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IAEA CRP on “Nuclear Data Libraries for Advanced Systems: Fusion Devices (FENDL-3)”- Contributions by FZK. U. Fischer , A. Konobeyev, P. Pereslavtsev, S. P. Simakov Association FZK-Euratom Karlsruhe Institute of Technology Forschungszentrum Karlsruhe. - PowerPoint PPT Presentation
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| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
IAEA CRP on “Nuclear Data Libraries for Advanced Systems: Fusion Devices (FENDL-3)”- Contributions by FZKU. Fischer, A. Konobeyev, P. Pereslavtsev, S. P. Simakov
Association FZK-EuratomKarlsruhe Institute of Technology Forschungszentrum Karlsruhe
1st Research Coordination Meeting on “Nuclear Data Libraries for Advanced Systems – Fusion Devices (FENDL)”, IAEA, Vienna, December 2-5, 2008
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Overview
• Recent FZK activities related to fusion and high energy nuclear data
• Proposed CRP contributions by FZK
Data evaluationsData files Validation analyses
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Nuclear Data Evaluations for Fusion Technology and High Energy Applications
• Objectives:To provide cross-section data evaluations required for fusion neutronics calculations (transport and transmutation/activation)
• Evaluation of neutron induced cross-sections for EFF/JEFF (Joint Evaluated Fusion Fission File) up to 150 MeV neutron energy– Production of complete data files (ENDF6 data format) for processing
with NJOY (use with MC & SN codes)
– Suitable for fusion and other applications
– Complete data files for 182,183,184,186W, 181Ta, 55Mn, 52Cr evaluation
– Largely with co-variance data
– Contributions to FENDL-3 project co-ordinated by IAEA/NDS• Evaluation of d + 6,7Li data up to 50 MeV for IFMIF D-Li source term
simulation using McDeLicious MC code
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
ENDF/B, JEFF-3.1, EAF2007
Experiment
Evaluated file
RIPL-2RIPL-2
ECISECIS
Transmission coefficients
el, non, tot
Nuclear model parameters Mass table
Nuclear level structure
INPUT files
Collective excitations
Flowchart of the evaluation procedure
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
0 20 40 60 80 100 120 1400
100
200
300
400
500
600
700
800
900
1000
1100
1200
Haight, 07 ENDF/B-VII EAF-2007 present result
Cr(n,xp)
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
0 20 40 60 80 100 120 1400
50
100
150
200
250
Haight, 07 ENDF/B-VII EAF-2007 present result
Cr(n,x)
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
Evaluation of n + 52Cr cross-section data up to 150 MeV for the Joint European Fusion Fission File (JEFF)
10-2 10-1 100 101 102
102
103
104
105
Carlton, 2000 Agrawal, 84 Foster, 71 Abfalterer, 01 ENDF/B-VII present result
Total cross section
Cro
ss s
ectio
n [m
barn
]
Neutron energy [MeV]
0 2 4 6 8 10 12 14
101
102
103
Takahashi, 88 Yabuta, 88 Matsuyama, 92 JEFF-3.1 present result
14 MeV 52Cr(n,xn)
ds/
dE
[m
b/M
eV
]
Neutron emission energy [MeV]
0 20 40 60 80 100 120 140 160 180100
101
102
103
Olsson, 87 ENDF/B-VII present work
n + 52Cr Elastic scatteringE
n= 21.6 MeV
d/d
[mb
/sr]
c.m.
