72-Hf-176

 72-HF-176 NAIG+      EVAL-JUL89 HIDA, YOSHIDA AND SHIBATA(JAERI) 
                      DIST-MAR02 REV3-APR01            20010417   
----JENDL-3.3         MATERIAL 7231                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
89-07 New evaluation for JENDL-3 was made by K.Hida, T.Yoshida    
      (naig) and K.Shibata (jaeri).                               
94-01 JENDL-3.2.                                                  
      Compiled by T.Nakagawa (ndc/jaeri)                          
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      (3,2), (3,4), (3,51), (3,55-73)                             
                    Curves of inelastic scattering cross sections 
                    were smoothed by adding interpolated values at
                    several energy points.                        
     ***********************************************************  
01-04 JENDL-3.3                                                   
      Compiled by K.Shibata (ndc/jaeri)                           
     *****   modified parts for JENDL-3.3   ********************  
      (1,451)       Updated.                                      
      (3,1)         Mesured data were considered between 110 keV  
                    and 7.5 MeV.                                  
      (3,2)         Re-calculated.                                
      (3,251)       Deleted.                                      
      (4,2)         Transformation matrix deleted.                
      (5,16-91)     INT=22                                        
     ***********************************************************  
                                                                  
                                                                  
mf=1  General information                                         
 mt=451  Descriptive data and dictionary                          
                                                                  
mf=2  Resonance parameters                                        
 mt=151 Resolved and unresolved resonance parameters              
  Resolved resonances for MLBW formula                            
   Energy range            : 1.0e-5 eV to 700 eV.                 
   Res. energies and gam-n : BNL-325 /1/.                         
   Gam-gamma               : 0.060 eV assumed if unknown.         
   Radius                  : 7.6 fm                               
  Unresolved resonances                                           
   Energy range            : 700 eV to 50 keV.                    
   s0, s1, r and gam-gamma : Adjusted so that the calculated total
                             and capture cross sections were      
                             reproduced well.                     
   Results are d-obs = 55.2 eV, s0 = 2.00e-4, s1 = 1.00e-4,       
   r = 9.1 fm and gam-gamma = 0.054 eV.                           
                                                                  
      2200 m/sec cross sections and calculated res. integrals.    
                    2200 m/sec    res. integ.                     
          total       29.02 b        -                            
          elastic      5.54 b        -                            
          capture     23.48 b      893.1 b                        
                                                                  
mf=3  Neutron cross sections                                      
Below 50 keV :                                                    
 No background was given.                                         
Above 50 keV :                                                    
 mt=1,2,4,51-73,91,102  Total,elastic,inelastic and capture       
  calculated with ecis /2/ and casthy /3/.  Deformed optical      
  potential for ecis calculation was determined so as to reproduce
  the experimental total cross section of natural hafnium,        
  starting with the Haouat potential /4/.                         
    V0 = 46.89-0.3*En, Ws = 3.84+0.4*En (En<10), Vso = 6.2 (MeV), 
                          = 7.84        (En>10)                   
     a0 = 0.63,         as = 0.52,                aso = 0.47 (fm),
     r0 = 1.24,         rs = 1.24,                rso = 1.12 (fm),
     beta-2 = 0.276,    beta-4 = 0.0.                             
  The deformation parameter beta-2 was determined from the        
  measured E2 transition probability data /5/.  The lowest three  
  levels belonging to the ground state rotational band were       
  coupled in the calculation.  The spherical optical potential for
  casthy calculation is the same as that of JENDL-2.              
         V0 = 38.0, Ws = 8.0+0.5*sqrt(En), vso = 7.0 (MeV),       
         a0 = 0.47, as = 0.52            , aso = 0.47 (fm),       
         r0 = 1.32, rs = 1.32            , rso = 1.32 (fm).       
  Capture cross section was normalized to the measured data of    
  beer et al. /6/ at 30 keV.  Competing processes (n,2n), (n,3n), 
  (n,p), and (n,alpha) were calculated with gnash /7/ and fed to  
  ecis-casthy calculation.  The level fluctuation and interference
  effects were considered.  Level scheme was taken from table of  
  isotopes /8/.                                                   
         no.    energy(MeV)   spin-parity                         
         g.s.    0.0             0 +                              
          1      0.0883          2 +                              
          2      0.2902          4 +                              
          3      0.5970          6 +                              
          4      0.9980          8 +                              
          5      1.1499          0 +                              
          6      1.2266          2 +                              
          7      1.2477          2 -                              
          8      1.2932          0 +                              
          9      1.3133          3 -                              
         10      1.3413          2 +                              
         11      1.3794          2 +                              
         12      1.4046          4 -                              
         13      1.4458          3 +                              
         14      1.5777          3 +                              
         15      1.6434          1 -                              
         16      1.6723          1 +                              
         17      1.7046          2 +                              
         18      1.7102          3 -                              
         19      1.7221          1 -                              
         20      1.7675          2 -                              
         21      1.7861          3 +                              
         22      1.7937          3 -                              
         23      1.8190          0 -                              
    Continuum levels assumed above 1.8400 MeV.                    
  The level density parameters for Gilbert and Cameron's formula  
  /9/ are the same as those of JENDL-2.                           
                 a(1/MeV)   c(1/MeV)  t(MeV)   Ex(MeV)  sigma**2  
         hf-176    22.77      1.74     0.454     4.38     6.09    
         hf-177    22.61      9.06     0.486     4.38     9.45    
  ***  modification for JENDL-3.3 ********************************
  For mt=1, measured data /10,11,12/ on natural element were      
  considered in the energy region from 110 keV to 7.5 MeV.        
  ****************************************************************
                                                                  
