evaluation of n+cr cross section data up to 200 mev neutron energy including covariances
DESCRIPTION
Evaluation of n+Cr cross section data up to 200 MeV neutron energy including covariances. P.Pereslavtsev, A. Konobeyev, L. Leal, U. Fischer. Objectives. Improvements of the nuclear model simulations based on the TALYS code. - PowerPoint PPT PresentationTRANSCRIPT
KIT – The cooperation of Forschungszentrum Karlsruhe GmbH and Universität Karlsruhe (TH)
Institute for Neutron Physics and Reactor Technology
Evaluation of n+Cr cross section data up to 200 MeV neutron energy including covariances
P.Pereslavtsev, A. Konobeyev, L. Leal, U. Fischer
23-26 March 2010, IAEA, Vienna2
Objectives
Improvements of the nuclear model simulations based on the TALYS code.
Calculations of the covariances up to 200 MeV using Unified Monte Carlo approach.
Inclusion in the files the new data for resonance region.
Preparation of the neutron transport data files for Cr-50,53,54 isotopes for incident energies up to 200 MeV.
Benchmarking of the newly developed neutron data files.
Compilation of the integral experimental data on Cr.MCNP benchmark transport calculations.Correction of the evaluated data if necessary.
23-26 March 2010, IAEA, Vienna3
Nucelar model calculations
TALYS-1.0 code was used for the nuclear modles calculations up to 200 MeV incident neutron energies
GDH model for the preequlibrium reactions was included in the code
The detailes are reported by A. Konobeyev (EFFDOC-1102)GDH model is included in TALYS as an option (preeqmode 5)TALYS executable and source files are available
Global OMPs for deuterons, tritons, helions and alphas are used instead of folding approach
Generalised superfluid model for level densities
The set of the best model parameters was found on the basis of the optimization procedure (Monte Carlo simulations)
23-26 March 2010, IAEA, Vienna4
Quality assurance of the evaluated data
TALYS code for the nuclear model calculations
Well proved nuclear models
Inclusion of the new resonance data
Detailed comparison with available experimental data
Cross sections for individual channelsDifferential cross sections (angular, energy, energy-angular distributions)
Cross check of the evaluated data within the covariances calculations
Particle transport calculations for comparison with integral experimental data and feedback for the evaluated data
23-26 March 2010, IAEA, Vienna5
Total and elastic scattering cross sections
10-2 10-1 100 101 102
102
103
104
n+50Cr
JEFF-3.1 Korzh, 77 present result
Elastic scattering cross section
Cro
ss s
ectio
n [m
barn
]
Neutron energy [MeV]10-2 10-1 100 101 102
102
103
104
105
Spencer, 72 Dyumin, 72 Farrell, 66 present result JEFF-3.1
Total cross section
Cro
ss s
ectio
n [m
barn
]
Neutron energy [MeV]
n+50Cr
23-26 March 2010, IAEA, Vienna6
Results of the evaluation for 50Cr (partial cross sections)
10 20 30 40 50 600
20
40
60
80
100
120
140
160
Ghorai, 87 Chatterjee, 69 Ercan, 91 Ikeda, 88 Bormann, 65 Qaim, 72 Bahal, 85 Feng-Qun, 05 Uwamino, 92 TENDL-2009 present result
C
ross
sec
tion
[mb]
Neutron energy [MeV]
50Cr(n,2n)49Cr
20 30 40 50 60 70 800
2
4
6
8
10
Uwamino, 92 TENDL-2009 present result
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
50Cr(n,3n)48Cr
0 10 20 30 40 50 600
20
40
60
80
100
120
140
Derndorfer, 81 Matsuyama, 93 Grimes, 79 Dolya, 73 EAF-2007 TENDL-2009 present result
