SK08ST009 - inis.iaea.org
Transcript of SK08ST009 - inis.iaea.org
SK08ST009Fuel cycles of WER-440
Yu.M. Semchenkov,V.V. Saprykin, I.I. Yasnopolskaya, A.N. Novikov
Russian Research Center "Kurchatov Institute"
ABSTRACT
The paper has as an objective to make conclusions for works performed onmodernization of VVER-440 fuel cycles. Possibilities and perspectives on further improvementof neutronics and operation characteristics of WER-440 are discussed basing on additionaloptimizations of fuel assembly design and of fuel load patterns. Discussion is applied to reactoroperation with power levels of 100 and 112% comprising equilibrium refueling regimes.
While obtaining operation experience on VVER-440 reactors {Ref.}, numerousadvancements of fuel assembly (FA) design characteristics have been realized having as anobjective to improve reactor safety and economics of fuel cycle. Below the effect of theseadvancements is demonstrated concerning neutronics and operation core characteristics. Inparallel the development of neutronics codes was in progress that has ensured an optimization ofcore load arrangement for improving of fuel cycle economics. In particular a reloading type "in-in-out" has been assessed ensuring lower neutron leakage from the core and reduced neutronfluence on reactor vessel. Below possibilities of further fuel cycle modification are discussedconcerning an optimization of fuel assembly design characteristics and features of fuel loads.
Advancement of base design of fuel assemblies (see Table 1 and Figs. 21-23, 25)allowed to increase sufficiently an effectiveness of fuel use due to:
using of zirconium spacer grids and reducing of FA shroud tube thickness thusincreasing FA multiplication factor;grading of fuel enrichment in plane of assembly fuel clusters thus reducing apeaking factor of linear fuel pin powers and ensuring by this a lightenedrealization of core loads with reduced neutron leakage;increasing of initial enrichment of fuel feed and reducing of fuel fraction replacedduring fuel reloading;using of burnable poison on the base of Gd2Os integrated with fuel ensuringdesirable fuel load arrangement and leading to improvement of load safety.
Effects of performed modifications of VVER-440 fuel cycle are presented in Table 2and Figs. 1-13.
Fuel cycles of Variant 5 at the use of working FAs and FAs with regulating absorberpart (ARK) with average fuel enrichment of 3.82% are applied to reactors VVER-440 of Novo-Voronez NPP (Russia), Kola NPP (Russia), Dukovany NPP (Czech), Bogunice NPP (Slovakia),
105
Mohovce NPP (Slovakia), Paksh NPP (Hungary) - with realization of power increase up to108%.
Fuel cycles 5 at the use of FAs with average fuel enrichment of 4.21% are applied tothe Unit 4 of Kola NPP and to the Units 1 and 2 of Rivno NPP (Ukraine).
Fuel cycle 6 is realized at the use of FAs with average fuel enrichment of 4.4% andwith uranium-gadolinium fuel pins at the Unit 4 of Kola NPP and at the use of FAs with averagefuel enrichment of 4.38% and with uranium-gadolinium fuel pins it is being realized atDukovany NPP (Czech). The same fuel cycle at the use of FAs of Second generation (see table1) with average fuel enrichment of 4.25% and with uranium-gadolinium fuel pins is beingrealized at Slovakian NPPs.
The assessment is in progress for using of graded FAs of Second generation withaverage fuel enrichment of 4.38% and with uranium-gadolinium fuel pins at the reactor powerincreasing up to 105-107% at NPPs in Czech and Slovakia.
Characteristics of fuel cycles which could be realized due to additional possiblemodifications of FA design and optimization of fuel reloading scheme are presented in Table 3and Figs. 14-20.
Possible changing of fuel cycle characteristics at the use of FAs of the Secondgeneration (see Table 1 and Fig. 25) with the same enrichment 4.38% in working FAs and ARKsis illustrated in Table 3 (variants 8-10) and Figs. 14-16. The feature of these variants is anincreased duration of ARK operation (6-7 years).
Possibility of power load factor increasing at the use of FAs of the Second generation(see Table 1 and Fig. 25) with enrichment 4.38% in working FAs and in ARKs is illustrated inTable 3 and Figs. 17-18. Here in Variant 11 the fuel load operation between reloadings isincreased up to 18 months due to increased number of reloaded FAs (126). In Variant 12 areactor power is increased up to 1540 Mw at the increased coolant flow rate of 43000 m3/h andat the reduced peaking factor of core power distribution due to reloading scheme optimization.
In Variants 13 and 14 the possibility of further design optimization for FAs of theSecond generation is presented (see Table 1 and Figs. 19, 20, 27) due to:
increasing of average fuel enrichment up to 4.87%;increasing of fuel pin weight due to increasing of fuel pellet diameter up to 7.8mm and liquidation of pellet central hole(fuel pins of the Third generation).
