Membrane distillation for radioactive wate treatment At the Institute method
of Nuclear
and Technology,
for low level liquid radioactive
distillation
has been developed.
advantageous,
Warsaw (INCT),
waste treatment
The researchers
of the apparatus
factors,
Chemical
but also due
solution
of’ rhis
radionuclides
finely
Radionuclides
liquid
radioactive
wasrrs.
artracrivc
in
decontamination
Traditional methods of low and intermediate level radioactive liquid waste treatment
Ion exchange Ion exchange proces\e\
industry.
nuclear
research
from orher (Isers of radioacrive medical
cenrres,
in other
scienrik
wide
range
liquid
from rhe and
such as
rhat
a
of liquid
Since the volume proceAses from
is generally
separare
the
non-radioacrive
radioactiviry
as
and
decontamination radioisoropes
J permeate
Tl
T>
asphalt
are employed radionuclides
‘I‘he
elimination
process
sewage
or
warer on
regenerated purificarion
precipirarion,
standards
water of
can methods
is
employed.
-I‘hc
(narurally
use
exchangers
of
ulrlafil~rx~on
01
small
materials
in
proved
a
ihs pr
is an c\rahlished
method
in
industry
for to
which he
including ion
rrcarmenr
of
provides
good
chosen
of
for communal
he accomplished
sedimentation,
on with
feldspars,
decotl[,lnllll.trioII
evaporation
wafer to the levels
purpose
sorthents
vcI-y effective
concentrarion.
processes
rhe concenrrarion
urilised
Iresins based formaldehyde
wirh
of
in glass,
and mulristagc
the
of
In ion
conjunction
of
reduction
and rhen fossilisation
ro reduce
To
:and rhc treatment
clays, /eoliles,
of inorganic ion
from
reprocessing.
phenol
J
6.~~1
operations
or Inorganic
are
in
of llranium
mining
fuel
material\:
synthetic)
other
the nuclear
cxrhanI;e
.lnd
Evaporarion
for suhsequenr
disposal.
by sanitary
number
Membrane Technology No. 103
concentrate
in regenerated
permirred
‘rhe
wasre and/or
includes
methods
depending Tl >T2 hydrophobic porous membrane
substances
or concrete.
Different
horn
from
groups
low
to
Evaporation
low the treatment
radioactive
from the waste, volume
of rhe concentrate
is economically
waste is quire large
inro small voIumcs
conditioning
acrivc
or
exchange,
I-clarively
extraction
organic
polysryrenc
amounts
conrain
dnd even derergcnrs.
well as radioisotopes. and the acriviry
exchange,
streams
.HL’ employed
of acrinideb
arlsing
occurring
users produce
wastes
emulsions.
wasres
and developmcnr
fields. l‘hese
initial
rhe separation
cenlres
(ion
of smges throughout from
hy onro
C. g. evaporation.
leach I’lquors coming
marerials
and research
of
parricularcs,
cycle,
waste
f.1cror.s compared
method,,
number
die il(lc
achieves
trearmenr
ICadioacrive liquid waste’s are generated
sed
hut
ionic form.
nuclear
i
in the
solurion sorprion
crc,) ‘l‘he process
in
rnainly
remove materidl.
from
d carrier,
present onto
chcmisorption, low-level
is m solid
lemtrvrd
wirh
particulares sorprion rhar arc present
ground
are
co-precipitarion
of radionuclides
process
from liquid waste by the use of an
inaoluhle
can have,
treatment.
scpararion
mcmbranc
.lIlJ
precipitation
‘Ike object&c
In this article Dr Grazyna Zakrzewskadistillation
cvap,r,trl,,n
permeation.
say this novel process is
discusses the benefits membrane
when applied to radioactive
rhermal
and its ability to utilise waste heat from
sources such as nuclear reactors.
Trznadel from INCT
a new
based on membrane
not only because of high decontamination
to the simplicity power
Chemistry
the
liquid
radioacrivc
deconraminarion~ Ikspirc
is at
when
high
(>I()‘)
discharge
is necessary
discharge
requirements.
Although
or when
conventional
costs,
invariably factors
arc
very low radioactivity
may he considered
rhat
chemical
in rhe treatment
high
in order to mcer regularory
evaporarion
operation,
and
with optracing
almoqr
deconrarnination
required
simple
high
present
for the
waste
is \utcesbtully mdustries.
of radioactive
a very used
in
its application
waste may give rise
to various
problems
such corrosion,
scaling
and
used.
foaming.
