20-Ca- 44 JAEA EVAL-JUN06 K.Shibata
DIST-MAY10 20091228
----JENDL-4.0 MATERIAL 2037
-----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 4.2473E+00
Elastic 3.3587E+00
n,gamma 8.8863E-01 4.2453E-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 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= 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 calculated with TNG/3/. Gamma-ray channel is not open.
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= 600-603 (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= 800-829 (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- 44 >
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 0 +
1 1.15710 2 +
2 1.88350 0 +
3 2.28310 4 +
4 2.65650 2 +
5 3.04430 4 +
6 3.28500 6 +
7 3.30130 2 +
8 3.30790 3 -
9 3.35720 3 +
10 3.58040 3 +
11 3.66150 1 -
12 3.67610 2 -
13 3.71180 4 -
14 3.77620 2 +
15 3.86500 5 -
16 3.91350 5 -
17 3.92260 3 +
18 4.01140 3 +
19 4.09200 2 +
20 4.16900 1 +
21 4.19570 2 +
22 4.26020 3 +
23 4.31520 3 +
24 4.35840 3 -
25 4.39940 3 -
26 4.40920 1 -
27 4.43700 2 +
28 4.47980 2 +
29 4.55260 1 -
30 4.56490 5 -
31 4.57300 3 -
32 4.58410 3 +
33 4.60400 1 +
34 4.65100 2 +
35 4.69020 2 +
36 4.80370 1 -
37 4.82400 2 -
38 4.86610 2 +
39 4.88400 2 -
The direct-reaction process was taken into account for the 1st,
3rd, 4th, 8th, 16th, and 25th 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- 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
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
K - 44 6.494 0.000 1.303 1.184 -1.660 5.909 0.812
K - 43 6.062 1.830 2.010 1.410 -1.729 10.733 3.393
Ar- 41 8.342 1.874 2.006 0.721 1.512 4.471 3.968
Ar- 40 5.998 3.795 1.822 1.464 -0.092 13.254 5.378
----------------------------------------------------------
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).