7-N - 14

  7-N - 14 JNDC       EVAL-JUN89 Y.KANDA(KYU) T.MURATA(NAIG)+     
                      DIST-MAY10                       20100317   
----JENDL-4.0         MATERIAL  725                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
89-06  New evaluation for JENDL-3                                 
        Sub-working group on evaluation of N-14,                  
        working group on nuclear data for fusion,                 
        Japanese Nuclear Data Committee                           
       In charge                                                  
        sig-t      K.Shibata (jaeri)                              
        sig-el     T.Asami (nedac), T.Murata (naig)               
        sig-in     T.Asami, T.Murata                              
        (n,2n),(n,p),(n,t),(n,a)                                  
                   Y.Kanda(kyu)                                   
        (n,na),(n,ap),(n,nd),(n,d)                                
                   T.Asami                                        
        capture    T.Asami                                        
        photon production                                         
                   T.Asami                                        
       Compilation                                                
        Evaluated data were compiled by T.Fukahori (jaeri).       
90-10  mf=5: Spectra were modified at low energies of emitted     
       neutrons by T.Asami(Data Engineering, Co. )                
90-11  Reevaluation was made for the data concerning with the     
       neutron emission double differential cross sections.       
        The inelastic scattering cross sections and the angular   
       distributions for the inelastically emitted neutrons were  
       revised considerably/1/.                                   
94-02  JENDL-3.2                                                  
        mf=3, mt=1,2,4,22,32,52-90,103,105: cross section modified
       and mf=4, mt=54-90: isotoropic angular dist. added         
       by T.Fukahori(jaeri).                                      
        mf=12,mt=102: multiplicity modified                       
       by K.Shibata (jaeri).                                      
                                                                  
       *****  Modified parts for JENDL-3.2  **********************
       (3,1),(3,2)         above 1 MeV                            
       (3,4),(3,22),(3,32) all energy region                      
       (3,52-71)           9-14 MeV                               
       (3,72)              (3,72)+(3,73) of JENDL-3.1             
       (3,73)              (3,74) of JENDL-3.1                    
       (3,74-90)           new pseud-level added                  
       (3,103)             above 7 MeV                            
       (3,105)             above 9 MeV                            
       (4,74-90)           new pseud-level added                  
       (12,102)            energy balance                         
       ***********************************************************
00-10  JENDL-3.3                                                  
       The (n,p) cross sections were taken from JENDL Fusion      
       File 99 /2/.  The file was compiled by K.Shibata (jaeri).  
01-07  JENDL-3.3                                                  
       The (n,p) cross sections were modified between 10-5 eV and 
       40 keV.                                                    
       *****  Modified parts for JENDL-3.3  **********************
       (1,451)             Updated                                
       (3,1),(3,2)         Re-calculated                          
       (3,103)             Taken from JENDL Fusion File 99        
                           Modified between 10-5 eV and 40 keV.   
       (3,251)             Deleted                                
       (4,2)               Transformation matrix deleted          
       (5,16-32)           Modified                               
       ***********************************************************
09-08  JENDL-4.0                                                  
       The data for MF/MT=12/103 were revised by K.Shibata (jaea).
10-01  (n,p) cross section was revised.                           
                                                                  
                                                                  
mf=1          General information                                 
  mt=451   Descriptive data                                       
                                                                  
mf=2          Resonance parameters                                
  mt=151   Scattering radius only.                                
                                                                  
mf=3          Cross sections                                      
           calculated 2200 m/s cross sections and res. integ.     
                  2200 m/s (b)     res. integ. (b)                
       total       11.905               -                         
       elastic     10.000               -                         
       capture     0.075             0.0034                       
                                                                  
