6.616300+4 1.615290+2 1 0 2 1
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 2.000000+7 7 0 10 31
0.000000+0 0.000000+0 0 0 111 1
66-Dy-163 ORNL, HEDL EVAL-OCT74 WRIGHT, SCHENTER, SCHMITTROTH
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 6646
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** 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 487.6 to 1000 eV. The number of resolved resonances is
increased from 60 to 115. The resonance parameters are taken
from Mughabghab [8].
UNRESOLVED RESONANCE RANGE-- no parameters given
MF= 3 SMOOTH CROSS SECTIONS
MT= 1 Total below 100 keV is much lower in the REVISED
evaluation relative to ENDF/B-V and is higher than ENDF/B-V
between 0.1 and 2 MeV. For the energy range 0.5 to 20 MeV
the total cross section is based on the "eye guide" or
recommended curve 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 1000 eV
For the energy range 3 to 700 keV the revision is based on
the measured data of Beer [7]. 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 [8]
2200 m/sec cross sections (barns)
Evaluation Mughabghab
total 127.66 127.2
elastic 3.39 3.2 +/- 0.5
capture 124.27 124 +/- 7
capture resonance integral (barns)
Evaluation Mughabghab
1489 1470 +/- 100
****************************************************************
ENDF/B-VI MOD 0, February 1990 (NNDC)
ENDF/B-V material converted to ENDF-6 format.
****************************************************************
ENDF/B-V Evaluation, MAT 9867, 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.
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. A.L. Pope and J.S. Story, report AEEW-M 1234 (1973)
7. H. Beer et al., private communication, R. Macklin (1984);
Data given in EXFOR 12881.002
8. S.F. Mughabghab, Neutron Cross Sections, Vol. 1, Neutron
Resonance Parameters and Thermal Cross Sections, Part B
(Academic Press, 1984)
9. V. Mclane, C.L. Dunford, and P.F. Rose, Neutron Cross
Sections, Vol. 2, Academic Press (1988)
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