Analyzing the results presented in Table 2 it could be concluded that the mentionedmodifications in the FA design of the Second generation allow to increase additionally aneffectiveness of fuel use in WER-440.
Almost all neutronics calculations (at coolant flow rate of 39000 m3/h and reactor inlettemperature of 270 C) have been performed with modern code complex of VVER physicsDepartment in the Institute of Nuclear Reactors of Russian Research Center "KurchatovInstitute": TVS-M and KASKAD (BIPR-7A and PERMAK-A). Calculations for the variant with112% power have been performed at the coolant flow rate of 43000 m3/h at reactor inlet.
Calculational results allow to believe that all considered perspective variants of fuelcycles will meet design requirements. Introduction of fuel cycles with increased power of 112%and reactor operation duration of 18 months will increase significantly a power load factor.Application of increased fuel enrichment and increased fuel pin weight improves aneffectiveness of fuel use.
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REFERENCE
Gorokhov A.K., Dragunov Yu.G., Lunin G.L., e. a., Assessment of neutronics andradiation parts of VVER designs. M., Akademkniga, 2004 (in Russian).
107
Characteristics of fuel assemblies
Table 1
Types of fuel assemblies
Characteristics of fuelassemblies
1Length of IF A active part incold state, cmWeight of uranium in IFA, kgLength of CA active part in coldstate, cmWeight of uranium in CA, kgSize "for key" of FA shroudtube (IFA/CA), cmFuel enrichment profiling acrossFA cross section
Burnable absorbers
Weight content of U-235/Gd2O3
in fuel of"tvegs", %Fuel enrichments in fuelrods, %Average fuel enrichment inFA, %Thickness of shroud tube of FAIFA/CA, mmMaterial of FA shroud tube
Material of spacer grids
Number of fuel rods in FAPitch of fuel rodslocation, cmOuter diameter of fuelrod, mmThicknes of fuel rodcladding, mmMaterial of fuel rod cladding
Diameter of fuel pellet, mm
FA of basictype
2
242120.2
232115.2
14.4/14.4no
absent
1.6, 2.4,3.6,4.4-
2/2.1zirconium
alloyStsteel
126
1.22
9.1
0.65zirconium
alloy7.56
Shtatny FA
3
242120.2
232115.2
14.5/14.4Yes
(see fig.21-23,25)
Gd2O3 - in 6fuel rods4.0/3.35
3.3,4.0,4.4,4.6
3.82,4.21,4.38,4.4
1.5/2.1zirconium
alloyzirconium
alloy126
1.23
9.1
0.65zirconium
alloy7.56
FA of 2d
generation
4
248126.2
236120.2
14.5/14.5Yes
(see fig24-27)
Gd2O3 - in 6fuel rods4.0/3.35
3.3,4.0,4.4,4.6
3.84, 4.25,4.87,4.38
1.5/1.5zirconium
alloyzirconium
alloy126
1.23
9.1
0.65zirconium
alloy7.6
FA of 2d gen.With rods of3d gen
5
248136.5
236129.9
14.5/14.5Yes
(see fig 27)
Gd2O3 - in 6fuel rods4.4/3.35
4.95, 4.6,4.4
4.87
1.5/1.5zirconium
alloyzirconium
alloy126
1.23
9.1
0.6zirconium
alloy7.8
108
Table 1 (continued)
1Diameter of central hole infuel pellet, mmDuration on FA operationin reactor, yearContent of Hf in materialsof fuel rod cladding and FAshroud tubes, %Correspondence betweenFA marking and averagefuel enrichment in FA
21.4
< 4
0.05
IFA E-2.4%IFAF-3/6%CAN-24%
31.4
< 5
0.05
IFA 1-2,4%,IFA G-3.6%CAS-2.4%CAH-3.6%IFAK-4.4%IFAU-4.4%
proff.IFAO-3.82%IFAP-4.21%IFAV-4.38%
41.2
7
0.01
CAC OG-3.84%
IFA VW-4.25%CACY-4.87%CAFY-4.87%
IFAFUV-4.38%
CA CVU-4.38%
50
7
0.01
IFA FZ-4.87%CACZ-4.87%
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0 50 100 150 200 250 300W= 1375 MW
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1.60 ^
1.52J-
1.441-
L36J-
0 50 100 150 200 250 300T, EFPD
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0 50 100 150 200 250 300 0 50 100~ 150 200 250 300T, EFPD
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50 100 150 200 250 300
310
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280
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0 50 100 150 200 250 300W = 1375 MW
120CH-
0 50 100 150 200 250 300 0 50 100 150 200 250 300
0 50 100 150 200 250 300 0 50 100 150 200 250 300T, EFPD
Fig. 3. Main neutronic characteristics in the equilibrium fuel reloading regimes(variant 2, odd year of operation)