[deg]
0 2 4 6 8 10 12 14 16 18 20 22 2410-4
10-3
10-2
10-1
100
101
102
103
Oblozinsky, 92 JEFF-3.1=ENDF/B-VII present result
14.6 MeV 52Cr(n,xg)
ds/
dE
d [
mb
/Me
V s
r]
Neutron emission energy [MeV]
=100o
Photon emission energy [MeV]
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Evaluation of n + 181Ta cross-section data up to 150 MeV for the Joint European Fusion Fission File (JEFF)
0 2 4 6 8 10 12 14100
101
102
103
104
Vonach, 80 Takahashi, 89 Takahashi, 92 Hermsdorf, 82 ENDF/B-VI JENDL-3.3 GNASH
14 MeV 181Ta(n,xn)
ds/d
E [
mb/
MeV
]
Neutron emission energy [MeV]
0 2 4 6 8 10 12 14 16 18 20100
101
102
103
104
Marcinkowski, 93 REX ENDF/B-VI JENDL-3.3 GNASH
20 MeV 181Ta(n,xn)
ds/d
E [
mb/
MeV
]
Neutron emission energy [MeV]
6 8 10 12 14 16 18 20 22 24 26 28 300
500
1000
1500
2000
2500
Veeser, 77 Frehaut, 80 Takahashi, 89 ENDF/B-VI JENDL-3.3 JEFF-3.0 GNASH
181Ta(n,2n)180Ta
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
8 10 12 14 16 18 20 22 24 26 28 300
2
4
6
8
10
12
14
16
18
20
22
Woelfle, 88 Xiangzhong, 92 Kasugai, 92 Han-Lin, 89 Begun, 02 Filatenkov, 01 ENDF/B-VI JENDL-3.3 JEFF-3.0 GNASH evaluation
181Ta(n,p)181Hf
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]0 20 40 60 80 100 120 140 160 180
100
101
102
103
104
Hansen, 85 Benenson, 73 Cross, 60 Hudson, 62 ENDF/B-VI JENDL-3.3 evaluation
n + 181Ta Elastic scatteringE
n= 15 MeV
d/d
[mb
/sr]
c.m.
[deg]
10-1 100 101 102
2
4
6
8
10 Total cross section
Finlay, 93 Poenitz, 81 Tsubone, 84 Byoun, 73 Poenitz, 83 Foster, 71 ENDF/B-VI JENDL-3.3 Koning Young
Cro
ss s
ectio
n [b
arn]
Neutron energy [MeV]
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Evaluation of n + 55Mn cross-section data up to 150 MeV for the Joint European Fusion Fission File (JEFF)
0 20 40 60 80 100 120 140 160 180100
101
102
103
Schweitzer, 78 Becker, 66 Holmqvist, 70 JENDL-HE ECIS evaluation
n + 55Mn Elastic scatteringE
n= 3.4 MeV
d/
d
[mb
/sr]
c.m.
[deg]
10-3 10-2 10-1 100 101 102
100
101
102
Abfalterer, 01 Pineo, 70 Foster, 71 Cierjacks, 69 Garg, 78 JENDL-HE ECIS evaluation
Total cross section
Cro
ss s
ectio
n [b
arn]
Neutron energy [MeV]
0 2 4 6 8 10 12 14100
101
102
103
104
Takahashi, 89 Baba, 88 Hermsdorf, 82 JENDL-HE evaluation
14 MeV 55Mn(n,xn)
ds/d
E [
mb/
MeV
]
Neutron emission energy [MeV]
0 2 4 6 8 10 12 1410-1
100
101
102
Salnikov, 72 Takahashi, 89 Baba, 88 evaluation
En=14 MeV
d/d
Ed
[m
b/sr
MeV
]
Emitted neutron CM energy [MeV]
10 15 20 25 30 35 400
500
1000
1500
Paulsen, 65 Menlove, 67 Ikeda, 88 Filatenkov, 99 Lu, 89 Greenwood, 87 Borman, 69 Auchampaugh, 77 Soewarsono, 92 Iwamino, 92 EAF-2005 JENDL-HE evaluation
55Mn(n,2n)54Mn
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
0 10 20 30 40100
101
102
Qaim, 94 Prasad, 71 Minetti, 67 Allan, 61 Weigold, 60 Mitra, 66 EAF-2005 (EFF-2.4) JENDL-HE evaluation
55Mn(n,p)55Cr
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Typical content of ENDF data files
MF=1 General description. MT=451
MF=2 Resonance parameters. MT=151
MF=3 MT=1, 2, 4, 5, 16, 22, 28, 51-60, 91, 102,103, 104, 105, 106, 107
MF=4 Angular distributions. MT=2, 51-60 (Legendre polynomials)
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=16,22,28,51-60,91,102-107
MF=14 Photon angular distributions. MT=16,22,28,51-60,91,102-107
MF=15 Photon energy spectra. MT=16,22,28,91,102-107
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Benchmark analyses
• Objectives:To check and validate the new data evaluations for a reliable use in application calculations (ITER TBM, Demo, IFMIF) and provide feed-back to the evaluators.
