36-Kr- 83 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda
DIST-MAY10 20091118
----JENDL-4.0 MATERIAL 3640
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda.
09-10 Compiled by K. Shibata.
MF= 1 General information
MT=451 Descriptive data and directory
MF= 2 Resonance parameters
MT=151 Resolved and unresolved resonance parameters
Resolved resonance region (MLBW formula) : below 0.272 keV
For JENDL-2, parameters were given for 2 positive and a
negative resonances on the basis of the data given by
Mughabghab et al./1/ Neutron orbital angular momentum L
were assumed to be 0. Neutron widths were modified so as to
reproduce the thermal capture cross section of 180+-30 barns
and the neutron resonance capture integral of 183+-25 barns
given by Mughabghab et al. Radiation width of 210 meV for
the first level/1/ was adopted for the other resonance
levels. However, the values of total spin j were unknown
and the target spin of 4.5 was adopted for all the levels.
For JENDL-3, the J-values of all resonance levels were
tentatively estimated with a random number method.
According to modification of the J-values, resonance
parameters were also modified so as to reproduce the thermal
capture cross section and the neutron resonance capture
integral mentioned above. Scattering radius was taken from
the graph (fig. 1, Part A) given by Mughabghab et al.
In JENDL-4, the radiation width of the negative resonance
was changed to 237 meV.
Unresolved resonance region: 272 eV - 260 keV
The parameters were obtained by fitting to the total and
capture cross sections calculated from POD /2/. The
unresolved parameters should be used only for self-shielding
calculation.
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 2.1147E+02
Elastic 9.1343E+00
n,gamma 2.0233E+02 1.5393E+02
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Calculated with POD code /2/.
MT= 2 Elastic scattering cross section
Obtained by subtracting non-elastic cross secitons from total
cross sections.
MT= 3 Non-elastic cross section
Sum of partial non-elastic cross sections.
MT= 4,51-91 (n,n') cross section
Calculated with POD code /2/.
MT= 16 (n,2n) cross section
Calculated with POD code /2/.
MT= 17 (n,3n) cross section
Calculated with POD code /2/.
MT= 22 (n,na) cross section
Calculated with POD code /2/.
MT= 28 (n,np) cross section
Calculated with POD code /2/.
MT= 32 (n,nd) cross section
Calculated with POD code /2/.
MT=102 Capture cross section
Calculated with POD code /2/.
MT=103 (n,p) cross section
Calculated with POD code /2/.
MT=104 (n,d) cross section
Calculated with POD code /2/.
MT=105 (n,t) cross section
Calculated with POD code /2/.
MT=106 (n,He3) cross section
Calculated with POD code /2/.
MT=107 (n,a) cross section
Calculated with POD code /2/.
MT=203 (n,xp) cross section
Calculated with POD code /2/.
MT=204 (n,xd) cross section
Calculated with POD code /2/.
MT=205 (n,xt) cross section
Calculated with POD code /2/.
MT=206 (n,xHe3) cross section
Calculated with POD code /2/.
MT=207 (n,xa) cross section
Calculated with POD code /2/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with POD code /2/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Neutron spectra calculated with POD/2/.
MT= 17 (n,3n) reaction
Neutron spectra calculated with POD/2/.
MT= 22 (n,na) reaction
Neutron spectra calculated with POD/2/.
MT= 28 (n,np) reaction
Neutron spectra calculated with POD/2/.
MT= 32 (n,nd) reaction
Neutron spectra calculated with POD/2/.
MT= 51 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 52 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 53 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 54 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 55 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 56 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 57 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 58 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 59 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 60 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 61 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 62 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 63 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 64 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 65 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 66 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 67 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 68 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 69 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 70 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 71 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 72 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 73 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 74 (n,n') reaction
Neutron angular distributions calculated with POD/2/.
MT= 91 (n,n') reaction
Neutron spectra calculated with POD/2/.
MT= 203 (n,xp) reaction
Proton spectra calculated with POD/2/.
MT= 204 (n,xd) reaction
Deuteron spectra calculated with POD/2/.
MT= 205 (n,xt) reaction
Triton spectra calculated with POD/2/.
