40-Zr- 96

 40-ZR- 96 JNDC       EVAL-AUG89 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV4-AUG01            20010810   
----JENDL-3.3         MATERIAL 4043                               
-----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   ********************  
      (3,2), (3,4), (3,16), (3,17), (3,51-91)                     
      (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.                                        
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL fusion file /3/  (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/4/ including contributions from        
         direct reactions.                                        
      -  Angular distributions of discrete inelastics were also   
         calculated with casthy2y and dwucky.                     
      -  The (n,2n) and (n,3n) reaction cross sections (mt=16, 17)
         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        
         continuum neutrons were calculated by Kumabe's systema-  
         tics /5/ using f15tob /3/.  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./4/.     
         Level schemes were determined on the basis of ENSDF/6/.  
     -------------------------------------------------------------
                                                                  
                                                                  
mf = 1  General information                                       
  mt=451 Comments and dictionary                                  
                                                                  
mf = 2  Resonance parameters                                      
  mt=151 Resolved and unresolved resonance parameters             
  Resolved resonance region (MLBW formula) : below 100 keV        
    Resonance parameters were taken from JENDL-2.                 
       Resonance energies and neutron widths were based on the    
    measured values by Coceva et al./7/ below 41.5 keV and those  
    by Musgrove et al./8/ above 41.5 keV.  The neutron widths of  
    Musgrove et al. were multiplied by a factor of 1.79 so as to  
    adjust to the data of Coceva et al.  The radiation widths were
    adopted from Brusegan et al./9/  The parameters of the 301-eV 
    level were taken from Salah et al./10/  Parameter of a nega-  
    tive resonance was based on the recommended parameters given  
    in ref./11/, and the radiation width was modified so as to    
    reproduce the capture cross section of 0.0229+-0.0010 barns at
    0.0253 eV/11/.  Average radiation widths of 0.068+-0.010 eV   
    and 0.170+-0.130 eV were adopted to s-wave and p-wave         
    resonances, respectively.                                     
                                                                  
  No unresolved resonance region                                  
                                                                  
  calculated 2200-m/s cross sections and res. integrals (barns)   
                     2200 m/s               res. integ.           
      total           6.154                    -                  
      elastic         6.131                    -                  
      capture         0.02280                   5.86              
                                                                  
mf = 3  Neutron cross sections                                    
  Below 100 keV, resolved resonance parameters were given.        
  Above 100 keV, the spherical optical and statistical model      
  calculation was performed with casthy/12/, by taking account of 
  competing reactions, of which cross sections were calculated    
  with pegasus/13/ standing on a preequilibrium and multi-step    
  evaporation model.  The omp's for neutron given in Table 1 were 
  determined by Iijima and Kawai/14/ to reproduce a systematic    
  trend of the total cross section.  The omp's for charged        
  particles are as follows:                                       
     proton   = Perey/15/                                         
     alpha    = Huizenga and Igo/16/                              
     deuteron = Lohr and Haeberli/17/                             
     helium-3 and triton = Becchetti and Greenlees/18/            
  Parameters for the composite level density formula of Gilbert   
  and Cameron/19/ were evaluated by Iijima et al./20/  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
  /21/.                                                           
                                                                  
     For JENDL-3.2, data of inelastic, (n,2n) and (n,3n) reaction 
  cross sections were adopted from JENDL fusion file.  The        
  calculation was made with sincros-ii system/4/ by adopting      
  Walter-Guss omp modified by Yamamuro/4/ for neutrons, Lemos omp 
  modified by Arthur and Young/22/ for alpha, the same omp's as   
  the pegasus calculation for other charged particles and standard
  level density parameters 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./6/  Contributions of the direct process was calculated   
    for the levels marked with '*'.                               
                                                                  
           no.      energy(MeV)    spin-parity (direct process)   
           gr.       0.0             0  +                         
            1        1.5940          0  +                         
            2        1.7505          2  +          *              
            3        1.8971          3  -          *              
            4        2.2259          1  -                         
            5        2.3300          2  +                         
            6        2.4400          1  -                         
            7        2.8574          3  -                         
      Levels above 2.857 MeV were assumed to be overlapping.      
                                                                  
  mt = 16  (n,2n) cross section                                   
  mt = 17  (n,3n) cross section                                   
    Data for JENDL fusion file were adopted.                      
                                                                  
  mt = 102  Capture                                               
    Spherical optical and statistical model calculation with      
    casthy was adopted.  Direct and semi-direct capture cross     
    sections were estimated according to the procedure of Benzi   
    and Reffo/23/ and normalized to 1 milli-barn at 14 MeV.       
                                                                  
    The gamma-ray strength function (1.40e-5) was adjusted to     
    reproduce the capture cross section of 12 milli-barns at 30   
    keV measured by Wyrick/24/                                    
                                                                  
    For JENDL-3.3, the cross section was modified so as to        
    reproduce elemental data measured by Stavisskij et al./29/ and
    Poenitz/30/.                                                  
                                                                  
  mt = 22  (n,n'a) cross section                                  
  mt = 28  (n,n'p) cross section                                  
  mt =103  (n,p) cross section                                    
  mt =104  (n,d) cross section                                    
  mt =105  (n,t) cross section                                    
  mt =107  (n,alpha) cross section                                
    These reaction cross sections were calculated with the        
    preequilibrium and multi-step evaporation model code pegasus. 
                                                                  
    The Kalbach's constant k (= 203.6) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/25/ and level  
    density parameters.                                           
                                                                  
    Finally, the (n,2n), (n,p) and (n,alpha) cross sections were  
    normalized to the following values at 14.5 MeV:               
      (n,2n)      1500.00  mb (measured by Ikeda+/26/)            
      (n,p)          3.79  mb (systematics of Forrest/27/)        
      (n,alpha)      3.00  mb (recommended by Forrest/27/)        
                                                                  
