25-Mn- 55

 25-Mn- 55 JAERI,MAPI EVAL-MAR87 K.Shibata,T.Hojuyama             
 NST 26, 955 (1989)   DIST-MAY10                       20100121   
----JENDL-4.0         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.         
****************************************************************  
10-01  Compiled by K.Shibata for JENDL-4.0.                       
*****  Modified parts for JENDL-4.0 ****************************  
(1,451)             Updated                                       
(2,151)             Evaluated by Derrien et al.                   
(3,1),(3,2)         Re-calculated                                 
(3,102)             Background evaluated by Derrien et al.        
(32,151)            Evaluated by Derrien et al.                   
****************************************************************  
The details of the resolved resonance parameters are given below: 
==================================================================
EVALUATION of the RESONANCE PARAMETERS of Mn-55 in the ENERGY     
RANGE 0 to 122 keV- H. Derrien, L.C. Leal, N.M.Larson, D. Wiarda  
K. Guber, and G. Arbanas.                                         
                                                                  
The resonance parameters were obtained from a sequential Bayes    
SAMMY analysis of the most recent experimental neutron            
transmissions and capture cross sections in the resolved energy   
range: Harvey et al. transmissions measured at ORELA in 1980,     
Aerts et al. Capture cross sections measured at GELINA in 2006,   
and Guber et al. Capture cross section measured at ORELA in 2007. 
For the evaluation in the thermal energy range Widder et al.      
(1975) capture cross section, Cote et al. (1964) total cross      
sections, and Rainwater et al. (1964) total cross sections were   
considered. The thermal capture cross sections were normalized at 
the 0.0253 eV value of 13.27 b which is an average of the         
available experimental values, consistent with the recent         
evaluation of Trkov et al.(2007).  The thermal cross sections     
calculated by the resonance parameters are the following:         
                                                Res. Int.         
                   Capture        13.274 b       13.514           
                   Total          15.390 b         -              
                   Scattering      2.116 b         -              
                                                                  
The capture resonance integral is 13.516 b in the energy range    
0.5 eV to 120 keV.                                                
                                                                  
Most of the p-wave resonances are not observed in the experimental
transmission data. For those resonances only the capture area     
could be obtained with good accuracy.  The capture area is        
proportional to   gamman*gammag / gammatot and only the product   
gamman*gammag could be defined.  A solution is to assign to all   
this resonances a constant capture width value equal to an        
estimated averaged value.  In this case the SAMMY fit to the      
capture data is generally poor.  The solution of varying both the 
capture width and the neutron width in the SAMMY fit has been     
chosen is the evaluation.  The resulting capture widths do not    
deviate too much from an average value.  The fit is obviously not 
unique but give a good description of the experimental data. The  
study of the statistical properties of the neutron widths has     
shown that the obtained set of parameters is reasonable.          
                                                                  
Only s-wave and p-wave resonances are given in the evaluation.    
However the study of the statistical properties of the p-wave     
resonance parameters has shown that 25% of them(the very small    
one) could be d-wave resonances. Including these possible d-wave  
resonances in the p-wave resonances has a negligible effect on    
the calculated capture cross section.                             
                                                                  
Two components of the capture cross section are given in the      
evaluation: the first component is calculated by the observed     
resonance parameters; the second component is given as a File 3   
background.  This background stands for the contribution of the   
the contribution of the direct capture,  for the contribution of  
non observed d-wave resonances, and for possible errors in the    
errors in the calculation of the multiple scattering effect by    
SAMMY in the experimental capture cross sections. The estimation  
of the average d-wave contribution below 122 keV was obtained from
SAMMY/URR.  The error on the background file is important (20% to 
30%), contributing to the most part of the uncertainty on the     
average captur cross section                                      
                                                                  
The following Table compares the average capture cross section to 
the experimental values of Lerigoleur , and of Garg and Macklin.  
The present evaluation is systematically lower than Lerigoleur    
(absolute measurement) by 12% on average; part of the discrepancy 
could be due to the inaccuracy of the calculation of the d-wave   
component in the background file.                                 
                                                                  
                                                                  
___________________________________________________________       
Energy Range   Present Results   Lerigoleur    Garg-Macklin       
   keV              mb               mb            Mb             
___________________________________________________________       
 15 - 20      47.98+/-2.05      57.05+/-4.56      48.6            
 20 - 30      35.79+/-1.79      40.97+/-3.28      44.6            
 30 - 40      25.24+/-1.20      27.43+/-2.19      44.7            
 40 - 50      25.24+/-1.20      19.58+/-1.57      28.2            
 50 - 60      20.40+/-1.20      20.41+/-1.63      26.0            
 60 - 80      16.69+/-1.30      20.19+/-1.61      21.5            
 80 -100      15.00+/-1.10      17.65+/-1.41      16.3            
100 -120      11.63+/-1.10      12.65+/-1.41      14.3            
___________________________________________________________       
                                                                  
Resonance parameter covariance was generated in the resolved      
energy region (1.0-5 eV to 125 keV) with the computer code SAMMY  
at ORNL. Experimental data and uncertainties were used to generate
covariance data. SAMMY covariance information was converted in    
the ENDF FILE32 representation. The covariance information was    
processed with the PUFF-IV code.                                  
                                                                  
The details of the evaluation are in progress of publication in   
an ORNL/TM report.                                                
                                                                  
 References:                                                      
                                                                  
 HA 90 Harvey, private communication, 2007                        
 AE 06, private communication 2006                                
 GU 07 Guber, to be published, 2007                               
 WI 75, Wilder, R_EIR-217, 1975                                   
 CO 64, Cote, PR/B, 134, 1047, 1964                               
 RA 64, Rainwater, RSI, 35, 263, 1964                             
 TR 07, private communication 2007                                
 LE 76, Lerigoleur CEA-R-4888, 1976                               
 GA 78, Garg-Macklin, PR/C, 18, 2079, 1978                        
                                                                  
==================================================================
                                                                  
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            -                           
                                                                  
        *****  JENDL-4.0  ****************************************
        The resolved resonance parameters were taken from the work
        done by Derrien et al.  See above.                        
        The unresolved resonance parameters were obtained so as to
        reproduce the total and capture cross sections in the     
        energy region from 125 keV to 1 MeV.  The unresolved      
        parameters should be used only for self-shielding         
        calculations.                                             
        **********************************************************
                                                                  
mf=3          Neutron cross sections                              
  mt=1      Total                                                 
        Below 100 keV   : No background                           
        Above 100 keV   : Based on the experimental data /3,4,5/. 
        *****  JENDL-4.0  ****************************************
        Below 125 keV   : Background due to capture               
        Above 125 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/. 
        *****  JENDL-4.0  ****************************************
        Below 125 keV : Background evaluated by Derrien et al.    
        Above 125 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/                           
       ******  JENDL-4.0 *************************************    
       Evalauted by Derrien et al.                                
       *******************************************************    
                                                                  
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).