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核废料地质处置库中混凝土工程屏障中钙浸出及其对迁移放射性核素的影响的建模。

Modelling of calcium leaching and its influence on radionuclide migration across the concrete engineered barrier in a NSDF.

机构信息

Safety Research Institute, Atomic Energy Regulatory Board (AERB), IGCAR, Kalpakkam 603 102, India.

出版信息

J Environ Radioact. 2013 Oct;124:93-100. doi: 10.1016/j.jenvrad.2013.04.009. Epub 2013 May 14.

Abstract

A multi barrier concept of disposal is adopted for both low and intermediate level radioactive waste disposal to prevent the spread of radionuclides into the human environment. Concrete engineered barrier is a part of multi barrier system for radioactive waste disposal. As long as the concrete barrier is intact, the containment of radioactive waste within the disposal facility is assured. However, every concrete structure has a finite lifetime. Concrete barriers degrade with time with lifetime dependent on type of concrete, external and internal environmental factors. This degradation allows the free moment of the radionuclides out of the concrete barrier. Hence an attempt was made to model the Calcium (Ca) leaching from side wall of a concrete engineered barrier in a Near Surface Disposal Facility (NSDF) and its influence on radionuclide migration across the concrete barrier, limited to conditions specified in the paper. The conceptual model assumes that rain water seeps into the engineered barrier through the top cover and dissolves radionuclides from the nuclear waste matrix. The modelling was attempted with Finite Difference analysis and validated with the results available in literature. The influence of Ca leaching on radionuclide migration in concrete barrier has been discussed for eight different radionuclides (Cs-137, Sr-90, I-129, H-3, Pu-239, Am-241, Co-60 and Tc-99).

摘要

对于低放和中放废物处置,采用了多重屏障概念,以防止放射性核素扩散到人类环境中。混凝土工程屏障是放射性废物处置多屏障系统的一部分。只要混凝土屏障完好无损,处置设施内放射性废物的包容就有保证。然而,每个混凝土结构都有有限的寿命。混凝土屏障会随时间降解,其寿命取决于混凝土的类型、外部和内部环境因素。这种降解会使放射性核素自由逸出混凝土屏障。因此,尝试对近地表处置设施(NSDF)中混凝土工程屏障侧壁的钙浸出及其对穿过混凝土屏障的放射性核素迁移的影响进行建模,建模仅限于本文规定的条件。概念模型假设雨水通过顶盖渗入工程屏障,并溶解核废物基质中的放射性核素。采用有限差分分析进行了建模,并与文献中可用的结果进行了验证。讨论了钙浸出对八种不同放射性核素(Cs-137、Sr-90、I-129、H-3、Pu-239、Am-241、Co-60 和 Tc-99)在混凝土屏障中迁移的影响。

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