8-O - 16

  8-O - 16 JNDC       EVAL-DEC83 Y.KANDA(KYU) T.MURATA(NAIG)+     
 JAERI-M 90-012       DIST-SEP89 REV2-DEC93                       
----JENDL-3.2         MATERIAL  825                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
83-12  NEW EVALUATION FOR JENDL-3                                 
        SUB-WORKING GROUP ON EVALUATION OF O-16,                  
        WORKING GROUP ON NUCLEAR DATA FOR FUSION,                 
        JAPANESE NUCLEAR DATA COMMITTEE                           
       IN CHARGE                                                  
        SIG-T       Y.NAKAJIMA K.SHIBATA(JAERI)                   
        SIG-EL      T.MURATA(NAIG)                                
        SIG-IN      S.TANAKA(JAERI)                               
        CAPTURE     T.ASAMI(JAERI)                                
        (N,2N),(N,P),(N,D),(N,ALPHA)    Y.KANDA(KYU)              
       COMPILATION                                                
        EVALUATED DATA WERE COMPILED BY K.SHIBATA.                
84-07  DATA OF MF=4 (MT=16,91) WERE REVISED.                      
       COMMENT WAS ALSO MODIFIED.                                 
87-01  DATA OF MF=3 (MT=51-64,67), MF=4 (MT=51-55) AND MF=5(MT=16)
       WERE MODIFIED (S.CHIBA, JAERI). COMMENT WAS ALSO MODIFIED. 
90-10  MF=5 (EXCEPT MT=91), MF=12, MT=102 MODIFIED.               
93-12  CAPTURE AND GAMMA PRODUCTION CROSS SECTIONS WERE MODIFIED. 
*****  MODIFIED PARTS FOR JENDL-3.2 ******************************
(3,102)         REEVALUATED BY K. SHIBATA.                        
(3,2),(3,3)     RECALCULATED                                      
(12,102)        MODIFIED DUE TO ENERGY CONSERVATION               
(12,51;57;62)   510 KEV GAMMAS INCORPORATED                       
(13,3)          REEVALUATED BY T. ASAMI (DE)                      
******************************************************************
                                                                  
MF=1          GENERAL INFORMATION                                 
  MT=451   DESCRIPTIVE DATA                                       
                                                                  
MF=2          RESONANCE PARAMETERS                                
  MT=151   SCATTERING RADIUS ONLY.                                
                                                                  
MF=3          CROSS SECTIONS                                      
           CALCULATED 2200M/S CROSS SECTIONS AND RES. INTEGRALS   
                 2200M/S (B)       RES. INTEG. (B)                
        TOTAL     3.780                 -                         
        ELASTIC   3.780                 -                         
        CAPTURE   1.9E-4             6.33E-4                      
                                                                  
