48-Cd-114

 48-CD-114 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV2-SEP01            20010907   
----JENDL-3.3         MATERIAL 4849                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/        
90-03 Modification for JENDL-3 was made/2/.                       
01-08 Compiled by K.Shibata(jaeri/ndc) for JENDL-3.3.             
      *******  modified parts for JENDL-3.3  *********************
      (1,451)         Updated.                                    
      (3,251)         Deleted.                                    
      (3,1)           Revised.                                    
      (3,2)           Revised.                                    
      (3,102)         Revised.                                    
      (4,2)           Transformation matrix deleted.              
      (12,16-107)     Added.                                      
      (14,16-107)     Added.                                      
      (15,16-107)     Added.                                      
      ************************************************************
                                                                  
mf = 1  General information                                       
  mt=451 Comments and dictionary                                  
                                                                  
mf = 2  Resonance parameters                                      
  mt=151 Resolved and unresolved resonance parameters             
  Resolved resonance region (MLBW formula) : below 8 keV          
       For JENDL-2, evaluation was made on the basis of experimen-
    tal data of Liou et al./3/ and Musgrove et al./4/  The average
    radiation width of s-wave resonances was assumed to be 0.11   
    eV/3/ below 2.0 keV, and to be 0.053 eV above 2.0 keV.  For   
    p-wave ones, the average width of 0.082 eV/4/ was assumed.    
       For JENDL-3, parameters of a negative resonance and        
    scattering radius were modified so as to reproduce the thermal
    capture and elastic scattering cross sections given by        
    Mughabghab et al./5/                                          
    *****  For JENDL-3.3  ****************************************
    R was changed from 7.5fm to 6.2fm so as to reproduce measured 
    elemental total cross sections.                               
    **************************************************************
                                                                  
  Unresolved resonance region : 8 keV - 100 keV                   
    The neutron strength functions, S0 and S1 were based on the   
    compilation of Mughabghab et al./5/, and S2 was calculated    
    with optical model code casthy/6/.  The observed level spacing
    was determined to reproduce the capture cross section         
    calculated with casthy.  The effective scattering radius was  
    obtained from fitting to the calculated total cross section at
    100 keV.  The radiation widths, Gg(s) and Gg(p), were based on
    the compilation of Mughabghab et al.                          
                                                                  
  Typical values of the parameters at 70 keV:                     
    S0 = 0.640e-4, S1 = 3.500e-4, S2 = 0.890e-4, Sg(s)= 2.12e-4,  
    Sg(p)= 2.80e-4, Gg(s)= 0.053 eV, Gg(p)= 0.070 eV, R= 5.804 fm.
                                                                  
  calculated 2200-m/s cross sections and res. integrals (barns)   
                     2200 m/s               res. integ.           
      total           4.2140                   -                  
      elastic         3.8736                   -                  
      capture         0.3404                   16.9               
                                                                  
mf = 3  Neutron cross sections                                    
  Below 100 keV, Resonance parameters were given.                 
  Above 100 kev, the spherical optical and statistical model      
  calculation was performed with casthy, by taking account of     
  competing reactions, of which cross sections were calculated    
  with pegasus/7/ standing on a preequilibrium and multi-step     
  evaporation model.  The omp's for neutron given in Table 1 were 
  determined to reproduce the Cd-natural total cross sections     
  measured by Foster and Glasgow/8/, Poenitz and Whalen/9/ and    
  so on.  The omp's for charged particles are as follows:         
     proton   = Perey/10/                                         
     alpha    = Huizenga and Igo/11/                              
     deuteron = Lohr and Haeberli/12/                             
     helium-3 and triton = Becchetti and Greenlees/13/            
  Parameters for the composite level density formula of Gilbert   
  and cameron/14/ were evaluated by Iijima et al./15/  More       
  extensive determination and modification were made in the       
  present work.  Table 2 shows the level density parameters used  
  in the present calculation.  Energy dependence of spin cut-off  
  parameter in the energy range below E-joint is due to Gruppelaar
  /16/.                                                           
                                                                  
  mt = 1  Total                                                   
    Spherical optical model calculation was adopted.              
    ******  For JENDL-3.3 ****************************************
    In the energy region from 100 keV to 2.5 MeV, cross section   
    was determined from the elemental data measured by Whalen     
    et al./25/, Green et al./26/ and Poenitz and Whalen/9/.       
    **************************************************************
                                                                  
