11-Na- 23

 11-NA- 23 SRI        EVAL-MAR87 H.YAMAKOSHI(SHIP RESEARCH INST.) 
                      DIST-SEP89 REV2-NOV93                       
----JENDL-3.2         MATERIAL 1125                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
 87-03  NEW EVALUATION WAS MADE FOR JENDL-3.                      
 89-08  THE DATA FOR MF=15,MT=102 MODIFIED.                       
 93-11  JENDL-3.2                                                 
        MF=3,MT=1: MODEFIED BY T.FUKAHORI(JAERI)                  
        MF=4,MT=91: CHANGED TO LAB. SYSTEM BY T.NAKAGAWA(JAERI)   
        GAMMA-RAY PART: MODEFIED BY T.ASAMI(DATA ENG. CO. LTD.)   
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      ( 3,  1)     LARSON'S DATA/1/ ABOVE 1 MEV                   
      ( 3,  2)     ACCORDING TO (3,1) ABOVE 1 MEV                 
      (3,16),(3,22),(3,51),(3,103),(3,107)  AROUND THRESHOLD      
                   ENERGIES.                                      
      ( 4, 91)     CHANGED TO LAB. SYSTEM                         
      (12,51-61)   UPPER ENERGY LIMIT: 6.26 MEV                   
      (12,62-67)   ADDED                                          
      (12,102)     FROM ENERGY BALANCE                            
                   UPPER ENERGY LIMIT: 6.26 MEV                   
      (12,103)     UPPER ENERGY LIMIT: 6.26 MEV                   
      (13,  3)     LOWER ENERGY LIMIT: 6.26 MEV                   
      (14,62-67)   ADDED                                          
      (15,102)     RECALCULATION BY CASTHY AT 1.0E-5,0.0253 EV.   
     ***********************************************************  
                                                                  
                                                                  
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 350 KEV.  PARAMETERS WERE MAINLY TAKEN
   FROM THE RECOMMENDED DATA OF BNL /2/, AND THE DATA FOR SOME    
   LEVELS WERE MODIFIED SO THAT THE CALCULATED TOTAL CROSS SEC-   
   TIONS FOR NA-23 WERE FITTED TO THE EXPERIMENTAL DATA.  THE     
   SCATTERING RADIUS WAS ASSUMED TO BE 5.2 FERMI.  CALCULATED 2200
   M/SEC CROSS SECTIONS AND RESONANCE INTEGRALS ARE AS FOLLOWS:   
                                                                  
