38-Sr- 88 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda
DIST-JAN15 20140703
----JENDL-4.0u1 MATERIAL 3837
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
Update File Distribution
Jan.22,2015 JENDL-4.0u1
History
09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda.
09-11 Compiled by K. Shibata.
14-07 It was found that some of the neutron widths in the resolved
resonances were underestimated mistakenly and that the
265.06-keV resonance was not considered. Modification was
made to resolve these problems. Moreover, the gamma width
at a negative resonance was re-adjusted.
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 300 keV
Resolved resonance parameters were taken from the work of
Koehler et al./1/ The new evaluation does not contains
the resonances at 2.780 keV and 12.70 keV which existed in
JENDL-3.3. The former resonance, which were observed only
by Adamchuk et al./2/, is possibly attributed to Sr-87.
A negative resonance was added so as to reproduce the
thermal capture cross section recommended by Mughabghab.
/3/
Unresolved resonance region: 300 keV - 1 MeV
The parameters were obtained by fitting to the total and
capture cross sections calculated from POD /4/. 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 5.5994E+00
Elastic 5.5936E+00
n,gamma 5.8014E-03 3.1278E-02
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Calculated with POD code /4/.
MT= 2 Elastic scattering cross section
Obtained 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 /4/.
MT= 16 (n,2n) cross section
Calculated with POD code /4/.
MT= 22 (n,na) cross section
Calculated with POD code /4/.
MT= 28 (n,np) cross section
Calculated with POD code /4/.
MT=102 Capture cross section
Calculated with POD code /4/.
MT=103 (n,p) cross section
Calculated with POD code /4/.
MT=104 (n,d) cross section
Calculated with POD code /4/.
MT=105 (n,t) cross section
Calculated with POD code /4/.
MT=106 (n,He3) cross section
Calculated with POD code /4/.
MT=107 (n,a) cross section
Calculated with POD code /4/.
MT=203 (n,xp) cross section
Calculated with POD code /4/.
MT=204 (n,xd) cross section
Calculated with POD code /4/.
MT=205 (n,xt) cross section
Calculated with POD code /4/.
MT=206 (n,xHe3) cross section
Calculated with POD code /4/.
MT=207 (n,xa) cross section
Calculated with POD code /4/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with POD code /4/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Neutron spectra calculated with POD/4/.
MT= 22 (n,na) reaction
Neutron spectra calculated with POD/4/.
MT= 28 (n,np) reaction
Neutron spectra calculated with POD/4/.
MT= 51 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 52 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 53 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 54 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 55 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 56 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 57 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 58 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 59 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 60 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 61 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 62 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 63 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 64 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 65 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 66 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 67 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 68 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 69 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 70 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 71 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 72 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 73 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 74 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 75 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 76 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 77 (n,n') reaction
Neutron angular distributions calculated with POD/4/.
MT= 91 (n,n') reaction
Neutron spectra calculated with POD/4/.
MT= 203 (n,xp) reaction
Proton spectra calculated with POD/4/.
MT= 204 (n,xd) reaction
Deuteron spectra calculated with POD/4/.
MT= 205 (n,xt) reaction
Triton spectra calculated with POD/4/.
MT= 206 (n,xHe3) reaction
He3 spectra calculated with POD/4/.
MT= 207 (n,xa) reaction
Alpha spectra calculated with POD/4/.
MF=12 Gamma-ray multiplicities
MT= 3 Non-elastic gamma emission
Calculated with POD code /4/.
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 /4/.
***************************************************************
* Nuclear Model Calculations with POD Code /4/ *
***************************************************************
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 /5/
Protons:
Koning and Delaroche /6/
Deuterons:
Lohr and Haeberli /7/
Tritons:
Becchetti and Greenlees /8/
He-3:
Becchetti and Greenlees /8/
Alphas:
Lemos /9/ potentials modified by Arthur and Young /10/
3. Level scheme of Sr- 88
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 0 +
1 1.83609 2 +
2 2.73414 3 -
3 3.15200 0 +
4 3.21851 2 +
5 3.48656 2 +
6 3.52294 2 +
7 3.58478 5 -
8 3.63511 2 +
9 3.95264 5 -
10 3.99300 1 -
11 4.01964 5 -
12 4.03560 2 +
13 4.03907 2 +
14 4.17042 3 -
15 4.17100 6 +
16 4.22410 4 +
17 4.22724 3 +
18 4.26871 2 +
19 4.29966 4 +
20 4.35500 1 -
21 4.36824 7 -
22 4.41395 2 +
23 4.44077 5 +
24 4.45202 4 +
25 4.48500 0 +
26 4.51402 2 -
27 4.51453 3 +
-------------------------
Levels above 4.52453 MeV are assumed to be continuous.
4. Level density parameters
Energy-dependent parameters of Mengoni-Nakajima /11/ were used
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Elv_max
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
Sr- 89 10.955 1.272 -0.954 0.720 1.043 4.477 3.524
Sr- 88 11.476 2.558 -1.509 0.753 2.134 6.189 4.515
Sr- 87 12.367 1.287 -0.021 0.633 0.786 4.453 2.596
Sr- 86 11.310 2.588 0.767 0.818 0.770 8.345 3.056
Rb- 88 10.406 0.000 -0.431 0.771 -0.492 3.809 1.916
Rb- 87 10.932 1.287 -0.777 0.871 -0.070 6.722 2.414
Rb- 86 9.932 0.000 0.007 0.898 -1.348 5.547 1.738
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
----------------------------------------------------------
5. Gamma-ray strength functions
M1, E2: Standard Lorentzian (SLO)
E1 : Generalized Lorentzian (GLO) /12/
6. Preequilibrium process
Preequilibrium is on for n, p, d, t, He-3, and alpha.
Preequilibrium capture is on.
References
1) P.E.Koehler et al., Phys. Rev., C62, 055803 (2000).
2) Yu.V.Adamchuk et al., Euoronuclear 2, 183 (1965).
3) S.F.Mughabghab, "Atlas of Neutron Resonances", Elsevier
(2006).
4) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).
5) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).
6) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).
7) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).
8) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization
Phenomena in Nuclear Reactions," p.682, The University
of Wisconsin Press (1971).
9) O.F.Lemos, Orsay Report, Series A, No.136 (1972).
10) E.D.Arthur, P.G.Young, LA-8626-MS (1980).
11) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151
(1994).
12) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).