56-Ba-135 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAY10                       20091217   
----JENDL-4.0         MATERIAL 5640                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
   Resonance parameters in JENDL-3.3 were revised for JENDL-4.    
   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.       
84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/        
90-03 Modification for JENDL-3 was made/2/.                       
93-11 JENDL-3.2 was made by JNDC FPND W.G.                        
     *****   modified parts for JENDL-3.2   ********************  
      (2,151)       Resolved resonance parameters.  Negative      
                    resonance parameters were slightly modified.  
10-03 JENDL-4.0 was made.                                         
      Unresolved resonance parameters were evaluated by S.Kunieda.
      The LSSF=1 was applied.                                     
      Compiled by S.Kunieda                                       
      *****   modified parts for JENDL-4.0   ******************** 
        (1,451)   Updated.                                        
        (2,151)   Unresolved resonance parameters were updated.   
        (3,1)     Re-calculated from partial cross sections.      
        (3,2)     Calculated from URP in lower energy range.      
        (3,4)     Re-calculated from partial cross sections.      
        (3,102)   Calculated from URP in lower energy range.      
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 5.96 keV the   
       evaluation for JENDL-2 was made by Kikuchi/3/.  For the    
    resonances below 1.4 keV, neutron widths were obtained from   
    the experimental data of Alves et al./4/ and Van de Vyver and 
    Pattenden/5/.  Radiation widths were based on the data of     
    Alves et al. or average value of 0.15 eV by Musgrove et al./6/
    above 3 keV, parameters were determined from the data of      
    Musgrove et al.  In the energy range below 3 keV, many        
    artificial levels were generated with stat/7/ by assuming     
    d=39.3 eV, S0=0.8e-4, S1=0.48e-4 and average radiation width  
    of 0.15 eV.  A negative resonance was added so as to reproduce
    the capture cross section of 5.8+-0.9 barns at 0.0253 eV/8/.  
       For JENDL-3, the JENDL-2 data were modified on the basis of
    the latest experimental data of Mizumoto/9/.  Resonance       
    energies and neutron widths of JENDL-2 were partially modified
    with Mizumoto's data in the energy range form 404.5 eV to 4.95
    keV. Total spin J of some resonances was tentatively estimated
    with a random number method.  The parameters of negative level
    were adjusted to the capture cross section recommended by     
    Mughabghab et al./8/                                          
       For JENDL-3.2, a slight modification of the negative level 
    was made.                                                     
  Unresolved resonance region : 5.96 keV - 100 keV                
    Parameters were adjusted to reproduce the capture cross       
    section calculated with CASTHY/10/ (JENDL-2 value) below 40   
    keV, and the capture cross section measured by Musgrove et    
    al./11/ above 40 keV.  The initial values of neutron strength 
    functions, S0 and S1, were adopted from the recommendation by 
    Mughabghab et al., and S2 was taken from calculation with     
    CASTHY/10/.  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 of         
    Mughabghab et al.                                             
  Typical values of the parameters at 70 keV:                     
    S0 = 0.922e-4, S1 = 0.491e-4, S2 = 0.584e-4, Sg = 70.2e-4,    
    Gg = 0.150 eV, R  = 5.232 fm.                                 
      For JENDL-4.0, the unresolved resonance parameters were     
    re-evaluated by the ASREP /26/ code so as to reproduce the    
    total and capture cross sections given in JENDL3.3 in the     
    energy region from 5.96 keV to 250 keV. The parameters        
    should be used only for self-shielding calculations.          
     Thermal cross sections & resonance integrals at 300 K        
                       0.0253 eV           res. integ. (*)        
                        (barns)              (barns)              
       Total          7.60237E+00                                 
       Elastic        1.80455E+00                                 
       n,gamma        5.79783E+00           1.31270E+02           
      (*) Integrated from 0.5 eV to 10 MeV.                       
mf = 3  Neutron cross sections                                    
  Below 100 keV, resonance parameters were given.                 
  Above 100 keV, 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/12/ 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 Ws and rso of Iijima-Kawai potential/13/.   