114
50 100 150 200 250 300
310 1-
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1 24l\
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1.20 -1-
0 50 100 150 200 250 300
1.18-40 50 100 150 200 250 300 0 50 100 150 200. 250 300
T, EFPD
Fig. 4. Main neutronic characteristics in the equilibrium fuel reloading regimes(variant 2, even year of operation)
115
0 50 100 150 200 250 300
310 i -
300-j-
290-j-
280 f
270 1
0 50 100 150 200 250 300W = 1375 MW
1200- j -
S 800€ -
0 50 100 150 200 250 300 0 50 100 150 200 250 300
0 50 100 150 200 250 300 0 50 100 150 200 250 300T, EFPD
Fig. 5. Main neutronic characteristics in the equilibrium fuel reloading regimes (variant 3)
116
0 50 100 150 200 250 300
310
300
290
2 a o
270
0 50 100 150 200 250 300
1.26 4
1200-1-
800-j-
400^-
0+r
50 100 150 200 250 300W = 1375 Mff
•I I | M I
0 50 100 150 200 250 300
0 50 100 150 200 250 300 50 100 150 200 250 300T, EFPD
Fig. 6. Main neutronic characteristics in the equilibrium fuel reloading regimes(variant 4, odd year of operation)
117
0 50 iOO 150 200 250 3000 1 u i inr t i j;TrTTTTrrrnTnTTrrfrrrrrrnT|
0 50 100 150 200 250 300VI = 1375 Mff
0 50 100 150 200 250 300
1200^-
400 i-
00 50 100 150 200 250 300
TTTJTTTTTrfrTTTTrTTTfnTTTTnTfn^
0 50 100 150 200 250 300 0 50 100 150 S00 250 300T, EFPD
Fig. 7. Main neutionic characteristics in the equilibrium fuel reloading regimes(variant 4, even year of operation)
118
TE0BC= 285.3 EFPDTmv= 304.8 EFPDTEOc= 304.6 EFPD g
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0 50 100 150 200 250 300
310 -I"300 4-290-j-280 J-270 4 .
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0 50 100 150 200 250 300
1.36-r
0 50 100 150 200 250 300
0 50 100 150 200 250 300 0 50 100 150 200 250 300T, EFPD
Fig. 8. Main neutronic characteristics in the equilibrium fuel reloading regimes(variant 5, odd year of operation)
119
0 50 100 150 200 250 300 0 50 100 150 200 250 300W= 1375 MW
310|-300-j-290-]-2801-270 I-
1200 4-
| 8001-
* 400-j-
.1 In0 50 100 150 200 250 300
1.35 |-
1.34jr
1.33-j-
1.32-j-
1.31 j
0 50 100 150 200 250 300
50 100 150 200 250 300
0 50 100 150 200 250 300T, EFPD
Fig. 9. Main neutronic characteristics in the equilibrium fuel reloading regimes(variant 5, even year of operation)
120
0 50 100 150 200 250 300
o 3 1 0 f5% 3001-SJ 290f% 2ao -j-J - 270-1-
c
1200 i
800]
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TTTTtTTTT,
200 250W = 13
TTTTKTTT-
30075 MW
0 50 100 150 200 250 300
0 50 100 150 200 250 300 0 50 100 150 200 250 300T, EFPD
Fig. 10. Main neutronic characteristics in the equilibrium fuel reloading regimes(variant 6, odd year of operation)
121
0 50 100 150 200 250 300
o 3 1 01"p 300\-~A 290o°h 280-j-| 270I-
TEOC= 303.1 EFPD
0 50 100 150 200 250 300
0 50 100 150 200 250 300
E
1200-
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* 400-
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D
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50
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100
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150
150
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200
200
/
250 300W= 1375 MW
250 300
/
0 50 100 150 200 250 300T, EFPD
Fig. 11. Main neutronic characteristics in the equilibrium fuel reloading regimes(variant 6, even year of operation)
122
is I
0 40 80 120 160 200 240 280 0 40 80 120 160 200 240 280
W = 1375 MW
0 40 80 120 160 200 240 280 0 40 80 120 160 200 240 280
T, EFPD
Fig. 12. Main neutronic characteristics in the equilibrium fuel reloading regimes(variant 7, odd year of operation)
123
0 40 80 120 160 200 240 280
I -3101- - -300|-290|-280|-270-t
0 40 80 120 160 200 240 280
1200^
40 80 120 160 2U0 240 280
W = 1375 MW
1 I n n0 40 80 120 160 200 240 280
0 40 80 120 160 200 240 280 0 40 80 120 160 200 240 280T, EFPD
Fig. 13. Main neutronic characteristics in the equilibrium fuel reloading regimes(variant 7, even year of operation)
124
310 f-
300|-
290J-280 j-
270 i-
t
1200 i
400 4
40
,ni|,,n.
