Author:
Orlova Ekaterina,Samokhin Dmitry,Holkin Ivan
Reference8 articles.
1. Adamov Е.О., Orlov V.V., Smirnov V.S. «Progress in lead cooled fast reactor design //Proc. Intern. Conf. on Design and Safety of Advanced Nuclear Power Plants». Tokyo, Japan, Oct. 25-29, 1992. v.2. Paper №16-6. 1-4.
2. Kordyukov A.G., Leonov V.N., Pikalov A.A. et al. (2004). «Testing of the BREST-OD-300 reactor mock-up fuel elements in a standalone lead cooled channel of the BOR-60 reactor». Atomnaya energiya. 97. (2). 131-138 (in Russian).
3. Belyayeva A.V., Kryukov F.N., Nikitin O.N. et al. (2012) «Key results of the uranium-plutonium nitride fuel examination after irradiation in the BOR-60 reactor» Book of reports at the International Scientific and Technical Conference “Innovative Designs and Technologies of Nuclear Power”, 27-29 November 2012. Moscow: NIKIET, 2012. P. 223-228 (in Russian).
4. Orlova E.A., Gurbich A.F., Molodtsov S.L., Orlov V.V., Bozin C.N., Bashkin A.V. (2008) «Formation and study of protective coatings compatible with nitride fuel on ferrite-martensite steels» Atomnaya energiya. 105 (5) 269-274 (in Russian).
5. Orlova E.A., Orlov Yu.I., Kryuchkov E.A., Komyshny V.N., Zhmurin V.G., Zagrebayev S.A., Kotovskiy N.A., Dvortsevoy V.G. (2015) «Self-organizing carbonitride coating of melted lead-magnesium eutectic on steel». Izvestiya vuzov. Yadernaya energetika. (1). 45-55 (in Russian).