After 10s the 90-99% of particles are released from the tungsten wall, mostly, towards the chamber. No element crosses the tungsten wall to the cooler.  With 1x1022p/m2of He inside the W wall, He starts occasioning damages in the material. For case HiPER4a that is not a proble

Alvarez Ruiz, Jesus

Garoz Gómez, David

Gonzalez Arrabal, Raquel

Hontoria, R.S.

Perlado Martín, José Manuel

Rivera de Mena, Antonio

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Assessment of the behaviour of hidrogen isotopes and helio in the W armor for inertial confinement

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ASSESSMENT OF THE BEHAVIOUR OF 
HIDROGEN ISOTOPES AND HELIUM IN A W
ARMOR FOR INERTIAL CONFINEMENT
R.S. Hontoria, J. Álvarez, D.Garoz,A. Rivera,
R. González-Arrabal, J.M. Perlado
Institute of Nuclear Fusion (DENIM)
DSL2011 28 June 2011 Vilamoura, Portugal 
Index
1. Inertial Fusion 
2. Case HiPER
3. Diffusion Simulation :TMAP7
4. Results
5. Conclusions and Future Plans
Brief introduction to Nuclear Fusion
Formulation D + T → He
¡¡Extremal conditions!!
Inertial confinement: Laser drive Magnetic confinement: Tokamak
ITER project 
Fusion Reaction:
HiPER
Block diagram showing HiPER Phase 4a 
representation on TMAP7:
HiPER Phase 4a 
reaction chamber. 5 
meters inner radius. 
European High Power 
laser Energy Research facility 
dedicated to demonstrating the 
feasibility of laser driven fusion
HiPER4a
CONDITIONS FOR HiPER4a
100 shoots at 10 Hz with just 5 fusion 
explosions. 
Light species yield of a 48 MJ shock ignition 
target which are transported and implanted in a 1 mm 
thick W wall.
Atoms energy: up some MeV
W temperature 2000ºC after each shot. It will 
decrease in microsec. to coolant temperature.
Coolant temperature 600ºC.
Reactor chamber is under  high vacuum 
conditions. (10-3 mbar)
HiPER4a
Fusion Products
For 48MJη=15%
D0 =1,2E
20D1= 1,05E
20
Diffusion Simulation :TMAP7
The TMAP Code was written at the Idaho National Engineering and Environmental 
Laboratory
The code let introduce heat and mass sources and drains.
Recombination/disotiation
Conventional ratedep recombination formulates the generation and release rate of 
molecules as the product of two atom concentrations at the surface and a 
recombination rate coefficient, often in Arrhenius form
Diffusion Simulation :TMAP7
Enclosures
Functional enclosures allow dynamic pressure and chemical reaction calculations to 
be included during the running of the problem. There may be diffusive flows of 
enclosure species to and from the surfaces
Traps
No traps has been taken in consideration in the simulations. But the coefficients that 
had been used in these simulations are experimental, so they had been calculated 
with traps in the tungsten.
LIMITATIONS
There are limited and confused database on hydrogen isotopes transport 
parameters in W. Therefore, the same recombination and dissociation parameters 
have been used for H,D and T.
Helium has been simulated independently with a different input, Helium does not 
has recombination/dissociation reactions in the surface
TMAP7 is a 1D model
Diffusion Simulation :TMAP7
Transport 
parameters of hydrogen 
isotopes in W used for 
diffusion in TMAP7 
model:
The  recombination 
and dissociation 
parameters that have 
been used  
D0[m
2/s] Ed[KJ/mol]
Deuterium1 5.49 x 10-10 10 
Tritium1 5.34 x 10-10 11.2
Hydrogen2 4.1x 10-7 38
K0r
[m4/s]
Er
[KJ/mol]
K0d
[molec/m2Pa]
Ed
[m2/s]
T2,D2,H2,HD,
HT,DT2
3.2 x 10-15 112 1.02x 1034 314
D[m2/s]
Helium3 10x10-10
1 Hydrogen isotope diffusive transport parameters in pure polycrystaliine tungsten 
G.A.Esteban
2 A recompilaiton of tritium-material interaction parameters in fusion reactor materials. 
F.Riter.
3 Helium behaviour and vacancy defect distribution in helium implanted tungsten
A. Debelle






RT
E
KK drdr dr
/
0/ exp/






RT
E
DD 00exp
Results
Initial distribution profile after 1 pulse. Mobil inventory (10s).
1E-8 1E-7 1E-6 1E-5 1E-4 1E-3 0.01 0.1 1
1E16
1E17
1E18
1E19
1E20
1E21
1E22
1E23
 
