48-Cd-106

 48-CD-106 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV2-SEP01            20010907   
----JENDL-3.3         MATERIAL 4825                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
90-03 New evaluation for JENDL-3 was completed by JNDC FPND       
      W.G./1/                                                     
01-08 Compiled by K.Shibata(jaeri/ndc) for JENDL-3.3.             
      *******  modified parts for JENDL-3.3  *********************
      (1,451)         Updated.                                    
      (2,151)         Revised.                                    
      (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 700 eV         
    Resonance parameters were based on Mughabghab et al./2/       
    Neutron orbital angular momentum L of some resonances was     
    estimated with a method of Bollinger and Thomas/3/.  Average  
    radiation width of 0.153 eV was determined from the experimen-
    tal data of Musgrove et al./4/ above 2.6 keV.  Scattering     
    radius of 6.5 fm was adopted from the systematics of measured 
    values.  A negative resonance was added so as to reproduce the
    thermal capture cross section given by Mughabghab et al.      
    *****  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 : 700 eV - 100 keV                  
    The neutron strength functions, S0 and S1 were based on the   
    compilation of Mughabghab et al., and S2 was calculated with  
    optical model code casthy/5/.  The observed level spacing was 
    adjusted to reproduce the capture cross section measured by   
    Musgrove et al./6,7/  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 = 1.000e-4, S1 = 5.000e-4, S2 = 0.970e-4, Sg(s)= 11.8e-4,  
    Sg(p)= 13.3e-4, Gg(s)= 0.155 eV, Gg(p)= 0.175 eV, R= 4.699 fm.
                                                                  
  calculated 2200-m/s cross sections and res. integrals (barns)   
                     2200 m/s               res. integ.           
      total           6.0032                    -                 
      elastic         5.0337                    -                 
      capture         0.9695                   10.4               
                                                                  
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/8/ 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/9/, Poenitz and Whalen/10/ and   
  so on.  The omp's for charged particles are as follows:         
     proton   = Perey/11/                                         
     alpha    = Huizenga and Igo/12/                              
     deuteron = Lohr and Haeberli/13/                             
     helium-3 and triton = Becchetti and Greenlees/14/            
  Parameters for the composite level density formula of Gilbert   
  and Cameron/15/ were evaluated by Iijima et al./16/  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
  /17/.                                                           
                                                                  
  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./29/, Green et al./30/ and Poenitz and Whalen/10/.      
    **************************************************************
                                                                  
  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 based on evaluated nuclear      
    structure data file (1987 version)/18/ and nuclear data       
    sheets/19/.                                                   
                                                                  
           no.      energy(MeV)    spin-parity    DWBA cal.       
           gr.       0.0             0  +                         
            1        0.6327          2  +             *           
            2        1.4938          4  +                         
            3        1.7166          2  +                         
            4        2.1045          4  +                         
            5        2.3050          4  +                         
            6        2.3306          5  +                         
            7        2.3386          4  +                         
            8        2.3705          3  -             *           
            9        2.4856          4  +                         
           10        2.4917          6  +                         
           11        2.5031          6  +                         
      Levels above 2.522 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/20/.  Deformation parameters (beta2 = 0.1732 and 
    beta3 = 0.194) were based on the data compiled by Raman et    
    al./21/ and Spear/22/, respectively.                          
                                                                  
  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/23/ and normalized to 1 milli-barn at 14 MeV.       
                                                                  
    The gamma-ray strength function (1.42e-03) was adjusted to    
    reproduce the capture cross section of 340 milli-barns at 70  
    keV measured by Musgrove et al./6,7/                          
                                                                  
    ******  For JENDL-3.3 ****************************************
    At the energies below 10 MeV, the cross section was modified  
    to well reproduce the elemental data measured by Kompe/31/ and
    Poenitz /32/, 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 =106  (n,he3) cross section                                  
  mt =107  (n,alpha) cross section                                
  mt =111  (n,2p) cross section                                   
    These reaction cross sections were calculated with the        
    preequilibrium and multi-step evaporation model code pegasus. 
                                                                  
    The kalbach's constant k (= 122.0) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/24/ and level  
    density parameters.                                           
                                                                  
    Finally, the (n,2n) and (n,alpha) cross sections were         
    normalized to the following values at 14.5 MeV:               
      (n,2n)       900.00  mb (recommended by Bychkov+/25/)       
      (n,alpha)    100.00  mb (recommended by Forrest/26/)        
    The (n,p) cross section was determined by eye-guiding of the  
    data measured by Bormann et al./27/                           
                                                                  
