![]() |
|
Back
48-Cd-114 UA,ANL, + EVAL-AUG94 J.McCabe, A.B. Smith, + DIST-JAN09 20090105 ----JEFF-311 MATERIAL 4849 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 ** ** ** ****************************************************************** ***************************** JEFF-3.1 ************************* ** ** ** Original data taken from: JEFF-3.0 ** ** ** ****************************************************************** ***************************** JEFF-3.0 *********************** DATA TAKEN FROM :- ENDF/B-VI rel.4 (DIST-APR95 REV3-AUG96) ****************************************************************** ENDF/B-VI MOD 4 Revision (R.Q. Wright, ORNL, V. McLane, NNDC, August, 1996) . Added file 1 comments . Unresolved resonance range scattering radius was changed to 6.19 fm in order to eliminate a discontinuity in the total cross section at 100 keV. **************************************************************** 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. **************************************************************** 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 resolvedresonance range but did not have unresolved resonance parameters. Resolved resonance range (1.0E-5 eV to 8.0 keV) ----------------------------------------------- The MLBW formalism is used for this evaluation. The highest energy resonance included is 10088 eV. The resolved resonance parameters are taken from Ref. 1 and from table 6 of Ref. 2. Upper limit of the resolved resonance range is 8000 eV. This evaluation has 40 s-wave and 45 p-wave resonances including 5 s-wave resonances above 8000 eV. The bound level at -225 eV has a gamma-n0 of 34.53 meV and gamma-gamma of 53.0 meV. The bound level accounts for about 43% of the thermal capture cross section. The elastic cross section at thermal is 4.461 barns. Note that the value of the capture resonance integral given on page 48-22 of Ref. 1 should read 13+/-2 barns (see ref. 4). Unresolved resonance range (8.0 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 = 235 eV, S0 = 0.64, S1 = 3.5, AND S2 = 1.0 D1 = 90 eV, SG0 = 2.26, SG1 = 7.78 File 3: ------- 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) = 0.336 computed resonance integral = 13.15 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). 4. S.F. Mughabghab, Neutron Cross Sections, vol 1B, Academic Press, New York (1984). See page D-2.Back |