93-Np-235

 93-Np-235 JAERI      EVAL-MAR95 T.Nakagawa                       
                      DIST-MAR02                       20001004   
----JENDL-3.3         MATERIAL 9340                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
95-02 New evaluation was made by T.Nakagawa. STAPRE calculation   
      was performed by Konshin /Ko95/.                            
00-10 Compiled by T.Nakagawa.                                     
                                                                  
MF=1 General information                                          
  MT=451 Descriptive data                                         
  MT=452 Number of neutrons per fission                           
    Sum of MT=455 and 456.                                        
  MT=455 Delayed neutrons per fission                             
    Tuttle's systematics /Tu79/ was adopted.                      
  MT=456 Prompt neutrons per fission                              
    Obtained from Howerton's sytematics /Ho77/.                   
                                                                  
MF=2 Resonance parameters                                         
  MT=151                                                          
    No resonance parameters were given.                           
                                                                  
      Thermal cross sections and resonance integral (barns)       
                                                                  
                  0.0253 eV     resonance int.                    
      Total        181.4            -                             
      Elastic       11.4            -                             
      Fission       20             46.6                           
      Capture      150            851                             
                                                                  
MF=3 Neutron cross sections                                       
  Below 0.4 eV                                                    
    The capture is based on the data of Landrum et al./La72/      
    The elastic scattering cross section of 11.4 b is the shape   
    elastic scattering calculated with optical model code         
    CASTHY/Ig91/. The fission cross section is assumed to be      
    similar to that of Pu-238.                                    
                                                                  
  Above 0.4 eV                                                    
    Three codes of CASTHY/Ig91/, ECIS/Ra00/ and STAPRE/Uh76/      
    were used.                                                    
                                                                  
    Parameters (MeV, fm) of deformed potential/Ko93/ for ECIS:    
         V   = 46.03 -  0.3*E                                     
         W-d = 3.05 + 0.4*E                0 =< E =< 10 MeV       
             = 7.05 - 0.082*(E-10)         10 < E <=20 MeV        
         W-v = 8.0/(1+exp(-(E-50)/10))                            
         V-so= 6.2                                                
         r-r = 1.26             a-r = 0.63                        
         r-d = 1.26             a-d = 0.52                        
         r-so= 1.12             a-so= 0.47                        
         beta-2 = 0.204       beta-4 =0.051                       
                                                                  
    The spherical potential parameters/Ig85/ used in CASTHY:      
         V   = 45.036 - 0.3*E, r-r = 1.256, a-r = 0.626           
         W-d = 4.115 + 0.4*E,  r-d = 1.260, a-d = 0.555+0.0045*E  
         V-so= 7.5,            r-so= 1.256, a-so= 0.626           
                                                                  
    Level density parameters used in CASTHY:                      
                a(1/MeV)  T(MeV)  delta(MeV) E-x(MeV) spin-cutoff 
      Np-235     30.4      0.38    0.7828      3.929     30.66    
      Np-236     28.0      0.35    0.0         2.258     20.50    
                                                                  
    STAPRE calculation is described in Ko95.                      
                                                                  
  MT=1 Total                                                      
    Calculated with CASTHY.                                       
                                                                  
  MT=2 Elastic scattering                                         
    Calculated as the (total) - (sum of partial) cross sections.  
                                                                  
  MT=4, 51-91 Inelastic scattering                                
    Compound process was calculated with CASTHY, and direct one   
    with ECIS.                                                    
                                                                  
    Level scheme/Sc93/:                                           
         Energy (keV)  Spin-parity direct-component               
            0.0           5/2 +                                   
           34.23          7/2 +          *                        
           49.1           5/2 -                                   
           79.1           9/2 +          *                        
           91.6           7/2 -                                   
          133.           11/2 +          *                        
          146.8           9/2 -                                   
          200.           13/2 +          *                        
          352.            3/2 -                                   
          371.            1/2 -                                   
          408.            7/2 -                                   
          441.            5/2 -                                   
          520.           11/2 -                                   
          565.            3/2 -                                   
          602.            5/2 -                                   
          644.            7/2 -                                   
          700.            9/2 -                                   
     Levels above 750 keV were assumed to be overlapping.         
     The direct process was calculated with ECIS for the levels   
     marked with *, and the compound process with CASTHY.         
                                                                  
  MT=16,17 (n,2n) and (n,3n) reactions                            
    Calculated with STAPRE.                                       
                                                                  
  MT=18 Fission                                                   
    Based on the calculation with STAPRE and systematics of the   
    fission cross section shape.                                  
                                                                  
  MT=102 capture                                                  
    Calculated with CASTHY. The direct and semi-direct cross      
    section was calculated with DSD /Ka99/.                       
                                                                  
MF=4 Angular distributions of secondary neutrons                  
  MT=2 Elastic scattering                                         
    Calculated with ECIS.                                         
                                                                  
  MT=16,17, 18 (n,2n), (n,3n) and Fission                         
    Assumed to be isotopic in the laboratory system.              
                                                                  
  MT=51-91 Inelastic scattering                                   
    Calculated with CASTHY and ECIS.                              
                                                                  
MF=5 Energy distributions of secondary neutrons                   
  MT=16, 17, 91                                                   
    Calculated with EGNASH /Ya90/.                                
                                                                  
  MT=18                                                           
    Evaporation spectrum with nuclear temperature obtained from   
    the systematics of Smith et al. /Sm79/ and Howerton and Doyas 
    /Ho71/.  The ratios of multi-chance fission to total were     
    estimated from the STAPRE calculation/Ko95/.                  
                                                                  
References                                                        
Ho71) R.J. Howerton and R.J. Doyas: Nucl. Sci. Eng., 46, 414      
      (1971).                                                     
Ho77) R.J. Howerton: Nucl. Sci. Eng., 62, 438 (1977).             
Ig85) A.V. Ignatyuk, et al.: Sov. J. Nucl. Phys. 42, 360 (1985).  
Ig91) S. Igarasi and T. Fukahori: JAERI 1321 (1991).              
Ka99) T. Kawano: private communication (1999).                    
Ko93) V.A. Konshin, et al.: Proc. Workshop on Computation and     
      Analysis of Nuclear Data Relevant to Nuclear Energy and     
      Safety, Trieste, Italy, 10 Feb. - 13 Mar 1992, World        
      Scientific, p.775 (1993).                                   
Ko95) V.A. Konshin: JAERI-Research 95-010 (1995).                 
La72) J.H. Landrum, et al.: UCRL-51263 (1972).                    
Ra00) J. Raynal: available from OECD NEA Data Bank.               
Sc93) M.R. Schmorak: Nucl. Data Sheets, 69, 375 (1993).           
Sm79) A. Smith, et al.: ANL/NDM-50 (1979).                        
Tu79) R.J. Tuttle: INDC(NDS)-107/G+Special, p.29 (1979).          
Uh76) M. Uhl and B. Stromaier: IRK-76/10 (1976).                  
Ya90) N. Yamamuro: JAERI-M 90-006 (1990).