20-Ca- 46 JAEA EVAL-JUN06 K.Shibata
DIST-MAY10 20091228
----JENDL-4.0 MATERIAL 2043
-----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
No resonance parameters are given.
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 3.6800E+00
Elastic 2.9325E+00
n,gamma 7.4023E-01 3.6492E-01
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF=3 Neutron cross sections
Below 1 keV, constant elastic scattering cross sections and
1/v capturte cross sections were given. The thermal scattering
and capture cross sections are the same as those of JENDL-3.3,
i.e., 2.9 b and 0.74 b, respectively.
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, 51-87, 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= 17 (n,3n)
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= 17 (n,3n) 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= 51-87 (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= 600-608 (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 (n,a) reactions leading to discrete levels
Alpha-particle angular distributions calculated with TNG/3/.
MT= 849 (n,a) reaction leading to continuum levels
Alpha-particle 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- 46 >
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 0 +
1 1.34600 2 +
2 2.42310 0 +
3 2.57470 4 +
4 2.97390 6 +
5 3.02260 2 +
6 3.61400 3 -
7 3.63890 2 +
8 3.85970 4 +
9 3.95200 2 -
10 3.98800 3 -
11 4.18450 5 -
12 4.26100 1 -
13 4.40700 3 -
14 4.43020 2 +
15 4.48940 4 +
16 4.72880 5 -
17 4.74490 4 +
18 4.75800 0 +
19 4.99470 4 +
20 5.01360 4 +
21 5.05100 4 +
22 5.15160 4 +
23 5.21800 2 -
24 5.25150 4 +
25 5.31700 0 +
26 5.37960 3 -
27 5.39200 3 -
28 5.41670 4 -
29 5.43670 4 +
30 5.47400 3 -
31 5.53670 4 +
32 5.60000 0 +
33 5.62800 0 +
34 5.63800 4 +
35 5.67900 1 -
36 5.69000 4 +
37 5.72200 5 +
The direct-reaction process was taken into account for the 1st
ans 6th 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- 47 7.460 1.750 -0.360 0.759 3.034 7.442 4.386
Ca- 46 6.726 3.539 0.523 1.285 1.138 10.682 5.782
Ca- 45 7.212 1.789 0.882 1.223 -0.908 9.109 3.556
Ca- 44 6.485 3.618 1.143 1.463 -0.604 13.607 4.905
K - 46 6.734 0.000 0.257 0.478 3.317 5.761 3.383
K - 45 6.294 1.789 1.446 1.108 0.827 6.485 3.690
Ar- 43 6.962 1.830 1.898 0.757 1.830 3.485 1.830
Ar- 42 6.243 3.703 2.211 1.223 1.384 10.373 2.415
----------------------------------------------------------
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).