ARTICLE IN PRESS
A.R. Lakshmanan et al. / Journal of Solid State Chemistry 177 (2004) 3460–3468
3461
much needed for the safety of reactor operators as well
as for the public.
sulfates are reduced to the sulfides by sodium, i.e.,
BaSO4 þ 2Na-BaS þ Na2O2 þ O2:
Experiments with water insoluble salts such as
ð2Þ
In the past, sodium has been disposed off by igniting
it by a fine spray of water and allowing it to burn in a
disposal yard located at a remote place while the
residues were dissolved with a fine spray of water and
the NaOH accumulated neutralized separately [2].
However, such a burning process releases highly
corrosive sodium aerosols into atmosphere. Use of
heavy alcohol like ethyl carbitol is not recommended for
sodium cleanup since explosions in Rapsodie, France in
gypsum, i.e CaSO Á 2H O did really confirm that
4
2
sodium dissolution in them is not feasible. Addition of
sodium into a mixture of gypsum and water resulted in
sodium fire accompanied with aerosol release. However,
the situation changed drastically with water soluble
salts. Among those tried, an aqueous solution of
(NH ) SO was found to dissolve sodium efficiently
4
2
4
1
994 and in FZK research facility in Germany in 1996
resulting in the formation of Na SO . However, a
2 4
during such a campaign indicated that it could decom-
pose to give gaseous products under some conditions
drawback in this case is the intense release of ammonia
gas which is not desirable since sodium is known to react
violently with ammonia. Sodium dissolution in aqueous
solutions of salts like Zn(NO ) and CuCl whose host
[
3,4]. The caustic process which uses a 10 M NaOH
activated aqueous solution is presently used for
destroying large quantities of sodium while decommis-
sioning the FBRs [5]. In this process also sodium
reacts with water but the reaction is made non-violent
due to the presence of concentrated NaOH. However,
to ward off any explosion risk due to hydrogen,
only small quantities of molten sodium are injected
on line at a given time into a strong current of
NaOH solution. The aqueous NaOH content is con-
tinuously adjusted to 10 M while the hydrogen gas is
diluted with nitrogen (acting as a purge gas) and
then released via a stack. The FBRs in Dounreay, UK
also employ a similar process using a 15 M aqueous
solution of sodium and potassium hydroxide for the
disposal of NaK alloy coolant [6]. The NaK feed rate
was a maximum of 18 kg/h while the solution tempera-
3
2
2
metals do not react with water turned very violent at all
salt concentrations. Other salt solutions studied include
NaCl, Na SO , KCl, LiCl, MgCl Á 6H O, CaCl Á 2H O,
2
4
2
2
2
2
CdCl Á 2.5H O, and BaBr Á 2H O. Preliminary studies
2
2
2
2
showed that the dissolution process is not entirely
peaceful in aqueous solutions of KCl, NaCl and BaBr2.
However, CdCl Á 2.5H O was quite effective. On
2
2
sodium dissolution, a black precipitate characteristic
of CdO was observed. CaCl Á 2H O aqueous solution
2
2
which gave rise to Ca(OH) precipitate was also found
2
to be effective. Na SO is another salt in which the
2
4
dissolution was found to be peaceful at high salt
concentrations. However, in this solution, Na SO
2
4
precipitation occurred during sodium dissolution due
to common ion effect. Moreover, the reaction product
consists of NaOH whose alkalinity is high. Despite
Mg(OH) precipitation, MgCl was not as effective as
ꢀ
ture was kept below 85 C. However, such a caustic
process is not suitable for cleanup of sodium in reusable
reactor components as NaOH and KOH are highly
corrosive.
2
2
MgSO . Among the aqueous salt solutions studied,
4
Epsom (MgSO Á 7H O) was found to be very efficient
4
2
Sodium-bonded spent nuclear fuel is distinguished
from other nuclear reactor spent fuel by the presence
of metallic sodium which is a highly chemically
reactive material. When the driver fuel, used mainly in
the center of the reactor core to ‘drive’ and sustain
the fission chain reaction, is irradiated for long
duration, the metallic fuel swells as fission products
are generated until it reaches the cladding wall.
During this process, some metallic sodium enters the
metallic fuel and becomes inseparable from it due to
inter diffusion between the fuel and cladding. Therefore,
mechanical stripping of the driver spent nuclear
fuel cladding is not a practical means of removing
sodium. After careful consideration of various options,
US DOE has decided to treat electro metallurgically the
EBR-II spent nuclear fuel (about 25 metric tons of
heavy metal) [7].
for non-violent dissolution of sodium metal which
results in non-corrosive reaction products. It is also an
inexpensive (50 US $ per metric ton) and eco-friendly
(used as a fertilizer) salt. Moreover, the formation of
Na SO Á MgSO Á 4H O mineral (natural bloedite) is
2
4
4
2
known to occur in nature and the solubility of Epsom in
3
ꢀ
water is quite high (91 g/100 cm at 40 C) [9]. Hence
detailed studies were carried out only with Epsom salt
solution.
The objectives of this work are two-fold. First is the
development of an improved method of non-violent
dissolution of sodium metal in which the reaction
products are non-corrosive and non-hazardous unlike
that of caustic process employing NaOH so that the
same process could be used for large scale sodium
processing as well as for the cleanup of FBR compo-
nents. Second is to develop an inexpensive liquid
hydrant/spray which is effective for sodium fire fighting
and sodium aerosol neutralization since such a devel-
opment would provide a valuable tool in the utility and
safety of sodium cooled FBRs.
In this work, in order to arrive at a non-violent and
eco-friendly method of sodium disposal, a number of
aqueous salt solutions were tried for sodium dissolution.
Literature [8] reports suggest that alkaline earth metal