28-Ni- 59 JAEA EVAL-FEB09 K.Shibata
DIST-SEP12 20120203
----JENDL-4.0u1 MATERIAL 2828
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
Update File Distribution
Sep.14,2012 JENDL-4.0u1
History
09-02 Model calculation was performed using the POD code.
09-11 Data were compiled by K. Shibata, JAEA.
12-02 Redundant data at 10 keV were deleted for (n,p) and (n,a).
Re-compiled by K. Shibata.
MF= 1 General information
MT=451 Descriptive data and directory
MF= 2 Resonance parameters
MT=151
Resolved resonance parameters were obtained from the data of
Harvey et al. /1/ up to 10 keV. The (n,p) and (n,a) cross
sections were also calculated using their parameters although
Gamma_g and Gamma_a at 203 eV were changed to 2.9 eV and
0.48 eV, respectively.
Unresolved resonance parameters were calculated using the
ASREP code /2/ from 10 keV to 300 keV. The unresolved
parameters should be used only for self-shielding calculation.
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 9.1811E+01
Elastic 2.3047E+00
n,gamma 7.5597E+01 1.1977E+02
n,p 1.4480E+00
n,alpha 1.2456E+01
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Calculated with POD code /3/ above 10 keV. Below 10 keV,
the cross section was given by the sum of the elastic and
non-elastic cross sections.
MT= 2 Elastic scattering cross section
The cross section was obtained by subtracting the
non-elastic cross section from the total cross section above
10 keV. Below 10 keV, the cross sections are reconstructed
from the resolved resonance parameters given in MF2.
MT= 3 Non-elastic cross section
Sum up of partial cross sections
MT= 4,51-91 (n,n') cross section
Calculated with POD code /3/.
MT= 16 (n,2n) cross section
Calculated with POD code /3/.
MT= 22 (n,na) cross section
Calculated with POD code /3/.
MT= 28 (n,np) cross section
Calculated with POD code /3/.
MT= 32 (n,nd) cross section
Calculated with POD code /3/.
MT=102 Capture cross section
Calculated with POD code /3/ above 10 keV. Below 10 keV,
cross sections are reconstructed from the resolved resonance
parameters given in MF2.
MT=103 (n,p) cross section
Calculated with POD code /3/. The values calculated from
resonance parameters were used between 1.0-5 eV and 10 keV.
MT=104 (n,d) cross section
Calculated with POD code /3/.
MT=105 (n,t) cross section
Calculated with POD code /3/.
MT=106 (n,He3) cross section
Calculated with POD code /3/.
MT=107 (n,a) cross section
Calculated with POD code /3/. The values calculated from
resonance parameters were used between 1.0-5 eV and 10 keV.
MT=203 (n,xp) cross section
Calculated with POD code /3/.
MT=204 (n,xd) cross section
Calculated with POD code /3/.
MT=205 (n,xt) cross section
Calculated with POD code /3/.
MT=206 (n,xHe3) cross section
Calculated with POD code /3/.
MT=207 (n,xa) cross section
Calculated with POD code /3/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with POD code /3/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Neutron spectra calculated with POD/3/.
MT= 22 (n,na) reaction
Neutron spectra calculated with POD/3/.
MT= 28 (n,np) reaction
Neutron spectra calculated with POD/3/.
MT= 32 (n,nd) reaction
Neutron spectra calculated with POD/3/.
MT= 51 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 52 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 53 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 54 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 55 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 56 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 57 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 58 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 59 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 60 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 61 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 62 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 63 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 64 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 65 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 66 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 67 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 68 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 69 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 70 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 71 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 72 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 73 (n,n') reaction
Neutron angular distributioins calculated with POD/3/.
MT= 91 (n,n') reaction
Neutron spectra calculated with POD/3/.
MT= 203 (n,xp) reaction
Proton spectra calculated with POD/3/.
MT= 204 (n,xd) reaction
Deuteron spectra calculated with POD/3/.
MT= 205 (n,xt) reaction
Triton spectra calculated with POD/3/.
MT= 206 (n,xHe3) reaction
He3 spectra calculated with POD/3/.