- Computational analyses of integral benchmark experiments (14 MeV neutrons) by means of Monte Carlo calculations with the MCNP code
- Comparisons for neutron and photon spectra and other measured responses (e. g. reaction rates)
- Cross-checks with calculations using data evaluations from different sources (JEFF-3.0/3.1, FENDL-2.0/2.1, JENDL-3.3, ENDF/B-VI/VII
- Checks of neutron emission cross-section data
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Benchmark analyses on Ta
• Integral benchmark experiments
– Lawrence Livermore National Laboratory (LLNL) pulsed sphere experiments with central 14 MeV neutron source: Time-of-flight spectra for spherical Ta shells (wall thicknesses of 3.4 and 10.2 cm).
– Lewis Research Centre (LRC) experiment on 9 cm thick Ta shell with central Am-Be neutron source: Neutron leakage spectrum measurement by proton recoil scintillation detector.
• Differential experimental data
– Few measurements of secondary neutron energy/angular distributions for incident energies 5 to 20 MeV by IPPE (Obninsk), IRK (Vienna), OSA (Osaka), TOH (Tohoku), TUD (Dresden)
• Available data evaluations
– ENDF/B-V (VI, VII), JENDL-3.3 (FENDL-2.1, JEFF-3.1), FZK 2006 (JEFF-3.2)
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Livermore (1986):
Shell #1: outer R = 3.4 cm (1 mfp) Shell #2: outer R = 10.2 cm (3 mfp)14 MeV-neutron source: TiT +d, Ed = 400 keVMethod: Time-of-Flight, L = 10 m n-detector: Θ = 26o, Ethresh > 1 MeV
L = 10 m
Θ = 26o
d-beam
n-detector
Ta-Shell
TiT-Target:14 MeV-Source
R
Shell: outer R = 12.1 cm inner r = 3.1 cm (wall 9 cm, 4 mfp)241Am-Be neutron source, <E> = 4 MeVMethod: Proton-recoil scintil. at L = 2 m n-detector: Θ = 26o, Ethresh > 1 MeV
Lewis Research Center (1974):
Ta shell
Am-Be source
n-detector
L = 2 m
Ta benchmark experiments
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
0 2 4 6 8 10 12 14 160.0
0.5
1.0
1.5
FZK'06
JEFF-3.2T
JENDL-3.3
C/E
Neutron Energy, MeV
ENDF/B-VI
10-4
10-3
10-2
10-1
FZK'06
JENDL-3.3
LLNL' Experiment
ENDF/B-VI
Ta shell: R = 3.4 cm (1mfp)
Lea
kage
Spe
ctru
m, 1
/sr/
MeV
0 2 4 6 8 10 12 14 160.0
0.5
1.0
1.5
JEFF-3.2T
FZK'06
JENDL-3.3
C/E
Neutron Energy, MeV
ENDF/B-VI
10-4
10-3
10-2
10-1
JEFF-3.2TFZK'06
JENDL-3.3
LLNL' Experiment
ENDF/B-VI
Ta shell: R = 10.2 cm (3mfp)
L
eaka
ge S
pect
rum
, 1/s
r/M
eV
Benchmarking of Ta data
LLNL Ta spheres experiments (14 MeV neutron source)
0 2 4 6 8 100.7
0.8
0.9
1.0
1.1
JEFF-3.2T
FZK'06
JENDL-3.3
C/E
Neutron Energy, MeV
ENDF/B-VI
100
101
102
Ta ShellFZK'06
