48-Cd-111

 48-CD-111 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV3-SEP01            20010907   
----JENDL-3.3         MATERIAL 4840                               
-----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/.                       
93-12 JENDL-3.2 was made by JNDC FPND W.G.                        
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      (2,151)       Resolved and unresolved resonance parameters  
      (3,102)       Renormalization to recent experiment          
      (3,2), (3,4), (3,51-91), (4,51-91)                          
                    Effects of renormalization of capture         
     ***********************************************************  
                                                                  
01-08 Compiled by K.Shibata(jaeri/ndc) for JENDL-3.3.             
      *******  modified parts for JENDL-3.3  *********************
      (1,451)         Updated.                                    
      (3,1)           Revised.                                    
      (3,2)           Revised.                                    
      (3,102)         Revised.                                    
      (3,251)         Deleted.                                    
      (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 1.8 keV        
    Resonance parameters of JENDL-2 were modified for JENDL-3.    
       For JENDL-2, evaluation was made on the basis of experimen-
    tal data of Liou et al./3/ and Wasson and Allen/4/.  The      
    average radiation width was assumed to be 0.102 eV/3/.        
    Scattering radius of 6.5 fm was assumed on the basis of       
    systematics of measured values.                               
       For JENDL-3, the lowest two p-wave resonances were added   
    according to the data by Alfimenkov et al./5/  Total spin J   
    of some resonances was tentatively estimated with a random    
    number method.  Parameters of a negative resonance were       
    modified so as to reproduce the thermal capture and elastic   
    scattering cross sections given by Mughabghab et al./6/       
       For JENDL-3.2, the capture data measured at ORELA of ORNL  
    were renormalized (factor=1.208)/7/.  The neutron and/or      
    radiation width were revised to reproduce the normalized      
    capture area for each resonance above 2.76 eV.                
    *****  For JENDL-3.3  ****************************************
    R was changed from 6.5fm to 6.2fm so as to reproduce measured 
    elemental total cross sections.                               
    **************************************************************
                                                                  
  Unresolved resonance region : 1.8 keV - 100 keV                 
    The same parameter values as JENDL-2 were used as initial     
    values.  Then the parameters were adjusted to reproduce the   
    capture cross section calculated with casthy /8/ (see mf=3,   
    mt=102) above 15 keV and those measured by Musgrove et al./9/ 
    below 15 keV.  The effective scattering radius was obtained   
    from fitting to the calculated total cross section at 100 keV.
                                                                  
  Typical values of the parameters at 70 kev:                     
    S0 = 0.450e-4, S1 = 3.900e-4, S2 = 0.530e-4, Sg = 101.e-4,    
    Gg = 0.160 eV, R  = 5.763 fm.                                 
                                                                  
  calculated 2200-m/s cross sections and res. integrals (barns)   
                     2200 m/s               res. integ.           
      total          28.545                    -                  
      elastic         4.606                    -                  
      capture        23.939                    49.3               
                                                                  
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/8/, by taking account of  
  competing reactions, of which cross sections were calculated    
  with pegasus/10/ 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/11/, Poenitz and Whalen/12/ and  
  so on.  The omp's for charged particles are as follows:         
     proton   = Perey/13/                                         
     alpha    = Huizenga and Igo/14/                              
     deuteron = Lohr and Haeberli/15/                             
     helium-3 and triton = Becchetti and Greenlees/16/            
  Parameters for the composite level density formula of Gilbert   
  and cameron/17/ were evaluated by Iijima et al./18/  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
  /19/.                                                           
                                                                  
  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/12/.      
    **************************************************************
                                                                  
  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./20/.           
                                                                  
           no.      energy(MeV)    spin-parity                    
           gr.       0.0            1/2 +                         
            1        0.2454         5/2 +                         
            2        0.3419         3/2 +                         
            3        0.3960        11/2 -                         
            4        0.4166         7/2 +                         
            5        0.6200         5/2 +                         
            6        0.7000         3/2 +                         
            7        0.7540         5/2 +                         
            8        0.8665         3/2 +                         
            9        1.0200         1/2 +                         
           10        1.1300         5/2 +                         
           11        1.1900         1/2 +                         
      Levels above 1.33 MeV were assumed to be overlapping.       
                                                                  
