44-Ru-101

 44-Ru-101 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAY10                       20100202   
----JENDL-4.0         MATERIAL 4440                               
-----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.       
   ===========================================================    
                                                                  
History                                                           
84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/        
90-03 Modification for JENDL-3 was made/2/.                       
93-10 JENDL-3.2 was made by JNDC FPND W.G.                        
10-02 Compiled by A.Ichihara.                                     
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      (2,151)       Small change in unresolved res. paramters     
      (3,2), (3,4), (3,51-91), (3,102)                            
      (4,51-91)                                                   
                    Level scheme for inelastic scattering cross   
                    sections were replaced.                       
     ***********************************************************  
                                                                  
     *****   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 1.06 keV)                
                                                                  
    The data of JENDL-3.3 was adopted, and parameters of a        
    negative resonance were modified so as to repruduce the       
    measured thermal capture cross section of 5.2 +- 0.3 b/3/,    
    and elastic scattering of 6.0 +- 0.5 b/4/.                    
                                                                  
    ** comments to JENDL-3.3 **                                   
    Resonance parameters of JENDL-2 were modified according to new
    experimental data.                                            
       For JENDL-2, parameters were determined from the experimen-
    tal data of Priesmeyer and Jung/5/ and Popov et al./6/        
    Values of spin J were based on the data of Coceva et al./7/   
    A negative resonance was added at -20 eV to reproduce the     
    capture cross section of 3.4+-0.9 barns at 0.0253 eV/8/.      
    Average radiation width of 0.180+-0.022 eV was deduced, and   
    adopted to the levels whose radiation width was unknown.      
       For JENDL-3, parameters of 40 levels were reevaluated on   
    the basis of the new experimental data of Anufriev/9/ for     
    neutron widths.  Radiation widths and total spin J of         
    several levels were also revised according to Anufriev's      
    data.  Scattering radius was modified to 6.1 fm.  Total spin  
    J of some resonances was tentatively estimated with a random  
    number method.  Neutron orbital angular momentum L of some    
    resonances was determined with a method of Bollinger and      
    Thomas/10/.                                                   
                                                                  
  Unresolved resonance region : 1.06 keV - 100 keV                
    The parameters were adjusted to reproduce the capture cross   
    section measured by Macklin et al./11,12/  The effective      
    scattering radius was obtained from fitting to the calculated 
    total cross section at 100 keV.                               
                                                                  
    The unresolved parameters should be used only for             
    self-shielding calculation.                                   
                                                                  
  Typical values of the parameters at 70 keV:                     
    S0 = 0.59e-4, S1 = 6.10e-4, S2 = 0.54e-4, Sg = 105.e-4,       
    Gg = 0.173 eV, R  = 5.062 fm.                                 
                                                                  
    Thermal cross sections and resonance integrals at 300K (b)    
    -------------------------------------------------------       
                    0.0253 eV    reson. integ.(*)                 
    -------------------------------------------------------       
    total           11.234                                        
    elastic          6.002                                        
    capture          5.232          101                           
    -------------------------------------------------------       
         (*) 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/13/, by taking account of 
  competing reactions, of which cross sections were calculated    
  with PEGASUS/14/ 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/15/.  The     
  OMP's for charged particles are as follows:                     
     proton   = Perey/16/                                         
     alpha    = Huizenga and Igo/17/                              
     deuteron = Lohr and Haeberli/18/                             
     helium-3 and triton = Becchetti and Greenlees/19/            
  Parameters for the composite level density formula of Gilbert   
  and Cameron/20/ were evaluated by Iijima et al./21/  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
  /22/.                                                           
                                                                  