80 120 160 200W =
40 280
1375 MW
Inimii.lnn120 160 200 240 280 40 80 120 160 200 240 280
120 160 200 240 280
T.EFPD
Fig. 14. Main neutronic characteristics in the equilibrium fuel reloading regimes (variant 8)
125
0 50 100 150 200 250 300
310
300
290
280
270
1.40
1
0 50
12001
| 800 \
* 400 \
j
100
1
150 200 250 300W= 1375 MW
0 50 100 150 200 250 300 0 50 100 150 200 250 300
1.68 #
> 1-60 J-I
1 1 I l l0 50 100 150 200 250 300 0 50 100 150 200 250 300
T, EFPD
Fig. 15. Main neutronic characteristics in the equilibrium fuel reloading regimes (variant 9)
126
3l2 |
al
T"
[ : :
c=310.8 EFPDc= 330.1 EFPD= 330.1 EFPD
50 100 150 200 250 300
7
3101-
300-1-
290 j-
2ao|-270 i-
0 50 100 150 200 250 300¥= 1375 MW
1200-̂ -
400
00 50 100 150 200 250 300 0 50 100 150 200 250 300
1.32 ̂0 50 100 150 200 250 300 0 50 100 150 200 250 300
T, EFPD
Fig. 16. Main neutronic characteristics in the equilibrium fuel reloading regimes (variant 10)
127
0 50 100 150 200 250 300 350 400 450 500 50 100 150 200 250 300 350 400 450 500
T, EFPD
Fig. 17. Main neutronic characteristics in the equilibrium fuel reloading regimes (variant 11)
128
310300290280270
0 50 100 150 200 250 300
0 50 100 150 200 250 300
=
1200-
400^
0-
1.68-1
g 1.60l
1.52-1
D 50
3 50
I n n
100
100
150
150
— \ ^
^rr+rrm
200
200
250 300W= 1540 MW
250 300
/ '
0 50 100 150 200 250 300 0 50 100 150 200 250 300T, EFPD
Fig. 18. Main neutronic characteristics in the equilibrium fuel reloading regimes (variant 12)
129
0 40 80 120 160 200 240 280 0 40 80 120 160 200 240 280
T, EFPD
Fig. 19. Main ncutronic characteristics in the equilibrium fuel reloading regimes (variant 13)
130
0 50 100 150 200 250 300
310
300
290
270 j-
0 50 100 150 200 250 300
0 50
1200 -i
800 i
400^
100 150 200 250 300W= 1375MW
0 50 100 150 200 250 300
0 50 100 150 200 250 300 0 50 100 150 200 250 300T, EFPD
Fig. 20. Main neutronic characteristics in the equilibrium fuel reloading regimes (variant 14)
131
CENTRAL TUBE
4.0% (84)
3.6% (24)
3.3% (18)
Fig.21. Diagram of fuel enrichment in the FA of O and T types (3.82%)
132
CENTRAL TUBE
4.6% (84)
4.0% (36)
4.0%U235 + (3.35%Gd2O3) (6)
Fig.22. Diagram of fuel enrichment in the FA of U type (4.40% c Gd2O3)
133
CENTRAL TUBE
4.4% (84)
4.0% (24)
3.6% (18)
Fig.23. Diagram of fuel enrichment in the FA of P type (4.21%)
134
CENTRAL TUBE
4.4% (84)
4.0% (30)
3.6% (6)
4.0%U235 + (3.35% Gd2O3) (6)
Fig.24. Diagram of fuel enrichment in the FA of VW type (4.25 % c Gd2O3)
135
CENTRAL TUBE
4.6% (84)
4.0% (30)
3.6% (6)
4.0%U235 + (3.35%Gd2O3) (6)
Fig.25. Diagram of fuel enrichment in the FA of V, FUV and CVU types (4.38 % c Gd2O3)
136
CENTRAL TUBE
4.0% (84)
3.6% (18)
3.3% (18)
4.0%U235 + (3.35%Gd2O3) (6)
Fig.26. Diagram of fuel enrichment in the FA of VW type OG (3.84 % c Gd2O3)
137
CENTRAL TUBE
4.95% (102)
4.4%U235 + (3.35%Gd2O3) (6)
4.6% (18)
Fig.27. Diagram of fuel enrichment in the FA of FZ, FY, CZ and CY types (4.87 % c Gd2O3)
138