Neutronic analysis of mixed thorium-uranium fuel bundle for CANDU reactors
نویسندگان
چکیده
منابع مشابه
محاسبات مصرف سوخت و پارامترهای نوترونیک مربوط به رآکتورهای آب سنگین تحقیقاتی با سوخت اورانیوم- توریوم توسط کد MCNPX
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ژورنال
عنوان ژورنال: IOP Conference Series: Earth and Environmental Science
سال: 2019
ISSN: 1755-1315
DOI: 10.1088/1755-1315/214/1/012024