Study on the contribution matrix for EAST radial neutron camera system

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

Fusion Engineering and Design Pub Date : 2024-07-25 DOI:10.1016/j.fusengdes.2024.114602

Yubo Zhang , Guoqiang Zhong , Liangsheng Huang , Mingyuan Xu , Liqun Hu , Juan Huang , Kun Xu , Ruixue Zhang , Li Yang , Chaowei Mai , Yongqiang Zhang , Weikun Chen , K. Ogawa , M. Isobe , Tieshuan Fan , Mengjie Zhou

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引用次数: 0

Abstract

The EAST (Experiment Advanced Superconductor Tokamak) Radial Neutron Camera (RNC) is designed to measure the temporal and spatial distribution of fast neutrons. The system primarily consists of detector components, shielding collimators, support structure, and data acquisition system. We have studied on the neutronic transport through MCNP with EAST reference D-D neutron source (EAST #77160), and calculated the plasma neutron source chord integral along the observation sightlines and scattering neutrons from structural facilities. Contribution matrixes, incorporating both uncollided and scattered neutrons determines the response from the neutron source to every detector unit. We evaluate the RNC primarily through the variation of the RNC sightlines to improve detector performance by reducing interference particles, thereby laying the foundation for subsequent upgrades. Benefiting from these measurements, we can better study the detector signals in relation to corresponding plasma configurations in the future.

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EAST 径向中子照相系统的贡献矩阵研究

EAST（先进超导托卡马克实验）径向中子照相机（RNC）旨在测量快中子的时间和空间分布。该系统主要由探测器组件、屏蔽准直器、支撑结构和数据采集系统组成。我们利用 EAST 参考 D-D 中子源（EAST #77160）对通过 MCNP 的中子传输进行了研究，并计算了沿观测视线的等离子体中子源弦积分和来自结构设施的散射中子。包含非对撞中子和散射中子的贡献矩阵决定了中子源对每个探测器单元的响应。我们主要通过改变 RNC 视线来评估 RNC，以通过减少干扰粒子来提高探测器性能，从而为后续升级奠定基础。受益于这些测量，我们可以在未来更好地研究探测器信号与相应等离子体配置的关系。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.