1 RRC KI Reduced leakage 17th Symposium of AER on VVER Reactor Physics and Reactor Safety September...
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Transcript of 1 RRC KI Reduced leakage 17th Symposium of AER on VVER Reactor Physics and Reactor Safety September...
1RRC KIRRC KI
Reduced leakage
17th Symposium of AER
on VVER Reactor Physics and Reactor Safety
September 24-29, 2007, Yalta, Crimea, Ukraine
ADVANCED FUEL CYCLES
FOR VVER-1000 REACTORS
Semchenkov Y.M., Pavlovichev A.M., Pavlov V.I., Spirkin E.I.,
Styrin Y.A. and Kosourov E.K.
RRC “Kurchatov Institute”
Moscow, Russia
2
Introduction
RRC KIRRC KI
Reduced leakage
In the present report following themes are discussed:
Stages of development of the Russian uranium fuel from the
point of view of increase of safety and profitability of fuel
loadings operation
Neutron-physical and economic characteristics of present-day
and perspective uranium fuel cycles
Potential of uranium-plutonium regenerate use in VVER-1000
reactors
Potential of weapon-grade plutonium disposition in VVER-
1000 reactors
3
RRC KIRRC KI
Evolution of VVER-1000 fuel cyclesEvolution of VVER-1000 fuel cyclesFFaaccttoorr ssccoorree FFaaccttoorr YYeesstteerrddaayy TTooddaayy FFuuttuurree
RReessuullttss
zziirrccoonniiuumm FFAA ssttrruuccttuurraall mmaatteerriiaall sstteeeell HHff
DDeelleetteerriioouuss nneeuuttrroonn aabbssoorrppttiioonn
BBuurrnnaabbllee aabbssoorrbbeerr BBoorriicc rrooddss UU--GGdd ffuueell RRaaddiioo--aaccttiivvee wwaassttee
MMaaxx KKrr,, QQll
SSttaabbiilliittyy ooff FFAA ggeeoommeettrryy LLooww HHiigghh FFAA bbuurrnnuupp lliimmiitt
MMaaxx KKrr,, QQll
FFuueell eennrriicchhmmeenntt,, %% nnoo mmoorree tthhaann 44..44 44..9955 PPeelllleett oouuttssiiddee ddiiaammeetteerr,, mmmm CCeennttrraall hhoollee ddiiaammeetteerr,, mmmm
77..5577 11..55//11..44
77..66 11..22
77..88 00..00
FFuueell hheeiigghhtt,, mmmm 33553300 33553300 ((33668800))
FFAA bbuurrnnuupp lliimmiitt,, MMWWdd//kkggUU
4499 5555 6600--6688
FFAA eenneerrggyy ppootteennttiiaall
NNuummbbeerr ooff ffrreesshh FFAA oonn ccoorree ppeerriipphheerryy ,, %%
110000 ~~ 6600 00 -- 3300 NNeeuuttrroonn lleeaakkaaggee
NNeeuuttrroonn fflluuxx oonn rreeaaccttoorr vveesssseell
4RRC KIRRC KI
Reduced leakage
Average burnup versus number of loaded FAs,
FA enrichment and cycle length
30
35
40
45
50
55
60
200 250 300 350 400 450 500 550
Cycle length, EFPD
Ave
rag
e b
urn
up
, MW
*d/k
qH
M
48 54
5.0%
36 42
60 66
72 78 3.6%%%5
3.8%
4.0% 4.2%
4.4%
4.6% 4.8%
5RRC KIRRC KI
Reduced leakage
Natural uranium consumption versus number of loaded FAs,
FA enrichment and cycle length
190
200
210
220
230
240
250
260
270
200 250 300 350 400 450 500 550
Cycle length, EFPD
Na
tura
l u
ran
ium
co
ns
um
pti
on
, g
/MW
d1
2
3
36
42
48
54
60
66
72
78 3.6% 3.8% 4.0% 4.2% 4.4% 4.6% 4.8% 5.0%
1
2
3
– 81 FA, steel
– 54 FA, steel
– 48 FA
– 42 FA
6RRC KIRRC KI
Reduced leakage
Cost of electricity generation versus number of loaded FAs,
FA enrichment and cycle length (cost of fuel-20%, reloading – 65 days)
0.94
0.96
0.98
1
1.02
1.04
1.06
1.08
200 250 300 350 400 450 500 550
Cycle length, EFPD
Co
st
of
ele
ctr
icit
y g
en
era
tio
n,
rel
5.0%
36
42 48
54 60 66 72 78
3.6%%%5
3.8%
4.0% 4.2%
4.4% 4.6%
4.8%
7RRC KIRRC KI
Reduced leakage
Cost of electricity generation versus number of loaded FAs,
FA enrichment and cycle length (cost of fuel-30%, reloading – 65 days)
0.94
0.96
0.98
1
1.02
1.04
1.06
1.08
