52-Te-123 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAY10                       20091214   
----JENDL-4.0         MATERIAL 5234                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
   JENDL-3.2 data were automatically transformed to JENDL-3.3.    
    Interpolation of spectra: 22 (unit base interpolation)        
    (3,251) deleted, T-matrix of (4,2) deleted, and others.       
90-03 New evaluation for JENDL-3 was completed by JNDC FPND       
93-09 JENDL-3.2 was made by JNDC FPND W.G.                        
09-12 Compiled by A.Ichihara.                                     
     *****   modified parts for JENDL-3.2   ********************  
      (2,151)       Unresolved resonance parameters re-adjusted   
                    so as to reproduce the re-normalized capture  
                    cross section.                                
      (3,102)       Re-normalization.                             
      (3,2), (3,4), (3,51-91) and angular distributions           
                    small effects of the re-normalization of      
                    capture cross section.                        
     *****   modified parts for JENDL-4.0   ********************  
      (2,151)       Unresolved resonance parameters were updated. 
mf = 1  General information                                       
  mt=451 Comments and dictionary                                  
mf = 2  Resonance parameters                                      
  mt=151 Resolved and unresolved resonance parameters             
  Resolved resonance region (MLBW formula) : below 700 eV         
    Resonance parameters were based on Mughabghab et al./2/ total 
    spin J of some resonances was tentatively estimated with a    
    random number method.  Neutron orbital angular momentum L was 
    estimated with a method of Bollinger and Thomas/3/.  Averaged 
    radiation width was deduced to be 107 meV, and applied to the 
    levels whose radiation width was unknown.  The scattering     
    radius was also taken from Mughabghab et al.                  
  Unresolved resonance region : 0.7 keV - 200 keV                 
    The neutron strength function S0 was based on the compilation 
    of Mughabghab et al., and S1 and S2 were calculated with      
    optical model code CASTHY/4/.  The observed level spacing was 
    determined to reproduce the capture cross sections calculated 
    with CASTHY.  The effective scattering radius was obtained    
    from fitting to the calculated total cross section at 100 keV.
    The radiation width Gg was based on the compilation of        
    Mughabghab et al.                                             
  Typical values of the parameters at 70 keV:                     
    S0 = 0.790e-4, S1 = 1.700e-4, S2 = 1.100e-4, Sg = 80.9e-4,    
    Gg = 0.124 eV, R  = 5.519 fm.                                 
    The unresolved resonance parameters were recalculated using   
    the ASREP code/20/.                                           
    The parameters should be used only for self-shielding         
    Thermal cross sections and resonance integrals at 300 K       
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
     Total            4.190E+02                                   
     Elastic          5.923E-01                                   
     n,gamma          4.184E+02             5.65E+03              
     n,alpha          4.6E-05                                     
       (*) Integrated from 0.5 eV to 10 MeV.                      
mf = 3  Neutron cross sections                                    
  Below 700 eV, resolved resonance parameters were given.         
  The spherical optical and statistical model                     
  calculation was performed with CASTHY, by taking account of     
  competing reactions, of which cross sections were calculated    
  with PEGASUS/5/ standing on a preequilibrium and multi-step     
  evaporation model.  The OMP's for neutron given in Table 1 were 
  determined to reproduce a systematic trend of the total cross   
  section by changing r0 and rso of Iijima-Kawai potential/6/.    
  The OMP's for charged particles are as follows:                 
     proton   = Perey/7/                                          
     alpha    = Huizenga and Igo/8/                               
     deuteron = Lohr and Haeberli/9/                              
     helium-3 and triton = Becchetti and Greenlees/10/            
  Parameters for the composite level density formula of Gilbert   
  and Cameron/11/ were evaluated by Iijima et al./12/   More      
  extensive determination and modification were made in the       
  present work.  Table 2 shows the level density parameters used  
  in the present calculation.  Energy dependence of spin cut-off  
  parameter in the energy range below E-joint is due to Gruppelaar
  mt = 1  Total                                                   
    Spherical optical model calculation was adopted.              
  mt = 2  Elastic scattering                                      
    Calculated as (total - sum of partial cross sections).        
  mt = 4, 51 - 91  Inelastic scattering                           
    Spherical optical and statistical model calculation was       
    adopted. The level scheme was based on Evaluated Nuclear      
    Structure Data File (1987 version)/14/ and Nuclear Data       
           no.      energy(MeV)    spin-parity                    
           gr.       0.0            1/2 +                         
            1        0.1590         3/2 +                         
            2        0.2475        11/2 -                         
            3        0.4400         3/2 +                         
            4        0.4897         5/2 +                         
            5        0.5053         3/2 +                         
            6        0.5996         1/2 +                         
            7        0.6880         3/2 +                         
            8        0.6975         7/2 +                         
            9        0.7693         5/2 +                         
           10        0.7836         3/2 +                         
           11        0.8947         3/2 +                         
           12        0.9961         5/2 -                         
           13        1.0366         3/2 +                         
           14        1.0682         3/2 +                         
           15        1.0800         7/2 +                         
      Levels above 1.21 MeV were assumed to be overlapping.       
  mt = 102  Capture                                               
    Spherical optical and statistical model calculation with      
    CASTHY was adopted.  Direct and semi-direct capture cross     
    sections were estimated according to the procedure of Benzi   
    and Reffo/16/ and normalized to 1 milli-barn at 14 MeV.       
