mcnpx simulations of spallation experiments
DESCRIPTION
MCNPX simulations of spallation experiments. Mitja Majerle [email protected]. Outline. Phasotron and EPT experiment Simulations Disagreement between experiment and simulation : Experimental uncertainties MCNPX code Other applications of MC simulations. Dubna experiments. Phasotron - PowerPoint PPT PresentationTRANSCRIPT
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Outline
Phasotron and EPT experiment Simulations Disagreement between experiment
and simulation : Experimental uncertainties MCNPX code
Other applications of MC simulations
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Dubna experiments
Phasotron Bare, lead target + 660 MeV protons Activation detectors longitudinally,
samples
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Dubna experiments
EPT Complex setup, energies from 0.7-2.5
GeV Activation detectors, SSNTd, samples
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Dubna experiments
+results from radial detectors, SSNTd, samples…
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MCNPX simulations
PHASOTRON SETUP
EPT SETUP
•Geometry is implemented in MCNPX
•Incident particles are directed to the setup
•Neutrons are counted at the places of the detectors
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Neutron spectra, cross-sections
•XS for convolution are calculated with the combination of TALYS and MCNPX codes
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Comparison exp/simPhasotron experiment
Beam monitors Longitudinal detectors
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Comparison exp/simEPT experiment
Activation detectors - radial
SSNTd
0
1
2
3
4
5
0 5 10 15
Radial distance [cm]
Bex
p/B
sim
Au-196Au-194Au-193Au-192Au-191
Energy range : 10-100 MeV Energy range : 200-1000 MeV
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Comparison exp/simEPT - (n,) reactions
EPT has neutron reflector – polyethylene (most neutrons back to the system and induce (n,) reactions)
(n,) product Au-198 reliably tells us about the number of produced neutrons
Production rates of Au-198 are very well predicted by MCNPX
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Comparison exp/sim Disagreement in the range 10-100
MeV Total number of neutrons is ok (n,) Activation detectors are NOT ok SSNTd are ok again
What are the possible reasons ? Experimental uncertainties Partially wrong code ?
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Experimental uncertainties INFLUENCE OF THE SETUP PARTS
simplifications of the setup description different parts of the setup
SYSTEMATIC ERROR (not accurately known exp. conditions)
beam geometry reactions with protons inserted detectors
ACCURACY OF SIMULATION intra-nuclear cascade model used in calculations
PARAMETERS OF THE SETUP the number of produced neutrons (spallation,
fission, ..) k (criticality)
From the seminary in 2005 :
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Polyethylene, Cd layer
The spectra were taken inside the 1st and 3rd gap.
No influence on HE neutrons.
1st gap, 3cm from axis
1E-06
1E-05
1E-04
1E-03
1E-02
1E-01
1E-10 1E-08 1E-06 1E-04 1E-02 1E+00 1E+02 1E+04
without Cd
without box
whole_setup
3rd gap, 3 cm from axis
1E-07
1E-06
1E-05
1E-04
1E-03
1E-02
1E-01
1E-10 1E-08 1E-06 1E-04 1E-02 1E+00 1E+02 1E+04
without Cd
without box
whole_setup
absorption done by 238U resonance capture
Comparison of HE part of spectra
0,85
0,9
0,95
1
1,05
1,1
1,15
0,1 1 10 100 1000
Neutron energy [MeV]
Ratio
w ith Cd/all
w ith box/all
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The wooden plate
Wooden plate under the target(1+2cm,0.5kg/l).
Without box. Detectors from top to
bottom. Asymmetry 5% =>
negligible wood influence. 0E+0
1E-5
2E-5
3E-5
4E-5
5E-5
-10 -5 0 5 10
Radial foil position [cm]
Pro
du
ctio
n r
ate
Au-198
Au-194
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Aluminum and iron holders, upper iron plate
Two simulations with and without Al, Fe components. The results do not differ outside the limits of statistical error - (HE 3%, LE 10%)
The upper iron plate reduces the number of neutrons for 2%.
