42-Mo- 95 JAEA EVAL-MAR09 K.Shibata, A.Ichihara, S.Kunieda+
DIST-MAY10 20091215
----JENDL-4.0 MATERIAL 4234
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-03 The data above the resolved resonance region were evaluated
by K.Shibata, A.Ichihara, and S.Kunieda /1/.
The resolved resonance parameters were evaluated by
T.Nakagawa.
09-12 Compiled by K.Shibata
MF= 1 General information
MT=451 Descriptive data and directory
MF= 2 Resonance parameters
MT=151 Resolved and unresolved resoannce parameters
Resolved resonance region: below 2 keV
Based on the experimental data of Shwe et al./2/, Weigmann
et al./3/, and Wang et al./4/
Unresolved resonance region: 2 keV - 400 keV
The parameters were obtained by fitting to the total and
capture cross sections calculated from POD /5/. 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 2.0102E+01
Elastic 6.4979E+00
n,gamma 1.3604E+01 1.0181E+02
n,alpha 3.0740E-05
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Sum of partial cross sections.
MT= 2 Elastic scattering cross section
Originally, the POD calculations were adopted. After
considering the benchmark results with molybdenum reflectors
for fast neutrons, the data were replaced with the JENDL-3.3
cross sections above 600 keV.
MT= 3 Non-elastic cross section
Sum of partial nonelastic 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= 32 (n,nd) 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
Below 2 keV, the cross section was calculated using the
resonance parameters given by Rapp et al./6/ The negative
resonance parameters were adjusted so as to reproduce the
experimental data measured by D'hondt et al./7/. The
average cross sections measured by Rapp et al. were used
between 2 keV and 500 keV. The cross section was calculated
with POD code /5/ above 500 keV.
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/ below 1 MeV. Above 1 MeV, the
data were taken from JENDL-3.3 by considering the benchmark
results with molybdenum reflectors for fast neutrons.
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= 32 (n,nd) 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= 63 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 64 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 65 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 66 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 67 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 68 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 69 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 70 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 71 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 72 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 73 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 74 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 75 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 76 (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 /8/
Protons:
Koning and Delaroche /9/
Deuterons:
Lohr and Haeberli /10/
Tritons:
Becchetti and Greenlees /11/
He-3:
Becchetti and Greenlees /11/
Alphas:
Lemos /12/ potentials modified by Arthur and Young /13/
3. Level scheme of Mo- 95
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 5/2 +
1 0.20412 3/2 +
2 0.76580 7/2 +
3 0.78620 1/2 +
4 0.82063 3/2 +
5 0.94768 9/2 +
6 1.03927 1/2 +
7 1.05676 5/2 +
8 1.07372 7/2 +
9 1.09200 3/2 +
10 1.30259 1/2 +
11 1.32400 3/2 +
12 1.36973 3/2 +
13 1.37601 9/2 +
14 1.42613 5/2 +
15 1.44050 9/2 -
16 1.54079 11/2 +
17 1.55172 9/2 +
18 1.62022 3/2 +
19 1.64510 7/2 +
20 1.66029 3/2 +
21 1.66600 7/2 +
22 1.68300 7/2 +
23 1.69800 1/2 +
24 1.74326 9/2 +
25 1.79666 11/2 +
26 1.80824 7/2 +
-------------------------
Levels above 1.81824 MeV are assumed to be continuous.
4. Level density parameters
Energy-dependent parameters of Mengoni-Nakajima /14/ were used
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Elv_max
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
Mo- 96 13.196 2.449 1.024 0.752 0.273 8.413 2.818
Mo- 95 13.125 1.231 0.096 0.761 -0.609 6.814 1.808
Mo- 94 12.185 2.475 -0.706 0.937 -0.368 10.169 2.853
Mo- 93 12.764 1.244 -1.843 0.892 -0.799 7.716 2.755
Nb- 95 11.759 1.231 1.730 0.720 -0.207 6.109 1.219
Nb- 94 12.820 0.000 0.583 0.682 -1.167 4.340 1.257
Nb- 93 11.549 1.244 0.114 0.953 -1.794 9.243 1.950
Zr- 93 12.411 1.244 0.480 0.758 -0.396 6.546 1.642
Zr- 92 11.702 2.502 -0.002 0.862 0.426 8.855 3.325
Zr- 91 11.895 1.258 -1.229 0.879 -0.489 7.274 3.167
----------------------------------------------------------
5. Gamma-ray strength functions
M1, E2: Standard Lorentzian (SLO)
E1 : Generalized Lorentzian (GLO) /15/
6. Preequilibrium process
Preequilibrium is on for n, p, d, t, He-3, and alpha.
Preequilibrium capture is on.
References
1) K.Shibata, A.Ichihara, S.Kunieda, J. Nucl. Sci. Technol.,
46, 278 (2009).
2) H. Shwe and R.E. Cote, Phys. Rev. 179, 1148 (1969).
3) H. Weigmann, et al., 1971 Knoxville, 749 (1971).
4) T.F. Wang et al., Nucl. Instrum. Meth. Phys. Research B, 266,
561 (2008).
5) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).
6) W. Rapp et al., Phys. Rev., C68, 015802 (2003).
7) D'hondt et al., 1982 Antwerp, 147 (1983).
8) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).
9) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).
10) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).
11) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization
Phenomena in Nuclear Reactions," p.682, The University
of Wisconsin Press (1971).
12) O.F.Lemos, Orsay Report, Series A, No.136 (1972).
13) E.D.Arthur, P.G.Young, LA-8626-MS (1980).
14) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151
(1994).
15) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).