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66-Dy-161 ORNL, HEDL EVAL-OCT74 WRIGHT, SCHENTER, SCHMITTROTH
DIST-JAN09 20090105
----JEFF-311 MATERIAL 6640
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
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** Original data taken from: JEFF-3.1 **
** **
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***************************** JEFF-3.1 *************************
** **
** Original data taken from: ENDF/B-VI.8 **
** **
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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 67.64 to 1000 eV. The number of resolved resonances is
increased from 27 to 254. The resonance parameters are taken
from Mughabghab [7].
UNRESOLVED RESONANCE RANGE 1.00 to 10 keV (added)
The following parameters are used in this range:
S0 = 1.9E-4, S1 = 1.0E-4, D0 = 1.98 eV,
GG = 0.113 eV, GG/D0 = 570.7E-4,
Scattering radius, R = 7.50 fm
These parameters are based on Mughabghab [7] and RIPL [9].
The same scattering radius also used for resolved range.
MF= 3 SMOOTH CROSS SECTIONS
MT= 1 Total below 10 keV is much lower in the REVISED
evaluation relative to ENDF/B-V. Total cross section above
10 keV is revised to join smoothly at 10 keV. For all of
the dysprosium isotopes the total cross section is based on
the "eye guide" curve as given on page 546 of McLane [10].
MT= 2 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 10 keV.
For the energy range 3 to 700 keV, the revision is based on
the measured data of Beer [8]. Capture above 700 keV is
revised to join smoothly at 700 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 617.10 616.5
elastic 16.60 16.5 +/- 1.5
capture 600.50 600 +/- 25
Capture resonance integral (barns)
Evaluation Mughabghab
1088 1200 +/- 100
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ENDF/B-VI MOD 0, February 1990 (NNDC)
ENDF/B-V material converted to ENDF-6 format.
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ENDF/B-V Evaluation, MAT 9865, 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. The calculated resonance integral agrees (to
within 1 sigma) with the value given in Pope [6].
MF=4 ANGULAR DISTRIBUTIONS
MT= 2 Elastic angular distribution assumed isotropic.
MT= 4,51,52,.,.,91 Inelastic angular distributions assumed
isotropic.
MF=5 ENERGY DISTRIBUTION OF SECONDARY PARTICLES
MT= 91 Evaporation spectrum (LF=9) parameters obtained using
NCAP code [2].
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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. A.L. Pope and J.S. Story, report AEEW-M 1234 (1973)
7. S.F. Mughabghab, Neutron Cross Sections, Vol. 1, Neutron
Resonance Parameters and Thermal Cross Sections, Part B
(Academic Press, 1984)
8. H. Beer et. al., Phys.Rev. C 30, 464 (1984)
9. 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).
10. V. Mclane, C.L. Dunford, and P.F. Rose, Neutron Cross
Sections, Vol. 2, Academic Press (1988)
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