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 71-Lu-175 ORNL,BNW   EVAL-MAR98 R.Q. WRIGHT, LEONARD-STEWART     
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 7125         REVISION 1            
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
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**         Original data taken from:  JEFF-3.1                  **
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*****************************  JEFF-3.1  *************************
**                                                              **
**         Original data taken from:  ENDF/B-VI.8               **
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 ENDF/B-VI MOD 1 Revision, March 1998, R.Q. Wright (ORNL)         
                                                                  
    This revision contains the following changes, relative to the 
 1967 evaluation:                                                 
                                                                  
 MF= 2  RESONANCE PARAMETERS                                      
  RESOLVED RESONANCE RANGE  1.0E-5 to 411.0 eV (revised)          
    The resolved resonance parameters are taken from Mughabghab   
  [24].  A MLBW formalism is used.                                
                                                                  
  UNRESOLVED RESONANCE RANGE  411 eV to 10 keV (revised)          
    The scattering radius, R = 7.7 fm.                            
                                                                  
 MF=3  SMOOTH CROSS SECTIONS                                      
    Total, elastic, and capture are set to zero below 10 keV.     
 The capture cross-section (MT = 102) is revised for the 10 keV   
 to 20 MeV energy range, based on data of Macklin [23].           
    Scattering cross-section is revised to reflect the change in  
 the capture and to keep the total cross-section unchanged.       
                                                                  
              Table 1.  Lu-175 Average Capture (mb)               
                                                                  
               Energy (keV)  Evaluation   Macklin [23]            
                              Flat wt.                            
                    3 - 4       4816        5159                  
                    4 - 5       4036        4170                  
                    5 - 6       3547        3360                  
                    6 - 8       3035        2997                  
                    8 -10       2595        2545                  
                   10 -12       2260        2171                  
                   12 -15       1988        1956                  
                   15 -18       1761        1724                  
                   18 -21       1600        1583                  
                   21 -25       1455        1446                  
                   25 -30       1315        1279                  
                   30 -35       1205        1192                  
                   35 -45       1093        1072                  
                   45 -55       985.8        986                  
                   55 -65       907.7        899                  
                   65 -80       834.3        824                  
                   80-100       756.4        749                  
                  100-120       695.0        700                  
                  120-150       615.2        611                  
                  150-180       543.0        545 +/- 4            
                  180-210       497.5        495 +/- 4            
                  210-250       464.9        462 +/- 3            
                  250-300       432.7        433 +/- 3            
                  300-350       392.4        397 +/- 3            
                  350-400       342.7        339 +/- 3            
                  400-450       291.8        293 +/- 3            
                  450-500       249.1        246 +/- 3            
                  500-550       218.8        223 +/- 3            
                  550-600       198.8        195 +/- 3            
                  600-650       184.4        185 +/- 3            
                  650-700       172.2        171 +/- 3            
                  700-750       161.9        164 +/- 3            
                  750-800       154.2        152 +/- 3            
                  800-850       148.2        149 +/- 3            
                  850-900       143.2        143 +/- 3            
                  900-950       139.7        133 +/- 3            
                 950-1000       136.5        135 +/- 3            
                1000-1100       132.6        135 +/- 3            
                1100-1200       128.1        126 +/- 3            
                1200-1300       124.4        126 +/- 3            
                1300-1400       121.4        125 +/- 3            
                1400-1500       119.2        125 +/- 3            
                1500-1600       117.7        118 +/- 4            
                1600-1700       116.7        120 +/- 4            
                1700-1800       116.2        115 +/- 4            
                1800-1900       115.5        117 +/- 5            
                1900-2000       114.5        127 +/- 5            
                                                                  
        2200 m/s cross sections (barns)                           
                          Evaluation        Macklin [23]          
               Total         29.52           30.2                 
               Elastic        6.44            7.1 +/- 0.4         
               Capture       23.08           23.1 +/- 1.1         
                                                                  
        Capture resonance integral (barns)                        
                          Evaluation        Macklin [23]          
           0.5   - 411 eV   590.40                                
           0.411 - 10  keV   27.25                                
           10 keV -           4.15                                
           Total RI         621.80          610.0 +/- 50          
                                                                  
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 ENDF/B-VI MOD 0, February 1990 (NNDC)                            
                                                                  
 ENDF/B-V material converted to ENDF-6 format by NNDC.            
                                                                  
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 ENDF/B-V Evaluation, MAT 1302, June 1967, B.R. Leonard and       
                      K.B. Stewart (BNW)                          
                                                                  
 This file transfered from ENDF/B-III with no modifications.      
                                                                  
 Data modified June, 1970 to conform to ENDF/B-II formats         
                                                                  
 MF= 1  GENERAL INFORMATION                                       
   MT=451 Atomic mass=174.9409  I=3.5  from Chart of Nuclides [2] 
   MT=453 Radioactive decay for MT=16,17,102,103,107 [2]          
                                                                  
