22-Ti- 47

 22-Ti- 47 KUR        EVAL-SEP88 K.KOBAYASHI(KUR),H.HASHIKURA(TOK)
                      DIST-MAY10                       20090804   
----JENDL-4.0         MATERIAL 2228                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
88-09  Compiled by T.Asami(nedac)                                 
93-12  JENDL-3.2                                                  
       Data were adopted from JENDL fusion file.                  
       Compiled by T.Nakagawa                                     
00-03  Reevaluation was made by T.Asami.                          
01-11  Compiled by K.Shibata (ndc/jaeri)                          
                                                                  
     *****   modified parts for JENDL-3.3   ********************  
      (3,2)                re-calculated                          
      (3,28,102,103)       revised                                
      (3,104,105,106,111, 203,207)  evaluated newly               
      (3,251)              deleted                                
      (4,2)                revised                                
      (4,16,22,28,91)      deleted                                
      (5,16,22,28,91)      deleted                                
      (6,16,22,28,91)      taken from JENDL fusion file           
      (6,203, 207)         taken from JENDL fusion file           
      (12,16-107)          evaluated newly                        
      (14,16-107)          isotropic distributions                
      (15,16-107)          evaluated newly                        
     ***********************************************************  
                                                                  
09-08  Compiled by K. Shibata.                                    
       The resolved resonance parameters were revised.            
                                                                  
mf=1  General information                                         
 mt=451  Descriptive data and dictionary                          
                                                                  
mf=2  Resonance parameters                                        
 mt=151  Resolved resonance parameters                            
   Resolved parameters for MLBW formula were given in the energy  
   region from 1.0e-5 eV to 100 keV.  Parameters were taken from  
   ref./5/, for positive resonances.  Parameters for negative     
   resonance were obtained so that the reproduced cross sections  
   for both scattering and capture gave the 2200 m/s values of    
   3.1+-0.2 and 1.7+-0.2 barns, respectively/5/.  The scattering  
   radius was assumed to be 4.5 fermi instead of 3.6 fermi in     
   ref./5/.                                                       
   For JENDL-4, the resolved resonance parameters were modified   
   by Kawano /18/.                                                
                                                                  
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total           4.8919E+00                                   
     Elastic         3.2656E+00                                   
     n,gamma         1.6264E+00           1.3393E+00              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
mf=3  Neutron cross sections                                      
   Below 100 kev, no background cross section was given.          
  The calculation with sincros-ii system/2/ was made by adopting  
  Walter-Guss omp modified by Yamamuro/2/ for neutron, Perey omp  
  /6/ for proton, Lemos omp modified by Arthur and Young/7/       
  for alpha, Lohr-Haeberli omp/8/ for deuteron, Becchettii-       
  Greenlees omp/9/ for triton and he-3, and standard level        
  density parameters of sincros-ii system.                        
                                                                  
 mt=1 Total                                                       
   Below 100 keV, created from the resonance paranmeters.         
   Above 100 keV, optical and statistical model calculation was   
   made with the casthy code/10/.                                 
   The optical potential parameters used are:                     
        V = 50.75 - 0.120*En,    Vso = 4.72   (MeV)               
       Ws = 10.9 - 0.234*En,      Wv = 0.0    (MeV)               
        r = 1.26,   rs = 1.02,   rso = 1.16    (fm)               
        a = 0.52,  aso = 0.52,     b = 0.40    (fm)               
                                                                  
 mt=2 Elastic scattering                                          
   Obtained by subtracting the sum of the partial cross sections  
   from the total cross section.                                  
                                                                  
 mt=4, 51-66, 91 Inelastic scattering                             
    The cross sections were taken from JENDL fusion file.  the    
    level scheme was based on ref./4/  Contributions of the       
    direct process were calculated for the levels marked with '*'.
                                                                  
           no.      energy(MeV)    spin-parity (direct process)   
          g.s.      0.0              5/2 -                        
            1       0.1594           7/2 -         *              
            2       1.2521           9/2 -         *              
            3       1.254            1/2 -                        
            4       1.4442          11/2 -         *              
            5       1.5499           3/2 -         *              
            6       1.67             1/2 -                        
            7       1.7941           1/2 -         *              
            8       1.825            3/2 +                        
            9       2.163            3/2 -         *              
           10       2.1667           5/2 +                        
           11       2.2595           5/2 +                        
           12       2.2971           3/2 -                        
           13       2.344            5/2 +                        
           14       2.3649           1/2 +                        
           15       2.4062           5/2 -                        
           16       2.4163           1/2 -                        
  Levels above 2.416 MeV were assumed to be overlapping.          
                                                                  