Corrosion
is a !;cvere
problem
in
by a
evaporators,
chemical exchange,
temperarure addition,
mainly of scaling
rhe
because of the relatively high heat
is caused
tl-ansfer
surface.
In
by the t&rmation
ot A W
the
overriding
factors
considerations. costs
of
streams
In short,
the
plant
are
capital
cleaning
improvement
cost has led to new and
specific for liquid
on methods
treatment.
considered
Membrane
For the selection the
secondly
the
a very
process
purity
method
describe
purification
process:
The volume
effluent the
the
ought
volume of the
rhe bulk of the radioacriviry
total activity in feed
_ a/v/ a,v,
a, are the specific
ur and
are the volumes
and
on
the
inner
surface
reducing
the heat transfer
it
expensive
making
Evaporation
more
may also enhance
of
the
There
efficiency
processes
operate.
radioactive
to
are
many
used
advantages
for
waste
the
of
membrane
concentration
(radwaste),
these
specific of
reasons
include:
corrosion.
respectively,
of feed and effluent.
Membrane
processes processes
established
methods,
can
Generally,
clean-up
of laundry
plants,
mixed
clean-up
wastes
laboratory
industry.
working
successfully
For example,
a mixed
processing
plant
Laboratory
of the Atomic
The
consists
plant
wound
tubular
is operated
the
Enhanced
Power Plant, cleaning
is also used in two stages
at
system
Removal
The contaminated polysulphone
volume
plant
volume
reduction
achieved.
decontamination (about
200)
problems
is one factor,
economically it is often used Other
processes
either
as bed
or the high costs of resin in
the case of ion exchange.
In addition,
intermediate
in
products
possible
biotechnological
processes
are a problem,
secondary
wastes,
accompanies
most other separation
can be very easily combined
with
Extensive
and the formation sludge,
feasibility
operations
etc.,
studies
have showed
processes
including
biotechnological,
or electroflotation
extraction
are
also
processes currently
and
under
as membrane
of
which
processes
membrane
can
have to be treated.
have
been
A variety particular
of factors purification
affect method,
the
choice
of any
but most notably
It
higher
seems
disadvantages
the
that
energy
that
all
production
operate
high-pressure
such regular
and
that
pressure
high
processes, requires
wastes
associated
and
which
operations
and
plant in the
secondary
45
Advantages of membrane distillation over other membrane techniques
pilot
cleaning
installations
examination.
and
some limitations
fouling,
involve
floe and
not
shortcomings,
pressure
used to separate
has been
many
complex
pilot
Good
also
give
of 10 -
is
waste treatment.
that
is treated
in the range
it
use of pressure-driven Other
electrochemical
acid
UK site an ultrafiltration
plant
easy to link in series,
at
100. At the Harwell liquid.
conditions,
other methods
solvent
of
operating
factor
with other processes,
for radioactive
are
(Table 1). A characteristic
though
competitive
that
disadvantages.
cause trouble.
boric
solution factor
factors
by other
have
Simple apparatus,
is used for
membranes
reduction
decontamination
Plant
at the Paks Nuclear
contaminated
solutions.
are several
Low energy consumption,
Processes
system.
an ultrafiltration
and recycling
that obtained
Ltd. a
by using a
River
of Canada
a
Actinide
those
methods, Moderate
and
UK. In Hungary,
factors
than
waste
units,
osmosis
reduction greater
those
many
is a high decontamination
even
blockage
in the nuclear aqueous
of microfiltration
reverse osmosis
Sellafield,
In
times
of membrane
at the Chalk
Energy
reverse
Ultrafiltration
for the
even
have
a low decontamination
of evaporation and
Volume
power
and
for recycling.
applications
factors,
to the
in nuclear
are many
technology
applied
wastes,
of boric acid solutions
fact, there
spiral
High decontamination
have been
T h e same of DFs for
radionuclides.
