36-Kr- 86 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda
DIST-MAY10 20091004
----JENDL-4.0 MATERIAL 3649
-----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 640 keV
Evaluation of resonance energies, neutron widths, neutron
orbital angular momentum L and total spin J was based on the
data measured by Carlton et al./1/ and by Raman et al.
/2/ Radiation widths for the 12 resonance levels in the
energy range from 19.238 to 88.329 keV were taken from the
data by Raman et al. The value of average radiation width
was determined so that the average capture cross section
around 640 keV might agree with that calculated by CASTHY
/3/, and thus obtained average radiation width was adopted
for the resonance levels whose radiation width was unknown.
Scattering radius was taken from the graph (Fig. 1, part A)
given by Mughabghab et al./4/ A negative resonance was
added at -20 keV so as to reproduce the thermal capture
cross section of 3 mb given by Mughabghab et al.
No unresolved resonance region is given.
Thermal cross sections and resonance integrals at 300 K
----------------------------------------------------------
0.0253 eV res. integ. (*)
(barns) (barns)
----------------------------------------------------------
Total 6.1895E+00
Elastic 6.1865E+00
n,gamma 3.0006E-03 2.3182E-02
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Calculated with POD code /5/.
MT= 2 Elastic scattering cross section
Obtanined by subtracting non-elastic cross sections 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 /5/.
MT= 16 (n,2n) cross section
Calculated with POD code /5/.
MT= 17 (n,3n) cross section
Calculated with POD code /5/.
MT= 22 (n,na) cross section
Calculated with POD code /5/.
MT= 28 (n,np) cross section
Calculated with POD code /5/.
MT=102 Capture cross section
Calculated with POD code /5/.
MT=103 (n,p) cross section
Calculated with POD code /5/.
MT=104 (n,d) cross section
Calculated with POD code /5/.
MT=105 (n,t) cross section
Calculated with POD code /5/.
MT=106 (n,He3) cross section
Calculated with POD code /5/.
MT=107 (n,a) cross section
Calculated with POD code /5/.
MT=203 (n,xp) cross section
Calculated with POD code /5/.
MT=204 (n,xd) cross section
Calculated with POD code /5/.
MT=205 (n,xt) cross section
Calculated with POD code /5/.
MT=206 (n,xHe3) cross section
Calculated with POD code /5/.
MT=207 (n,xa) cross section
Calculated with POD code /5/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with POD code /5/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Neutron spectra calculated with POD/5/.
MT= 17 (n,3n) reaction
Neutron spectra calculated with POD/5/.
MT= 22 (n,na) reaction
Neutron spectra calculated with POD/5/.
MT= 28 (n,np) reaction
Neutron spectra calculated with POD/5/.
MT= 51 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 52 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 53 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 54 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 55 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 56 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 57 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 58 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 59 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 60 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 61 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 62 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 91 (n,n') reaction
Neutron spectra calculated with POD/5/.
MT= 203 (n,xp) reaction
Proton spectra calculated with POD/5/.
MT= 204 (n,xd) reaction
Deuteron spectra calculated with POD/5/.
MT= 205 (n,xt) reaction
Triton spectra calculated with POD/5/.
MT= 206 (n,xHe3) reaction
He3 spectra calculated with POD/5/.
MT= 207 (n,xa) reaction
Alpha spectra calculated with POD/5/.
MF=12 Gamma-ray multiplicities
MT= 3 Non-elastic gamma emission
Calculated with POD code /5/.
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 /5/.
***************************************************************
* Nuclear Model Calculations with POD Code /5/ *
***************************************************************
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 /6/
Protons:
Koning and Delaroche /7/
Deuterons:
Lohr and Haeberli /8/
Tritons:
Becchetti and Greenlees /9/
He-3:
Becchetti and Greenlees /9/
Alphas:
Lemos /10/ potentials modified by Arthur and Young /11/
3. Level scheme of Kr- 86
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 0 +
1 1.56487 2 +
2 2.25017 4 +
3 2.34993 2 +
4 2.72400 0 +
5 2.85077 2 +
6 2.92652 2 +
7 3.01100 1 +
8 3.09928 3 -
9 3.32200 4 +
10 3.33000 4 +
11 3.54000 0 +
12 3.57500 5 -
-------------------------
Levels above 3.58500 MeV are assumed to be continuous.
4. Level density parameters
Energy-dependent parameters of Mengoni-Nakajima /12/ were used
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Elv_max
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
Kr- 87 12.111 1.287 -0.112 0.649 0.793 4.518 3.172
Kr- 86 11.310 2.588 -0.507 0.715 2.085 6.130 3.575
Kr- 85 11.890 1.302 0.718 0.695 0.285 5.433 2.637
Kr- 84 11.089 2.619 1.235 0.745 1.364 7.286 3.951
Br- 86 11.279 0.000 0.170 0.829 -1.635 5.577 0.207
Br- 85 10.720 1.302 -0.138 0.819 0.183 6.155 1.944
Br- 84 11.060 0.000 0.608 0.898 -2.409 6.862 0.408
Se- 84 11.089 2.619 -0.251 0.922 0.380 9.391 2.716
Se- 83 12.088 1.317 0.801 0.772 -0.514 6.837 1.331
Se- 82 10.867 2.650 1.071 0.699 1.874 6.455 3.586
----------------------------------------------------------
5. Gamma-ray strength functions
M1, E2: Standard Lorentzian (SLO)
E1 : Generalized Lorentzian (GLO) /13/
6. Preequilibrium process
Preequilibrium is on for n, p, d, t, He-3, and alpha.
Preequilibrium capture is on.
References
1) R.F.Carlton et al., Phys. Rev. C 38, 1605 (1988).
2) S.Raman et al., Phys. Rev. C 28, 602 (1983).
3) S.Igarasi, J. Nucl. Sci. Technol., 12, 67 (1975).
4) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I,
Part A", Academic Press (1981).
5) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).
6) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).
7) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).
8) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).
9) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization
Phenomena in Nuclear Reactions," p.682, The University
of Wisconsin Press (1971).
10) O.F.Lemos, Orsay Report, Series A, No.136 (1972).
11) E.D.Arthur, P.G.Young, LA-8626-MS (1980).
12) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151
(1994).
13) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).