Radiation effects in concrete for nuclear power plants - Part I: Quantification of radiation exposure and radiation effects

被引:140
作者
Field, K. G. [1 ]
Remec, I. [1 ]
Le Pape, Y. [1 ]
机构
[1] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
关键词
HIGH-TEMPERATURE; GAMMA-RADIATION; STRENGTH; AMORPHIZATION; QUARTZ; DAMAGE; IRRADIATION;
D O I
10.1016/j.nucengdes.2014.10.003
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A large fraction of light water reactor (LWR) construction utilizes concrete, including safety-related structures such as the biological shielding and containment building. Concrete is an inherently complex material, with the properties of concrete structures changing over their lifetime due to the intrinsic nature of concrete and influences from local environment. As concrete structures within LWRs age, the total neutron fluence exposure of the components, in particular the biological shield, can increase to levels where deleterious effects are introduced as a result of neutron irradiation. This work summarizes the current state of the art on irradiated concrete, including a review of the current literature and estimates the total neutron fluence expected in biological shields in typical LWR configurations. It was found a first-order mechanism for loss of mechanical properties of irradiated concrete is due to radiation-induced swelling of aggregates, which leads to volumetric expansion of the concrete. This phenomena is estimated to occur near the end of life of biological shield components in LWRs based on calculations of estimated peak neutron fluence in the shield after 80 years of operation. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:126 / 143
页数:18
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