200 250 300 350 400 450 500 550
Cycle length, EFPD
Co
st
of
ele
ctr
icit
y g
en
era
tio
n,
rel
5.0%
36 42 48 54 60 66
72 78
3.6%%%5
3.8%
4.0%
4.2%
4.4% 4.6%
4.8%
8RRC KIRRC KI
Reduced leakage
Cost of electricity generation versus number of loaded FAs,
FA enrichment and cycle length (cost of fuel-20%, reloading – 40 days)
0.94
0.96
0.98
1
1.02
1.04
1.06
200 250 300 350 400 450 500 550
Cycle length, EFPD
Co
st
of
ele
ctr
icit
y g
en
era
tio
n,
rel
5.0% 36
42 48 54 60 66 72 78
3.6%%%5 3.8%
4.0% 4.2%
4.4% 4.6%
4.8%
9RRC KIRRC KI
Reduced leakage
Average burnup versus number of loaded FAs,
FA enrichment and cycle length
35
40
45
50
55
60
65
70
250 300 350 400 450 500 550 600 650
Cycle length, EFPD
Ave
rag
e b
urn
up
, MW
*d/k
g H
M
36 42
54
66
78
36
42
54
66
78
В1 В2 В3
B1 – Fuel rod characteristics -7.57/ 1.4/ 353 cm, reduced leakage B2 – Fuel rod characteristics - 7.57/ 1.4/ 353 cm, low leakage B3 – Fuel rod characteristics -7.60/ 1.2/ 368 cm, low leakage B4 – Fuel rod characteristics -7.8/ 0/ 368 cm, low leakage
В4
В2 В3 В4
4.4%
5.0%
10RRC KIRRC KI
Reduced leakage
Loading patterns of Loading patterns of advanced equilibrium cyclesHeight of core – 3680 mm, fuel pellet diameter -7,6 mm, central hole - 1,2 mm
12-month cycle (36 FAs)Average enrichment – 4,83%Cycle length – 324 EFPDFA operational time – 4 or 5 cycles
18-month cycle (60 FAs)Average enrichment – 4,88%Cycle length – 478 EFPDFA operational time – 2 or 3 cycles
11
RRC KIRRC KI
Main neutronic characteristics of advanced equilibrium cycles
11
Advanced cycles Today's 12-month 12-month 18-month
Core height, cm 353 368 368 Amount of loaded uranium FAs, pcs 42 36 60 Amount of UGBA rods in loaded uranium FAs, pcs 252 216 900 Average enrichment, % 4,33 4,83 4,88 Reactivity compensated by liquid boron, % k/k (BOC) 8,1 8,4 9,5 Cycle length, EFPD 297 324 478
Average Burnup of unloaded uranium FAs, MWd/kg HM Maximum over FAs
49,2 53
58,5 62
52,0 61
Boric acid critical concentration at BOC, HFP, (g/kgH2O) 6,3 7,2 8,7 Maximal relative power of fuel rods in the core, Krmax 1,46 1,59 1,56 Maximal value of fuel rods linear heat rate, W/cm 285 323 318 Moderator temperature reactivity coefficient at BOC, HZP ( pcm/C) -4,7 -4,4 -0,6
Boric acid concentration at BOC, CZP, no Xe, =-2% (g/kg H2O) 10,7 12,4 13,8 Repeated criticality temperature at EOC, Xe и Sm, no boron ( oС) 182 195 182 Effective fraction of delayed neutrons, % BOC
EOC 0,63 0,56
0,63 0,56
0,66 0,55
Natural uranium consumption, g/MWd 200 188 214
12
Uranium-plutonium regenerate in VVER-1000
RRC KIRRC KI
Reduced leakage
It was proposed to use uranium-plutonium regenerate in thermal reactors by using spent fuel of these reactors cleaned from other actinides and fission products, and by following mixing of cleaned fuel with enriched uranium
Weight fraction of uranium-plutonium regenerate and highly enriched uranium at their mixing is 0,8 and 0,2 correspondingly
Enrichment of highly enriched uranium has been defined from a set of calculations under condition that the equilibrium cycle of VVER-1000 with feed by 42 fresh FAs has the same cycle length as the design uranium cycle. The enrichment of highly enriched uranium for uranium-plutonium fuel was 17,1%
13
Isotopic content of regenerated fuel (kg/tHM)
RRC KIRRC KI
Reduced leakage
Nuclide
Uranium fuel,
kg/tHM
Regenerated uranium fuel,
kg/tHM
Regenerated uranium-
plutonium fuel, kg/tHM
234U
235U 236U 238U U
