8-O - 16

  8-O - 16 JNDC       EVAL-DEC83 Y.KANDA(KYU) T.MURATA(NAIG)+     
 JAERI-M 90-012       DIST-MAY10                       20090629   
----JENDL-4.0         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. 
08-07  Total and elastics scattering cross sections were modified 
       below 3 MeV.  The elastic angular distributions were       
       replaced with new R-matrix calculations between 100 keV and
       3 MeV.                                                     
09-04  The (n,a) cross sections was modified.                     
09-06  The interpolation of MF/MT=12/102 was changed to 2.        
*****  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)                      
******************************************************************
*****  modified parts for JENDL Fusion File  96/1/26 *************
(3,102)         Calculated by A. Mengoni (enea)                   
(3,2),(3,3)     Recalculated                                      
******************************************************************
2002-1 Compiled by K.Shibata (jaeri) for JENDL-3.3.               
*****  modified parts for JENDL-3.3  2001/5/23 *******************
(1,451)         Modified.                                         
(3,1),(3,2)     Recalculated                                      
(3,16)          Corrected                                         
                The JENDL-3.2 data were ten times larger than the 
                measurement /2/ by mistake.                       
(3,3)           Deleted                                           
(3,251)         Deleted                                           
(4,2)           Transformation matrices were deleted.             
(5,22),(5,28)   Distributions at threshold were modified.         
                Interpolation was changed to 22.                  
(12,51-107)     Calculated.                                       
(13,3)          Deleted.                                          
(14,51-107)     Prepared.                                         
(15,3)          Deleted.                                          
(15,51-107)     Calculated.                                       
(33,1-107)      Taken from JENDL-3.2 covariance file except for   
                mt=16.  The covariance for mt=16 was revised on   
                the basis of experimental data.                   
(34,2)          Taken from JENDL-3.2 covariance file.             
******************************************************************
2009-04 Compiled by K.Shibata (jaea) for JENDL-4                  
*****  modifications for JENDL-4  2008/07/02 *********************
(1,451)         Modified                                          
(3,2)           R-matrix calculations below 3 MeV                 
(3,1)           Re-calculated from partial cross sections         
(4,2)           R-matrix calculations between 100 keV and 3 MeV   
(3,107)         The data were replaced with those of ENDF/B-VII.0 
                below 6.5 MeV.                                    
******************************************************************
                                                                  
mf=1          General information                                 
  mt=451   Descriptive data                                       
                                                                  
mf=2          Resonance parameters                                
  mt=151   Scattering radius only.                                
                                                                  
mf=3          Cross sections                                      
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total           3.9624E+00                                   
     Elastic         3.9646E+00                                   
     n,gamma         1.8988E-04           6.7337E-04              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
  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/.                                     
         *********************************************************
         For JENDL-4, data were modified below 3 MeV.  See above. 
         *********************************************************
  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.                                 
         *********************************************************
         For JENDL-4, data were modified below 3 MeV.  See above. 
         *********************************************************
  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 10 MeV.                       
           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.                
         Between 1 eV and 1 MeV, model calculations (direct       
         capture and resonance) were performed by A. Mengoni      
         (enea)/28/.                                              
         Above 1 MeV, a value of 0.1 mb was assumed by            
         considering inverse reaction data.                       
  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/.                 
         For JENDL-4, the measured (n,a) cross sections, which    
         were coverted from the inverse-reaction data/18,21,32/,  
         were compared with the existing libraries.  As a result, 
         it was found that the ENDF/B-VII.0 data reproduce the    
         experimental data fairly well below 6.5 MeV.  Therefore, 
         we decided to replace the (n,a) data with those of       
         ENDF/B-VII.0 below 6.5 MeV.  Above 6.5 MeV, the cross    
         sections remain unchanged from JENDL-3.3.                
                                                                  
