61-Pm-147

 61-Pm-147 JAEA       EVAL-Dec09 N.Iwamoto                        
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 6149                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-12 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 resonances                       
    RESOLVED RESONANCE PARAMETERS FOR MLBW FORMULA (BELOW 102 EV) 
      FOR JENDL-3, THE EXISTING JENDL-2 DATA WERE ENTIRELY        
      REPLACED BY NEW EVALUATION MENTIONED BELOW.  THE RADIATION  
      WIDTHS AND NEUTRON WIDTHS WERE ADOPTED FROM REF./1/.  THE   
      ORBITAL ANGULAR MOMENTUM L WAS ASSIGNED BY TAKING INTO      
      ACCOUNT THE MAGNITUDE OF NEUTRON WIDTHS.  TOTAL SPIN J OF   
      SOME RESONANCES WAS TENTATIVELY ESTIMATED WITH A RANDOM     
      NUMBER METHOD.  SCATTERING RADIUS OF 8.21 FM WAS ESTIMETED  
      FROM THE MEASURED VALUES FOR ADJACENT NUCLIDES/1/.  A       
      NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE THERMAL 
      CAPTURE AND ELASTIC SCATTERING CROSS SECTIONS GIVEN BY      
      MUGHABGHAB/1/.                                              
                                                                  
    Unresolved resonance region : 102.0 eV - 100.0 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           1.8871e+02                                 
       Elastic         2.0979e+01                                 
       n,gamma         1.6773e+02           2.1876e+03            
       n,alpha         1.0533e-03                                 
      ----------------------------------------------------------  
         (*) 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= 25 (n,3na) 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= 41 (n,2np) 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= 25 (n,3na) 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= 41 (n,2np) 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: 0,3,14 (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 Pm-147                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000  7/2 +  *                                           
   1  0.09110  5/2 +                                              
   2  0.35000  5/2 -                                              
   3  0.38000  9/2 +  *                                           
   4  0.40820  9/2 +                                              
   5  0.41051  3/2 +                                              
   6  0.48925  7/2 +                                              
   7  0.50000  5/2 +                                              
   8  0.53101  5/2 +                                              
   9  0.62000  5/2 +                                              
  10  0.63280  1/2 +                                              
  11  0.64130  5/2 +                                              
  12  0.64930 11/2 -                                              
  13  0.66000  9/2 +                                              
  14  0.66720 11/2 +  *                                           
  15  0.68046  5/2 +                                              
  16  0.68589  5/2 +                                              
  -------------------                                             
  *) Coupled levels in CC calculation                             
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   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-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         
   Pr-146 17.5893  0.0000  2.4188  0.5462 -1.6453  4.0472         
   Pr-145 16.8637  0.9965  1.7883  0.6002 -0.8883  5.5766         
   Pr-144 15.5000  0.0000  0.9153  0.6715 -1.9662  5.0412         
   Pr-143 16.6639  1.0035  0.4682  0.6161 -0.5920  5.4208         
   Pr-142 16.4000  0.0000 -0.4377  0.7390 -2.6336  6.4135         
   Pr-141 16.4637  1.0106 -1.2280  0.6590 -0.3966  5.5793         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Pm-148                   
  --------------------------------------------------------        
  K0 = 2.040   E0 = 4.500 (MeV)                                   
  * E1: ER = 13.19 (MeV) EG = 3.59 (MeV) SIG = 121.81 (mb)        
        ER = 15.85 (MeV) EG = 5.09 (MeV) SIG = 243.63 (mb)        
  * M1: ER =  7.75 (MeV) EG = 4.00 (MeV) SIG =   1.24 (mb)        
  * E2: ER = 11.91 (MeV) EG = 4.33 (MeV) SIG =   3.45 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) MUGHABGHAB,S.F.: "NEUTRON CROSS SECTIONS, VOL. I, PART B",    
    ACADEMIC PRESS (1984).                                        
 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).