  MT=1     SIG-T                                                  
         BELOW 3 MEV, THE TOTAL CROSS SECTION WAS CALCULATED      
         WITH THE R-MATRIX THEORY.                                
         ABOVE 3 MEV, BASED ON THE EXPERIMENTAL DATA OF           
         CIERJACKS ET AL./1/.                                     
  MT=2     SIG-EL                                                 
         BELOW 3 MEV, CALCULATED WITH THE R-MATRIX THEORY.        
         ABOVE 3 MEV, THE ELASTIC SCATTERING CROSS SECTION WAS    
         OBTAINED BY SUBTRACTING THE REACTION CROSS SECTIONS FROM 
         THE TOTAL CROSS SECTION.                                 
  MT=3     NON-ELASTIC                                            
         SUM OF MT=4, 16, 102, 103, 104 AND 107.                  
  MT=4     TOTAL INELASTIC                                        
         SUM OF MT=51 TO 91.                                      
  MT=16    (N,2N)                                                 
         BASED ON EXPERIMENTAL DATA/2/.                           
  MT=51-79,91  SIG-IN                                             
         SHAPE OF THE EXCITATION FUNCTIONS WAS CALCULATED WITH    
         THE STATISTICAL MODEL.                                   
         THE OPTICAL POTENTIAL PARAMETERS ARE THE FOLLOWING:      
            V = 48.25-0.053E,  WS = 3.0 + 0.25E,  VSO = 5.5  (MEV)
            R = 1.255       ,  RS = 1.352      ,  RSO = 1.15 (FM) 
            A = 0.536       ,  B  = 0.205      ,  ASO = 0.50 (FM).
         LEVEL SCHEME                                             
            NO        ENERGY(MEV)    SPIN-PARITY                  
           G.S.          0.0            0+                        
             1           6.0490         0+                        
             2           6.1300         3-                        
             3           6.9170         2+                        
             4           7.1169         1-                        
             5           8.8720         2-                        
             6           9.6300         1-                        
             7           9.8470         2+                        
             8           10.360         4+                        
             9           10.960         0-                        
            10           11.080         3+                        
            11           11.100         4+                        
            12           11.520         2+                        
            13           11.600         3-                        
            14           12.050         0+                        
            15           12.440         1-                        
            16           12.530         2-                        
            17           12.800         0-                        
            18           12.970         2-                        
            19           13.020         2+                        
            20           13.090         1-                        
            21           13.120         3-                        
            22           13.260         3-                        
            23           13.660         1+                        
            24           13.870         4+                        
            25           13.980         2-                        
            26           14.030         0+                        
            27           14.100         3-                        
            28           14.300         4+                        
            29           14.400         5+                        
           CONTINUUM LEVELS WERE ASSUMED ABOVE 14.4 MEV.          
           CONSTANT TEMPERATURE OF 3.4 MEV WAS USED.              
           FOR THE INELASTIC SCATTERING TO THE SECOND AND THIRD   
           LEVELS, THE (N,N')GAMMA DATA OF NORDBORG ET AL./3/ AND 
           LUNDBERG ET AL./4/ BELOW 10MEV.                        
           FOR MT=51 TO 55, THE 14 MEV CROSS SECTIONS WERE        
           NORMALIZED TO THE EXPERIMENTAL DATA/5/-/8/.            
           CROSS SECTIONS FOR MT=56-64 AND 67 WERE NORMALIZED TO  
           REPRODUCE THE DDX DATA AT 14 MEV/8/,/9/.               
  MT=102   CAPTURE                                                
         1/V CURVE NORMALIZED TO THE RECOMMENDED VALUE IN THE     
         4TH EDITION OF BNL-325 /10/ AT 0.0253 EV.                
         ABOVE 100 EV, P-WAVE CAPTURE WAS CONSIDERED./28/         
  MT=103   (N,P)                                                  
         BASED ON EXPERIMENTAL DATA/11/-/14/.                     
  MT=104   (N,D)                                                  
         BASED ON THE EVALUATION OF FOSTER, JR. AND YOUNG /15/.   
  MT=107   (N,ALPHA)                                              
         BASED ON EXPERIMENTAL DATA/3/,/16/-/21/.                 
  MT=251   MU-BAR                                                 
         CALCULATED FROM ANGULAR DISTRIBUTIONS IN MF=4.           
                                                                  
MF=4          ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS         
  MT=2                                                            
         10E-5 EV TO 3 MEV  R-MATRIX CALCULATION                  
         3 MEV TO 5 MEV     BASED ON THE EXPERIMENTAL DATA OF     
                            LISTER AND SAYRES /22/.               
         5 MEV TO 9 MEV     MULTI-LEVEL FORMULA/23/.              
         9 MEV TO 15 MEV    BASED ON THE EXPERIMENTAL DATA OF     
                            GLENDINNING ET AL./24/                
         15 MEV TO 20 MEV   CALCULATED WITH THE SPHERICAL         
                            OPTICAL MODEL.  THE POTENTIAL         
                            PARAMETERS ARE THE SAME AS THOSE      
                            GIVEN IN SIG-IN.                      
  MT=16                                                           
         ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.        
  MT=51-79                                                        
         CALCULATED WITH THE STATISTICAL MODEL.                   
         FOR MT=51, 52 AND 55, EXPERIMENTAL DATA/8/ AT 14.2 MEV.  
         FOR MT=53 AND 54 ENDF/B-IV WAS ADOPTED.                  
  MT=91                                                           
         ISOTROPIC DISTRIBUTIONS IN THE CENTER OF MASS SYSTEM     
         WERE TRANSFORMED INTO THE ONES IN THE LABORATORY SYSTEM. 
         THE FORMULA IS GIVEN IN REF./25/.                        
                                                                  
