کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
299548 511865 2005 19 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Transient thermal–hydraulic simulations of direct cycle gas cooled reactors
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Transient thermal–hydraulic simulations of direct cycle gas cooled reactors
چکیده انگلیسی

This work concerns the design and safety analysis of gas cooled reactors. The CATHARE code is used to test the design and safety of two different concepts, a High Temperature Gas Reactor concept (HTGR) and a Gas Fast Reactor concept (GFR). Relative to the HTGR concept, three transient simulations are performed and described in this paper: loss of electrical load without turbo-machine trip, 10 in. cold duct break, 10 in. break in cold duct combined with a tube rupture of a cooling exchanger. A second step consists in modelling a GFR concept. A nominal steady state situation at a power of 600 MW is obtained and first transient simulations are carried out to study decay heat removal situations after primary loop depressurisation. The turbo-machine contribution is discussed and can offer a help or an alternative to “active” heat extraction systems.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 235, Issue 23, December 2005, Pages 2527–2545
نویسندگان
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