20-Ca- 40 JAEA EVAL-JUN06 K.Shibata
DIST-MAY10 20091228
----JENDL-4.0 MATERIAL 2025
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
06-06 Evaluated by K.Shibata.
09-12 Compiled by K.Shibata
MF=1 General information
MT=451 Descriptive data and dictionary
MF=2 Resonance parameters
MT=151 Resolved resonance parameters
The resolved resonance region remains unchanged from JENDL-3.3.
Resolved parameters for MLBW formula were given in the energy
region from 1.0e-5 eV to 500 keV. Parameters were taken from
the recommended data of BNL/1/ and the data for a negative
resonance were added so as to reproduce the recommended thermal
cross sections for capture and scatterng/1/. The scattering
radius was assumed to be 3.6 fermi.
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 3.4685E+00
Elastic 3.0610E+00
n,gamma 4.0760E-01 2.1274E-01
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF=3 Neutron cross sections
Below 500 keV, zero background cross section was given and all
the cross-section data are reproduced from the evaluated
resolved resonance parameters with MLBW formula.
The cross sections were calcualted /2/ by using the TNG code
/3/. The optilcal model parameters of Koning and Delaroche /4/
were used for neutrons and protons. The alpha-particle
potential parameters were derived from the code developed by
Kumar and Kailas./5/
MT= 1 Total
The total cross section was taken from the JENDL-3.3 evaluation
that was based on the experimental data of Cierjacks et al./6/
and Foster, Jr. and Glasgow /7/.
MT= 2 Elastic scattering
Obtained by subtracting the sum of the partial cross sections
from the total cross section.
MT= 4, 51-73, 91 Inelastic scattering
The cross sections were calculated with the TNG code./3/
MT= 16 (n,2n)
The cross sections were calculated with the TNG code./3/
MT= 22 (n,na)
The cross sections were calculated with the TNG code./3/
MT= 28 (n,np)
The cross sections were calculated with the TNG code./3/
MT= 102 Capture
The cross sections were calculated with the TNG code./3/
MT= 103 (n,p)
The cross sections were calculated with the TNG code./3/
MT= 107 (n,a)
The cross sections were calculated with the TNG code./3/
MT= 600-649 partial (n,p) cross sections
The cross sections were calculated with the TNG code./3/
MT= 800-849 partial (n,a) cross sections
The cross sections were calculated with the TNG code./3/
MF=4 Angular distributions of secondary neutrons
MT=2
Calculated with the TNG code/3/.
MF=6 Energy-angle distributions of secondary particles
MT= 16 (n,2n) reaction
Neutron and gamma-ray spectra calculated with TNG/3/.
MT= 22 (n,na) reaction
Neutron, alpha-particle, and gamma-ray spectra calculated with
TNG/3/.
MT= 28 (n,np) reaction
Neutron, proton, and gamma-ray spectra calculated with TNG/3/.
MT= 51-73 (n,n') reaction
Neutron angular distributions and discrete gamma-ray spectra
calculated with TNG/3/.
MT= 91 (n,n') reaction
Neutron spectra, and discrete-continuous gamma-ray spectra
calculated with with TNG/3/.
MT= 102
Calculated with the TNG code /3/.
MT= 600-639 (n,p) reactions leading to discrete levels
Proton angular distributions and discrete gamma-ray spectra
calculated with TNG/3/.
MT= 649 (n,p) reaction leading to continuum levels
Proton spectra and discrete-continuous gamma-ray spectra
calculated with TNG/3/.
MT= 800-832 (n,a) reactions leading to discrete levels
Alpha-particle angular distributions and gamma-ray spectra
calculated with TNG/3/.
MT= 849 (n,a) reaction leading to continuum levels
Alpha-particle spectra and discrete-continuous gamma-ray
spectra calculated with TNG/3/.
< Appendix >
******************************************************************
* Nuclear Model Calcualtions with TNG Code /3/ *
******************************************************************
The description of the model calculations is given in Ref.2.
< Optical model parameters >
Neutron and protons:
Koning and Delaroche /4/
Alphas:
The potential parameters were obtained using the code developed
by Kumar and Kailas./5/
< Level scheme of Ca- 40 >
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 0 +
1 3.35260 0 +
2 3.73670 3 -
3 3.90440 2 +
4 4.49140 5 -
5 5.21160 0 +
6 5.24880 2 +
7 5.27880 4 +
8 5.61350 4 -
9 5.62940 2 +
10 5.90260 1 -
11 6.02550 2 -
12 6.02970 3 +
13 6.28520 3 -
14 6.42240 2 +
15 6.50790 4 +
16 6.54280 4 +
17 6.58250 3 -
18 6.75040 2 -
19 6.90870 2 +
20 6.93020 6 +
21 6.93130 3 -
22 6.93800 3 -
23 6.95050 1 -
The direct-reaction process was taken into account for the 2nd,
3rd, 4th, 6th, 7th, 9th, 13th, 14th, 15th, 17th, and 19th levels
by DWBA.
< Level density parameters >
Energy dependent parameters of Mengoni-Nakajima /8/ were used.
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Econt
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
Ca- 41 6.285 1.874 -0.149 1.397 -0.507 9.227 4.728
Ca- 40 5.998 3.795 -1.846 1.494 2.450 10.045 7.113
Ca- 39 6.455 1.922 -0.346 0.839 3.517 8.268 4.920
K - 40 6.010 0.000 -0.027 1.352 -1.491 6.250 3.557
K - 39 5.593 1.922 -0.694 1.476 0.637 8.268 5.502
Ar- 37 6.197 1.973 -0.393 1.348 0.521 8.189 5.213
Ar- 36 5.504 4.000 -1.321 1.645 1.856 11.777 7.423
----------------------------------------------------------
References
1) Mughaghab S.F. et al.:"Neutron Cross Sections", Vol. 1, Part
A (1981).
2) Shibata, K: J. Nucl. Sci. Technol., 44, 10 (2007).
3) Fu, C.Y.: ORNL/TM-7042 (1980); Shibata, K., Fu, C.Y.: ORNL/TM-
10093.
4) Koning, A.J., Delaroche, J.P.: Nucl. Phys., A713, 231 (2003).
5) Kumar, A., Kailas, S: a computer code contained in RIPL-2,
private communication (2002).
6) Cierjacks, S. et al.: KFK-1000 (1968).
7) Foster, D.G, Glasgow, D.W.: Phys. Rev. C3, 576 (1971).
8) Mengoni, A., Nakajima, Y. Nucl. Sci. Technol., 31, 151 (1994).