26-Fe- 59

 26-Fe- 59 JAEA       EVAL-FEB09 K.Shibata                        
                      DIST-MAY10                       20091112   
----JENDL-4.0         MATERIAL 2640                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
                                                                  
History                                                           
09-02 Model calcualtion was performed using the POD code.         
09-11 Data were compiled by K. Shibata, JAEA.                     
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2 Resonance parameters                                        
  MT=151                                                          
    No resolved resonance parameters is given.                    
    Unresolved resonance parameters were calculated using the     
    ASREP code /1/ from 1.7 keV to 200 keV.  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           1.2605E+01                                   
     Elastic         6.5681E+00                                   
     n,gamma         6.0024E+00           2.8088E+00              
    ----------------------------------------------------------    
       (*) 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                         
    Obtained by subtracting non-elastic cross sections from total 
    cross sections.                                               
                                                                  
  MT=  3 Non-elastic cross section                                
    Sum of partial non-elastic cross sections.                    
                                                                  
  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/ above 1.7 keV.  A value of       
    6.0 b at thermal was obtained from the work of Knie et al.    
    /3/ and extrapolated as 1/v form up to 1.7 keV.               
                                                                  
  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= 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 /4/                    
Protons:                                                          
  Koning and Delaroche /5/                                        
Deuterons:                                                        
  Lohr and Haeberli /6/                                           
Tritons:                                                          
  Becchetti and Greenlees /7/                                     
He-3:                                                             
  Becchetti and Greenlees /7/                                     
Alphas:                                                           
  Lemos /8/ potentials modified by Arthur and Young /9/           
                                                                  
3. Level scheme of Fe- 59                                         
  -------------------------                                       
   No.   Ex(MeV)     J  PI                                        
  -------------------------                                       
    0    0.00000    3/2  -                                        
    1    0.28702    1/2  -                                        
    2    0.47274    5/2  -                                        
    3    0.57087    5/2  -                                        
    4    0.61305    1/2  +                                        
    5    0.64280    7/2  -                                        
    6    0.72643    3/2  -                                        
    7    1.02315    7/2  -                                        
    8    1.07781    3/2  -                                        
    9    1.16210    3/2  -                                        
   10    1.21133    1/2  -                                        
   11    1.51724    9/2  +                                        
   12    1.56990    5/2  -                                        
   13    1.64800    5/2  +                                        
   14    1.74978    5/2  -                                        
   15    1.91892    5/2  +                                        
   16    1.96197    1/2  -                                        
   17    2.16190    1/2  +                                        
   18    2.27790    5/2  -                                        
   19    2.31225   13/2  +                                        
   20    2.32240    3/2  +                                        
   21    2.34820    7/2  -                                        
   22    2.39000    3/2  +                                        
   23    2.44727    3/2  +                                        
   24    2.49380    7/2  -                                        
  -------------------------                                       
  Levels above  2.50380 MeV are assumed to be continuous.         
                                                                  
4. Level density parameters                                       
 Energy-dependent parameters of Mengoni-Nakajima /10/ were used.  
  ----------------------------------------------------------      
  Nuclei    a*    Pair    Esh     T     E0    Ematch Elv_max      
          1/MeV   MeV     MeV    MeV    MeV    MeV    MeV         
  ----------------------------------------------------------      
  Fe- 60   8.376  3.098  1.194  1.008  1.125  9.601  3.562        
  Fe- 59   8.428  1.562  0.283  1.040 -0.270  8.013  2.494        
  Fe- 58   8.307  3.151 -0.526  1.221  0.265 11.760  4.006        
  Fe- 57   9.205  1.589 -1.308  1.096 -0.485  8.567  3.059        
  Mn- 59   7.894  1.562  2.440  0.853  0.564  6.070  1.351        
  Mn- 58   8.141  0.000  1.029  0.800 -0.379  3.387  1.322        
  Mn- 57   7.671  1.589  0.841  1.225 -1.485 10.432  1.928        
  Cr- 57   8.678  1.589  2.201  0.752  0.823  5.314  0.000        
  Cr- 56   7.911  3.207  1.580  1.044  1.087  9.987  3.675        
  Cr- 55   8.934  1.618  0.427  0.928  0.154  7.011  2.687        
  ----------------------------------------------------------      
                                                                  
5. Gamma-ray strength functions                                   
   M1, E2: Standard Lorentzian (SLO)                              
   E1    : Generalized Lorentzian (GLO) /11/                      
                                                                  
6. Preequilibrium process                                         
   Preequilibrium is on for n, p, d, t, He-3, and alpha.          
   Preequilibrium capture is on.                                  
                                                                  
References                                                        
 1) K.Kikuchi et al., JAERI-Data/Code 99-025 (1999).              
 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 3) K.Knie et al., Nucl. Phys. A723, 343 (2003).                  
 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).      
 5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).      
 6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).           
 7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization               
    Phenomena in Nuclear Reactions," p.682, The University        
    of Wisconsin Press (1971).                                    
 8) O.F.Lemos, Orsay Report, Series A, No.136 (1972).             
 9) E.D.Arthur, P.G.Young, LA-8626-MS (1980).                     
10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151         
    (1994).                                                       
11) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).