JENDL-3.3
241Am-Be Source
ENDF/B-VI
Ta shell: R = 12.07cm (3.4mfp)
Neu
tron
spe
ctra
, 1/c
m2 /s/M
eV
LRC Ta shell experiment with Am-Be source (4 MeV mean neutron energy)
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 153x100
101
102
103
4x103
JEFF-3.2T
FZK'06
Experiment:
JENDL-3.3
(n,n')
- IRK - Osaka - Tohoku
181Ta(n,xn), E = 14.1 MeV
d(E
)/dE
, mb/
MeV
Secondary Neutron Energy, MeV
(n,2n)
ENDF-B6
Benchmarking of Ta data
Ta(n,xn) single and double differential neutron emission distributions
0 1 2 3 4 5 6 7 8101
102
103
JEFF-3.2T
FZK'06
Experiment:IPPE'82(n
,2n)
ENDF/B-VI
JENDL-3.3
181Ta(n,n'), E = 7.94 MeV
d(E
)/dE
, mb/
MeV
Secondary Neutron Energy, MeV
(n,n')
10
20
30
40
50
60
0 30 60 90 120 150 1800
5
10
15ENDF/B-VI
JEFF-3.2T
Eout
= 4.0 - 6.0 MeV
Angle, degrees
ENDF/B-VI
Experiment: IPPE'82
JEFF-3.2T
Eout
= 2.0 - 4.0 MeV
181Ta(n,xn), Ein = 7.94 MeV
d/d,
mb/
sr
80
90
100
110
120
130
JEFF-3.2T
ENDF/B-VI Eout
= 0.6 - 2.0 MeV
Ein=14.1 MeV
Ein=7.94 MeV
Ein=7.94 MeV
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0101
102
103
JEFF-3.2T
39 excited levels in 181Ta below 1.50 MeV =>
FZK'06
Experiment IPPE'82
ENDF-B6JENDL-3.3
181Ta(n,n'), E = 5.19 MeV
d(E
)/dE
, mb/
MeV
Secondary Neutron Energy, MeV
0
10
20
30
40
0 30 60 90 120 150 1800
5
10
15 ENDF/B-VI
JEFF-3.2T
Eout
= 3.0 - 4.0 MeV
Angle, degrees
ENDF/B-VI
Experiment: IPPE'82
JEFF-3.2T
Eout
= 2.0 - 3.0 MeV
181Ta(n,n'), Ein = 5.19 MeV
d/d,
mb/
sr
80
100
120
140
160
180
ENDF/B-VI
JEFF-3.2T
Eout
= 0.6 - 2.0 MeV
Ta(n,xn) single and double differential neutron emission distributions
Benchmarking of Ta data
Ein=5.19 MeV
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Benchmark analyses on Mn
• Integral neutron transport benchmark experiment: OKTAVIAN pulsed Mn sphere (dia. 61 cm) with central 14 MeV neutron
source: – n-leakage spectrum measured by Time-of-flight technique– g-leakage spectrum measured by pulse height technique (NaI detector)
• Differential experimental data– Two measurements of secondary neutron energy/angular distributions
at incident energy 14 MeV by TOH (Tohoku) and OKTAVIAN
• Available data evaluations– ENDF/B-VII and VII, JENDL-3.3 (adopted in FENDL-2.1 and JEFF-3.1)
and FZK 2006 (JEFF-3.2)
• Integral neutron activation benchmark experiment: JAERI/USDOE experiment with Mn-Cu alloy foil in quasi-mono energetic 14
MeV neutron source: – 3 radioactive isotopes were detected - Mn-54, Mn-56, V-52
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
