418
Journal of Nuclear Materials 130 (I 985) 4 I8425 North-Holland, Amsterdam
THERMODYNAMIC
PERFORMANCE
W. BOERSMA-KLEIN, FOM-Institute
OF A GAS CORE FISSION
F. KELLING,
for Atomic
REACTOR
J. KISTEMAKER
and Molecular
Physics,
Kruislaan
407,
1098 SJ Amsterdam,
The Netherlands
and R.J. HEIJBOER Westerduinweg
nr. 3, 1755 LE Petten, The Netherlands
In this work we investigated the thermodynamic behaviour of fission products and plutonium as obtained in a gas core fission reactor with graphite walls and operated at 1200 MW thermal power. Equilibrium compositions of the system U-C-F-Pu-fission products were calculated for pressures of 0.1 MPa and 2.5 MPa and temperatures of 1300 K to 10000 K. We found that the reactor can be operated at a pressure of 2.5 MPa and a wall temperature of 2500 K without condensation of any component; no carbides are formed. The main plutonium compound is PuF4 which, from thermodynamic point of view, can be recycled with UF4.
1. INTRODUCTION
the corresponding
The basic principles of a gas core fission
and operating
reactor,
conditions
build-up
of gra-
formed,
fluorine
the fuel composition
lation possibilities,
phite and using uranium fluoride as a fuel were treated previously 1,2,3 . It is shown that such
positions
a reactor,
2. FUEL COMPOSITION
based on an energy
MWth, can be operated
hold up of 0.6 ton uranium
UF4 and 30% CF43. Briefly,
lindrical diameter
(30% enriched).
of a cy-
by a layer of graphite
100 cm thick, which acts as moderator is divided
the two end sections ed by cooling pressurized
the temperature
rods of carbon,
helium
rises in the center
In
is regulat-
In the middle
is applied;
the tempe-
to about 25000 K, but
the wall has to be kept at 2500 K. Because
of
the high temperature
there
is a plasma,
in the middle
section
from which energy can be extracted
by means of electromagnetic
mainly on the inventory
of the fission
and the relative
the thermodynamic
abundances
ducts which are formed
perfor-
reactor described
of the fission
to operating
times of
50 hours till IO years and the inventory fission
products
by applying nuclear
data required
computer
about
program.
for the calculation
were based on the reactor
as calculated
temperature
The
of the neu-
for this type of reThe effective
actor by v. Dam and Hoogenboom5. neutron
of the
up to 200 hours were calculated
the "ORIGEN"4
tron spectrum
pro-
in our system. The fuel
corresponding
in the thermal region was
1300 K.
The cross sections uranium,
plutonium
of the main isotopes of
and neptunium
were calculated
the code FOUR ACES and using the da-
ta files ENDF/BIV
products,
the isotope
B.V.
OF THE FISSION
above, we needed data about the fuel composition
ourselves
0022-3 115/85/$03.30 0 Elsevier Science Publishers (North-Holland Physics Publishing Division)
AND INVENTORY
mance of the gas core fission
by applying
induction.
In the present work we concentrated
com-
of 10000 K.
PRODUCTS
fuel composition
through which
is circulated.
section only wall cooling rature
reflector.
into three sections.
with its recircu-
up to temperatures
composition
having a length of 24 m, a
of 3 m surrounded
The cylinder
The
of 70%
which are
and the equilibrium
In order to analyze
from a point of view
the reactor consists
vessel,
of
of 2.5 MPa and a
in the reactor consists
of construction,
of 1200
at a wall temperature
about 2500 K, at a pressure
gaseous mixture
production
compounds
and ENDF/BV.
species the nuclear
For the rest of data were ob-
419
W. Boersma-Klein et al. /A gas core fission reactor
tained from the LWR library of the ter program ditions
and corrected
for the operating
Table
con-
of the gas core reactor.
In the calculations computer
program
operating keeping
performed
of the gas core reactor by
the inventory
of the fissile components
performed
with different
amounts
In these preliminary
assumed
computations
that the feed consists
this latter va-
from various
points of
view, we could draw some conclusions bulk composition thermodynamic composition
it was
of uranium en-
riched from 35% to 90%. Although lue is not practical
were
of feed and
calculations
about the
total
665
Np total
21
1
Pu total
28
20
Am total
2
4
Cm total
3
7
U
described
tonium and neptunium
together
below. This
non-proliferation.
I.
requires
able in this reactor.
a factor ten more material
was about 4-7% of
these isotopes
the total amount of heavy metals.
