57-La-139 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAY10                       20091214   
----JENDL-4.0         MATERIAL 5728                               
-----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                 
10-03 JENDL-4.0 was made.                                         
      Resoloved resonance parameters were evaluated by T.Nakagawa.
      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 15.0 keV       
      Resonance parameters of JENDL-2/3/ were modified on the     
    basis of the experimental data of Nakajima/4/ at 72.3 eV, and 
    in the energy range from 617.2 to 2464 eV where 20 resonances 
    were given.  Resonance energies were mainly based on the data 
    of JENDL-2 and supplemented with the experimental data of     
    Nakajima.  Neutron widths were derived from the neutron       
    capture area data by using the average radiation width of     
    0.050 eV/3/.                                                  
      Total spin J of some resonances was tentatively estimated   
    with a random number method.  Assignment of neutron orbital   
    angular momentum L is the same as the JENDL-2 evaluation.     
      Two negative resonances were added so as to reproduce the   
    thermal capture and scattering cross sections given by        
    Mughabghab et al.                                             
      For JENDL-3.2, these resonance parameters were modified so  
    as to reproduce the area data measured at ORNL, by taking     
    account of the correction factor of 1.0737 announced by Allen 
    et al./5/.  The upper boundary was changed from 25.9 keV to   
    15 keV.                                                       
      The JENDL-3.3 evaluation was based on the data obtained     
      by Shwe et al./24/, Morgenstern et al./25/, Hacken et al.   
      /26/, Musgrove et al./27/, and Nakajima et al./4/           
      In JENDL-4, the data below 9 keV were replaced with the     
      ones measured by Terlizzi et al./28/  Total spin J was      
      determined by a random number method.  The parameters for   
      a negative resonance were adjusted so as to reproduce the   
      averege of the measured thermal capture cross section       
      8.936+-0.035 b.                                             
  Unresolved resonance region : 15 keV - 100 keV                  
    The neutron strength function S0 and S1 were based on the     
    compilation of Mughabghab et al., and S2 was calculated with  
    optical model code CASTHY/6/.  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 radiation width Gg was based on the compilation of        
    Mughabghab et al.                                             
  Typical values of the parameters at 70 keV:                     
    S0 = 0.780e-4, S1 = 0.400e-4, S2 = 0.500e-4, Sg = 2.04e-4,    
    Gg = 0.055 eV, R  = 5.455 fm.                                 
  calculated 2200-m/s cross sections and res. integrals (barns)   
                     2200 m/s               res. integ.           
      total          19.060                    -                  
      elastic        10.130                    -                  
      capture         8.930                    11.8               
      For JENDL-4.0, the unresolved resonance parameters were     
    re-evaluated by the ASREP /29/ code so as to reproduce the    
    total and capture cross sections given in JENDL3.3 in the     
    energy region from 15 keV to 160 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          1.90109E+01                                 
       Elastic        1.00706E+01                                 
       n,gamma        8.94030E+00           1.16047E+01           
      (*) 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/7/ standing on a preequilibrium and multi-step     
  evaporation model.  The OMP's for neutron given in Table 1 were 
  determined so as to reproduce the La-139 total cross sections   
  measured by Foster and Glasgow/8/, Islam et al./9/, Nishimura et
  al./10/ and so on.  The OMP's for charged particles are as      
     proton   = Perey/11/                                         
     alpha    = Huizenga and Igo/12/                              
     deuteron = Lohr and Haeberli/13/                             
     helium-3 and triton = Becchetti and Greenlees/14/            
  Parameters for the composite level density formula of Gilbert   
  and Cameron/15/ were evaluated by Iijima et al./16/  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./18/.           
           no.      energy(MeV)    spin-parity                    
           gr.       0.0            7/2 +                         
            1        0.1658         5/2 +                         
            2        1.2060         1/2 +                         
            3        1.2191         9/2 +                         
            4        1.2566         5/2 +                         
            5        1.3813         7/2 +                         
            6        1.4205         7/2 +                         
            7        1.4390        11/2 -                         
            8        1.4764         7/2 +                         
            9        1.5363         7/2 +                         
           10        1.5582         3/2 +                         
           11        1.5782         9/2 +                         
           12        1.6831         7/2 +                         
      Levels above 1.75 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/19/ and normalized to 1 milli-barn at 14 MeV.       
