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  2-He-  3 LANL       EVAL-MAY90 G.HALE, D.DODDER, P.YOUNG        
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL  225                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.1                  **
**                                                              **
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*****************************  JEFF-3.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.0                  **
**                                                              **
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*****************************  JEFF-3.0  *************************
                                                                  
   DATA TAKEN FROM   :-   ENDF/B-VI.3 (DIST-SEP91 REV1-JUL91)     
                                                                  
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                  MOD1 OF ENDF/B-VI                               
                                                                  
     THE ONLY REVISION MADE FOR MOD1 OF ENDF/B-VI WAS TO ADD THE  
 COMMENTS BELOW ON THE STANDARDS COVARIANCES.  THE DESCRIPTION    
 OF THE ENDF/B-VI EVALUATION IS GIVEN BELOW.                      
                                                                  
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 ---------------------------------------------------------------- 
                HE-3 FREE ATOM EVALUATION                         
                  ENDF/B-VI DESCRIPTION                           
 ---------------------------------------------------------------- 
                                                                  
* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * 
                                                                  
 this file transfered from l.stewart's endf/b-iii evaluation with 
 modifications only in the 3he(n,p) and the elastic cross sections
 below 5 MeV, and the total cross section below 0.1 MeV.          
 *         *          *          *         *          *          *
 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
 *                                                               *
 * cross section standard        he-3  (n,p)                     *
 *                                                               *
 * the he-3 (n,p) cross section for this material is recommended  
 * as a standard for neutron energies from thermal to 50 kev      
 *                                                               *
 *         *          *          *         *          *          *
                                                                  
                                                                  
  mf=1                                                            
                                                                  
    mt=451, atomic mass=3.0160                                    
                                                                  
  mf=2                                                            
                                                                  
    mt=151, scattering length=0.2821e-12 cm.                      
                                                                  
  mf=3                                                            
                                                                  
    mt=  1, total cross sections --- from .00001 ev to 200 kev    
            mt1 taken as sum mt2+mt102+mt103. from 200 kev to 20  
            mev, mt1 evaluated using experimental data from ref.6.
                                                                  
    mt=  2, elastic scattering cross sections --- from .00001 ev  
            to 200 kev, mt2 taken approximately from r-matrix     
            analysis described below. above 200 kev, obtained     
            from mt2=mt1-mt102-mt103-mt104.  note two reactions   
            missing from this evaluation, namely n,n-prime,p and  
            n,2n,2p.  exp. data at 15 mev indicates non-zero      
            cross sections for these.  included in mt2 this eval. 
                                                                  
    mt=102, radiative capture cross sections --- thermal value    
            taken from ref.17, with assumption of 1/v energy      
            energy variation at all other energies.               
                                                                  
    mt=103, n-p cross sections --- below 5 mev taken from an      
            r-matrix calculation of the four-body reactions       
            by hale and dodder.  3he(n,p) data included were      
            from refs. 5,13,14, and 15.  for energies in the      
            5-20 mev range, data were used as follows -           
            ref.4 - 5.8 mev to 11. mev                            
            ref.10- 5.0 mev to 11. mev                            
            ref.12- 5.0 mev to 12. mev                            
            ref.16- 14. mev                                       
            data extrapolated to 20. mev.                         
                                                                  
    mt=104, n-d cross sections --- threshold=4.36147mev           
            q=-3.2684 mev.  evaluation from a detailed balance    
            calculation(ref.13) and experimental data(ref.11).    
                                                                  
    mt=251, average value of cosine of elastic scattering angle,  
            laboratory system.  obtained from data mf=4,mt=2.     
                                                                  
