01.006.0327-2008 . .
3. - . 1.1.1.01.007.0281-2010
4. .., .., .. - - . 2- - - , . . 19-23 2001.
5. -. .., .., .. , .. -. . - . 15. . , , 2006, . 100-116.
6. .. -440 . 2- -
. - , , , 2006.
7. .., .., .. -1000 . . . - . 19. . , 2007, . 43-54.
8. .., .., .., .., .. , .. 2- - -. . - . - -. 21. . . 2008, . 31-36.
The paper summarizes experience in implementation of SACOR at operating power units of NPP during their lifetime extension. The first stage is the selection of control points and zones for which the service life of equipment and pipes is predicted, as well as development of the program to control lifetime characteristics. Approaches are defined for a quantitative estimation of cumulative fatigue damage in the chosen control points and zones at power units after long-term operation. Methods of operating parameter monitoring with the use of other diagnostics systems applied previously at NPP and examples of solving the operational problems by means of the introduced SACOR are shown.
: , , , , , , , .Keywords: lifetime extension, control of lifetime characteristics, cumulative fatigue damage, stratification, equip-ment and pipes, reactor plant, displacement of equipment, control points.
83
-
2008-2011 .. - - - (- -). [1]. - , - , - , [1,2]. Generation-4, , - - [3,4]. - : - 5-10% , - , - ( - -).
, - ( 600 25 ) . - - , - , - .
- - , , , - -, , .. [4-6].
, - - . -, - 540 , .. 50-60 , . - -. [7].
621.039.57
.., ...; ..; .., ...; .., ... ([email protected]); .., ...; ..
( )
.. ...; ..; .., ...( )
- -
( 30.10.2014 .)
- (small test reactor) - - (-88/97, .1.2.5) - . - -, .
84
-
- - ~600. , - .
: - - 24-30 - 590-600. : 35 , - 650. 37,5 700 [3]. , , - - .
, - - . - - -, (test reactor) 100 - -. - (-88/97) .
- -, - - .
SCWR
- 50- 60- . 21 - Generation-4 "Super Critical Water Reactor (SCWR)". 2000 2013 .. - (ISSCWR-1ISSCWR-6) SCWR , , , , , , . - SCWR [2, 4]. PWR - 16 25 , 320 500 625 . 35 % 40-45 %. SCWR - [3]. - - - 0,4 ( ) , 1, - , 238U [1].
15 SCWR. SCWR, , 1 [2,4]. 21 , - (), - - , () - [1]. - - ,
85
-
(, -, ), (, ) - (, , , - - .). - 270-290 350-388 25 , ( 1). - . - .
- -88/97 (.1.2.5) , , , - , , - . -082-07 .2.1.4 ( - - , ). , -, ,
, . - - - . - (test reactor) , - .
- , . - ( ):
- () - . - [4, 8];
1
SCWR-R SCLWR
SCWR
Ultra-CANDU+
SCWR HPLWR
SCWR
SCFR
, 3989 2273 3570 2540 2188 2284 3832 , 1739 950 1600 1220 1000 1000 1698, % 43,7 42 44,8 48 44 43 44,3 . , C 350 280 280 350 280 280 280 , C 510 508 500 625 508 500 523 , 25 25 25 25 25 25 25 , / 2518 1816 1843 1312 1113 1177 1897
- -
86
-
-- ( -, test reactor) - ;
- - , , .
- - , - .
- - - - - - - (, -, .) (, , - ). -60 ( 60 ) (150 ) - , - - - .
PWR - , - (). -, . -, - .
(BWR ) PWR - - , . , , Humbold Bay, Dodewaard . [9]. , ()
. -. - BWR - 6004200 - ( ), - ( ):
- ( BWR-1BWR-6, 1955-1972 .);
- (ABWR, 1996 .).
( SBWR ESBWR, - ).
-50 - - (. , 1965 .) [10]. - . [11] - . - ( ). ( - 1,8 , - 2 ). - , (- ) [12].
, , -50 150 200 .
, - - .
SCWR - BWR
87
-
- , - . - BWR SCWR -- .
, SCWR
- SCWR - : =25 600-650C. - - - , , , - , , . - - -88/97 -082-07.
