44-Ru-100 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAY10                       20091208   
----JENDL-4.0         MATERIAL 4437                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
   JENDL-3.2 data were automatically transformed to JENDL-3.3.    
    Interpolation of spectra: 22 (unit base interpolation)        
    (3,251) deleted, T-matrix of (4,2) deleted, and others.       
84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/        
90-03 Modification for JENDL-3 was made/2/.                       
09-12 JENDL-4.0.                                                  
      Compiled by A.Ichihara (jaea/ndc).                          
      *****   modified parts for JENDL-4.0   *******************  
      (2,151)      Resolved resonance parameters were revised     
                   by T.Nakagawa.                                 
mf = 1  General information                                       
  mt=451 Comments and dictionary                                  
mf = 2  Resonance parameters                                      
  mt=151 Resolved and unresolved resonance parameters             
  Resolved resonance region (MLBW; below 11.89 keV)               
    The data of JENDL-3.3 was adopted, and capture width of a     
    negative resonance was adjusted to repruduce the measured     
    thermal cross section of 5.8 +- 0.4/3/                        
    ** comments to JENDL-3.3 **                                   
    Resonance parameters were taken from JENDL-2 except for those 
    of negative and hypothetical resonances, angular momentum for 
    some levels and scattering radius.                            
    For JENDL-2, the 228.5-eV resonance was adopted from          
    Priesmeyer and Jung/4/.  Resonances above 2679.7 eV were      
    mainly based on the experimental data of Macklin and Halperin 
    /5/.  Resonances at 120 eV and between 336 and 2497 eV were   
    hypothetical levels generated by assuming S0=0.43e-4, D0=340  
    eV, S1=4.1e-4, D1=110 eV. The average radiation width of      
    0.124+-0.017 eV was deduced and adopted to the levels whose   
    radiation width was unknown.  Two negative resonances were    
    added, and parameters of the 120-eV level were adjusted so as 
    to reproduce the capture cross section of 5.0+-0.6 barns at   
    0.0253 eV and the capture resonance integral of 11.2+-1.1     
    For JENDL-3, the reduced neutron width was decreased from     
    43 meV to 23 meV.  Scattering radius was changed to 6.1 fm    
    according to the systematics of measured values.  Number of   
    negative resonances was reduced to one and its parameters were
    reevaluated.  Neutron orbital angular momentum l of some      
    resonances was estimated with a method of Bollinger and Thomas
  Unresolved resonance region : 11.89 keV - 100 keV               
    Unresolved resonance parameters were adopted from JENDL-2.    
    The neutron strength functions, S0, S1 and S2 were calculated 
    with optical model code CASTHY/8/.  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 = 0.450e-4, S1 = 6.500e-4, S2 = 0.530e-4, Sg = 3.91e-4,    
    Gg = 0.125 eV, R  = 4.971 fm.                                 
    The unresolved resonance parameters were calculated using     
    the ASREP code/9/.                                            
    The parameters should be used only for self-shielding         
    Thermal cross sections and resonance integrals at 300K (b)    
                    0.0253 eV    reson. integ.(*)                 
    total           12.341                                        
    elastic          6.498                                        
    capture          5.842          11.5                          
         (*) In the energy range from 0.5 eV to 10 MeV.           
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, by taking account of     
  competing reactions, of which cross sections were calculated    
  with PEGASUS/10/ standing on a preequilibrium and multi-step    
  evaporation model.  The OMP's for neutron given in Table 1 were 
  determined to reproduce a systematic trend of the total cross   
  section by changing rso of Iijima-Kawai potential/11/.  The     
  OMP's for charged particles are as follows:                     
     proton   = Perey/12/                                         
     alpha    = Huizenga and Igo/13/                              
     deuteron = Lohr and Haeberli/14/                             
     helium-3 and triton = Becchetti and Greenlees/15/            
  Parameters for the composite level density formula of Gilbert   
  and Cameron/16/ were evaluated by Iijima et al./17/  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
  mt = 1  Total                                                   
    Spherical optical model calculation was adopted.              
  mt = 2  Elastic scattering                                      
    Calculated as (total - sum of partial cross sections).        
  mt = 4, 51 - 91  Inelastic scattering                           
    Spherical optical and statistical model calculation was       
    adopted.  The level scheme was taken from Ref./19/.           
           no.      energy(MeV)    spin-parity     dwba cal.      
           gr.       0.0             0  +                         
            1        0.5396          2  +              *          
            2        1.1304          0  +                         
            3        1.2265          4  +                         
            4        1.3621          2  +                         
            5        1.7407          0  +                         
            6        1.8653          1  +                         
            7        1.8812          3  +                         
            8        2.0517          0  +                         
            9        2.0639          3  -              *          
           10        2.0777          6  +                         
           11        2.0993          2  -                         
           12        2.1673          2  -                         
           13        2.2406          1  +                         
           14        2.3872          0  +                         
           15        2.4694          2  -                         
           16        2.5168          2  +                         
      Levels above 2.613 MeV were assumed to be overlapping.      
