کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
9638361 505055 2005 5 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Neutronic analysis of ITER neutral beam test bed
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Neutronic analysis of ITER neutral beam test bed
چکیده انگلیسی
The neutron dose arising during the operation of the ITER neutral beam test bed was calculated using the Monte-Carlo code MCNP. The activation of the injector components was determined using the inventory code FISPACT and the resultant gamma ray doses at the end of the test programme were determined. It is found that there would be a neutron dose during beam operations sufficient to entail restricted and monitored access to areas outside the shield wall. A careful assessment of the shielding is needed. The individual components of the injector are generally not activated excessively, i.e. their activation levels fall below the hands on limit within 1 year. However, the total gamma dose close to the vessel is substantially higher than any individual contact dose. This must be taken into consideration in maintenance planning.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Fusion Engineering and Design - Volume 74, Issues 1–4, November 2005, Pages 461-465
نویسندگان
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