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 11-Na- 23 NEA        EVAL-APR99 E. Fort et al.                   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 1125                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.1                  **
**                                                              **
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*****************************  JEFF-3.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.0                  **
**                                                              **
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*****************************   JEFF-3.0   ***********************
                                                                  
   DATA TAKEN FROM   :-   JEF-2.2 (DIST-JAN92)                    
   Modifications by E. Fort et al. (see comments below)           
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THIS IS NOT AN EVALUATION IN THE CLASSICAL SENSE. THE ORIGINAL    
JEF-2 EVALUATION (EVAL MARS 87 BY H. YAMAKOSHI WHICH, IN TURN WAS 
ESSENTIALY BASED ON AN "OLD" AMERICAN WORK.) WAS DEMONSTRATED, BY 
THE EXTENSIVE VALIDATION WORK [1] TO BE OF INSUFFICIENT QUALITY,  
IN SUCH A WAY THAT THE RESULT OF THE GENERAL ADJUSTMENT COULD BE  
QUESTIONNED (LINEARITY CONDITION). THEN, IT WAS A NECESSITY TO    
INTRODUCE IN THE ADJUSTEMENT "A PRIORI" DATA OF BETTER QUALITY.   
IN THIS CONTEXT THE BEST CHOICE OF DATA   WAS REPRESENTED BY A    
WORK BY KOPECKY, SHELLEY, MARTEN AND H. WEIGMAN PRESENTED AT THE  
TRIESTE CONFERENCE [II]. IT IS THIS CHOICE WHICH IS PROPOSED TO   
THE JEFF PROJECT.                                                 
THE AUTHORS OF REFERENCE [II] HAVE ANALYSED SIMULTANEOUSLY        
INELASTIC CROSS SECTION DATA OBTAINED AT GEEL [III] AND THE TOTAL 
CROSS SECTION DATA OBTAINED AT ORELA [IV]. THE ANALYSIS HAS BEEN  
PERFORMED USING SAMMY CODE AND R MATRIX FORMALISM IN THE          
REICH-MOORE APPROXIMATION WITH TWO ELASTIC CHANNELS AND TWO       
INELASTIC CHANNELS FOR EVERY GIVEN RESONANCE. THE QUALITY OF THE  
FIT BETWEEN THE INELASTIC THRESHOLD AND 2.0 MEV IS EXCELLENT AND  
WAS OBTAINED BY USING A SINGLE SET OF RESONANCE PARAMETERS.       
THIS WAS A CONVINCING ISSUE ENABLING US TO PROPOSE THIS SET       
OF DATA AS A STARTING VERSION OF AN EVALUATION TO BE COMPLETED IN 
THE FUTURE BY USING THE CLASSICAL RULES.                          
BELOW 450 KEV (INELASTIC THRESHOLD) THE DATA ARE UNCHANGED WITH   
RESPECT TO  JEF2 EVALUATION.                                      
ABOVE 2 MEV, THE JEF2 DATA WERE SCALED BY 0.69 FOR WHAT CONCERNS  
THE INELASTIC CROSS SECTION AND BY 1.32 FOR WHAT CONCERNS THE     
ELASTIC CROSS SECTION. THESE CORRECTIVE FACTORS WERE DETERMINED   
IN ORDER TO MATCH WITH KOPECKY'S DATA AT LOWER ENERGY. THEY ARE   
ALSO CONSISTENT WITH THE VALIDATION INDICATION.                   
THE PROPOSED DATA SET HAS BEEN SUCCESSFULLY TESTED AGAINST        
INTEGRAL DATA. WITH RESPECT TO THE JEF2.2 EVALUATION, THERMAL     
CONSTANTS AND RESONANCE CAPTURE INTEGRAL ARE UNCHANGED AND THE    
CAPTURE CROSS SECTION ON THE FULL ENERGIE RANGE ALSO.             
 [I] E. FORT, W. ASSAL, A,AVERY, PBLAISE, J.C. BOSQ, S. CATHLAU   
     C. DEAN, J.P. FINK, G. RIMPAULT, J. ROWLANDS, P. SMITH,      
     M. SALVARORES, R.SOULE, V.ZAMMIT.                            
           JEF2 VALIDATION. PART 1. GENERAL PURPOSE FILE. JEF/DOC 
                                                                  
 [II]  S. KOPECKY, R. SHELLEY, H. MARTEN AND H. WEIGMAN.          
           CONFERENCE PROCEEDINGS. NUCLEAR DATA FOR  SCIENCE AND  
           TECHNOLOGY. TRIESTE MAY 1987.                          
                                                                  
 [III] H. MARTEN, J. WARTENA AND H. WEIGMAN                       
           IRMM REPORT GE/R/ND/02/94 1994                         
                                                                  
 [IV]  D.C. LARSON                                                
           PRIVATE COMUNICATION TO THE AUTHORS OF REFERENCE [II]  
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*   JEF-2 DATA WERE TAKEN FROM JENDL-3                            
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*  2-FEB-90: MODIFICATIONS TO THIS FILE IN THE ENERGY RANGE       
*            1.0E-5 EV TO 700 KEV IS PROPOSED BY M. MOXON AND     
*            M. SOWERBY, HARWELL, AND WILL BE INCLUDED IN THE     
*            NEAR FUTURE.                                         
********  HYSTORY OF JE2                                          
 87-03  NEW EVALUATION WAS MADE FOR JENDL-3.                      
 89-08  THE DATA FOR MF=15,MT=102 MODIFIED.                       
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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  
   /1/, AND THE DATA FOR SOME LEVELS WERE MODIFIED SO THAT THE    
   CALCULATED TOTAL CROSS SECTIONS 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/2/ IN TRACING THEIR FINE     
  STRUCTURES. ABOVE 14 MEV, BASED ON THE EXPERIMENTAL DATA OF     
  LANGSFORD/3/, STOLER/4/ AND LARSON/5/.                          
 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/.                          
 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/15/.                           
                                                                  
MF=12  PHOTON PRODUCTION MULTIPLICITIES                           
 MT=102                                                           
   CALCULATED WITH THE GNASH CODE/15/ AND MODIFIED AT             
   THERMAL BASED ON THE EXPERIMENTAL DATA OF MAERKER/19/.         
                                                                  
MF=13  PHOTON PRODUCTION CROSS SECTIONS                           
 MT=3                                                             
   CALCULATED WITH THE GNASH CODE/15/.                            
                                                                  
MF=14  PHOTON ANGULAR DISTRIBUTIONS                               
 MT=3, 102                                                        
   ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.              
                                                                  
MF=15  CONTINUOUS PHOTON ENERGY SPECTRA                           
 MT=3                                                             
   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/.         
                                                                  
 REFERENCES                                                       
 1) MUGHABGHAB S.F. AND GARBER D.I. :"NEUTRON CROSS SECTIONS",    
    VOL. 1, PART B (1984).                                        
 2) CIERJACKS S. ET AL. : KFK-1000 (1969).                        
 3) LANGSFORD A. ET AL. : 1965 ANTWERP CONF. 529 (1965).          
 4) STOLER P. ET AL. : 1971 KNOXVILLE CONF. VOL.1, 311 (1971).    
 5) LARSON D.C. ET AL. : ORNL-TM-5614 (1976).                     
 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. : J. NUCL. SCI. TECH. 12, 67 (1975).               
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).                           
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