1. Radiochemical characterization of graphite from Julich experiment reactor (AVR);Bisplinghoff;Nucl. Energy,1999
2. Limits for qualitative detection and quantitative determination;Currie;Anal. Chem.,1968
3. Hong, Sang Bum, 2005. Technology development of irradiated graphite waste treatment for the decommissioning of research reactor in KAERI. In:Proceedings of KAPC-KAERI Decommissioning Technology Seminar
4. Rapid analysis of 14C and 3H in graphite and concrete for decommissioning of nuclear reactor;Hou;Appl. Radiat. Isot.,2005
5. IAEA, 1992. Application of Exemption Principles to the Recycle and Reuse of Materials from Nuclear Facilities. IAEA Safety Series No. 111-P-1.1, IAEA, Vienna, p. 97.