90-Th-227

 90-Th-227 JAEA+      EVAL-JAN10 O.Iwamoto, T.Nakagawa, et al.    
                      DIST-MAY10                       20100303   
----JENDL-4.0         MATERIAL 9025                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
07-06 Theoretical calculation was performed with CCONE code.      
07-11 Re-calculation with CCONE code was done.                    
      Data were compiled as JENDL/AC-2008/1/.                     
09-08 (MF1,MT458) was evaluated.                                  
10-01 Data of prompt gamma rays due to fission were given.        
10-03 Covariance data were given.                                 
                                                                  
                                                                  
MF=1 General information                                          
  MT=452 Number of Neutrons per fission                           
    Sum of MT's=455 and 456.                                      
                                                                  
  MT=455 Delayed neutron data                                     
    (Same as JENDL-3.3)                                           
    Average values of systematics of Tuttle/2/, Benedetti et      
    al./3/ and Waldo et al./4/ were adopted.                      
    Decay constants were calculated by Brady and England/5/.      
                                                                  
  MT=456 Number of prompt neutrons per fission                    
    (Same as JENDL-3.3)                                           
    Based on the systematics recommended by Manero and Konshin/6/ 
    and by Howerton/7/.                                           
                                                                  
  MT=458 Components of energy release due to fission              
    Total energy and prompt energy were calculated from mass      
    balance using JENDL-4 fission yields data and mass excess     
    evaluation. Mass excess values were from Audi's 2009          
    evaluation/8/. Delayed energy values were calculated from     
    the energy release for infinite irradiation using JENDL FP    
    Decay Data File 2000 and JENDL-4 yields data. For delayed     
    neutron energy, as the JENDL FP Decay Data File 2000/9/ does  
    not include average neutron energy values, the average values 
    were calculated using the formula shown in the report by      
    T.R. England/10/. The fractions of prompt energy were         
    calculated using the fractions of Sher's evaluation/11/ when  
    they were provided. When the fractions were not given by Sher,
    averaged fractions were used.                                 
                                                                  
                                                                  
MF= 2 Resonance parameters                                        
  MT=151                                                          
  No resonance parameters are given.                              
                                                                  
                                                                  
     Thermal cross sections and resonance integrals (at 300K)     
    -------------------------------------------------------       
                    0.0253 eV    reson. integ.(*)                 
                     (barns)       (barns)                        
    -------------------------------------------------------       
    total            620.06                                       
    elastic           12.53                                       
    fission          202.08          330                          
    capture          405.16          661                          
    -------------------------------------------------------       
      (*) In the energy range from 0.5 eV to 10 MeV.              
                                                                  
                                                                  
MF= 3 Neutron cross sections                                      
  Below 0.65 eV:                                                  
    Elastic scattering cross section is 12.5 b calculated from    
    scattering radius/12/.                                        
    Fission cross section is in the 1/v shape, and 202 b at       
    0.0253 eV/13/.                                                
    Capture cross section is also in the 1/v shape, and 405       
    b at 0.0253 eV. A capture to fission ratio calculated with    
    CCONE code/12/ at 1 eV was used.                              
                                                                  
  Above 0.65 eV:                                                  
    All the Cross sections were calculated with CCONE code/12/.   
                                                                  
  MT= 1 Total cross section                                       
    The cross section was calculated with CC OMP of Soukhovitskii 
    et al./14/                                                    
                                                                  
                                                                  
MF= 4 Angular distributions of secondary neutrons                 
  MT=2  Elastic scattering                                        
    Calculated with CCONE code/12/.                               
                                                                  
  MT=18 Fission                                                   
    Isotropic distributions in the laboratory system were assumed.
                                                                  
                                                                  
MF= 5 Energy distributions of secondary neutrons                  
  MT=18 Prompt neutrons                                           
    Calculated with CCONE code/12/.                               
                                                                  
  MT=455 Delayed neutrons                                         
    Calculated by Brady and England/5/.                           
                                                                  
                                                                  
MF= 6 Energy-angle distributions                                  
    Calculated with CCONE code/12/.                               
    Distributions from fission (MT=18) are not included.          
                                                                  
                                                                  
MF=12 Photon production multiplicities                            
  MT=18 Fission                                                   
    Calculated from the total energy released by the prompt       
    gamma-rays due to fission given in MF=1/MT=458 and the        
    average energy of gamma-rays.                                 
                                                                  
