12-Mg- 26

 12-MG- 26 DEC,NEDAC  EVAL-MAR87 M.HATCHYA(DEC),T.ASAMI(NEDAC)    
                      DIST-SEP89                                  
----JENDL-3.2         MATERIAL 1231                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
 87-03  NEW EVALUATION WAS MADE FOR JENDL-3.                      
 87-03  COMPILED BY T.ASAMI.                                      
                                                                  
MF=1  GENERAL INFORMATION                                         
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          
                                                                  
MF=2  RESONANCE PARAMETERS                                        
 MT=151  RESOLVED RESONANCE PARAMETERS                            
   RESOLVED PARAMETERS FOR MLBW FORMULA WERE GIVEN IN             
   THE ENERGY REGION FROM 1.0E-5 EV TO 450 KEV.                   
   PARAMETERS WERE TAKEN FROM THE RECOMMENDED DATA OF BNL/1/ AND  
   THE DATA FOR A NEGATIVE RESONANCE WERE ADDED SO AS TO REPRODUCE
   THE RECOMMENDED THERMAL CROSS SECTIONS FOR CAPTURE AND SCATTER-
   ING/1/.                                                        
   THE SCATTERING RADIUS WAS ASSUMED TO BE 4.3 FERMI.             
   CALCULATED 2200 M/SEC CROSS SECTIONS AND RESONANCE INTEGRALS   
   ARE AS FOLLOWS:                                                
           2200 M/S CROSS SECTION(B)     RES. INTEGRAL(B)         
   ELASTIC    2.83                                                
   CAPTURE    0.038                        0.0190                 
   TOTAL      2.87                                                
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BELOW 450 KEV, ZERO BACKGROUND CROSS SECTION WAS GIVEN AND  ALL 
  THE CROSS-SECTION DATA ARE REPRODUCED FROM THE EVALUATED RESOLV-
  ED RESONANCE PARAMETERS WITH MLBW FORMULA.                      
  ABOVE 450 KEV, THE TOTAL AND PARTIAL CROSS SECTIONS WERE GIVEN  
  POINTWISE.                                                      
 MT=1 TOTAL                                                       
  OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH         
  THE CASTHY CODE/2/. THE OPTICAL POTENTIAL PARAMETERS USED ARE:  
    V = 49.68,                VSO = 7.12   (MEV)                  
   WS = 7.76 - 0.5*EN,         WV = 0      (MEV)                  
    R = 1.17,  RS = 1.09,  RSO = 1.17      (FM)                   
    A = 0.6,   ASO = 0.6,   B = 0.69       (FM)                   
 MT=2 ELASTIC SCATTERING                                          
  OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS   
  FROM THE TOTAL CROSS SECTION.                                   
 MT=4, 51-63, 91 INELASTIC SCATTERING                             
  CALCULATED WITH CASTHY /2/, TAKING ACCOUNT OF THE CONTRIBUTION  
  FROM THE COMPETING PROCESSES. THE DIRECT COMPONENT WAS          
  CALCULATED WITH THE DWUCK CODE/3/.                              
  THE LEVEL DATA USED IN THE ABOVE TWO CALCULATIONS WERE TAKEN    
  FROM REF./4/ AS FOLLOWS:                                        
    MT   LEVEL ENERGY(MEV)   SPIN-PARITY                          
             0.0                 0+                               
    51       1.8087              2+                               
    52       2.9384              2+                               
    53       3.5880              0+                               
    54       3.9405              3+                               
    55       4.3180              4+                               
    56       4.3320              2+                               
    57       4.3500              3+                               
    58       4.8340              2+                               
    59       4.9000              4+                               
    60       4.9720              0+                               
    61       5.2910              2+                               
    62       5.4740              4+                               
    63       5.6900              1+                               
  LEVELS ABOVE 8.0 MEV WERE ASSUMED TO BE OVERLAPPING.            
                                                                  
 MT=16, 22, 28, 103, 107     (N,2N), (N,NA), (N,NP), (N,P), (N,A) 
   CALCULATED WITH THE GNASH CODE/6/ USING THE ABOVE OPTICAL      
   MODEL PARAMETERS                                               
   THE (N,A) CROSS SECTIONS WERE NORMALIZED TO THE EXPERIMENTAL   
   DATA OF BORMANN/5/ AT 14 MEV.                                  
 MT=102      CAPTURE                                              
   CALCULATED WITH THE CASTHY CODE/2/ AND NORMALIZED TO 1.7 MB    
   AT 30 KEV.                                                     
 MT=251      MU-BAR                                               
   CALCULATED WITH THE OPTICAL MODEL.                             
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2                                                             
   CALCULATED WITH THE CASTHY CODE/2/.                            
 MT=51-63                                                         
   CALCULATED WITH THE CASTHY CODE/2/ AND THE DWUCK CODE/3/.      
 MT=91                                                            
   CALCULATED WITH THE CASTHY CODE/2/.                            
 MT=16, 22, 28                                                    
   ISOTROPIC IN THE LABORATORY SYSTEM.                            
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 22, 28, 91                                                
   CALCULATED WITH THE GNASH CODE/6/.                             
                                                                  
 REFERENCES                                                       
1) MUGHABGHAB S.F. AND GARBER D.I. :"NEUTRON CROSS SECTIONS", VOL.
   1, PART B (1984).                                              
2) IGARASI S. : J. NUCL. SCI. TECH. 12, 67 (1975).                
3) KUNZ P.D. : UNPUBLISHED.                                       
4) ENSDF(EVALUATED NUCLEAR STRUCTURE DATA FILE)                   
5) BORMANN M. ET AL. : 1966 PARIS CONF. VOL.1, 225 (1967).        
6) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).