22-Ti- 48

 22-Ti- 48 KUR        EVAL-SEP88 K.KOBAYASHI(KUR),H.HASHIKURA(TOK)
                      DIST-JUL13                       20130527   
----JENDL-4.0u2       MATERIAL 2231                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
88-09  Compiled by T.Asami(nedac)                                 
93-03  (4,91) changed into lab system.                            
93-12  JENDL-3.2                                                  
       Data were mainly 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   ********************  
      (2,151)              revised                                
      (3,1)                revised                                
      (3,2)                re-calculated                          
      (3,28,102,103)       revised                                
      (3,104,105,106,203,207)  evaluated newly                    
      (3,251)              deleted                                
      (4,2)                re-evaluated                           
      (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                        
     ***********************************************************  
                                                                  
02-02  Covariances were estimated by T. Asami.                    
09-08  Compiled by K. Shibata.                                    
       The resolved resonance parameters were revised.  The upper 
       limit of the resolved resonance region was changed to      
       367.2 keV from 300 keV.  As a result, the total, elastic   
       scattering and capture cross sections were revised between 
       300 and 367.2 keV.                                         
11-12  The resonance formula of Reich-Moore was adopted.  The     
       MF2MT151 data were re-arranged in order to conform with the
       Reich-Moore formula.                                       
13-05  The gamma-widths at -323.4 keV and 501.605 keV were found  
       to be 0.0 in JENDL-4.0u1.  These values were replaced with 
       1.0 meV for JENDL-4.0u2.                                   
                                                                  
                                                                  
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 300 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    
   4.61+-0.2 and 7.84+-0.25 barns, respectively/5/.  The scatter- 
   ing radius was assumed to be 4.2 fermi instead of 3.9 fermi in 
   ref./5/.                                                       
   For JENDL-4, the resonance parameters were modified by Kawano  
   /21/.                                                          
                                                                  
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total           1.2383E+01                                   
     Elastic         4.0544E+00                                   
     n,gamma         8.3278E+00           3.7136E+00              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
mf=3  Neutron cross sections                                      
  Below 300 keV, no background cross section was given.           
                                                                  
  For JENDL-3.2, all cross-section data except for the total,     
  capture and (n,a) were adopted from JENDL fusion file.  The     
  calculation was made with sincros-ii system/2/ 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                                                       
    Optical and statistical model calculation was made with       
    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)               
    In JENDL-3.1, the total cross section was not the same as this
    calculation.  For JENDL-3.2, it was replaced with the casthy  
    calculation.                                                  
    For JENDL-3.3, the total cross sections were determined so as 
    to reproduce measured elemental data.                         
                                                                  
 mt=2 Elastic scattering                                          
    Obtained by subtracting the sum of the partial cross sections 
    from the total cross section.                                 
                                                                  
 mt=4, 51-68, 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 '*', using 
    deformation parameters compiled by Raman et al./11/ and       
    Spear/12/.                                                    
                                                                  
           no.      energy(MeV)    spin-parity (direct process)   
          g.s.      0.0                 0+                        
            1       0.9835              2+         *              
            2       2.2956              4+         *              
            3       2.421               2+         *              
            4       2.9973              0+         *              
            5       3.224               3+                        
            6       3.2398              4+         *              
            7       3.3332              6+                        
            8       3.3588              3-         *              
            9       3.3709              2+                        
           10       3.5085              6+                        
           11       3.6168              2+         *              
           12       3.6336              2+                        
           13       3.6994              1+                        
           14       3.711               1+                        
           15       3.7386              1+                        
           16       3.7825              4-                        
           17       3.8028              1+                        
           18       3.8522              3-         *              
  Levels above 3.852 MeV were assumed to be overlapping.          
                                                                  
 mt=16      (n,2n)                                                
    Adopted from JENDL fusion file.  Theoretical calculation was  
    made with sincros-ii.                                         
                                                                  
 mt=22      (n,na)                                                
    Obtained from from the sincros-ii calculation made with the   
    the egnash code/2/.                                           
                                                                  
 mt=28      (n,np)                                                
    Adopted from JENDL activation file/14/.                       
                                                                  
 mt=102      Capture                                              
    Calculated with the casthy code/10/ and normalized to 4.3 mb  
    at 20 keV, and added the semidirect component calculated      
     with the quick gnash code/17,18/.                            
                                                                  
 mt=103      (n,p)                                                
    Adopted from JENDL activation file/14/.                       
                                                                  
 mt=107      (n,a)                                                
    Evaluated based on the experimental data.                     
                                                                  
mf=4  Angular distributions of secondary neutrons                 
 mt=2                                                             
    Calculated with the casthy code/10/, newly for JENDL-3.3.     
 mt=51-68                                                         
    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, 51-68, 91,103, 104, 107                           
      mt=51-68 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, 51-68, 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/.                         
     For 18-133.5 keV, based on the data measured by the Tokyo    
     Institute of Tech. group /19/.                               
                                                                  
mf=33  Covariances of cross sections /20/                         
 mt=1                                                             
     Based on experimental data.  A chi-value was 5.86.           
 mt=4                                                             
     Based on experimental data.  A chi-value was 2.29.           
 mt=16                                                            
     Based on experimental data.                                  
 mt=22                                                            
     Based on systematics.                                        
 mt=28                                                            
     Based on experimental data.  A chi-value was 2.45.           
 mt=102                                                           
     Based on experimental data.  A chi-value was 3.52.           
 mt=103                                                           
     Based on experimental data.  A chi-value was 1.10.           
 mt=107                                                           
     Based on experimental data.  A chi-value was 0.82.           
                                                                  
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) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1     
    (1987)                                                        
12) Spear, R.H.: Atom. Data and Nucl. Data Table, 42, 55 (1989).  
13) Kalbach C. : Phys. Rev. C37, 2350(1988).                      
14) JAERI Nuclear Data Center : private communication (1996).     
15) Hida K.: JAERI-M 86-150 (1986) (in Japanese).                 
17) Young P.G. et al. : LA-12343-MS (1992).                       
18) Koning A.J. and Delaroche J.P. : ECN-RX-98-015 (1998).        
19) Igashira M.: private communication (1999).                    
20) Asami T.: private communication (2002).                       
21) Kawano T.: Private communication (2008).