83-Bi-209
83-Bi-209 JAERI EVAL-MAY89 N.YAMAMURO,A.ZUKERAN,JENDL-3 C.G.
DIST-MAY10 20100302
----JENDL-4.0 MATERIAL 8325
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
89-04 Evaluation was performed for JENDL-3.
89-05 Compiled by K.Shibata and T.Narita (jaeri).
94-02 JENDL-3.2.
Compiled by T.Nakagawa (ndc/jaeri)
***** Modified parts for JENDL-3.2 ********************
(3,2), (3,4), (3,58) Around 3 MeV.
(4,16-91), (5,16-91) Taken from JENDL fusion file.
(12,102) From energy balance.
***********************************************************
-------------------------------------------------------------
JENDL fusion file /1/ (as of sep. 1993)
Evaluated and compiled by S. Chiba (ndc/jaeri)
Data were taken from JENDL-3.1 except for the following:
The neutron energy distributions of mt=16, 17, 22, 28
and 91 were replaced with calculated values with snicros-
II/2/. However, those of mt=16 and 91 above 17 MeV were
taken from JENDL-3.1 because they reproduced the data
measured by Matsuyama et al./3/ at 18 MeV better than the
sincros-II calculation. The angular distributions of
continuum neutrons were created by f15tob/1/. The MSD/MSC
ratio was taken from the sincros-II calculation, and
Kumabe's systematics/4/ was used.
Optical-model, level-density and other parameters used
in the sincros-ii calculation are described in ref./2/.
Level schemes were determined on the basis of ENSDF/5/.
-------------------------------------------------------------
01-09 JENDL-3.3
Compiled by K.Shibata (jaeri).
***** Modified parts for JENDL-3.3 **********************
(1,451) Updated.
(3,1) Re-calculated.
(3,2) Re-calculated.
(3,102) Revised above 200 keV.
(3,203-207) Calculated.
(3,251) Deleted.
(4,2) Tranformation matrix deleted.
(4,16-91) Deleted.
(5,16-91) Deleted.
(6,16-91) Taken from JENDL fusion file.
(6,203-207) Taken from JENDL fusion file.
***********************************************************
06-05 Covariances for MF/MT=33/4,33/51-62,33/91 were added by
K.Shibata.
10-01 JENDL-4.0
Compiled by K.Shibata and A.Ichihara (jaea).
***** Modified parts for JENDL-4.0 **********************
(1,451) Updated.
(2,151) Updated.
(3,102) Replaced by the POD calculation.
(8,102) Added.
(9,102) Calculated with the POD code.
***********************************************************
mf=1 General information
mt=451 Descriptive data and dictionary
mf=2 Resonance parameters
mt=151 Resolved resonance parameters for MLBW formula
Parameters were mainly taken from the work of Mughabghab
et al. /6/.
Resonance region : 1.0e-5 eV to 200 keV.
Scattering radius: 9.68 fm
*************************************************************
In JENDL-4.0, the resolved resonance parameters were upodated
by considering the data obtained by Domingo-Pardo et al./25/
A negative resonance was placed in order to reproduce the
thermal capture cross seciton recommended by Mughabghab./26/
*************************************************************
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 9.4242E+00
Elastic 9.3900E+00
n,gamma 3.4210E-02 1.715E-01
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
mf=3 Neutron cross sections
mt=1 Total
Below 200 keV : Background cross sections given between
30 kev and 200 keV.
200 keV to 20 MeV: Based on the experimental data
/7,8,9/.
mt=2 Elastic scattering
(total) - (reaction cross section)
mt=3 Non elastic
Sum of mt=4, 16, 17, 22, 28, 102, 103, 104, 107
mt=4,51-62,91 Inelastic scattering
Statistical model calculations were made with the sincros
system /2/ using the modified Walter-Guss potential
parameters for neutrons. For mt=51,52,58,62, the experi-
mental data of Smith et al./10/ were adopted below 5 MeV.
The calculated cross section of mt=91 was modified so as
to reproduce the measurements of the total inelastic cross
section below 8 MeV. The direct-process components were
considered for the levels of mt=51,52,58,91 by the DWBA
calculations.
The level scheme is given as follows:
no. energy(MeV) spin-parity
g.s. 0.0 9/2 -
1. 0.8964 7/2 -
2. 1.6085 13/2 +
3. 2.4300 1/2 +
4. 2.4920 3/2 +
5. 2.5645 9/2 +
6. 2.5830 7/2 +
7. 2.5990 11/2 +
8. 2.6017 13/2 +
9. 2.6170 5/2 +
10. 2.7411 15/2 +
11. 2.7660 5/2 +
12. 2.8220 5/2 -
Levels above 2.85 MeV were assumed to be overlapping.
mt=16,17,22,28,103,104,107 (n,2n),(n,3n),(n,n'a),(n,n'p),(n,p)
(n,d) and (n,a) cross sections
Calculated with sincros/2/. Optical potential parameters
for proton, alpha-particle and deuteron were taken from
the works of Perey/11/, Lemos/12/ and Lohr and Haeverli
/13/, respectively. The calculated (n,p) cross section
was multiplied by 0.3333 in order to fit to the
experimental data /14,15,16/ around 14 MeV.
mt=102 Radiative capture cross section
1.0e-5 eV to 200 keV: Resonance parameters given between
30 keV and 200 keV.
