论文部分内容阅读
退役核燃料干式贮存设施主体由混凝土构成,混凝土得在长时期内承受残余核燃料释出的衰变热,加上台湾地区特殊的环境气候条件,混凝土材料可能产生劣化。依据核能安全混凝土结构物的材料规定的配比,我们制作了混凝土试样,用实验室模拟法研究干式贮存混凝土护箱在高温环境作用下可能出现的损害或劣化,甚至耐久性变差等。利用非破坏性检测方法(超音波试验、动弹性模数试验及反弹锤试验等),观察混凝土受持续高温作用下的结构致密性及内部是否产生裂缝,而影响混凝土的质量及耐久性安全。研究结果表明,混凝土干式贮存设施在高温(94℃)长期作用下,其抗压强度所受影响有限,不致损及混凝土结构承载之能力;其超音波波速及动弹性模数在初期会略有降低,而后趋于稳定;混凝土受热环境作用后体积产生收缩,且温度越高收缩量越大,但不随受热历时增加而再有明显收缩;就抵抗高温作用而言,添加卜作岚材料的混凝土优于纯水泥混凝土。
The main body of the decommissioned nuclear fuel dry storage facility is made of concrete. The concrete can withstand the decay heat released by the residual nuclear fuel for a long period of time. Coupled with the special environmental climatic conditions in Taiwan, the concrete material may be deteriorated. According to the stipulation of the ratio of material of nuclear energy-safe concrete structure, we made concrete samples, and used laboratory simulation method to study the possible damage or deterioration of dry-storage concrete box under the action of high temperature environment and even the deterioration of durability . Nondestructive testing methods (ultrasonic test, dynamic modulus test and rebound hammer test) were used to observe the structural densification and cracks in the concrete under continuous high temperature, which affected the quality and durability of the concrete. The results show that the compressive strength of dry-type concrete storage facilities has a limited impact under long-term high temperature (94 ℃), and will not damage the bearing capacity of concrete structures. The ultrasonic wave velocity and dynamic elastic modulus will be slightly reduced in the initial stage There is a decrease and then tends to be stable. After the concrete is heated by environment, the volume of the concrete shrinks, and the higher the shrinkage is, the greater the shrinkage is. However, the shrinkage is not obvious as the heating time increases. Pure cement concrete.