  mt=1     sig-t                                                  
         Below 1 eV, a sum of partial cross sections.             
         Above 1 eV, based on the experimental data /3,4,5,6/.    
  mt=2     sig-el                                                 
         Below 1 eV, sig-el = 10 barns.                           
         above 1 eV, the elastic scattering cross section was     
         obtained by subtracting the reaction cross sections from 
         the total cross section.                                 
  mt=4     total inelastic                                        
         Sum of mt=51 to 91.                                      
  mt=16    (n,2n)                                                 
         Based on experimental data/7,8,9/.                       
  mt=22    (n,n alpha)                                            
         Adopted the half of values calculated with the gnash     
         code/10/.                                                
  mt=28    (n,np)                                                 
         Calculated with the gnash code/10/, and normalized       
         to the experimental data/11/.                            
  mt=32    (n,nd)                                                 
         Adopted the half of values calculated with the gnash     
         code/10/.                                                
  mt=51-90  sig-in                                                
         The cross sections were calculated with the statistical  
         model.  The low-energy portion was analyzed with the     
         resonance theory/12/.  For mt=51 to 73, the direct       
         components were calculated with the dwuck code/13/. For  
         74 to 90, pseud-levels were assumed and adjusted to fit  
         to the experimental data/14/.                            
         The optical potential parameters used are the following  
         /15/:                                                    
            V = 50.08-0.01E ,  Ws = 9.0 + 0.62E,  Vso = 5.5  (MeV)
            r = 1.22        ,  rs = 1.45       ,  rso = 1.15 (fm) 
            a = 0.66        ,  b  = 0.13       ,  aso = 0.50 (fm).
         Level scheme                                             
            no.       energy(MeV)    spin-parity                  
            g.s.        0.0             1 +                       
             1.         2.3129          0 +                       
             2.         3.9478          1 +                       
             3.         4.9150          0 -                       
             4.         5.1059          2 -                       
             5.         5.6900          1 -                       
             6.         5.8320          3 -                       
             7.         6.2040          1 +                       
             8.         6.4440          3 +                       
             9.         7.0280          2 +                       
            10.         7.9670          2 -                       
            11.         8.0620          1 -                       
            12.         8.4880          4 -                       
            13.         8.6180          0 +                       
            14.         8.7900          0 -                       
            15.         8.91            3 -                       
            16.         8.96            5 +                       
            17.         9.13            3 +                       
            18.         9.17            2 +                       
            19.         9.51            2 -                       
            20.        10.23            1 -                       
            21.        10.81            5 +                       
            22.        11.05            3 +                       
                       11.07            1 +   (summing up)        
            23.        11.24            3 -                       
            24.        11.5                   (pseud-level)       
            25.        11.75                  (pseud-level)       
            26.        12.0                   (pseud-level)       
            27.        12.25                  (pseud-level)       
            28.        12.5                   (pseud-level)       
            29.        13.0                   (pseud-level)       
            30.        13.5                   (pseud-level)       
            31.        14.0                   (pseud-level)       
            32.        14.5                   (pseud-level)       
            33.        15.0                   (pseud-level)       
            34.        15.5                   (pseud-level)       
            35.        16.0                   (pseud-level)       
            36.        16.5                   (pseud-level)       
            37.        17.0                   (pseud-level)       
            38.        17.5                   (pseud-level)       
            39.        18.0                   (pseud-level)       
            40.        18.5                   (pseud-level)       
  mt=102   Capture                                                
         Calculated with the casthy code/16/.                     
  mt=103   (n,p)                                                  
         Below 7 MeV, based on experimental data/17,18,19,20,21,  
         22/.                                                     
         Above 7 MeV, based on experimental data/23/.             
         For JENDL-3.3, the data were taken from FENDL-1 (BROND-2)
         above 6 MeV.                                             
         The 1/v part was modified so as to reproduce a thermal   
         cross section of 1.93 b mesured by Wagemans et al. /24/  
                                                                  
  mt=104   (n,d)                                                  
         Below 8.5 MeV, based on experimental data/25/.           
         Above 8.5 MeV, calculated with gnash.                    
  mt=105   (n,t)                                                  
         Below 9 MeV, based on experimental data/26/.             
         Above 9 MeV, based on experimental data/27,28/.          
  mt=107   (n,alpha)                                              
         Based on the experimental data/21,22,25,26/.             
  mt=108   (n,2alpha)                                             
         Calculated with gnash and normalized at 14.1 mev to an   
         average value among the experimental data/29,30/.        
  mt=800   (n, alpha0)                                            
         Based on experimental data.                              
  mt=801   (n, alpha1)                                            
         Based on experimental data.                              
  mt=849   (n, alpha) continuum                                   
         Based on experimental data.                              
                                                                  
