24-Cr- 54

 24-CR- 54 NEDAC      EVAL-MAR87 T.ASAMI(NEDAC)                   
                      DIST-MAR02 REV3-DEC01            20011226   
----JENDL-3.3         MATERIAL 2437                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
87-03  New evaluation was made for JENDL-3.                       
93-09  JENDL-3.2.                                                 
       Compiled by T.Nakagawa (ndc/jaeri)                         
00-03  Reevaluation was made by T.Asami.                          
01-11  Compiled by K.Shibata (ndc/jaeri)                          
                                                                  
     *****   modified parts for JENDL-3.3   ********************  
      (2,151)              revised                                
      (3,2)                re-calculated                          
      (3,102)              revised                                
      (3,104,105,106,111, 203,207)  evaluated newly               
      (3,251)              deleted                                
      (4,2)                transformation matrix deleted          
      (4,16,22,28,91)      deleted                                
      (5,16,22,28,91)      deleted                                
      (6,16,22,28,91)      taken from JENDL fusion file           
      (6,203, 207)         taken from JENDL fusion file           
      (12,16-107)          evaluated newly                        
      (14,16-107)          isotropic distributions                
      (15,16-107)          evaluated newly                        
     ***********************************************************  
                                                                  
                                                                  
                                                                  
mf=1  General information                                         
 mt=451  Descriptive data and dictionary                          
                                                                  
mf=2  Resonance parameters                                        
 mt=151  Resolved resonance parameters                            
   Resolved parameters for rech-moore formula were given in the   
   energy region from 1.0e-5 eV to 750 keV.  Evaluated based on   
   the experimental data of Stieglitz+71/4/, Beer+74/5/,          
   Allen+77/6/, Kenny+77/7/ and Brusegan+86/8/.                   
   Effective scattering radius =  5.3 fm/9/.                      
                                                                  
    calculated 2200 m/s cross sections and resonance integral.    
            2200 m/s cross section(b)     res. integral(b)        
    elastic      2.72                                             
    capture      0.34                        0.18                 
    total        3.06                                             
                                                                  
mf=3  Neutron cross sections                                      
    Below 750 keV, no background cross section was given.         
    Above 750 keV, the total and partial cross sections were given
    pointwise.                                                    
                                                                  
 mt=1 Total                                                       
    Below 750 keV, created from the resonance parameters.         
    Above 750 keV, optical and statistical model calculation was  
    made with the casthy code/10/.                                
     The optical potential parameters used are:                   
      V = 46.78 - 0.262*En,    Vso = 7.0    (MeV)                 
     ws = 4.87 + 0.352*En,      Wv = 0      (MeV)                 
      r = 1.30,  rs = 1.40,  rso = 1.30     (fm)                  
      a = 0.55,   b = 0.40,  aso = 0.48     (fm)                  
       Surface imaginary part is in derivative woods-saxon form.  
                                                                  
 mt=2 Elastic scattering                                          
    Obtained by subtracting the sum of the partial cross sections 
    from the total cross section.                                 
                                                                  
 mt=4, 51-56, 91 Inelastic scattering                             
    Calculated with the casthy code/10/, taking account of the    
    contribution from the competing processes and using the       
    discrete level data/3/ shown below.  The contributions from   
    the direct process for the levels marked with '*' were calcu- 
    lated with the dwuck code/11/. The deformation parameters used
    in the calculation were assumed based on a weak coupling      
    model.                                                        
                                                                  
                                                                  
       mt no.    level energy(mev)                                
         51         0.8349            *                           
         52         1.8237            *                           
         53         2.6195            *                           
         54         2.8294            *                           
         55         3.0739            *                           
         56         3.1600            *                           
         91         3.2000                                        
       levels above 3.20 MeV were assumed to be overlapping.      
                                                                  
 mt=16       (n,2n)                                               
    Calculated with the gnash code/12/.                           
                                                                  
 mt=22       (n,na)                                               
    Calculated with the gnash code/12/ and normalized.            
                                                                  
 mt=28       (n,np)                                               
    Calculated with the gnash code/12/ and normalized.            
                                                                  
 mt=102      Capture                                              
    Below 750 keV, created from the resonance parameters.         
    Above 750 keV, calculated with the casthy code/10/ and        
    normalized at 50 keV so as to reproduce the element data of   
    10 mb, and added the semidirect component calculated with the 
    quick gnash code/19,20/.                                      
                                                                  