MT= 207 (n,xa) reaction
Alpha spectra calculated with POD/3/.
MF=12 Gamma-ray multiplicities
MT= 3 Non-elastic gamma emission
Calculated with POD code /3/.
MF=14 Gamma-ray angular distributions
MT= 3 Non-elastic gamma emission
Assumed to be isotropic.
MF=15 Gamma-ray spectra
MT= 3 Non-elastic gamma emission
Calculated with POD code /3/.
***************************************************************
* Nuclear Model Calculations with POD Code /3/ *
***************************************************************
1. Theoretical models
The POD code is based on the spherical optical model, the
distorted-wave Born approximaiton (DWBA), one-component exciton
preequilibrium model, and the Hauser-Feshbach-Moldauer statis-
tical model. With the preequilibrim model, semi-empirical
pickup and knockout process can be taken into account for
composite-particle emission. The gamma-ray emission from the
compound nucleus can be calculated within the framework of the
exciton model. The code is capable of reading in particle
transmission coefficients calcualted by separate spherical or
coupled-channel optical model code.
2. Optical model parameters
Neutrons:
Coupled-channel optical model parameters /4/
Protons:
Koning and Delaroche /5/
Deuterons:
Lohr and Haeberli /6/
Tritons:
Becchetti and Greenlees /7/
He-3:
Becchetti and Greenlees /7/
Alphas:
Lemos /8/ potentials modified by Arthur and Young /9/
3. Level scheme of Ni- 59
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 3/2 -
1 0.33942 5/2 -
2 0.46498 1/2 -
3 0.87795 3/2 -
4 1.18879 5/2 -
5 1.30141 1/2 -
6 1.33789 7/2 -
7 1.67970 5/2 -
8 1.69500 3/2 -
9 1.73472 3/2 -
10 1.73924 9/2 -
11 1.74610 7/2 -
12 1.76745 9/2 -
13 1.94793 7/2 -
14 2.33000 7/2 -
15 2.41497 3/2 -
16 2.42800 9/2 +
17 2.48000 3/2 +
18 2.53040 9/2 -
19 2.53550 11/2 -
20 2.55340 1/2 +
21 2.62707 7/2 -
22 2.64000 1/2 -
23 2.68140 3/2 -
-------------------------
Levels above 2.69140 MeV are assumed to be continuous.
4. Level density parameters
Energy-dependent parameters of Mengoni-Nakajima /10/ were used.
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Elv_max
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
Ni- 60 8.376 3.098 -2.241 1.395 -0.352 13.291 4.399
Ni- 59 9.585 1.562 -3.079 1.277 -1.341 10.484 2.681
Ni- 58 8.144 3.151 -4.036 1.607 -0.588 14.685 4.538
Ni- 57 8.678 1.589 -5.289 1.539 -0.391 10.513 3.726
Co- 59 7.894 1.562 -1.228 1.399 -2.110 12.025 3.140
Co- 58 8.141 0.000 -2.316 1.407 -3.180 9.864 1.813
Co- 57 7.671 1.589 -2.982 1.619 -2.652 13.777 3.262
Fe- 57 9.205 1.589 -1.308 1.096 -0.485 8.567 3.059
Fe- 56 7.911 3.207 -2.147 1.461 -0.420 13.836 4.540
Fe- 55 9.160 1.618 -2.977 1.301 -1.160 10.397 3.457
----------------------------------------------------------
5. Gamma-ray strength functions
M1, E2: Standard Lorentzian (SLO)
E1 : Generalized Lorentzian (GLO) /11/
6. Preequilibrium process
Preequilibrium is on for n, p, d, t, He-3, and alpha.
Preequilibrium capture is on.
References
1) J.A.Harvey et al., ORNL-5137, 2 (1976).
2) K.Kikuchi et al., JAERI-Data/Code 99-025 (1999).
3) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).
4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).
5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).
6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).
7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization
Phenomena in Nuclear Reactions," p.682, The University
of Wisconsin Press (1971).
8) O.F.Lemos, Orsay Report, Series A, No.136 (1972).
9) E.D.Arthur, P.G.Young, LA-8626-MS (1980).
10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151
(1994).
11) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).