  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/21/ and normalized to 1 milli-barn at 14 MeV.       
                                                                  
    The gamma-ray strength function (1.032e-02) was adjusted to   
    reproduce the capture cross section of 664 milli-barns at 90  
    keV measured by Musgrove et al./9/                            
                                                                  
    ******  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 = 32  (n,n'd) 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 (= 107.8) 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)         50.00  mb (recommended by Forrest/23/)        
      (n,alpha)      4.52  mb (systematics of Forrest/23/)        
                                                                  
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.  For other reactions, isotropic distri- 
  butions 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 /8/.                              
  mt=51-61                                                        
    Transitioin probability arrays                                
                                                                  
mf = 14  Photon angular distributions                             
  mt=16, 17, 22, 28, 51-61, 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 /8/.                              
                                                                  
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       a(1/MeV)  t(MeV)    c(1/MeV)  Ex(MeV)   pairing    
 ---------------------------------------------------------------  
 46-Pd-107     1.916e+01 6.110e-01 6.467e+00 6.507e+00 1.350e+00  
 46-Pd-108     1.790e+01 6.460e-01 8.844e-01 7.957e+00 2.600e+00  
 46-Pd-109     2.071e+01 6.030e-01 1.194e+01 6.925e+00 1.350e+00  
 46-Pd-110     1.880e+01 6.300e-01 1.215e+00 7.897e+00 2.490e+00  
                                                                  
 47-Ag-108     1.671e+01 5.760e-01 1.221e+01 3.609e+00 0.0        
 47-Ag-109     1.650e+01 6.300e-01 2.761e+00 5.709e+00 1.250e+00  
 47-Ag-110     1.791e+01 5.900e-01 2.444e+01 4.282e+00 0.0        
 47-Ag-111     1.955e+01 5.810e-01 6.505e+00 5.835e+00 1.140e+00  
                                                                  
 48-Cd-109     1.812e+01 6.120e-01 3.856e+00 6.132e+00 1.360e+00  
 48-Cd-110     1.750e+01 6.300e-01 5.212e-01 7.482e+00 2.610e+00  
 48-Cd-111     1.874e+01 5.930e-01 3.762e+00 6.000e+00 1.360e+00  
 48-Cd-112     1.797e+01 6.190e-01 6.327e-01 7.351e+00 2.500e+00  
 ---------------------------------------------------------------  
                                                                  
 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 4.636 for Cd-111 and 3.236 for Cd-112.             
                                                                  
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.: J. Nucl. Sci. Technol., 29, 195 (1992).     
 3) Liou, H.I., et al.: Phys. Rev., C10, 709 (1974).              
 4) Wasson, O.A., Allen, B.J.: Phys. Rev., C7, 780 (1973).        
 5) Alfimenkov et al.: Nucl. Phys. A397, 93(1983).                
 6) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
 7) Allen, B.J. et al.: Nucl. Sci. Eng., 82, 230 (1982).          
 8) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).              
 9) Musgrove, A.R. de L., et al.: "Proc. Int. Conf. on Neutron    
    Physics and Nucl. Data for Reactors, Harwell 1978", 449p.     
10) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
11) Foster, D.G. Jr. and Glasgow, D. W.: Phys. Rev., C3, 576      
    (1971).                                                       
12) Poenitz, W.P. and Whalen, J.F.: ANL-NDM-80 (1983).            
13) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
14) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
15) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
16) 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).                                                       
17) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
    (1965).                                                       
18) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
19) Gruppelaar, H.: ECN-13 (1977).                                
20) Matsumoto, J.: Private communication (1981).                  
21) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
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).