                                                                  
MF=14 Photon angular distributions                                
  MT=18 Fission                                                   
    Isotoropic distributions were assumed.                        
                                                                  
                                                                  
MF=15 Continuous photon energy spectra                            
  MT=18 Fission                                                   
    Experimental data measured by Verbinski et al./15/ for        
    U-235 thermal fission were adopted.                           
                                                                  
                                                                  
MF=31 Covariances of average number of neutrons per fission       
  MT=452 Number of neutrons per fission                           
    Sum of covariances for MT=455 and MT=456.                     
                                                                  
  MT=455                                                          
    Error of 15% was assumed.                                     
                                                                  
  MT=456                                                          
    Covariance was obtained by fitting a linear function to the   
    at 0.0 and 5.0 MeV with an uncertainty of 5%.                 
                                                                  
                                                                  
MF=33 Covariances of neutron cross sections                       
  Covariances were given to all the cross sections by using       
  KALMAN code/16/ and the covariances of model parameters         
  used in the cross-section calculations.                         
                                                                  
  For the following cross sections, standard deviations in the    
  energy region below 0.65 eV were assumed as follows:            
                                                                  
     Total               33 %                                     
     Elastic scattering  50 %                                     
     Fission              7.7 % estimated from experimental data  
     Capture             50 %                                     
                                                                  
                                                                  
MF=34 Covariances for Angular Distributions                       
  MT=2 Elastic scattering                                         
    Covariances were given only to P1 components.                 
                                                                  
                                                                  
MF=35 Covariances for Energy Distributions                        
  MT=18 Fission spectra                                           
    Estimated with CCONE and KALMAN codes.                        
                                                                  
                                                                  
                                                                  
***************************************************************** 
  Calculation with CCONE code                                     
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE/12/ calculation         
  1) Coupled channel optical model                                
     Levels in the rotational band were included. Optical model   
     potential and coupled levels are shown in Table 1.           
                                                                  
  2) Two-component exciton model/17/                              
    * Global parametrization of Koning-Duijvestijn/18/            
      was used.                                                   
    * Gamma emission channel/19/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Moldauer width fluctuation correction/20/ was included.     
    * Neutron, gamma and fission decay channel were included.     
    * Transmission coefficients of neutrons were taken from       
      coupled channel calculation in Table 1.                     
    * The level scheme of the target is shown in Table 2.         
    * Level density formula of constant temperature and Fermi-gas 
      model were used with shell energy correction and collective 
      enhancement factor. Parameters are shown in Table 3.        
    * Fission channel:                                            
      Double humped fission barriers were assumed.                
      Fission barrier penetrabilities were calculated with        
      Hill-Wheler formula/21/. Fission barrier parameters were    
      shown in Table 4. Transition state model was used and       
      continuum levels are assumed above the saddles. The level   
      density parameters for inner and outer saddles are shown in 
      Tables 5 and 6, respectively.                               
    * Gamma-ray strength function of Kopecky et al/22/,/23/       
      was used. The prameters are shown in Table 7.               
                                                                  
                                                                  
------------------------------------------------------------------
                              Tables                              
------------------------------------------------------------------
                                                                  
Table 1. Coupled channel calculation                              
  --------------------------------------------------              
  * rigid rotor model was applied                                 
  * coupled levels = 0,2,1 (see Table 2)                          
  * optical potential parameters /14/                             
    Volume:                                                       
      V_0       = 49.97    MeV                                    
      lambda_HF = 0.01004  1/MeV                                  
      C_viso    = 15.9     MeV                                    
      A_v       = 12.04    MeV                                    
      B_v       = 81.36    MeV                                    
      E_a       = 385      MeV                                    
      r_v       = 1.2568   fm                                     
      a_v       = 0.633    fm                                     
    Surface:                                                      
      W_0       = 17.2     MeV                                    
      B_s       = 11.19    MeV                                    
      C_s       = 0.01361  1/MeV                                  
      C_wiso    = 23.5     MeV                                    
      r_s       = 1.1803   fm                                     
      a_s       = 0.601    fm                                     
    Spin-orbit:                                                   
      V_so      = 5.75     MeV                                    
      lambda_so = 0.005    1/MeV                                  
      W_so      = -3.1     MeV                                    
      B_so      = 160      MeV                                    
      r_so      = 1.1214   fm                                     
      a_so      = 0.59     fm                                     
    Coulomb:                                                      
      C_coul    = 1.3                                             
      r_c       = 1.2452   fm                                     
      a_c       = 0.545    fm                                     
    Deformation:                                                  
      beta_2    = 0.213                                           
      beta_4    = 0.066                                           
      beta_6    = 0.0015                                          
                                                                  