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Beam profile
Simulations with 3mm, 3cm homogenous beams and with a beam with gaussian profile (FWMH=3cm).
Differences only for few percents.
Not important.-10
-8
-6
-4
-2
0
2
4
6
1 2 3 4 5 6 7 8 9 10
Foil and reaction number
beam
/3cm
-1 (i
n %
)
3mm/3cm-1
gauss/3cm-1
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Beam displacement
Beam displaced for 3,5,8, and 10 mm.
Differences between results up to tens of % Displacement must be measured as accurately as possible !
0
10
20
30
40
50
60
70
1 2 3 4 5 6 7 8 9 10
Foil and reaction
Dis
pla
ced
bea
m/c
ente
r b
eam
-1 (
in %
)
3 mm
5 mm
8 mm
10 mm
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The influence of detectors on neutron field
Metal plate on top reduces the number of neutrons only for 2%. Our detectors are much smaller.
Golden strap (2mm, 4mm) in the first gap has no influence on detectors in other gaps.
Only 0.1 mm thick golden strap is an obstacle for thermal neutrons : it can reduce the production rates of reactions with thermal neutrons inside the same gap for 20%.
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Intra-Nuclear Cascade models
In MCNPX are 3 models (above 150 MeV): Bertini CEM Isabel
The differences are up to 30% (standard, our detectors).
-25
-20
-15
-10
-5
0
5
10
15
20
25
30
1 2 3 4 5 6 7 8 9 10
Foil and reaction
mo
del
/ber
tin
i-1
(in
%)
cem
isabel
-40
-30
-20
-10
0
10
20
30
40
50
60
1 6
11
16
21
26
31
36
41
46
51
56
61
Foils and reactions of the Rez group
mo
del
/BE
RT
INI-
1 (i
n %
)
CEM/BERTINI-1
ISABEL/BERTINI-1
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Total uncertainty:50%
Setup description < 10%Experimental uncert. ca 20%Differences in models ca 30%
Total for SSNTd :>>50%
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Comparison exp/simPhasotron experiment
Beam monitors Longitudinal detectors
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Comparison exp/simEPT experiment
Activation detectors - radial
SSNTd
0
1
2
3
4
5
0 5 10 15
Radial distance [cm]
Bex
p/B
sim
Au-196Au-194Au-193Au-192Au-191
Energy range : 10-100 MeV Energy range : 200-1000 MeV
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Systematical error in analysis ?
HPGe detectors simulations (efficiencies, cascade coefficients)
Good knowledge of processes Consistent results Little chance to explain the
discrepancies…
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Is MCNPX wrong ?
Calculations with simplified setup were repeated in FLUKA code (Maxime Oden)
The same, wrong trends exp/sim were obtained (presented on Prague Physics summer school)
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Is MCNPX wrong ?Spallation experiments on thin targets
Recent experiments with protons directed on thin targets Leroy, Ledoux Trebukhovskiy, Yurevich Meigo…
Some of their simulations show that there are exp/sim discrepancies in the region 20-80 MeV
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.. or is something wrong with our experiments ?
Repeat one experiment, which we believe that is good and see if we get the same results
Perform experiments with changed setup (without blanket, uranium)
.. not very likely, so ..
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Other work connected to ADS simulations
Polish subcritical setup, based on MARIA reactor (Gael de Cargouet)
Beam from horizontal channel of the reactor
EK-10 rods
Blanket made of ENH, BaF rods and lead
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GAMMA-MD
Pb target Graphite
block
2.33 GeV deuterons
Neutron spectrum in detectors
1E-8
1E-7
1E-6
1E-5
1E-4
1E-3
1E-2
1E-1
1E+0
1E-9 1E-7 1E-5 1E-3 1E-1 1E+1 1E+3
Neutron energy
Neu
tro
n f
lux
[p-1
cm
-2]
50 cm from target20 cm from target
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Simulations unify experimental data from different experiment well, but they are not precise everywhere
Maybe we can confirm exp/sim discrepancies from completely different experiments
That many simulations require a lot of processor power (CESNET)
Thank you for your attention.
Conclusion