All treatment
of these disadvantages Membrane
activities
and z, and v<,
can be used for calculation
expression
residues
(OF) defined as
factor
total activity in efjuent
deposits
before
containing
Where
rhe
(VRF), which
factor waste
volume
of feed and effluent,
Two of
to
Decontamination
be and
to be of
treatment
DF=
solid
to
volume,
performance
of the
two First
safe discharge.
reduction
ratio
have
small
to allow
parameters
is the
evaporator,
can be
into account.
compounds to
sufficient
Table 2. Comparison of membrane distillation and reverse osmosis processes
and
radioactive
of a purification
radioactive
l
research
distillation
have to be taken
concentrated
l
the at low
as a one such new method.
assumptions
processes
radioactive
Subsequently,
development waste
Table 1. Different treatment
the
have to be minimised.
need for deconraminarion
economical
and operational
at increased
pumps
and
be
run
the
above
can be avoided
decontamination
under and
the
requirement. mentioned
by the use of MD.
This process does not require high pressures, can
of Also,
moderate
conditions
temperature. factors
were
expected
and of High with
Membrane Technology No. 103
Table 3. Preliminary cost evaluation of membrane distillation in comparison with reverse osmosis (in German DM)
,\~l)
IOI non-vola~ilc
lnostlv
low
.~nd
radioactive \hown
solutions.
which
intermediate
wastes.
I’ilot
level
tests
at
,111hll)
plani
other methods
liquid
INCYI
such high decontamination
energy sources, the process can compete
form
factor\
whcl-c only one filtration
proccsves:
of
whtch
I<0
introdllccd illu\trared
two
h.15
to rhc nuclear
.~nti Ml 1 whtch
advantage
stage is
in~lustry, stage
IS shown
capital
cost\
of membrane
is
module
110 units ofthc I&oratory
distillati~~n
i> generally
experiments
showed
effluents
f.~ctor~ could
only bc c)bt.lined
similar
cnerb7
comumptton .md
the
be
than
inlprovcments.
and careful
plant
design
heat of condensation
Hut.
with
it is possible to minimise
economic
‘l‘he study plant
INCT
reactor
makes
of the MD
experiments
process,
discharged
stainless
and minimising
all radioisotopes
or
factor
is
stream Such
not
are
that can in
utilised
processes.
many accurate
to recover heat
MD
more
beneficial.
The
reached
two
a
of
MI1
of the following
.
‘The capability
the process
concentrations
of waste of
the
to produce required
radwaste
high
for
the
in concrete
Membrane
l
concentration
of liquid
can bc applied
Achieving
this high concentration
in a one-
l
Elimination
of high
reverse osmosis
pressures
and expensive
required
by
high-pressure
pumps Because of such advantages moderate apparatus,
process
.md the possibility
Membrane Technology No. 103
simple
of using cheap
radioactive
the
as tritium.
need
that
home
are often
waste:S. purification
of
Waste in one stage and does
additional puritv
prcccsses
of water
to
ensure
discharged
to
the
Barriers to the commercialisation of membrane distillation ‘rhc
main
barriers
implementation
unit
area,
along
energy consumption
the case of nuclear power
commercial distillation
low fluxes which are ohtained
membrane
thermal
to
of membrane
stations
there
heat, so the nuclear
with
are from high
in the process, ‘l‘he
by efficient sources
research
heat recovery
or waste heat. In centres
or nuclear
ate rich sources industry
of waste
:seems I-Obe one of
the better areaS for MI) implementation.
as high retention,
conditions,
at
‘aso decreases
the complete
or by use of low-energv
wastes. .
in radioactive
latter can be overcome
to the
low level radioactive
temperatures
steel. even at Operation
environment.
the
have led researcht%rs at
distillation
of srainless
\uch
two
temperature
concentrations.
of nuclide\
the generally
(25% of solute)
stage process .
acid
drops
separates
of iodines and ruthenium
liquid
using
points:
by
conclusions:
the corrosion
nitric
such as
and
operational
MD also allows
high
processes:
advantage
over RO is the consequence
and a very followed
(membl-ant
inhibits
volatility
foaming
MD and RO show that in some case5 MD can bc
fossilisation
process
the
of
problems
evaporation
or
Lower
forms
z~vo~d:; various
scaling
streams).
present
other a
losses. svstem
MI1
entrainment
not between
of the
sorption
minimisation
with convcnrlonal
sufftctent
proposition.
to the fJlowing
enable the
evaporation.
