|کد مقاله||کد نشریه||سال انتشار||مقاله انگلیسی||ترجمه فارسی||نسخه تمام متن|
|366570||621451||2015||4 صفحه PDF||سفارش دهید||دانلود رایگان|
The possibility is examined to develop fast reactor for the purpose of implementation of research, education of undergraduate and doctoral students in handling innovative fast reactors and training specialists for atomic research centers and nuclear power plants. Main characteristics of liquid lead-cooled reactor using commercially implemented uranium dioxide with 19.7% enrichment with 235 U isotope as the fuel load are examined. Hard neutron spectrum achieved in the fast reactor with compact core and natural lead coolant and, in longer term perspective, cooled with lead enriched with 208 Pb isotope will allow addressing a number of research tasks under fast neutron flux densities of the order of 1013 neutrons/(cm2 s). Relatively low thermal power equal to 0.5 MW is envisaged for the purpose of safe handling of the reactor. Possibility of prompt neutron runaway of the reactor is excluded due to the low reactivity margin which is less than the effective fraction of delayed neutrons. The studies are implemented based on the experience of development of low-power reactors available at the INPE NRNC “MEPhI”, as well as on the experience gained at the Joint-Stock Company “SSC RF-IPPE” in the field of development of fast reactors cooled with heavy liquid metal.
Journal: Nuclear Energy and Technology - Volume 1, Issue 3, November 2015, Pages 191–194