کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
297664 511763 2011 8 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
New fuel rod design based on LEU/Th fuel and an assessment on in-core fuel cycle length of the MHR core
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
New fuel rod design based on LEU/Th fuel and an assessment on in-core fuel cycle length of the MHR core
چکیده انگلیسی

The current Modular Helium Reactor (MHR) fuel cycle uses fissile LEU (19.8 wt% U-235) and depleted uranium in separate TRISO particles, in a single fuel rod within a graphite matrix. The TRISO particle volume packing fraction (PF) in the fuel rods is 29%, of which the LEU particle PF is 62%. The lifetime between refuelings is about 476 effective full power days (EFPD). In this paper we assess the possibility of replacing the depleted uranium TRISO particles with thorium TRISO particles, and evaluate the impact of such replacement on fuel cycle length. A preliminary scoping study was performed to determine the most promising fuel rod/zoning configurations. The scoping study indicates that there is advantage to separating the thorium TRISO particles from the LEU particles at the fuel rod level instead of mixing them within a single rod. An axial checkerboard distribution of the fuel rods where all uranium and all thorium rods are interchangeable along the axial direction within the graphite block is the most promising configuration that was identified in this study and can be lead to a fuel cycle length extension of 50–80% relative to the current design, with only a modest increase in the fissile material loading (15–20%). To this advantage can be added the benefit of a significant reduction in nuclear waste and in health risk. This study also lays the foundation for improving the fuel rod arrangement within the graphite block and the graphite blocks within the entire reactor core. The analysis is limited to a once – through fuel cycle based on in situ fissioning of the U-233, without further separation and reprocessing. The preliminary heat transfer analysis indicates that the maximum temperature in the fuel will be raised by about 10–15% over that of current MHR design.

Research highlights▶ Improving fuel utilization in the gas cooled reactor. ▶ New geometrical rod configurations of fertile and fissile TRISO particles extending fuel cycle. ▶ Axial checkerboard configuration is a promising one for fuel life extension. ▶ Longer fuel cycles can be achieved by replacing the natural uranium particles with thorium particles. ▶ Higher burnup and use of thorium improved the waste form for storage and transportation.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 241, Issue 1, January 2011, Pages 185–192
نویسندگان
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