25-Mn- 55

 25-MN- 55 JAERI,MAPI EVAL-MAR87 K.SHIBATA,T.HOJUYAMA             
 NST 26, 955 (1989)   DIST-MAR02 REV3-FEB02            20020214   
----JENDL-3.3         MATERIAL 2525                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
87-03  Resonance parameters were evaluated by T.Hojuyama (mapi).  
       Multistep Hauser-Feshbach calculations were performed      
       by K.Shibata (jaeri).                                      
88-01  Compiled by K.Shibata (jaeri).                             
88-03  Covariance data added                                      
91-08  Modifed  by B.Yu (ciae) and S.Chiba (ndc/jaeri) as follows 
       for JENDL fusion file/20/.                                 
       Compiled by B.Yu.                                          
     Cross sections were mainly taken from JENDL-3.1.  The (n,n') 
 continumm cross section (mt=91) in the whole energy region and   
 its spectra were taken from the sincros-II /21/ calculation.     
 Several discrete level scattering cross sections (mt=67, 68, 69, 
 70, 71, 72, 73, 74, 75, 76, 77, 78, 79) and their angular distri-
 butions were deleted as well as their covariance matrices        
 because they are included in the new continuum inelastic         
 scattering cross section taken from the sincros-II calculation.  
93-08  JENDL-3.2                                                  
       File-6 of the JENDL fusion file was converted to files 4   
       and 5.                                                     
       Data were compiled by K. Shibata (jaeri).                  
                                                                  
02-01  Compiled by K.Shibata for JENDL-3.3.                       
*****  Modified parts for JENDL-3.3 ****************************  
(1,451)             Updated                                       
(3,3)               Deleted                                       
(3,203-207)         Calcualted                                    
(3,251)             Deleted                                       
(4,2)               Transformation matrix deleted                 
(4,16),(4,22),      Deleted                                       
(4,28),(4,91)       Deleted                                       
(5,16-91)           Deleted                                       
(6,16-91)           Taken from JENDL fusion file                  
(6,203-207)         Taken from JENDL fusion file                  
(12,102)            Modified                                      
(15,102)            Experimental data were inserted for           
                    En = 14-559 keV.                              
(33,2)              Taken from JENDL-3.2 covariance file.         
****************************************************************  
                                                                  
mf=1          General information                                 
  mt=451    Descriptive data and dictionary                       
                                                                  
mf=2          Resonance parameters                                
  mt=151    Resolved resonance parameters for MLBW formula        
     The parameters of the lowest four resonances were taken      
     from the work of Macklin /1/.  Others were taken from the    
     compilation of Mughabghab et al./2/ except that the          
     parameters of two negative resonances were adjusted so as    
     to fit to experimental thermal cross sections.               
     Resonance region : 1.0e-5 eV to 100 keV.                     
     Scattering radius: 5.15 fm                                   
     Calculated 2200-m/s cross sections and res. integrals        
                  2200-m/s         res. integ.                    
      elastic      2.167 b            -                           
      capture     13.413 b          11.77  b                      
      total       15.579 b            -                           
                                                                  