In Fig. 1 we
tonium while
give the inventory
and plutonium
is about 67-82%
obtained
of the uranium
as a function
of operation
PUCK', PUCK', which
aspect
%
is a
an operation
is about
15-30% of the total plu-
in the gas core fission
products
obtained
in Table
II.
In Table III
0.23 0.24 0.021 0.0046
Uranium
YEARS
235 gU/s (35%U235) g IJ/s(~O%U~~~) gU/s(90%U235i gU/s (3O%U
and plutonium
235 Feed: 0.021 gU/s (90%U235i Drain: O.O046gU/s(3O%U
FIGURE 1 isotope vector as a function
Feed: 0.23gU/s Drain: 0.24gU/s
of operational
recycling
after
compounds,
YEARS
time
it
with
we give their
U 238
Feed: -'Drain: Feed: -(Drain:
reactor
time of 200 hours, together
their assumed most stable fluorine given
than avail-
In a LWR the amount of
The amount of fission
It has
isotopes
from a point of view of
YEARS
__
time.
that the main plutonium
are Pu238,
very favourable
A bomb of this composition
the amount of plu-
is given in Table
In all of the calculations
isotopes
549
of the fuel to be used in the
calculations
to be remarked
Feed: 0.23 (35% LJ3$' Drain: 0.24 g U s (30% u23 6 )
Feed: 0.021 (90% uj3u5js Drain: 0.0046 u/s (30% u2 ! 5)
the
conditions
Herefore
I. Fuel composition (Kg) after 5 years of operation at constant reactivity 1200 MWth. Initial inventory: 600 Kg U (30% U235)
with the ORIGEN
it was aimed to simulate
and of U235 constant.
drain.
ORIGENcompu-
is
total thermal
decay power and their radioactivi-
ty up to a periode of one year. From the fission
products
we selected
some
typical ones with regard to their volatility relative abundances. refreshment
Different
of the fission
their concentration
of one of the
products.
Thermal decay power KW
-~ Radioactivity MCurie
initial
7.27x 104
5240
IO min
2.27~
lo4
2370
I day
0.25~
lo4
520
after a time of
Therefore
must remain small and they
hardly will have any influence economy
and
from a LWR the
time of the fuel is only determined
by the danger of condensation fluorides
Table III. Thermal decay power and radioactivity of the fission products extracted from the reactor after an operation time of 200 hours; total amount of fission products 1.05~ 104 g,
on the neutron
in this type of reactor.
1 year Table
II.
Inventory
Element
Atomic weight
of the most abundant quantity of fission products in grams
fission
products
in case of a refreshment
For the element _I b oiling ’ point vapour pressure in Kelvin at2500 Kin Torr
Br
79.9
8
330
Kr
83.7
147
120
1.7
time of 200 hours
For the molecule moleboiling point cule in Kelvin
gas
Br2
330
gas
Kr
120
Rb
85.5
137
960
gas
RbF
1700
Sr
87.6
579
1650
gas
SrF2
2760
Y
88.9
252
3000
N IO
yF3
1660
Zr
91.2
1320
4600
1om2
ZrF4
1179*
Nb
92.9
15
4950
1o-5
NbF5
500
MO
96.0
880
4900
1O-3
MoF4
?
Tc
99.0
163
5150
1o-3
?
?
Ru
101.7
664
4200
1oe2
RuF5
520 _-
Sn
118.7
9
2550
102
SnF4
1000
Sb
121.8
8
1950
103
SbF3,5
500
Te
127.6
240
I260
high
TeF4
660
J
126.9
232
457
gas
J2
457
Xe
131.3
1620
166
gas
Xe
166
cs
132.9
513
960
high
CaF
Ba
137.4
742
1910
high
BaF2
2410
La
138.9
446
3700
-2
LaF3
‘..2500
Ce
140.1
1190
3450
-1
CeF3
2570
1520
Pr
140.9
287
3450
- 20
?
?
Nd
144.3
764
3450
N IO
NdF3
2570
Pm
145.0
63
3200
- 50
?
?
