Page 252 - Inorganic Mass Spectrometry - Fundamentals and Applications
P. 252

238                                                          Smith


                                                                          of
           0.1 % to 0.5% [49]. The same  laboratory  measured  part  per  million  (ppm)  levels
           iron  in  zirconium  using  isotope  dilution  [SO]; the study  was  aimed at elucidating
            the defo~ation effects of iron  contamination  in  alloys  used  in  reactors.  In  both
                                                       for
           these  studies,  mass  spectrometers  specifically  designed the measurement of iso-
            tope ratios were  used,  and  thermal  ionization  was  employed to generate the ion
            beams.
                                                    to
                In a different  application  not  directly  related nuclear  matters  but  nonethe-
            less addressing a similar  problem,  Beer  and  Heumann  used  isotope  dilution  to
            quantify  trace  levels of U, Th, Cu, Lb, Cd,  Cr,  Ni,  and  Fe  in  titanium, a metal  ex-
            tensively  used  in  the  microelectronics  industry,  in  which  purity critical import-
                                                              of
                                                             is
            ance [S l]. Detection  limits  ranged  from 0.07 ngg for U and  Th  to 35 ndg for Fe.
                An example of  what  one  might  call  “double”  isotope  dilution  was  reported
            by Smith et al. [52]. The specific  problem  addressed  was the dete~nation of the
            quantity of material  (either by weight or volume)  in  holding  tanks  in the nuclear
            fuel cycle.  Safeguards  require  establishing material  balance for these  tanks,  which
                                             a
            contain  solutions of  spent  reactor fuel and,  being  highly  radioactive,  constitute a
            hostile  matrix. The method is a general  one,  however,  and  can be applied to any
            situation  in  which the amount of solution is desired. The method  involves  adding
            a known  amount of natural  lutetium  to the tank;  this  was the first  spike.  Lutetium
            was  chosen  because it was  not  present  in  the  sample  solutions  and well  behaved
                                                                is
            under  thermal  ionization; other elements  could of course be used.  After  addition
                                of
            of the  spike,  the  contents the tank  were  thoroughly  mixed.  An  aliquot  was  with-
            drawn  and a lutetium  spike of enriched 176L,u (the  second  spike)  added.  Isotope di-
            lution analysis  via  thermal  ionization  mass  spectrometry  was  carried out; knowl-
                                                 the
            edge of the  amount of natural  lutetium  added  to tank  and its conc~ntration made
            calculation of the  amount of solution  in  the  tank  simple.  Precision  and  accuracy
                                                                           of
            about 0.5%, superior to those of other  methods of tank  calibration [53], were  ob-
            tained.





            It is with  considerable  gratification to the  author  that  preparation of this  chapter
            brought  home  the  realization  that in his  professional  lifetime  isotope  dilution  has
                                               by
            moved  from a recondite  technique  used  only a few initiates into the mainstream
            of analytical  science,  making  valuable  contributions a multitude of fields  as  dis-
                                                     in
            parate  as  the  nuclear fuel cycle  and the workings of the  human  body.




             1.  Inghram, M. G.; Hayden,  R. J.   and book on Mass Spe~tros~o~~, Nuclear  Series,  Re-
                port No. 14, NRC-USA, 1954.
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