Fast Breeder Reactor had been interested to be developed over the world because it inexhaustible source energy, one of those is CANDLE reactor which is have strategy in burn-up scheme, need not control roads for control burn-up, have a constant core characteristics during energy production and don’t need fuel shuffling. The calculation was made by basic reactor analysis which use Sodium coolant geometry core parameter as a reference core to study on minimum core reactor radius of CANDLE for long life Pb-Bi cooled, also want to perform pure coolant effect comparison between LBE and sodium in a same geometry design. The result show that the minimum core radius of Lead Bismuth cooled CANDLE is 100 cm and 500 MWth thermal output. Lead-Bismuth coolant for CANDLE reactor enable to reduce much reactor size and have a better void coefficient than Sodium cooled as the most coolant for FBR, then we will have a good point in safety analysis.

1.
Miura
,
R.
, and
Takaki
,
N.
, “
Study on Core Radius Minimization of Sodium Cooled CANDLE
4th Int. Symposium on Innovative Nuclear Energy System
,
6–8 November 2013
,
Tokyo, Japan
2.
Sekimoto
,
H.
, Light a CANDLE, page
12
,
CRINES Tokyo Institute of Technology
,
Japan
(
2010
)
3.
Okawa
,
T.
, and
Sekimoto
,
H.
, “
A design study on Pb-208 cooled compact CANDLE burning reactor for future nuclear energy supply
,”
Annals of Nuclear Energy
37
(
2010
)
1620
1625
4.
Takaki
,
N.
,
Sagawa
,
Y.
, and
Sekimoto
,
H.
, “Start-up fuel and power flattening of sodium-cooled CANDLE core”
Global, Salt City
,
Utah
(
2013
)
5.
Waltar
,
Alan E.
, and
Reynolds
,
Albert B.
, Fast Breeder Reactor,
533
,
Pergamon Press
,
United States of America
(
1981
)
6.
Mizutani
,
A.
, and
Sekimoto
,
H.
, “
Core Performance of Equilibrium Fast Reactor for Different Coolant Materials and Fuel Types
Ann. Nuclear Energy
, Vol.
25
, No
13
, pp.
1011
1020
(
1998
).
7.
Okawa
,
T.
, and
Sekimoto
,
H.
, “
A Design Study on Pb-208 cooled compact CANDLE Burning Reactor for Future Nuclear Energy Supply
”,
Annals of Nuclear Energy
, Vol.
37
,
1620
1625
(
2010
).
8.
Zaki
,
S.
, and
Sekimoto
,
H.
, “
Accident Analyses of Lead-bismuth Cooled Small Safe Long-Life Fast Reactor Using Metallic or Nitride Fuel
”,
Nuclear Engineering and Design
Vol.
162
, pp
205
222
(
1996
)
9.
Cognet
,
R.
, and
Greenspan
,
E.
, “
Feasibility of Lead-Lithium Coolant for the ENHS Nuclear Battery Reactor
”,
Proceeding of ICAPP 2011, paper 11119
,
France
(
2011
)
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