Total production * Sublimation
1.05. IO4 grams
point
421
W. Boersma-Klein et al. / A gas core fission reactor given elsewhere7.
3. EQUILIBRIUMCOMPOSITIONS The method equilibrium nimization system
applied
compositions method.
cal potentials
is the free energy mi-
as a function
Eriksson's
compositions
of the in-
the equilibrium
"SOLGASMIX"6
used. Two sets of calculations 1) Equilibrium
of the chemi-
and the mole fractions
species. To calculate
compositions
of the
The total free energy of the
is expressed
dividual
for the computation
program was
were performed:
in the temperature
range 1300 K to 4500 K. 2) Equilibrium
compositions
Equilibrium
nium, plutonium
and neptunium,
those given in Table thermodynamic
tunium fluorides
the corresponding
to those obtained 1) Equilibrium range
compositions
in the temperature
pressures
compositions
were calculated
for
200 hours, as given
it
compositions,
and several condensed
dynamic
The thermo-
data used for these calculations
are
investigated
of certain
the possibi-
species. There-
of the equilibrium
we considered
consisted
time of
II.
we included
fore in the calculations
with
viz. solid carbon.
thermodynamic
products correspond
in Table
tures up to 2400 K and 2800 K respectively
the reactor wall,
of simplicity of plutonium
after a refreshment
was assumed
that the gas is in equilibrium
and nep-
compounds.
lity of condensation
of 0.1 MPa and 2.5 MPa. For tempera-
were
were those of plutonium
In our calculations
1300 K to 4500 K.
Equilibrium
of plutonium
abundances
considered
and its fluorine
of ura-
considered
and for purposes
we added the relative and neptunium;
for
I. Because of the similar
properties
The amounts of fission
range 4500 K to 10000 K.
were calculated
of about 27% CF4, 68%
UF4 and 5% PuF4 and NpF4. The amounts
properties in the temperature
compositions
a gas phase composition
one gaseous mixture
phases. The total system of 52 species,
as given
below.
2.5 MPa
2cioo
3000 Temperature K
FIGURE 2 Equilibrium composition of the system U-C-F-Pu-fission products. "PuF3' and "PuF4" refer to the sum of the plutonium and neptunium compounds. ----- condensed species; gas species.
422
W. Boersma-Klein et al. / A gas core fission reactor
P = 2.5 MPa 0.8 0.6 .k 0.4 ti / z 0.2 IL w
s z
0.1-
4500
6000
8000 Temperature
to000
K
P= 2.5 MPa
0.008-
g 0.006.2 Lk 0.004W z ZE
0002-
Temperature
Equilibrium
composition
K
FIGURE 3 of the system U-C-F at high temperatures
423
W.Boersmu-Klein et al. / A gas core fission reactor
Gaseous
mixture
UF,
:
n=O-6;
CF,,
:
n= 1-4;
LaF,:
n= O-3;
consisting C
:
n
'ZF2n' SrF, :
data used in these calculations
of: n= l-5;
ble IV.
n= l-3;
cluded
n= O-2;
UF,
:
CF,
:
BaF,:
n= O-2;
PuF,
:
n= 0,3,4,6;
ZrF,:
n= 0,4;
LaC,
:
n=2.
F
n= 1,2;
:
Pure eventually
condensed
number of condensed
compositions
as ob-
species
we present
moles of component
not given. The relative ponents occuring the equilibrium total pressure
:
n= l-5;
at total pressures for a pres-
abundance
not given. Only
is taken into considera-
tion. of 0.1 MPa all the processes
and ionization
lower temperatures;
are shifted
dissociations
to
of CF4 and UF4
i, divii.
than 0.01 are of the com-
in minor amounts, compositions
n= l-2.
gas, no solid phase,
of dissociation
the
ded by the total number of moles of component smaller
Fn n
sure of 2.5 MPa are given in Fig. 3. Mole frac-
of the condensed
mole fractions
n=O-5;
were performed
For a pressure
The mole fractions
UF+: n C :
tions smaller than O.OOOl'are
in Fig. 2.
Actually
n=l-4;
Calculations
of 2.5 MPa are given
refer to the pure components;
are given in Taspecies were in-
of 0.1 and 2.5 MPa; results obtained
UC2' U2C3, LaC2, PuF4, PuF3, Pu equilibrium
n=O-6;
C2F2n' F-, C-, e-;
UF4, UF3, LaF3, SrF2, BaF2, ZrF4, C, UC,
The resulting
gaseous
in the calculations:
n=l-3;
phases:
tained for a total pressure
The following
as well as
corresponding
1
P~2.5
“E
MPa
0
3
0.8
to a
of 0.1 MPa are given elsewhere7.
