Rapid analysis of 14C and 3H in graphite and concrete for decommissioning of nuclear reactor

Author:

Hou Xiaolin

Publisher

Elsevier BV

Subject

Radiation

Reference20 articles.

1. Radiochemical characterization of graphite from Julich experiment reactor (AVR);Bisplinghoff;Nuclear Energy,1999

2. Brodersen, K., 2003. Interpretation of measurements on graphite from DR2 and method for estimating integrated flux. Technical Report, Risø National Laboratory.

3. Quantitative determination of the amounts of 3H and 14C in reactor graphite;Bushuev;Atomic Energy,1992

4. Bushuev, A.V., Verzilov, Yu.M., Zubarev, V.M., Kachanovskii, A.E., Proshin, I.M., Petrova, E.V., Aleeva, T.B., Samarkin, A.A., Silin, B.G., Dmitriev, A.M., Zakharova, E.V., Ushakov, S.I., Baranov, I.I., Kabanov, Yu.I., Kolobova, E.N., Nikolaev, A.G., 1999. Radionuclide characterization of graphite stacks from plutonium production reactors of the Siberian group of chemical enterprises. Proceedings of a Technical Committee Meeting, Manchester, UK, Nuclear Graphite Waste Management, IAEA-NGWM/CD-01.

5. Determination of total C-14 residues of sarafloxacin in eggs of laying hens, J;Chu;Agric. Food Chemistry,2000

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