41-Nb- 93

 41-Nb- 93 JAEA       EVAL-NOV09 A.Ichihara, K.Shibata, S.Kunieda+
                      DIST-MAY10                       20091201   
----JENDL-4.0         MATERIAL 4125                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
82-10 Evaluation of resonance parameters for JENDL-2 was made     
      by Kawai.                                                   
88-10 Evaluation was performed for JENDL-3.                       
88-10 Compiled by K.Shibata (JAERI).                              
94-02 JENDL-3.2                                                   
        Resonance parameters modified by M.Kawai(Toshiba).        
        Gamma-ray production data by S.Igarasi(NEDAC).            
        Other data were adopted from JENDL fusion file.           
      Compiled by T.Nakagawa                                      
     *****   Modified parts for JENDL-3.2   ********************  
      (2,151)     resolved resonance parameters modified          
      (3,1), (3,2), (3,4), (3,51-91) from JENDL fusion file       
      (4,16-91)   taken from JENDL fusion file                    
      (5,16-91)   taken from JENDL fusion file                    
      (12,102)    below 100 keV                                   
      (15,102)    below 100 keV                                   
      JENDL fusion file /1/  (as of Feb. 1994)                    
            Evaluated by B.Yu(CIAE) and S.Chiba (NDC/JAERI)       
            Compiled  by S.Chiba.                                 
       - Cross sections were mainly taken from JENDL-3.1 except   
         for the (n,2n) and continuum inelastic scattering cross  
         sections which were taken from the SINCROS-II/2/         
         calculation.  Interpolation scheme of the discrete       
         inelastic scattering cross sections was changed from 3   
         to 2.  The total cross section at 10 and 15 keV, which   
         is the background cross section, were set to 0.0.        
       - Energy distributions were replaced with the SINCROS-II   
       - MF=6 was made by the M15TOB program/1/.  The precom-     
         und to compound ratio was taken from output of the       
         SINCROS-II calculation.  Kalbach's systematics/3/ was    
         adopted for DDX.                                         
       - Optical-model, level density and other parameters used in
         the SINCROS-II calculation are described in ref./2/.     
         Level schemes were determined on the basis of ENSDF/4/.  
            Modefied by T.Fukahori (NDC/JAERI) on Aug. 13, 1996   
       - Total cross section between 0.5 and 4 MeV is modified so 
         as to reproduce the experimental data L. Green et al./5/ 
         A.B. Smith et al./6/.                                    
       - Newly evaluated value of (n,alpha) reaction cross section
         considered old version of JENDL fusion file, FENDL-1 and 
         the experimental data measured by A. Mannan et al./7/    
         and R. Woelfle et al./8/ is replaced old one.            
2001-08 JENDL-3.3                                                 
            Evaluated by Y. Watanabe (Kyushu Univ.)               
            Compiled  by Y. Watanabe and K. Shibata               
      Gamma-ray energy distributions for radiative capture        
      (MT=102) were modified.  Other data were adopted from       
      JENDL-3.2 and JENDL-fusion file.                            
     *****   modified parts for JENDL-3.3   ********************  
     (6,16-91)            taken from the JENDL fusion file        
     (6,202,203,204,207)  taken from the JENDL fusion file        
     (12,102),(15,102)    newly evaluated above 3 MeV             
      - Cross sections were taken from the JENDL-3.2.             
      - Energy-angle distributions (MF=6) were taken from the     
        JENDL fusion file.                                        
      - For the (n,gamma) energy distribution, semi-direct        
        component calculated using the GNASH code/9/ was added    
        to the statistical component taken from JENDL-3.2         
        after appropriate renormalization for incident energies   
        above 3 MeV.                                              
2009-11 JENDL-4.0                                                 
     *****   modified parts for JENDL-4.0   ********************  
      (1,451)       Updated.                                      
      (2,151)       Resolved resonance parameters.  (T.Murata)    
                    Unresolved resonance parameters.              
      (3,2),(3,207) Revised.                                      
      Following data were calculated by the POD code/10,11/.      
      (3,28)        Revised.                                      
      (3,103)       Revised.                                      
      (3,203)       Revised.                                      
      (6,16)        Revised.                                      
      (6,91)        Revised.                                      
      (6,203)       Revised.                                      
MF=1          General information                                 
  MT=451    Descriptive data and dictionary                       
MF=2          Resonance parameters                                
  MT=151 Resolved and unresolved resonance parameters             
    Resolved resonances: 1.0e-5 eV - 7 keV                        
      Parameters in JENDL-3.1 were taken from JENDL-2 by modifying
      J values. The JENDL-2 parameters were evaluated on the basis
      of following measurements:                                  
       transmission  by Garg et al./12/, Poittevin et al./13/     
                     and Iliescu et al./14/                       
       scattering    by Iliescu et al./14/                        
       capture       by Macklin /15/, Lopez et al./16/ and        
                     Iliescu et al. /14/                          
      J values determined by Haste et al. /17/  were adopted.     
      average radiative width was assumed to be 0.172 eV (0.212 eV
      for doublet), and Scattering radius to be 7.10 fm.  The J   
      values of resonances without known j values were randomly   
      For JENDL-3.2, re-assignment of J and modification of       
      neutron and radiative widths were made to reproduce the     
      measured capture area data/15/.                             