- , - . - (=22,1 , t=374,1C). > - . - , ( =25 , ~ 385C). 350-400C =25 - 3 - 625 /3 166 /3; - 1626 2583 /. - . -- .
SCWR, - BWR, - - - .
- .
[5, 6, 8, 13, 14]. ~10 . - , [5, 6, 8]. - , , - [13]. , , .
- . - , ( .. .. [14]). , BWR -50, - , , - [15, 16].
, , - . SCWR , , - - -. , - -.
-50,
88
-
- - () [17].
SCWR, , - , - . - . (, - , -- .).
- (-50, -60 ), , . . . - .
-
- (, -, , - .) ( , , ). - - , , [1].
- - -. - [1].
- -. 2 3 - [18].
-
. - : = 5,1810
14 /2 ( 0,11) = 8,851014 /2 ( 4 ).
-: 6,14( 0,11) 12,0( 4 )1014 /2. , - - (- 20%). , . - .
1. - - SCWR:
- ;
- (test reactor);
.
2. SCWR - -
. -
89
-
. - - - , , -88/97.
3. - , -. ( ).
4. (-60 -, -50
-300) - - 100 ( ) , .
5. - , . - - , .. .
2
- ( SCWR) [18]
1)
, 3830 , / 1890 , , 24,5 , 270-290 , , 540 , 350 , 27
, 600
, 60 , : - -
21,15,32
, . 241 (), 207
, 205 , 2,25 , 10,70,55 2)
, 12
, / 115
, / 156 , :- -
4,053,76
0,94 , / U 40 60
, 50
, 5 , . 121) , 2) -68
90
-
, .
1. .., .., .. : . - , , 6, C.3-10, 2010.
2. Duffy R.B., Pioro I.L. Supercritical water-cooled nuclear reactors: revief and status, Nuclear Energy Materials and ReactorsVol.II, Encyclopedia jf Life Support Systerm (EOLSS).
3. , .1 , .. , .: , 2008, 472 .
4. .., .., .., .. . - (-). (), , - 25, . 2009, .5-14.
5. .., .., .., ..
, -3051, , 2005, 51 .
6. .., .., .. - / -2988. : , 2003, 20 .
7. .. - : . - . - .: , 1987, 280 .
8. .. , , .1, 2, 1963, .267-275.
9. Ragheb M. Boiling Water Reactors, chapter 3, 04.09.2011, multimedia_fukushima_data_General Documents_uiuc.edu_Boiling Water Reactors[1]
10. .. . - , /306 , Zeneva III, , 1984, . 237-247.
11. .. . , , 5, 1968, .63-67.
12. Nayak A.K., Vijayan P.K. Flow Instabilities in Boiling Two-Phase Natural Circulation Systems: A Review (Review Article), Science and Technology of Nuclear Installations,Volume 2008
3
-
, 30 , / 14,7 , 25 / , 290/540 U2 (U + Pu
)2 (U + Pu)2
D.*)/, 73,9/85 66,1/70 66,1/70 /, . 91/90 73/72 73/72 , 5,23 5,23 5,23
/, . 19/18 19/18 19/18
, 12 12 12/ , 10,7/0,55 10,7/0,55 10,7/0,55 / (..) , 1728,4/345,7 1139,2/256,6 1159,7/236,1
, /3 82,4 125 125 , / 105,4 159,7 159,7
*) D... ( ), ().
91
-
(2008), Article ID 573192, 15 p. http://dx.doi.org/10.1155/2008/573192
13. Li H., Zhan M., Cu H. et al Heat Transfer Research on Supercritical Water Flow in 2x2 Bundles, report ISCWR-2013, China, Shenzhen March, 2013.
14. Pioro I.L., Duffey R.B., Heat transfer and gidraulic resistance at supercritical pressures in power-engineering applications, ACME; NY, 2006.
15. .. . -- - ( - -50). . , , 28-31 2013, http://www.gidropress.podolsk.ru/files/proceedings/mntk2013/autorun/article141-ru.htm
16. .., ..
-50 - RELAP5/MOD3.3. . . , 2007, .19, . 111-122.
17. .. . - -50, - , - - -, , 10-16 1968 ., .72-78.
