72-Hf-176 JAEA EVAL-JUL09 K. Shibata (JAEA)
DIST-MAY10 20091111
----JENDL-4.0 MATERIAL 7231
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
History
09-07 Evaluated by K. Shibata.
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 parameters (MLBW formula) : Below 700 eV
JENDL-3.3 was based on the compilation of Mughabghab./1/
In JENDL-4, the data below 177.1 eV were replaced with the
data obtained by Trbovich et al./2/.
Unresolved resonance region: 700 eV - 150 keV
The parameters were obtained by fitting to the total and
capture cross sections calculated from POD /3/. 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 2.7965E+01
Elastic 5.8262E+00
n,gamma 2.2139E+01 6.9898E+02
----------------------------------------------------------
(*) Integrated from 0.5 eV to 10 MeV.
MF= 3 Neutron cross sections
MT= 1 Total cross section
Calculated with POD code /3/.
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 /3/.
MT= 16 (n,2n) cross section
Calculated with POD code /3/.
MT= 17 (n,3n) cross section
Calculated with POD code /3/.
MT= 22 (n,na) cross section
Calculated with POD code /3/.
MT= 28 (n,np) cross section
Calculated with POD code /3/.
MT= 32 (n,nd) cross section
Calculated with POD code /3/.
MT=102 Capture cross section
Calculated with POD code /3/.
MT=103 (n,p) cross section
Calculated with POD code /3/.
MT=104 (n,d) cross section
Calculated with POD code /3/.
MT=105 (n,t) cross section
Calculated with POD code /3/.
MT=106 (n,He3) cross section
Calculated with POD code /3/.
MT=107 (n,a) cross section
Calculated with POD code /3/.
MT=203 (n,xp) cross section
Calculated with POD code /3/.
MT=204 (n,xd) cross section
Calculated with POD code /3/.
MT=205 (n,xt) cross section
Calculated with POD code /3/.
MT=206 (n,xHe3) cross section
Calculated with POD code /3/.
MT=207 (n,xa) cross section
Calculated with POD code /3/.
MF= 4 Angular distributions of emitted neutrons
MT= 2 Elastic scattering
Calculated with POD code /3/.
MF= 6 Energy-angle distributions of emitted particles
MT= 16 (n,2n) reaction
Neutron spectra calculated with POD/3/.
MT= 17 (n,3n) reaction
Neutron spectra calculated with POD/3/.
MT= 22 (n,na) reaction
Neutron spectra calculated with POD/3/.
MT= 28 (n,np) reaction
Neutron spectra calculated with POD/3/.
MT= 32 (n,nd) reaction
Neutron spectra calculated with POD/3/.
MT= 51 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 52 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 53 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 54 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 55 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 56 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 57 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 58 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 59 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 60 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 61 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 62 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 63 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 64 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 65 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 66 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 67 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 68 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 69 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 70 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 71 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 72 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 73 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 74 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 75 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 76 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 77 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 78 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 79 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 80 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 81 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 82 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 83 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 84 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 85 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 86 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 87 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 88 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 89 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 90 (n,n') reaction
Neutron angular distributions calculated with POD/3/.
MT= 91 (n,n') reaction
Neutron spectra calculated with POD/3/.
MT= 203 (n,xp) reaction
Proton spectra calculated with POD/3/.
MT= 204 (n,xd) reaction
Deuteron spectra calculated with POD/3/.
MT= 205 (n,xt) reaction
Triton spectra calculated with POD/3/.
MT= 206 (n,xHe3) reaction
He3 spectra calculated with POD/3/.
MT= 207 (n,xa) reaction
Alpha spectra calculated with POD/3/.
MF=12 Gamma-ray multiplicities
MT= 3 Non-elastic gamma emission
Calculated with POD code /3/.
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 /3/.
***************************************************************
* Nuclear Model Calculations with POD Code /3/ *
***************************************************************
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 /4/
Protons:
Koning and Delaroche /5/
Deuterons:
Lohr and Haeberli /6/
Tritons:
Becchetti and Greenlees /7/
He-3:
Becchetti and Greenlees /7/
Alphas:
Lemos /8/ potentials modified by Arthur and Young /9/
3. Level scheme of Hf-176
-------------------------
No. Ex(MeV) J PI
-------------------------
0 0.00000 0 +
1 0.08835 2 +
2 0.29018 4 +
3 0.59682 6 +
4 0.99774 8 +
5 1.14994 0 +
6 1.22663 2 +
7 1.24768 2 -
8 1.29312 0 +
9 1.31335 3 -
10 1.33306 6 +
11 1.34131 2 +
12 1.36200 1 +
13 1.37937 2 +
14 1.39019 4 +
15 1.40456 4 -
16 1.41293 4 -
17 1.44580 3 +
18 1.48107 10 +
19 1.50581 7 +
20 1.50857 5 -
21 1.53260 4 -
22 1.54030 4 +
23 1.55930 8 -
24 1.57756 3 +
25 1.59150 4 +
26 1.60700 8 -
27 1.62855 6 +
28 1.64343 1 -
29 1.65306 6 -
30 1.67234 1 +
31 1.67595 4 +
32 1.69991 8 +
33 1.70460 2 +
34 1.71043 3 -
35 1.72205 1 -
36 1.72780 5 +
37 1.73245 5 +
38 1.74900 0 +
39 1.76146 6 +
40 1.76689 4 +
-------------------------
Levels above 1.77689 MeV are assumed to be continuous.
4. Level density parameters
Energy-dependent parameters of Mengoni-Nakajima /10/ were used.
----------------------------------------------------------
Nuclei a* Pair Esh T E0 Ematch Elv_max
1/MeV MeV MeV MeV MeV MeV MeV
----------------------------------------------------------
Hf-177 20.775 0.902 1.759 0.533 -1.190 6.000 0.624
Hf-176 20.775 1.809 1.927 0.538 -0.407 7.077 1.767
Hf-175 20.255 0.907 2.027 0.481 -0.496 4.897 1.076
Hf-174 20.572 1.819 2.164 0.475 0.383 5.813 1.827
Lu-176 19.534 0.000 1.378 0.516 -1.470 4.263 0.659
Lu-175 19.850 0.907 1.723 0.499 -0.529 5.031 1.167
Lu-174 20.425 0.000 1.598 0.504 -1.597 4.342 0.561
Yb-174 20.077 1.819 1.456 0.506 0.310 6.070 2.037
Yb-173 19.765 0.912 1.401 0.553 -1.074 5.982 0.659
Yb-172 20.454 1.830 1.744 0.567 -0.670 7.581 1.720
----------------------------------------------------------
5. Gamma-ray strength functions
M1, E2: Standard Lorentzian (SLO)
E1 : Generalized Lorentzian (GLO) /11/
6. Preequilibrium process
Preequilibrium is on for n, p, d, t, He-3, and alpha.
Preequilibrium capture is on.
References
1) S.F.Mughabghab, Neutron Cross Sections, Vol.2, Part B,
(1984).
2) M.J.Trbovich et al., Nucl. Sci. Eng. 161, 303 (2009).
3) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).
4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).
5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).
6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).
7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization
Phenomena in Nuclear Reactions," p.682, The University
of Wisconsin Press (1971).
8) O.F.Lemos, Orsay Report, Series A, No.136 (1972).
9) E.D.Arthur, P.G.Young, LA-8626-MS (1980).
10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151
(1994).
11) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).