    mt=252, values of xi, obtained from data mf=4,mt=2            
                                                                  
    mt=253, values of gamma,obtained from data mf=4,mt=2          
                                                                  
  mf=4                                                            
                                                                  
    mt=  2, angular distribution of secondary neutrons from       
            elastic scatter.  evaluated from experimental data    
            from refs.2,7,9,11,16,17 covering incident energies   
            as follows -                                          
             incident energy         references                   
                 1.e-5ev             (isotropic)                  
                 0.5 mev             (isotropic)                  
                 1.0 mev              9                           
                 2.0 mev              9                           
                 2.6 mev             11                           
                 3.5 mev              9                           
                 5.0 mev             11                           
                 6.0 mev              9,7(from p+t elastic scatt) 
                 8.0 mev             11,7(from p+t elastic scatt) 
                14.5 mev             16,17(from p+t elastic scatt)
                17.5 mev             11                           
                20.0 mev              2(from p+t elastic scatt)   
                                                                  
  references                                                      
                                                                  
    1.  r.batchelor,r.aves,and t.h.r.skyrme,rev.sci.instr.26,1037 
        (1955).                                                   
    2.  r.a.vanetsian and e.d.fenchenko,soviet journal of atomic  
        energy 2,141(1957).                                       
    3.  j.n.bradbury and l.stewart,bull.am.phys.soc.3,417(1958)   
    4.  g.f.bogdanov,n.a.vlasov,c.p.kalinin,b.v.rybakov,l.n.      
        samoilov,and v.a.sidorov,jetp(ussr)36,633(1959).          
    5.  j.h.gibbons and r.l.macklin,phys.rev.114,571(1959).       
    6.  los alamos physics and cryogenics groups,nucl.phys.12,    
        291(1959).                                                
    7.  j.e.brolley,jr.,t.m.putnam,l.rosen,and l.stewart,phys.    
        rev.159,777(1967).                                        
    8.  j.e.perry,private communication to stewart(1960)          
    9.  j.d.seagrave,l.cranberg,and j.e.simmons,phys.rev.119,     
        1981(1960)                                                
   10.  m.d.goldberg,j.d.anderson,j.p.stoering,and c.wong,phys.   
        rev.122,1510(1961).                                       
   11.  a.r.sayers,k.w.jones,and c.s.wu,phys.rev.122,1853(1961).  
   12.  w.e.wilson,r.l.walter,and d.b.fossan,nucl.phys.27,421     
        (1961).                                                   
   13.  j.als-nielsen and o.dietrich,phys.rev.133,b925(1964).     
   14.  r.l.macklin and j.h.gibbons,proceedings of the internatl. 
        conf.on the study of nucl.struct.with neuts.,antwerp(1965)
   15.  j.h.gibbons,private communication to stewart(1966).       
   16.  b.antolkovic,g.paic,p.tomas,and r.rendic,phys.rev.159,    
        777(1967).                                                
   17.  l.rosen and w.leland,private communication(1967)          
   18.  s.mughabghab et al., neut.cross sect., vol.1, neut.reson. 
        parameters and thermal cross sect., academic pr.(1981).   
                                                                  
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                        STANDARDS COVARIANCES                     
                                                                  
 Phase 1 reviewers of the ENDF/B-VI standards cross sections have 
 expressed the concern that the uncertainties resulting from the  
 combination of R-matrix and simultaneous evaluations might have  
 led to uncertainties that are too small.  As a result, the       
 Standards Subcommittee produced (at the May, 1990 CSEWG meeting) 
 a set of expanded covariance estimates for the standard cross    
 section reactions.  These uncertainties are estimates such that  
 if a modern day experiment were performed on a given standard    
 cross section using the best techniques, approximately 2/3 of    
 the results should fall within these expanded uncertainties. The 
 expanded uncertainties for the He-3(n,p) cross section are as    
 follows:                                                         
                                                                  
    Energy Range          Estimated Uncertainty                   
      (keV)                  (percent)                            
                                                                  
 1.0E-08 - 0.1                  0.3                               
     0.1 - 1.0                  0.7                               
     1.0 - 10.                  2.0                               
     10. - 50.                  5.0                               
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