design study of pb-bi- and nak-cooled small deep sea fast ... · design study of pb-bi- and...
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Design Study of Pb-Bi- and NaK-Cooled Small Deep Sea Fast Reactors
Akira Otsubo and Minoru Takahashi
N1-18, Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
2-12-1 O-okayama, Meguro-ku, Tokyo 152-8550, JapanTel: 81-3-5734-2957, Fax: 81-3-5734-2957,
E-mail: [email protected]
Abstract – The liquid lead-bismuth eutectic (Pb-Bi) has good compatibility with water, which is different from sodium.
It is expected that the Pb-Bi could be used as a coolant of the deep sea fast reactor (DSFR).
Physics analysis of the Pb-Bi-cooled small reactor cores with and without inner control rods was performed. The coolant of Pb-Bi seems to be good as well as NaK for DSFR
301010.10.010.0011W
10W
100W
1kW
10kW
100kW
1MW
10MW
100MW
TERM(YEAR)
Fixed Pointlong termcontinuousobservation
Medium-sizedsubmersible
Small deep sea submersible
Remotely operated vehicle
Sea bottomphotographing
Mother ship of submersibleSea bottom oil exploitation
Large scale fixedpoint continuousobservation
Mineralsourcemining
Fig. 1 Demand of electric power for activities in the sea
Nuclear powerHeat engine
Storage battery RI
RI & Heat engine
0.001 0.01 0.1 1 3010
Fuel cell
1W
10W
100W
1kW
10kW
100kW
1MW
10MW
TERM(YEAR)
DSFR
Fig. 2 Supply of electric power
Item NaK Pb-BiWeight 64 t 67.5 t
S.S.corrosion Twice as high as in sodium
Higher than in NaK
Coolant & sea water reaction
Violent reaction.
No reaction(right)
several hundreds kW15th from the bottom
Core immersion accident
Re liner in cladding required
No liner required
Neutron economy
Good Excellent
Coolant freezing at the sea lowest temp. of 2ºC
No freezing due to melting point of -12ºC
Freezing. Heating with NaK reactor required
Table 1Comparison ofNaK- & Pb-Bi-cooled 200kWeDSFRs used in the 6km-deep sea
AbsorberReflector
Core
Control Drum
AbsorberReflector
CoreCont. Rod
Control Drum
(a) Reactor without control rods inside core
(b) Reactor with control rods inside core
Fig.10 Schematics of Pb-Bi-cooled and NaK-cooled reactors
(a) Reactor without control rods inside core
(b) Reactor with control rods inside core
Fig. 11 Analytical systems of Pb-Bi-cooled and NaK-cooled reactors
Without inner cont. rods
With innercont. rods
FuelNitride fuel UN-PuN UNPu fraction 50wt.% 0wt.%
Enrich. of U235 20% 20-60%Enrich. of N15 100% 100%
Fuel pel. Outer diameter 5.56mm 5.56mmSmear density 85% 85%
Fuel pin cladding
Material SUS316 SUS316Outer diameter 6.5mm 6.5mmThickness 0.47mm 0.47mm
Re liner in cladding Exist. or not Exist. or notFuel pin pitch 7.3mm 6.5, 7.3mmAxial reflector Be,SUS316 Be, cladding,
coolantCore radius 10.5-14.5 cm 20.0cm
Table 2 Analytical parameters
10.0 10.5 11.0 11.5 12.0 12.5 13.0 13.5 14.0 14.5
0.860.880.900.920.940.960.981.001.021.041.061.081.101.121.141.16
Keff
Radius cm
NaK SUS NaK SUS Re liner PbBi SUS NaK Be NaK Be Re liner PbBi Be
Fig. 12 Dependence of effective multiplication factor Keffon core radius in the reactor without control rodsinside core
15 20 25 30 35 40 45 50 55 60 65
0.70
0.75
0.80
0.85
0.90
0.95
1.00
1.05
1.10
1.15
1.20
1.25
1.30
Keff
U235%
PbBi Pi:7.3mm NaK ditto. NaK ditto. Re liner PbBi Pi:6.5mm NaK ditto. NaK ditto. Re liner
Fig. 13 Dependence of Keff on enrichment of U235
in the reactor with control rods inside core
0 1000 2000 3000 4000 5000 6000
0.970.980.991.001.011.021.031.041.051.061.071.081.091.101.111.121.13
Keff
Days
PbBi NaK
Fig. 14 Change in Keff with burn-up in the reawithout control rods inside core
300 400 500 600 7000
2
4
6
8
10
12
14
16
18
20
22
24
Thermal efficiency %
Temperature C
Fig. 15 Thermal efficiency and turbine inlet temperature