High-Purity Titanium,Zirconium And Hafnium In Nuclear-Power Engineering
Development of nuclear-power engineering is one of priorities in economic activity of the Russian Federation, which increases its power potential. The share of atomic power stations in power output of the Russian Federation makes 16. 7 ％ and will grow to 25％-30％ in prospect The service life of reactors must grow to 60 years. Up to 2030 optimized water-cooled power reactors (WWER) will remain the main type of nuclear reactors. At present prerequisites are established for introduction of high-efficiency fuel cycles on the existing atomic power stations with water-cooled power reactors. Introduction of such cycles is accompanied by increase of the service life, increase of fuel burn-up and coolant void fraction, growth of claddings temperature and strain in them. Titanium,zirconium,hafnium and alloys based on them are widely used in nuclear-power engineering as constructional and absorbing materials of slow neutron reactors.
M. Kotsar S. Lavrikov V. Nikonov A. Alexandrov A. Alexandrov S. Akhtonov
JSC Leading Scientific-Research Institute of Chemical Technology 33,Kashirskoye Shosse,Moscow,115 JSC Interstate Association Titan 3,Orshanskaya st.,Moscovu,121522 JSC Chepetsky Mechanical Plant,7,Belova,Glazov,427620,Russia
国际会议
The 12th World Conference Titanium(第十二届世界钛会 Ti-2011)
北京
英文
2237-2239
2011-06-19（万方平台首次上网日期，不代表论文的发表时间）