mf=3          Neutron cross sections                              
  mt=1      Total                                                 
        Below 100 keV   : No background                           
        Above 100 keV   : Based on the experimental data /3,4,5/. 
  mt=2      Elastic scattering                                    
        (total) - (nonelastic cross section)                      
  mt=4,51-66,91 Inelastic scattering                              
        Statistical-model calculations were performed using the   
        tng code /6/.  The precompound process was considered     
        above 5 MeV.  The calculated cross section of mt=51       
        was multiplied by a factor of 1.2.                        
        For the levels of mt=51,52,57,61,64,65,67,70,             
        the direct process components were taken into account     
        by the DWBA calculations.                                 
        The optical potential parameters used are as follows/7/   
        (in the units of MeV and fm):                             
   V  = 49.747 - 0.4295*E - 0.0003*E**2  r0 = 1.287  a0  = 0.56   
   Ws = 11.2 - 0.09*E                    rs = 1.345  as  = 0.47   
   Vso= 6.2                              rso= 1.120  aso = 0.47   
        The level scheme was taken from ref./8/.                  
          no.    energy(MeV) spin-parity                          
          g.s.      0.0        5/2 -                              
           1.       0.126      7/2 -                              
           2.       0.984      9/2 -                              
           3.       1.290      1/2 -                              
           4.       1.292     11/2 -                              
           5.       1.293      1/2 -                              
           6.       1.528      3/2 -                              
           7.       1.884      7/2 -                              
           8.       2.015      7/2 -                              
           9.       2.198      7/2 -                              
          10.       2.215      5/2 -                              
          11.       2.252      3/2 -                              
          12.       2.267      5/2 -                              
          13.       2.312     13/2 -                              
          14.       2.366      5/2 -                              
          15.       2.398      9/2 +                              
          16.       2.427      1/2 +                              
          17.       2.563      3/2 -                              
          18.       2.727      7/2 -                              
          19.       2.753      5/2 -                              
          20.       2.822      9/2 -                              
          21.       2.824      5/2 -                              
          22.       2.873      1/2 -                              
          23.       2.954      3/2 -                              
          24.       2.976      3/2 -                              
          25.       2.992      7/2 -                              
          26.       3.006      3/2 -                              
          27.       3.036     11/2 -                              
          28.       3.038      1/2 -                              
          29.       3.040      3/2 +                              
                                                                  
        Levels above 3.046 MeV were assumed to be overlapping.    
        *****  JENDL-3.2 **************************************** 
        The cross sections for mt=67-79 were deleted and that for 
        mt=91 was modified so that the calculated spectra could   
        give a better fit to the measured ddx data.               
        ********************************************************* 
                                                                  
  mt=16,22,28,103,107 (n,2n),(n,n'a),(n,n'p),(n,p) and (n,a)      
      cross sections                                              
        Calculated with tng.                                      
        Global optical-potential parameters were employed         
        for protons and alpha-particles /9,10/.                   
                                                                  
  mt=102    Radiative capture cross section                       
        Below 100 keV : Resonance parameters given (no background)
        Above 100 keV : Based on the experimental data /11/-/15/. 
                                                                  
  mt=104    (n,d) cross section                                   
        The excitation function of the (n,p) cross section        
        calculated with tng was used for the (n,d) reaction by    
        shifting the threshold energy.  The cross sections were   
        normalized to the experimental datum at 14.1 MeV /16/.    
                                                                  
  mt=105    (n,t) cross section                                   
        The excitation function of the (n,p) cross section        
        calculated with tng was used for the (n,t) reaction by    
        shifting the threshold energy.  The cross sections were   
        normalized to the experimental datum at 14.7 MeV /17/.    
                                                                  
  mt=106    (n,He-3) cross section                                
        Based on the experimental data /18,19/.                   
                                                                  
  mt=203  : Total proton production                               
        Sum of mt=28 and 103.                                     
                                                                  
  mt=204  : Total deuteron production                             
        Equal to mt=104.                                          
                                                                  
  mt=205  : Total triton production                               
        Equal to mt=105.                                          
                                                                  
  mt=206  : Total He-3 production                                 
        Equal to mt=106.                                          
                                                                  
  mt=207  : Total alpha production                                
        Sum of mt=22 and 107.                                     
                                                                  
mf=4          Angular distributions of secondary neutrons         
  mt=2,51-66                                                      
        Optical and statistical-model calculations                
        the components of the direct process were added to        
        the levels of mt=51,52,57,61,64,65 by the DWBA            
        calculations.                                             
                                                                  
mf=6          Energy-angle distributions of secondary particles   
  mt=16, 22, 28, 91, 203, 204, 205, 206, 207                      
        Taken from the file-6 of the JENDL fusion file.           
                                                                  
mf=12         Photon production multiplicities                    
  mt=4,16,22,28,102,103,107                                       
        Calculated with tng.                                      
        For mt=102, modified by using gamma-ray intensity data    
        in ENSDF below thermal energy.                            
        ******  JENDL-3.3 ************************************    
        For mt=102, multiplicities were modified between 1.0e-5   
        and 5.59e+5 eV.                                           
        ******************************************************    
                                                                  
mf=14         Photon angular distributions                        
  mt=4,16,22,28,102,103,107                                       
        Assumed to be isotropic.                                  
                                                                  
