64-Gd-158

 64-Gd-158 JAEA+      EVAL-Dec09 N.Iwamoto,A.Zukeran,K.Shibata    
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 6443                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-12 The resolved resonance parameters were evaluated by         
      A.Zukeran,K.Shibata.                                        
      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 (MLBW formula): below 6.58 keV      
      In JENDL-3.3, parameters were mainly taken from the         
      experimental data of Rahn et al./1/.  The average           
      radiative capture width of 0.088 eV was assumed.  A negative
      resonance was added so as to reproduce the thermal capture  
      cross section given by Mughabghab and Garber/4/.  Scattering
      radius of 6.5 fm was adopted from ref./2/                   
      In JENDL-4, the parameters for 4 resonances between 22.3 and
      277.4 eV were replace with those obtained by Leinweber et   
      al./3/  The energy of the negative resonance was adjusted.  
                                                                  
    Unresolved resonance region : 6.58 keV - 250.0 keV            
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /4/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      CCOM /5/ and CCONE /6/. 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           5.8418e+00                                 
       Elastic         3.6411e+00                                 
       n,gamma         2.2007e+00           7.2063e+01            
       n,alpha         9.1239e-12                                 
      ----------------------------------------------------------  
         (*) 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 /6/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 24 (n,2na) cross section                                    
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /6/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /6/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /6/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /6/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 24 (n,2na) reaction                                         
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /6/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /6/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /6/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,1,2,3,4,15 (see Table 1)                  
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./7/ (+)                      
      proton   omp: Koning,A.J. and Delaroche,J.P./8/             
      deuteron omp: Lohr,J.M. and Haeberli,W./9/                  
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./10/     
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./10/     
      alpha    omp: Huizenga,J.R. and Igo,G./11/                  
      (+) omp parameters were modified.                           
                                                                  
  2) Two-component exciton model/12/                              
    * Global parametrization of Koning-Duijvestijn/13/            
      was used.                                                   
    * Gamma emission channel/14/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/15/ 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/16/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of enhanced generalized         
      Lorentzian form/17/,/18/ 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 Gd-158                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +  *                                           
   1  0.07951   2  +  *                                           
   2  0.26146   4  +  *                                           
   3  0.53902   6  +  *                                           
   4  0.90412   8  +  *                                           
   5  0.97715   1  -                                              
   6  1.02370   2  -                                              
   7  1.04164   3  -                                              
   8  1.15897   4  -                                              
   9  1.17648   5  -                                              
  10  1.18714   2  +                                              
  11  1.19617   0  +                                              
  12  1.25987   2  +                                              
  13  1.26351   1  -                                              
  14  1.26552   3  +                                              
  15  1.35000  10  +  *                                           
  16  1.35847   4  +                                              
  17  1.37194   6  -                                              
  18  1.38063   4  +                                              
  19  1.39100   7  -                                              
  20  1.40294   3  -                                              
  21  1.40670   4  +                                              
  22  1.41400   2  -                                              
  23  1.44000   5  +                                              
  24  1.45235   0  +                                              
  25  1.48142   5  +                                              
  26  1.49910   5  +                                              
  27  1.51748   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         
  --------------------------------------------------------        
   Gd-159 19.9000  0.9517  2.6302  0.5300 -1.1252  5.4620         
   Gd-158 19.3000  1.9093  2.8152  0.5596 -0.4648  6.8458         
   Gd-157 20.0000  0.9577  3.0516  0.5315 -1.2892  5.6268         
   Gd-156 19.0000  1.9215  3.2702  0.5513 -0.3880  6.7098         
   Eu-158 18.8084  0.0000  2.4374  0.4933 -1.3276  3.5000         
   Eu-157 18.0565  0.9577  2.7904  0.5507 -0.9395  5.3155         
   Eu-156 18.0000  0.0000  2.8275  0.5361 -1.7176  4.0906         
   Eu-155 17.9000  0.9639  3.3259  0.5676 -1.2578  5.7030         
   Sm-157 19.4276  0.9577  2.5335  0.5242 -0.9010  5.1968         
   Sm-156 18.7270  1.9215  2.8073  0.5682 -0.4051  6.8309         
   Sm-155 19.5000  0.9639  2.9414  0.5495 -1.3709  5.8007         
   Sm-154 18.5215  1.9340  3.2136  0.5576 -0.3117  6.6726         
   Sm-153 20.0000  0.9701  3.6781  0.5579 -1.8633  6.3072         
   Sm-152 19.7000  1.9467  3.6242  0.5066 -0.0488  6.1904         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Gd-159                   
  --------------------------------------------------------        
  K0 = 2.000   E0 = 4.500 (MeV)                                   
  * E1: ER = 11.70 (MeV) EG = 2.60 (MeV) SIG = 165.00 (mb)        
        ER = 14.90 (MeV) EG = 3.80 (MeV) SIG = 249.00 (mb)        
        ER =  3.20 (MeV) EG = 1.20 (MeV) SIG =   0.20 (mb)        
        ER =  4.90 (MeV) EG = 0.20 (MeV) SIG =   0.30 (mb)        
  * M1: ER =  7.57 (MeV) EG = 4.00 (MeV) SIG =   1.39 (mb)        
  * E2: ER = 11.63 (MeV) EG = 4.20 (MeV) SIG =   3.65 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Rahn, F., et al.: Phys. Rev., C10, 1904 (1974).               
 2) Mughabghab, S.F. and Garber, D.I.: "Neutron Cross Sections,   
    Vol.1, Resonance Parameters", BNL 325, 3rd ed., Vol. 1,       
    (1973).                                                       
 3) Leinweber, G et al.: Nucl. Sci. Eng., 154, 261 (2006).        
 4) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 5) Iwamoto,O.: JAERI-Data/Code 2003-020 (2003).                  
 6) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 7) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 8) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
 9) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
10) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
11) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
12) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
13) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
14) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
15) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
16) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
17) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
18) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).