12-Mg- 24

 12-MG- 24 DEC,NEDAC  EVAL-MAR87 M.HATCHYA(DEC), T.ASAMI(NEDAC)   
                      DIST-SEP89 REV2-APR93                       
----JENDL-3.2         MATERIAL 1225                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
 87-03  NEW EVALUATION WAS MADE FOR JENDL-3.                      
 87-03  COMPILED BY T.ASAMI.                                      
 93-04  JENDL-3.2                                                 
        COMPILED BY T.NAKAGAWA (NDC/JAERI)                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (4,91)               CHANGED TO THE LABORATORY SYSTEM       
     ***********************************************************  
                                                                  
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 520 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 SCATTERING/1/.  THE DATA FOR    
   SOME LEVELS WERE MODIFIED SO THAT THE CALCULATED TOTAL CROSS   
   SECTIONS OF THE ELEMENT MG WERE FITTED TO THE EXPERIMENTAL DATA
   OF HIBDON/2/ AND SINGH/3/.  THE SCATTERING RADIUS WAS ASSUMED  
   TO BE 5.4 FERMI.  CALCULATED 2200 M/SEC CROSS SECTIONS AND     
   RESONANCE INTEGRALS ARE AS FOLLOWS:                            
                                                                  
           2200 M/S CROSS SECTION(B)     RES. INTEGRAL(B)         
   ELASTIC      3.75                                              
   CAPTURE      0.050                       0.0312                
   TOTAL        3.80                                              
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BELOW 520 KEV, NO BACKGROUND CROSS SECTION IS GIVEN AND ALL THE 
  CROSS-SECTION DATA ARE REPRODUCED FROM THE EVALUATED RESOLVED   
  RESONANCE PARAMETERS WITH THE MLBW FORMULA.                     
  ABOVE 520 KEV, THE TOTAL AND PARTIAL CROSS SECTIONS ARE GIVEN IN
  THE POINTWISE FORM.                                             
 MT=1 TOTAL                                                       
  OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH         
  CASTHY CODE/4/. 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, 51-61, 91 INELASTIC SCATTERING                             
  CALCULATED WITH CASTHY /4/, TAKING ACCOUNT OF THE CONTRIBUTION  
  FROM THE COMPETING PROCESSES. THE DIRECT COMPONENTS FOR MT=51   
  AND 52 WERE, CALCULATED WITH THE DWUCK/5/. THE CALCULATED DATA  
  FOR THE FIRST LEVEL WERE NORMALIZED AT 12 MEV TO THE EXPERIMEN- 
  TAL DATA/6/.  THE LEVEL DATA USED IN THESE TWO CALCULATIONS WERE
  TAKEN FROM REF./7/ AS FOLLOWS:                                  
       MT   LEVEL ENERGY(MEV)   SPIN-PARITY                       
                0.0                 0+                            
       51       1.3686              2+                            
       52       4.1200              4+                            
       53       4.2384              2+                            
       54       5.2361              3+                            
       55       6.0103              4+                            
       56       6.4322              0+                            
       57       7.3479              2+                            
       58       7.5530              1-                            
       59       7.6162              3-                            
       60       7.7472              1+                            
       61       7.8120              3+                            
  LEVELS ABOVE 10.0 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/8/ USING THE ABOVE OPTICAL MODEL
   PARAMETERS.  THE (N,2N) CROSS SECTIONS WERE MODIFIED SO AS TO  
   FIT TO THE EXPERIMENTAL DATA.                                  
 MT=102      CAPTURE                                              
   CALCULATED WITH THE CASTHY CODE/4/ AND NORMALIZED TO 1.8 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/4/.                            
 MT=51-61                                                         
   CALCULATED WITH THE CASTHY CODE/4/, AND CONTRIBUTIONS FROM THE 
   DIRECT PROCESS CALCULATED WITH THE DWUCK CODE/5/ WERE ADDED TO 
   MT=51 AND 52.                                                  
 MT=91                                                            
   CALCULATED WITH THE CASTHY CODE/4/ AND TRANSFORMED INTO THE    
   LABORATORY SYSTEM.                                             
 MT=16, 22, 28                                                    
   ASSUMED TO BE ISOTOROPIC IN THE LABORATORY SYSTEM.             
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 22, 28, 91                                                
   CALCULATED WITH THE GNASH CODE/8/.                             
                                                                  
REFERENCES                                                        
1) MUGHABGHAB S.F. AND GARBER D.I. :"NEUTRON CROSS SECTIONS", VOL.
   1, PART B (1984).                                              
2) HIBDON C.T. : TAKEN FROM EXFOR (1969).                         
3) SINGH U.N. ET AL. : PHYS. REV. C10, 2150 (1974).               
4) IGARASI S. : J. NUCL. SCI. TECH. 12, 67 (1975).                
5) KUNZ P.D. : UNPUBLISHED.                                       
6) FOERTSCH ET AL. : NUCL. INSTR. METH. 169, 533 (1980).          
7) ENSDF(EVALUATED NUCLEAR STRUCTURE DATA FILE)                   
8) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).