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
50Cr(n,a)47Ti
0 10 20 30 40 50 600
100
200
300
400
500
TENDL-2009 present result
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
50Cr(n,p)50V
23-26 March 2010, IAEA, Vienna7
Results of the evaluation for 52Cr (partial cross sections)
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 400
200
400
600
Fessler, 98 Erkan, 91 Ikeda, 88 Maslov, 72 Uno, 96 Ghorai, 87 Wagner, 90 Liskien, 89 Molla, 97 Bormann, 68 Zhou, 05 Mannhart, 07 JEFF-3.1 present result
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
52Cr(n,2n)51Cr
0 2 4 6 8 10 12 14 16 18 200
200
400
600
800
1000
1200
1400
1600
1800
Mihailesku, 04 JEFF-3.1 present result
Cro
ss s
ectio
n [
mb]
Neutron energy [MeV]
52Cr(n,n')
0 2 4 6 8 10 12 14 16 18 200
200
400
600
800
1000
1200
1400
1600
Mihailescu, 04 Schmidt, 98 Olsson, 89 JEFF-3.1 present results
C
ross
sec
tion
[mb]
Neutron energy [MeV]
52Cr(n,n')E
lev=1.434 MeV
0 5 10 15 20 25 30 35 400
10
20
30
40
50
60
70
80
90
100
Fessler, 98 Ikeda, 88 Ghorai, 87 Kasugai, 98 Smith, 80 EAF-2007 present result
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
52Cr(n,p)52V
23-26 March 2010, IAEA, Vienna8
Results of the evaluation for 53Cr (partial cross sections)
0 10 20 30 40 50 600
10
20
30
40
50
60
Dolya, 73 TENDL-2009 present result
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
53Cr(n,)50Ti
10 15 20 25 30 35 400
50
100
150
Thiep, 03 Husain, 67 Ribansky, 85 Sakane, 02 TENDL-2009
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
53Cr(n,np)52V
0 10 20 30 40 50 600
10
20
30
40
50
60
Fessler, 98 Thiep, 03 Valkonen, 76 Artemjev, 80 Osman, 96 Bahal, 85 Viennot, 82 Kawade, 90 TENDL-2009
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
53Cr(n,p)53V
0 2 4 6 8 10 12 14 16 18 200
50
100
150
200
250
300
350
400
Kramarovskiy Van Patter, 62 present result
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
53Cr(n,n')E
lev=0.564MeV
23-26 March 2010, IAEA, Vienna9
Results of the evaluation for 54Cr (partial cross sections)
0 5 10 15 20 25 30 35 400
2
4
6
8
10
12
14
16
18
Kasugai, 98 Fessler, 98 Sailer, 77 Erkan, 91 Thiep, 03 Qaim, 74 TENDL-2009 present result
C
ross
sec
tion
[mb]
Neutron energy [MeV]
54Cr(n,)51Ti
0 10 20 30 40 50 600
5
10
15
20
25
30
Fessler, 98 Luc, 86 Qaim, 77 Valkonen, 76 Bahal, 84 Kawade, 92 Ribansky, 85 TENDL-2009 present result
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
54Cr(n,p)54V
10-3 10-2 10-1 100 101 102
10-1
100
101
102
103
Stieglitz, 71 Stieglitz, 71 TENDL-2009 present work
Cro
ss s
ectio
n [m
barn
]
Neutron energy [MeV]
54Cr(n,)
10 15 20 25 30 35 40
1
10
100
Luc, 86 Thiep, 03 Ribansky, 85 Sakane, 02 Fessler, 98 TENDL-2009 present result
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
54Cr(n,x)53V
23-26 March 2010, IAEA, Vienna10
Gas production data (protons)
0 20 40 60 80 100 120 1400
200
400
600
800
1000
1200
Haight, 07 TENDL-2009 present result
Cr(n,xp)
C
ross
sec
tion
[mb]
Neutron energy [MeV]
23-26 March 2010, IAEA, Vienna11
Gas production data (alphas)
0 20 40 60 80 100 120 1400
50
100
150
200
250
Haight, 07 TENDL-2009 present result
Cr(n,x)
Cro
ss s
ectio
n [m
b]
Neutron energy [MeV]
23-26 March 2010, IAEA, Vienna12
Particle emission spectra (neutrons)
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14
101
102
103
