72-Hf- 0

 72-HF-  0 NAIG+      EVAL-JUL89 HIDA, YOSHIDA AND SHIBATA(JAERI) 
                      DIST-SEP89 REV2-JAN94                       
----JENDL-3.2         MATERIAL 7200                               
-----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), (3,3), (3,4), (3,51-54),(3,58-62), (3,66-68)         
      (3,70-74), (3,76-78)                                        
                    CURVES OF INELASTIC SCATTERING CROSS SECTIONS 
                    WERE SMOOTHED BY ADDING INTERPOLATED VALUES AT
                    SEVERAL ENERGY POINTS.                        
      (3,102)       Q-VALUE WAS CHANGED.                          
      (12,102)      MODIFIED.                                     
     ***********************************************************  
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          
                                                                  
MF=2  RESONANCE PARAMETERS                                        
 MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS              
  RESONANCE REGION: 1.0E-5 EV TO 50 KEV                           
  RESOLVED RESONANCES FOR MLBW FORMULA                            
   MADE UP OF ISOTOPIC FILES.                                     
  UNRESOLVED RESONANCES                                           
   MADE UP OF ISOTOPIC FILES.                                     
                                                                  
      2200 M/SEC CROSS SECTIONS AND CALCULATED RES. INTEGRALS.    
                    2200 M/SEC    RES. INTEG.                     
          TOTAL     114.9 B          -                            
          ELASTIC     9.9 B          -                            
          CAPTURE   105.0 B       1996. B                         
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
BELOW 50 KEV :                                                    
 NO BACKGROUND WAS GIVEN.                                         
ABOVE 50 KEV :                                                    
 MT=1     TOTAL                                                   
  50 KEV - 110 KEV : MADE UP OF ISOTOPIC FILES.                   
  110 KEV - 7.5 MEV: SPLINE-FUNCTION FITTING TO THE EXPERIMENTAL  
                     DATA/1,2,3/.                                 
  7.5 MEV - 20 MEV : MADE UP OF ISOTOPIC FILES.                   
 MT=2     ELASTIC                                                 
  OBTAINED BY SUBTRACTING A SUM OF PARTIAL REACTION CROSS SECTIONS
  FROM THE TOTAL CROSS SECTION.                                   
 MT=3     NONELASTIC                                              
  SUM OF MT=4, 16, 17, 102, 103, 107.                             
 MT=4     TOTAL INELASTIC                                         
  SUM OF MT=51-79, 91.                                            
 MT=51-79, 91    INELASTIC                                        
  MADE UP OF ISOTOPIC FILES.                                      
  THE DISCRETE LEVELS WERE LUMPED.                                
 MT=16,17,102,103,107  (N,2N),(N,3N),(N,GAMMA),(N,P),(N,ALPHA)    
  MADE UP OF ISOTOPIC FILES.                                      
 MT=251  MU-BAR                                                   
  CALCULATED FROM MF/MT=4/2.                                      
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2,51-79,91                                                    
  MADE UP OF ISOTOPIC FILES.                                      
 MT=16,17                                                         
  ISOTROPIC IN THE LABORATORY SYSTEM.                             
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16,17,91                                                      
  MADE UP OF ISOTOPIC FILES.                                      
                                                                  
MF=12 PHOTON PRODUCTION MULTIPLICITIES                            
 MT=3,102                                                         
  MADE UP OF ISOTOPIC FILES.                                      
                                                                  
MF=14 PHOTON ANGULAR DISTRIBUTIONS                                
 MT=3,102                                                         
  ISOTROPIC.                                                      
                                                                  
MF=15 CONTINUOUS PHOTON ENERGY SPECTRA                            
 MT=3,102                                                         
  MADE UP OF ISOTOPIC FILES.                                      
                                                                  
REFERENCES                                                        
 1) SHERWOOD G.L. ET AL.: NUCL. SCI. ENG., 39, 67 (1970).         
 2) FOSTER JR. D.G. AND GLASGOW D.W.: PHYS. REV. C3, 576 (1971).  
 3) POENITZ W.P. AND WHALEN J.F.: ANL/NDM-80 (1983).