53-I -130

 53-I -130 JAEA       EVAL-DEC09 K.Shibata                        
                      DIST-MAY10                       20100105   
----JENDL-4.0         MATERIAL 5334                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-12 Statistical model calculations were performed by K.Shibata. 
10-01 Data were compiled by K.Shibata.                            
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2 Resonance parameters                                        
  MT=151 Resolved and unresolved resonance parameters             
    No resolved resonance parameters are given.                   
      The 1/v-shped capture cross section is assumed below 16 eV. 
      At 0.0253 eV, the cross section was normalized to the value 
      of 18 b, which was recommended by Mughabghab/1/.            
      The scattering cross section was calculated from 4*pi*R**2, 
      where the scattering radius R was obtained in the unresolved
      resonance region: R=5.467 fm.                               
    Unresolved resonance region: 16 eV - 40 keV                   
      The parameters were obtained by fitting to the total and    
      capture cross sections calculated from POD /2/.  The        
      unresolved parameters should be used only for self-shielding
      calculation.                                                
                                                                  
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total           2.1806E+01                                   
     Elastic         3.7713E+00                                   
     n,gamma         1.8008E+01           1.1857E+02              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    Calculated with POD code /2/.                                 
                                                                  
  MT=  2 Elastic scattering cross section                         
    The cross sections were obtained by subtracting the nonelastic
    cross sections from the total cross sections.                 
                                                                  
  MT=  3 Non-elastic cross section                                
    Calculated with POD code /2/.                                 
                                                                  
  MT=  4,51-91 (n,n') cross section                               
    Calculated with POD code /2/.                                 
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT=102 Capture cross section                                    
    Calculated with POD code /2/.                                 
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with POD code /2/.                                 
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with POD code /2/.                                 
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with POD code /2/.                                 
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with POD code /2/.                                 
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with POD code /2/.                                 
                                                                  
  MT=203 (n,xp) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT=204 (n,xd) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT=205 (n,xt) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT=206 (n,xHe3) cross section                                   
    Calculated with POD code /2/.                                 
                                                                  
  MT=207 (n,xa) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with POD code /2/.                                 
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 17 (n,3n) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 32 (n,nd) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 51 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 52 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 53 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 54 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 55 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 56 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 57 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 58 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 59 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 60 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 61 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 62 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 63 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 64 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 65 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 66 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 67 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 68 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 69 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 70 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 71 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 72 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 73 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 74 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 75 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 76 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 77 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 78 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 79 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 80 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 81 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 82 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 83 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 84 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 85 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 86 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 87 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 91 (n,n') reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 203 (n,xp) reaction                                         
    Proton spectra calculated with POD/2/.                        
                                                                  
  MT= 204 (n,xd) reaction                                         
    Deuteron spectra calculated with POD/2/.                      
                                                                  
  MT= 205 (n,xt) reaction                                         
    Triton spectra calculated with POD/2/.                        
                                                                  
  MT= 206 (n,xHe3) reaction                                       
    He3 spectra calculated with POD/2/.                           
                                                                  
  MT= 207 (n,xa) reaction                                         
    Alpha spectra calculated with POD/2/.                         
                                                                  
MF=12 Gamma-ray multiplicities                                    
  MT=  3 Non-elastic gamma emission                               
    Calculated with POD code /2/.                                 
                                                                  
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 with POD code /2/.                                 
                                                                  
                                                        
                                                                  
***************************************************************   
*        Nuclear Model Calculations with POD Code /2/     *       
***************************************************************   
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 preequilibrim 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.                               
                                                                  
2. Optical model parameters                                       
Neutrons:                                                         
  Coupled-channel optical model parameters /3/                    
Protons:                                                          
  Koning and Delaroche /4/                                        
Deuterons:                                                        
  Lohr and Haeberli /5/                                           
Tritons:                                                          
  Becchetti and Greenlees /6/                                     
He-3:                                                             
  Becchetti and Greenlees /6/                                     
Alphas:                                                           
  Lemos /7/ potentials modified by Arthur and Young /8/           
                                                                  
