65-Tb-159

 65-Tb-159 JAEA+      EVAL-Dec09 N.Iwamoto,A.Zukeran              
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 6525                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-12 The resolved resonance parameters were evaluated by         
      A.Zukeran.                                                  
      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 1.188keV      
      In the JENDL-2 evaluation, resonance parameters were mainly 
      taken from the experimental data by Ohkubo and Kawarasaki   
      /1/ and by Derrien and Alix/2/.  The average radiation      
      width was assumed to be 0.097 eV.  A negative resonance was 
      added at -0.1 eV so as to reproduce the capture cross       
      section of 25.5+-1.1 barns and the elastic scattering of    
      20+-2 barns at 0.0253 eV/3/.  Scattering radius of 8.3 fm   
      was taken from the recommendation by Mughabghab and Garber  
      /3/.                                                        
      In JENDL-4, the data for 3.36 - 14.5 eV were replaced with  
      the ones obtained by Vertebnyj et al./4/  The parameters    
      for the negative resonance were re-adjusted.  The scattering
      radius was changed to 7.8 fm.                               
                                                                  
    Unresolved resonance region : 1.188 keV - 130.0 keV           
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /5/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      OPTMAN /6/ and CCONE /7/. 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           3.0033e+01                                 
       Elastic         6.8988e+00                                 
       n,gamma         2.3134e+01           4.0913e+02            
       n,alpha         2.1716e-09                                 
      ----------------------------------------------------------  
         (*) 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 /7/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 33 (n,nt) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 41 (n,2np) cross section                                    
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /7/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /7/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /7/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /7/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /7/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /7/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /7/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /7/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 33 (n,nt) reaction                                          
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 41 (n,2np) reaction                                         
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /7/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /7/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /7/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,1,2,3,5,10,17 (see Table 1)               
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./8/ (+)                      
      proton   omp: Koning,A.J. and Delaroche,J.P./9/ (+)         
      deuteron omp: Lohr,J.M. and Haeberli,W./10/                 
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./11/     
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./11/     
      alpha    omp: McFadden,L. and Satchler,G.R./12/ (+)         
      (+) omp parameters were modified.                           
                                                                  
  2) Two-component exciton model/13/                              
    * Global parametrization of Koning-Duijvestijn/14/            
      was used.                                                   
    * Gamma emission channel/15/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/16/ 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/17/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of enhanced generalized         
      Lorentzian form/18/,/19/ 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 Tb-159                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000  3/2 +  *                                           
   1  0.05800  5/2 +  *                                           
   2  0.13750  7/2 +  *                                           
   3  0.24115  9/2 +  *                                           
   4  0.34828  5/2 +                                              
   5  0.36205 11/2 +  *                                           
   6  0.36355  5/2 -                                              
   7  0.38840  7/2 -                                              
   8  0.42820  7/2 +                                              
   9  0.45460  9/2 -                                              
  10  0.51040 13/2 +  *                                           
  11  0.53200  9/2 +                                              
  12  0.53670  7/2 +                                              
  13  0.54510 11/2 -                                              
  14  0.54760  7/2 -                                              
  15  0.58081  1/2 +                                              
  16  0.61762  3/2 +                                              
  17  0.66891 15/2 +  *                                           
  18  0.67424  5/2 +                                              
  19  0.67790  9/2 -                                              
  20  0.76130  7/2 +                                              
  21  0.77710  7/2 +                                              
  22  0.79900 15/2 -                                              
  23  0.82220 11/2 -                                              
  24  0.85496  1/2 -                                              
  25  0.85730  9/2 +                                              
  -------------------                                             
  *) Coupled levels in CC calculation                             
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Tb-160 18.9000  0.0000  2.5855  0.5446 -1.9885  4.4661         
   Tb-159 21.0000  0.9517  2.9024  0.4767 -0.7563  4.8234         
   Tb-158 19.3000  0.0000  3.0376  0.4617 -1.2200  3.2269         
   Tb-157 18.0565  0.9577  3.3696  0.5538 -1.1365  5.5068         
   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         
   Eu-154 19.2000  0.0000  3.6717  0.5485 -2.4486  4.8922         
   Eu-153 17.3400  0.9701  3.8805  0.5963 -1.6297  6.1695         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Tb-160                   
  --------------------------------------------------------        
  K0 = 1.900   E0 = 4.500 (MeV)                                   
  * E1: ER = 12.22 (MeV) EG = 2.34 (MeV) SIG = 160.00 (mb)        
        ER = 15.67 (MeV) EG = 4.97 (MeV) SIG = 220.00 (mb)        
        ER =  5.60 (MeV) EG = 1.80 (MeV) SIG =   5.00 (mb)        
        ER =  3.00 (MeV) EG = 1.50 (MeV) SIG =   0.60 (mb)        
  * M1: ER =  7.55 (MeV) EG = 4.00 (MeV) SIG =   1.37 (mb)        
  * E2: ER = 11.60 (MeV) EG = 4.19 (MeV) SIG =   3.75 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Ohkubo, M. and Kawarasaki, Y.: JAERI-M 7545 (1978).           
 2) Derrien, H. and Alix, M.: CEA-N-1867 (1975).                  
 3) Mughabghab, S.F. and  Garber, D.I.: "Neutron Cross Sections,  
    Vol. 1, Resonance Parameters", BNL 325, 3rd ed., Vol. 1,      
    (1973).                                                       
 4) Vertebnyj, V.P. et al.: 83 Kiev, 3, 37 (1983).                
 5) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 6) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).   
 7) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 8) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 9) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
10) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
11) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
12) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966).    
13) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
14) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
15) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
16) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
17) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
18) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
19) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).