40-Zr- 91

 40-Zr- 91 JNDC       EVAL-AUG89 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAY10                       20100216   
----JENDL-4.0         MATERIAL 4028                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/        
89-08 Modification for JENDL-3 was made/2/.                       
90-10 mf=5: Spectra at threshold energies were modified.          
93-09 JENDL-3.2.                                                  
      Compiled by T.Nakagawa (ndc/jaeri)                          
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      Almost all cross section data except (3,1), (3,102),        
      (3,103) and (3,107):                                        
          (3,4), (3,51-91), (3,16), (3,17), (3,22), (3,28),       
          (3,32), (3,104), (3,105), (3,106)                       
      (4,16-91)                                                   
      (5,16-91)                                                   
             These data were taken from JENDL fusion file.        
     ***********************************************************  
01-08 Compiled by K.Shibata (jaeri/ndc) for JENDL-3.3.            
     *****   modified parts for JENDL-3.3   ********************  
      (1,451)       Updated.                                      
      (3,1)         Revised.                                      
      (3,2)         Re-calculated.                                
      (3,102)       Revised.                                      
      (3,251)       Deleted.                                      
      (3,203-207)   Calcualted.                                   
      (4,2)         Transformation matrix deleted.                
      (4,16-91)     Deleted.                                      
      (5,16-91)     Deleted.                                      
      (6,16-207)    Taken from JENDL fusion file.                 
      (12,16-107)   Added.                                        
      (14,16-107)   Added.                                        
      (15,16-107)   Added.                                        
     ***********************************************************  
09-07 Compiled by A.Ichihara (jaea/ndc) for JENDL-4.0.            
     *****   modified parts for JENDL-4.0   ********************  
      (1,451)       Updated.                                      
      (2,151)       Resolved resonance parameters.                
                                           (T.Murata, K.Shibata)  
      (4,2)         Re-calculated for energies larger than 6 MeV. 
      (6,204)       Re-calculated with the POD code/3,4/.         
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL fusion file /5/  (as of Sep. 1993)                    
            Evaluated and comiled by S. Chiba (ndc/jaeri)         
                                                                  
      Data were taken from JENDL-3.1 except for the following:    
      -  The discrete and continuum inelastic scattering cross    
         sections were calculated with casthy2y and dwucky in     
         sincros-ii system/6/ including contributions from        
         direct reactions.                                        
      -  Angular distributions of discrete inelastics were also   
         calculated with casthy2y and dwucky.                     
      -  Threshold reaction cross sections (mt=16, 17, 22, 28, 32,
         104, 105 and 106) were replaced with those calculated by 
         egnash2 in the sincros-ii.                               
      -  Energy distributions of secondary neutrons were replaced 
         by those calculated by egnash2.  The ddx's of the conti- 
         nuum neutrons were calculated by Kumabe's systematics/7/ 
         using f15tob /5/.  The precompound/compound ratio was    
         calculated by the sincros- ii code system.               
      -  Optical-model, level density and other parameters used in
         the sincros-ii calculation are described in ref./6/.     
         Level schemes were determined on the basis of ENSDF/8/.  
     -------------------------------------------------------------
                                                                  
                                                                  
mf = 1  General information                                       
  mt=451 Comments and dictionary                                  
                                                                  
mf = 2 Resonance parameters                                       
  mt=151 Resolved and unresolved resoannce parameters             
    Resolved resonance region: below 26.0 keV                     
      The resolved resonance parameters were taken from the work  
      of Tagliente et al./9/  A negative resonance was inserted   
      so as to be consistent with the lower-limit of the capture  
      cross section measured by Nakamura et al./10/               
                                                                  
  Unresolved resonance region : 26.0 keV - 100 keV                
    The neutron strength functions, S0, S1 and S2 were calculated 
    with optical model code casthy/11/.  The observed level       
    spacing was determined to reproduce the capture cross section 
    calculated with casthy.  The effective scattering radius was  
    obtained from fitting to the calculated total cross section   
    at 100 keV.                                                   
                                                                  