 
D
e
n
s
it
iy
 (
P
/m
3
)
W depth (mm)
 T
 D
 H
0 2 4 6 8 10
0.00E+000
2.00E+016
4.00E+016
6.00E+016
8.00E+016
1.00E+017
1.20E+017
1.40E+017
1.60E+017
1.80E+017
 
 
M
o
b
il 
in
v
e
n
to
ry
 (
P
/m
2
)
Temp (s)
 T
 D
 H
Isotope Particles to W per 
pulse [P/m2]
% Particles lost after 
10 seconds [P/m2]
H 1.880x1016 99.26%
D 1.350x1017 96.57%
T 1.445x1017 95.4%
Results
0 1 2
1E16
1E17
M
o
b
il 
in
v
e
n
ta
ry
 (
P
/m
2
)
Temp (s)
 T cte  800K
 T 2000-800k
Temperature effect
For this simulations there is not changes with the temperature
Results
Deuterium
distribution profile 
with time
Tritium distribution profile 
with time
Hydrogen
distribution profile 
with time
Isotope Particles T= 0s 
[P/m2]
Particles after 10 
seconds [P/m2]
Particles [P/m2]
H 1.880x1016 6.996x1014 2.004E6 (20 min)
D 1.350x1017 2.316x1016 3.064x100 (5h)
T 1.445x1017 3.325x1016 4.471x100 (6h)
0.01 0.1 1
1E13
1E14
1E15
1E16
1E17
1E18
1E19
1E20
1E21
1E22
1E23
1E24
 
 
D
e
n
s
it
y
 (
P
/m
3
)
depth (mm)
 T 0s
 T 10s
 T 6h
0.01 0.1 1
1E13
1E14
1E15
1E16
1E17
1E18
1E19
1E20
1E21
1E22
1E23
 
 
D
e
n
s
it
y
(P
/m
2
)
Depth (mm)
 D-0
 D-10
 D-5h
0.01 0.1 1
1E8
1E9
1E10
1E11
1E12
1E13
1E14
1E15
1E16
1E17
1E18
1E19
1E20
1E21
1E22
 
 
D
e
n
s
it
y
 (
P
/m
2
)
Depth (mm)
 H 0s
 H 10s
 H 20min
Results
1 2 3 4 5 6 7 8 9 10000 20000 30000 40000
0.1
1E9
1E19
 
 
M
o
b
il 
In
v
e
n
to
ry
 (
P
/m
2
)
Temp (s)
1E-4 1E-3 0.01 0.1 1
1E7
1E8
1E9
1E10
1E11
1E12
1E13
1E14
1E15
1E16
1E17
1E18
1E19
1E20
1E21
1E22
1E23
1E24
 
 
D
e
n
s
it
y
 (
P
/m
3
)
Depth(mm)
 He  0s
 He 10s
 He 106min
Helium distribution profile 
with the time
He mobil inventory (10s)
Particles T= 
0s[P/m2]
Particles  after 10 
seconds [P/m2]
Particles lost after 
106min [P/m2]
He 2.4085x1016 8.7982x1015 3.0966
Conslusions and Future plans.
CONCLUSIONS
• After 10s the 90-99% of particles are released 
from the tungsten wall, mostly, towards the 
chamber. No element crosses the tungsten wall to 
the cooler.
Element Particles
T= 0s [P/m2]
Particles 
after 10 
seconds 
[P/m2]
Particles 
[P/m2]
H 1.880x1016 6.996x1014 2.0x106 (20 
min)
D 1.350x1017 2.316x1016 3.1x1010 (5h)
T 1.445x1017 3.325x1016 4.5x1010 (6h)
He 2.4085x1016 8.7982x1015 3.1 (106 min)
• With 1x1022 p/m2 of He inside the W wall, He 
starts occasioning damages in the material. 
For case HiPER4a that is not a problem.
Conslusions and Future plans.
FUTURE PLANS
•In this study traps have not been calculated; in future investigations 
different  traps must be studied for HiPER project and its working conditions.
• A wall of steel or other structural  material must be joint to the W wall. It is 
necessary to know the behavior of  the different elements with the second 
wall, and see if there is any problem with tritium, which is radioactive.
• Another enclosure should be added in TMAP7 to be able to simulate the 
pump that goes inside the chamber. This pump will maintain the chamber 
free of isotopes and their products. It must be calculated the quantity of 
Tritium release to the coolant side after longer periods of time.
THANK YOU VERY MUCH  FOR
YOUR ATTETION


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Assessment of the behaviour of hidrogen isotopes and helio in the W armor for inertial confinement

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