کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1740461 1521755 2015 9 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Neutronics evaluation of a super-deep-burn with TRU Fully Ceramic Microencapsulated (FCM) fuel in CANDU
کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Neutronics evaluation of a super-deep-burn with TRU Fully Ceramic Microencapsulated (FCM) fuel in CANDU
چکیده انگلیسی


• The FCM fuel was introduced to transmute the LWR TRUs in CANDU.
• The neutronics analysis was performed in a 2-D lattice with a Monte Carlo code.
• A super-deep-burn of over 70% burnup can be achieved by the TRU FCM fuel.
• Safety parameters of TRU FCM fuel are more favourable than those of natural U case.

One of the potential approaches for dealing with spent nuclear fuel in order to ensure the sustainable development of the nuclear energy is to fully utilize (transmute) the transuranics (TRU) in nuclear reactors. The CANDU reactor has an extremely high neutron economy which is necessary for an efficient TRU burning. The current CANDU fuel elements are unable to achieve the high burnup required to transmute the TRUs. In this paper, a special nuclear fuel called FCM (Fully Ceramic Microencapsulated) is introduced to achieve a super-deep-burn of the TRUs and to tackle the issue of fuel element integrity. In the FCM fuel, the conventional TRISO fuel particles are randomly dispersed in a fully dense SiC matrix and the FCM fuel is expected to be able to accommodate an extremely high burnup. The core performances and characteristics were analysed from the neutronics perspective through the fuel lattice analysis. The fuel depletion calculations were conducted using the Serpent Monte Carlo code and the fuel discharge burnup was determined based on the non-linear reactivity theory. Kinetic and major safety parameters including the fuel temperature coefficient, void reactivity, and coolant temperature coefficient were also evaluated.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Progress in Nuclear Energy - Volume 83, August 2015, Pages 261–269
نویسندگان
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