MT= 206 (n,xHe3) reaction
He3 spectra calculated with POD/2/.
MT= 207 (n,xa) reaction
Alpha spectra calculated with POD/2/.
MF=12 Gamma-ray multiplicities
MT= 3 Non-elastic gamma emission
Calculated with POD code /2/.
MF=14 Gamma-ray angular distributions
MT= 3 Non-elastic gamma emission
Assumed to be isotropic.
MF=15 Gamma-ray spectra
MT= 3 Non-elastic gamma emission
Calculated with POD code /2/.
***************************************************************
* Nuclear Model Calculations with POD Code /2/ *
***************************************************************
1. Theoretical models
The POD code is based on the spherical optical model, the
distorted-wave Born approximaiton (DWBA), one-component exciton
preequilibrium model, and the Hauser-Feshbach-Moldauer statis-
tical model. With the preequilibrim model, semi-empirical
pickup and knockout process can be taken into account for
composite-particle emission. The gamma-ray emission from the
compound nucleus can be calculated within the framework of the
exciton model. The code is capable of reading in particle
transmission coefficients calculated by separate spherical or
coupled-channel optical model code.
2. Optical model parameters
Neutrons:
Coupled-channel optical model parameters /3/
Protons:
Koning and Delaroche /4/
Deuterons:
Lohr and Haeberli /5/
Tritons:
Becchetti and Greenlees /6/
He-3:
Becchetti and Greenlees /6/
Alphas:
Lemos /7/ potentials modified by Arthur and Young /8/
3. Level scheme of Kr- 83
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 9/2 +
1 0.00940 7/2 +
2 0.04154 1/2 -
3 0.56202 5/2 -
4 0.57120 3/2 -
5 0.69015 5/2 -
6 0.79890 5/2 +
7 0.81100 3/2 -
8 1.01186 11/2 +
9 1.10000 1/2 -
10 1.10289 9/2 +
11 1.12203 13/2 +
12 1.17040 7/2 -
13 1.22188 5/2 +
14 1.27790 1/2 +
15 1.51680 7/2 +
16 1.52916 9/2 -
17 1.53369 9/2 +
18 1.53810 7/2 -
19 1.64249 9/2 +
20 1.66800 7/2 -
21 1.72161 13/2 +
22 1.73847 11/2 +
23 1.78090 7/2 -
24 1.88890 7/2 -
-------------------------
Levels above 1.89890 MeV are assumed to be continuous.
4. Level density parameters
Energy-dependent parameters of Mengoni-Nakajima /9/ were used
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Elv_max
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
Kr- 84 11.089 2.619 1.235 0.745 1.364 7.286 3.951
Kr- 83 11.668 1.317 2.381 0.710 -0.316 6.290 1.889
Kr- 82 10.867 2.650 2.503 0.781 0.700 8.353 3.187
Kr- 81 11.444 1.333 3.305 0.766 -1.104 7.552 1.829
Br- 83 10.507 1.317 1.382 0.813 -0.276 6.734 2.134
Br- 82 10.599 0.000 2.092 0.832 -2.117 6.154 1.261
Br- 81 10.293 1.333 2.879 0.880 -1.411 8.480 1.587
Se- 81 10.589 1.333 1.999 0.755 -0.063 6.204 2.253
Se- 80 10.645 2.683 2.442 0.815 0.539 8.768 3.226
Se- 79 10.473 1.350 3.245 0.875 -1.656 8.768 0.729
----------------------------------------------------------
5. Gamma-ray strength functions
M1, E2: Standard Lorentzian (SLO)
E1 : Generalized Lorentzian (GLO) /10/
6. Preequilibrium process
Preequilibrium is on for n, p, d, t, He-3, and alpha.
Preequilibrium capture is on.
References
1) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,
Part A", Academic Press (1981).
2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).
3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).
4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).
5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).
6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization
Phenomena in Nuclear Reactions," p.682, The University
of Wisconsin Press (1971).
7) O.F.Lemos, Orsay Report, Series A, No.136 (1972).
8) E.D.Arthur, P.G.Young, LA-8626-MS (1980).
9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151
(1994).
10) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).