62-Sm-149

 62-Sm-149 JAEA+      EVAL-Nov09 N.Iwamoto,A.Zukeran              
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 6240                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-11 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 0.52 keV     
      Parameters of the lowest 2 levels were evaluated on the     
      basis of data measured by Akyuez et al./1/, Asami et al.    
      /2/ and Pattenden/3/.  The data of Mizumoto/4/ were         
      adopted for other resonances.  The J values were determined 
      according to Marshak/5/, Cauvin et al./6/, Karzhavina et    
      al./7/ and Becvar et al./8/  Radiation widths have been     
      measured for seven resonances and their average value of 62 
      meV was used as a recommended value.                        
      For jendl-3, total spin J of some resonances was            
      tentatively estimated with a random number method.  The     
      parameters of the 1st level were modified so as to reproduce
      the thermal capture cross section and resonance integral    
      /9/.                                                        
      In JENDL-4, the radiations widths for 25.26 - 263.2 eV were 
      replaced with those obtained by Georgiev et al./10/         
                                                                  
    Unresolved resonance region : 520.0 eV - 120.0 keV            
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /11/ so as to reproduce the evaluated total and  
      capture cross sections calculated with optical model code   
      CCOM /12/ and CCONE /13/. 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           4.0723e+04                                 
       Elastic         1.7884e+02                                 
       n,gamma         4.0544e+04           3.5174e+03            
       n,alpha         3.1173e-02                                 
      ----------------------------------------------------------  
         (*) 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 /13/.                              
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 24 (n,2na) cross section                                    
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 33 (n,nt) cross section                                     
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 41 (n,2np) cross section                                    
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /13/.                              
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /13/.                              
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /13/.                              
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /13/.                              
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /13/.                              
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /13/.                              
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /13/.                              
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /13/.                              
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 24 (n,2na) reaction                                         
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 33 (n,nt) reaction                                          
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 41 (n,2np) reaction                                         
    Calculated with CCONE code /13/.                              
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /13/.                              
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /13/.                              
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /13/             
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,3,11,14 (see Table 1)                     
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./14/ (+)                     
      proton   omp: Koning,A.J. and Delaroche,J.P./15/            
      deuteron omp: Lohr,J.M. and Haeberli,W./16/                 
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./17/     
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./17/     
      alpha    omp: McFadden,L. and Satchler,G.R./18/ (+)         
      (+) omp parameters were modified.                           
                                                                  
  2) Two-component exciton model/19/                              
    * Global parametrization of Koning-Duijvestijn/20/            
      was used.                                                   
    * Gamma emission channel/21/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/22/ 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/23/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of enhanced generalized         
      Lorentzian form/24/,/25/ 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 Sm-149                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000  7/2 -  *                                           
   1  0.02251  5/2 -                                              
   2  0.27708  5/2 -                                              
   3  0.28594  9/2 -  *                                           
   4  0.35004  3/2 -                                              
   5  0.39909  1/2 -                                              
   6  0.52860  3/2 -                                              
   7  0.55837  5/2 -                                              
   8  0.59089  9/2 -                                              
   9  0.63646  7/2 -                                              
  10  0.65860  5/2 +                                              
  11  0.66405 11/2 -  *                                           
  12  0.69700  3/2 -                                              
  13  0.70986  3/2 -                                              
  14  0.74755 13/2 -  *                                           
  15  0.78523  5/2 -                                              
  16  0.78947 11/2 +                                              
  17  0.83041  9/2 -                                              
  18  0.83323  7/2 +                                              
  19  0.83559  7/2 -                                              
  20  0.87864 13/2 +                                              
  21  0.88194  7/2 -                                              
  22  0.92548  5/2 +                                              
  23  0.95278  5/2 +                                              
  24  0.96700  1/2 +                                              
  25  0.99460 11/2 +                                              
  26  1.01200  1/2 +                                              
  27  1.03900  5/2 -                                              
  28  1.04800  3/2 +                                              
  29  1.08300  1/2 +                                              
  30  1.11300  1/2 +                                              
  31  1.12300  1/2 +                                              
  32  1.13245  1/2 +                                              
  33  1.15400  1/2 +                                              
  34  1.17320  1/2 +                                              
  35  1.18100  1/2 +                                              
  36  1.18700  5/2 -                                              
  37  1.19272 13/2 +                                              
  38  1.19500  1/2 +                                              
  -------------------                                             
  *) Coupled levels in CC calculation                             
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Sm-150 19.2000  1.9596  3.2458  0.5078  0.1619  6.0033         
   Sm-149 19.2000  0.9831  2.9030  0.5042 -0.6887  4.8887         
   Sm-148 18.4000  1.9728  2.0339  0.5337  0.3686  5.9610         
   Sm-147 18.4207  0.9897  1.4097  0.5385 -0.5090  4.9131         
   Pm-149 17.2625  0.9831  3.6138  0.5926 -1.4731  6.0264         
   Pm-148 18.3000  0.0000  2.8623  0.4670 -1.0648  3.0412         
   Pm-147 17.0632  0.9897  2.3331  0.6101 -1.2455  5.9682         
   Pm-146 17.5893  0.0000  1.5389  0.5962 -1.9822  4.7135         
   Pm-145 16.8637  0.9965  0.9449  0.5991 -0.6199  5.3282         
   Nd-148 21.1000  1.9728  2.8636  0.4784  0.2048  5.9010         
   Nd-147 19.7000  0.9897  2.4886  0.4934 -0.5694  4.7470         
   Nd-146 18.1900  1.9863  1.6792  0.5692  0.1138  6.4542         
   Nd-145 18.5400  0.9965  1.1101  0.5235 -0.2928  4.6189         
   Nd-144 17.5000  2.0000  0.3419  0.6111  0.2496  6.6190         
   Nd-143 17.7000  1.0035 -0.4179  0.5516  0.0353  4.4179         
   Nd-142 15.0000  2.0140 -1.2557  0.6895  0.7987  6.4278         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Sm-150                   
  --------------------------------------------------------        
  K0 = 1.660   E0 = 4.500 (MeV)                                   
  * E1: ER = 14.61 (MeV) EG = 5.97 (MeV) SIG = 312.00 (mb)        
  * M1: ER =  7.72 (MeV) EG = 4.00 (MeV) SIG =   1.64 (mb)        
  * E2: ER = 11.86 (MeV) EG = 4.31 (MeV) SIG =   3.54 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Akyuez, OE.R., et al.: CNAEM-52 (1968).                       
 2) Asami, T., et al.: J. Phys. Soc. Jpn., 26, 225 (1969).        
 3) Pattenden, N.J.: Nucl. Sci. Eng., 17, 371 (1963).             
 4) Mizumoto, M.: Nucl. Phys., A357, 90 (1981).                   
 5) Marshak, H., et al.: Phys. Rev., 128, 1287 (1967).            
 6) Cauvin, B., et al.: "Proc. 3rd Conf. on Neutron Cross         
    Sections and Technol., Knoxville 1971", 785.                  
 7) Karzhavina, E.N., et al. JINER-P3-6237 (1972).                
 8) Becvar, F., et al.: Nucl. Phys., A236, 173 (1974).            
 9) Mughabghab, S.F.: "Neutron Cross Sections, Vol. I, Part B",   
    Academic Press (1984).                                        
10) Georgiev, G., et al.: Nucl. Phys., A565, 643 (1993).          
11) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
12) Iwamoto,O.: JAERI-Data/Code 2003-020 (2003).                  
13) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
14) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
15) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
16) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
17) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
18) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966).    
19) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
20) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
21) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
22) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
23) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
24) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
25) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).