Forschungszentrum Karlsruhe
in der Helmholz-Gemeinschaft Karlsruhe Institute of Technology
Nuclear Data Library for Advanced Systems – Fusion Devices (FENDL-3)
Consistent data evaluations for tungsten isotopes including covariances
P.Pereslavtsev, A. Konobeyev, U. Fischer
Association FZK-Euratom, Forschungszentrum Karlsruhe, Germany
FENDL-3, IAEA
Outline
FZK nuclear data evaluation work
◦ Consistence of nuclear data◦ Quality of the evaluated data
Tungsten nuclear data evaluations for energies up to 150 MeV
Calculations of covariances for the evaluated cross sections
Validation of the new general purpose neutron transport files
◦ TUD measurements on W at FNG◦ FNG experiment on W
FENDL-3, IAEA
FZK
Nuclear data evaluation
Nuclear data validation
(MCNP5)
Uncertainty evaluations Covariance
matrix preparation
Nuclear data evaluation in FZK
FENDL-3, IAEA
Nuclear data evaluation
Covariances and uncertancies
Data processing
Nuclear data validation
Consistent evaluation
Microscopic cross sections
Corrections based on Monte-Carlo method
Strict ENDF-6 format
Benchmark MCNP calculations
Consistent nuclear data evaluation
Data file for users
FENDL-3, IAEA
Assurance of evaluated data quality
Quality of the microscopic cross sections
GNASH and ECIS codes for nuclear model calculations Comparison with experimental data Comparison with available evaluations Correction of the data during covariances calculations
Quality of the data representation (format)
Use of the standard format checkers NJOY processing Cross check of the evaluated data
Quality of the integral data
Accurate MCNP transport calculations Evaluated data modifications
FENDL-3, IAEA
Optical model calculations
Global OMPs for n, p, d, t, 3He, from 0.001 to 150 MeV
ECIS coupled-channel and DWBA calculations
Nuclear data evaluation
GNASH, ECIS
Experimental data
Systematics
Available evaluations
Covariance matrices calculations
Unified Monte Carlo approach (D. Smith)
Nuclear model calculations
Experimental data
Corrections of evaluated data
New tungsten evaluations
FENDL-3, IAEA
Resonance parameters
Resonance parameters are taken from existing evaluations and checked against recommended data (S.Mughabghab, 2006)
IsotopeResolved region
Unresolved region
182W JENDL-3.3 ENDF/B-VII
183W ENDF/B-VII ENDF/B-VII
184W ENDF/B-VII ENDF/B-VII
186W ENDF/B-VII ENDF/B-VII
Evaluated resolved resonance parameters used are very close to the data by S. Mughabghab
FENDL-3, IAEA
5 10 15 20 25 30 35 400
500
1000
1500
2000
2500
Frehaut, 80 Qaim, 74 Vonach, 68 Xiangzhong, 97 Maslov, 72 Druzhinin, 67 EAF2007 IAEA FZK
182W(n,2n)181W
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
182W cross sections evaluations (examples)
0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 15010-1
100
101
Qaim (syst), 75 Majdeddin (syst) EAF2007 IAEA FZK IAEA (MF10, MT107)
182W(n,)179Hf
Cro
ss s
ectio
n [m
b]Neutron energy [MeV]
EAF-2007
FENDL-3, IAEA
10-11 10-10 10-9 10-8 10-7 10-6 10-5 10-4 10-3 10-2 10-1 100 101 102
0
2000
4000
6000
8000
10000
12000
14000
16000
MT4, MF3 (IAEA) MT4, MF10 (IAEA) FZK
183W(n,n')
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
Threshold
4 6 8 10 12 14 16 18 20 22 24 26 28 300
500
1000
1500
2000
Frehaut, 80 EAF2007 IAEA FZK
183W(n,2n)182W
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
183W cross sections evaluations (examples)
FENDL-3, IAEA
0 20 40 60 80 100 120 1400,01
0,1
1
10
Qaim, 75 Kasugai, 92 Filatenkov, 03 EAF2007 (n,+) IAEA FZK (n,+) IAEA (MF10, MT107)
184W(n,)181Hf
Cro
ss s
ectio
n [m
b]Neutron energy [MeV]
0 20 40 60 80 100 120 14010
100
1000
Frehaut (80) EAF2007 IAEA FZK
184W(n,3n)182W
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
184W cross sections evaluations (examples)
FENDL-3, IAEA
0 20 40 60 80 100 120 14010-8
10-7
10-6
10-5
10-4
10-3
10-2
10-1
100
101
EAF-2007 IAEA (MF3 MT800+849) FZK IAEA (MF10 MT107)
186W(n,)183Hf
Cro
ss s
ectio
n [m
b]Neutron energy [MeV]
5 10 15 20 25 30 35 400
500
1000
1500
2000
2500
Xiangzhong, 97 Filatenkov, 03 Frehaut, 80 Druzhinin, 67 Lindner, 69 EAF2007 IAEA FZK
186W(n,2n)185W
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
186W cross sections evaluations (examples)
EAF-2007
FENDL-3, IAEA
Elastic scattering angular distributions
0 20 40 60 80 100 120 140 160 180100
101
102
103
104
Annand, 85 JENDL-HE IAEA FZK
n + 184W Elastic scatteringE
n= 4.87 MeV
d
/d
[mb/
sr]
c.m.