  mt = 2  Elastic scattering                                      
    Calculated as (total - sum of partial cross sections).        
    *****  For JENDL-3.3  ****************************************
    Background cross sections were generated so as to cancel      
    capture background.                                           
    **************************************************************
                                                                  
  mt = 4, 51 - 91  Inelastic scattering                           
    Spherical optical and statistical model calculation was       
    adopted.  The level scheme was taken from ref./17/.           
                                                                  
           no.      energy(MeV)    spin-parity   DWBA cal.        
           gr.       0.0             0  +                         
            1        0.5583          2  +            *            
            2        1.1342          0  +                         
            3        1.2093          2  +                         
            4        1.2833          4  +                         
            5        1.3052          0  +                         
            6        1.3639          2  +                         
            7        1.7318          4  +                         
            8        1.7571          1  +                         
      Levels above 1.776 MeV were assumed to be overlapping.      
                                                                  
    For the levels with an asterisk, the contribution of direct   
    inelastic scattering cross sections was calculated by the     
    dwuck-4 code/18/.  Deformation parameter (beta2 = 0.1912) was 
    based on the data compiled by Raman et al./19/                
                                                                  
  mt = 102  Capture                                               
    Spherical optical and statistical model calculation with      
    casthy was adopted.  Direct and semi-direct capture cross     
    sections were estimated according to the procedure of Benzi   
    and Reffo/20/ and normalized to 1 milli-barn at 14 MeV.       
                                                                  
    The gamma-ray strength function (2.50e-04) was adjusted to    
    reproduce the capture cross section of 150 milli-barns at 30  
    keV measured by Musgrove et al./21/                           
                                                                  
    ******  For JENDL-3.3 ****************************************
    At the energies below 10 MeV, the cross section was modified  
    to well reproduce the elemental data measured by Kompe/27/ and
    Poenitz /28/, by adopting background data in the unresolved   
    resonance region and multipling an energy dependent factor    
    above 100 keV.                                                
    **************************************************************
                                                                  
  mt = 16  (n,2n) cross section                                   
  mt = 17  (n,3n) cross section                                   
  mt = 22  (n,n'a) cross section                                  
  mt = 28  (n,n'p) cross section                                  
  mt =103  (n,p) cross section                                    
  mt =104  (n,d) cross section                                    
  mt =105  (n,t) cross section                                    
  mt =107  (n,alpha) cross section                                
    These reaction cross sections were calculated with the        
    preequilibrium and multi-step evaporation model code pegasus. 
                                                                  
    The Kalbach's constant k (=  76.1) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/22/ and level  
    density parameters.                                           
                                                                  
    Finally, the (n,p) and (n,alpha) cross sections were          
    normalized to the following values at 14.5 MeV:               
      (n,p)         10.00  mb (recommended by Forrest/23/)        
      (n,alpha)      0.70  mb (recommended by Forrest)            
                                                                  
mf = 4  Angular distributions of secondary neutrons               
  Legendre polynomial coefficients for angular distributions are  
  given in the center-of-mass system for mt=2 and discrete inelas-
  tic levels, and in the laboratory system for mt=91.  They were  
  calculated with casthy.  contribution of direct inelastic       
  scattering was calculated with dwuck-4.  For other reactions,   
  isotropic distributions in the laboratory system were assumed.  
                                                                  
mf = 5  Energy distributions of secondary neutrons                
  Energy distributions of secondary neutrons were calculated with 
  pegasus for inelastic scattering from overlapping levels and for
  other neutron emitting reactions.                               
                                                                  
mf = 12  Photon production multiplicities                         
  mt=16, 17, 22, 28, 91, 103, 107                                 
    Calculated with gnash code /24/.                              
  mt=102                                                          
    Calculated with casthy code /6/.                              
  mt=51-58                                                        
    Transitioin probability arrays                                
                                                                  
mf = 14  Photon angular distributions                             
  mt=16, 17, 22, 28, 51-58, 91, 102, 103, 107                     
    Isotropic.                                                    
                                                                  
mf = 15  Continuous photon energy distributions                   
  mt=16, 17, 22, 28, 91, 103, 107                                 
    Calculated with egnash code /24/.                             
  mt=102                                                          
    Calculated with casthy code /6/.                              
                                                                  