 mt=16,17,103,107  (n,2n), (n,3n), (n,p) and (n,alpha)            
  Calculated with gnash /7/. The transmission coefficients for    
  the incident channel were generated with ecis /2/, while those  
  for the exit channels with eliese-3 /13/.  The preequilibrium   
  parameter f2 was adjusted to reproduce the measured (n,2n) cross
  section at 14.5 MeV and resulted in f2=5.0.                     
                                                                  
mf=4  Angular distributions of secondary neutrons                 
 mt=2,51-73,91                                                    
  Calculated with ecis /2/ and casthy /3/.                        
 mt=16,17                                                         
  Isotropic in the laboratory system.                             
                                                                  
mf=5  Energy distributions of secondary neutrons                  
 mt=16,17,91                                                      
  Calculated with gnash /7/.                                      
                                                                  
mf=12 Photon multiplicities and transition probabilities          
 mt=16,17,91,102,103,107                                          
  Calculated with gnash /7/ and stored under option-1 (photon     
  production multiplicities).  The photon strength functions for  
  most nuclei were taken from /1/, while those for some hafnium   
  isotopes were determined from capture cross section normaliza-  
  tion to the experimental data.  The photon profile function is a
  superposition of the Berman-type giant dipole resonance /14/    
  and the pygmy resonance whose parameter values were cited from  
  the neighbouring nucleus Ta /15/.                               
         eg1 = 15.23,   eg2 = 12.3 ,   ep = 5.2 (MeV),            
         gg1 =  4.48,   gg2 =  2.43,   gp = 2.5 (MeV),            
         sig-pygmy/sig-gdr = 0.0245.                              
                                                                  
 mt=51-73                                                         
  Stored under option-2 (transition probability array).  Data were
  taken from /8/.                                                 
                                                                  
mf=14 Photon angular distributions                                
 mt=16,17,51-68,91,102,103,107                                    
  Isotropic.                                                      
                                                                  
mf=15 Continuous photon energy spectra                            
 mt=16,17,91,102,103,107                                          
  Calculated with gnash /7/.                                      
                                                                  
References                                                        
 1) Mughabghab S.F.: Neutron cross sections, Vol.1, Part B (1984).
 2) Raynal J.: IAEA SMR-9/8 (1970).                               
 3) Igarasi S. and Fukahori T.: JAERI 1321 (1991).                
 4) Haouat G. et al.: Nucl. Sci. Eng., 81, 491 (1982).            
 5) Raman S. et al.: At. Data Nucl. Data Tables, 36, 1 (1987).    
 6) Beer H. et al.: Phys. Rev., C30, 464 (1984).                  
 7) Young P.G. and Arthur E.D.: LA-6947 (1977).                   
 8) Lederer C.M. and Shirley V.S.: Table of isotopes 7th edition  
    (1979).                                                       
 9) Gilbert A. and Cameron A.G.W.: Can. J. Phys., 43, 1446 (1965).
10) Sherwood G.L. et al.: Nucl. Sci. Eng., 39, 67 (1970).         
11) Foster,Jr. D.G. and Glasgow D.W.: Phys. Rev., C3, 576 (1971). 
12) Poenitz W.P. and Whalen J.F.: ANL/NDM-80 (1983).              
13) Igarasi S.: JAERI-1224 (1972).                                
14) Berman B.L.: At. Data Nucl. Data Tables, 15, 319 (1975).      
15) Igashira M. et al.: Int. Symp. Capture Gamma-ray Specroscopy  
    and Related Topics - 1984, 523 (1985).