mf=15         Photon energy distributions                         
  mt=4,16,22,28,102,103,107                                       
        Calculated with tng.                                      
        For mt=102, modified by using gamma-ray intensity data    
        in ENSDF below thermal energy.                            
        ******  JENDL-3.3 ************************************    
        For mt=2, experimental data /22/ were inserted between    
        14 and 559 keV.                                           
        ******************************************************    
                                                                  
mf=32         Covariances of resolved resonance parameters        
  mt=151                                                          
       Based on experimental data. /23/                           
                                                                  
mf=33         Covariance data                                     
  mt=1,2,4,16,22,28,51-66,91,102,103,104,105,106,107              
        Estimated from experimental data.                         
                                                                  
Refernces                                                         
 1) Macklin, R.L.: Nucl. Sci. Eng., 89, 362 (1985).               
 2) Mugabghab, S.F., Divadeenam, M. and Holden, N.E.: "Neutron    
    Cross Sections", Vol. 1, Part A, Academic Press (1981).       
 3) Cierjacks, S., Forti, P., Kopsch, D., Kropp, L., Nebe, J.     
    and Unseld, H.: "High Resolution Total Cross Sections         
    for Na, Cl, K, V, Mn and Co between 0.5 and 30 MeV",          
    KfK-1000 (1968).                                              
 4) Pineo, W.F.E., Divadeenam, M., Bilpuch, E.G., Seth, K.K.      
    and Newson, H.W.: Ann. Phys., 84, 165 (1974).                 
 5) Garg, J.B., Rainwater, J. and Havens, Jr., W.W.:              
    Nucl. Sci. Eng., 65, 76 (1978).                               
 6) Fu, C.Y.: "A Consistent Nuclear Model for Compound and        
    Precompound Reactions with Conservation of Angular            
    Momentum", ORNL/TM-7042 (1980).                               
 7) Fu, C.Y.: Private communication (1985).                       
 8) Zhou Enchen, Huo Junde, Zhou Chunmei, Lu Xiane and            
    Wang Lizheng: Nucl. Data Sheets, 44, 463 (1985).              
 9) Perey, F.G.: Phys. Rev., 131, 745 (1963).                     
10) Huizenga, J.R. and Igo, G.J.: Nucl. Phys., 29, 462 (1962).    
11) Garg, J.B., Macklin, R.L. and Halperin, J.: Phys. Rev.,       
    C18, 2079 (1978).                                             
12) Dovbenko, A.G., Kolesov, V.E., Koroleva, V.P., Tolstikov,     
    V.A.: Atom. Energ., 26, 67 (1969).                            
13) Menlove, H.O., Coop, K.L., Grench, H.A. and Sher, R.:         
    Phys. Rev., 163, 1299 (1967).                                 
14) Schwerer, O., Winkler-Rohatsch, M., Warhanek, H. and          
    Winkler, G.: Nucl. Phys., A264, 105 (1976).                   
15) Budnar, M., Cvelbar, F., Hodgson, E., Hudoklin, A.,           
    Ivkovic, V., Likar, A., Mihailovic, M.V., Martincic, R.,      
    Najzer, M., Perdan, A., Potokar, M. and Ramsak, V.:           
    "Prompt Gamma-ray Spectra and Integarted Cross Sections       
    for the Radiative Capture of 14 MeV Neutrons for 28           
    Natural Targets in the Mass Region from 12 to 208",           
    INDC(YUG)-6 (1979).                                           
16) Colli, L., Iori, I., Micheletti, S. and Pignanelli, M.:       
    Nuovo. Cim., 21, 966 (1962).                                  
17) Sudar, S. and Csikai, J.: Nucl. Phys., A319, 157 (1979).      
18) Diksic, M., Strohal, P. and Slaus, I.: J. Inorg. Nucl.        
    Chem., 36, 477 (1974).                                        
19) Wu, C.H., Woelfle, R. and Qaim, S.M.: Nucl. Phys., A329,      
    63 (1979).                                                    
20) Chiba, S et al.: JAERI-M 92-027, p. 35 (1992)                 
21) Yamamuro, N.: JAERI-M 90-006 (1990)                           
22) Igashira, M.: Private communication (2000).                   
23) Shibata, K. et al.: JAERI-Research 98-045 (1998).