42-Mo-100

 42-Mo-100 JAEA       EVAL-MAR09 K.Shibata, A.Ichihara, S.Kunieda+
                      DIST-MAY10                       20091211   
----JENDL-4.0         MATERIAL 4249                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-03 The data above the resolved resonance region were evaluated 
      by K.Shibata, A.Ichihara, and S.Kunieda /1/.                
      The resolved resonance parameters were evaluated by         
      T.Nakagawa.                                                 
09-12 Compiled by K.Shibata                                       
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2 Resonance parameters                                        
  MT=151 Resolved and unresolved resoannce parameters             
    Resolved resonance region: below 26 keV                       
      Based on the experimental data of Weigmann et al./2/,       
      Weigmann et al./3/, and Musgrove /4/.                       
      The parameters for 97-eV p-wave resonance were taken from   
      the data of Wang et al./5/.                                 
                                                                  
    Unresolved resonance region: 26 keV - 1 MeV                   
      The parameters were obtained by fitting to the evaluated    
      total and capture cross sections mentioned below.  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           6.2049E+00                                   
     Elastic         6.0111E+00                                   
     n,gamma         1.9382E-01           3.9548E+00              
    ----------------------------------------------------------    
       (*) 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 POD calculations/6/ were accepted above 1 MeV.            
    Below 1 MeV, the cross sections were taken from JENDL-3.3     
    in order to improve the benchmark results with molybdenum     
    reflectors for fast neutrons.                                 
                                                                  
  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 /6/.                                 
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with POD code /6/.                                 
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with POD code /6/.                                 
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with POD code /6/.                                 
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with POD code /6/.                                 
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with POD code /6/.                                 
                                                                  
  MT=102 Capture cross section                                    
    Calculated with POD code /6/.                                 
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with POD code /6/.                                 
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with POD code /6/.                                 
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with POD code /6/.                                 
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with POD code /6/.                                 
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with POD code /6/.                                 
                                                                  
  MT=203 (n,xp) cross section                                     
    Calculated with POD code /6/.                                 
                                                                  
  MT=204 (n,xd) cross section                                     
    Calculated with POD code /6/.                                 
                                                                  
  MT=205 (n,xt) cross section                                     
    Calculated with POD code /6/.                                 
                                                                  
  MT=206 (n,xHe3) cross section                                   
    Calculated with POD code /6/.                                 
                                                                  
  MT=207 (n,xa) cross section                                     
    Calculated with POD code /6/.                                 
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with POD code /6/ above 3.5 MeV.  Below 3.5 MeV,   
    the data were taken from JENDL-3.3 by considering the         
    benchmark results with molybdenum reflectors for fast-neutron 
    cores.                                                        
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with POD/6/.                       
                                                                  
  MT= 17 (n,3n) reaction                                          
    Neutron spectra calculated with POD/6/.                       
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with POD/6/.                       
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with POD/6/.                       
                                                                  
  MT= 32 (n,nd) reaction                                          
    Neutron spectra calculated with POD/6/.                       
                                                                  
  MT= 51 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 52 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 53 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 54 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 55 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 56 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 57 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 58 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 59 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 60 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 61 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 62 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 63 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 64 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 65 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 66 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 67 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 68 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 69 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 70 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 71 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 72 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 73 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 74 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 75 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 76 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 77 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 78 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/6/.         
                                                                  
  MT= 91 (n,n') reaction                                          
    Neutron spectra calculated with POD/6/.                       
                                                                  
  MT= 203 (n,xp) reaction                                         
    Proton spectra calculated with POD/6/.                        
                                                                  
  MT= 204 (n,xd) reaction                                         
    Deuteron spectra calculated with POD/6/.                      
                                                                  
  MT= 205 (n,xt) reaction                                         
    Triton spectra calculated with POD/6/.                        
                                                                  
  MT= 206 (n,xHe3) reaction                                       
    He3 spectra calculated with POD/6/.                           
                                                                  
  MT= 207 (n,xa) reaction                                         
    Alpha spectra calculated with POD/6/.                         
                                                                  
MF=12 Gamma-ray multiplicities                                    
  MT=  3 Non-elastic gamma emission                               
    Calculated with POD code /6/.                                 
                                                                  
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 /6/.                                 
                                                                  
                                                        
                                                                  
