76-Os-188

 76-Os-188 JAEA       EVAL-Jan10 N.Iwamoto                        
                      DIST-MAY10                       20100121   
----JENDL-4.0         MATERIAL 7637                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
10-01 The resolved resonance parameters were evaluated by         
      N.Iwamoto.                                                  
      The data above the resolved resonance region were evaluated 
      and compiled by N.Iwamoto.                                  
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2  Resonance parameters                                       
  MT=151 Resolved and unresolved resonance parameters             
    Resolved resonance region: below 5.0 keV                      
      Resolved resonance parameters were taken from Mughabghab    
      /1/. The negative resonance was placed so as to             
      reproduce the cross sections at thermal energy recommended  
      by Mughabghab /1/.                                          
                                                                  
    Unresolved resonance region : 5.0 keV - 200 keV               
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /2/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      CCOM /3/ and CCONE /4/. 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. (*)        
                        (barn)               (barn)               
      ----------------------------------------------------------  
       Total           1.3230e+01                                 
       Elastic         7.7271e+00                                 
       n,gamma         5.5029e+00           1.5400e+02            
       n,alpha         1.2351e-05                                 
      ----------------------------------------------------------  
         (*) 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                         
    Obtained by subtracting non-elastic scattering cross sections 
      from total cross section.                                   
                                                                  
  MT=  4 (n,n') cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 24 (n,2na) cross section                                    
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 33 (n,nt) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /4/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /4/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /4/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /4/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 24 (n,2na) reaction                                         
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 33 (n,nt) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /4/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /4/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /4/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,1,2,5,17 (see Table 1)                    
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./5/ (+)                      
      proton   omp: Koning,A.J. and Delaroche,J.P./6/             
      deuteron omp: Lohr,J.M. and Haeberli,W./7/                  
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./8/      
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./8/      
      alpha    omp: Huizenga,J.R. and Igo,G./9/                   
      (+) omp parameters were modified.                           
                                                                  
  2) Two-component exciton model/10/                              
    * Global parametrization of Koning-Duijvestijn/11/            
      was used.                                                   
    * Gamma emission channel/12/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/13/ was applied.               
    * Neutron, proton, deuteron, triton, He3, alpha and gamma     
      decay channel were taken into account.                      
    * Transmission coefficients of neutrons were taken from       
      optical model calculation.                                  
    * The level scheme of the target is shown in Table 1.         
    * Level density formula of constant temperature and Fermi-gas 
      model were used with shell energy correction/14/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of enhanced generalized         
      Lorentzian form/15/,/16/ was used for E1 transition.        
      For M1 and E2 transitions the standard Lorentzian form was  
      adopted. The prameters are shown in Table 3.                
                                                                  
                                                                  
------------------------------------------------------------------
                              Tables                              
------------------------------------------------------------------
                                                                  
Table 1. Level Scheme of Os-188                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +  *                                           
   1  0.15502   2  +  *                                           
   2  0.47794   4  +  *                                           
   3  0.63301   2  +                                              
   4  0.78998   3  +                                              
   5  0.94031   6  +  *                                           
   6  0.96565   4  +                                              
   7  1.08636   0  +                                              
   8  1.18086   5  +                                              
   9  1.27909   4  +                                              
  10  1.30482   2  +                                              
  11  1.41378   3  -                                              
  12  1.42484   6  +                                              
  13  1.44350   1  -                                              
  14  1.45753   2  +                                              
  15  1.46251   2  -                                              
  16  1.47804   0  +                                              
  17  1.51470   8  +  *                                           
  18  1.51610   5  +                                              
  19  1.56670   4  +                                              
  20  1.57700   2  +                                              
  21  1.62048   2  +                                              
  22  1.66866   5  -                                              
  23  1.68529   3  +                                              
  24  1.68550   7  +                                              
  25  1.70427   0  +                                              
  26  1.72942   2  +                                              
  27  1.74650   2  -                                              
  28  1.76540   0  +                                              
  29  1.77100   7  -                                              
  30  1.80761   2  +                                              
  31  1.82494   0  +                                              
  32  1.84292   0  +                                              
  33  1.85500   0  +                                              
  34  1.87790   0  +                                              
  35  1.89300   0  +                                              
  36  1.93690   0  +                                              
  37  1.94102   0  +                                              
  38  1.94860   0  +                                              
  39  1.95709   0  +                                              
  40  1.96498   2  +                                              
  -------------------                                             
  *) Coupled levels in CC calculation                             
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Os-189 23.6000  0.8729  0.7207  0.5092 -1.1969  5.5241         
   Os-188 23.1000  1.7504  0.7049  0.4799  0.1757  5.6719         
   Os-187 22.9000  0.8775  0.9894  0.5173 -1.2331  5.5812         
   Os-186 21.7766  1.7598  1.0161  0.5003  0.1144  5.8222         
   Re-188 22.0000  0.0000  0.8388  0.4802 -1.4013  3.6931         
   Re-187 20.9976  0.8775  1.0287  0.5196 -0.8390  5.1039         
   Re-186 21.4000  0.0000  0.9320  0.4744 -1.2480  3.4655         
   Re-185 20.8032  0.8823  1.1055  0.4981 -0.5577  4.6703         
    W-187 23.5700  0.8775  1.1868  0.4614 -0.6754  4.6629         
    W-186 23.1400  1.7598  1.2307  0.4935 -0.1424  6.0929         
    W-185 22.7200  0.8823  1.2247  0.4842 -0.8101  4.9225         
    W-184 22.1100  1.7693  1.2350  0.5106 -0.1439  6.1796         
    W-183 21.5000  0.8871  1.1150  0.5015 -0.7444  4.9247         
    W-182 21.6000  1.7790  1.2320  0.4968  0.1520  5.7824         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Os-189                   
  --------------------------------------------------------        
  K0 = 1.700   E0 = 4.500 (MeV)                                   
  * E1: ER = 12.68 (MeV) EG = 2.71 (MeV) SIG = 268.00 (mb)        
        ER = 14.68 (MeV) EG = 3.62 (MeV) SIG = 395.00 (mb)        
        ER =  5.50 (MeV) EG = 1.10 (MeV) SIG =   2.50 (mb)        
        ER =  1.70 (MeV) EG = 0.50 (MeV) SIG =   0.04 (mb)        
  * M1: ER =  7.14 (MeV) EG = 4.00 (MeV) SIG =   1.22 (mb)        
  * E2: ER = 10.98 (MeV) EG = 3.84 (MeV) SIG =   4.74 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Mughabghab,S.F.: "Atlas of Neutron Resonances, Fifth          
    Edition: Resonance Parameters and Thermal Cross Sections.     
    Z=1-100", Elsevier Science (2006).                            
 2) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 3) Iwamoto,O.: JAERI-Data/Code 2003-020 (2003).                  
 4) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 5) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 6) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
 7) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
 8) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
 9) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
10) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
11) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
12) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
13) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
14) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
15) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
16) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).