44-Ru-104

 44-Ru-104 JNDC       EVAL-MAR90 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAY10                       20091210   
----JENDL-4.0         MATERIAL 4449                               
-----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/.                       
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.                                 
      (2,151)      Unresolved resonance parameters were updated.  
      **********************************************************  
                                                                  
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 11.12 keV)               
                                                                  
    Resonance parameters of JENDL-3.3 were adopted by revising    
    those of the negative resonance so that the thermal capture   
    cross section was in good areement with experimental data of  
    0.47 b/3,4/.  Scattering radius was changed from 6.35         
    fm to 6.5 fm considering its systematics/5/.                  
                                                                  
    ** comments to JENDL-3.3 **                                   
    Resonance parameters were taken from JEDL-2 except those of   
    the 1st positive and a negative resonances.                   
       Parameters for JENDL-2 were evaluated as follows:          
    Resonance energies below 2 keV were taken from the experimen- 
    tal data by Priesmeyer and Jung/6/ and Shaw et al./7/, other  
    resonances above 2.7 keV were determined from Macklin and     
    Halperin/8/.  The neutron widths were evaluated on the basis  
    of the data of Priesmeyer and Jung, and of Macklin and        
    Halperin.  The radiation widths of large resonances were taken
    from Ref./8/  For the others, the average radiation width of  
    0.103+-0.018 eV was deduced, and adopted to the levels whose  
    radiation width was unknown.  Seven hypothetical resonances   
    were generated in the energy range from 2 to 2.7 keV.  For the
    levels observed by Shaw et al. and the hypothetical ones,     
    reduced neutron widths of 12 and 38 meV were given for s-wave 
    and p-wave resonances, respectively.  A negative resonance was
    added at -941 eV so as to reproduce the capture cross section 
    of 0.32+-0.02 barns at 0.0253 eV/9/.                          
       For JENDL-3, parameters of the first positive and negative 
    resonances were modified so as to reproduce the resonance     
    integral recommended by Mughabghab et al./9/  Scattering      
    radius was reduced from 6.35 fm to 6.1 fm on the basis of the 
    systematics.                                                  
                                                                  
  Unresolved resonance region : 11.12 keV - 300 keV               
    The neutron strength functions, S0 and S2 were calculated with
    optical model code CASTHY/10/, and S1 was based on the the    
    compilation of Mughabghab et al./9/  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 = 5.700e-4, S2 = 0.530e-4, Sg = 2.95e-4,    
    Gg = 0.110 eV, R  = 5.366 fm.                                 
                                                                  
    The unresolved resonance parameters were calculated using     
    the ASREP code/11/.                                           
    The parameters should be used only for self-shielding         
    calculation.                                                  
                                                                  
    Thermal cross sections and resonance integrals at 300K (b)    
    -------------------------------------------------------       
                    0.0253 eV    reson. integ.(*)                 
    -------------------------------------------------------       
    total            6.931                                        
    elastic          6.462                                        
    capture          0.4691          6.62                         
    -------------------------------------------------------       
         (*) In the energy range from 0.5 eV to 10 MeV.           
                                                                  
mf = 3  Neutron cross sections                                    
  Below 11.12 keV, resolved resonance parameters were given.      
  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/12/ 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/13/.  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/.                                                           
                                                                  
  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./21/.           
                                                                  
           no.      energy(MeV)    spin-parity    dwba cal.       
           gr.       0.0             0  +                         
            1        0.3580          2  +             *           
            2        0.8885          4  +                         
            3        0.8930          2  +                         
            4        0.9881          0  +                         
            5        1.2423          3  +                         
      Levels above 1.5 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/22/.  Deformation parameter (beta2 = 0.2742) was 
    based on the data compiled by Raman et al./23/                
                                                                  
  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 (2.85e-04) was adjusted to    
    reproduce the capture cross section of 95 milli-barns at 70   
    keV measured by Macklin et al./25,26/                         
                                                                  
  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 =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 (=  62.0) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/27/ 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)          7.00  mb (recommended by Forrest/28/)        
      (n,alpha)      2.60  mb (recommended by 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.  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 from 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  SYST A(1/MEV)  T(MEV)    C(1/MEV)  EX(MEV)   PAIRING    
 ---------------------------------------------------------------  
 42-MO-100     1.780E+01 6.000E-01 6.702E-01 6.645E+00 2.220E+00  
 42-MO-101     2.085E+01 5.650E-01 7.153E+00 6.092E+00 1.280E+00  
 42-MO-102  *  1.856E+01 6.452E-01 1.419E+00 8.145E+00 2.520E+00  
 42-MO-103     2.175E+01 5.300E-01 5.321E+00 5.655E+00 1.280E+00  
                                                                  
 43-TC-101     1.675E+01 6.440E-01 6.361E+00 5.761E+00 9.400E-01  
 43-TC-102     1.761E+01 5.400E-01 1.217E+01 3.317E+00 0.0        
 43-TC-103     1.810E+01 6.310E-01 6.436E+00 6.379E+00 1.240E+00  
 43-TC-104     1.600E+01 5.500E-01 7.030E+00 2.960E+00 0.0        
                                                                  
 44-RU-102     1.643E+01 6.550E-01 8.872E-01 7.106E+00 2.220E+00  
 44-RU-103     1.890E+01 6.480E-01 1.210E+01 7.110E+00 1.280E+00  
 44-RU-104     1.650E+01 6.780E-01 8.593E-01 7.878E+00 2.520E+00  
 44-RU-105     2.025E+01 6.060E-01 1.144E+01 6.747E+00 1.280E+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 4.524 for Ru-104 and 5.0 for Ru-105.               
                                                                  
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.: Proc. Int. Conf. on Nuclear Data for Science
    and Technology, Mito, p. 569 (1988).                          
 3) P.M.Lantz: ORNL 3679, p.11 (1964).                            
 4) R.E.Heft: 1978 MAYAG, p.495 (1978).                           
 5) S.F.Mughabghab: "Atlas of Neutron Resonances," Elsevier       
    (2006).                                                       
 6) H.G.Priesmeyer, H.H.Jung: Atomkernenergie, 19,111 (1972).     
 7) R.A.Shaw et al.: Bull. Amer. Phys. Soc., 20, 560 (1975).      
 8) R.L.Macklin, J.Halperin: Nucl. Sci. Eng., 73, 174 (1980).     
 9) S.F.Mughabghab et al.: "Neutron Cross Sections, Vol. I,       
    Part A," Academic Press (1981).                               
10) Igarasi, S.: J. Nucl. Sci. Technol., 12, 67 (1975).           
11) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
     [in Japanese].                                               
12) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
13) Iijima, S. and Kawai, M.: J. Nucl. Sci. Technol., 20, 77      
    (1983).                                                       
14) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
15) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
16) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
17) 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).                                                       
18) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
    (1965).                                                       
19) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
20) Gruppelaar, H.: ECN-13 (1977).                                
21) Matsumoto, J., et al.: JAERI-M 7734 (1978).                   
22) Kunz, P.D.: private communication.                            
23) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1     
    (1987)                                                        
24) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
25) Macklin, R.L., et al.: Proc. Specialists' Meeting on Neutron  
    Cross Sections of Fission Products, Bologna 1979, NEANDC(E)   
    209L, 103.                                                    
26) Macklin, R.L. and Winters, R.R.: Nucl. Sci. Eng., 78, 110     
    (1981).                                                       
27) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
28) Forrest, R.A.: AERE-R 12419 (1986).