33-As- 75 JAEA EVAL-APR09 K.Shibata, G.Chiba, A.Ichihara+
DIST-MAY10 20100107
----JENDL-4.0 MATERIAL 3325
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-04 Evaluated by K.Shibata, G.Chiba, A.Ichihara, and S.Kunieda.
10-01 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 9.7 keV
Resonance parameters for the 39 levels from 47.0 to 2616 eV
were evaluated on the basis of the data given by Mughabghab
et al./1/ Resonance energies for the 210 levels from 2676
to 11960 eV were based on the measurement by Macklin/2/.
Neutron and radiation widths for the 210 levels were
determined by different methods according to the following
three conditions, respectively.
1) In cases where total width and neutron capture area
measured by macklin are given for a resonance level, the
neutron and radiation widths were simultaneously obtained by
solving a quadratic equation.
2) In cases where neutron capture area measured by Macklin
and 2g*(neutron width) given by Mughabghab et al. are
available for a resonance level, the radiation widths were
derived from the both data.
3) In cases where only neutron capture area by Macklin is
available, or g*(neutron width) by Mughabghab et al. is
smaller than neutron capture area by Macklin for a resonance
level, the average radiation width of 318 meV given by
Macklin was adopted for the level. The neutron width was
derived from this average radiation width and the neutron
capture area.
Neutron orbital angular momentum l of some resonances was
estimated with a method of Bollinger and Thomas/3/. Total
spin j of some resonances was tentatively estimated with a
random number method. Scattering radius was taken from
Mughabghab et al. Two negative resonances were added so as
to reproduce the thermal capture and scattering cross
sections given by Mughabghab et al.
In JENDL-4, the energy of a negative resonace was changed
to 100 meV so as to reproduce the thermal capture cross
section measured by Mustafa Karadag et al./4/
Unresolved resonance region: 9.7 keV - 500 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 9.6199E+00
Elastic 5.4673E+00
n,gamma 4.1525E+00 6.3735E+01
----------------------------------------------------------
(*) 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
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 /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
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= 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= 77 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 78 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 79 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 80 (n,n') reaction
Neutron angular distributions calculated with POD/5/.
MT= 91 (n,n') reaction
Neutron spectra calculated with POD/5/.
A giant resonance was considered at an excitation energy of
2.8 MeV and it was broadened with a Gaussina distribution with
FWHM=1.41 MeV.
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 As- 75
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 3/2 -
1 0.19861 1/2 -
2 0.26466 3/2 -
3 0.27954 5/2 -
4 0.30392 9/2 +
5 0.40066 5/2 +
6 0.46860 1/2 -
7 0.57222 5/2 -
8 0.58500 3/2 -
9 0.61770 3/2 -
10 0.82156 7/2 -
11 0.85990 1/2 +
12 0.86480 1/2 -
13 0.88600 3/2 +
14 1.04180 7/2 -
15 1.06430 3/2 -
16 1.07560 3/2 -
17 1.08040 5/2 +
18 1.09550 7/2 -
19 1.10100 1/2 -
20 1.12770 1/2 +
21 1.12800 1/2 -
22 1.17160 11/2 +
23 1.20450 3/2 -
24 1.26310 1/2 +
25 1.30120 5/2 +
26 1.30900 5/2 -
27 1.34930 3/2 -
28 1.37000 3/2 -
29 1.41980 5/2 -
30 1.43030 3/2 +
-------------------------
Levels above 1.44030 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
----------------------------------------------------------
As- 76 9.954 0.000 3.702 0.933 -3.511 8.279 0.669
As- 75 9.648 1.386 3.768 0.921 -1.771 9.165 1.430
As- 74 9.955 0.000 3.777 0.902 -3.209 7.736 0.776
As- 73 9.432 1.404 3.632 1.014 -2.603 10.639 1.344
Ge- 75 9.958 1.386 3.393 0.852 -1.123 8.044 1.603
Ge- 74 9.691 2.790 3.220 0.910 -0.065 10.140 2.711
Ge- 73 10.618 1.404 3.764 0.886 -2.153 9.468 0.994
Ga- 73 9.432 1.404 3.322 0.797 -0.248 6.711 1.528
Ga- 72 9.658 0.000 3.408 0.897 -2.795 7.185 0.684
Ga- 71 9.215 1.424 3.011 0.843 -0.395 7.131 2.396
----------------------------------------------------------
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) S.F.Mughabghab et al., Neutron Cross Sections, Vol.1,
Part A, (1981).
2) R.L.Macklin, Nucl. Sci. Eng. 99, 133 (1988).
3) L.M.Bollinger, G.E.Thomas, Phys. Rev., 171,1293(1968).
4) Mustafa Karadag et al., Nucl. Phys., A501, 524 (2003).
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).