화학공학소재연구정보센터
검색결과 : 7건
No. Article
1 Corrosion in the molten fluoride and chloride salts and materials development for nuclear applications
Guo SQ, Zhang JS, Wu W, Zhou WT
PROGRESS IN MATERIALS SCIENCE, 97, 448, 2018
2 Experimental study on thermal hazard of tributyl phosphate-nitric acid mixtures using micro calorimeter technique
Sun Q, Jiang L, Gong L, Sun JH
Journal of Hazardous Materials, 314, 230, 2016
3 How can Korea secure uranium enrichment and spent fuel reprocessing rights?
Roh S, Kim W
Energy Policy, 68, 195, 2014
4 Optimization of Flowsheet for Scrubbing of Ruthenium during the Reprocessing of Fast Reactor Spent Fuels
Natarajan R, Dhamodharan K, Sharma PK, Pugazhendi S, Vijayakumar V, Pandey NK, Rao RVS
Separation Science and Technology, 48(16), 2494, 2013
5 China's spent nuclear fuel management: Current practices and future strategies
Zhou Y
Energy Policy, 39(7), 4360, 2011
6 Single and binary component sorption of the fission products Sr2+, Cs+ and Co2+ from aqueous solutions onto sulphate reducing bacteria
Ngwenya N, Chirwa EMN
Minerals Engineering, 23(6), 463, 2010
7 Studies on the Development of a Flow-Sheet for AHWR Spent Fuel Reprocessing Using TBP
Dhami PS, Jagasia P, Panja S, Achuthan PV, Tripathi SC, Munshi SK, Dey PK
Separation Science and Technology, 45(8), 1147, 2010