As it can be seen from Fig. 2, condensation
of
SrF2, BaF2, LaF3, UF4, PuF3 occurs below a temperature
of about
2200 K at a pressure
MPa. At a pressure
of 0.1 MPa condensation
curs below a temperature
2) Equilibrium
of 2.5
of about
compositions
oc-
1900 K.
is j
in the temperature
o.2L 2
range 4500 K to 10000 K. Equilibrium
compositions
were calculated
initial gas phase composition UF4 and 30% CF4. Sources Table
consisting
Number density of temperature
IV. Sources of thermodynamic
Component UF,: n-1-6 UF;: n= O-5 UF,: n= l-6
data used for the calculations range 4500 K to 10000 K
Thermodynamic
property
Heat of formation
8
UF,: n=O-6 UF;: n=O-5
Difference
between
heat of forlo
FIGURE 4 of uranium atoms as a function
of the equilibrium
Component
at 298 K
mation at 298 K and 0 K
8 10 K(x103)
for an of 70%
of the thermodynamic
the temperature
4 6 Temperature
Thermodynamic '1 I
compositions
in
property
Free energy function'
C-F compounds
Standard
C-, F-, e-
mationl'
free energy of for-
424
W. Boersma-Klein et al. /A gas core fission reactor
start at temperatures pectively,
while
of 1600 K and 2400 K res-
ionization
of UF, components
Actually
we are investigating
tions which
starts at a temperature
of 4300 K. In Fig. 4 we
interested
give the number density
of the uranium atoms as
CF4 and the fission
a function
of temperature.
we accounted presented
In these calculations
for dissociation
in figures
and ionization
as
2 and 3 above.
mainly
tal fluorides separation fluoride
in the possibility products
of uranium
In Table composition
partial
of the fuel for different
most critical
conditions
pressure
It has to be emphasized
that
and relative
these values are the result of preliminary
cal-
vapour
which were performed
in order to get
about the performance
type of reactor. dynamic
from plutonium
is required.
I and Fig. 1 we give the isotopic
some estimates
fluoride
In this case no
are based on a refreshment
time of 200 hours limited by the maximum
of feed and drain.
culations
to separate
from the heavy me-
by centrifugation.
Our calculations 4. DISCUSSION
the unit opera-
should be used in the cycle. We are
Nevertheless,
calculations,
of this
for the thermo-
which were the main pur-
pose of our work, they are satisfactory. over, they give us the possibility
more detail the fuel cycle connected type of reactor.
More-
to study in
of SrF2. This compound
plutonium where7.
is the
from a point of view of volatility abundance.
pressures
the fission
allowed
Detailed
figures about
and the partial pressures
product
fluorides
tri and tetra fluorides
At a wall temperature
still a factor
are givenelse-
of 2500 K we are
five below the vapour
SrF2. Therefore
temperature
at a total pressure
of
and of uranium and
pressure of
excursions
of 200 K
of 2.5 MPa are allowed.
to this
In Fig. 5 we give a block dia-
5. CONCLUSIONS We have demonstrated
gram of such a fuel cycle.
sures of the fission
(2)
in a gas-core-fission
that the partial
product-fluorine reactor
pres-
compounds
(with a hold-up of
70% UF4 and 30% CF4), after 200 hours operation at 1200 MW thermal
8 5 30 TJ* ,I
L Reprocessing t Feed
Separator
sures. Therefore, products
ZLZ .&z Purifier
mation
fission produ;ts
CF,
I
J
(2)
1.51
x IO-~
moles/set
U CFL
FIGURE 5 Block diagram of a gas fuel cycle.
No foroccurs. beha-
with the in-
ones and with Sr, Ba, Zr compounds, formation
either of
these components. fluorine
compound
with UF4. No condensation
ly five main species exist,
about65%
is
and recycled
will occur. At a pres-
sure of 2.5 MPa and a temperature
the whole mixture
formed
point of view, thiscom-
pound can easily be reprocessed
actinides
3.45 x 10-3moles/sec
compounds
we don't expect any carbide
PuF4. From thermodynamic
(11 UFL+CFL+
carbides
of the thermodynamic
viour of other rare-earth
pres-
of fission
inside the reactor.
of uranium and lanthanum
From the similarity
The plutonium
7I Make- up CFL
no condensation
is expected
vestigated
PI Waste
power at 2.5 MPa and 2500
Kelvin are below their correspondingvapour
of 10000 K on-
viz. C,F,U,U+,e-;
is practically
dissociated
and
of the original IAraniumatoms are ionized.
W. Boersma-Klein et al. /A gas core fission reactor
425
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Nieskens,
6. G. Eriksson,
Chemica
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Nucl.Techn.
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