 MF= 3  SMOOTH CROSS SECTIONS                                     
   MT=  1  Total at 0.0001 eV to 1.0 eV calculated by UNICORN [10]
      for 0 K using parameters of File 2 to fit [1] the data of   
      Baston [8], 31.14 barns at 0.0253 eV.                       
         10 keV to 20 MeV: 10 keV to 2.5 MeV total similar to     
      erbium and hafnium; 2.5 to 15 MeV eye fit to data of Otter  
      [11].                                                       
         15 to 20 MeV Optical-Model calculations [1] using        
      ABACUS-2 [12].                                              
   MT=  2  Elastic scattering 0.0001 eV to 1.0 eV from UNICORN    
      calculation [1]. No Bragg effects.                          
          10 keV to 20 MeV by subtraction of all others from      
      total.                                                      
   MT=  4  Inelastic scattering from ABACUS calculation [1].      
   MT= 16,17  Threshold to 20 MeV Calculated [1] by procedure     
      of Pearlstein [13].                                         
   MT=102 Capture 0.0001 eV to 1.0 eV from UNICORN calculation    
      [1], 25.88 barns at 0.0253 eV.                              
          10 keV to 20 MeV: 10-20 keV extrapolation of data Block 
      [14], 24 keV Chaubey [15], 30-200 keV Macklin [16],         
      14 MeV Kenna [17].                                          
   MT=103 n,p constructed to pass [1] experimental value 14 MeV   
      Coleman [18].                                               
   MT=107 n,alpha shape as 197Au (ENDF/B) passing through 14 MeV  
      value of Marcazzan [19].                                    
                                                                  
 MF= 4  LEGENDRE POLYNOMIALS                                      
   MT=  2  20 by 20 transformation matrix c.m.-lab calculated [1] 
      by CHAD. 19 c.m. Legendre coefficients 10 keV to 20 MeV     
      calculated from distributions of ABACUS [1] by modified     
      version [1] of CHAD. No compound-elastic for E > 5. MeV.    
                                                                  
 MF= 5  SECONDARY ENERGY DISTRIBUTIONS                            
   MT=  4  Inelastic scattering threshold to 2.0 MeV to 8 levels  
      [21] from Hausser Feshbach ABACUS calculation [1].          
      2-20 MeV nuclear temperatures for Maxwellian [22].          
   MT= 16,17  Nuclear temperatures for Maxwellian [22]            
      thresholds to 20 MeV.                                       
                                                                  
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 REFERENCES                                                       
  1. B.R. Leonard and K.B. Stewart, PNL (June 1967).              
  2. D.T. Goldman, Chart of the Nuclides, June 1964               
  3. H.H. Landon, Phys.Rev. 100, 1414 (1955)                      
  4. J. Harvey, R. Block, Slaughter, report ORNL-59-2-83 (1959)   
  5. J. Harvey, D. Hughes, R. Carter, R. Pilcher, Phys.Rev. 99,   
     100 (1955)                                                   
  6. M. Atoji, Phys.Rev. 121, 610 (1961)                          
  7. J. Brunner and F. Widder, Nuclear Data for Reactors, Proc.   
     Conf., Paris, France, October, 1966 (IAEA, 1967) p. 61       
  8. A.H. Baston, J.C. Lisle and G.S.G. Tuckey, J.Nucl.En. A13,   
     35 (1960)                                                    
  9. H.W. Newson, Neutron Cross Section Technology, Proc. Conf.,  
     Washington, DC, March 1966 (AEC Tecnical Information Div.,   
     1966) p. 562                                                 
 10. J.M. Otter, report NAA-SR-11980, Vol.6 (1966)                
 11. D.G. Foster Jr. and D.W. Glasgow, Phys.Rev.C 3, 576 (1971)   
 12. E.H. Auerbach, report BNL-6562 (1962)                        
 13. S. Pearlstein, Nucl.Sci.Eng. 23, 238 (1965)                  
 14. R. Block et al., Neutron Time-of-Flight Methods, Proc. Conf. 
     Saclay, France, July 1961 (EURATOM, 1961) p. 203             
 15. A.K. Chaubey and M.L. Sehgal, Nucl.Phys. 66, 267 (1965)      
 16. R.L. Macklin and J.H. Gibbons, Phys.Rev. 159, 1007 (1967)    
 17. B.T. Kenna and F.J. Conrad, report SC-RR-66-229 (1966)       
 18. R.F. Coleman et al., Proc.Phys.Soc. 73, 215 (1959)           
 19. G.M. Marcazzan, F. Tonolini and L. Zetta, Nucl.Phys. 46, 51  
     (1963)                                                       
 20. R.F. Berland, report NAA-SR-11231 (1965)                     
 21. Nucl.Data Sheets, 6-6-15 (June 1965)                         
 22. S. Weinberg and E. Wigner, The Physical Theory of Nuclear    
     Chain Reactions (U. of Chicago Press, 1958)                  
 23. R.L. Macklin, D.M. Drake and J.J. Malanify, Los Alamos       
     report LA-7479-MS (1978); data taken from EXFOR 10720.005.   
 24. S.F. Mughabghab, Neutron Cross Sections, Vol. 1, Neutron     
     Resonance Parameters and Thermal Cross Sections (Academic    
     Press, 1984)                                                 
                                                                  
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