           2200 M/S CROSS SECTION(B)     RES. INTEGRAL(B)         
   ELASTIC       3.024                                            
   CAPTURE       0.531                         0.3122             
   TOTAL         3.555                                            
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BELOW 350 KEV, BACKGROUND CROSS SECTION WAS GIVEN FOR THE TOTAL 
  AND ELASTIC SCATTERING CROSS SECTIONS.  THE CROSS-SECTION DATA  
  ARE REPRODUCED FROM THE EVALUATED RESOLVED RESONANCE PARAMETERS 
  WITH MLBW FORMULA.  ABOVE 350 KEV, THE TOTAL AND PARTIAL CROSS  
  SECTIONS WERE GIVEN POINTWISE.                                  
 MT=1 TOTAL                                                       
  IN THE ENERGIES BETWEEN 350 KEV AND 14 MEV, EVALUATED BASED ON  
  THE EXPERIMENTAL DATA OF CIERJACKS/3/ IN TRACING THEIR FINE     
  STRUCTURES. ABOVE 14 MEV, BASED ON THE EXPERIMENTAL DATA OF     
  LANGSFORD/4/, STOLER/5/ AND LARSON/1/.  MODEFICATION WAS DONE BY
  T.FUKAHORI(JAERI) TO BE BASED ON THE EXPERIMENTAL DATA OF ONLY  
  LARSON/1/ ABOVE 1 MEV.                                          
 MT=2 ELASTIC SCATTERING                                          
  OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS   
  FROM THE TOTAL CROSS SECTION.                                   
 MT=4, 51-77, 91 INELASTIC SCATTERING                             
  BELOW 5 MEV, THE INELASTIC SCATTERING CROSS SECTION TO THE 1ST  
  LEVEL(MT=51) WAS EVALUATED BASED ON THE EXPERIMENTAL DATA OF    
  TOWLE AND GILBOY/6/, CHRIEN AND SMITH/7/, AND LIND AND DAT/8/.  
  BELOW 5 MEV, THE INELASTIC SCATTERING CROSS SECTION TO THE 2ND  
  AND 3RD LEVEL(MT=52, 53) WAS EVALUATED BASED ON THE EXPERIMENTAL
  DATA OF FREEMAN AND MONTAGUE/9/, LIND AND DAT/8/, AND TOWLE AND 
  OWENS/10/. FOR THE INELASTIC SCATTERING CROSS SECTIONS TO THE   
  1ST TO 3RD LEVELS ABOVE 5 MEV AND THE OTHER INELASTIC SCATTERING
  DATA, OPTICAL AND STATISTICAL MODEL CALCULATIONS WERE MADE WITH 
  THE CASTHY CODE/11/, TAKING ACCOUNT OF THE CONTRIBUTION FROM THE
  COMPETING PROCESSES. THE DIRECT COMPONENT WAS CALCULATED WITH   
  WITH THE DWUCK CODE/12/ FOR FIVE LOWEST LEVELS. THE DEFORMATION 
  PARAMETERS WERE ESTIMATED BASED ON A WEAK COUPLING MODEL.  THE  
  OPTICAL POTENTIAL PARAMETERS USED ARE:                          
    V = 46.0 - 0.25*EN,       VSO = 6.0      (MEV)                
   WS = 14.0 - 0.2*EN,         WV = 0.125*EN (MEV)                
    R = 1.286, RS = 1.39,  RSO = 1.07        (FM)                 
    A = 0.62,  ASO = 0.62,  B = 0.7          (FM)                 
 THE LEVEL DATA USED IN THE ABOVE TWO CALCULATIONS WERE TAKEN     
 FROM REF./13/ AS FOLLOWS:                                        
    MT   LEVEL ENERGY(MEV)   SPIN-PARITY                          
             0.0               3/2+                               
    51       0.4399            5/2+                               
    52       2.0764            7/2+                               
    53       2.3909            1/2+                               
    54       2.6398            1/2-                               
    55       2.7037            9/2+                               
    56       2.9824            3/2+                               
    57       3.6783            3/2-                               
    58       3.8480            5/2-                               
    59       3.9147            5/2+                               
    60       4.4320            1/2+                               
    61       4.7756            7/2+                               
    62       5.3800            3/2+                               
    63       5.5360           11/2+                               
    64       5.7410            3/2+                               
    65       5.7660            5/2+                               
    66       5.9310            1/2-                               
    67       5.9670            3/2-                               
    68       6.0430            1/2-                               
    69       6.1170           11/2+                               
    70       6.1910           11/2+                               
    71       6.2360           13/2+                               
    72       6.3080            1/2+                               
    73       6.3506            9/2-                               
    74       6.5770            5/2+                               
    75       6.6170            9/2+                               
    76       6.7340            3/2+                               
    77       6.8680            5/2+                               
  LEVELS ABOVE 6.9 MEV WERE ASSUMED TO BE OVERLAPPING.            
                                                                  
 MT=16     (N,2N)                                                 
    MAINLY BASED ON THE EXPERIMENTAL DATA OF ADAMSKI/14/.         
 MT=22     (N,NA)                                                 
    CALCULATED WITH THE GNASH CODE/15/ AND NORMALIZED TO THE      
    EXPERIMENTAL DATA OF WOELFER/16/ AT 16.4 MEV.                 
 MT=28     (N,NP)                                                 
    CALCULATED WITH THE GNASH CODE/15/.                           
 MT=102      CAPTURE                                              
    CALCULATED WITH THE CASTHY CODE/11/ AND NORMALIZED TO 0.3 MB  
    AT 500 KEV.                                                   
 MT=103    (N,P)                                                  
    BELOW 10 MEV, BASED ON THE EXPERIMENTAL DATA/17,18/.          
    ABOVE 10 MEV, CALCULATED WITH THE GNASH CODE/15/ AND NORMALIZ-
    ED TO CONNECT SMOOTHLY WITH THE DATA BELOW 10 MEV.            
 MT=107    (N,A)                                                  
    BELOW 12 MEV, BASED ON THE EXPERIMENTAL DATA/17,18/.          
    ABOVE 12 MEV, CALCULATED WITH THE GNASH CODE/15/ AND NORMALIZ-
    ED TO CONNECT SMOOTHLY WITH THE DATA BELOW 10 MEV.            
 MT=251      MU-BAR                                               
    CALCULATED WITH THE OPTICAL MODEL.                            
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2                                                             
    CALCULATED WITH THE CASTHY CODE/11/.                          
 MT=51-77                                                         
    CALCULATED WITH THE CASTHY CODE/11/ AND THE DWUCK CODE/7/.    
 MT=91                                                            
    CALCULATED WITH THE CASTHY CODE/11/ AND TRANSFORMED INTO THE  
    LABORATORY SYSTEM.                                            
 MT=16, 22, 28                                                    
    ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.             
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 22, 28, 91                                                
    CALCULATED WITH THE GNASH CODE/15/.                           
                                                                  
