1GRENECHE D, MASSON M, BROSSARD P. The reproeessing issue for HTR fuels[C]//An Assessment of Its Interest and Its Feasibility:Global 2003. [S. l.]: [s. n.], 2003: 1 309-1 317.
2BRADLEY M J, FERRIS L M. Recovering uranium from graphite fuel elements[J]. Ind Eng Chem, 1961, S3(4): 279-281.
3FERRIS L M. Mellitic acid from the oxidation of graphite with 90% nitric acid[J].J Chem Eng Data, 1964, 9(3): 387-388.
4HAAS P, FERRIS L. Dissolution of graphited base reactor fuels by pressurized aqueous processes [J]. I & E C Process Design and Development, 1966, 5(3): 234-238.
5MAEDA M, TSUJINO T, IWAMOTO K. Process study on advanced graphite-burn method for head-end step of HTR fuel reprocessing[C]// Specialists' Meeting on Gas-Cooled Reactor Fuel Development and Spent Fuel Treatment, Moscow (Russian Federation), 1983. Moscow: [s. n. ], 1983: 345-356.
6ZIMME E, MERZ E. Chemical processing of HTR fuels applying either THOREX or PUREX flow sheets[C]//Specialists' Meeting on Gas- Cooled Reactor Fuel Development and Spent Fuel Treatment, Moscow ( Russian Federation ), 1983. Moscow: [s.n.], 1983: 333-344.
7LOTTS A L, BONDS W D, FORSBERG C W, et al. Options for treating high-temperature gascooled reactor fuel for repository disposal, Oak Ridge Tennessee 37831 [R]. Las Vegas, Nevada: Oak Ridge National Laboratory, 1992.
8FORSBERG C W, DELCUL G D, SPENCER B B, et al. A new repository waste form: Graphitecarbon high-level waste[C]//International High- Level Radioactive Waste Management Conference. Las Vegas, Nevada: Oak Ridge National Laboratory, 2003.
9MASSON M, GRANDJEAN S. HTGR spent fuels processing: The CEA investigation program [C]//Proceedings of the Conference on High Temperature Reactors. Beijing, China:[s. n. ], 2004 : 22-24.
10SAWA K, YOSHIMUTA S, SHIOZAWA S, et al. Study on storage and reprocessing concept of the high temperature engineering test reactor (HTTR) fuel[R/OL]. Vienna, Austria: IAEA, 1998[2007-01-30]. http://www-pub. iaea. org/ MTCD/ publications/PDF/ngwm- cd/PDF-Files/ paper%208%20(Fuji).pdf.