15 higher
This IIX of waste heat from the cooling of the nuclear
inherent
from J 2.3 stage
demands
the
high
from the distillate
retention
decontamination
in Ml>
and
and
waste cenerntion.
In addition,
(e.g.
reactors)
of expensive
corrosion
technological
that in the case
process
~,perati~,nal
pilot
instead
(Iomparison
111 RO
.tttractivc
uye of plastics
removed
Ii0 plam. ‘fh~
process conditions
cycles because
for low heat
system of nuclear
The moderate
In a one-stage
are
the, price
higher
fouling
low evaporation
same cffectivc area. Additionally,
of radioactive
than
waste
total costs of installation
of the
even though
of
secondary
the
in 1’:thlc 3. It can 1,~ seen
Iowcr (for one unit plant), of .I rtm-‘Ml)
distillation
utilising
steel, eliminating evaluation
washing
corrosion,
in I:tblc J..
two methods
indicated
.i Iready
been
technolog
economic
has
of membrane plants
from the cooling
membrane
I\ still .u rhe testing
‘I’ll? prelimlnal-y that
analysis
Economic capacity
compuison
133s frequent elimination phenomena
have using
acquired. A general
.
with
used for LI.LW treatment.
l
Avoidance l”7Cs’,
of sorption
‘j4Cs+
of such ions as j°Co2*,
inside the membrane
pores
Another consumption
possible
way
is to use the
to spiral
minimise
energy
wound
module
0
increase
of
permeate
energy
consumption
warm
streams
tlux,
but
the
for additional makes
rise
of
heating
of
operation
the
uneconomic. Experiments process
showed
conditions
temperatures range This
the
optimum
higher
inlet
feed
energy
consumption
per
unit
of
is lower than that at lower temperatures.
illustrates
the importance
the unit. This design
wdistillatg
at
(70 - 80 ‘C). In this temperature
the
product
that
are
re-use
of the design
should
a significant
of
aim to recover and
amount
of conducted
heat
and latent heat of condensation. For this study, tests were performed
L
active solutions or original activity
with
integrated
heat
the GORE-TEX
now
under
integrated
energy is equal -600
interest
present. along
temperature
polarisation the
distillation A study showed
that
economically In some
nuclear
pilot
do not
of
purification
by other
It is also possible
MD
cycle methods
clean-up
processes.
One
final cleaning condensate
pass to the distillate opportunity
to
with
factor of the evaporator a hydrophobic,
comprised
the
an
with PTFE
in Japan
and was used for cleaning
At present implementation
of
which is also a barrier some new applications cost of commercial lack of commercially
0
membranes
through
modules. available
and the required
that
the heat filters
module.
The
from
through
the heater
the
the heat
and then through
Both
streams
(tetentate)
-
permeate
to
stream to
is obtained.
for speedy
(7).
cooled
temperature
down
was
Under
these
on
is the high is a
The at
highest higher
rates
distillate in
water
the
to
the
temperatures flow
radioactive
compounds
retentate.
in
Retention
retentate
was
of
complete
$=I).
Concluding remarks Membrane
processes
alternative
for nuclear
they can provide relatively
low
volume
energy
competitive membrane
combined
with
can
separation
or replace
existing
be
In easily
processes ‘Ihey
can
and also
techniques
such
extraction.
ion
etc. distillation
concentration
radioactive
justifiable
solutions
therefore
for liquid is extremely
can
treated be
replacement
for
combination
of MD with
with
of
lower
methods.
additives.
adsorption,
high
costs much
methods
other
It is economically and
and
often
require
distillation,
effluent
are
as
factors,
operating
separation
addition,
supplement
operations
consumption The
separations
do not
to be an attractive
clean-up
high decontamination
reductions.
membrane
seem
RO units with
the
reverse operated
when
radioactive interesting. volumes
of
ate not too large,
considered osmosis.
a good Finally,
evaporation
the
or even
in the nanofilttation
subsequent
lower
prove to be a very advantageous
pressures, option.
stream For further information please contact:
were obtained and resulted
the
coefficient
could
high
flow rates. The increase rate
of
in
(retention
dm’/hr.
permeate
volumes
was
ions
range,
1500
During and
radioactive
feed and
(180 - 300 dmj/m2day).