- Mn spherical shell, R = 30.5 cm (3.4 mfp for 14 MeV neutrons) - 14 MeV-neutron source: TiT +d, Ed = 240 keV- n-spectrometry: Time-of-Flight, NE218-detector at 11 m/55o, E = 0.076 -14 MeV- -spectrometry: Pulse-height/unfolding, NaI-detector at 5.8 m/55o, E = 0.5-11 MeV
L = 11 m
Θ = 55o
d-beam
γ-detectorNaI( pulse height)
Mn shell
TiT-Target:14 MeV-Source
R
n-detectorNE-218(TOF)
L = 5.8 m
Benchmarking of Mn dataOKTAVIAN benchmark experiment
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
10-3
10-2
10-1
100
101
0.1 1 100.4
0.6
0.8
1.0
1.2
1.4 ENDF/B-VI JENDL-3.3
FZK
C/E
Neutron Energy, MeV
FZK
JENDL-3.3
ENDF/B-VI
Experiment
n-L
eaka
ge
, 1/M
eV Mn shell
Benchmarking of Mn data
OKTAVIAN benchmark experiment: neutron leakage
spectrum
0 2 4 6 8 10 12 14101
102
103
2x103
FZK'07
Experiment:Tohoku'88OKTAVIAN'89
JENDL-3.3
(n,n')
55Mn(n,xn), E = 14.1 MeV
d(E
)/d
E, m
b/M
eV
Secondary Neutron Energy, MeV
(n,2n)
ENDF/B-VI.8
Mn(n,xn) neutron emission spectra
at 14 MeV incident neutron energy
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
10-5
10-4
10-3
10-2
10-1
100
0.5 1 100.0
0.2
0.4
0.6
0.8
1.0
1.2
ENDF/B-VI
JENDL-3.3
FZK
C/E
-ray Energy, MeV
Contributionfrom Source gammas
FZK
JENDL-3.3
ENDF/B-VIExperiment
-Le
aka
ge
, 1
/Me
V
60cm dia. Mn shell
Benchmarking of Mn data
0 2 4 6 8 10 12 14 16 18 20 22 2410-2
10-1
100
101
102
103
104
(n,2n), Q=-(10.23+0.06)MeV
NJS'77 (E = 14.1MeV)
FZK'07
ORNL'76 (E = 15.5MeV)
JENDL-3.3
(n,), Q=+7.27MeV
55Mn(n,x), E = 14-16 MeV
d(E
)/d
E, m
b/M
eV
Photon Energy, MeV
(n,n'), Q = (-0.0 +0.125) MeV
ENDF/B-VI.8
Mn(n,x) neutron emission spectra
at 14 MeV incident neutron energy
OKTAVIAN benchmark experiment: photon leakage
spectrum
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
ITER Streaming Experiment at FNG
Measurements of neutron/photon flux spectra by TUD (K. Seidel et al.)
• Mock-up of ITER inboard blanket/shield system with streaming channel in the blanket and cavity at the bottom of channel.
• Neutron and photon flux spectra measured at positions A (41.4 cm) and B (87.6 cm) with source on and off axis (A0, B0).
• Additional measurements with detectors shifted off the axis by 7.5 cm, 15.0 and 9.0 cm (A1, A2 and B1).
• Neutron spectra measured in the energy range between about 20 keV and 15 MeV. – A set of gas-filled proportional counters and a
stilbene scintillation spectrometer used in the energy range up to 3 MeV.
– NE-213 scintillation spectrometer for energy range 1 to 15 MeV.
• Photon flux spectra measured with NE-213 spectrometer above 0.2 MeV.
