用于 BNCT 的束谱分析、质量保证、实时监测和微观模拟的新技术

IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY
Hiroaki Kumada , Akihiko Masuda , Hiroki Tanaka , Masashi Takada , Naonori Hu
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引用次数: 0

摘要

硼中子俘获疗法(BNCT)是一种新一代放射疗法,它将中子束与可选择性积聚在癌细胞中的硼化合物结合在一起。由于这种疗法需要中子进行照射,因此世界各地都在开发可安装在医院的紧凑型加速器中子源设备。日本、中国和韩国已对几种设备进行了临床试验。最先进的设备已于 2020 年获得日本监管机构的批准。因此,在日本的两家医院,使用该设备的 BNCT 作为复发性头颈癌的保险疗法正在实施。因此,在 BNCT 领域,基于加速器的中子发生器的开发正在进行中。然而,要将这种疗法确立为一种常见的癌症治疗方法并在全球推广,还有许多工作要做。BNCT 的剂量测定方法是问题之一。在治疗过程中,必须准确估计中子辐照给病人带来的剂量。然而,准确和实时测量中子是很困难的。目前,我们无法测量患者在治疗过程中受到的中子剂量。取而代之的是测量辐照中子靶材料的带电粒子的电流,以间接评估中子通量和剂量。此外,根据中子与人体内各种元素的反应进行精确的剂量估算需要使用蒙特卡洛方法,而这种方法在计算上非常耗时。为了解决这些剂量测定问题,目前正在开发几种中子通量和剂量测量方法。本综述简要介绍了当前的剂量测定方法,然后介绍了几种正在开发的可用于 BNCT 的实时中子测量方法。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
New technologies for beam spectrometry, quality assurance, real-time monitoring and microdosimetry in BNCT

Boron neutron capture therapy (BNCT) is a next-generation radiotherapy that combines neutron beams with boron compounds that selectively accumulate in cancer cells. Because this therapy requires neutrons for irradiation, compact accelerator-based neutron source devices that can be installed in hospitals are being developed around the world. Clinical trials of several devices have been conducted in Japan, China, and South Korea. The most advanced device was approved by the Japanese regulatory authorities in 2020. As a result, BNCT with the device is being implemented as an insured therapy for recurrent head and neck cancer at two hospitals in Japan. Thus, the development of accelerator-based neutron generators is proceeding in the field of BNCT. However, much remains to be done to establish this therapy as a common cancer treatment and to make it available worldwide. Dosimetry methods in BNCT are one of the issues. In the treatment, the dose given to a patient by neutron irradiation has to be estimated accurately. However, it is difficult to measure neutrons accurately and in real time. Currently, the neutron dose delivered to patients during treatment is not measured. Instead, the current of the charged particles that irradiate the neutron target material is measured to indirectly evaluate the neutron fluence and dose. In addition, accurate dose estimation based on reactions with neutrons and various elements in a human body uses the Monte Carlo method, which is computationally time-consuming. To address these dosimetry issues, several neutron fluence and dose measurement methods are being developed. This review briefly describes the current dosimetry methods and then presents several methods under development that allow real-time neutron measurements applicable to BNCT.

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来源期刊
Radiation Measurements
Radiation Measurements 工程技术-核科学技术
CiteScore
4.10
自引率
20.00%
发文量
116
审稿时长
48 days
期刊介绍: The journal seeks to publish papers that present advances in the following areas: spontaneous and stimulated luminescence (including scintillating materials, thermoluminescence, and optically stimulated luminescence); electron spin resonance of natural and synthetic materials; the physics, design and performance of radiation measurements (including computational modelling such as electronic transport simulations); the novel basic aspects of radiation measurement in medical physics. Studies of energy-transfer phenomena, track physics and microdosimetry are also of interest to the journal. Applications relevant to the journal, particularly where they present novel detection techniques, novel analytical approaches or novel materials, include: personal dosimetry (including dosimetric quantities, active/electronic and passive monitoring techniques for photon, neutron and charged-particle exposures); environmental dosimetry (including methodological advances and predictive models related to radon, but generally excluding local survey results of radon where the main aim is to establish the radiation risk to populations); cosmic and high-energy radiation measurements (including dosimetry, space radiation effects, and single event upsets); dosimetry-based archaeological and Quaternary dating; dosimetry-based approaches to thermochronometry; accident and retrospective dosimetry (including activation detectors), and dosimetry and measurements related to medical applications.
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