Decommissioning industrial uranium-graphite reactorsSoviet Atomic Energy - Tập 87 - Trang 569-576 - 1999
I. D. Kulikov, V. D. Safutin, V. M. Simanovskii, M. I. Abramov, B. K. Bylkin, Yu. A. Zverkov, N. E. Kukharkin, V. V. Vainshtein, B. A. Pyatunin, Yu. I. Kabanov, V. M. Kondakov, A. G. Nikolaev
The basic problems in decommissioning industrial uranium-graphite reactors are analyzed, taking account of experience in decommissioning the I-1 and ÉI-2 reactors at the Siberian Chemical Combine. On the basis of the analysis, decommissioning with delayed dismantling of the reactor structures is recommended.
Environmental radioactivitySoviet Atomic Energy - Tập 33 - Trang 760-765 - 1972
L. I. Gedeonov
Studies of radioactive contamination of various media in the biosphere carried out at the Radium Institute over many years have made it possible to develop methods of investigation which are widely applicable at the present time. A large amount of data has been accumulated on the distribution of radioactive contaminants in space and on the variation of their concentration in time. Certain relation...... hiện toàn bộ
High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen ProductionSoviet Atomic Energy - Tập 116 - Trang 241-251 - 2014
E. A. Orlova, A. V. Morozov, V. V. Alekseev, V. Yu. Stogov, G. P. Bogoslovskaya, A. P. Sorokin, F. A. Kozlov, A. P. Ivanov, M. A. Konovalov, S. G. Kalyakin
Studies show that in principle it is possible by relying on the BN-600 design to secure the required parameters of a reactor setup with a fast reactor with high-temperature sodium coolant (BN-VT) for hydrogen production. The calculations for 600 MW(t) BN-VT for electricity and hydrogen production based on solid-oxide electrolysis of water taking account of a fundamentally different method of purif...... hiện toàn bộ