18. Baranaev Y.D., Glebov A.P., Kirillov P.L., Neutronic Characteristics of a 30 MWt SCW Experimental Reactor: From Water-Cooled Power Reactor Technology to a Direct Cyclr Nuclear Reactor with Supercritical Water Parameters and Fast Neutron Spectrum, report ISCWR-2013, China, Shenzhen March, 2013.
The necessity is shown to create a prototype of the power plant with supercritical coolant parameters (a small test reactor) for experimental justification of engineering solutions and optimization of choice of the design and operating parameters of the supercritical pressure VVER reactor (VVER-SCP) and for meeting the require-ments of the fundamental normative document General provisions for safety assurance of nuclear power plants (OPB-88/97, i.1.2.5) regarding the use of justified and proven engineering solutions in nuclear power industry. Basic technical requirements and conceptual solutions are proposed for VVER-SCP reactor prototype, as well as suggestions are made on the research program and economically sound usage of this plant over a long period.
: , , Keywords: prototype, reactor, super-critical coolant parameters.
, - , c 1999 - .
, . 33 .
, - , , , ..
- .
www.gidropress.podolsk.ru.
92
-
, , () Rainbow-TPP, [1] [2, 3].
- Rainbow-TPP . 1 [4, 5], -7 [7]. -- Rainbow-TPP - -95 [6].
- :
10 () - ;
- 8, 9 10 - ;
- ,
- . - ;
;
;
- ;
.
- .
.
1 - [4, 5].
1 - - 12 . .
2 - 9 .
1 2,
621.039.58
.. , ... ([email protected]); .. , ...( )
RAINBOW-TPP
3- 1
( 06.11.2014 .)
- Rainbow-TPP 1 . - -95.
93
-
.
3 ( 10) - . 1-9 . =0 .. ( - ) , =279, = 159 /
2, n=4, 135 .
3 - , -7/, . - - (10) - -7/ [7].
- - 4.
0,1 /.
5 - =50 .. , , ( -7/ Rainbow-TPP), , - -. : N=2194 , 10=270 , t=285.
6 - =50 .. .
7 - =304,0 .. .
5-7,
.2.
.3. 10- :
1- , ;2- , (-7/);3- , (Rainbow-
TPP); 4- , ; 5- ,
(-7/); 6- , (Rainbow-TPP).
.1.
94
-
, - -7 [7].
2
8 (10) - . 1-9 .
8, 10- - 2- Rainbow-TPP - , - -7/.
- -7/ Rainbow-TPP - , - , 9 - 12.
- - 9.
10 - =9,5 .. : N=2816 , 10=296 , t=287.
11 - =9,5 .. .
12 - =294,6 .. .
3-
13 (10)
.4.
.5. =50 .
.6.
=50 ..
95
-
. 1-9 - .
- 3- 12.
14 , 130- - , . - - , -7/ Rainbow-TPP, . , .
15 - =10,6 .. : N=2993 , 10=281 , t=288.
16 - =10,6 .. 3- .
17 - =245,0 .. .
.7.
=304,0 ..
.8. 10-
1- , ;2- , (-7/);3- , (Rainbow-
TPP); 4- , ; 5- ,
(-7/); 6- , (Rainbow-TPP
.9.
.10.
=9,5 ..96
-
1 - - Rainbow-TPP.
- 1
.11.
=9,5 ..
.12.
=294,6 ..
.13. 10
1- , ;2- , (-7/);3- , (Rainbow-
TPP); 4- , ; 5- ,
(-7/); 6- , (Rainbow-TPP)
.14. 3-
.15.
=10,6 ..97
-
- - , , Rainbow-TPP. - , - -7/ , - - - Rainbow-TPP .
1. 62 17.10.1996. , - , 1996.
2. .. , -// . .: - (-.). -1999. .2. .17-39.
3. .. .
. 621.039.534. , 1999.
4. -- - - / .., .. , .. .//. . 2003. .4. . 55-81.
5. .., .., .., .. - () 1 - . // . . 2003. 1. .32-45.
6. 116 - -95 02.03.2000. .: , , 2000.
7. 137 -7 ( 1.3) 21.02.2002. .: -, , 2002.
