А. М. Дмитриев
Publications by Year
Research Areas
Graphite, nuclear technology, radiation studies, Nuclear reactor physics and engineering, Nuclear and radioactivity studies, Nuclear Materials and Properties, Radioactive element chemistry and processing
Most-Cited Works
- → Feasibility of Converting Russian Icebreaker Reactors from HEU to LEU Fuel(2006)35 cited
- → Fission Products and Actinides in Spent Graphite Masonry of the Reactors at the Siberian Chemical Combine(2000)12 cited
- → Experimental Study of the Radioactive Contamination of Graphite Masonry in the Commercial Reactors at the Siberian Chemical Combine(2002)11 cited
- → Experimental Determination of the Spent Graphite Radioactive Contamination at Plutonium-Production Reactors of the Siberian Group of Chemical Enterprises (TOMSK-7)(2002)10 cited
- → Investigation of the thermal inertia and thermal stresses of heat-transferring elements in a solid-coolant nuclear reactor(2011)9 cited
- → Converting Russian plutonium‐production reactors to civilian use(1994)6 cited
- → Some Results of an Investigation and Prospects for the Development of a High-Temperature Power Reactor with a Solid Coolant(2005)4 cited
- → Concept and salient design features of a high-temperature nuclear reactor with solid coolant(2007)4 cited
- → 60Co content in the spent graphite masonry of commercial reactors at the siberian chemical combine(1999)2 cited
- → Evaluation of the technological parameters of a high-temperature reactor with solid coolant in the electricity generating regime(2008)2 cited