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, 22, 28, 91, 103, 107                                     
    Calculated with gnash code /28/.                              
  mt=102                                                          
    Calculated with casthy code /5/.                              
  mt=51-61                                                        
    Transitioin probability arrays                                
                                                                  
mf = 14  Photon angular distributions                             
  mt=16, 22, 28, 51-61, 91, 102, 103, 107                         
    Isotropic.                                                    
                                                                  
mf = 15  Continuous photon energy distributions                   
  mt=16, 22, 28, 91, 103, 107                                     
    Calculated with egnash code /28/.                             
  mt=102                                                          
    Calculated with casthy code /5/.                              
                                                                  
                                                                  
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-102     1.831e+01 6.210e-01 6.406e-01 7.665e+00 2.640e+00  
 46-Pd-103     1.733e+01 6.550e-01 5.327e+00 6.637e+00 1.350e+00  
 46-Pd-104     1.630e+01 6.650e-01 8.743e-01 7.305e+00 2.290e+00  
 46-Pd-105     1.791e+01 6.700e-01 9.137e+00 7.207e+00 1.350e+00  
                                                                  
 47-Ag-103  *  1.627e+01 6.427e-01 2.835e+00 5.882e+00 1.290e+00  
 47-Ag-104  *  1.737e+01 6.403e-01 3.551e+01 5.016e+00 0.0        
 47-Ag-105  *  1.848e+01 6.379e-01 1.390e+01 6.378e+00 9.400e-01  
 47-Ag-106     1.839e+01 5.480e-01 1.824e+01 3.696e+00 0.0        
                                                                  
 48-Cd-104  *  1.643e+01 6.403e-01 3.532e-01 7.266e+00 2.650e+00  
 48-Cd-105     1.600e+01 6.850e-01 4.000e+00 6.612e+00 1.360e+00  
 48-Cd-106     1.468e+01 6.950e-01 5.785e-01 7.078e+00 2.300e+00  
 48-Cd-107     1.647e+01 6.740e-01 4.374e+00 6.626e+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 1.094 for Cd-106 and 5.0 for Cd-107.               
                                                                  
References                                                        
 1) Kawai, M. et al.: Proc. Int. Conf. on Nuclear Data for Science
    and Technology, Mito, p. 569 (1988).                          
 2) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
 3) Bollinger, L.M. and Thomas, G.E.: Phys. Rev., 171,1293(1968). 
 4) Musgrove, A.R. de L., et al.: J. Phsics pt G, 4, 771 (1978).  
 5) Igarasi, S.: J. Nucl. Sci. Technol., 12, 67 (1975).           
 6) Musgrove, A.R. de L., et al.: Proc. of Int. Conf. on Neutron  
    Physics and Nucl. Data for Reactors, Harwell 1978, p.449      
 7) Allen, B.J., et al.: Nucl. Sci. Eng., 82, 230 (1982).         
 8) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
 9) Foster, D.G. Jr. and Glasgow, D. W.: Phys. Rev., C3, 576      
    (1971).                                                       
10) Poenitz, W.P. and Whalen, J.F.: ANL-NDM-80 (1983).            
11) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
12) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
13) Lohr, J.M. and Haeberli, W.: Nucl. Phys. a232, 381 (1974).    
14) 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).                                                       
15) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
    (1965).                                                       
16) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
17) Gruppelaar, H.: ECN-13 (1977).                                
18) ENSDF: Evaluated Nuclear Structure Data File (June 1987).     
19) Nuclear Data Sheets, 30, 305 (1980).                          
20) Kunz, P.D.: Private communication.                            
21) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1     
    (1987)                                                        
22) Spear, R.H.: Atom. Data and Nucl. Data Table, 42, 55 (1989).  
23) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
24) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
25) Bychkov, V.M. et al.: INDC(CCP)-146/LJ (1980).                
26) Forrest, R.A.: AERE-R 12419 (1986).                           
27) Bormann, M., et al.: Nucl. Phys., A115, 309 (1968).           
28) Young, P.G. and Arthur, E.D.: LA-6947 (1977).                 
29) Whalen, J.F. et al.: ANL-7210, 16 (1966).                     
30) Green, L. et al.: Data in EXFOR (1971).                       
31) Kompe, D.: Nucl. Phys., A133, 513 (1969).                     
32) Poenitz, W.P.: ANL-83-4, 239 (1982).