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Determining the Specific Activity of Carbon-14 in Samples of Irradiated Mixed Nitride Uranium-Plutonium Nuclear Fuel
Radiochemistry Pub Date : 2021-07-08 , DOI: 10.1134/s1066362221030140
V. N. Momotov 1 , E. A. Erin 1 , A. Yu. Volkov 1 , D. E. Tikhonova 1 , A. S. Kupriyanov 1 , A. Yu. Shadrin 2
Affiliation  

Abstract

A procedure for determining the specific activity of carbon-14 in samples of irradiated nuclear fuel (INF) has been developed and metrologically certified. The procedure is based on oxidation of 14C to 14CO2 and its catching with alkaline traps, followed by determination of its β-activity by the method of liquid-scintillation counting (LSC). The specific activity of 14C was determined in two samples of mixed nitride uranium-plutonium (MNUP) fuel irradiated in a BN-600 reactor.



中文翻译:

确定辐照混合氮化物铀钚核燃料样品中碳 14 的比活度

摘要

已开发出确定辐照核燃料 (INF) 样品中碳 14 比活度的程序并通过了计量认证。该程序基于将14 C氧化为14 CO 2并用碱性捕集器对其进行捕获,然后通过液体闪烁计数 (LSC) 方法测定其 β 活性。在 BN-600 反应堆中辐照的两个混合氮化物铀钚 (MNUP) 燃料样品中测定了14 C的比活度。

更新日期:2021-07-08
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