Safety_Series_041_1975 - gnssn - International Atomic Energy ...

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This publication is no longer valid Please see http://www.ns-iaea.org/standards/ 42 APPENDIX I maintained. The la b ora tories should maintain uniform m inim um detectable le v e l capabilities and should routinely take part in in te r laboratory quality con trol p rogra m m es. A minimum quality con trol frequency of 10% o f all nuclide analysis, including in-house blanks, standards and splits is recom m ended. A nalytical con trol m ethods generally include cro ss-ch e ck in g or splitting sam ples with a con trol laboratory. A c r o s s -c h e c k involves the analyses o f sam ples provided by the con trol laboratory and com parison o f the resu lts with those of the con trol laboratory as w ell as with other la b ora tories that receiv ed portions of the sam e sam ples. Splitting a sam ple involves obtaining two iden tical sam ples from a single collection , one sam ple being, analysed by the m on i toring laboratory and the other by the con trol la b oratory, with subsequent com p arison of resu lts. When splitting sam ples for interlaboratory com p a rison , it is very im portant that both sam ples parts are represen tative of the m edia in question. Some typical analytical m ethods and the associated detection capabilities are illu strated in Tables I and II. REPORTING PROCEDURES R eporting of data should be done follow ing a clea r and uniform form at suitable for autom atic data p rocessin g . ' The reported inform ation should generally include the follow ing inform ation: (1) G eographic location of sam ple site (2) Sample type (m edia) (3) Sample num ber (optional) (4) Identification o r organization o r person collecting the sample (5) Identification of organization analysing the sam ple (6) Tim e and date sam ple was taken (include duration of sam ple period for integrated sam ples) (7) Sample preparation as appropriate (e. g. concentration or wet versu s dry) (8) Type o f analysis p erform ed (9) Value and units for each analysis and associated 2-sigm a e rro r (10) P aram eters needed to calculate decay of sam ple p rio r to analysis where sh ort-liv ed radionuclides are involved (11) Any known events that may have affected the analytical resu lts. Much o f the above inform ation, such as sam ple site location and organization iden tification , can be coded to reduce the re co rd volum e.
This publication is no longer valid Please see http://www.ns-iaea.org/standards/ APPENDIX I 43 T ABLE I. A N A LYTIC A L METHODS FOR ROUTINE ENVIRONMENTAL RADIOACTIVITY SURVEILLANCE [15] M edium Code A nalytical method G am m a-spectrom etry for 131I o f air filters or cartridge samples D osim eter-external exposure C ryogenic separation and liquid scintillation counting Determ ination o f tritium in water Gross beta counting o f air filters Oxalate precipitation C obalt and nickel Gam m a analysis in water C aesium -phosphom olybdate-chloroplatinate m ethod Radioactive manganese (ASTM D 2039-69) Radioactive iron (ASTM D2461-69) Radioactive iodine distillation (ASTM D2334-68) Zircon iu m - niobium - 95 Basic carbonate m ethod Radioactive barium (ASTM D 2038-68) Radioactive tritium (ASTM D 2476-69) Determ ination o f tritium in water Distillation m e th od -tritiu m C arbon -14—distillation to C a C 0 3 Basic carbonate m ethod for saline water Radiostrontium in saline water Oxalate precipitation method TBP extraction (90Sr) D ifference m ethod (90Sr) Carbonate 14C by liquid scintillation counting I o d in e -131 by ion exchange and precipitation Reference m ethod - TBP extraction TC A precipitation m ethod - nitric acid separation Ion-exchange procedure - TBP extraction Batch ion -ex ch ange procedure - TBP extraction G am m a-spectrom etry on m ilk G am m a-spectrom etry o f soft tissue Radioactive iron (ASTM D 2461-69) T T A extraction method TBP extraction m ethod HDEHP extraction method
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