                                                                  
Table 1  Neutron optical potential parameters                     
                                                                  
                depth (MeV)       radius(fm)    diffuseness(fm)   
         ----------------------   ------------  ---------------   
        V  = 50.01-0.5528E        r0 = 5.972    a0 = 0.56         
        Ws = 8.165                rs = 6.594    as = 0.44         
        Vso= 5.261                rso= 5.97     aso= 0.267        
  The form of surface absorption part is der. Woods-Saxon type.   
                                                                  
Table 2  Level density parameters                                 
                                                                  
 nuclide  syst a(1/MeV)  t(MeV)    c(1/MeV)  Ex(MeV)   pairing    
 ---------------------------------------------------------------  
 46-Pd-110     1.880e+01 6.300e-01 1.215e+00 7.897e+00 2.490e+00  
 46-Pd-111     2.143e+01 5.610e-01 7.376e+00 6.267e+00 1.350e+00  
 46-Pd-112  *  1.821e+01 6.210e-01 5.620e-01 7.654e+00 2.670e+00  
 46-Pd-113  *  1.800e+01 6.185e-01 4.082e+00 6.206e+00 1.350e+00  
                                                                  
 47-Ag-111     1.955e+01 5.810e-01 6.505e+00 5.835e+00 1.140e+00  
 47-Ag-112  *  1.857e+01 6.210e-01 4.959e+01 5.129e+00 0.0        
 47-Ag-113  *  1.837e+01 6.185e-01 5.132e+00 6.321e+00 1.320e+00  
 47-Ag-114  *  1.816e+01 6.161e-01 3.785e+01 4.871e+00 0.0        
                                                                  
 48-Cd-112     1.797e+01 6.190e-01 6.327e-01 7.351e+00 2.500e+00  
 48-Cd-113     1.973e+01 5.760e-01 4.397e+00 6.018e+00 1.360e+00  
 48-Cd-114     1.910e+01 6.010e-01 5.651e-01 7.611e+00 2.680e+00  
 48-Cd-115     2.072e+01 5.570e-01 4.805e+00 5.966e+00 1.360e+00  
 ---------------------------------------------------------------  
  syst:  * = ldp's were determined from systematics.              
                                                                  
 Spin cutoff parameters were calculated as 0.146*sqrt(a)*a**(2/3).
 in the casthy calculation. Spin cutoff factors at 0 MeV were     
 assumed to be 3.875 for Cd-114 and 5.0 for Cd-115.               
                                                                  
References                                                        
 1) Aoki, T. et al.: Proc. Int. Conf. on Nuclear Data for Basic   
    and Applied Science, Santa Fe., Vol. 2, p.1627 (1985).        
 2) Kawai, M. et al.: Proc. Int. Conf. on Nuclear Data for Science
    and Technology, Mito, p. 569 (1988).                          
 3) Liou, H.I., et al.: Phys. Rev., C10, 709 (1974).              
 4) Musgrove, A.R. de L., et al.: J. Phys. G, 4, 771 (1978).      
 5) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
 6) Igarasi, S.: J. Nucl. Sci. Technol., 12, 67 (1975).           
 7) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
 8) Foster, D.G. Jr. and Glasgow, D. W.: Phys. Rev., C3, 576      
    (1971).                                                       
 9) Poenitz, W.P. and Whalen, J.F.: ANL-NDM-80 (1983).            
10) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
11) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
12) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
13) Becchetti, F.D., Jr. and Greenlees, G.W.: Polarization        
    Phenomena in Nuclear Reactions ((Eds) H.H. Barshall and       
    W. Haeberli), p. 682, the University of Wisconsin Press.      
    (1971).                                                       
14) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
    (1965).                                                       
15) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
16) Gruppelaar, H.: ECN-13 (1977).                                
17) Lederer, C.M., et al.: "Table of Isotopes, 7th ed.", Wiley-   
    Interscience Publication (1978).                              
18) Kunz, P.D.: Private communication.                            
19) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1     
    (1987)                                                        
20) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
21) Musgrove, A.R. de L., et al.: Proc. Int. Conf. on Neutron     
    Physics and Nucl. Data for Reactors, Harwell 1978, 449.       
22) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
23) Forrest, R.A.: AERE-R 12419 (1986).                           
24) Young, P.G. and Arthur, E.D.: LA-6947 (1977).                 
25) Whalen, J.F. et al.: ANL-7210, 16 (1966).                     
26) Green, L. et al.: Data in EXFOR (1971).                       
27) Kompe, D.: Nucl. Phys., A133, 513 (1969).                     
28) Poenitz, W.P.: ANL-83-4, 239 (1982).