20-Ca- 42 JAEA EVAL-JUN06 K.Shibata
DIST-MAY10 20091228
----JENDL-4.0 MATERIAL 2031
-----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 300 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 1.9199E+00
Elastic 1.2369E+00
n,gamma 6.8308E-01 3.7692E-01
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF=3 Neutron cross sections
Below 300 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 cross sections were calculated with the TNG code./3/
MT= 2 Elastic scattering
Obtained by subtracting the sum of the partial cross sections
from the total cross section.
MT= 4, 51-89, 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= 51-89 (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= 800-830 (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- 42 >
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 0 +
1 1.52470 2 +
2 1.83730 0 +
3 2.42420 2 +
4 2.75240 4 +
5 3.18930 6 +
6 3.25390 4 +
7 3.30000 0 +
8 3.39200 2 +
9 3.44700 3 -
10 3.65400 2 +
11 3.88500 1 -
12 3.95440 4 -
13 3.99970 3 -
14 4.04700 3 -
15 4.09970 5 -
16 4.11700 3 -
17 4.23200 1 -
18 4.35400 4 -
19 4.41800 3 -
20 4.44300 4 +
21 4.45200 2 +
22 4.50500 3 +
23 4.56700 2 -
24 4.69010 3 -
25 4.71500 4 +
26 4.75970 2 +
27 4.86600 2 +
28 4.89600 5 -
29 4.90400 3 -
30 4.94700 2 -
31 4.97100 3 -
32 5.01710 4 +
33 5.07500 2 -
34 5.15800 3 -
35 5.18800 3 +
36 5.21000 2 +
37 5.21500 4 -
38 5.32000 3 -
39 5.34500 0 +
The direct-reaction process was taken into account for the 1st,
3rd, 4th, 9th, 20th, 24th, and 31st levels by DWBA.
< Level density parameters >
Energy dependent parameters of Mengoni-Nakajima /6/ were used.
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Econt
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
Ca- 43 6.962 1.830 0.922 1.322 -1.548 10.316 3.419
Ca- 42 6.243 3.703 0.470 1.550 -0.451 13.961 5.357
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
K - 42 6.253 0.000 1.255 1.396 -3.279 8.501 2.251
K - 41 5.828 1.874 1.299 1.617 -2.774 12.920 3.572
Ar- 39 6.455 1.922 1.140 1.228 -0.117 8.268 4.178
Ar- 38 5.752 3.893 0.184 1.501 1.229 11.878 6.824
----------------------------------------------------------
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) Mengoni, A., Nakajima, Y. Nucl. Sci. Technol., 31, 151 (1994).