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International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
EPEP--450 Steel450 Steel as Cladding Material for Fast as Cladding Material for Fast Neutron Reactor Fuel RodsNeutron Reactor Fuel Rods
A.Povstyanko, V.Prokhorov,A. Fedoseyev , F.Kryukov
JSC “SSC – RIAR”
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
0.005-0.015
0.1-0.3
0.15-0.40
1.5-2.0
0.05-0.30
11.0-13.5≤≤≤≤ 1.0≤≤≤≤ 0.50.10-
0.15EP-450
BVNbMoNiCrMnSiCComposition, % mass.
Material
VNIINM (Bochvar Institute)R I A R
Patent № 677544 15.11.77
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
Main irradiation parameters of fuel rods with EP-450 steel claddings and pelleted oxide fuel in BOR-60 and BN-350 reactors
Test time within
temperature range, h
Temperature of cladding internal layer, 0С
Linear power, W/cm
Test time at power, h
Dose,dpa
Burnup %, h.a.
UO2 fuel pelletsFA index
Reactor
-650-537470-36097506011,233% enrichmentU235
ОP-6
-690-587536-43075004810,632,8 % enrichmentU235
ОP-5BN-350
16408500
>730730-700
450125004512,5- « -ОP-25- « -- « -- « -- « -4110,6- « -ОP-24- « -- « -- « -- « -4210,8- « -ОP-23- « -- « -- « -- « -4010,4- « -ОP-22
10905780
725-700700-655
> 490490-400
100804210,8- « -ОP-21
29709903
> 690690-630
> 464464-340
1384041,513,4- « -А-337
13988685
> 667 667-620
> 477477-400
104204912,390%enrichmentU235
А-336BOR-60
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
-- tight fuel rods;tight fuel rods;
- damage fuel rods .- leaky fuel rods;
Chart of the OP-25 FA
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
Typical diametral strain in OP-25 fuel rod
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
Typical areas of local thinning damage areas and several non-through ruptures of the cladding in the upper part of the fuel rods
Damage fuel rods
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
Maximum diametral strain in OP-25 fuel rods (BOR-60 reactor) vs. maximum initial irradiation temperature (--- level of maximum allowable form change)
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
Structure of cross section fragments of OP-21 fuel rods after irradiation:
a) cladding matrix corrosion;b) cladding pitting
Corrosion
a b
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
0 40 80
120 160 200
510 560 610 660 710 Temperature, °С
Corro
sion d
epth,
mkm
Corrosion
Temperature dependence of corrosion depth in EP-450 steel claddings at a burn-up of 10.8 % h.a.
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
Decarburization of EP-450- steel claddings from the coolant side
Decarburization
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
Storage in cooling pool BOR-60
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
Storage in cooling pool BN-350
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
600 - 470352∼16330.0UO2VS-007
650 - 510478∼14227.8(0.8U+0.2Pu)O2ОG-117
650 - 530476∼13224.4(0.8U+0.2Pu)O2ОG-116
690 - 540485∼10821.0(0.8U+0.2Pu)O2ОG-115
Maximum and minimum
temperature of cladding internal
layer, 0С
Maximum linear power, W/cm
Maximum damage dose,
dpa
Burnup%, h.a.
FuelFA index
Irradiation parameters of fuel rods with EP-450 steel claddings and
vibropacked fuel
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
0,0
1,0
2,0
3,0
4,0
100 110 120 130 140 150 160 170Damage dose, dpa
Strain
, %Swelling x1/3Diameter change
Maximum diametral strain of EP-450 steel claddings
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
a b c
Structure of EP-450 steel as cladding material for BS-007 fuel rods irradiated in BOR-60 reactor (a – general view, х20000; b –voids,
dislocation network and χ -phase precipitates in ferrite, х40000; c – voidsand secondary phase precipitates in sorbite, х40000
Structure of EP-450 steel
International Conference on Fast Reactors and Related Fuel Cycles (FR09), December 7 - 11, 2009 Kyoto, Japan
�The EP-450 steel as a cladding material for fast reactor fuel rods retains its high resistance to radiation swelling at damagedoses of up to 160 dpa.
�The main factors hindering reliable performance of the fuel rods with EP-450 claddings are the maximum initial temperature and the level of stresses in the claddings caused by gas and fuel pressure.
�The problems associated with heat strength and corrosion by the iodine transport reaction can be resolved by decreasing the maximum initial temperature down to 650°C. �Use of the EP-450 steel as a cladding material in the BN commercial reactors is impossible with the FA storage technology available now.
Conclusions