D. Rochman and A.J. Koning · Fm 242-257 Md 245-260 No...Ds =) 36 flmediumfl or flbetterfl...
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1 / 19 TENDL-2009β: Chasing JEFF-3.2 D. Rochman and A.J. Koning Nuclear Research and Consultancy Group, NRG, Petten, The Netherlands June 4, 2009
Transcript of D. Rochman and A.J. Koning · Fm 242-257 Md 245-260 No...Ds =) 36 flmediumfl or flbetterfl...
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TENDL-2009β: Chasing JEFF-3.2
D. Rochman and A.J. Koning
Nuclear Research and Consultancy Group,
NRG, Petten, The Netherlands
June 4, 2009
Contents
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① Motivations:=⇒ a roadmap to consistent and state-of-the-art evaluations
② Concept:=⇒ Exp. Data + Resonances +TALYS + Monte Carlo =
TENDL-2009
③ Is TENDL-2009 available and when ?
④ Content 1:=⇒ Neutrons, protons, deuterons, tritons, alphas, photons
⑤ Content 2:=⇒ Neutrons: 19F to 281Ds (Z=110), from MF-1 to MF-34
⑥ Examples
⑦ Conclusions and Future Improvements
Concept: TALYS + Monte Carlo = TENDL-2009
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Experimentaldata (i.e. XS)
5000 randomENDF files
=⇒ TotalMonte Carlo
Compilations(EXFOR)
TALYS+MCPackage
AverageENDF file
TENDL-2009library
Adjustedparameters
Covariancefiles
Concept: Standard nuclear data scheme
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ResonanceParameters
Determ.Codes
ENDFGen. purp.
File NJOY MCNP
ExperimentalData
EXFOR TEFAL
Output
ENDF/EAFActiv.File
Proc.codes
FIS-PACT
NuclearModel
Parameters TALYSOtherCodes
-keff-Flux-Etc.
-Activation-Burn-up
Concept: Nuclear Data Scheme with covariances
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ResonanceParameters TARES
Determ.Codes
ENDFGen. purp.
File NJOY MCNP
ExperimentalData
EXFOR TEFAL
Output
ENDF/EAFActiv.File
Proc.codes
FIS-PACT
NuclearModel
Parameters TALYSOtherCodes
TASMAN
+ Covariances
+ Covariances
-keff-Flux-Etc.
+ Covariances
-Activation-Burn-up
+ Covariances
Monte Carlo: 1000 TALYS runs
Concept: Nuclear Data Scheme with Total Monte Carlo
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ResonanceParameters TARES
Determ.Codes
ENDFGen. purp.
File NJOY MCNP
ExperimentalData
EXFOR TEFAL
Output
ENDF/EAFActiv.File
Proc.codes
FIS-PACT
NuclearModel
Parameters TALYSOtherCodes
TASMAN TMC
+ Covariances
+ Covariances
-keff-Flux-Etc.
+ Covariances
-Activation-Burn-up
+ Covariances
Monte Carlo: 1000 runs of all codes
Is TENDL-2009 available ?
7 / 19
Not yet, but...
www.talys.eu/tendl-2009beta
Her
e
Here
Here
Here
HereH
ere
Is TENDL-2009 available ?
7 / 19
Not yet, but...
www.talys.eu/tendl-2009beta
Her
e
Here
Here
Here
HereH
ere
Content 1- TENDL-2009
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� Neutrons: ENDF files, plots, ACE files
� Protons: ENDF files, ACE files
� Alphas: ENDF files, ACE files
� ...Ne
utron
Proto
n
Deute
ron
Trito
n
Alph
a
Heliu
m3
Photo
n
TENDL-2009 >1000 >1000 >1000 >1000 >1000 >1000 >1000TENDL-2008 348 344 336 339 342 338 327(JEFF-3.1) 381 26(ENDF/B-VII.0) 393 48 5 3 163
Content 2- TENDL-2009 Neutron library: 19F to 281Ds (t1/2 > 1 µsec)
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Default Calculations Medium Quality Better Quality
Nucl
ear
Charg
eZ
Mass A
0
8
16
24
32
40
48
56
64
72
80
88
96
104
112
120
0 13 26 39 52 65 78 91 104 117 130 143 156 169 182 195 208 221 234 247 260 273 286 299 312
TENDL-2009
JEFF-3.1 (shifted + 50 A)
Fe 46-66
Pb 180-241
Pu 229-247
Content 3- TENDL-2009 Transport, Activation and EAF files
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TENDL-2009
ENDF File (200 MeV)MF1-15, 32,33,34
Activation File (200 MeV)MF3,6, 33
EAF File (60 MeV)MF3, 33
Content 3- TENDL-2009 Transport, Activation and EAF files
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TENDL-2009
ENDF File (200 MeV)MF1-15, 32,33,34
Activation File (200 MeV)MF3,6, 33
EAF File (60 MeV)MF3, 33
E < 20 MeV all MTsE > 20 MeV MT5
E < 200 MeV all MTs
Content 4- TENDL-2009 Neutron library: from MF-1 to MF-34
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Content of a typical file up to 200 MeV (out of > 1000 files):
☞ MF-1: Description
☞ MF-2: Resonance parameters (Reich-Moore or Multi-level Breit Wigner)
☞ MF-3: Cross sections (n,tot), (n,el), (n,non), (n,inli), ..., (n,γ), (n,pi), (n,αi)
☞ MF-4: Elastic angular distribution (Legendre Polynomials)
☞ MF-6: Double differential distributions and spectra for (n,2n), ..., (n,αi)
☞ MF- 8-10: Isomeric cross sections
☞ MF-32: Resonance parameter covariances