[deg]
0 20 40 60 80 100 120 140 160 180
100
101
102
103
104 Elastic scatteringE
n= 14 MeV
n + natW
Li (1986) Pearlstein (1965) Nauta (1957) Dikarevich (1961) Schmidt, 06 JENDL-HE IAEA FZK
d/d
[mb/
sr]
c.m.
[deg]
0 20 40 60 80 100 120 140 160 18010-1
100
101
102
103
104
Delaroche (1997) JENDL-HE IAEA FZK
n + 184W Elastic scatteringE
n= 26 MeV
d/d
[mb/
sr]
c.m.
[deg]
0 20 40 60 80 100 120 140 160 180100
101
102
103
104
n + 184W Elastic scatteringE
n= 6 MeV
Annand (1985) JENDL-HE IAEA FZK
d/d
[mb/
sr]
c.m.
[deg]
FENDL-3, IAEA
Elastic scattering angular distributions (questions ...)
0 20 40 60 80 100 120 140 160 18010-1
100
101
102
103
104
IAEA FZK
Elastic scatteringE
n= 14 MeV
n + natW
d/d
[mb/
sr]
c.m.
[deg]
0 20 40 60 80 100 120 140 160 18010-1
100
101
102
103
104
IAEA FZK "pure elastic" (Leg. fit)
Elastic scatteringE
n= 14 MeV
n + natW
d/d
[mb/
sr]
c.m.
[deg]
0 20 40 60 80 100 120 140 160 18010-1
100
101
102
103
104
IAEA FZK "pure elastic" elastic+inelastic (measured)
Elastic scatteringE
n= 14 MeV
n + natW
d/d
[mb/
sr]
c.m.
[deg]
0 20 40 60 80 100 120 140 160 18010-1
100
101
102
103
104
IAEA FZK "pure elastic" elastic+inelastic (measured) elastic+inelastic (IAEA)
Elastic scatteringE
n= 14 MeV
n + natW
d/d
[mb/
sr]
c.m.
[deg]
FENDL-3, IAEA
0 20 40 60 80 100 120 140 160 18010-4
10-3
10-2
10-1
100
101
102
103
104
ENDF/B-VII JENDL-HE IAEA FZK
n + 182W Elastic scatteringE
n= 55 MeV
d/d
[mb/
sr]
c.m.
[deg]
0 20 40 60 80 100 120 140 160 18010-7
10-6
10-5
10-4
10-3
10-2
10-1
100
101
102
103
104
105
JENDL-HE IAEA FZK
n + 182W Elastic scatteringE
n= 150 MeV
d/d
[mb/
sr]
c.m.
[deg]
Elastic scattering angular distributions (high energies)
FENDL-3, IAEA
0 20 40 60 80 100 120 140 160 18010-2
10-1
100
Annand (1985) IAEA FZK
184W(n,n')184W(0'+)E
level=1.0023 MeV
En=4.87 MeV
d/d
[mb/
sr]
c.m.
[deg]
102
Günther, 82 Delaroche, 81 IAEA FZK
186W(n,n')186W(2+)E
n= 3.5 MeV
d/d
[mb/
sr]
0 20 40 60 80 100 120 140 160 180100
101
Günther, 82 Delaroche, 81 IAEA FZK
186W(n,n')186W(4+)E
n= 3.5 MeV
d/d
[mb/
sr]
c.m.