  Typical values of the parameters at 70 keV:                     
    S0 = 0.420e-4, S1 = 5.700e-4, S2 = 0.360e-4, Gg = 0.205 eV    
    Do = 660.4 eV, R  = 6.621 fm.                                 
                                                                  
  calculated 2200-m/s cross sections and res. integrals (barns)   
                     2200 m/s               res. integ.           
      total          12.24                     -                  
      elastic        10.98                     -                  
      capture         1.261                     5.73              
                                                                  
mf = 3  Neutron cross sections                                    
  Below 100 keV, resonance parameters were given.                 
  Above 100 keV, the spherical optical and statistical model      
  calculation was performed with casthy/11/, by taking account of 
  competing reactions, of which cross sections were calculated    
  with pegasus/12/ standing on a preequilibrium and multi-step    
  evaporation model.  The omp's for neutron given in Table 1 were 
  determined by Iijima and Kawai/13/ to reproduce a systematic    
  trend of the total cross section.  The omp's for charged        
  particles are as follows:                                       
     proton   = Perey/14/                                         
     alpha    = Huizenga and Igo/15/                              
     deuteron = Lohr and Haeberli/16/                             
     helium-3 and triton = Becchetti and Greenlees/17/            
  Parameters for the composite level density formula of Gilbert   
  and Cameron/18/ were evaluated by Iijima et al./19/.  More      
  extensive determination and modification were made in the       
  present work.  Table 2 shows the level density parameters used  
  in the present calculation.  Energy dependence of spin cut-off  
  parameter in the energy range below E-joint is due to Gruppelaar
  /20/.                                                           
                                                                  
     For JENDL-3.2, data of neutron emitting reactions were       
  adopted from JENDL fusion file.  The calculation was made with  
  sincros-ii system/6/ by adopting Walter-Guss omp modified by    
  Yamamuro/6/ for neutrons, Lemos omp modified by Arthur and      
  Young/21/ for alpha, the same omp's as the pegasus calculation  
  for other charged particles and standard level density parame-  
  ters of sincros-ii system.                                      
                                                                  
  mt = 1  Total                                                   
    Spherical optical model calculation was adopted.              
    For JENDL-3.3, the cross sections was modified so as to       
    reproduce measured elemental data.                            
                                                                  
  mt = 2  Elastic scattering                                      
    Calculated as (total - sum of partial cross sections).        
                                                                  
  mt = 4, 51 - 91  Inelastic scattering                           
    Taken from JENDL fusion file.  The level scheme was taken from
    ref./8/  contributions of the direct process was calculated   
    for the levels marked with '*'.                               
                                                                  
           no.      energy(MeV)    spin-parity (direct process)   
           gr.       0.0            5/2 +                         
            1        1.2048         1/2 +                         
            2        1.4663         5/2 +          *              
            3        1.8821         7/2 +          *              
            4        2.0422         3/2 +          *              
            5        2.1313         9/2 +          *              
            6        2.1700        11/2 -                         
            7        2.1899         5/2 +                         
            8        2.2007         7/2 +                         
            9        2.2597        13/2 -                         
           10        2.2876        15/2 -                         
           11        2.3201        11/2 -          *              
           12        2.3558         1/2 -          *              
           13        2.3669         7/2 -          *              
           14        2.3949         9/2 -          *              
      Levels above 2.395 MeV were assumed to be overlapping.      
                                                                  
  mt = 16  (n,2n) cross section                                   
  mt = 17  (n,3n) cross section                                   
  mt = 22  (n,n'a) cross section                                  
  mt = 28  (n,n'p) cross section                                  
  mt = 32  (n,n'd) cross section                                  
  mt =104  (n,d) cross section                                    
  mt =105  (n,t) cross section                                    
  mt =106  (n,he3) cross section                                  
    Data were adopted from JENDL fusion file.                     
                                                                  
  mt = 102  Capture                                               
    Spherical optical and statistical model calculation with      
    casthy/11/ was adopted.  Direct and semi-direct capture cross 
    sections were estimated according to the procedure of Benzi   
    and Reffo/22/ and normalized to 1 milli-barn at 14 MeV.       
                                                                  
    The gamma-ray strength function (3.199e-04) was adjusted to   
    reproduce the capture cross section of 25 milli-barns at 100  
    keV measured by Musgrove et al./23/                           
                                                                  
    For JENDL-3.3, the cross section was modified so as to        
    reproduce elemental data measured by Stavisskij et al./24/ and
    Poenitz/25/.                                                  
                                                                  
  mt =103  (n,p) cross section                                    
  mt =107  (n,alpha) cross section                                
    These reaction cross sections were calculated with the        
    preequilibrium and multi-step evaporation model code          
    pegasus/12/.                                                  
                                                                  
    The Kalbach's constant k (=269.1) was estimated by the formula
    derived from Kikuchi-Kawai's formalism/26/ and level density  
    parameters.                                                   
                                                                  