☞ MF-33: Cross section covariances (with cross correlation)
☞ MF-34: Elastic angular distribution covariances (up to the 6th Legendrepolynomial coefficient)
Content 5- TENDL-2009: Actinides
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Element Isotopes Element IsotopesTh 208-227, 228-232, 233-239 Pa 213-230, 231,233, 234-239U 222-232, 233-238, 239-242 Np 225-236, 237, 238-244Pu 229-237, 238-244, 245-247 Am 232-238, 239-243, 245-247Cm 238-242, 243-248, 249-252 Bk 238-248, 249, 250, 251Cf 237-248, 249, 250-256 Es 241-253, 254, 255-257Fm 242-257 Md 245-260No...Ds
=⇒ 36 ”medium” or ”better” quality evaluations and 406 ”default” qualityevaluations (with isomers)
Examples 1: U-235
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TalysENDF/B-VII.0
40 Talys RandomExp235U(n,2n)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
2015105
2.0
1.5
1.0
0.5
0.0
This workENDF/B-VII.0
40 Talys RandomExp
235U(n,γ)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
10110010−110−2
100
10−1
10−2
10−3
10−4
TalysENDF/B-VII.0
40 Talys RandomExp
235U(n,inl)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
20151050
3.5
3.0
2.5
2.0
1.5
1.0
0.5
TalysJEFF-3.1
ENDF/B-VII.0Exp
235U(n,f)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
20151050
2.5
2.0
1.5
1.0
0.5
Examples 1: U-238
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TALYSENDF/B-VII.0
JEFF-3.1Exp238U(n,2n)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
2015105
2.0
1.5
1.0
0.5
0.0
TALYSENDF/B-VII.0
JEFF-3.1Exp
238U(n,γ)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
10110010−110−2
101
100
10−1
10−2
10−3
10−4
TALYSENDF/B-VII.0
JEFF-3.1
238U(n,inl)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
20151050
4
3
2
1
0
TALYSJEFF-3.1
ENDF/B-VII.0Exp 238U(n,f)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
20151050
1.5
1.0
0.5
Examples 2: Pu-241
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TalysENDF/B-VII.0
JEFF-3.1241Pu(n,2n)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
2015105
1.0
0.8
0.6
0.4
0.2
0.0
TalysENDF/B-VII.0
JEFF-3.1
241Pu(n,γ)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
10110010−110−2
101
100
10−1
10−2
10−3
10−4
TalysENDF/B-VII.0
JEFF-3.1
241Pu(n,inl)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
20151050
2.5
2.0
1.5
1.0
0.5
0.0
TalysJEFF-3.1
ENDF/B-VII.0Exp
241Pu(n,f)
Incident Energy (MeV)
Cro
ssse
ctio
n(b
)
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3.0
2.5
2.0
1.5
1.0
0.5
0.0
Examples 3: Ga-69 and Ga-84
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∆σ/σ vs. E for 69Ga(n,γ)
10-3 10-1 101 103 105 1070
10
20
30
40
50
60
∆σ/σ
vs.
E fo
r 69
Ga(
n,γ)
10-3
10-1
101
103
105
107
0102030405060Li
near
Axe
s:
Rel
. Sta
ndar
d D
ev. (
%)
Loga
rithm
ic A
xes:
Ene
rgy
(eV
)
Cor
rela
tion
Mat
rix
0.0
0.2
0.4
0.6
0.8
1.0
0.0
-0.2
-0.4
-0.6
-0.8
-1.0
∆σ/σ vs. E for 84Ga(n,γ)
10-3 10-1 101 103 105 1070
10
20
30
40
50
60
∆σ/σ
vs.
E fo
r 84
Ga(
n,γ)
10-3
10-1
101
103
105
107
0102030405060Li
near
Axe
s:
Rel
. Sta
ndar
d D
ev. (
%)
Loga
rithm
ic A
xes:
Ene
rgy
(eV
)
Cor
rela
tion
Mat
rix
0.0
0.2
0.4
0.6
0.8
1.0
0.0
-0.2
-0.4
-0.6
-0.8
-1.0
Examples 4: 61−85Ga(n,inl)
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TENDL-2009
6162-63
66
64
65
68
67
7169
61−85Ga(n,inl)
Incident Neutron Energy (MeV)
Cro
ssSec
tion
(Bar
ns)
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2.5
2.0
1.5
1.0
0.5
0.0
Examples 5: 60−85Ga(n,γ)
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TENDL-2009
6463
65-66
61
7268
60
60−85Ga(n,γ)
Incident Neutron Energy (MeV)
Cro
ssSec
tion
(Bar
ns)
10110010−110−210−3
100
10−1
10−2
10−3
10−4
Conclusions and Future improvements
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☞ - Consistent data files
☞ - Automatic updates
☞ - Extensive set of covariance files
☞ - Reproducible with TALYS-1.2 (released with the library and referencepapers)
☞ - Best TALYS and resonance parameters fitting
Release date: End of 2009 !
☛ - More adjustment to experimental data
☛ - More extensive validation
☛ - Addition of original URR
Conclusions and Future improvements
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☞ - Consistent data files
☞ - Automatic updates
☞ - Extensive set of covariance files
☞ - Reproducible with TALYS-1.2 (released with the library and referencepapers)
☞ - Best TALYS and resonance parameters fitting
Release date: End of 2009 !
☛ - More adjustment to experimental data
☛ - More extensive validation
☛ - Addition of original URR
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