[deg]
10-1
100
101
Annand (1985) IAEA FZK
184W(n,n')184W(2'+)E
level=0.9033 MeV
En= 6 MeV
d/d
[mb/
sr]
Inelastic scattering angular distributions
FENDL-3, IAEA
Neutron emission spectra (low energy)
0 2 4 6 8 10 12 14 16 18 20 22 24 26
101
102
103
104
26 MeV 184W(n,xn)
Marcinkowski, 89 ENDF/B-VII IAEA FZK
ds/d
E [
mb/
MeV
]
Neutron emission energy [MeV]0 2 4 6 8 10 12 14
10
100
1000 Pavlik, 92 ENDF/B-VII IAEA FZK TENDL-2008
14.1 MeV 186W(n,xn)
Neutron emission energy [MeV]
ds/d
E [
mb/
MeV
]
FENDL-3, IAEA
Neutron emission spectra (high energy)
0 20 40 60 80 100 120 14010-1
100
101
102
103
ENDF/B-VII REX (ALICE) IAEA FZK
150 MeV 184W(n,xn)
d/d
E [
mb/
MeV
]
Neutron emession energy [MeV]0 20 40
100
101
102
103
ENDF/B-VII REX (ALICE) IAEA (38 MeV) FZK
40 MeV 184W(n,xn)
d/d
E [
mb/
MeV
]
Neutron emession energy [MeV]
FENDL-3, IAEA
0 20 40 60 80 100 120 1400
2000
4000
6000
8000
10000
12000
ENDF/B-VII REX IAEA FZK
184W(n,xn)
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]0 20 40
100
101
102
103
ENDF/B-VII REX IAEA FZK
55 MeV 184W(n,xn)
d/d
E [
mb/
MeV
]
Neutron emession energy [MeV]
IFMIF related data
FENDL-3, IAEA
Gas production data
IAEA: p, given in the files
FZK: p, d, t, 3He, given in the files
0 20 40 60 80 100 120 1400
20
40
60
80
100
120
140
W(n,x)
Haight, 07 (181Ta) IAEA FZK
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
0 20 40 60 80 100 120 1400
100
200
300
400
500
600
W(n,xp)
LANSCE, 05 IAEA FZK
Cro
ss s
ectio
n [m
b]Neutron energy [MeV]
FENDL-3, IAEA
Selection and treatment of experimental data
Calculations using nuclear models. Evaluation of covariance matrix by Monte Carlo method (D. Smith)
Evaluation of data and covariances using experimental data and results of code calculations
Recording in ENDF/B format
Evaluation of covariances using Monte Carlo approach
FENDL-3, IAEA
Evaluation of cross-sections and covariances using nuclear models
K
K,1kj0kji0kij,i ))(()K/1(V
Set of “best” model parameters
p0={p01,….p0M}
Result of the calculation
s0={s01, ..... s0N}
Choice of parameters by Monte Carlo
pk={p01 D pk1,,..…,p0M D pkM}
Covariance matrix after K histories
for i,j=1,N (energy)
ii
K
K,1kki
evali V)K/1(
Evaluated cross-section
FENDL-3, IAEA
8 10 12 14 16 18 200
20
40
60
80 182W(n,2n)181W
after model calculations final
Rel
ativ
e st
and
ard
dev
iati
on
(%
)
Neutron energy (MeV)12 14 16 18 20
0
10
20
30
40
50
10.5
182W(n,p)182Ta
after model calculations final
Neutron energy (MeV)
Calculations of uncertainties
Uncertainty before and after the use of experimental data
FENDL-3, IAEA
10-11 10-9 10-7 10-5 10-3 10-1 1010
2
4
6
8
10Total cross-section
Rel
ativ
e st
and
ard
dev
iati
on
(%
)
Neutron energy (MeV)
10-11 10-9 10-7 10-5 10-3 10-1 1010
20
40
60(n,)
Neutron energy (MeV)
Continuous uncertainty evaluation
Evaluated uncertancies for 183W
FENDL-3, IAEA
8 10 12 14 16 18 20
8
10
12
14
16
18
20
184W(n,2n)183W
Neu
tro
n e
ner
gy
(MeV
)
Neutron energy (MeV)
-0,8000-0,5750-0,3500-0,12500,10000,32500,55000,77501,000
8 10 12 14 16 18 20
8
10
12
14
16
18
20
184W(n,2n)183W
Neu
tro
n e
ner
gy
(MeV
)
Neutron energy (MeV)
Calculations of corelation matrix
After nuclear model calculations Final results including experimental data
FENDL-3, IAEA
-0,8000-0,5750-0,3500-0,12500,10000,32500,55000,77501,000
4 6 8 10 12 14 16 18 20
4
6
8
10
12
14
16
18
20
184W(n,p)184Ta
