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Results 1 - 10 of about 25995. Search took: 1.21 seconds.
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Characteristics of high-pressure mixtures of CO2-TBP-UO2(NO3)2HNO3-H2O for actinide extraction from solid matrices with supercritical fluid
by Sawada, K.; Koyamal, T.; Shimada, T.; Mori, Y.; Enokidal, Y.; Nagoya University, Chikusa-ku, Nagoya-shi, Aichi-ken 4648603 (Japan); Japan Nuclear Cycle Development Institute, 4-49, Muramatsu, Tokai-mura, Naka-gun, Ibaraki, 319-1184 (Japan); Mitsubishi Heavy Industries, Ltd., 5007, Itozaki-cho, Mihara, Hiroshima 729-0393 (Japan)
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Spent fuel management newsletter. No. 2
1 MB - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/32/047/32047901.pdf - Text Version
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Independent Review and Analysis of the Safety Class Helium System 30-LB Safety Relief Valve and Vent Path, Tempered Water System and Process Water Conditioning Sysen at the Cold Vacuum Drying Facility
2 MB - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/34/007/34007546.pdf - Text Version
by HEARD, F.J.; NHC (US). Funding organisation: ENVIRONMENTAL MANAGEMENT (United States)
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Comparative study for axial and radial shuffling scheme effect on the performance of Pb-Bi cooled fast reactors with natural uranium as fuel cycle input
by Zaki Suud; Indah Rosidah; Maryam Afifah (Nuclear Research Group, FMIPA, Bandung Institute of Technology, Jl. Ganesha 10, Bandung (Indonesia)); Ferhat Aziz (National Atomic Energy Agency (BATAN) (Indonesia)); Sekimoto, H. (Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology (Japan)), E-mail: szaki@fi.itb.ac.id
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Advanced fuel cycles of WWER-1000 reactors
309 KB - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/36/040/36040494.pdf - Text Version
by Lunin, G.; Novikov, A.; Pavlov, V.; Pavlovichev, A. (RRC Kurchatov Institute, Moscow (Russian Federation))
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Quantification of fluoride from radioactive liquid wastes by pyrohydrolysis separation and ion chromatography
by Sawant, R.M.; Mahajan, M.A.; Shah, D.J.; Thakur, U.K.; Tomar, B.S.; Ramakumar, K.L. (Radioanalytical Chemistry Division, Bhabha Atomic Research Centre, Mumbai (India))
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HIGH SENSITIVITY NEUTRON ASSAY OF GROUTED SPENT NUCLEAR FUEL SLUDGE AT HANFORD
https://www.osti.gov/servlets/purl/919248-Vv1Auq/
by ABDURRAHMAN, NM; Hanford Site HNF, Richland, WA (United States). Funding organisation: USDOE - Office of Environmental Management EM (United States)
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Recovery of uranium from phosphoric acid medium by polymeric composite beads encapsulating organophosphorus extractants
by Singh, D.K.; Yadav, K.K.; Varshney, L.; Singh, H. (Bhabha Atomic Research Centre, Mumbai 400 085 (India))
fromProceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads
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A view of treatment process of melted nuclear fuel on a severe accident plant using a molten salt system
by Fujita, R.; Takahashi, Y.; Nakamura, H.; Mizuguchi, K. (Power and Industrial Research and Development Center, Toshiba Corporation Power Systems Company, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki 210-0862 (Japan)); Oomori, T. (Chemical System Design and Engineering Department, Toshiba Corporation Power Systems Company, 8 Shinsugita-cho, Isogo-ku, Yokohama 235-8523 (Japan))
fromProceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads
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