Takahashi, 88 Yabuta, 88 Matsuyama, 92 Simakov, 88 JEFF-3.1 present result
14 MeV 52Cr(n,xn)
ds/d
E [
mb/
MeV
]
Neutron emission energy [MeV]
0 1 2 3 4 5 6 7 8101
102
103
Schmidt, 97 present result
8 MeV Cr(n,xn)
ds/d
E [
mb/
MeV
]
Neutron emission energy [MeV]
0 1 2 3 4 5 6 7 8 9 10101
102
103
Schmidt, 97 present result
10 MeV Cr(n,xn)
ds/d
E [
mb/
MeV
]
Neutron emission energy [MeV]
23-26 March 2010, IAEA, Vienna13
Particle emission spectra (photons)
0 2 4 6 8 10 12 14 16 18 20 2210-5
10-4
10-3
10-2
10-1
100
101
102
103
104
Morgan, 77 present result
5 MeV Cr(n,xg)
ds/d
Ed
[mb/
MeV
sr]
Neutron emission energy [MeV]
=125o
0 5 10 15 20 25 30 3510-6
10-5
10-4
10-3
10-2
10-1
100
101
102
103
104
105
106
107
Morgan, 77 present result
19 MeV Cr(n,xg)
ds/d
Ed
[m
b/M
eV s
r]
Neutron emission energy [MeV]
=125o
23-26 March 2010, IAEA, Vienna14
Charged particle emission spectra(alphas)
2 4 6 8 10 12 14 16 1810-2
10-1
100
101
102
Grimes, 79 present result
14.8 MeV 50Cr(n,x)
ds/d
E [
mb/
MeV
]
Alpha emission energy [MeV]
0 5 10 1510-2
10-1
100
101
102
Matsuyama, 93 TENDL-2009 present work
11.5 MeV 50Cr(n,x)
ds/d
E [
mb/
MeV
]
Alpha emission energy [MeV]0 2 4 6 8 10 12 14
10-4
10-3
10-2
10-1
100
101
Matsuyama, 93 TENDL-2009 (www.talys.eu) TENDL-2009 (ENDF-6 file) present result
6 MeV 50Cr(n,x)
ds
/dE
[m
b/M
eV]
Alpha emission energy [MeV]
0 5 10 1510-2
10-1
100
101
102
Matsuyama, 93 TENDL-2009 present work
8 MeV 50Cr(n,x)
ds/d
E [
mb/
MeV
]
Alpha emission energy [MeV]
23-26 March 2010, IAEA, Vienna15
Evaluated data file content (promising)
MF1
MF2
MF3
MF4
MF6
MF8
MF10
MF12
MF14
MF33
MF40
MT= 2, 51-70
MT= 5 (n, p, d, t, h, , recoils, - spectra), 102
MT= 5
MT= 5 (subsections for each recoil)
MT= 51-70
MT= 51-70
MT= 1, 2, 51-70, 102
MT= 5 (subsections for each recoil)
MT=451, general information
MT=151, resonance parameters
MT= 1, 2, 5, 51-70, 102
23-26 March 2010, IAEA, Vienna16
Evaluated data file content (conventional)
MF1
MF2
MF3
MF4
MF6
MF8
MF10
MF12
MF14
MF33
MT= 2, 51-70
MT= …
MT= …
MT= 51-70
MT= 51-70
MT=451, general information
MT=151, resonance parameters
MT= 1,2,4,5,16,17,22,28,5,51-70,102,103,104,105,106,107
MT= 1,2,4,5,16,17,22,28,5,51-70,102,103,104,105,106,107
MT= 1,2,4,5,16,17,22,28,5,51-70,102,103,104,105,106,107
23-26 March 2010, IAEA, Vienna17
OKTAVIAN benchmark: neutron leakage spectra
10-2 10-1 100 101
10-4
10-3
10-2
10-1
100
101
OKTAVIAN JEFF3.1 FZK
Neutron emission energy [MeV]
Neu
tron
leak
age
curr
ent
[u-1sn
-1]
23-26 March 2010, IAEA, Vienna18
OKTAVIAN benchmark: neutron flux integrals
0,1 1 100,90
0,95
1,00
1,05
1,10
1,15
1,20
1,25
TENDL-2009 JEFF3.1
FZK (52Cr)
Neutron energy [MeV]
C/E
Experimental error
Oktavian chromium spherical shell
23-26 March 2010, IAEA, Vienna19
Conclusions
The neutron transport files are available for all stable Cr isotopes for neutron energies up to 200 MeV
GDH model for the preequilibrium reactions was included as an option in TALYS code
The set of the optimal models paramers and nuclear models for TALYS calculations was obtained for Cr-50,53,54 isotopes
Very good description of the avalable experimental data was achieved
The calculations of the covariances are being finalized.
The newly evaluated resonance parameters will be supplied by L. Leal
The ENDF-6 files are expected to be prepared by the end of April 2010
The benchmark calculations were done