کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1740559 1521761 2014 19 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
A summary of sodium-cooled fast reactor development
ترجمه فارسی عنوان
خلاصه ای از توسعه راکتور سریع سدیم سرد
کلمات کلیدی
راکتور سریع سدیم خنک کننده، چرخه سوخت بسته مدیریت اقلیمی کوچک، بهبود عملکرد ایمنی، تجربه توسعه بلند مدت، انجمن جهانی چهارم،
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
چکیده انگلیسی
Much of the basic technology for the Sodium-cooled fast Reactor (SFR) has been established through long term development experience with former fast reactor programs, and is being confirmed by the Phénix end-of-life tests in France, the restart of Monju in Japan, the lifetime extension of BN-600 in Russia, and the startup of the China Experimental Fast Reactor in China. Planned startup in 2014 for new SFRs: BN-800 in Russia and PFBR in India, will further enhance the confirmation of the SFR basic technology. Nowadays, the SFR development has advanced to aiming at establishment of the Generation-IV system which is dedicated to sustainable energy generation and actinide management, and several advanced SFR concepts are under development such as PRISM, JSFR, ASTRID, PGSFR, BN-1200, and CFR-600. Generation-IV International Forum is an international collaboration framework where various R&D activities are progressing on design of system and component, safety and operation, advanced fuel, and actinide cycle for the Generation-IV SFR development, and will play a beneficial role of promoting them thorough providing an opportunity to share the past experience and the latest data of design and R&D among countries developing SFR.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Progress in Nuclear Energy - Volume 77, November 2014, Pages 247-265
نویسندگان
, , , , , , , ,