کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
833385 908142 2007 8 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Radiation damage on low activation materials used in a hybrid reactor
موضوعات مرتبط
مهندسی و علوم پایه سایر رشته های مهندسی مهندسی (عمومی)
پیش نمایش صفحه اول مقاله
Radiation damage on low activation materials used in a hybrid reactor
چکیده انگلیسی

Structural material selection in design of fusion–fission (hybrid) reactors is very crucial to enhance the neutronic performance. Low activation materials have important potential to be used in fusion or hybrid reactors. This study presents radiation damage behavior of the primary low activation materials namely, ferritic steel (9Cr–2VWTa), vanadium alloy (V–4Cr–4Ti) and SiCf/SiC composite used as first wall and fuel clad structural material in a (DT) fusion driven hybrid reactor under a NWL of 2 MW/m2 for a plant operation of 1 year. Calculations were performed by using the code, SCALE4.3 solving the Boltzmann neutron transport equation. Among the investigated materials V–4Cr–4Ti showed the best performance with respect to radiation damage.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Materials & Design - Volume 28, Issue 5, 2007, Pages 1453–1460
نویسندگان
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