摘要
铝基碳化硼是一种新型的乏燃料贮存格架用材料,为检验其辐照性能,需进行堆内辐照实验。本文从样品成分及形状、辐照罐结构、辐照位置等方面,对铝基碳化硼材料堆内辐照方案进行设计。经初步中子物理学和热工计算表明:在所选择的两个辐照孔道内进行辐照考验,试件所接受的累积γ射线照射剂量和相应的快中子积分注量均满足技术要求,且辐照罐样品入堆后对功率峰值因子、反应性、发热率等与堆运行安全相关因子的影响均在安全范围内。
As a new candidate for spent fuel storage framework material,in-core irradiation test for aluminum matrix boron carbide（B4C） was performed to evaluate its irradiation behavior.The experiment was designed and analyzed according to sample＇s composition and shape,irradiation box characters,and core arrangement.The neutronic and thermal hydraulic simulations indicate that the scheme of the experiment chosen can meet the requirement of all parameters,such as γ dose,integral fast neutron flux,power peaking factor,core reactivity,and sample heating rate.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2012年第B09期440-444,共5页
Atomic Energy Science and Technology
基金
国家自然科学基金资助项目(11175162)
关键词
碳化硼
辐照
安全
B4C
irradiation
safety