200 keV to 3 MeV: calculated with the casthy code/17/.
The calculation was normalized to
4 mb at 100 keV.
3 MeV to 20 MeV: Based on the measurements./18,19,20/.
******* For JENDL-3.3 **********************************
At 200 keV, a background cross section of 1.5 mb was set.
**********************************************************
******* For JENDL-4.0 **********************************
Cross sections above 200 keV were calculated by the POD
code /27/. The cross section was normalized to 1.42 mb
at 500 keV with the measured data by Saito et al./23,28/
**********************************************************
mt=203 : Total proton production
Sum of mt=28 and 103.
mt=204 : Total deuteron production
Equal to mt=104.
mt=207 : Total alpha production
Sum of mt=22 and 107.
mf=4 Angular distributions of secondary neutrons
mt=2,51-62
Calculated with casthy for equilibrium process.
the components of the direct process were added to
the levels of mt=51,52,58 by using the dwuck code /21/.
mf=6 Energy-angle distributions of secondary particles
mt=16, 17, 22, 28, 91
Based on Kumabe's systematics/1,4/.
mt=203,204,207
Based on Kalbach's systematics/1,22/.
mf=8 Radioactive nuclide production
mt=102
Decay data were taken from ENSDF.
mf=9 Multiplicities for production of radioactive elements
mt=102
The isomeric ratio in thermal region was obtained
from the table of Mughabghab /26/.
The ratio was calculated by the POD code for neutron
energies larger than 30 keV.
The calculated data at 30 keV is consistent with the
measured data by Saito et al. /29/
mf=12 Photon production multiplicities
mt=3 (above 200 keV)
Calculated with sincros.
mt=102 (below 200 keV)
Calculated from energy balance.
mf=14 Photon angular distributions
mt=3,102
Assumed to be isotropic.
mf=15 Photon energy distributions
mt=3,102
Calculated with sincros.
mf=33
mt=4
Sum up of mf/mt=33/51-91.
mt=51-63, 91
Covariances of statistical model calculations were
estimated on the kalman system/24/. Covariances of
optical model parameters were obtained by assuming 5%
standard deviations of calculated total cross sections.
Standard deviations of the target level density a and the
deforamtion parameters for DWBA were assumed to be 2% and
10%, respctviely.
References
1) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).
2) Yamamuro, N.: JAERI-M 90-006 (1990).
3) Matsuyama, S. et al.: JAERI-M 92-027, p.309 (1992).
4) Kumabe, I. et al.: Nucl. Sci. Eng., 104, 280 (1990).
5) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.
6) Mughabghab S.F.: "Neutron Cross Sections, Vol. 1, Part B",
Academic Press (1984).
7) Foster, Jr., D.G. and Glasgow, D.W.: Phys. Rev., C3, 576
(1971).
8) Smith, A.B., et al.: Nucl. Sci. Eng., 41, 63 (1970).
9) Cierjacks, S., et al.: "High Resolution Total Neutron
Cross-Sections between 0.5 and 30 MeV", KfK-1000, (1968).
10) Smith, A., et al.: Nucl. Sci. Eng., 75, 69 (1980).
11) Perey, F.G.: Phys. Rev. 131, 745 (1963).
12) Lemos, O.F.: "Diffusion Elastique de Particules Alpha de
21 a 29.6 MeV sur des Noyaux de la Region Ti-Zn", Orsay
report, Series A., No. 136, (1972).
13) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).
14) Coleman, R.F., et al.: Proc. Phys. Soc.(London), 73, 215
(1959).
15) Poularikas, A. and Fink, R.W.: Phys. Rev., 115, 989 (1959).
16) Belovitckij, G.E., et al.: Proc. 3rd All Union Conf. Neutron
Physics, Kiev, 1975, 4, 209 (1976).
17) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).
18) Budnar, M., et al.: "Prompt Gamma-ray Spectra and Integrated
Cross Sections for the Radiative Capture of 14 MeV neutrons
for 28 Natural Targets in the Mass Region from 12 to 208",
INDC(YUG)-6,(1979).
19) Csikai, J., et al.: Nucl. Phys., A95, 229 (1967).
20) Bergqvist, I., et al.: Nucl. Phys., A120, 161 (1968).
21) Kunz, P.D.: Univ. Colorado (1974).
22) Kalbach, C. and Mann, F.M.: Phys. Rev., C23, 112 (1981).
23) Saito, K., et al.: J. Nucl. Sci. Technol., 41, 406 (2004).
24) Kawano, T and Shibata, K.: "Covariance Evaluation System,"
JAERI-Data/Code 97-037 (1997) [in Japanese].
25) Domingo-Pardo, C., et al.: Phys. Rev., C74, 025807 (2006).
26) Mughabghab, S.F.: Atlas on Neutron Resonances, Elsevier,
(2006).
27) Ichihara, A., et al.: JAEA-Data/Code 2007-012 (2007).
28) Ichihara, A. and Shibata, K.: J. Nucl. Sci. Technol., 40, 980
(2003).
29) Saito, K., et al.: JAERI-Conf 2003-006, 133 (2003).