37-Rb- 86

 37-Rb- 86 JAEA       EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda 
                      DIST-MAY10                       20091005   
----JENDL-4.0         MATERIAL 3728                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda.        
09-10 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 resovled resonance parameters are given.                   
      The 1/v-shaped capture cross section is assumed below 75 eV.
      At 0.0253 eV, the cross section was normalized to the value 
      of 1.5622, which was adopted in ENDF/B-VII.0.               
      The scattering cross section was calculated from 4*pi*R**2, 
      where the scattering radius R was obtained in the unresolved
      resonance region: R=6.515 fm.                               
    Unresolved resonance region: 75 eV - 380 keV                  
      The parameters were obtained by fitting to the total and    
      capture cross sections calculated from POD /1/.  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           6.9417E+00                                   
     Elastic         5.3699E+00                                   
     n,gamma         1.5629E+00           2.4614E+01              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    Sum of elatic and non-elastic cross sections below 75 eV.     
    Calculated with POD code /1/ above 75 eV.                     
                                                                  
  MT=  2 Elastic scattering cross section                         
    Obtained by subtracting non-elastic cross sections from total 
    cross sections above 75 eV.  A constant value of 5.334 b was  
    assumed below 75 eV.                                          
                                                                  
  MT=  3 Non-elastic cross section                                
    Sum of parial non-elastic cross sections.                     
                                                                  
  MT=  4,51-91 (n,n') cross section                               
    Calculated with POD code /1/.                                 
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT=102 Capture cross section                                    
    Calculated with POD code /1/.                                 
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with POD code /1/.                                 
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with POD code /1/.                                 
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with POD code /1/.                                 
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with POD code /1/.                                 
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with POD code /1/.                                 
                                                                  
  MT=203 (n,xp) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT=204 (n,xd) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT=205 (n,xt) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT=206 (n,xHe3) cross section                                   
    Calculated with POD code /1/.                                 
                                                                  
  MT=207 (n,xa) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with POD code /1/.                                 
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 17 (n,3n) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 32 (n,nd) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 51 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 52 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 53 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 54 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 55 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 56 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 57 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 58 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 59 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 60 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 61 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 62 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 63 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 64 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 65 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 66 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 67 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 68 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 69 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 70 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 71 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 72 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 73 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 74 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 75 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 76 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 77 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 91 (n,n') reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 203 (n,xp) reaction                                         
    Proton spectra calculated with POD/1/.                        
                                                                  
  MT= 204 (n,xd) reaction                                         
    Deuteron spectra calculated with POD/1/.                      
                                                                  
  MT= 205 (n,xt) reaction                                         
    Triton spectra calculated with POD/1/.                        
                                                                  
  MT= 206 (n,xHe3) reaction                                       
    He3 spectra calculated with POD/1/.                           
                                                                  
  MT= 207 (n,xa) reaction                                         
    Alpha spectra calculated with POD/1/.                         
                                                                  
MF=12 Gamma-ray multiplicities                                    
  MT=  3 Non-elastic gamma emission                               
    Calculated with POD code /1/.                                 
                                                                  
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 /1/.                                 
                                                                  
                                                        
                                                                  
***************************************************************   
*        Nuclear Model Calculations with POD Code /1/         *   
***************************************************************   
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 /2/                    
Protons:                                                          
  Koning and Delaroche /3/                                        
Deuterons:                                                        
  Lohr and Haeberli /4/                                           
Tritons:                                                          
  Becchetti and Greenlees /5/                                     
He-3:                                                             
  Becchetti and Greenlees /5/                                     
Alphas:                                                           
  Lemos /6/ potentials modified by Arthur and Young /7/           
                                                                  
3. Level scheme of Rb- 86                                         
  -------------------------                                       
   No.   Ex(MeV)     J  PI                                        
  -------------------------                                       
    0    0.00000     2   -                                        
    1    0.48820     1   +                                        
    2    0.55605     6   -                                        
    3    0.55700     3   -                                        
    4    0.78030     7   -                                        
    5    0.87320     4   -                                        
    6    0.97870     3   -                                        
    7    1.02720     1   +                                        
    8    1.03270     3   -                                        
    9    1.09280     5   -                                        
   10    1.10560     2   +                                        
   11    1.12200     2   +                                        
   12    1.15600     0   +                                        
   13    1.19640     3   -                                        
   14    1.24800     4   -                                        
   15    1.30510     3   +                                        
   16    1.30900     6   -                                        
   17    1.38940     3   +                                        
   18    1.41200     5   -                                        
   19    1.43900     3   -                                        
   20    1.47080     2   +                                        
   21    1.50170     3   +                                        
   22    1.55000     6   -                                        
   23    1.55850     7   +                                        
   24    1.66680     2   +                                        
   25    1.68370     8   +                                        
   26    1.70920     2   +                                        
   27    1.73800     1   -                                        
  -------------------------                                       
  Levels above  1.74800 MeV are assumed to be continuous.         
                                                                  
4. Level density parameters                                       
 Energy-dependent parameters of Mengoni-Nakajima /8/ were used    
  ----------------------------------------------------------      
  Nuclei    a*    Pair    Esh     T     E0    Ematch Elv_max      
          1/MeV   MeV     MeV    MeV    MeV    MeV    MeV         
  ----------------------------------------------------------      
  Rb- 87  10.932  1.287 -0.777  0.871 -0.070  6.722  2.414        
  Rb- 86   9.932  0.000  0.007  0.898 -1.348  5.547  1.738        
  Rb- 85  10.720  1.302  1.529  0.855 -0.855  7.650  2.088        
  Rb- 84  11.060  0.000  2.125  0.783 -1.914  5.688  0.797        
  Kr- 86  11.310  2.588 -0.507  0.715  2.085  6.130  3.575        
  Kr- 85  11.890  1.302  0.718  0.695  0.285  5.433  2.637        
  Kr- 84  11.089  2.619  1.235  0.745  1.364  7.286  3.951        
  Br- 84  11.060  0.000  0.608  0.898 -2.409  6.862  0.408        
  Br- 83  10.507  1.317  1.382  0.813 -0.276  6.734  2.134        
  Br- 82  10.599  0.000  2.092  0.832 -2.117  6.154  1.261        
  ----------------------------------------------------------      
                                                                  
5. Gamma-ray strength functions                                   
   M1, E2: Standard Lorentzian (SLO)                              
   E1    : Generalized Lorentzian (GLO) /9/                       
                                                                  
6. Preequilibrium process                                         
   Preequilibrium is on for n, p, d, t, He-3, and alpha.          
   Preequilibrium capture is on.                                  
                                                                  
References                                                        
 1) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 2) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007).      
 3) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).      
 4) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).           
 5) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization               
    Phenomena in Nuclear Reactions," p.682, The University        
    of Wisconsin Press (1971).                                    
 6) O.F.Lemos, Orsay Report, Series A, No.136 (1972).             
 7) E.D.Arthur, P.G.Young, LA-8626-MS (1980).                     
 8) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151         
    (1994).                                                       
 9) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).