节点文献
反应堆退役废物中氚含量的测定方法研究
DETERMINATION OF TRITIUM CONTENT INREACTOR DECOMMISSIONING WASTE
【摘要】 本文介绍了反应堆退役废物如不锈钢、碳钢锈垢、合金铝和水池底泥固体样品介质中氚含量的测定方法。建立了高温加湿解析、催化氧化、鼓泡器收集的分析方法,并对该方法中有关参数的确定及测量结果的准确性进行了讨论。
【Abstract】 A determination method of tritium content in solid material samples such asstainless steel,carbon steel rust,scrap aluminium alloy and scale and sediment deposit instorage water pool is studied experimentally by wet-outgassing at high temperature,catalysoxidation and bubbler collection,the parameters involved in this method and the detinitnesof measurement results are discussed also in this paper.
【关键词】 反应堆;
退役废物;
氚;
含量;
测定;
【Key words】 Tritium Facility Decommissioning; Tritium Decontamination; Tritium Content Measment.;
【Key words】 Tritium Facility Decommissioning; Tritium Decontamination; Tritium Content Measment.;
- 【文献出处】 辐射防护 ,PADIATION PROTECTION , 编辑部邮箱 ,1996年03期
- 【分类号】TL943
- 【被引频次】8
- 【下载频次】156