![]() |
|
Back
48-Cd-112 UA,ANL, + EVAL-AUG94 J.McCabe, A.B. Smith, + DIST-JAN09 20090105 ----JEFF-311 MATERIAL 4843 -----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) File 1 comments added File 3, MT=4 Obsolete code deleted **************************************************************** 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 resolved resonance range and did not have unresolved resonance parameters. Resolved resonance range (1.0E-5 eV to 7.35 keV) ------------------------------------------------ The MLBW formalism is used for this evaluation. The highest energy resonance included is 11455 eV. The resolved resonance parameters are taken from ref. 1 and from table 5 of ref. 2. Upper limit of the resolved resonance range is 7350 eV. This evaluation has 64 s-wave and 54 p-wave resonances including 24 s-wave resonances above 7350 eV. The bound level at -125 eV has a gamma-n0 of 93.91 meV and gamma-gamma of 83 meV (ref. 1). The bound level accounts for about 95% of the thermal capture cross section. The elastic cross section at thermal is 6.31 barns. Unresolved resonance range (7.35 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 = 190 eV, S0 = 0.5, S1 = 4.4, AND S2 = 1.5 D1 = 75 eV, SG0 = 4.05, SG1 = 12.0 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) = 2.195 computed resonance integral = 13.50 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 1.0069 (see Nucl.Sci.Eng. 82, p. 230).Back |