62-Sm-144

 62-Sm-144 JAEA       EVAL-Nov09 N.Iwamoto                        
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 6225                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-11 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             
    THE RESOLVED RESONANCE PARAMETERS WERE EVALUATED ON THE BASIS 
      OF THE DATA RECENTLY MEASURED BY MACKLIN ET AL./1/          
      FOR RESONANCES WHOSE NEUTRON WIDTH WAS NOT MEASURED, THE    
      NEUTRON WIDTH WAS OBTAINED FROM THE CAPTURE AREA ASSUMING   
      THE RADIATION WIDTH OF 0.074 EV AND 0.089 EV FOR THE S-WAVE 
      AND P-WAVE RESONANCES, RESPECTIVELY.  FOR P-WAVE RESONANCES,
      THE VALUE OF THE TOTAL SPIN J WAS ARBITRARILY ASSIGNED WITH 
      THE RATIO 1:2 IN THE NUMBER OF THE RESONANCES WITH J=1/2    
      AND J=3/2.  TO REPRODUCE THE THERMAL CROSS SECTION OF       
      1.64+-0.10 B AT 0.0253 EV/2/, A NEGATIVE RESONANCE WAS      
      ADDED AT -104 EV.  THE EFFECTIVE SCATTERING RADIUS WAS      
      EMPLOYED FROM THE MEASURED DATA BY MACKLIN ET AL./1/        
                                                                  
    Unresolved resonance region : 10.0 keV - 160.0 keV            
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /3/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      CCOM /4/ and CCONE /5/. 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           2.4027e+00                                 
       Elastic         7.6157e-01                                 
       n,gamma         1.6411e+00           1.8549e+00            
       n,alpha         3.0297e-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 /5/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 44 (n,n2p) cross section                                    
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /5/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /5/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /5/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /5/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /5/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /5/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /5/.                               
                                                                  
  MT=108 (n,2a) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT=111 (n,2p) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT=112 (n,pa) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT=115 (n,pd) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /5/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 44 (n,n2p) reaction                                         
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /5/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /5/.                               
                                                                  
  MT=108 (n,2a) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT=111 (n,2p) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT=112 (n,pa) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT=115 (n,pd) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /5/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,1,5,6 (see Table 1)                       
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./6/ (+)                      
      proton   omp: Koning,A.J. and Delaroche,J.P./7/             
      deuteron omp: Lohr,J.M. and Haeberli,W./8/                  
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./9/      
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./9/      
      alpha    omp: McFadden,L. and Satchler,G.R./10/ (+)         
      (+) omp parameters were modified.                           
                                                                  
  2) Two-component exciton model/11/                              
    * Global parametrization of Koning-Duijvestijn/12/            
      was used.                                                   
    * Gamma emission channel/13/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/14/ 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/15/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of generalized Lorentzian form  
      /16/,/17/ 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-144                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +  *                                           
   1  1.66003   2  +  *                                           
   2  1.81017   3  -                                              
   3  2.12000   0  +                                              
   4  2.16700   3  -                                              
   5  2.19089   4  +  *                                           
   6  2.32360   6  +  *                                           
   7  2.42321   2  +                                              
   8  2.47765   0  +                                              
   9  2.58778   4  +                                              
  10  2.64470   1  +                                              
  11  2.66069   2  +                                              
  12  2.68839   3  +                                              
  13  2.70704   5  +                                              
  14  2.72900   1  +                                              
  15  2.79965   2  +                                              
  16  2.80400   2  +                                              
  17  2.82252   0  +                                              
  18  2.82571   5  -                                              
  19  2.82700   0  +                                              
  -------------------                                             
  *) 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-145 16.2400  0.9965 -0.2231  0.5462  0.3438  3.9136         
   Sm-144 16.1000  2.0000 -1.0862  0.6960  0.2760  7.1522         
   Sm-143 20.5000  1.0035 -0.2532  0.3689  0.8950  2.4246         
   Sm-142 17.2820  2.0140  0.2631  0.5569  0.9064  5.5796         
   Pm-144 17.3850  0.0000 -0.0322  0.6228 -1.7232  4.6797         
   Pm-143 16.6639  1.0035 -0.8001  0.5676  0.2359  4.2170         
   Pm-142 17.1803  0.0000 -0.2854  0.5225 -0.6526  2.8315         
   Pm-141 16.4637  1.0106  0.6651  0.6120 -0.5464  5.3348         
   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         
   Nd-141 17.8113  1.0106 -0.4633  0.5388  0.1405  4.2362         
   Nd-140 17.0742  2.0284  0.1378  0.5639  0.9372  5.6042         
   Nd-139 17.6073  1.0178  0.9560  0.5563 -0.3594  4.8725         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Sm-145                   
  --------------------------------------------------------        
  * E1: ER = 14.92 (MeV) EG = 4.54 (MeV) SIG = 358.40 (mb)        
  * M1: ER =  7.80 (MeV) EG = 4.00 (MeV) SIG =   0.67 (mb)        
  * E2: ER = 11.99 (MeV) EG = 4.37 (MeV) SIG =   3.61 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) MACKLIN,R.L. ET AL.: PHYS. REV., C48, 1120 (1993).            
 2) ALEXANDER,C.W. ET AL.: NUCL. SCI. ENG., 95, 194 (1987).       
 3) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 4) Iwamoto,O.: JAERI-Data/Code 2003-020 (2003).                  
 5) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 6) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 7) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
 8) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
 9) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
10) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966).    
11) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
12) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
13) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
14) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
15) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
16) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
17) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).