Trace Elements in Clinical Medicine 1990
DOI: 10.1007/978-4-431-68120-5_57
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A Guideline for Application of Neutron Activation Analysis to Biological and Medical Samples

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Cited by 3 publications
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“…Tritium is generated by neutron capture and inelastic scattering from beryllium nuclides and its content in the waste stream will depend on the applied waste treatment technologies. 7 Be is produced from beryllium by 9 Be(n,3n) 7 Be reaction 82 .…”
Section: Activation and Waste Index Results Of Beryllium Reflectormentioning
confidence: 99%
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“…Tritium is generated by neutron capture and inelastic scattering from beryllium nuclides and its content in the waste stream will depend on the applied waste treatment technologies. 7 Be is produced from beryllium by 9 Be(n,3n) 7 Be reaction 82 .…”
Section: Activation and Waste Index Results Of Beryllium Reflectormentioning
confidence: 99%
“…In order to assess the radionuclide inventory, simulation was performed with MCNPX2.7 49 using ENDF/B-VII cross section libraries coupled with CINDER'90 31 similarly to the method of statement 3. I showed that at shutdown after 1-year operation the most active gamma-emitting isotopes are 56 Mn (1.8×10 9 Bq/cm 3 ) and 7 Be (9.7×10 8 Bq/cm 3 ). The dose rate on the external surface of the beryllium reflector after 1-year irradiation time is 720 Sv/h at the end of operation, decreasing to 60 mSv/h after 2 weeks cooling time.…”
Section: Discussionmentioning
confidence: 99%
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