Forschungszentrum Karlsruhe in der Helmholz-Gemeinschaft Karlsruhe Institute of Technology Nuclear...

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


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


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



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]


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]



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


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]



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


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]



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= 26 MeV

d/d

[mb/

sr]

c.m.

[deg]

0 20 40 60 80 100 120 140 160 180100

101

102

103

104


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= 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= 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]


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


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

(%

)


10-11 10-9 10-7 10-5 10-3 10-1 1010

20

40

60(n,)


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

)


-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

)


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


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)


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


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

]


Pos1 (5 cm)

1 1010-9

10-8

10-7

10-6

10-5


Neu

tron

flux

[cm

-2M

eV-1

sn-1

]


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


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


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 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 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

Forschungszentrum Karlsruhe in der Helmholz-Gemeinschaft Karlsruhe Institute of Technology Nuclear...

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