mf=4          Angular distributions of secondary neutrons         
  mt=2                                                            
         1.e-5 eV to 8 MeV  calculated with the resonance theory. 
         8 MeV to 20 MeV    calculated with casthy.               
  mt=16,22,28,32                                                  
         Assumed to be isotropic in the center of mass system.    
         The distributions were converted to the ones in the      
         laboratory system.                                       
  mt=51-73                                                        
         Calculated with casthy/16/ and dwuck/13/.                
  mt=74-90                                                        
         Assumed to be isotropic in the center of mass system.    
                                                                  
mf=5          Energy distribution for secondary neutrons          
  mt=16,22,28,32                                                  
         Calculated with the gnash code/10/.                      
                                                                  
mf=12         Photon production multiplicities                    
  mt=102,103                                                      
         Calculated with the gnash code.                          
         for mt=102, modified by considering energy balance.      
                                                                  
mf=13         Photon production cross sections                    
  mt=3                                                            
         Calculated with the gnash code/10/.                      
                                                                  
mf=14         Photon angular distributions                        
  mt=3,102,103                                                    
         Isotropic                                                
                                                                  
mf=15         Photon energy distributions                         
  mt=3,102,103                                                    
         Calculated with the gnash code/10/.                      
         For mt=102, modified by using the experimental data/31/  
         at thermal energy.                                       
                                                                  
mf=33         Covariances for neutron cross sections              
  mt=103                                                          
         Below 60 keV, uncertainty of 3% /24/ was assumed.        
                                                                  
                                                                  
References                                                        
 1) Kanda Y. et al.: JAERI-M 91-032 (1991) p.376.                 
 2) Chiba S. et al.: Fusion Eng. Des., 37, 175 (1997).            
 3) Melkonian E.: Phys. Rev., 76, 1750 (1949).                    
 4) Bilpuch E.G. et al.: Bull. Am. Phys. Soc., 4, 42 (1959).      
 5) Bilpuch E.G. et al.: Taken from EXFOR (1962).                 
 6) Heaton, II H.T. et al.: Bull. Am. Phys. Soc., 15, 568 (1970). 
 7) Ferguson J.W. et al.: Phys. Rev., 118, 228 (1960).            
 8) Bormann N. et al.: Nucl. Phys., 63, 438 (1965).               
 9) Ryves T.B. et al.: J. Phys., G4, 1783 (1978).                 
10) Young P.G. and Arthur E.D.: LA-6947 (1977).                   
11) Csikai J. and Nacy S.: Nucl. Phys., A91, 222 (1967).          
12) Murata T.: Proc. Int. Conf. Nuclear Data for Science and      
    Technology, Mito, 1988, p.557, (1988).                        
13) Kunz P.D.: unpublished.                                       
14) Baba M. et al.: Proc. of Int. Conf. on Nucl. Data for Basic   
    and Applied Sci. at Santa Fe, p.223 (1986).                   
15) Templon J.A. et al.: Nucl. Sci. Eng., 91, 451 (1985).         
16) Igarasi S.: J. Nucl. Sci. Technol., 12, 67 (1975).            
17) Batchelor R.: AERE-N/R-370 (1949).                            
18) Coon J.H. et al.: Phys. Rev., 75, 1358 (1949).                
19) Cure P. et al.: J. Phys. Radium., 12, 6 (1951).               
20) Hanna G.C. et al.: Can. J. Phys., 39, 1784 (1961).            
21) Morgan G.L. et al.: Nucl. Sci. Eng., 70, 163 (1979).          
22) Felber H. et al.: Z. Phys., A276, 75 (1976).                  
23) Anderson J.D. et al.: UCRL-50001-66-2, (1966).                
24) Wagemans J. et al.: Phys. Rev., C61, 064601 (2000).           
25) Chase, Jr L.F. et al.: AFSWC-TR-61-15 (1961).                 
26) Gabbard F. et al.: Nucl. Phys., 14, 277 (1959).               
27) Suhaimi A.: Jul-2196, (1988).                                 
28) Dimbylow P.: Phys. in Medicine and Biology, 25, 637 (1980).   
29) Lillie A.B.: Phys. Rev., 87, 726 (1952).                      
30) Schmidt G. et al.: Nucl. Phys., a103, 238 (1967).             
31) Maerker R.E.: ORNL/TM-5203 (1976).