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 73-Ta-182 NEA        RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 7331                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
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**         Original data taken from:  JEFF-3.1                  **
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*****************************  JEFF-3.1  *************************
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**         Original data taken from:  JEFF-3.0                  **
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*****************************   JEFF-3.0   ***********************
                                                                  
   DATA TAKEN FROM   :-   JEF-2.2 (DIST-JAN92)                    
                                                                  
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*   JEF-2                                                        *
*     DATA WERE TAKEN FROM ENDF/B-IV (MAT=1127)                  *
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*   20-AUG-84: J-VALUES FOR UNRES.RES.PARAM. CORRECTED            
*    8-JAN-85: Q-VALUE FOR MT=107 CORRECTED                       
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           AI         EVAL-APR71 J.OTTER,C.DUNFORD,AND E.OTTEWITTE
 AI-AEC-12990 (1971)  DIST-MAY74                                  
 EXTENDED TO 20 MEV FOR ENDF/B VERSION-IV                         
 *         *          *          *         *          *          *
 TANTALUM-182 ENDF/B MAT 1127, MAY 1971 (REF) AI-AEC-12990        
  THERMAL XSCX AND RESONANCE PARAMETERS EVALUATED BY JOHN OTTER.  
  FAST CROSS SECTIONS EVALUATED BY CHARLES DUNFORD AND ERIC       
  OTTEWITTE. FILE ASSEMBLY BY PHILIP ROSE.                        
                                                                  
 MF=1 MT=451. DESCRIPTIVE INFORMATION                             
  ATOMIC MASS/  MATTAUCH,THIELE,WAPSTRA. NUCL.PHYS. 67,1(65).     
                                                                  
 MF=2 MT=151. RESONANCE PARAMETERS                                
  RESOLVED RESONANCES - E, 2*G*(GAMMA,N), AND GAMMA GAMMA WHERE   
 KNOWN FROM NSE 33,16. UNKNOWN GAMMA GAMMA EQUAL TO AVERAGE OF    
 KNOWN VALUES. J ASSIGNED IN PROPORTION TO 2*J+1. NEGATIVE        
 ENERGY RESONANCE PARAMETERS FROM FIT TO TOTAL CROSS SECTIONS AT  
 ONE AND THREE EV. CALCULATED 2200 M/S CROSS SECTIONS ARE         
 CAPTURE=8249B, SCATTERING=31B, AND TOTAL=8280B. POTENTIAL        
 SCATTERING ASSUMED SAME AS TA-181, = 8.3B.                       
  UNRESOLVED RESONANCE PARAMETERS ENERGY INDEPENDENT. DOBS AND    
 GAMMA GAMMA FROM RESOLVED RESONANCE RANGE  S0, S1, AND S2 SAME   
 AS TA-181. D(J)/DOBS FROM AAEC/TM 392.                           
  RESONANCE INTEGRAL - CAPTURE (0.5EV-100KEV) = 1020B. THERE IS   
 NO EXPERIMENTAL COMPARISON.                                      
                                                                  
 MF=3 MT=1. TOTAL CROSS SECTION                                   
  2PLUS AND COMNUC CALCULATIONAL RESULTS WERE USED DIRECTLY.      
                                                                  
 MF=3 MT=2. ELASTIC CROSS SECTION                                 
  2PLUS AND COMNUC CALCULATIONAL RESULTS WERE USED DIRECTLY.      
                                                                  
 MF=3 MT=4. TOTAL INELASTIC CROSS SECTION                         
  EQUAL TO THE SUM OF THE LEVEL EXCITATION AND CONTINUUM XSCS.    
                                                                  
 MF=3 MT=16. N-2N CROSS SECTION                                   
  THE ADOPTED CROSS SECTION IS THE TA-181 N-2N CROSS SECTION      
 SHIFTED IN ENERGY TO THE TA-182 THRESHHOLD.                      
                                                                  
 MF=3 MT=17. N-3N CROSS SECTION                                   
  THE N-3N CROSS SECTION WAS OBTAINED BY SUBTRACTING THE N-2N     
 AND INELASTIC CONTINUUM FROM THE NON-ELASTIC CROSS SECTION.      
                                                                  
 MF=3 MT=51. INELASTIC EXCITATION (DIRECT AND COMPOUND NUCLEUS)   
 TO THE 97 KEV LEVEL.                                             
  CROSS SECTIONS CALCULATED BY THE COMPUTER PROGRAMS 2PLUS AND    
 COMNUC HAVE BEEN ADOPTED WITHOUT CHANGE AT ENERGIES WELL ABOVE   
 THE THRESHHOLD. SEEMINGLY UNPHYSICAL STRUCTURE CALCULATED BY THE 
 COMNUC CODE WAS SMOOTHED OUT NEAR THE THRESHHOLD.                
                                                                  
 MF=3 MT=52-58,91. INELASTIC EXCITATION (COMPOUND NUCLEUS ONLY)   
  CALCULATION BY 2PLUS-COMNUC FOR 114, 173, 237, 270, 292, 315    
 AND 360 KEV LEVELS PLUS THE CONTINUUM. STRUCTURE IN THE 114 KEV  
 LEVEL NEAR THRESHHOLD SMOOTHED OUT. STRUCTURE CAUSED BY          
 COMPETITION FOR OPEN CHANNELS DUE TO 1ST LEVEL WEAKLY COUPLED    
 AND 2ND LEVEL STRONGLY COUPLED TO THE GROUND STATE.              
                                                                  
 MF=3 MT=102. N-GAMMA CROSS SECTION                               
  2PLUS-COMNUC RESULTS USED TO 5 MEV. ABOVE 5 MEV THE THEORY OF   
 V. BENZI AND G. REFFO WAS USED. REF  CCDN-NW/10 ENEA DATA CENTER 
                                                                  
 MF=3 MT=107. N-ALPHA CROSS SECTION                               
  SAME AS TA-181 (MAT 1126)                                       
                                                                  
 MF=4 MT=2. ANGULAR DISTRIBUTION OF ELASTICALLY-SCATTERED NEUTS.  
  TRANSFORMATION MATRIX CALCULATED FOR MASS 182. LEGENDRE         
 COEFFICIENTS TAKEN DIRECTLY FROM 2PLUS-COMNUC RUNS.              
                                                                  
 MF=4 MT=51-58,91. ANGULAR DISTRIBUTION OF NEUTRONS INELASTICALLY 
 SCATTERED TO DISCRETE LEVELS.                                    
  THE LEVEL DISTRIBUTIONS WERE MADE ISOTROPIC IN THE CM FRAME.    
 THE CONTINUUM WAS MADE ISOTROPIC IN THE LAB FRAME.               
                                                                  
 MF=5 MT=16,17. NUCLEAR TEMPERATURES - (N,2N),(N,3N) REACTIONS.   
  TEMPERATURE OF FIRST EMITTED NEUTRON SAME AS FOR MT=91.         
 TEMPERATURE OF SECOND AND THIRD EMITTED NEUTRONS DEDUCED BY      
 CONSERVATION OF ENERGY, ASSUMING THE KINETIC ENERGY OF AN        
 EMITTED NEUTRON IS 2*KT.                                         
                                                                  
 MF=5 MT=91. NUCLEAR TEMPERATURE - INELASTIC CONTINUUM            
  MAXWELLIAN DISTRIBUTION USED TO DESCRIBE NUCLEAR TEMPERATURE.   
 LEVEL SPACING SAME AS TA-181 (MAT 1126). U SPECIFIED FOR TA-182  
 THRESHHOLDS.                                                     
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