MF=5          ENERGY DISTRIBUTION FOR SECONDARY NEUTRONS          
  MT=16                                                           
         EVAPORATION SPECTRUM WAS ASSUMED.  CONSTANT TEMPERATURE  
         WAS DEDUCED FROM THE EXPERIMENTAL DATA OF CHIBA ET AL.   
         /26/ FOR LI-7 ACCORDING TO THE SQRT(E/A) LAW.            
  MT=91                                                           
         EVAPORATION SPECTRUM WAS ASSUMED.  CONSTANT TEMPERATURE  
         OF 3.4 MEV WAS DETERMINED FROM THE STAIR CASE PLOTTING.  
                                                                  
MF=12         PHOTON PRODUCTION MULTIPLICITIES                    
  MT=52-68,102,103,107                                            
         CALCULATED WITH GNASH/27/.                               
                                                                  
MF=13         PHOTON PRODUCTION CROSS SECTIONS                    
  MT=3                                                            
         CALCULATED WITH GNASH/27/.                               
                                                                  
MF=14         PHOTON ANGULAR DISTRIBUTIONS                        
  MT=3,52-68,102,103,107                                          
         ISOTROPIC                                                
                                                                  
MF=15         PHOTON ENERGY DISTRIBUTIONS                         
  MT=3,102,103,107                                                
         CALCULATED WITH GNASH/27/.                               
                                                                  
REFERENCES                                                        
1) CIERJACKS,S. ET AL.: NUCL. INSTR. METH. 169 (1980) 185.        
2) BRILL,O.D. ET AL.: SOVIET PHYS. DOKLADY 6 (1961) 24.           
3) NORDBORG,C. ET AL.: NUCL. SCI. ENG. 66 (1978) 75.              
4) LUNDBERG,B. ET AL.: PHYS. SCR. 2 (1970) 273.                   
5) BAUER,R.W. ET AL.: NUCL. PHYS. 47(1963) 241.                   
6) MCDONALD,W.J. ET AL.: NUCL. PHYS. 75(1966)353.                 
7) MEIER,D. ET AL.: EXFOR 20907,007 (1969).                       
8) BABA,M. ET AL.: "NUCL. DATA FOR BASIC AND APPLIED SCIENCE",    
   SANTA FE, 1985, P223.                                          
9) TAKAHASHI,A. ET AL.: OKTAVIAN REPORT.                          
10)MUGHABGHAB,S.F. ET AL.: NEUTRON CROSS SECTIONS VOL.1,          
   ACADEMIC PRESS, 1981.                                          
11)BORMANN,N. ET AL.: FIRST IAEA CONF. NUCLEAR DATA FOR REACTORS, 
   1 (1967) 225.                                                  
12)DE JUREN,J.A. ET AL.: PHYS. REV. 127 (1962) 1229.              
13)SEEMAN,K.W. ET AL.: BULL. AM. PHYS. SOC. 6 (1961) 237.         
14)MARTINE,H.C. ET AL.: PHYS. REV. 93 (1954) 498.                 
15)FOSTER,JR. D.G. AND YOUNG P.G.: LA-4780 (1972).                
16)DAVIS,E.A. ET AL.: NUCL. PHYS. 48 (1963) 169.                  
17)SICK,I. ET AL.: HELV. PHYS. ACTA 41 (1968) 573.                
18)DIVATITA,A.S. ET AL.: FIRST IAEA CONF. NUCLEAR DATA FOR        
   REACTORS, 1 (1967) 233.                                        
19)DICKENS,J.K. ET AL: NUCL. SCI. ENG. 40 (1970) 283.             
20)ORPHAN,V.J. ET AL.: NUCL. SCI. ENG. 42 (1970) 352.             
21)BAIR,J.K. ET AL.: PHYS. REV. C7 (1972) 1356.                   
22)LISTER,D. AND SAYRES A.: PHYS. REV. 143 (1966) 745.            
23)MURATA,T.: PROC. INT. CONF. NUCLEAR DATA FOR SCIENCE AND       
   TECHNOLOGY, MITO, 1988, P.557, (1988).                         
24)GLENDINNING, S.G. ET AL.: NUCL. SCI. ENG. 82(1982) 393.        
25)NAKAGAWA,T: JAERI-M 84-103 (1984).                             
26)CHIBA, S. ET AL.: J. NUCL. SCI. TECH., 22(1985)771.            
27)YOUNG,P.G. AND ARTHUR,E.D.: LA-6947 (1977).                    
28)IGASHIRA,M. ET AL.: NUCL. PHYS. A536 (1992) 285.