Position A41.4 cm
Position B87.6 cm
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
ITER Streaming Experiment
Neutron flux spectra at position B0
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
ITER Streaming ExperimentPhoton flux spectra at position
B0
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
ITER Streaming Experiment
Photon flux spectra at position B1
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
ITER Streaming ExperimentC/E comparison for neutron flux
integrals Position A0 Statistical error (fsd) in A0-position: Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1
0.1 - 1.0 1.37 1.39 1.42 0.59% 0.57% 0.63% 1.0 - 5.0 1.37 1.38 1.34 0.81% 0.80% 0.90%
5.0 - 10.0 1.73 1.79 1.80 1.22% 1.20% 1.26% E > 10.0 0.78 0.78 0.78 0.70% 0.69% 0.75%
Position A1 Statistical error (fsd) in A1-position: Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1
0.1 - 1.0 Inf Inf Inf 0.17% 0.17% 0.19% 1.0 - 5.0 0.89 0.89 0.90 0.21% 0.21% 0.23%
5.0 - 10.0 0.96 0.97 1.00 0.42% 0.42% 0.47% E > 10.0 0.90 0.89 0.91 0.40% 0.41% 0.45%
Position A2 Statistical error (fsd) in A2-position: Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1
0.1 - 1.0 Inf Inf Inf 0.16% 0.15% 0.17% 1.0 - 5.0 0.88 0.89 0.90 0.22% 0.21% 0.22%
5.0 - 10.0 0.92 0.93 0.96 0.49% 0.47% 0.51% E > 10.0 0.90 0.89 0.90 0.49% 0.47% 0.50%
Position B0 Statistical error (fsd) in B0-position: Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1
0.1 - 1.0 0.77 0.79 0.80 0.56% 0.61% 0.59% 1.0 - 5.0 0.88 0.90 0.90 0.65% 0.71% 0.69%
5.0 - 10.0 1.03 1.06 1.10 0.76% 0.83% 0.81% E > 10.0 0.70 0.70 0.70 1.01% 1.11% 1.08%
Position B1 Statistical error (fsd) in B1-position: Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1
0.1 - 1.0 Inf Inf Inf 0.51% 0.56% 0.51% 1.0 - 5.0 0.71 0.72 0.73 0.58% 0.63% 0.58%
5.0 - 10.0 0.84 0.86 0.90 0.73% 0.79% 0.72% E > 10.0 0.69 0.68 0.70 0.73% 0.80% 0.74%
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
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ITER Streaming Experiment
Position A0 Statistical error (fsd) in A0-position: Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1
0.4 - 1.0 0.82 0.80 0.80 0.73% 0.68% 0.76% E > 1.0 0.82 0.84 0.83 0.62% 0.59% 0.64%
Position A1 Statistical error (fsd) in A1-position:
Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1 0.4 - 1.0 0.99 1.00 1.01 0.31% 0.32% 0.36% E > 1.0 0.99 1.01 1.00 0.24% 0.23% 0.25%
Position A2 Statistical error (fsd) in A2-position:
Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1 0.4 - 1.0 0.93 0.94 0.93 0.33% 0.32% 0.34% E > 1.0 0.93 0.96 0.95 0.25% 0.24% 0.27%
Position B0 Statistical error (fsd) in B0-position:
Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1 0.4 - 1.0 0.83 0.82 0.82 0.68% 0.67% 0.65% E > 1.0 0.84 0.87 0.90 0.50% 0.49% 3.03%
Position B1 Statistical error (fsd) in B1-position:
Energy, MeV FENDL-2.0 FENDL-2.1 JEFF-3.1 FENDL-2.0 FENDL-2.1 JEFF-3.1 0.4 - 1.0 0.77 0.77 0.78 0.69% 0.83% 1.19% E > 1.0 0.78 0.80 0.80 0.52% 0.50% 0.54%
C/E comparison for photon flux integrals
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Neutron Leakage Spectra from Pb-shells at 14 MeV incident neutron energy
IPPE & IRD shell (t = 7.5 cm) TUD shell (t = 22.5 cm)
10-2
10-1
100
0.03 0.1 1 10 200.7
0.8
0.9
1.0
1.1
JEFF-3.1T
C/E
Neutron Energy, MeV
ENDF-B6
Pb shell (R = 25.0, r = 2.5 cm)
- TUD Exp. - ENDF-B6 - JEFF-3.1T
Lea
kage
Spe
ctru
m, 1
/Let
harg
y
0.5
1.0
1.5
2.0
10-2
10-1
100
0.4 1 10 200.80.91.01.11.2
C/E
(IR
D)
JEFF-3.1T
C/E
(IP
PE
)
Neutron Energy, MeV
ENDF-B6
ENDF-B6JEFF-3.1T
Pb shell (R = 12.0, r = 4.5 cm)
- IPPE Exp.(ToF) - IRD Exp.(p-Recoil) - ENDF-B6 - JEFF-3.1T
Lea
kage
Spe
ctru
m, 1
/MeV