    For the levels with an asterisk, the contribution of direct   
    inelastic scattering cross sections was calculated by the     
    DWUCK-4 code/20/.  Deformation parameters (beta2 = 0.2172 and 
    beta3 = 0.116) were based on the data compiled by Raman et    
    al./21/ and Spear/22/, respectively.                          
  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 (3.79e-04) was adjusted to    
    reproduce the capture cross section of 120 milli-barns at 70  
    keV measured by Macklin et al./24,25/                         
  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 =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 (=  89.2) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/26/ and level  
    density parameters.                                           
    Finally, the (n,p) and (n,alpha) cross sections were          
    normalized to the following values at 14.5 MeV:               
      (n,p)         15.00  mb (recommended by Forrest/27/)        
      (n,alpha)      8.70  mb (systematics of Forrest/27/)        
  mt = 251  mu-bar                                                
    Calculated with CASTHY.                                       
mf = 4  Angular distributions of secondary neutrons               
  Legendre polynomial coefficients for angular distributions are  
  given in the center-of-mass system for mt=2 and discrete inelas-
  tic levels, and in the laboratory system for mt=91.  They were  
  calculated with CASTHY.  Contribution of direct inelastic       
  scattering was calculated with DWUCK-4.  For other reactions,   
  isotropic distributions in the laboratory system were assumed.  
mf = 5  Energy distributions of secondary neutrons                
  Energy distributions of secondary neutrons were calculated with 
  PEGASUS for inelastic scattering to overlapping levels and for  
  other neutron emitting reactions.                               
                DEPTH (MEV)       RADIUS(FM)    DIFFUSENESS(FM)   
         ----------------------   ------------  ---------------   
        V  = 47.5                 R0 = 5.972    A0 = 0.62         
        WS = 9.74                 RS = 6.594    AS = 0.35         
        VSO= 7.0                  RSO= 5.97     ASO= 0.62         
TABLE 2  LEVEL DENSITY PARAMETERS                                 
 NUCLIDE       A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 42-MO- 96     1.403E+01 7.410E-01 6.991E-01 7.645E+00 2.400E+00  
 42-MO- 97     1.517E+01 6.800E-01 2.769E+00 6.036E+00 1.280E+00  
 42-MO- 98     1.594E+01 6.900E-01 7.358E-01 7.888E+00 2.570E+00  
 42-MO- 99     1.774E+01 6.200E-01 4.294E+00 6.058E+00 1.280E+00  
 43-TC- 97     1.600E+01 6.700E-01 4.756E+00 6.089E+00 1.120E+00  
 43-TC- 98     1.659E+01 6.120E-01 1.776E+01 4.176E+00 0.0        
 43-TC- 99     1.600E+01 6.550E-01 2.973E+00 5.984E+00 1.290E+00  
 43-TC-100     1.637E+01 5.850E-01 1.189E+01 3.635E+00 0.0        
 44-RU- 98     1.382E+01 7.400E-01 6.070E-01 7.507E+00 2.400E+00  
 44-RU- 99     1.650E+01 6.570E-01 4.016E+00 6.235E+00 1.280E+00  
 44-RU-100     1.520E+01 7.200E-01 7.835E-01 8.078E+00 2.570E+00  
 44-RU-101     1.726E+01 6.700E-01 7.228E+00 6.836E+00 1.280E+00  
 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 4.062 for Ru-100 and 14.30 for Ru-101.             
 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.: Proc. Int. Conf. on Nuclear Data for Science
    and Technology, Mito, p. 569 (1988).                          
 3) J.Halperin et al.: ORNL 3832, p.4 (1965).                     
 4) H.G.Priesmeyer, H.H.Jung: Atomkernenergie, 19, 111 (1972).    
 5) R.L.Macklin, J.Halperin: Nucl. Sci. Eng., 73, 174 (1980).     
 6) S.F.Mughabghab et al.: "Neutron Cross Sections, Vol. I,       
    Part A", Academic Press (1981).                               
 7) L.M.Bollinger, G.E.Thomas: Phys. Rev., 171,1293 (1968).       
 8) Igarasi, S.: J. Nucl. Sci. Technol., 12, 67 (1975).           
 9) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
     [in Japanese].                                               
10) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
11) Iijima, S. and Kawai, M.: J. Nucl. Sci. Technol., 20, 77      
12) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
13) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
14) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
15) 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.      
16) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
17) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
18) Gruppelaar, H.: ECN-13 (1977).                                
19) Matsumoto, J.: private communication (1981).                  
20) Kunz, P.D.: private communication.                            
21) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1     
22) Spear, R.H.: Atom. Data and Nucl. Data Table, 42, 55 (1989).  
23) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
24) Macklin, R.L., et al.: Proc. Specialists' Meeting on Neutron  
    Cross Sections of Fission Products, Bologna 1979, NEANDC(E)   
    209L, 103.                                                    
25) Macklin, R.L., Winters, R.R.: Nucl. Sci. Eng., 78, 110(1981). 
26) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
27) Forrest, R.A.: AERE-R 12419 (1986).