The paper presents results of verification of neutronic module of Rainbow-TPP code. Experimental data of the first three fuel cycles of Rostov NPP Unit 1 was used for verification. Neutronic cross-section data library is calculated by Sapfir-95 code.
: , - , , , Rainbow-TPP, -7/, -95Keywords: simulation, neutronic cross-sections, reactor plant, fuel cycle, Rainbow-TPP, BIPR-7/A, Sapfir-95.
.16.
=10,6 ..
.17.
=245,0 ..
98
-
, - (). . - . , .
() - . - . -, - , , . -, - - . , , . - . - .
1. [1]. 25 / ( ).
, - , , . - .
. , . , . , . . - . - , , , . - . , , , . , - , . . , , , , ,
621.039.534.23
.. , ... ([email protected]); .. ; .. ; .. , ...( )
( 16.10.2014 .)
, . - . , . - , .
99
-
.
, - .
- - . [2, 3] , - - . - . . - .
- - 36- , [4]. - , - . - . [2-4] - .
, - , - 70- . [5] FLECHT . - , PWR. 1010 91 , - . 19,05 , . 10,72 14,3 3,66 . - 1,66 . . .
: 0,172 0,414 ; 10,16 38,1 /;
.1.
100
-
(- ) 149 871;
11,1 100;
- 140 371,1.
. . , . - - . , . , . - , - 2,137 , 3,048 3,810 . . - , , .
FLECHT -, - - , . - FLECHT - [6], ( ) [7].
FEBA REBEKA [8, 9], , , -, . , - , - .
- 1974
- 7- . . 1975 . , 7- . - [10]. - , - -440. , , - 5 . , - . , 7 9,1 - 2,13 .
-. . - 600 . . - , , - 40 . 200 -. 2.
11 . 3 4 - . , 7- - . .
. - . , -, . , ,
101
-
. , . , .. .
1976 [11] , -440 . -, -. , ( - ). - -440, 126 2,5 - . - 10 . - . - 240 . - , - . 5, - 6. 1 , .
- . , - . 0,3 . , , 600. . - . - , - . .
.2. 7-
112 - , - ,
.3. 7-
.4. 7-
102
-
- ( 200). - 0,5 . 7 - .
, -, - . -. ,
. - , 7- . , ( 1510 ) - . , - . , ( - , , ) .
,
1
G, / t, qmax, /2 .t,
1 1,4 40 30 5702 2,4 46 24 6103 1,4/2,4 41 31,2 6304 2,06 46 28,5 6405 1,9 46 31,4 6906 1,9 40 29,2 630
.5. -440
1 ; 2 ; 3 ; 4
; 5 ; 6 ; 7 ; 8 ;
9 ; 10 -
.6.
103
-
, . 2.
, , -, , - . , - .
90- - [12, 13]. 1- , - 37 , -1000. - 1,62. , 37-
- 10 % , . .
: -
( - ) , - - ;
; -
; -
- ;
- .
4 . . :
2
7- -440
, 0,1 0,1
1 , 2,65 2,24
, 720 690
1 , / 128 57
.7.
104
-
- -97 /1 - [14]. 3 - , .
37- 8. 700, 37-- 300 . , , . . 37- , , .
, , , - - . ,
, - .
2003 . , -1000. , (126 .). - - (z= 1,345). 3,5 . -440 - - . 20 255 .
-, -440. 20 - 120 . 6 - . 10 , .
, , , -- NATIONAL INSTRUMENTS. - - :
130 ; 3 ; 10 ; 8 ; 2 ; 2 .
. . - .
. - 10-15 ( 45 /) - .
.8. 37-
-1 -2
- , ....... ...0,278 ...0,246- ,.................................................... ....90.... .....50- , /................................ ....2,0... .....4,9
- , /............................................... ...2,94.. .....1,77- , ........................................... ...700... .....700
105
-
, - 400. - , . 2-3 - .
, , , , . - 650 -. , .. - . - - , .
- :
;
; ; ;
. -
- 800 . 4 . 9-11. - 4.
- . ( ) . - 400 .
.9. 1.
1-9 ; N-
.10. 2.
1-9 ; N-
.11. 3.
1-9 ;N-
3,
, , / /
7 0,278 2,94 2,0
37 0,246 1,77