    The gamma-ray strength function (2.06e-04) was adjusted to    
    reproduce the capture cross section of 38 milli-barns at 30   
    keV measured by Musgrove et al./20/                           
  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 = 33  (n,n't) 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 (= 322.9) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/21/ 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)          5.00  mb (recommended by Forrest/22/)        
      (n,alpha)      2.50  mb (measured by Woelfle+/23/)          
  mt = 251  mu-bar                                                
    Calculated with CASTHY/6/.                                    
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 from overlapping levels and for
  other neutron emitting reactions.                               
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 41.8                 R0 = 6.874    A0 = 0.62         
        WS = 2.95+0.789E          RS = 7.081    AS = 0.35         
        VSO= 7.0                  RSO= 6.874    ASO= 0.62         
TABLE 2  LEVEL DENSITY PARAMETERS                                 
 NUCLIDE       A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 55-CS-135     1.343E+01 6.537E-01 1.831E+00 4.203E+00 7.000E-01  
 55-CS-136     1.400E+01 6.000E-01 4.424E+00 2.967E+00 0.0        
 55-CS-137     1.336E+01 6.200E-01 9.986E-01 3.836E+00 8.500E-01  
 55-CS-138     1.470E+01 5.737E-01 4.715E+00 2.858E+00 0.0        
 56-BA-136     1.610E+01 6.500E-01 5.721E-01 6.928E+00 2.280E+00  
 56-BA-137     1.645E+01 5.640E-01 5.394E-01 4.905E+00 1.580E+00  
 56-BA-138     1.390E+01 7.200E-01 4.123E-01 7.233E+00 2.430E+00  
 56-BA-139     2.022E+01 4.800E-01 5.326E-01 4.629E+00 1.580E+00  
 57-LA-137     1.558E+01 6.210E-01 3.521E+00 4.624E+00 7.000E-01  
 57-LA-138     1.450E+01 6.310E-01 7.202E+00 3.634E+00 0.0        
 57-LA-139     1.380E+01 6.500E-01 1.653E+00 4.468E+00 8.500E-01  
 57-LA-140     1.558E+01 5.900E-01 7.912E+00 3.425E+00 0.0        
 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 7.875 for La-139 and 5.0 for La-140.               
 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) Nakajima, Y., et al.: J. Nucl. Sci. Technol., 20, 183(1983).  
 5) Allen, B.J., et al.: Nucl. Sci. Eng., 82, 230 (1982).         
 6) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).              
 7) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
 8) Foster, D.G. Jr. and Glasgow, D.W.: Phys. Rev., C3, 576       
 9) Islam, E., Hussain, M., Ameen, N., et al.: Nucl. Phys., A209, 
    189 (1973).                                                   
10) Nishimura, K., Yamanouti, Y., Kikuchi, S., et al.:  EANDC(J)  
    -22, p.22 (1971),                                             
    Nishimura, K. et al.: JAERI-M 6883 (1977).                    
11) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
12) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
13) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
14) 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.      
15) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
16) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
17) Gruppelaar, H.: ECN-13 (1977).                                
18) Matsumoto, J., et al.: JAERI-M 7734 (1978).                   
19) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
20) Musgrove, A.R. de L., et al.: Proc. Int. Conf. on Neutron     
    Physics and Nucl. Data for Reactors, Harwell 1978, 449.       
21) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
22) Forrest, R.A.: AERE-R 12419 (1986).                           
23) Woelfle, R., et al.: Applied Radiation and Isotopes, 39,      
    407 (1988).                                                   
24) Shwe, H. et al.: Phys. Rev., 159, 1050 (1967).                
25) Morgenstern, J.: Nucl. Phys., A123, 561 (1969).               
26) Hacken, G. et al.: Phys. Rev., C13, 1884 (1976).              
27) Musgrove, A.R.de L. et al.: Aust. J. Phys. 30, 599 (1977).    
28) Terlizzi, R. et al.: Phys. Rev., C75, 035807 (2007).          
29) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
    [in Japanese].