238Pu 239Pu 240Pu 241Pu 242Pu Pu
235U+239Pu+241Pu
0 43,3
0
956,7 1000
0
0
0 0 0 0
43,3
1,5E-3 44,98 4,77
950,25 1000
0 0 0 0 0 0
44,98
1,5E-3 41,40 4,71
943,90 990 0,25 5,37 2,55 1,14 0,69 10
47,91
14
Main neutronic characteristics of equilibrium cycles with regenerated uranium-plutonium fuel
RRC KIRRC KI
Reduced leakage
Uranium fuel
Regenerated uranium
fuel
Regenerated uranium-plutonium
fuel Amount of loaded FAs, pcs 42 Content of 235U, % 4,33 4,48 4,14 Content of 235U+239Pu +241Pu, % 4,33 4,48 4,79 Cycle length, EFPD 297 Reactivity compensated by liquid boron, BOC, % k/k 8,1 8,0 6,4 Boric acid critical concentration at BOC, HFP, g/kg H2O 6,3 6,3 6,0 Maximal relative power of fuel rods in the core (Krmax) 1,46 1,47 1,46 Maximal value of fuel rods linear heat rate, W/cm 285 293 288 Moderator temperature reactivity coefficient at BOC, HZP, pcm/C -4,7 -6,0 -11,6
Boric acid concentration at BOC, CZP,=-2%, g/kg H2O 10,7 11,2 12,3 Repeated criticality temperature at EOC, Xe и Sm, no boron, oС 182 183 185 Effective fraction of delayed neutrons, % BOC
EOC 0,63 0,56
0,63 0,56
0,58 0,55
Effective lifetime of fission prompt neutrons, 10-5 s BOC EOC
2,0 2,3
1,9 2,2
1,6 1,9
Natural uranium consumption, g/MWd 200 185 168
15
Weapon Plutonium MOX FA in VVER-1000 core
RRC KIRRC KI
Low leakage
Reduced leakage
Fuel rod with high plutonium content
Fuel rod with medium plutonium content
Fuel rod with low plutonium content
UGBA rod
Guide tube
Instrumental tube
Preliminary researches with participation of US, French and German experts have shown possibility of use of W-МОХ fuel in existing VVER-1000.
The pattern of the typical MOX FA
16
Loading patterns of equilibrium cycles with MOX FAs
RRC KIRRC KI
Reduced leakage
MOX FAs- 30, UOX FAs-24 MOX FAs- 36, UOX FAs- 36 307 EFPD 465 EFPD 684 UGBA 1188 UGBA
17
Main characteristics of equilibrium cycles with MOX fuel
RRC KIRRC KI
Reduced leakage
* CR CPS boron is enriched by the isotope boron-10 up to 80%
12-month
18-month
Amount of loaded uranium FAs, pcs 24 36 Amount of loaded MOX FAs, pcs 30 36 MOX fuel rods part in core, % 38.2 40.3 Cycle length, EFPD 307 465 Annual plutonium consumption, kg 445 450 Average burnup of unloaded uranium FAs, MWd/kg HM 50.4 46.3 Average burnup of unloaded MOX FAs, MWd/kg HM 31.1 43.5 Maximal relative power of fuel rods in the core (Krmax) 1.41 1.47 Maximal value of fuel rods linear heat rate, W/cm 278 306 Boric acid critical concentration at BOC, HFP, (g/kg H2O) 7.7 10.7
Moderator temperature coefficient ( pcm/C) -6 -1
Boric acid concentration at BOC,CZP,=-2%,(g/kg H2O) 13.2 16.2 Repeated criticality temperature, oС 180* 177*
Natural uranium consumption, g/MWd 200 185
18
Conclusion
RRC KIRRC KI
Reduced leakage
Advanced uranium fuel cycles for VVER-1000 ensure under meeting safety requirements:
effective use of natural uranium;
possibility of cycle length variation in a wide interval and consequently possibility of NPP power production adaptation to demands of power net and to eventual changes in relations between components of electricity generation cost;
reducing of neutron fluence on reactor vessel in view of its service life prolongation.
Expanding of fuel raw material nomenclature is possible for VVER-1000 by using regenerated uranium and uranium-plutonium fuel.
VVER-1000 reactors could ensure a high rate of weapon-grade plutonium disposition at effective using of plutonium power potential.