Determining aqueous deuterium detection limits via infrared spectroscopy to understand its capabilities for real-time monitoring of tritiated water

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2024-08-31 DOI:10.1016/j.fusengdes.2024.114647

A. Cooper , T. Stokes , M. Irwin , E. Dixon , A. Wilson , G. Cefali

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引用次数: 0

Abstract

Tritiated water will be present in many demonstrator class fusion devices in a wide array of locations and concentrations. Accurate and fast measurement will be a key requirement to ensure suitable process monitoring, safety assurance and tritium tracking is in place. This work quantifies the deuterium detection limits achievable using a benchtop transmission Fourier transform infrared (FTIR) instrument and an industrialised attenuated total reflectance (ATR)-FTIR instrument to understand the capabilities of these techniques for real-time monitoring of aqueous tritium. Deuterium limits of detection of 4.62 × 10^-5 mol mL^-1 and 1.07 × 10^-3 mol mL^-1 were demonstrated with measurement times of 10s for the transmission FTIR and ATR-FTIR, respectively. These instruments are considered viable for the measurement of high concentration tritiated water and have many potential benefits associated with their deployment.

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通过红外光谱测定水体氘检测限，了解其对三价水的实时监测能力

氚水将以各种不同的位置和浓度出现在许多示范级聚变装置中。准确而快速的测量将是确保合适的过程监控、安全保证和氚跟踪到位的关键要求。这项工作对使用台式透射傅立叶变换红外（FTIR）仪器和工业化衰减全反射（ATR）-FTIR 仪器所能达到的氘检测限进行了量化，以了解这些技术对水氚进行实时监测的能力。透射 FTIR 和 ATR-FTIR 的氘检测限分别为 4.62 × 10-5 mol mL-1 和 1.07 × 10-3 mol mL-1，测量时间均为 10 秒。这些仪器被认为是测量高浓度氚水的可行方法，其部署具有许多潜在的好处。

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.