    Finally, (n,p) and (n,alpha) cross sections were normalized to
    the following values at 14.5 MeV:                             
      (n,p)         29.00  mb (recommendation by Forrest/27/)     
      (n,alpha)      8.51  mb (systematics of by Forrest/27/)     
                                                                  
  mt=203   Total proton production                                
    Sum of mt=28 and 103.                                         
                                                                  
  mt=204   Total deuteron production                              
    Sum of mt=32 and 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                                                          
    Calculated with casthy/11/.                                   
                                                                  
    In JENDL-4.0, the angular distributions were re-calculated    
    for neutron energies larger than 6 MeV with the Koning        
    and Delaroche local OMP/28/.                                  
                                                                  
  mt = 51-64                                                      
    Taken from JENDL fusion file data which was calculated with   
    casthy and dwuck/29/ (dwucky) in the sincros-ii system.       
                                                                  
mf = 6  Energy-angle distributions of secondary particles         
  mt = 16,17,22,28,32,91                                          
    Based on Kumabe's systematics/7/.                             
  mt = 203,204,205,206,207                                        
    Based on Kalbach's systematics/30/.                           
                                                                  
mf = 12  Photon production multiplicities                         
  mt=16, 22, 28, 91, 103, 107                                     
    Calculated with gnash code /6/.                               
  mt=102                                                          
    Calculated with casthy code /11/.                             
  mt=51-64                                                        
    Transitioin probability arrays                                
                                                                  
mf = 14  Photon angular distributions                             
  mt=16, 22, 28, 51-64, 91, 102, 103, 107                         
    Isotropic.                                                    
                                                                  
mf = 15  Continuous photon energy distributions                   
  mt=16, 22, 28, 91, 103, 107                                     
    Calculated with egnash code /6/.                              
  mt=102                                                          
    Calculated with casthy code /11/.                             
                                                                  
                                                                  
================================================================= 
<> 
================================================================= 
                                                                  
Table 1  Neutron optical potential parameters                     
                                                                  
                depth (MeV)       radius(fm)    diffuseness(fm)   
         ----------------------   ------------  ---------------   
        V  = 46.0-0.25E           r0 = 5.893    a0 = 0.62         
        Ws = 7.0                  rs = 6.393    as = 0.35         
        Vso= 7.0                  rso= 5.893    aso= 0.62         
                                                                  
Table 2  Level density parameters                                 
                                                                  
 nuclide       a(/MeV)   t(MeV)    c(/MeV)   Ex(MeV)   pairing    
 ---------------------------------------------------------------  
 38-Sr- 87     1.030e+01 8.610e-01 1.186e+00 5.938e+00 1.240e+00  
 38-Sr- 88     9.160e+00 7.510e-01 8.288e-02 4.550e+00 2.170e+00  
 38-Sr- 89     9.380e+00 8.200e-01 5.043e-01 4.642e+00 1.240e+00  
 38-Sr- 90     9.940e+00 8.530e-01 3.795e-01 6.252e+00 1.960e+00  
                                                                  
 39-Y - 88     1.109e+01 7.450e-01 3.738e+00 3.570e+00 0.0        
 39-Y - 89     7.900e+00 8.500e-01 3.983e-01 3.440e+00 9.300e-01  
 39-Y - 90     1.027e+01 6.770e-01 1.716e+00 2.209e+00 0.0        
 39-Y - 91     1.050e+01 7.140e-01 8.362e-01 3.521e+00 7.200e-01  
                                                                  
 40-Zr- 89     1.095e+01 8.260e-01 1.379e+00 5.864e+00 1.200e+00  
 40-Zr- 90     9.152e+00 8.222e-01 1.526e-01 5.383e+00 2.130e+00  
 40-Zr- 91     1.036e+01 8.000e-01 7.822e-01 5.057e+00 1.200e+00  
 40-Zr- 92     1.088e+01 8.192e-01 5.122e-01 6.429e+00 1.920e+00  
 ---------------------------------------------------------------  
                                                                  
  Spin cutoff params were calculated as 0.146*sqrt(a)*a**(2/3).   
  in the casthy calculation. Spin cutoff factors at 0 MeV were    
  assumed to be 12.04 for Zr- 91 and 6.937 for Zr- 92.            
                                                                  
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    and Applied Science, Santa Fe., Vol. 2, p.1627 (1985).        
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20) Gruppelaar, H.: ECN-13 (1977).                                
21) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980).              
22) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
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25) Poenitz, W.P.: ANL-83-4, p.239 (1982).                        
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    Reactions", North Holland (1968).                             
27) Forrest, R.A.: AERE-R 12419 (1986).                           
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    (2003).                                                       
29) Kunz, P.D.: Private communication.                            
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