在DTE3和Frascati中子发生器期间JET上与iter相关的实验中子活动

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
N. Fonnesu , P. Beaumont , T. Berry , A. Colangeli , F. Dacquait , M. Damiano , D. Flammini , C.L. Grove , X. Litaudon , S. Loreti , M. Lungaroni , S. Mianowski , F. Moro , S. Noce , J. Peric , A. Previti , V. Radulović , R. Villari , P. Zito , JET Contributors
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引用次数: 0

摘要

在欧洲核聚变工作包PrIO (ITER运行准备)下,JET对氘-氚(DT)运动的技术开发旨在利用ITER相关辐射领域,提高对核技术和安全的认识,并通过专门的实验开发和验证核代码、数据和测量技术。其中,利用基于离子室的剂量学系统进行关断剂量率(SDDR)测量,对ITER中SDDR评估的数值工具进行验证;利用金刚石探测器对ITER HCPB-TBM(氦冷卵石床-测试毯模块)模型中的氚产量进行在线测量,以测试一些能够在恶劣环境下作为tbm工作的测量系统;以及首次在DT操作期间测量托卡马克冷却水中子诱导活化的实验,以验证ITER中水活化评估的多物理场方法。此外,由于在冷却系统中循环的活化腐蚀产物(ACPs)是ITER辐射危害的主要来源之一,因此目前正在ENEA 14-MeV弗拉斯卡蒂中子发生器(FNG)上设计一项实验,以证明ITER(即OSCAR-Fusion)在聚变相关条件下在这方面的参考代码的准确性。最后,考虑到辐射诱导效应在ITER和未来核聚变机器中的重要性,值得一提的是,ENEA正在开发一个名为GENeuSIS(通用实验中子系统辐照站)的模块化辐照站,该辐照站将安装在FNG,旨在重现特定的中子和伽马能谱,用于研究电子设备的响应和诊断。目前的工作范围是对上述活动进行概述,主要是从实验的角度来描述它们的现状、成就、出现的关键问题以及下一步的优化。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
ITER-relevant experimental neutronic activities at JET during DTE3 and at the Frascati neutron generator
The technological exploitation of deuterium-tritium (DT) campaigns at JET under EUROfusion work package PrIO (Preparation of ITER Operations) aimed at taking advantage of the ITER-relevant radiation fields to improve the knowledge of nuclear technology and safety and to develop and validate nuclear codes, data and measurement techniques through dedicated experiments. Among them, the shutdown dose rate (SDDR) measurement with a dosimetry system based on ion chambers for the validation of the numerical tools for the SDDR assessment in ITER, the on-line measurement of tritium production in the mock-up of the ITER HCPB-TBM (Helium Cooled Pebble Bed - Test Blanket Module) with a diamond detector to test some measurement systems capable of working in harsh environments as TBMs, and the first-of-a-kind experiment to measure the neutron-induced activation of cooling water in a tokamak during DT operation, to validate the multi-physics methodologies for water activation assessment in ITER. Moreover, as one of the main sources of radiological hazard in ITER is due to the Activated Corrosion Products (ACPs) circulating in the cooling system, an experiment is currently under design at the ENEA 14-MeV Frascati Neutron Generator (FNG) to prove the accuracy of the reference code in this matter for ITER (i.e., OSCAR-Fusion) under fusion relevant conditions. Finally, considering the importance of radiation-induced effects on electronics in ITER and future fusion machines, it is worth mentioning the development of a modular irradiation station at ENEA named GENeuSIS (General Experimental Neutron System Irradiation Station), to be installed at FNG and which aims at reproducing specific neutron and gamma energy spectra for studying the response of electronic devices and diagnostics.
The scope of the present work is to give an overview of the mentioned activities, mostly from an experimental point of view, to describe their status, achievements, criticalities emerged and the optimization of the next steps.
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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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