3. Level scheme of I -130                                         
  -------------------------                                       
   No.   Ex(MeV)     J  PI                                        
  -------------------------                                       
    0    0.00000     5   +                                        
    1    0.03995     2   +                                        
    2    0.04325     2   +                                        
    3    0.04394     3   -                                        
    4    0.04433     4   +                                        
    5    0.04883     4   +                                        
    6    0.06220     2   +                                        
    7    0.06959     6   -                                        
    8    0.08240     2   -                                        
    9    0.08240     2   +                                        
   10    0.08511     6   -                                        
   11    0.09176     4   -                                        
   12    0.09371     3   +                                        
   13    0.11106     5   -                                        
   14    0.12576     4   +                                        
   15    0.18030     6   -                                        
   16    0.20974     2   +                                        
   17    0.22398     3   +                                        
   18    0.22440     4   +                                        
   19    0.24510     5   -                                        
   20    0.25155     3   +                                        
   21    0.25479     3   +                                        
   22    0.26205     3   +                                        
   23    0.26470     5   +                                        
   24    0.29604     4   -                                        
   25    0.34960     2   +                                        
   26    0.35373     4   -                                        
   27    0.37468     4   +                                        
   28    0.37835     5   -                                        
   29    0.42860     4   -                                        
   30    0.43764     4   +                                        
   31    0.46091     5   -                                        
   32    0.48070     4   -                                        
   33    0.52588     3   +                                        
   34    0.53160     4   -                                        
   35    0.54497     3   +                                        
   36    0.59399     5   -                                        
   37    0.60655     5   -                                        
  -------------------------                                       
  Levels above  0.61655 MeV are assumed to be continuous.         
                                                                  
4. Level density parameters                                       
 Energy-dependent parameters of Mengoni-Nakajima /9/ were used    
  ----------------------------------------------------------      
  Nuclei    a*    Pair    Esh     T     E0    Ematch Elv_max      
          1/MeV   MeV     MeV    MeV    MeV    MeV    MeV         
  ----------------------------------------------------------      
  I -131  15.478  1.048 -1.637  0.768 -0.998  7.174  1.936        
  I -130  15.949  0.000 -0.675  0.730 -2.268  6.187  0.607        
  I -129  15.276  1.057 -0.097  0.665 -0.447  5.960  1.401        
  I -128  16.656  0.000  0.638  0.607 -1.637  4.766  0.613        
  Te-130  16.035  2.105 -2.605  0.776  0.214  8.076  2.878        
  Te-129  20.890  1.057 -1.466  0.582 -0.739  5.889  0.967        
  Te-128  15.825  2.121 -0.936  0.754 -0.273  8.576  2.508        
  Sb-128  15.742  0.000 -2.373  0.850 -2.827  7.493  0.078        
  Sb-127  15.073  1.065 -1.601  0.710 -0.225  5.924  2.373        
  Sb-126  15.534  0.000 -0.617  0.741 -2.251  6.198  0.128        
  ----------------------------------------------------------      
                                                                  
5. Gamma-ray strength functions                                   
   M1, E2: Standard Lorentzian (SLO)                              
   E1    : Generalized Lorentzian (GLO) /10/                      
                                                                  
6. Preequilibrium process                                         
   Preequilibrium is on for n, p, d, t, He-3, and alpha.          
   Preequilibrium capture is on.                                  
                                                                  
References                                                        
 1) S.F.Mughabghab, Atlas of Neutron Resonances, Elsevier,        
    (2006).                                                       
 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).      
 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).      
 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).           
 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization               
    Phenomena in Nuclear Reactions," p.682, The University        
    of Wisconsin Press (1971).                                    
 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972).             
 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980).                     
 9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151         
    (1994).                                                       
10) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).