 mt=16, 22   (n,2n), (n,na)                                       
    Adopted from JENDL fusion file.  Theoretical calculation was  
    made with sincros-ii.  The (n,2n) results were normalized to  
    0.200  b at 14.9  MeV systematics by Kasugai/11/              
                                                                  
 mt=28       (n,np)                                               
    Obtained from from the sincros-ii calculation made with the   
    the egnash code/2/.                                           
                                                                  
 mt=102      Capture                                              
    Calculated with the casthy code/10/ and normalized to 65.5 mb 
    at 30 keV.  Added the semidirect component calculated with    
    the quick  gnash code/16,17/.                                 
                                                                  
 mt=103      (n,p)                                                
    Taken from JENDL dosimetry file/14/.                          
                                                                  
 mt=107      (n,a)                                                
    Calculated with the gnash code/12/.                           
                                                                  
mf=4  Angular distributions of secondary neutrons                 
 mt=2                                                             
    Calculated with the casthy code/10/,newly for JENDL-3.3.      
 mt=51-66                                                         
    Taken from JENDL fusion file/1/.                              
                                                                  
mf=6  Energy-angle distributions of secondary particles           
    Taken from JENDL fusion file/1/.                              
      -  Energy distributions of secondary neutrons were replaced 
         by those calculated by egnash2.  The ddx's of the        
         continuum neutrons were calculated by Kumabe's systema-  
         tics /3/ using f15tob /1/.  The precompound/compound     
         ratio was calculated by the sincros-ii code system/2/.   
 mt=16, 22, 28, 91                                                
    Based on modified Kumabe's systematics/1/.                    
 mt=203, 207                                                      
    Based on kalbach's 1988 systematics/13/.                      
                                                                  
mf=12  Photon production multiplicities and transition probability
         arrays                                                   
 mt=16, 22, 28, 51-66, 91,103, 104, 107                           
       mt=51-66 were given as the transition probability arrays.  
     mt=16, 22, 28, 91, 102, 103, 104, 107 were calculated with   
     the egnash code/2/ and processed by the gamfil2 code/15/.    
     mt=102 was calculated with the casthy code/10/.              
                                                                  
mf=14  Photon angular distributions                               
 mt=16, 22, 28, 51-66, 91, 102, 103, 104, 107                     
        Assumed to be isotropic distributions                     
                                                                  
mf=15  Continuous photon energy spectra                           
 mt=16, 22, 28, 91, 103, 104, 107                                 
     Calculated with the egnash code/2/.                          
 mt=102                                                           
     Calculated with the casthy code/10/.                         
                                                                  
                                                                  
References                                                        
 1) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).                
 2) Yamamuro, N.: JAERI-M 90-006 (1990).                          
 3) Kumabe, I. et al.: Nucl. Sci. Eng., 104, 280 (1990).          
 4) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.       
 5) Mughabghab S.F. et al. : " Neutron Cross Sections ", Vol.1,   
    Part A (1981).                                                
 6) Perey, F.G.: Phys. Rev., 131, 745 (1963).                     
 7) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980).              
 8) Lohr, J.M. and Haeberli W.: Nucl. Phys., A232, 381 (1974).    
 9) Becchetti, F.D. Jr. and Greenlees G.W.: "Polarization         
    Phenomena in Nucl. Reactions," Univ. Wisconsin Press, p.682   
    (1971).                                                       
10) Igarasi S. and Fukahori T.: JAERI 1321 (1991).                
11) Kasugai Y.: private communication (1993).                     
12) Young P.G. and Arthur E.D. : LA-6947 (1977).                  
13) Kalbach C. : Phys. Rev. C37, 2350(1988).                      
14) Nakazawa M. et al. : JAERI 1325 (1992).                       
15) Hida K.: JAERI-M 86-150 (1986) (in Japanese).                 
16) Young P.G. et al. : LA-12343-MS (1992).                       
17) Koning A.J. and Delaroche J.P. : ECN-RX-98-015 (1998).        
18) Kawano T.: Private communication (2008).