  * Calculated strength function                                  
    S0= 0.98e-4 S1= 1.27e-4 R'=  9.91 fm (En=1 keV)               
  --------------------------------------------------              
                                                                  
Table 2. Level Scheme of Th-227                                   
  -------------------                                             
  No.  Ex(MeV)   J PI                                             
  -------------------                                             
   0  0.00000  1/2 +  *                                           
   1  0.00929  5/2 +  *                                           
   2  0.02438  3/2 +  *                                           
   3  0.03786  3/2 -                                              
   4  0.07367  3/2 -                                              
   5  0.07623  3/2 +                                              
   6  0.07762  3/2 +                                              
   7  0.08678  9/2 +                                              
   8  0.09919  1/2 +                                              
   9  0.12730  3/2 +                                              
  10  0.18371  1/2 -                                              
  11  0.20002  5/2 -                                              
  12  0.20710  3/2 -                                              
  13  0.22848  3/2 -                                              
  14  0.23146  7/2 -                                              
  -------------------                                             
  *) Coupled levels in CC calculation                             
                                                                  
Table 3. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Th-228 17.7035  1.5894  3.0590  0.3964 -0.1539  3.9563         
   Th-227 17.6369  0.7965  3.1200  0.4219 -1.2457  3.5201         
   Th-226 17.5702  1.5965  2.8637  0.4068 -0.2170  4.0544         
   Th-225 17.5034  0.8000  2.7304  0.3997 -0.9049  3.1303         
   Th-224 17.4367  1.6036  2.4990  0.4108 -0.1826  4.0385         
  --------------------------------------------------------        
                                                                  
Table 4. Fission barrier parameters                               
  ----------------------------------------                        
  Nuclide     V_A    hw_A     V_B    hw_B                         
              MeV     MeV     MeV     MeV                         
  ----------------------------------------                        
   Th-228   3.900   1.040   6.400   0.600                         
   Th-227   4.100   0.800   6.400   0.520                         
   Th-226   3.900   1.040   8.200   0.600                         
   Th-225   4.200   0.800   8.000   0.520                         
   Th-224   4.100   1.040   7.600   0.600                         
  ----------------------------------------                        
                                                                  
Table 5. Level density above inner saddle                         
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Th-228 19.8280  1.8543  2.6000  0.3346 -0.5570  3.8543         
   Th-227 19.7533  0.9292  2.6000  0.3352 -1.4822  2.9292         
   Th-226 19.6786  1.8625  2.6000  0.3359 -0.5488  3.8625         
   Th-225 19.6038  0.9333  2.6000  0.3366 -1.4780  2.9333         
   Th-224 19.5291  1.8708  2.6000  0.3373 -0.5405  3.8708         
  --------------------------------------------------------        
                                                                  
Table 6. Level density above outer saddle                         
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Th-228 19.8280  1.8543 -0.3000  0.3812  0.1590  3.8543         
   Th-227 19.7533  0.9292 -0.3400  0.3826 -0.7655  2.9292         
   Th-226 19.6786  1.8625 -0.3800  0.3840  0.1685  3.8625         
   Th-225 19.6038  0.9333 -0.4200  0.3854 -0.7601  2.9333         
   Th-224 19.5291  1.8708 -0.4600  0.3868  0.1781  3.8708         
  --------------------------------------------------------        
                                                                  
Table 7. Gamma-ray strength function for Th-228                   
  --------------------------------------------------------        
  K0 = 1.503   E0 = 4.500 (MeV)                                   
  * E1: ER = 11.03 (MeV) EG = 2.71 (MeV) SIG = 302.00 (mb)        
        ER = 13.87 (MeV) EG = 4.77 (MeV) SIG = 449.00 (mb)        
  * M1: ER =  6.71 (MeV) EG = 4.00 (MeV) SIG =   2.82 (mb)        
  * E2: ER = 10.31 (MeV) EG = 3.37 (MeV) SIG =   6.27 (mb)        
  --------------------------------------------------------        
                                                                  
                                                                  
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   (2006).                                                        
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