***************************************************************   
*        Nuclear Model Calculations with POD Code /6/         *   
***************************************************************   
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 /7/                    
Protons:                                                          
  Koning and Delaroche /8/                                        
Deuterons:                                                        
  Lohr and Haeberli /9/                                           
Tritons:                                                          
  Becchetti and Greenlees /10/                                    
He-3:                                                             
  Becchetti and Greenlees /10/                                    
Alphas:                                                           
  Lemos /11/ potentials modified by Arthur and Young /12/         
                                                                  
3. Level scheme of Mo-100                                         
  -------------------------                                       
   No.   Ex(MeV)     J  PI                                        
  -------------------------                                       
    0    0.00000     0   +                                        
    1    0.53557     2   +                                        
    2    0.69512     0   +                                        
    3    1.06379     2   +                                        
    4    1.13611     4   +                                        
    5    1.46391     2   +                                        
    6    1.50464     0   +                                        
    7    1.60737     3   +                                        
    8    1.76650     2   +                                        
    9    1.77146     4   +                                        
   10    1.84690     6   +                                        
   11    1.90830     3   -                                        
   12    1.97734     2   +                                        
   13    2.03749     0   +                                        
   14    2.04277     2   +                                        
   15    2.08200     2   -                                        
   16    2.08631     0   +                                        
   17    2.10317     4   +                                        
   18    2.15600     1   -                                        
   19    2.18954     0   -                                        
   20    2.20109     2   -                                        
   21    2.28646     2   +                                        
   22    2.31000     6   +                                        
   23    2.32030     4   -                                        
   24    2.33900     5   -                                        
   25    2.36966     3   -                                        
   26    2.39600     1   -                                        
   27    2.41668     3   -                                        
   28    2.43200     1   -                                        
  -------------------------                                       
  Levels above  2.44200 MeV are assumed to be continuous.         
                                                                  
4. Level density parameters                                       
 Energy-dependent parameters of Mengoni-Nakajima /13/ were used   
  ----------------------------------------------------------      
  Nuclei    a*    Pair    Esh     T     E0    Ematch Elv_max      
          1/MeV   MeV     MeV    MeV    MeV    MeV    MeV         
  ----------------------------------------------------------      
  Mo-101  14.580  1.194  4.672  0.645 -1.632  7.428  0.914        
  Mo-100  12.837  2.400  3.838  0.682  0.172  8.104  2.432        
  Mo- 99  13.082  1.206  3.377  0.716 -1.379  7.501  1.405        
  Mo- 98  13.582  2.424  2.452  0.685  0.275  8.035  2.350        
  Nb-100  12.789  0.000  4.702  0.495 -0.696  2.882  0.504        
  Nb- 99  12.177  1.206  4.589  0.647 -0.587  6.199  1.264        
  Nb- 98  12.575  0.000  3.150  0.552 -0.760  3.224  0.226        
  Zr- 98  12.620  2.424  3.955  0.649  0.598  7.460  1.859        
  Zr- 97  12.179  1.218  2.499  0.394  1.420  2.287  2.265        
  Zr- 96  12.403  2.449  2.151  0.635  1.347  6.496  3.608        
  ----------------------------------------------------------      
                                                                  
5. Gamma-ray strength functions                                   
   M1, E2: Standard Lorentzian (SLO)                              
   E1    : Generalized Lorentzian (GLO) /14/                      
                                                                  
6. Preequilibrium process                                         
   Preequilibrium is on for n, p, d, t, He-3, and alpha.          
   Preequilibrium capture is on.                                  
                                                                  
References                                                        
 1) K.Shibata, A.Ichihara, S.Kunieda, J. Nucl. Sci. Technol.,     
    46, 278 (2009).                                               
 2) H.Weigmann et al., Phys. Rev., C20, 115 (1969).               
 3) H.Weigmann et al., 1971 Knoxville, 749 (1971).                
 4) A.R.de L.Musgrove, Nucl. Phys., A270, 108 (1976).             
 5) T.F.Wang et al., Nucl. Instrum. Meth. Phys. Research B, 266,  
    561 (2008).                                                   
 6) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 7) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).      
 8) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).      
 9) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).           
10) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization               
    Phenomena in Nuclear Reactions," p.682, The University        
    of Wisconsin Press (1971).                                    
11) O.F.Lemos, Orsay Report, Series A, No.136 (1972).             
12) E.D.Arthur, P.G.Young, LA-8626-MS (1980).                     
13) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151         
    (1994).                                                       
14) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).