56-Ba-130

 56-Ba-130 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAY10                       20091217   
----JENDL-4.0         MATERIAL 5625                               
-----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.       
   ===========================================================    
                                                                  
History                                                           
90-03 New evaluation for JENDL-3 was completed by JNDC FPND       
      W.G./1/                                                     
                                                                  
10-03 JENDL-4.0 was made.                                         
      Resoloved resonance parameters were evaluated by K.Shibata. 
      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)   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 2.53 keV       
    Resonance parameters were based on Mughabghab et al./2/ a     
    negative resonance was added so as to reproduce the thermal   
    capture cross section given by Mughabghab et al.  Neutron     
    orbital angular momentum L was assumed to be 0 for all the    
    resonances.  Average radiation width was taken from Mughabghab
    et al. and scattering radius was determined from optical model
    calculation with CASTHY/3/.                                   
    ************************************************************* 
      Resonance parameters were based on Mughabghab et al./2/     
      Neutron orbital angular momentum L was assumed to be 0 for  
      all the resonances.  Average radiation width was taken from 
      Mughabghab et al. and scattering radius was determined from 
      optical model calculation with CASTHY/3/.  A negative       
      resonance was added to so as to reproduce the thermal       
      capture cross section recommended by Mughabghab /22/        
    ************************************************************* 
                                                                  
  Unresolved resonance region : 2.53 keV - 100 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/3/.  The observed level spacing was 
    determined to reproduce the capture cross section calculated  
    with CASTHY.  The effective scattering radius was obtained    
    from fitting to the calculated total cross section at 100 keV.
    The gamma width Gg was based on the compilation of Mughabghab 
    et al.                                                        
                                                                  
  Typical values of the parameters at 70 keV:                     
    S0 = 1.300e-4, S1 = 0.890e-4, S2 = 0.600e-4, Sg = 54.5e-4,    
    Gg = 0.100 eV, R  = 4.562 fm.                                 
                                                                  
   ***************************************************************
      For JENDL-4.0, the unresolved resonance parameters were     
    re-evaluated by the ASREP /23/ code so as to reproduce the    
    total and capture cross sections given in JENDL3.3 in the     
    energy region from 2.53 keV to 200 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          1.18396E+01                                 
       Elastic        3.13813E+00                                 
       n,gamma        8.70145E+00           1.76261E+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/4/ 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/5/.    
  The OMP's for charged particles are as follows:                 
     proton   = Perey/6/                                          
     alpha    = Huizenga and Igo/7/                               
     deuteron = Lohr and Haeberli/8/                              
     helium-3 and triton = Becchetti and Greenlees/9/             
  Parameters for the composite level density formula of Gilbert   
  and Cameron/10/ were evaluated by Iijima et al./11/  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
  /12/.                                                           
                                                                  
  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)/13/ and Nuclear Data       
    Sheets/14/.                                                   
                                                                  
           no.      energy(MeV)    spin-parity   dwba cal.        
           gr.       0.0             0  +                         
            1        0.3573          2  +            *            
            2        0.9017          4  +                         
            3        0.9079          2  +                         
            4        1.3609          4  +                         
            5        1.4774          4  +                         
            6        1.5573          2  +                         
            7        1.5928          6  +                         
      Levels above 1.844 MeV were assumed to be overlapping.      
                                                                  
    For the levels with an asterisk, the contribution of direct   
    inelastic scattering cross sections was calculated by the     
    DWUCK-4 code/15/.  Deformation parameter (beta2 = 0.230) was  
    based on the data compiled by Raman et al./16/                
                                                                  
  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/17/ and normalized to 1 milli-barn at 14 MeV.       
                                                                  
    The gamma-ray strength function (6.84e-03) was adjusted to    
    reproduce the capture cross section of 750 milli-barns at 25  
    keV measured by Bradley et al./18/                            
                                                                  
  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                                
  mt =111  (n,2p) cross section                                   
    These reaction cross sections were calculated with the        
    preequilibrium and multi-step evaporation model code PEGASUS. 
                                                                  
    The Kalbach's constant k (= 127.0) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/19/ 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)      1380.00  mb (systematics of Wen Den Lu+/20/)    
      (n,p)         24.60  mb (systematics of Forrest/21/)        
      (n,alpha)     10.10  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.  Contribution of direct inelastic       
  scattering was calculated with DWUCK-4.  For other reactions,   
  isotropic distributions 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.                               
                                                                  
TABLE 1  NEUTRON OPTICAL POTENTIAL PARAMETERS                     
                                                                  
                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         
  THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.   
                                                                  
TABLE 2  LEVEL DENSITY PARAMETERS                                 
                                                                  
 NUCLIDE  SYST A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 54-XE-126     1.908E+01 6.110E-01 8.260E-01 7.676E+00 2.550E+00  
 54-XE-127     1.982E+01 5.420E-01 3.686E+00 5.152E+00 1.120E+00  
 54-XE-128     1.800E+01 5.830E-01 5.017E-01 6.396E+00 2.210E+00  
 54-XE-129     1.936E+01 5.729E-01 5.108E+00 5.590E+00 1.120E+00  
                                                                  
 55-CS-127  *  1.818E+01 5.847E-01 2.138E+00 5.710E+00 1.430E+00  
 55-CS-128  *  1.791E+01 5.822E-01 2.111E+01 4.140E+00 0.0        
 55-CS-129  *  1.763E+01 5.798E-01 2.754E+00 5.088E+00 1.090E+00  
 55-CS-130  *  1.735E+01 5.774E-01 1.541E+01 3.856E+00 0.0        
                                                                  
 56-BA-128  *  1.832E+01 5.822E-01 1.449E-01 7.297E+00 3.010E+00  
 56-BA-129     1.978E+01 6.490E-01 1.150E+01 7.812E+00 1.580E+00  
 56-BA-130     1.850E+01 6.240E-01 6.573E-01 7.832E+00 2.670E+00  
 56-BA-131     1.990E+01 6.090E-01 5.764E+00 6.979E+00 1.580E+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 8.696 for Ba-130 and 5.0 for Ba-131.               
                                                                  
References                                                        
 1) Kawai, M. et al.: Proc. Int. Conf. on Nuclear Data for Science
    and Technology, Mito, p. 569 (1988).                          
 2) Mughabghab, S.F.: "Neutron Cross Sections, Vol. I, Part B",   
    Academic Press (1984).                                        
 3) Igarasi, S.: J. Nucl. Sci. Technol., 12, 67 (1975).           
 4) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
 5) Iijima, S. and Kawai, M.: J. Nucl. Sci. Technol., 20, 77      
    (1983).                                                       
 6) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
 7) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
 8) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
 9) 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.      
    (1971).                                                       
10) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
    (1965).                                                       
11) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
12) Gruppelaar, H.: ECN-13 (1977).                                
13) ENSDF: Evaluated Nuclear Structure Data File (June 1987).     
14) Nuclear Data Sheets, 13, 133 (1974).                          
15) Kunz, P.D.: private communication.                            
16) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1     
    (1987)                                                        
17) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
18) Bradley, T., et al.: Proc. Int. Conf. Nuclear Cross Sections  
    for Technology, Knoxville 1979, p.344 (1980).                 
19) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
20) Wen Den Lu and Fink, R.W.: Phys. Rev., C4, 1173 (1971).       
21) Forrest, R.A.: AERE-R 12419 (1986).                           
22) Mughabghab, S.F.: "Atlas of Neutron Resonances", Elsevier     
    (2006).                                                       
23) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
    [in Japanese].