    The gamma-ray strength function (7.93e-03) was adjusted to    
    reproduce the capture cross section of 553 milli-barns at 70  
    keV measured by Macklin et al./17/                            
  mt = 16  (n,2n) cross section                                   
  mt = 17  (n,3n) cross section                                   
  mt = 22  (n,n'a) cross section                                  
  mt = 28  (n,n'p) cross section                                  
  mt = 32  (n,n'd) cross section                                  
  mt =103  (n,p) cross section                                    
  mt =104  (n,d) cross section                                    
  mt =105  (n,t) cross section                                    
  mt =106  (n,he3) cross section                                  
  mt =107  (n,alpha) cross section                                
    These reaction cross sections were calculated with the        
    preequilibrium and multi-step evaporation model code PEGASUS. 
    The Kalbach's constant k (= 149.5) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/18/ and level  
    density parameters.                                           
    Finally, the (n,p) and (n,alpha) cross sections were          
    normalized to the following values at 14.5 MeV:               
      (n,p)         10.60  mb (systematics of Forrest/19/)        
      (n,alpha)      5.05  mb (systematics of Forrest)            
    The (n,alpha) cross section below 0.7 keV was calculated from 
    resonance parameters, by assuming a mean alpha width of       
    1.15e-8 eV so as to reproduce the thermal cross section/2/.   
    The cross section was averaged in suitable energy intervals.  
    Above 0.7 keV, the cross section was connected smoothly to the
    PEGASUS calculation.                                          
  mt = 251  mu-bar                                                
    Calculated with CASTHY.                                       
mf = 4  Angular distributions of secondary neutrons               
  Legendre polynomial coefficients for angular distributions are  
  given in the center-of-mass system for mt=2 and discrete inelas-
  tic levels, and in the laboratory system for mt=91.  They were  
  calculated with CASTHY.  For other reactions, isotropic distri- 
  butions in the laboratory system were assumed.                  
mf = 5  Energy distributions of secondary neutrons                
  Energy distributions of secondary neutrons were calculated with 
  PEGASUS for inelastic scattering to overlapping levels and for  
  other neutron emitting reactions.                               
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 45.97-0.199E         R0 = 6.481    A0 = 0.62         
        WS = 6.502                RS = 6.926    AS = 0.35         
        VSO= 7.0                  RSO= 6.49     ASO= 0.62         
TABLE 2  LEVEL DENSITY PARAMETERS                                 
 50-SN-119     1.635E+01 5.990E-01 1.772E+00 5.050E+00 1.190E+00  
 50-SN-120     1.595E+01 6.540E-01 4.691E-01 7.083E+00 2.430E+00  
 50-SN-121     1.630E+01 6.100E-01 2.010E+00 5.217E+00 1.190E+00  
 50-SN-122     1.434E+01 7.060E-01 3.423E-01 7.416E+00 2.620E+00  
 51-SB-120  *  1.834E+01 6.016E-01 3.366E+01 4.659E+00 0.0        
 51-SB-121     1.730E+01 5.740E-01 1.715E+00 5.022E+00 1.240E+00  
 51-SB-122     1.772E+01 5.500E-01 1.346E+01 3.517E+00 0.0        
 51-SB-123     1.585E+01 6.213E-01 1.285E+00 5.469E+00 1.430E+00  
 52-TE-121     1.800E+01 6.200E-01 5.720E+00 6.022E+00 1.140E+00  
 52-TE-122     1.705E+01 6.350E-01 6.339E-01 7.160E+00 2.380E+00  
 52-TE-123     1.874E+01 5.850E-01 4.619E+00 5.627E+00 1.140E+00  
 52-TE-124     1.784E+01 6.740E-01 1.452E+00 8.479E+00 2.570E+00  
  syst:  * = ldp's were determined from systematics.              
 Spin cutoff parameters were calculated as 0.146*sqrt(a)*a**(2/3).
 In the CASTHY calculation, spin cutoff factors at 0 MeV were     
 assumed to be 4.266 for Te-123 and 3.991 for Te-124.             
 1) Kawai, M. et al.: J. Nucl. Sci. Technol., 29, 195 (1992).     
 2) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
 3) Bollinger, L.M. and Thomas, G.E.: Phys. Rev., 171,1293(1968). 
 4) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).              
 5) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
 6) Iijima, S. and Kawai, M.: J. Nucl. Sci. Technol., 20, 77      
 7) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
 8) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
 9) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
10) Becchetti, F.D., Jr. and Greenlees, G.W.: Polarization        
    Phenomena in Nuclear Reactions ((Eds) H.H. Barshall and       
    W. Haeberli), p. 682, the University of Wisconsin Press.      
11) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
12) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
13) Gruppelaar, H.: ECN-13 (1977).                                
14) ENSDF: Evaluated Nuclear Structure Data File (June 1987).     
15) Nuclear Data Sheets, 29, 453 (1980).                          
16) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
17) Macklin, R.L. et al.: ORNL-6561 (1989).                       
18) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
19) Forrest, R.A.: AERE-R 12419 (1986).                           
20) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
    [in Japanese].