57-La-140 JAEA EVAL-DEC09 K.Shibata, T.Nakagawa
DIST-MAY10 20100105
----JENDL-4.0 MATERIAL 5731
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
06-12 Thermal cross sections were determined by T.Nakagawa.
09-12 Statistical model calculations were performed by K.Shibata.
10-01 Data were compiled by K.Shibata.
MF= 1 General information
MT=451 Descriptive data and directory
MF= 2 Resonance parameters
MT=151 Resolved and unresolved resonance parameters
No resolved resonance parameters are given.
The 1/v-shped capture cross section is assumed below 57 eV.
At 0.0253 eV, the cross section was normalized to the value
of 2.7 b, which was recommended by Mughabghab/1/.
Constant scattering cross sections of 3.14 b were assumed
below 57 eV.
Unresolved resonance region: 57 eV - 40 keV
The parameters were obtained by fitting to the total and
capture cross sections calculated from POD /2/. 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 5.8655E+00
Elastic 3.1545E+00
n,gamma 2.7012E+00 2.0439E+01
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Calculated with POD code /2/.
MT= 2 Elastic scattering cross section
The cross sections were obtained by subtracting the nonelastic
cross sections from the total cross sections.
MT= 3 Non-elastic cross section
Calculated with POD code /2/.
MT= 4,51-91 (n,n') cross section
Calculated with POD code /2/.
MT= 16 (n,2n) cross section
Calculated with POD code /2/.
MT= 17 (n,3n) cross section
Calculated with POD code /2/.
MT= 22 (n,na) cross section
Calculated with POD code /2/.
MT= 28 (n,np) cross section
Calculated with POD code /2/.
MT= 32 (n,nd) cross section
Calculated with POD code /2/.
MT=102 Capture cross section
Calculated with POD code /2/.
MT=103 (n,p) cross section
Calculated with POD code /2/.
MT=104 (n,d) cross section
Calculated with POD code /2/.
MT=105 (n,t) cross section
Calculated with POD code /2/.
MT=106 (n,He3) cross section
Calculated with POD code /2/.
MT=107 (n,a) cross section
Calculated with POD code /2/.
MT=203 (n,xp) cross section
Calculated with POD code /2/.
MT=204 (n,xd) cross section
Calculated with POD code /2/.
MT=205 (n,xt) cross section
Calculated with POD code /2/.
MT=206 (n,xHe3) cross section
Calculated with POD code /2/.
MT=207 (n,xa) cross section
Calculated with POD code /2/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with POD code /2/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Neutron spectra calculated with POD/2/.
MT= 17 (n,3n) reaction
Neutron spectra calculated with POD/2/.
MT= 22 (n,na) reaction
Neutron spectra calculated with POD/2/.
MT= 28 (n,np) reaction
Neutron spectra calculated with POD/2/.
MT= 32 (n,nd) reaction
Neutron spectra calculated with POD/2/.
MT= 51 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 52 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 53 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 54 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 55 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 56 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 57 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 58 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 59 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 60 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 61 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 62 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 63 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 64 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 65 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 66 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 67 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 68 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 69 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 70 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 71 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 72 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 73 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 74 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 75 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 76 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 77 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 78 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 79 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 80 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 81 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 82 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 83 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 84 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 85 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 86 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 91 (n,n') reaction
Neutron spectra calculated with POD/2/.
MT= 203 (n,xp) reaction
Proton spectra calculated with POD/2/.
MT= 204 (n,xd) reaction
Deuteron spectra calculated with POD/2/.
MT= 205 (n,xt) reaction
Triton spectra calculated with POD/2/.
MT= 206 (n,xHe3) reaction
He3 spectra calculated with POD/2/.
MT= 207 (n,xa) reaction
Alpha spectra calculated with POD/2/.
MF=12 Gamma-ray multiplicities
MT= 3 Non-elastic gamma emission
Calculated with POD code /2/.
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 /2/.
***************************************************************
* Nuclear Model Calculations with POD Code /2/ *
***************************************************************
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 calculated by separate spherical or
coupled-channel optical model code.
2. Optical model parameters
Neutrons:
Coupled-channel optical model parameters /3/
Protons:
Koning and Delaroche /4/
Deuterons:
Lohr and Haeberli /5/
Tritons:
Becchetti and Greenlees /6/
He-3:
Becchetti and Greenlees /6/
Alphas:
Lemos /7/ potentials modified by Arthur and Young /8/
3. Level scheme of La-140
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 3 -
1 0.02996 2 -
2 0.03465 5 -
3 0.04381 1 -
4 0.04886 6 -
5 0.06317 4 -
6 0.09280 4 +
7 0.10380 6 -
8 0.16266 2 -
9 0.27234 4 -
10 0.28467 7 -
11 0.31826 3 -
12 0.32206 5 -
13 0.46753 1 -
14 0.57554 2 -
15 0.58107 0 -
16 0.59211 2 -
17 0.60201 4 -
18 0.65826 3 -
19 0.67302 4 -
20 0.71122 3 -
21 0.74472 4 -
22 0.75483 1 -
23 0.77144 3 -
24 0.79625 2 -
25 0.83090 3 -
26 0.90575 2 -
27 0.91217 3 -
28 0.91387 4 -
29 0.91753 3 -
30 0.93030 5 -
31 0.94175 2 -
32 0.96866 3 -
33 0.98670 4 -
34 1.03566 4 -
35 1.05507 5 -
36 1.07690 3 -
-------------------------
Levels above 1.08690 MeV are assumed to be continuous.
4. Level density parameters
Energy-dependent parameters of Mengoni-Nakajima /9/ were used
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Elv_max
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
La-141 16.484 1.011 -0.489 0.648 -0.555 5.963 1.551
La-140 17.670 0.000 -1.423 0.570 -0.837 3.629 1.077
La-139 16.284 1.018 -2.218 0.689 -0.214 5.762 2.061
La-138 16.775 0.000 -1.494 0.610 -0.937 3.955 1.067
Ba-140 17.080 2.028 -1.371 0.619 0.890 6.291 2.522
Ba-139 20.278 1.018 -2.243 0.495 0.501 3.845 2.350
Ba-138 16.832 2.043 -3.149 0.730 0.626 7.232 3.184
Cs-138 16.775 0.000 -2.915 0.677 -0.982 4.356 0.691
Cs-137 16.083 1.025 -3.799 0.731 0.198 5.459 2.217
Cs-136 16.569 0.000 -2.913 0.933 -4.227 9.651 0.010
----------------------------------------------------------
5. Gamma-ray strength functions
M1, E2: Standard Lorentzian (SLO)
E1 : Generalized Lorentzian (GLO) /10/
6. Preequilibrium process
Preequilibrium is on for n, p, d, t, He-3, and alpha.
Preequilibrium capture is on.
References
1) S.F.Mughabghab, Atlas of Neutron Resonances, Elsevier,
(2006).
2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).
3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).
4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).
5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).
6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization
Phenomena in Nuclear Reactions," p.682, The University
of Wisconsin Press (1971).
7) O.F.Lemos, Orsay Report, Series A, No.136 (1972).
8) E.D.Arthur, P.G.Young, LA-8626-MS (1980).
9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151
(1994).
10) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).