  The OMP's for charged particles are as follows:                 
     proton   = Perey/14/                                         
     alpha    = Huizenga and Igo/15/                              
     deuteron = Lohr and Haeberli/16/                             
     helium-3 and triton = Becchetti and Greenlees/17/            
  Parameters for the composite level density formula of Gilbert   
  and Cameron/18/ were evaluated by Iijima et al./19/  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 taken from Ref./21/.           
           no.      energy(MeV)    spin-parity                    
           gr.       0.0            3/2 +                         
            1        0.2210         1/2 +                         
            2        0.2682        11/2 -                         
            3        0.4806         5/2 +                         
            4        0.5879         3/2 +                         
            5        0.8550         3/2 +                         
            6        0.8745         7/2 +                         
            7        0.9800         3/2 +                         
      Levels above 1.17 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/22/ and normalized to 1 milli-barn at 14 MeV.       
    The gamma-ray strength function (5.93e-03) was adjusted to    
    reproduce the capture cross section of 250 milli-barns at 100 
    keV measured by Musgrove et al./11/                           
  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 (= 268.3) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/23/ and level  
    density parameters.                                           
    Finally, the (n,2n), (n,p) and (n,alpha) cross sections were  
    normalized to the following values at 14.5 MeV:               
      (n,2n)      1630.00  mb (systematics of Wen Den Lu+/24/)    
      (n,p)          5.88  mb (systematics of Forrest/25/)        
      (n,alpha)      2.64  mb (systematics of Forrest)            
  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  = 41.8                 R0 = 6.89     A0 = 0.62         
        WS = 2.95+0.789E          RS = 7.098    AS = 0.35         
        VSO= 7.0                  RSO= 6.89     ASO= 0.62         
TABLE 2  LEVEL DENSITY PARAMETERS                                 
 54-XE-131     1.740E+01 6.000E-01 3.176E+00 5.394E+00 1.120E+00  
 54-XE-132     1.563E+01 6.500E-01 5.485E-01 6.600E+00 2.160E+00  
 54-XE-133     1.600E+01 6.250E-01 2.327E+00 5.284E+00 1.120E+00  
 54-XE-134     1.400E+01 6.300E-01 3.184E-01 5.224E+00 1.820E+00  
 55-CS-132  *  1.676E+01 5.726E-01 1.123E+01 3.569E+00 0.0        
 55-CS-133     1.750E+01 6.000E-01 3.784E+00 5.352E+00 1.040E+00  
 55-CS-134     1.598E+01 6.450E-01 1.710E+01 4.505E+00 0.0        
 55-CS-135     1.343E+01 6.537E-01 1.831E+00 4.203E+00 7.000E-01  
 56-BA-133     1.941E+01 5.930E-01 3.357E+00 6.465E+00 1.580E+00  
 56-BA-134     1.800E+01 6.100E-01 4.177E-01 7.309E+00 2.620E+00  
 56-BA-135     1.902E+01 5.820E-01 2.277E+00 6.108E+00 1.580E+00  
 56-BA-136     1.610E+01 6.500E-01 5.721E-01 6.928E+00 2.280E+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 5.285 for Ba-135 and 6.925 for Ba-136.             
 1) Aoki, T. et al.: Proc. Int. Conf. on Nuclear Data for Basic   
    and Applied Science, Santa Fe., Vol. 2, p.1627 (1985).        
 2) Kawai, M. et al.: J. Nucl. Sci. Technol., 29, 195 (1992).     
 3) Kikuchi, Y. et al.: JAERI-M 86-030 (1986).                    
 4) Alves, R.N., et al.: Nucl. Phys., A134, 118 (1969).           
 5) Van de Vyver, R.E., Pattenden, N.J.: Nucl. Phys., A177, 393   
 6) Musgrove, A.R. de L., et al.: AAEC/E325 (1974).               
 7) Kikuchi, Y.: JAERI-M 6248 (1975).                             
 8) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
 9) Mizumoto, M: J. Nucl. Sci. Technol., 25, 757 (1988).          
10) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).              
11) Musgrove, A.R. de L., et al.: Proc. Int. Conf. on Neutron     
    Physics and Nucl. Data for Reactors, Harwell 1978, 449.       
12) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
13) Iijima, S. and Kawai, M.: J. Nucl. Sci. Technol., 20, 77      
14) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
15) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
16) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
17) 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.      
18) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
19) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
20) Gruppelaar, H.: ECN-13 (1977).                                
21) Lederer, C.M., et al.: "Table of Isotopes, 7th Ed.", Wiley-   
    interscience Publication (1978).                              
22) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
23) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
24) Wen Den Lu and Fink, R.W.: Phys. Rev., C4, 1173 (1971).       
25) Forrest, R.A.: AERE-R 12419 (1986).                           
26) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
    [in Japanese].