用于第四代核反应堆的高贫化锂循环分析

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

Nuclear Engineering and Design Pub Date : 2024-10-29 DOI:10.1016/j.nucengdes.2024.113664

Sean R. Scott , Johnny Williams , Sara Mastromarino , Norbert Gajos , Christian Berry , Ian Anderson , Steven Shen , Trent R. Graham , Cole Hexel , Josh Wimpenny , Jacob Brookhart , Alan Kruizenga

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引用次数: 0

摘要

目前还没有含有非天然高丰度 7Li 的锂参考材料，这给第四代核反应堆所需的高贫化锂材料（即贫化 6Li）带来了质量控制问题。本研究对一种碳酸锂（NIST SRM924a）和一种高贫化氢氧化锂材料（Li-7 含量为 99.95%）进行了实验室间比较，前者含有名义上的天然同位素丰度（Li-7 含量为 92.4%），后者则含有名义上的天然同位素丰度（Li-7 含量为 99.95%）。NIST SRM924a 的天然锂同位素丰度得到了证实，氢氧化锂的 6Li/7Li 比率介于 0.000399 至 0.000436 之间，平均值为 0.000428 ± 0.000023（2SD，n = 9）。今后，这种材料可用作涉及高贫化锂的分析工作的质量控制。

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Round-robin analysis of highly depleted lithium for Generation IV nuclear reactor applications

Lithium reference materials containing unnaturally high abundances of ⁷Li are not currently available, which poses quality control problems for highly depleted lithium materials (i.e., depleted in ⁶Li) required for Generation IV nuclear reactors. This study presents an interlaboratory comparison of a lithium carbonate (NIST SRM924a) containing nominally natural isotopic abundances (∼92.4 % Li-7) and a highly depleted lithium hydroxide material (∼99.95 % Li-7). The natural lithium isotope abundances of NIST SRM924a are confirmed, and the ⁶Li/⁷Li ratio of the lithium hydroxide ranged from 0.000399 to 0.000436 with an average of 0.000428 ± 0.000023 (2SD, n = 9). Going forward this material can be used as quality control for analytical work involving highly depleted lithium.

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来源期刊

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

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.