Neutron energy (MeV)
Neu
tro
n e
ner
gy
(MeV
)
Calculations of corelation matrix
After nuclear model calculations Final results including experimental data
FENDL-3, IAEA
0,0 0,5 1,0 1,5 2,0 2,5 3,0 3,5 4,0 4,5 5,00
500
1000
1500
2000186W(n,n')186W (E
lev=121 keV)
Lister (67) Guenther (82) prior evaluation final evaluation
Cro
ss s
ecti
on
(m
b)
Neutron energy (MeV)
6 8 10 12 14 16 18 200
500
1000
1500
2000
2500 186W(n,2n)185W
Lindner (59) Frehaut (80) Kong Xiangzhong (97) Druzhinin (66) Avrigeanu (06) prior evaluation final evaluation
Neutron energy (MeV)
Accounting for experimental data uncertanties
Final evaluation
FENDL-3, IAEA
MF=1 General description. MT=451
MF=2 Resonance parameters. MT=151
MF=3 MT=1, 2, 4, 5, 16, 17, 22, 24, 28, 41, 51-70, 91, 102,103, 104, 105, 106, 107
MF=4 Angular distributions. MT=2, 51-70
MF=6Energy-angular distributions. MT=16,22,28,91, 103-107 (below 20 MeV), MT=5 (above 20 MeV): particles, photons, recoils
MF=12Photon production multiplicities and transmission probabilities. MT=16,22,24,28,41, 51-70,91,102-107
MF=14 Photon angular distributions. MT=16,22,24,28,41,51-70,91,102-107
MF=15 Photon energy spectra. MT=16,22,24,28,91,102-107
MF=33 Covariance matrices. MT=1, 2, 4, 5, 16,22,24,28, 91, 102-107
Evaluated files content
FENDL-3, IAEA
neutrons
Tungsten blocks
5 cm 10
cm
15 c
m
35 c
m
FNG tungsten experiment
FENDL-3, IAEA
1 1010-6
10-5
10-4
10-3
TUD IAEA present result
Neu
tron
flux
[cm
-2M
eV-1
sn-1
]
Neutron energy [MeV]
Pos1 (5 cm)
1 1010-9
10-8
10-7
10-6
10-5
TUD IAEA present result
Neu
tron
flux
[cm
-2M
eV-1
sn-1
]
Neutron energy [MeV]
Pos4 (35 cm)
Results for neutron spectra
FENDL-3, IAEA
0 1 2 3 4 5 6 7 8 9 1010-9
10-8
10-7
10-6
10-5
TUD IAEA present result
Pho
ton
flux
[cm
-2M
eV-1
sn-1
]
Photon energy [MeV]
Pos4 (35 cm)
0 1 2 3 4 5 6 7 8 9 1010-8
10-7
10-6
10-5
10-4
10-3
TUD IAEA present result
Pho
ton
flux
[cm
-2M
eV-1
sn-1
]
Photon energy [MeV]
Pos1 (5 cm)
Results for photon spectra
FENDL-3, IAEA
5 10 15 20 25 30 35
0,8
0,9
1,0
1,1
1,2
Detector position [cm]
IAEA FZK
C
/ENeutron flux 1-2.5 MeV
5 10 15 20 25 30 35
0,8
0,9
1,0
1,1
1,2
IAEA FZK
C/E
Neutron energy [MeV]
Neutron flux >12.5 MeV
5 10 15 20 25 30 35
0,8
0,9
1,0
1,1
1,2
IAEA FZK
C/E
Detector position [cm]
Neutron flux 10.0-12.5 MeV
C/E flux integrals
5 10 15 20 25 30 35
0,8
0,9
1,0
1,1
1,2
IAEA FZK
C/E
Neutron energy [MeV]
Neutron flux >1 MeV
FENDL-3, IAEA
5 10 15 20 25 30 350,8
0,9
1,0
1,1
1,2
27Al(n,)
197Au(n,) 56Fe(n,p)
115In(n,n')
93Nb(n,2n)
58Ni(n,2n)
58Ni(n,p)
90Zr(n,2n)
Distance [cm]
C/E
IAEA
5 10 15 20 25 30 350,8
0,9
1,0
1,1
1,2
Distance [cm]
C/E
FZK
MCNP benchmark calculations (reaction rates)
FENDL-3, IAEA
Conclusions
Consistent approach for nuclear data evaluations was elaborated in FZK
This method includes nuclear data evaluation up to 150 MeV, covariance matrixes calculations for all nuclear reactions presented in the files, nuclear data processing and finally benchmark calculations with MCNP
The microscopic evaluated data show good agreement with available experimental data
Calculated uncertainties are continuous in full energy range from thermal point to 150 MeV
Results of the benchmark calculations show good agreement with measured values
The developed approach is going to be applied for angular distributions covariance matrixes calculation