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.                      
         *********************************************************
         For JENDL-4, data were modified between 100 keV and 3    
         MeV.  See above.                                         
         *********************************************************
  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=22,28                                                        
         Calcualted by GNASH /27/.                                
  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=22,51-55,59,61,63,66-68,103,107                              
         Calculated with GNASH/27/.                               
  mt=102                                                          
         Calculated with CASTHY/29/.                              
         Below 280 keV, based on the data measured by Igashira    
         et al./30/                                               
                                                                  
mf=14         Photon angular distributions                        
  mt=22,51-55,59,61,63,66-68,102,103,107                          
         Isotropic                                                
                                                                  
mf=15         Photon energy distributions                         
  mt=22,103,107                                                   
         Calculated with GNASH/27/.                               
  mt=102                                                          
         Calculated with CASTHY/29/.                              
                                                                  
mf=33         Covariances of cross sections (ref. 31)             
  mt=1                                                            
         Based on experimental data.  A chi-value was 6.53.       
  mt=2                                                            
         Constructed from mt=1, 16, 22, 28, 51-91, 102, 103, 104, 
         and 107.                                                 
  mt=4                                                            
         Constructed from mt=51-91.                               
  mt=16                                                           
         Based on experimental data.                              
  mt=22                                                           
         Based on systematics.                                    
  mt=28                                                           
         Based on systematics.                                    
  mt=51-91                                                        
         The covariances were estimated by using kalman system.   
         A chi-value was 2.45.                                    
         For mt=52,53, based on experimental data between 7 and   
         11 MeV.                                                  
  mt=102                                                          
         Based on experimental data.                              
  mt=103                                                          
         Based on experimental data.                              
  mt=104                                                          
         Based on experimental data.                              
  mt=107                                                          
         Based on experimental data.                              
                                                                  
mf=34        Covariances of angular distributions                 
  mt=2                                                            
         Based on experimental data and model calculations.       
                                                                  
                                                                  
References                                                        
1) Cierjacks,S. et al.: Nucl. Instr. Meth., 169, 185 (1980).      
2) Brill,O.D. et al.: Soviet Phys. Doklady, 6, 24 (1961).         
3) Nordborg,C. et al.: Nucl. Sci. Eng., 66, 75 (1978).            
4) Lundberg,B. et al.: Phys. Scr. 2, 273 (1970).                  
5) Bauer,R.W. et al.: Nucl. Phys., 47, 241 (1963).                
6) McDonald,W.J. et al.: Nucl. Phys., 75, 353 (1966).             
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, 1229 (1962).            
13)Seeman,K.W. et al.: Bull. Am. Phys. Soc., 6, 237 (1961).       
14)Martin,H.C. et al.: Phys. Rev., 93, 498 (1954).                
15)Foster,Jr. D.G. and Young P.G.: LA-4780 (1972).                
16)Davis,E.A. et al.: Nucl. Phys., 48, 169 (1963).                
17)Sick,I. et al.: Helv. Phys. Acta, 41, 573 (1968).              
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, 283 (1970).           
20)Oorphan,V.J. et al.: Nucl. Sci. Eng., 42, 352 (1970).          
21)Bair,J.K. and Haas,F.X. : Phys. Rev., C7, 1356 (1973).         
22)Lister,D. and Sayres A.: Phys. Rev., 143, 745 (1966).          
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, 393 (1982).     
25)Nakagawa,T: JAERI-M 84-103 (1984).                             
26)Chiba, S. et al.: J. Nucl. Sci. Technol., 22, 771 (1985).      
27)Young,P.G. and Arthur,E.D.: LA-6947 (1977).                    
28)Mengoni A.: Private communication (1995).                      
29)Igarasi S. and Fukahori T.: JAERI 1321 (1991).                 
30)Igashira M. et al.: private communication (1993).              
31)Shibata,K. et al.: JAERI-Research 97-074 (1997).               
32)Harissopulos,S. et al.: Phys. Rev., C72, 062801 (2005).