  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=207   Total alpha production                                 
    Sum of mt=22 and 107.                                         
                                                                  
mf = 4  Angular distributions of secondary neutrons               
  mt = 2                                                          
    Calculated with casthy/12/.                                   
  mt = 51-57                                                      
    Taken from JENDL fusion file data which was calculated with   
    casthy2y and dwuck/28/ (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/5/.                             
  mt = 203,204,205,207                                            
    Based on Kalbach's systematics/31/.                           
                                                                  
mf = 12  Photon production multiplicities                         
  mt=16, 17, 22, 28, 91, 103, 107                                 
    Calculated with gnash code /4/.                               
  mt=102                                                          
    Calculated with casthy code /12/.                             
  mt=51-57                                                        
    Transitioin probability arrays                                
                                                                  
mf = 14  Photon angular distributions                             
  mt=16, 17, 22, 28, 51-57, 91, 102, 103, 107                     
    Isotropic.                                                    
                                                                  
mf = 15  Continuous photon energy distributions                   
  mt=16, 17, 22, 28, 91, 103, 107                                 
    Calculated with egnash code /4/.                              
  mt=102                                                          
    Calculated with casthy code /12/.                             
                                                                  
                                                                  
================================================================= 
<> 
================================================================= 
                                                                  
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         
  The form of surface absorption part is der. Woods-Saxon type.   
                                                                  
Table 2  Level density parameters                                 
                                                                  
 nuclide  syst a(1/MeV)  t(MeV)    c(1/MeV)  Ex(MeV)   pairing    
 ---------------------------------------------------------------  
 38-Sr- 92  *  1.288e+01 7.065e-01 2.515e-01 6.391e+00 2.360e+00  
 38-Sr- 93  *  1.386e+01 6.989e-01 1.878e+00 5.664e+00 1.240e+00  
 38-Sr- 94  *  1.485e+01 6.915e-01 4.495e-01 7.333e+00 2.530e+00  
 38-Sr- 95  *  1.586e+01 6.842e-01 4.531e+00 6.411e+00 1.240e+00  
                                                                  
 39-Y - 93     1.150e+01 8.053e-01 1.740e+00 5.854e+00 1.120e+00  
 39-Y - 94     9.149e+00 7.385e-01 1.378e+00 2.222e+00 0.0        
 39-Y - 95     1.070e+01 8.306e-01 1.082e+00 5.839e+00 1.290e+00  
 39-Y - 96  *  1.603e+01 6.771e-01 2.794e+01 5.117e+00 0.0        
                                                                  
 40-Zr- 94     1.275e+01 7.530e-01 4.411e-01 7.019e+00 2.320e+00  
 40-Zr- 95     1.331e+01 6.070e-01 5.453e-01 3.985e+00 1.200e+00  
 40-Zr- 96     1.320e+01 7.000e-01 2.235e-01 6.589e+00 2.490e+00  
 40-Zr- 97     1.259e+01 5.590e-01 2.497e-01 3.084e+00 1.200e+00  
 ---------------------------------------------------------------  
  syst:  * = ldp's were determined from systematics.              
                                                                  
 Spin cutoff parameters were calculated as 0.146*sqrt(a)*a**(2/3).
 in the casthy calculation. Spin cutoff factors at 0 MeV were     
 assumed to be 3.791 for Zr- 96 and 5.0 for Zr- 97.               
                                                                  
References                                                        
 1) Aoki, T. et al.: Proc. Int. Conf. on Nuclear Data for Basic   
    and Applied Science, Santa Fe., Vol. 2, p.1627 (1985).        
 2) Kawai, M. et al.: J. Nucl. Sci. Technol., 29, 195 (1992).     
 3) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).                
 4) Yamamuro, N.: JAERI-M 90-006 (1990).                          
 5) Kumabe, I. et al.: Nucl. Sci. Eng., 104, 280 (1990).          
 6) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.       
 7) Coceva, C., et al.: "Proc. Int. Conf. on Neutron Cross        
    Sections for Technology, Knoxville 1979", 319 (1980).         
 8) Musgrove, A.R. de L., et al.: AAEC/E-415 (1977).              
 9) Brusegan, A., et al.: "Proc. 4th Int. Symp. on Neutron-Capture
    Gamma-Ray Spectroscopy and Related Topics, Grenoble 1981",    
    406, the Institute of Physics, London (1982).                 
10) Salah, M.M, et al.: "Proc. Int. Conf. on Nuclear Data for     
    Basic and Applied Science, Santa Fe 1985", Vol. 1, 593 (1986).
11) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
12) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).              
13) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
14) Iijima, S. and Kawai, M.: J. Nucl. Sci. Technol., 20, 77      
    (1983).                                                       
15) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
16) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
17) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
18) Becchetti, F.D., Jr. and Greenlees, G.W.: Polarization        
    Phenomena in Nuclear Reactions ((Eds) H.H. Barshall and       
    W. Haeberli), p. 682, the University of Wisconsin Press.      
    (1971).                                                       
19) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
    (1965).                                                       
20) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
21) Gruppelaar, H.: ECN-13 (1977).                                
22) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980).              
23) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
24) Wyrick, J.M. and Poenitz, W.P.: ANL-83-4, 196 (1982).         
25) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
26) Ikeda, Y. et al.: JAERI 1312 (1988).                          
27) Forrest, R.A.: AERE-R 12419 (1986).                           
28) Kunz, P.D.: Private communication.                            
29) Stavisskij, Ju.Ja. et al.: At. Energija, 15, 323 (1963).      
30) Poenitz, W.P.: ANL-83-4, p.239 (1982).                        
31) Kalbach, C. : Phys. Rev. C37, 2350(1988).