  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./23/.           
                                                                  
           no.      energy(MeV)    spin-parity                    
           gs        0.0            5/2 +                         
            1        0.12723        3/2 +                         
            2        0.30685        7/2 +                         
            3        0.31133        5/2 +                         
            4        0.32480        1/2 +                         
            5        0.42230        3/2 +                         
            6        0.52750       11/2 -                         
            7        0.53500        5/2 +                         
            8        0.54508        7/2 +                         
            9        0.59830        5/2 -                         
           10        0.61630        3/2 +                         
           11        0.62300        3/2 +                         
           12        0.62350        1/2 +                         
           13        0.68400        3/2 +                         
           14        0.71800        1/2 -                         
           15        0.72000        9/2 +                         
           16        0.82300        3/2 +                         
           17        0.84278        7/2 +                         
           18        0.90800        1/2 -                         
           19        0.92700        3/2 +                         
           20        0.92872        9/2 +                         
           21        0.93847        7/2 +                         
           22        0.97340        5/2 +                         
           23        1.0012        11/2 +                         
           24        1.0410         3/2 +                         
           25        1.0510         7/2 +                         
           26        1.0980         1/2 +                         
           27        1.1100         1/2 +                         
           28        1.1690         3/2 +                         
      Levels above 1.2068 MeV were assumed to be overlapping.     
                                                                  
  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/24/ and normalized to 1 milli-barn at 14 MeV.       
                                                                  
    The gamma-ray strength function (1.16e-02) was adjusted to    
    reproduce the capture cross section of 500 milli-barns at 100 
    keV measured by Macklin et al./11,12/                         
                                                                  
  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 =106  (n,he3) 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 (= 106.5) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/25/ 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)         24.00  mb (systematics of Forrest/26/)        
      (n,alpha)      6.07  mb (systematics of Forrest)            
                                                                  
  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.  For other reactions, isotropic distri- 
  butions 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.                               
                                                                  
TABLE 1  NEUTRON OPTICAL POTENTIAL PARAMETERS                     
                                                                  
                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         
  THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE.   
                                                                  
TABLE 2  LEVEL DENSITY PARAMETERS                                 
                                                                  
 NUCLIDE       A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 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  
 42-MO-100     1.780E+01 6.000E-01 6.702E-01 6.645E+00 2.220E+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        
 43-TC-101     1.675E+01 6.440E-01 6.361E+00 5.761E+00 9.400E-01  
                                                                  
 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  
 44-RU-102     1.643E+01 6.550E-01 8.872E-01 7.106E+00 2.220E+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 14.30 for Ru-101 and 7.654 for Ru-102.             
                                                                  
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) J.Halperin et al.: ORNL 3832, p.4 (1965).                     
 4) S.F.Mughabghab: "Atlas of Neutron Resonances," Elsevier       
    (2006).                                                       
 5) H.G.Priesmeyer, H.H.Jung: Atomkernenergie, 19, 111 (1972).    
 6) Ju.P.Popov et al.: Yad. Fiz., 29, 561 (1979).                 
 7) C.Coceva et al.: Nucl. Phys., A117, 586 (1968).               
 8) S.F.Mughabghab et al.: "Neutron Cross Sections, Vol. I,       
    Part A", Academic Press (1981).                               
 9) V.A.Anufriev et al.: Atom. Energiya, 58, 279 (1985).          
10) L.M.Bollinger, G.E.Thomas: Phys. Rev., 171, 1293 (1968).      
11) Macklin, R.L., et al.: "Proc. Specialists' Meeting on Neutron 
    Cross Sections of Fission Products, Bologna 1979", NEANDC(E)  
    209L, 103.                                                    
12) Macklin, R.L., Winters, R.R.: Nucl. Sci. Eng., 78, 110(1981). 
13) Igarasi, S. and Fukahori, T. JAERI 1321 (1991).               
14) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
15) Iijima, S. and Kawai, M.: J. Nucl. Sci. Technol., 20, 77      
    (1983).                                                       
16) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
17) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
18) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
19) 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).                                                       
20) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
    (1965).                                                       
21) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
22) Gruppelaar, H.: ECN-13 (1977).                                
23) ENSDF: Evaluated Nuclear Structure Data File (Oct. 1993).     
24) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
25) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
26) Forrest, R.A.: AERE-R 12419 (1986).