54-Xe-124

 54-Xe-124 JAEA       EVAL-FEB22 S.Kunieda, A.Ichihara, K.Shibata+
                      DIST-MAY10                       20100316   
----JENDL-4.0         MATERIAL 5425                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-11 Re-evaluation was performed for JENDL-4.0                   
10-03 Compiled by S.Kunieda                                       
                                                                  
MF= 1 General information                                         
                                                                  
  MT=451 Descriptive data and directory                           
                                                                  
                                                                  
MF= 2 Resonance parameters                                        
                                                                  
  MT=151 Resolved and unresolved resonance parameters             
                                                                  
    - Resolved resonance region (MLBW formula): below 0.29 keV    
        The neutron and radiation widths of the levels at 5.09 and
      10.12 eV were taken from the work of Skoy et al./1/.        
      The neutron width for the level at 251.6 eV was taken from  
      the measurement by Ribon et al. /2/  The neutron orbital    
      angular momentum l was assumed to be 0 for all resonance    
      levels. The scattering radius was also taken from the graph 
      (fig. 1, Part A) given by Mughabghab et al./3/              
      A negative resonance at -118 eV was kept not to make the    
      thermal scattering cross section too small, although the    
      neutron width was changed to 1 eV.                          
                                                                  
    - Unresolved resonance region: 0.29 keV - 300 keV             
        The parameters were obtained by fitting to the total and  
      capture cross sections calculated by the POD code /4/.      
      The ASREP code /5/ was employed in this evaluation.         
      The unresolved parameters should be used only for           
      self-shielding calculation.                                 
                                                                  
     Thermal cross sections & resonance integrals at 300 K        
      ----------------------------------------------------------  
                       0.0253 eV           res. integ. (*)        
                        (barns)              (barns)              
      ----------------------------------------------------------  
       Total          1.48558E+02                                 
       Elastic        1.59751E-01                                 
       n,gamma        1.48399E+02           3.26731E+03           
      ----------------------------------------------------------  
      (*) Integrated from 0.5 eV to 10 MeV.                       
                                                                  
                                                                  
MF= 3 Neutron cross sections                                      
                                                                  
  MT=  1 Total cross section                                      
    Sum of partial cross sections.                                
                                                                  
  MT=  2 Elastic scattering cross section                         
    The OPTMAN /6/ & POD /4/ calculations.                        
                                                                  
  MT=  3 Non-elastic cross section                                
    Sum of partial non-elastic cross sections.                    
                                                                  
  MT=  4,51-91 (n,n') cross section                               
    The OPTMAN /6/ & POD /4/ calculations.                        
                                                                  
  MT= 16 (n,2n) cross section                                     
  MT= 17 (n,3n) cross section                                     
  MT= 22 (n,na) cross section                                     
  MT= 28 (n,np) cross section                                     
  MT= 32 (n,nd) cross section                                     
  MT=102 Capture 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,a) cross section                                      
    Calculated by the POD code /4/.                               
                                                                  
  MT=203 (n,xp) cross section                                     
    Sum of (n,np) and (n,p)                                       
                                                                  
  MT=204 (n,xd) cross section                                     
    Sum of (n,nd) and (n,d)                                       
                                                                  
  MT=205 (n,xt) cross section                                     
  MT=206 (n,xHe3) cross section                                   
    Calculated by the POD code /4/.                               
                                                                  
  MT=207 (n,xa) cross section                                     
    Sum of (n,na) and (n,a)                                       
                                                                  
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
                                                                  
  MT=  2 Elastic scattering                                       
    The OPTMAN /6/ & POD /4/ calculations.                        
                                                                  
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
                                                                  
  MT= 16 (n,2n) reaction                                          
  MT= 17 (n,3n) reaction                                          
  MT= 22 (n,na) reaction                                          
  MT= 28 (n,np) reaction                                          
  MT= 32 (n,nd) reaction                                          
    Neutron spectra calculated by the POD code /4/.               
                                                                  
  MT= 51-90 (n,n') reaction                                       
    Neutron angular distributions calculated by                   
    OPTMAN /6/ & POD /4/.                                         
                                                                  
  MT= 91 (n,n') reaction                                          
    Neutron spectra calculated by the POD code /4/.               
                                                                  
  MT= 203 (n,xp) reaction                                         
  MT= 204 (n,xd) reaction                                         
  MT= 205 (n,xt) reaction                                         
  MT= 206 (n,xHe3) reaction                                       
  MT= 207 (n,xa) reaction                                         
    Light-ion spectra calculated by the POD code /6/.             
                                                                  
                                                                  
MF=12 Gamma-ray multiplicities                                    
                                                                  
  MT=  3 Non-elastic gamma emission                               
    Calculated by the POD code /4/.                               
                                                                  
                                                                  
MF=14 Gamma-ray angular distributions                             
                                                                  
  MT=  3 Non-elastic gamma emission                               
    Assumed to be isotropic.                                      
                                                                  
                                                                  
MF=15 Gamma-ray spectra                                           
                                                                  
  MT=  3 Non-elastic gamma emission                               
    Calculated by the POD code /4/.                               
                                                                  