      In JENDL-4.0, we took account of the data for eight         
      resonances obtained by Drindak et al./18/  The J values     
      for 364.93-eV s-wave, 362.71-eV p-wave and 392,53-eV p-wave 
      resonances were taken from ENDF/B-VI.8.                     
      After JENDL-3.3 evaluation, new measurements 93Nb resonance 
      parameters have been made by Drindak et al./18/ and by      
      Wang et al./19/.                                            
      Resonance parameters of JENDL-3.3 are replaced by           
      those of Drindak et al./18/ in the resonance energy region  
      below 500eV, in detail, an s-wave resonance at Er=194.25 eV;
      J=4 was added and a p-wave resonance at Er=184.3 eV was     
      Resonance parameters of a negative resonance were determined
      to reproduce thermal cross sections and resonance integral  
      given by Mughabghab/20/.                                    
  Unresolved resonances: 7 keV - 600 keV                          
     Determined with the asrep code/21/ so as to reproduce        
     the evaluated sig-c and sig-t up to 600 keV.                 
     Typical parameters at 70 keV:                                
       s0= 0.4e-4, s1=6.68e-4, d-obs=96.0 ev, r=6.477 fm,         
       radiative width= 0.172 eV                                  
    The parameters should be used only for self-shielding         
    Thermal cross sections and resonance integrals at 300 K       
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
     Total           7.498E+00                                    
     Elastic         6.356E+00                                    
     n,gamma         1.142E+00           8.982E+00                
       (*) Integrated from 0.5 eV to 10 MeV.                      
MF=3          Neutron cross sections                              
  MT=1      Total                                                 
        Above 7 keV.                                              
        100 keV to 20 MeV: spline-function fitting to the         
                           experimental data/22/.                 
  MT=2      Elastic scattering                                    
        (total) - (reaction cross section)                        
  MT=4,51-62,91 Inelastic scattering                              
        The inelastic scattering cross sections to discrete levels
        were calculated with the statistical-model code casthy    
        /23/, considering level fluctuation, using modified       
        walter-guss potential parameters for neutrons.  The       
        components of the direct process were added to the levels 
        of mt=53, 54, 56, 57, 58, 60 by using the DWUCK code /24/.
        The cross section to continuum was calculated with the    
        GNASH code /25/ considering pre-equilibrium.  The         
        modification made for JENDL fusion file was also adopted  
        to JENDL-3.2.                                             
        The level scheme is given as follows:                     
          no.    energy(mev) spin-parity                          
           g.s   0.0          9/2 +                               
           1.    0.0304       1/2 -                               
           2.    0.6860       3/2 -                               
           3.    0.7440       7/2 +                               
           4.    0.8087       5/2 +                               
           5.    0.8101       3/2 -                               
           6.    0.9499      13/2 +                               
           7.    0.9791      11/2 +                               
           8.    1.0826       9/2 +                               
           9.    1.2900       3/2 -                               
          10.    1.2974       9/2 +                               
          11.    1.3156       5/2 +                               
          12.    1.3351      17/2 +                               
        Levels above 1.34 mev were assumed to be overlapping.     
        Optical-model parameters are as follows:                  
          V=52.56-0.30*En,  Ws=3.233+0.271*En,  Vso=6.004-0.015*En
          Vsym=-16.5     ,  Wi=-0.963+0.153*en, Wso=0.291-0.018*En
          r0=1.229       ,  rs=1.282   , ri=1.42,  rso=1.103      
          a0=0.688       ,  b=0.512    , ai=0.509, aso=0.56       
        The level density parameters for GNASH and CASTHY         
        calculations are as follows:                              
                 a        ex      t      ds    gamma-g            
               (1/mev)  (mev)   (mev)   (ev)     (ev)             
        Nb-94   14.4    4.059   0.719   30.0    0.052             
        Nb-93   13.0    5.884   0.834    -      0.170             
        Nb-92   11.5    3.254   0.790    -      0.170             
        Nb-91   11.0    5.461   0.895    -      0.170             
        Zr-93   13.7    5.923   0.781    -      0.140             
        Zr-92   11.9    6.284   0.858    -      0.140             
        Y-90    11.1    1.441   0.721   1210.   0.130             
        Y-89    10.7    2.946   0.762    -      0.130             
  MT=16  (n,2n)                                                   
        Based on the experimental data/26,27/.                    