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Secondary neutron Energy Distributions (SED) from Pb(n,xn) reaction at 14 MeV incident neutron energy
Findings: satisfactory agreement for energy differential cross section
for natPb(n,xn) and 208Pb(n,xn) or 208Pb(n,n’) reactions at 14MeV
Neutron emission for natural LeadNeutron emission and inelastic for Lead-208
0 1 2 3 4 5 6 7 8 9 10 11 12 132x100
101
102
103
3x103
3-2+3-
1/2-
(n,2
n)
5/2-
3/2-
3/2+
7/2-
5/2-
208Pb(n,2n)
208Pb(n,n')
JEFF-3.1T
207Pb levels208Pb levels
208Pb(n,xn) & 208Pb(n,n'), E = 14.1 MeV
d(E
)/dE
, mb/
MeV
Neutron Energy, MeV
ENDF-B6
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14101
102
103
3x103
OKTAVIANJEFF-3.1T
natPb(n,xn), E = 14 MeV
d/d
E, m
b/M
eV
Neutron Energy, MeV
ENDF-B6IPPE (208Pb)
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Gamma leakage spectra from Pb spherical shell & γ-spectra from Pb(n,xγ) reaction at 14 MeV incident neutron energy
γ - Leakage Spectrum from Pb-Shell
γ - Spectrum from Pb(n,xγ) reaction
0 2 4 6 8 10 12 14 16 18 20 22 2410-4
10-3
10-2
10-1
100
101
102
103
104
natPb(n,n'n) natPb(n,)
JEFF-3.1T
ENDF-B6
natPb(n,x), E = 14 MeV
d/d
E,
mb/
MeV
Gamma Energy, MeV
Exp: Lubljana'79
0 2 4 6 8 10 120.00.20.40.60.81.01.21.4
C/E
Gamma Energy, MeV
10-5
10-4
10-3
10-2
10-1
JEFF-3.1T
ENDF-B6
Pb shell (R = 20, r = 10cm)
-ray
Lea
kage
Spe
ctru
m, 1
/MeV
OKTAVIAN'89
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Evaluation and validation of high energy cross-section data for the FENDL-3 nuclear data library
• Proposed research activities by FZK
– Full evaluations of neutron and proton induced high energy cross-section data (up to 150 MeV) including co-variance information
– Preparation of data files in ENDF-6 format– Validation analyses based on Monte Carlo calculations
of available integral experiments– Preparation of special radiation damage cross-sections
for structural materials.
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Proposed research activities by FZK
• Validation analyses– Monte Carlo calculations with the MCNP code will be
performed for the FENDL-3 data evaluations using suitable integral benchmark experiments.
– Measured and calculated responses will be compared and possible discrepancies will be analysed to identify deficient cross-section data.
– This information will be used to improve the FENDL-3 data evaluations.
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Proposed research activities by FZK
• Neutron cross-section data– Consistent evaluation of high energy neutron cross-sections (up to
150 MeV) for selected nuclides such as Cr-50, -52, -53, -54, Mn-55, Ta-181, W-182, -183, -184, -186 and others including co-variance data information.
– General purpose 150 MeV data files will be prepared in standard ENDF-6 data and made available for FENDL-3.
• Proton activation cross-section data– Current version of the Proton Activation Data File PADF-2007
(comprising 418,575 excitation functions for 2355 target nuclei from Mg to Ra for proton energies from 0 up to 150 MeV) will be extended to include more nuclides, it will be updated to take into account new experiments, and will be complemented by co-variance data
| U. Fischer et al | FZK Contributions to FENDL-3 CRP
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Proposed research activities by FZK
• Radiation damage data: – Neutron and proton induced displacement cross-
section data will be evaluated for structural materials such as Cr, Fe, Ni and others using experimental information about defect generations in irradiated materials, results of molecular dynamics simulations, and results of binary collision approximation model calculations.
– These data will be prepared in a special data file for FENDL-3.