                                                                  
                                                        
                                                                  
***************************************************************   
*        Nuclear Model Calculations with POD Code /4/     *       
***************************************************************   
1. Theoretical models                                             
 The POD code is based on the spherical optical model, the        
distorted-wave Born approximaiton (DWBA), one-component exciton   
preequilibrium model, and the Hauser-Feshbach-Moldauer statis-    
tical model.  With the preequilibrium model, semi-empirical       
pickup and knockout process can be taken into account for         
composite-particle emission.  The gamma-ray emission from the     
compound nucleus can be calculated within the framework of the    
exciton model.  The code is capable of reading in particle        
transmission coefficients calculated by separate spherical or     
coupled-channel optical model code. In this evaluation, the OPTMAN
code /6/ was employed for neutrons, while the ECIS code           
/7/ was adopted for charged particles.                            
                                                                  
2. Optical model & parameters                                     
  Neutrons:                                                       
    Model: The coupled-channel method based on the rigid-rotor    
           model was adopted. Deformation parameter beta2 was     
           taken from ref./8/                                     
    OMP  : Coupled-channel optical potential /9/ was applied.     
  Protons:                                                        
    Model: Spherical                                              
    OMP  : Koning and Delaroche /10/                              
  Deuterons:                                                      
    Model: Spherical                                              
    OMP  : Bojowald et al. /11/                                   
  Tritons:                                                        
    Mode: Spherical                                               
    OMP : Becchetti and Greenlees /12/                            
  He-3:                                                           
    Model: Spherical                                              
    OMP  : Becchetti and Greenlees /12/                           
  Alphas:                                                         
    Model: Spherical                                              
    OMP  : A simplified folding model potential /13/              
           (The nucleon OMP was taken from Ref./9/.)              
                                                                  
3. Level scheme of Xe-124                                         
  ------------------------------------                            
   No.   Ex(MeV)     J  PI      CC                                
  ------------------------------------                            
    0    0.00000     0   +       *                                
    1    0.35414     2   +       *                                
    2    0.84661     2   +                                        
    3    0.87903     4   +       *                                
    4    1.24804     3   +                                        
    5    1.26895     0   +                                        
    6    1.43805     4   +                                        
    7    1.54878     6   +       *                                
    8    1.62869     2   +                                        
    9    1.69002     0   +                                        
  ------------------------------------                            
  Levels above  1.70002 MeV are assumed to be continuous.         
                                                                  
                                                                  
4. Level density parameters                                       
 Energy-dependent parameters of Mengoni-Nakajima /14/ were used   
  ----------------------------------------------------------      
  Nuclei    a*    Pair    Esh     T     E0    Ematch Elv_max      
          1/MeV   MeV     MeV    MeV    MeV    MeV    MeV         
  ----------------------------------------------------------      
  Xe-125  16.165  1.073  2.346  0.622 -1.147  6.601  0.471        
  Xe-124  15.399  2.155  2.182  0.621  0.273  7.267  1.690        
  Xe-123  15.957  1.082  2.651  0.664 -1.723  7.515  0.307        
  Xe-122  15.188  2.173  2.307  0.638  0.114  7.579  1.149        
  I -124  15.322  0.000  2.324  0.625 -1.946  5.211  0.151        
  I -123  14.648  1.082  2.421  0.634 -0.757  6.207  1.315        
  I -122  15.113  0.000  2.707  0.561 -1.330  4.124  0.149        
  Te-122  15.188  2.173  1.912  0.607  0.581  6.853  2.200        
  Te-121  15.749  1.091  2.474  0.637 -1.236  6.808  0.923        
  Te-120  14.977  2.191  2.149  0.589  0.772  6.556  1.924        
  ----------------------------------------------------------      
                                                                  
5. Gamma-ray strength functions                                   
   M1, E2: Standard Lorentzian (SLO)                              
   E1    : Generalized Lorentzian (GLO) /15/                      
                                                                  
6. Preequilibrium process                                         
   Preequilibrium is on for n, p, d, t, He-3, and alpha.          
   Preequilibrium capture is on.                                  
                                                                  
                                                                  
References                                                        
 1) Skoy, V.R. et al.: Nucl. Instrum. Meth. Phys. Res., B267,     
   2351 (2009).                                                   
 2) Ribon, P. et al.: CEA-N-1149 (1969).                          
 3) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
 4) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 5) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
    [in Japanese].                                                
 6) E.Soukhovitski et al., JAERI-Data/Code 2005-002 (2005).       
 7) J.Raynal, CEA Saclay report, CEA-N-2772 (1994).               
 8) S.Raman et al., At. Data and Nucl. Data Tables 78, 1 (1995)   
 9) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).      
10) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).      
11) Bojowald et al., Phys. Rev. C 38, 1153 (1988).                
12) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization               
    Phenomena in Nuclear Reactions," p.682, The University        
    of Wisconsin Press (1971).                                    
13) D.G.Madland, NEANDC-245 (1988), p. 103.                       
14) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151         
     (1994).                                                      
15) M.Brink, Ph.D thesis, Oxford University, 1955.