用金刚石探测器鉴定 D-T 便携式中子发生器的脉冲模式工作特性

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-10-26 DOI:10.1016/j.fusengdes.2024.114695
Tomas Bily, Ondrej Novak, Ondrej Huml, Zhao-Ming Pan
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摘要

单晶快中子钻石探测器被用于研究 MP320 便携式中子发生器的脉冲模式运行。脉冲由带有修改过的 FPGA 固件的 Red Pitaya - STEMlab 125-14 记录。研究包括影响中子发生器中子脉冲输出的主要参数,即脉冲频率、占空比和束流。中子脉冲形状,即中子发生器在脉冲模式下工作时中子发射的时间相关性,已在 250 Hz 至 20 kHz 范围内的四个频率、两个占空比值(10 % 和 50 %)以及三个束流值(20、45 和 70 μA)下进行了测量。测量结果表明,理想化矩形中子发射的性能明显下降,特别是在高频率和低束流值时。结果证实,快中子金刚石探测器可在 DT 便携式中子发生器的整个运行参数范围内,用于描述其脉冲运行特性。
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Characterisation of pulse-mode operation of D-T portable neutron generator by diamond detector
A single-crystal fast neutron diamond detector has been applied to study the pulse-mode operation of the MP320 portable neutron generator. The pulses were recorded by the Red Pitaya – STEMlab 125–14 with modified FPGA firmware. The study includes the main parameters that affect the neutron pulse output of the neutron generator, i.e. pulsing frequency, duty factor, and beam current. Neutron pulse shapes, i.e. time dependences of neutron emission of neutron generator operated in pulsing mode, have been measured for four frequencies in the range from 250 Hz to 20 kHz, for two values of duty factors (10 % and 50 %), and for three values of beam current (20, 45 and 70 μA). The measurement showed significant deterioration from idealised rectangular neutron emission, especially for high frequencies and for low values of beam current. The results confirm that the fast neutron diamond detectors can be advantageously used for characterisation of pulse operation of DT portable neutron generator in the whole range of its operational parameters.
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来源期刊
Fusion Engineering and Design
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.
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