Neutron emission from water activation: Experiments and modeling under fusion-relevant conditions at the KATANA facility

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Julijan Peric, Domen Kotnik, Luka Snoj, Vladimir Radulović
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引用次数: 0

Abstract

Jožef Stefan Institute’s water activation experiment, called KATANA, was developed to procure benchmark quality experiments on the water activation process. This paper presents the optimization process of the neutron detector holder to achieve the neutron flux measurement system with the highest detection efficiency. Water is activated by the nuclear reactions on oxygen isotopes. The active oxygen and nitrogen isotopes then decay, emitting gamma rays and neutrons with different energies. The reaction 17O(n,p)17N is responsible for the emission of high-energy neutrons. In future fusion plants such as ITER, the neutron flux in the water cooling system will be high, with an estimated flux of approx Φ1013 n/cm2s. Therefore, adequate shielding must be considered. The design and implementation of neutron flux measurement system at the KATANA water activation facility represents a significant step towards a better understanding of water activation processes. Despite the challenges associated with water activation experiments, the first test measurements of neutron emission during the water activation process have yielded promising results. The following results will be presented: the measured half-life for the decay of 17N, activity of 17N as a function of reactor power and water flow rate. The initial results indicate the possibility of using such a facility for the measurements of the integral cross section for the 17O(n,p)17N reaction.
水活化的中子发射:在KATANA设施核聚变相关条件下的实验和建模
Jožef斯蒂芬研究所的水活化实验,称为KATANA,是为了获得水活化过程的基准质量实验而开发的。为实现中子通量测量系统的最高探测效率,提出了中子探测器支架的优化过程。水是由氧同位素的核反应激活的。活性氧和氮同位素随后衰变,释放出不同能量的伽马射线和中子。17O(n,p)17N反应产生了高能中子。在未来的核聚变装置中,如ITER,水冷却系统中的中子通量将很高,估计通量约为Φ≈1013 n/cm2s。因此,必须考虑适当的屏蔽。KATANA水活化设施中子通量测量系统的设计和实施是朝着更好地理解水活化过程迈出的重要一步。尽管与水活化实验相关的挑战,水活化过程中中子发射的第一次测试测量取得了令人鼓舞的结果。将给出以下结果:17N衰变的测量半衰期,17N的活度作为反应堆功率和水流速率的函数。初步结果表明,用这种装置测量17O(n,p)17N反应的积分截面是可行的。
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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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