使用带金和铟活化箔的单圆柱中子谱仪在 18F 生产过程中对自屏蔽回旋加速器内的中子谱进行测量

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

Annals of Nuclear Energy Pub Date : 2024-09-27 DOI:10.1016/j.anucene.2024.110949

Rasito Tursinah , Sidik Permana , Zaki Su’ud , Alan Maulana , A.K. Rivai , Muhayatun Santoso , Putu Sukmabuana , Nurhuda , Hari Suryanto , Wahyudi , Kusdiana , Djoko Prakoso , M.F. Ramadhani , Bunawas

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引用次数: 0

摘要

单圆筒中子能谱仪（SCNS）是一个直径为 8 厘米、长度为 16 厘米的圆筒形单慢化剂能谱仪。七个金活化箔式中子探测器以不同的距离安装在慢化剂轴上。该光谱仪用于测量自屏蔽回旋加速器在使用 11 MeV 质子和 25 µA 束流进行 70 分钟 18F 生产过程中的中子能谱。探测器的响应使用 MCNPX 2.7 进行计算。测量结果得到了 198Au 和 116mIn 的放射性活度，并通过 MCNPX 进行了模拟验证。利用测量得出的探测器响应值和探测器活度，使用 UMG 程序的展开技术获得了中子能谱。使用 SCNS 和金、铟活化箔探测器测量得出的中子谱相差 8%。同时，根据 MCNPX 计算结果，使用金箔的测量结果为 1%，而使用铟箔的测量结果为 10%。

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Neutron spectrum measurements inside a self-shielded cyclotron during 18F production using a single-cylindrical neutron spectrometer with gold and indium activation foils

The Single-Cylindrical Neutron Spectrometer (SCNS) is a single moderated spectrometer in the form of a cylinder with a diameter of 8 cm and a length of 16 cm. Seven Au activation foil type neutron detectors are installed on the moderator axis with varying distances. This spectrometer is used to measure the neutron spectrum in self-shielded cyclotron during ¹⁸F production using a proton of 11 MeV and a beam current of 25 µA for 70 min. The detector response was calculated using MCNPX 2.7. The measurement results obtained activity of ¹⁹⁸Au and ^116mIn and were validated with simulation using MCNPX. With the detector response values and detector activity from the measurements, a neutron spectrum was obtained using the unfolding technique using the UMG program. The neutron spectrum from measurements using SCNS with Au and In activation foil detectors has a difference of 8 %. Meanwhile, with the MCNPX calculation results, the measurement results using the Au foil are 1 % while with the In foil it is 10 %.

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.