39-Y - 91 JAEA EVAL-NOV09 A.Ichihara, K.Shibata, S.Kunieda+
DIST-MAY10 20100209
----JENDL-4.0 MATERIAL 3931
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-11 Compiled by A.Ichihara
MF= 1 General information
MT=451 Descriptive data and directory
Cross sections were calculated with the POD code/1/ in
the neutron energy range from 300 eV to 20 MeV.
Cross sections below 300 eV were taken from JENDL-3.3.
In JENDL-3.3, the capture and elastic scattering cross sections
were assumed to be in 1/v form and constant, respectively.
The capture cross section at 0.0253 eV was adopted from /2/.
The scattering cross section was calculated from R = 6.7 fm.
MF= 2 Resonance parameters
MT=151 Unresolved resonance region : 300 eV - 200 keV
The unresolved resonance parameters were calculated using
the ASREP code/3/.
The 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 7.1488E+00
Elastic 5.7323E+00
n,gamma 1.4005E+00 3.7661E+00
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Calculated with POD code /1/.
MT= 2 Elastic scattering cross section
Calculated as (total - sum of partial cross sections).
MT= 3 Non-elastic cross section
Calculated as sum of partial cross sections.
MT= 4,51-91 (n,n') cross section
Calculated with POD code /1/.
MT= 16 (n,2n) cross section
Calculated with POD code /1/.
MT= 17 (n,3n) cross section
Calculated with POD code /1/.
MT= 22 (n,na) cross section
Calculated with POD code /1/.
MT= 28 (n,np) cross section
Calculated with POD code /1/.
MT= 32 (n,nd) cross section
Calculated with POD code /1/.
MT=102 Capture cross section
Calculated with POD code /1/.
MT=103 (n,p) cross section
Calculated with POD code /1/.
MT=104 (n,d) cross section
Calculated with POD code /1/.
MT=105 (n,t) cross section
Calculated with POD code /1/.
MT=106 (n,He3) cross section
Calculated with POD code /1/.
MT=107 (n,a) cross section
Calculated with POD code /1/.
MT=203 (n,xp) cross section
Calculated with POD code /1/.
MT=204 (n,xd) cross section
Calculated with POD code /1/.
MT=205 (n,xt) cross section
Calculated with POD code /1/.
MT=206 (n,xHe3) cross section
Calculated with POD code /1/.
MT=207 (n,xa) cross section
Calculated with POD code /1/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with POD code /1/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Neutron spectra calculated with POD/1/.
MT= 17 (n,3n) reaction
Neutron spectra calculated with POD/1/.
MT= 22 (n,na) reaction
Neutron spectra calculated with POD/1/.
MT= 28 (n,np) reaction
Neutron spectra calculated with POD/1/.
MT= 32 (n,nd) reaction
Neutron spectra calculated with POD/1/.
MT= 51 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 52 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 53 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 54 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 55 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 56 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 57 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 58 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 59 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 60 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 61 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 62 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 63 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 64 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 65 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 66 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 67 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 68 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 69 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 70 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 71 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 72 (n,n') reaction
Neutron angular distributions calculated with POD/1/.
MT= 91 (n,n') reaction
Neutron spectra calculated with POD/1/.
MT= 203 (n,xp) reaction
Proton spectra calculated with POD/1/.
MT= 204 (n,xd) reaction
Deuteron spectra calculated with POD/1/.
MT= 205 (n,xt) reaction
Triton spectra calculated with POD/1/.
MT= 206 (n,xHe3) reaction
He3 spectra calculated with POD/1/.
MT= 207 (n,xa) reaction
Alpha spectra calculated with POD/1/.
MF=12 Gamma-ray multiplicities
MT= 3 Non-elastic gamma emission
Calculated with POD code /1/.
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 /1/.
***************************************************************
* Nuclear Model Calculations with POD Code /1/ *
***************************************************************
1. Theoretical models
The POD code is based on the spherical optical model, the
distorted-wave Born approximation (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:
Koning and Delaroche /4/
Protons:
Koning and Delaroche /4/
The radius parameter r_V = 1.25 fm was used in the calculation.
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/.
The radius parameters r_V = r_I = 1.40 fm were used in the
calculation.
3. Level scheme of Y - 91
Nuclear discrete levels were obtained from RIPL-2/9/.
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 1/2 -
1 0.55558 9/2 +
2 0.65303 3/2 -
3 0.92575 5/2 -
4 1.18689 7/2 -
5 1.30540 5/2 +
6 1.47370 3/2 -
7 1.54591 5/2 -
8 1.54800 7/2 -
9 1.57994 7/2 +
10 1.98042 3/2 -
11 2.06663 5/2 +
12 2.12910 3/2 +
13 2.16300 3/2 -
14 2.20676 5/2 -
15 2.27935 7/2 -
16 2.41220 3/2 -
17 2.47400 3/2 -
18 2.53000 5/2 -
19 2.57000 1/2 -
20 2.57214 7/2 -
21 2.63100 5/2 -
22 2.68900 7/2 -
-------------------------
Levels above 2.69900 MeV are assumed to be continuous.
4. Level density parameters
Energy-dependent parameters of Mengoni-Nakajima /10/ were used
---------------------------------------------------
Nuclei a* Pair T E0 Ematch Elv_max
1/MeV MeV MeV MeV MeV MeV
---------------------------------------------------
Y - 92 11.929 0.000 0.493 0.199 1.501 2.900
Y - 91 11.338 1.258 0.772 0.115 5.977 2.689
Y - 90 10.454 0.000 0.865 -0.779 4.677 2.624
Y - 89 11.127 1.272 0.682 1.455 3.665 4.023
Sr- 91 12.543 1.258 0.625 0.591 4.649 4.249
Sr- 90 11.748 2.530 0.778 1.141 7.584 3.627
Sr- 89 10.953 1.272 0.720 1.044 4.474 4.050
Rb- 89 11.127 1.272 0.818 -0.434 6.915 1.999
Rb- 88 10.411 0.000 0.994 -2.333 7.292 1.964
Rb- 87 10.916 1.287 0.895 -0.274 7.103 3.099
---------------------------------------------------
5. Gamma-ray strength functions
M1, E2: Standard Lorentzian (SLO)
E1 : Standard Lorentzian (SLO) /11/
The position and width parameters in the E1
radiation were taken from the tabulation of
Dietrich and Berman/12/.
6. Preequilibrium process
Preequilibrium is on for n, p, d, t, He-3, and alpha.
The single particle state density parameters were
7.390, 6.958, 7.877, 6.188, 7.202, 5.500, 7.059 (MeV^-1)
for Y-92, Y-91, Sr-91, Rb-88, Sr-90, Sr-89, and Rb-89.
Effects of the particle pickup (and knockout for alpha) were
estimated using the semi-empirical formulas by Kalbach/13/.
These components were multiplied by a factor of two and
added to the statistical model calculation.
Preequilibrium capture is on (the parameters were obtained
from /12/).
References
1) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).
2) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I,
Part A," Academic Press (1981).
3) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)
[in Japanese].
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) T.Belgya et al., IAEA-TECDOC-1506 (2006).
10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151
(1994).
11) M.Brink, Ph.D thesis, Oxford University, 1955.
12) S.S.Dietrich, B.L.Berman, Atom. Data Nucl. Data Tables,
38, 199 (1988).
13) C.Kalbach, Z. Phys. A283, 401 (1977).