Back
66-Dy-162 ORNL, HEDL EVAL-OCT74 WRIGHT, SCHENTER, SCHMITTROTH
DIST-JAN09 20090105
----JEFF-311 MATERIAL 6643
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
******************************************************************
***************************** JEFF-3.1 *************************
** **
** Original data taken from: ENDF/B-VI.8 **
** **
******************************************************************
*****************************************************************
ENDF/B-VI MOD 1 Revision, April 1998, R.Q. Wright (ORNL)
MF= 2 RESONANCE PARAMETERS
RESOLVED RESONANCE RANGE
The upper limit of the resolved resonance range is increased
from 430.2 to 12200 eV. The number of resolved resonances is
increased from 8 to 142. The resonance parameters are taken
from Mughabghab [7].
UNRESOLVED RESONANCE RANGE 12.2 to 50 keV
The following parameters are used in this range:
S0 = 1.8E-4, S1 = 1.1E-4, D0 = 65 eV,
GG = 0.112 eV, GG/D0 = 17.23E-4,
Scattering radius, R = 7.82 fm
These parameters are based on Mughabghab [7] and RIPL [8].
Same scattering radius also used for resolved range.
MF= 3 SMOOTH CROSS SECTIONS
MT= 1 Total below 12.2 keV is much lower in the REVISED
evaluation relative to ENDF/B-V. Total cross section above
12.2 keV is revised to join smoothly at 12.2 keV. For all
dysprosium isotopes the total cross section is based on the
"eye guide" curve as given on page 546 of McLane [9].
MT= 2 The elastic scattering cross section is revised to
reflect the changes in the total and capture cross sections.
Elastic = Total - Nonelastic
MT=102 Capture is revised above 50 keV
For the energy range 16 to 500 keV the revision is based on
the measured data of Kononov [6]. Capture above 500 keV
is revised to join smoothly at 500 keV.
THERMAL CROSS SECTIONS AND CAPTURE RESONANCE INTEGRAL--
The revised thermal cross sections and the resonance integral
are compared with the values given by Mughabghab [7].
2200 m/sec cross sections (barns)
Evaluation Mughabghab
total 193.91 194.3
elastic 0.01 0.28 +/- 0.20
capture 193.90 194 +/- 10
Capture resonance integral, barns
Evaluation Mughabghab
2746 2755 +/- 270
*****************************************************************
ENDF/B-VI MOD 0, February 1990 (NNDC)
ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT.
*****************************************************************
ENDF/B-V Evaluation, MAT 9866, October 1974, R.E. Schenter and
F. Schmittroth (HEDL)
FILE INFORMATION
MF= 3 SMOOTH CROSS SECTIONS
MT= 1 Total cross section calculated using Moldauer
potential [4] for E > EH.
MT= 2 Elastic cross section from Total-Capture-Inelastic
for E > EH.
MT= 4,51,52,.,.,91 Inelastic cross sections calculated
using COMNUC-3 [5].
MT=102 Neutron capture evaluated using methods (NCAP code)
of Schmittroth [1,2] for E > EH. A 1/v component was added
to give the 2200 m/s cross section of Mughabghab [3] for
E < EH.
MF=4 ANGULAR DISTRIBUTIONS
MT= 2 Elastic angular distribution assumed isotropic.
Non-elastic angular distribution assumed isotropic.
MF=5 ENERGY DISTRIBUTION OF SECONDARY PARTICLES
MT= 91 Evaporation spectrum (LF=9) parameters obtained using
NCAP code [2].
****************************************************************
REFERENCES
1. F. Schmittroth and R.E. Schenter, report HEDL TME 73-63
(1973)
2. F. Schmittroth, report HEDL TME 73-79 (1973)
3. S.F. Mughabghab and D.I. Garber, report BNL 325, 3 Ed.,
Vol.1 (1973)
4. P.A. Moldauer, Nucl.Phys. 47, 65 (1963)
5. C.L. Dunford, report AI-AEC-12931 (1970) and private
communication
6. V. N. Kononov et al., Neutron-Capture Gamma-Ray Spectroscopy
and Related Topics, Symposium, September 1981, Grenoble,
France (Institute of Physics, 1982); data in EXFOR 40621.006
7. S.F. Mughabghab, Neutron Cross Sections, Vol. 1, Neutron
Resonance Parameters and Thermal Cross Sections, Part B
(Academic Press, 1984)
8. RIPL project, IAEA, Nuclear Data Project; web address:
//iaeand.iaea.or.at/ripl, select "resonances", then
"obninsk.dat".
Note: look under 66-Dy-161 (i.e., Dy-160 + neutron).
9. V. Mclane, C.L. Dunford, and P.F. Rose, Neutron Cross
Sections, Vol. 2, Academic Press (1988)
Back
|