 mt=103      (n,p)                                                
    Calculated with the gnash code/12/ and normalized at 14.7 MeV 
    to an average value of the experimental data/13,14,15/.       
                                                                  
 mt=104,105,106    (n,d), (n,t), (n,He-3)                         
    Obtained from from the sincros-ii calculation made with the   
    the egnash code/2/.                                           
                                                                  
 mt=107      (n,a)                                                
    Calculated with the gnash code/12/ and normalized at 14.8 MeV 
    to an average value of the experimental data/14,15,16/.       
                                                                  
 mt=111     (n,2p)                                                
    Obtained from from the sincros-ii calculation made with the   
    the egnash code/2/.                                           
                                                                  
 mt=203      Total proton production                              
    Sum of mt=28 and 103.                                         
                                                                  
 mt=207      Total alpha production                               
    sum of mt=22 and 107.                                         
                                                                  
mf=4  Angular distributions of secondary neutrons                 
 mt=2   Elastic scattering                                        
    Calculated with the casthy code/10/.                          
 mt=51-56   Inelastic scattering                                  
    Calculated with the casthy code and the dwuck code/11/.       
                                                                  
                                                                  
mf=6  Energy-angle distributions of secondary particles           
 mt=16, 22, 28, 91                                                
    Based on modified Kumabe's systematics/1/.                    
 mt=203, 207                                                      
    Based on Kalbach's 1988 systematics/17/.                      
                                                                  
mf=12  Photon production multiplicities and transition probability
         arrays                                                   
 mt=16, 22, 28, 51-56, 91,103, 104, 107                           
       mt=51-16 were given as the transition probability arrays.  
     mt=16, 22, 28, 91, 102, 103, 104, 107 were calculated with   
     the egnash code/2/ and processed by the gamfil2 code/18/.    
     mt=102 was calculated with the casthy code/10/.              
                                                                  
mf=14  photon angular distributions                               
 mt=16, 22, 28, 51-56, 91, 102, 103, 104, 107                     
        assumed to be isotropic distributions                     
                                                                  
mf=15  Continuous photon energy spectra                           
 mt=16, 22, 28, 91, 103, 104, 107                                 
     Calculated with the egnash code/2/.                          
 mt=102                                                           
     Calculated with the casthy code/10/.                         
                                                                  
                                                                  
                                                                  
references                                                        
 1) Chiba S. et al.: JAERI-M 92-027, p.35 (1992).                 
 2) Yamamuro N.: JAERI-M 90-006 (1990).                           
 3) Data taken from ENSDF(Evaluated Nuclear Structure Data File). 
 4) Stiegliz R.G. et al.: Nucl. Phys. A163, 592 (1971).           
 5) Beer H. and Spencer R.P.: KfK-2063 (1974), also Nucl. Phys.   
    A240, 29 (1975).                                              
 6) Allen B.J. and Musgrove A.R.de L.: Neutron Data of Structural 
    Materials for FBR, 1977 Geel meeting, p.447, Pergamon Press   
    (1979).                                                       
 7) Kenny M.J. et al.: AAEC/E-400 (1977).                         
 8) Brusegan A. et al.: 85 Santa Fe Vol.1 p.633 (1986).           
 9) Mughabghab S.F. et al.: "Neutron Cross Sections ", Vol.1,     
    Part A (1981).                                                
10) Igarasi S. and Fukahori T.: JAERI 1321 (1991).                
11) Kunz P.D.: unpublished.                                       
12) Young P.G. and Arthur E.D.: LA-6947 (1977).                   
13) Valkonen M.: Taken from EXFOR (1976).                         
14) Husain L. et al.: J. Inorg. Nucl. Chem. 29, 2665 (1967).      
15) Qaim S.M. et al.: Nucl. Phys. A283, 269 (1977).               
16) Sailer K. et al.: 1977 Kiev Conf. Vol.1, 246 (1977).          
17) Kalbach C. : Phys. Rev. C37, 2350(1988).                      
18) Hida K.: JAERI-M 86-150 (1986) (in Japanese).                 
19) Young p.g. et al. : LA-12343-MS (1992).                       
20) Koning A.J. and Delaroche J.P. : ECN-RX-98-015 (1998).