MF=12  PHOTON PRODUCTION MULTIPLICITIES                           
 MT=51-67,102,103                                                 
   CALCULATED WITH THE GNASH CODE.                                
   FOR THE JENDL-3.2, MODIFICATIONS WERE DONE FOR ENERGY BALANCE  
   AND FOR CHANGING UPPER ENERGY LIMIT FROM 5.21937 MEV TO 6.26325
   MEV.                                                           
                                                                  
MF=13  PHOTON PRODUCTION CROSS SECTIONS                           
 MT=3                                                             
   CALCULATED WITH THE GNASH CODE/15/.                            
   FOR THE JENDL-3.2, LOWER ENERGY LIMIT WAS CHANGED TO 6.26325   
   MEV, ACCORDING TO MF=12 MODIFICATION.                          
                                                                  
MF=14  PHOTON ANGULAR DISTRIBUTIONS                               
 MT=3,51-67,102,103                                               
   ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.              
                                                                  
MF=15  CONTINUOUS PHOTON ENERGY SPECTRA                           
 MT=3,103                                                         
   CALCULATED WITH THE GNASH CODE/15/.                            
 MT=102                                                           
   CALCULATED WITH THE GNASH CODE/15/ AND MODIFIED AT THERMAL     
   BASED ON THE EXPERIMENTAL DATA OF MAERKER/19/ AND CASTHY       
   CALCULATION.                                                   
                                                                  
REFERENCES                                                        
 1) LARSON D.C. ET AL. : ORNL-TM-5614 (1976).                     
 2) MUGHABGHAB S.F. AND GARBER D.I. :"NEUTRON CROSS SECTIONS",    
    VOL. 1, PART B (1984).                                        
 3) CIERJACKS S. ET AL. : KFK-1000 (1969).                        
 4) LANGSFORD A. ET AL. : 1965 ANTWERP CONF. 529 (1965).          
 5) STOLER P. ET AL. : 1971 KNOXVILLE CONF. VOL.1, 311 (1971).    
 6) TOWLE J.H. AND GILBOY W.B. : NUCL. PHYS. 32, 610 (1962).      
 7) CHRIEN J.P. AND SMITH A.B. : NUCL. SCI. ENG. 26, 500 (1966).  
 8) LIND D.A. AND DAY R.B. : ANN. PHYS. 12, 485 (1961).           
 9) FREEMAN J.M. AND MONTAGUE J.H. : NUCL. PHYS. 9, 181 (1958).   
10) TOWLE J.H. AND OWENS R.O. : NUCL. PHYS. A100, 257 (1967).     
11) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
12) KUNZ P.D. : UNPUBLISHED.                                      
13) ENSDF(EVALUATED NUCLEAR STRUCTURE DATA FILE)                  
14) ADAMSKI L. ET AL. : ANNA. NUCL. ENER. 7, 397 (1980).          
15) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).                  
16) WOELFER G. ET AL. : Z. PHYS. 194, 75 (1966).                  
17) WILLIAMSON C.F. : PHYS. REV. 122, 1877 (1961).                
18) BASS R. ET AL. : 1965 ANTWERP CONF. 495 (1966).               
19) MAERKER R.E. : ORNL-TM-5203 (1976).