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48-Cd-116 UA,ANL, + EVAL-AUG94 J.McCabe, A.B. Smith, +
DIST-JAN09 20090105
----JEFF-311 MATERIAL 4855
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
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***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
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***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- ENDF/B-VI rel.4 (DIST-APR95 REV3-AUG96)
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ENDF/B-VI MOD 4 Revision (R.Q. Wright, ORNL, V. McLane, NNDC,
August 1996)
. Added file 1 comments
. Unresolved resonance parameters were revised in order to
eliminate a discontinuity in total cross section at 100 keV.
. The s- and p-wave strength functions are increased to
0.2E-4 and 3.4E-4, respectively.
. The scattering radius is increased to 6.50 fm. This revised
value is used for both the resolved and the unresolved
resonance regions.
The calculated resolved resonance thermal scattering cross
section is 5.806 barns, in good agreement with the experimental
value, 6 +/- 1. The revised evaluation has higher total and
elastic cross sections between 9 and 100 keV but the capture is
almost identical to the previous evaluation. The differences
vary from +1.2 to -2.0%, relative to the previous capture in
the ENDF/B-VI, release 2, evaluation.
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ENDF/B-VI MOD 3 (J. McCabe, A.B. Smith, J.W. Whalen, ANL,
August, 1994)
Comprehensive neutronic evaluated files for the naturally-
occurring isotopes of cadmium are deduced from the experimental
data and nuclear models. Particular attention is given to those
processes relevant to fuel-cycle and fisson-product applications.
Some discrepancies with the previous evaluation are very large
(e.g., as much as 100%), and the differences have the potential
for a pronounced effect on applications usage. The present files
are comprehensive, including many important processes that are
not represented in the previous evaluation. See Ref.1 for
complete documentation.
The resonance region evaluation was carried over from the
previous evaluation, see following.
REFERENCE
1. J. McCabe, A.B. Smith, J.W. Whalen, Report ANL/NDM-129 (1993)
Argonne National Laboratory.
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ENDF/B-VI MOD 2 Revision (R.Q. Wright, ORNL, December 1991)
See ANS Transactions, volume 68, part A, page 468
The ENDF/B-V evaluation used the SLBW formalism in the
resolved resonance range but did not have unresolved resonance
parameters.
Resolved resonance range (1.0E-5 eV to 9.0 keV)
-----------------------------------------------
The MLBW formalism is used for this evaluation. The highest
energy resonance included is 8825 eV. The resolved resonance
parameters are taken from Ref. 1 and from table 7 of Ref. 2.
Upper limit of the resolved resonance range is 9000 eV. This
evaluation has 27 s-wave and 21 p-wave resonances. The bound
level at -550 eV has gamma-n0 of 101 meV and gamma-gamma of 48
meV. The bound level accounts for about 90% of the thermal
capture cross section. The elastic cross section at thermal is
5.39 barns.
Unresolved resonance range (9.0 to 100 keV)
-------------------------------------------
The unresolved resonance range fit is based on the average
capture cross sections from Ref. 3. The unresolved resonance
parameters are based on:
D0 = 390 eV, S0 = 0.16, S1 = 2.8, AND S2 = 1.0
D1 = 150 eV, SG0 = 1.205, SG1 = 4.67
File 3:
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Total, elastic, and capture are set to zero in the resolved
and unresolved resonance ranges (1.0E-5 eV to 100 keV).
2200 m/s capture cross section, barns
(from resonance parameters) = 0.075
computed resonance integral = 1.735
REFERENCES
1. S.F. Mughabghab, M. Divadeenam, and N.E. Holden, Neutron
Cross Sections, vol 1A, Academic Press, New York (1981).
2. Musgrove et al., Neutron-capture resonance parameters and
cross sections for the even-A isotopes of cadmium, J. of
Physics, part G 4 (5), 771 (1978).
3. Musgrove et al., 1978 Harwell Conf. on Neutron Physics and
Nucl. Data, table V, page 449. (1978). Values are mult. by
a factor of 1.0187 (see Nucl.Sci.Eng. 82, p. 230).
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