permeate
and tetentate
cooling
inlet, with
of up
conditions
inlet
in
of 45 - 80 IJC at feed inlet,
and 5 - 20 CC at distillate flow
is
process
conducted
in experiments
solutions.
the
Membrane
due
distillate the
range
the
temperature
(8).
factor.
were obtained
radioactivity
exchange,
to
was 30 - 50 dm3/hr
distillation,
The
the retention
on the level of natural
through
in the heat exchanger process
distillate
(BWR).
did and
results
after
of distillate
as
of waste heat is possible
exchanger
The
a
The outlet
at the
activity
coefficients
is lower than that of the cold
and recovery
heat
are set in such a
transport
pS/cm
flow rate significantly
permeate
place
than
cold
are returned
heat-transfer
of the warm stream
is an
In fact, there
PTFE
filters.
appropriate
membrane
This which
MD units because
the reservoir
is circulated
200
in concentration
concentration
took
The conducrivity
from
and
for pte-
through
The flow rates in the module
liquid wastes
of the process,
from
the
ions
all of them
40 hr. An increase
experiment
they
is the
working
the stream)
and warm
way
additionally
membrane
(9,lO);
with ceramic
pumping
other
temperature
for researchers
filters
(6);
X-6150
the membrane.
radioactive
stable
the reservoirs.
stages
with
barrier
(JAD
and is pte-treated
contacting
In fact, a new
reactor
(I), equipped
(sodium that
to a 10 pS/cm
with the
(3); PRI 505M
Ebara pump,
exchanger,
and
installation
Omegu supplier
(7.8);
is pumped
the pre-treatment
was developed
water
an additional
distillate
by
There
at a
salts
showed
of experiment
Similar
(V = 80 dm3) (2); a
heat
and ceramic
reservoir
factors
evaporator
demister
from a boiling
6/50)
for
decontamination
membrane. of
JAD
(4,5);
exchangers
(warm
by using a demisrer
porous
Ebara pumps
traditionally
droplets.
improve
inorganic
chloride)
decreased
not affect
of effective surface area
(V = 80 dmj)
reservoir
centre,
module
retentate heat
approx.
of specific
Bq/dmj.
in the retentate.
of distillate
low-level
The
reservoir
before
radionuclides,
m’/ht.
(4 m2); a distillate
two
were retained beginning
at the
clean
a nuclear
with a PTFE membrane
tetentate
after evaporation.
contains
from
of spiral-wound
most
several
contact
and Technology
can
-0.05
The
such possibility
of distillate often
consists
shown of
(distillate)
and
Chemistry
wastes
exchangers
any additional
that
with
potassium
did not change
plant
radioactive used
direct
2).
Cold
methods.
many
nitrate,
with non-
salts and simulated
waste samples
to 4.7.104
Experiments
for
was constructed
of Nuclear
by the PRI 505M
waste,
to use MD in specific
purification
designed
employing
distillation
radioactive
units.
decontamination
combines
modules
treatment.
produce
of
justified.
is plants
separation
for liquid
seems
is high
tests and
distillation
in a single unit without
generated
will
experiments
volumes
of MD
purpose
with
that
advantage
obtained
system
of
membrane
plant
numerous
treatment
plant
throughput
control
for low capacity
centres
large
important
a
by the
operational
of
membrane
implementation
of
The
the careful
favourable
extremely
this
(Figure
coupled
after
that do not involve
wastes
of MD
phenomena
of literature
at INCT
pilot
Institute
in the future.
analysis
A
one of the reasons
productivity
use
operations.
Results of pilot plant tests
the
sticking
in MD shown
with
researchers
membrane
However,
developments increase
recovery
implementation
This is probably
for only moderate
as
while for
are a crucial
point as far as industrial
at
is estimated
heat
most
microfiltration
radioactive
2.10’
did not pass through
kWhl,,/m3.
low fluxes
is concerned.
are
energy
per I rnj of distillate,
without
As stated,
is based on modules
Thermal
in such a module
150 - 280 kWh,,
industry
that
These
development.
consumption modules
recovery,
principle.
of inorganic
in
the
Dr Grazyna Zakrzewska-Trznadel,
Institute of Nuclear
Chemistry and Technology, Dorodna 16, 03-195 Warsaw, Poland. Tel: +48 22 811 09 16; fax: +48 22 811 15 32. E-mail:
[email protected]
Membrane Technology No. 103