  MT=17,22,28,103,104,107 (n,3n),(n,n'a),(n,n'p),(n,p)            
     (n,d) and (n,a) cross sections                               
        calculated with gnash/25/.                                
        optical potential parameters for proton, alpha-particle   
        and deuteron were taken from the works of Perey/28/,      
        Lemos/29/ and Lohr and Haeverli/30/, respectively.        
  MT=102    Radiative capture cross section                       
        1.0e-5 eV to 7 keV: resolved resonance parameters given.  
        100 kev to 20 MeV: calculated with the CASTHY code/23/.   
              t-gamma=0.0109; determined so as to reproduce       
              sig-c=107mb at 100 keV, measured by Reffo et al./31/
MF=4          Angular distributions of secondary neutrons         
        Calculated with CASTHY for equilibrium process.  The      
        components of the direct process were added to the levels 
        of MT=53,54,56,57,58,60 by using the DWUCK code /24/.     
MF=6          Energy and angle distributions of secondary         
              neutron, proton, deuteron, and alpha particle       
  MT=16, 17, 22, 28, 91, 202, 203, 204, 207                       
        Taken from JENDL fusion file.                             
MF=12         Photon production multiplicities                    
        Calculated with GNASH/25/.                                
        From energy balance. Semi-direct component was taken      
        into account above 3 MeV.                                 
MF=14         Photon angular distributions                        
        Assumed to be isotropic.                                  
MF=15         Photon energy distributions                         
        Calculated with GNASH/25/.                                
        Below 3 MeV, calculated with CASTHY, referring to         
        the compilation of gamma-ray spectra for thermal neutron  
        by Lone et al./32/ Primary transitions were taken into    
        account at 1.0e-5, 2.53e-2, 1.0e+1, 1.0e+3, 3.0e+4 and    
        1.0e+5 eV. More than 3 MeV, semi-direct component         
        calculated by GNASH code/9/ was included. The component   
        was normalized to the experimental data of                
        Rigaud et al./33/.                                        
 1) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).                
 2) Yamamuro, N.: JAERI-M 90-006 (1990).                          
 3) Kalbach, C.: Phys. Rev. C, 37, 2350 (1988).                   
 4) ENSDF: Evaluated nuclear structure data file, BNL/NNDC.       
 5) Green, L., et al.: WAPD-TM-1073 (1973).                       
 6) Smith, A.B., et al.: ANL-NDM-70 (1982).                       
 7) Mannan, A., et al.: Phys. Rev. C, 38, 630 (1988).             
 8) Woelfle, R., et al.: Appl. Rad. Isotopes 39, 407 (1988).      
 9) Young, P.G., et al.: LA-12343-MS (1992).                      
10) A.Ichihara et al.: JAEA-Data/Code 2007-012 (2007).            
11) A.Ichihara et al.: J. Nucl. Sci. Technol. 45, 793 (2008).     
12) Garg, J.B. et al.: Phys. Rev. B137, 547 (1965).               
13) Poittevin, G.Le. et al.: Nucl. Phys. 70, 497 (1965).          
14) Iliescu, N. et al.: Nucl. Phys. 72, 298 (1965).               
15) Macklin, R.L.: Nucl. Sci. Eng. 59, 12 (1976).                 
16) Lopez, W.M. et al.: Nucl. Phys. A93, 340 (1967).              
17) Haste, T.J. and Thomas B.W.: J. Phys. G1, 967 (1975).         
18) Drindak, N.J. et al.: Nucl. Sci. Eng. 154, 294 (2006).        
19) Wang,T. et al.: 16th Pacific Basin Nuclear Conf.(Aomori,      
     Japan, 2008), P16P1280.                                      
20) Mughabghab, S.F.: "Atlas of Neutron Resonances," Elsevier     
21) Kikuchi, Y. et al.: JAERI-Data/Code 99-025 (1999).            
22) Poenitz, W.P. and Whalen, J.F.: ANL/NDM-80 (1983).            
23) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).              
24) Kunz, P.D.: Univ. Colorado (1974).                            
25) Young, P.G. and Arthur, E.D.: LA-6947 (1977).                 
26) Frehaut, J. et al.: Proc. Symp. Neutron Cross-sections from 10
    to 50 MeV, BNL, 1980, p. 399 (1980).                          
27) Veeser, L.R. et al.: Phys. Rev. C, 16, 1792 (1977).           
28) Perey, F.G.: Phys. Rev. 131, 745 (1963).                      
29) Lemos, O.F.: "Diffusion elastique de particules alpha de 21 a 
    29.6 mev sur des noyaux de la region ti-zn", Orsay Report,    
    Series A., No. 136, (1972).                                   
30) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
31) Reffo, G. et al.: Nucl. Sci. Eng., 80, 630 (1982).            
32) Lone, M.A., Leavitt, R.A. and Harrison D.A.: At. Data and     
    Nucl. Data Tables, 26, 511 (1981).                            
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