20-Ca- 43 JAEA EVAL-JUN06 K.Shibata
DIST-MAY10 20091228
----JENDL-4.0 MATERIAL 2034
-----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 40 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.
For JENDL-4.0, the parameters were updated by using the values
obtained by Moxon et al./2/
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 1.1334E+01
Elastic 5.1312E+00
n,gamma 6.2030E+00 4.3115E+00
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF=3 Neutron cross sections
Below 40 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 /3/ by using the TNG code
/4/. The optilcal model parameters of Koning and Delaroche /5/
were used for neutrons and protons. The alpha-particle
potential parameters were derived from the code developed by
Kumar and Kailas./6/
MT= 1 Total
The cross sections were calculated with the TNG code./4/
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./4/
MT= 16 (n,2n)
The cross sections were calculated with the TNG code./4/
MT= 17 (n,3n)
The cross sections were calculated with the TNG code./4/
MT= 22 (n,na)
The cross sections were calculated with the TNG code./4/
MT= 28 (n,np)
The cross sections were calculated with the TNG code./4/
MT= 102 Capture
The cross sections were calculated with the TNG code./4/
MT= 103 (n,p)
The cross sections were calculated with the TNG code./4/
The calculated cross sections were multiplied by 2.4 in order
to reproduce measured data.
MT= 107 (n,a)
The cross sections were calculated with the TNG code./4/
MT= 600-649 partial (n,p) cross sections
The cross sections were calculated with the TNG code./4/
The calculated cross sections were multiplied by 2.4 in order
to reproduce measured total (n,p) data.
MT= 800-849 partial (n,a) cross sections
The cross sections were calculated with the TNG code./4/
MF=4 Angular distributions of secondary neutrons
MT=2
Calculated with the TNG code/4/.
MF=6 Energy-angle distributions of secondary particles
MT= 16 (n,2n) reaction
Neutron and gamma-ray spectra calculated with TNG/4/.
MT= 17 (n,3n) reaction
Neutron calculated with TNG/4/. Gamma-ray channel is not open.
MT= 22 (n,na) reaction
Neutron, alpha-particle, and gamma-ray spectra calculated with
TNG/4/.
MT= 28 (n,np) reaction
Neutron, proton, and gamma-ray spectra calculated with TNG/4/.
MT= 51-89 (n,n') reaction
Neutron angular distributions and discrete gamma-ray spectra
calculated with TNG/4/.
MT= 91 (n,n') reaction
Neutron spectra, and discrete-continuous gamma-ray spectra
calculated with with TNG/4/.
MT= 102
Calculated with the TNG code /4/.
MT= 600-634 (n,p) reactions leading to discrete levels
Proton angular distributions and discrete gamma-ray spectra
calculated with TNG/4/.
MT= 649 (n,p) reaction leading to continuum levels
Proton spectra and discrete-continuous gamma-ray spectra
calculated with TNG/4/.
MT= 800-839 (n,a) reactions leading to discrete levels
Alpha-particle angular distributions and gamma-ray spectra
calculated with TNG/4/.
MT= 849 (n,a) reaction leading to continuum levels
Alpha-particle spectra and discrete-continuous gamma-ray
spectra calculated with TNG/4/.
< Appendix >
******************************************************************
* Nuclear Model Calcualtions with TNG Code /4/ *
******************************************************************
The description of the model calculations is given in Ref.3.
< Optical model parameters >
Neutron and protons:
Koning and Delaroche /5/
Alphas:
The potential parameters were obtained using the code developed
by Kumar and Kailas./6/
< Level scheme of Ca- 43 >
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 7/2 -
1 0.37280 5/2 -
2 0.59340 3/2 -
3 0.99030 3/2 +
4 1.39450 5/2 +
5 1.67780 11/2 -
6 1.90180 7/2 +
7 1.93130 5/2 -
8 1.95740 1/2 +
9 2.04630 3/2 -
10 2.06730 7/2 -
11 2.09390 9/2 -
12 2.10270 3/2 -
13 2.22400 3/2 -
14 2.24900 9/2 -
15 2.27270 5/2 +
16 2.40980 9/2 +
17 2.52300 9/2 -
18 2.61100 1/2 -
19 2.67370 7/2 -
20 2.69690 5/2 +
21 2.75300 1/2 +
22 2.75400 15/2 -
23 2.76970 1/2 +
24 2.84570 9/2 +
25 2.87800 1/2 -
26 2.94320 3/2 -
27 2.95140 11/2 +
28 3.02860 5/2 +
29 3.04940 7/2 +
30 3.05050 11/2 -
31 3.07590 5/2 +
32 3.09610 1/2 -
33 3.09710 5/2 +
34 3.19630 7/2 +
35 3.27800 7/2 +
36 3.28570 3/2 -
37 3.31530 3/2 -
38 3.37130 13/2 +
39 3.37700 5/2 -
The direct-reaction process was taken into account for the 5th,
7th, 9th, 10th, and 11th levels by DWBA.
< Level density parameters >
Energy dependent parameters of Mengoni-Nakajima /7/ were used.
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Econt
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
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
Ca- 41 6.285 1.874 -0.149 1.397 -0.507 9.227 4.728
K - 43 6.062 1.830 2.010 1.410 -1.729 10.733 3.393
K - 42 6.253 0.000 1.255 1.396 -3.279 8.501 2.251
Ar- 40 5.998 3.795 1.822 1.464 -0.092 13.254 5.378
Ar- 39 6.455 1.922 1.140 1.228 -0.117 8.268 4.178
----------------------------------------------------------
References
1) Mughaghab S.F. et al.:"Neutron Cross Sections", Vol. 1, Part
A (1981).
2) Moxon, M.C. et al.: Phys. Rev., C48, 553 (1993).
3) Shibata, K: J. Nucl. Sci. Technol., 44, 10 (2007).
4) Fu, C.Y.: ORNL/TM-7042 (1980); Shibata, K., Fu, C.Y.: ORNL/TM-
10093.
5) Koning, A.J., Delaroche, J.P.: Nucl. Phys., A713, 231 (2003).
6) Kumar, A., Kailas, S: a computer code contained in RIPL-2,
private communication (2002).
7) Mengoni, A., Nakajima, Y. Nucl. Sci. Technol., 31, 151 (1994).