俄罗斯研究核反应堆生物屏蔽周围的中子场特征

IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY
M.D. Pyshkina, A.V. Vasilyev, E.I. Nazarov, A.A. Ekidin
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引用次数: 0

摘要

本文介绍了对俄罗斯研究核反应堆生物屏蔽周围中子场特征的研究结果,以确定其预期行为并加强人员中子监测。研究涵盖五个核研究反应堆:IVV-2M、IRT-T、IRT-MEPhI、RBT-6 和 SM-3。所有反应堆都是水池式反应堆;其中一些(RBT-6 和 SM-3)采用加压水,而其他反应堆(IVV-2M、IRT-T 和 IRT-MEPhI)则采用常压水。所分析的中子场位于反应堆水箱盖、生物屏蔽覆盖的堆芯前方以及水平实验通道前方。频谱平均中子能量从 0.01 MeV(RBT-6)到 1.0 MeV(SM-3)不等。通量-环境剂量转换系数从 15 pSv ∙ cm2(RBT-6)到 260 pSv ∙ cm2(SM-3)不等。其他测量点的光谱显示了生物屏蔽后中子辐射通量密度的能量分布特征。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Characteristics of neutron fields around biological shielding of research nuclear reactors in Russia
The paper presents the results of a study of the neutron field characteristics surrounding biological shielding of Russian research nuclear reactors to establish their expected behavior and enhance personnel neutron monitoring. The study covered five nuclear research reactors: IVV-2M, IRT-T, IRT-MEPhI, RBT-6, and SM-3. All reactors are pool-typed; some (RBT-6 and SM-3) have pressurized water, while others (IVV-2M, IRT-T, and IRT-MEPhI) have water under normal pressure. The neutron fields analyzed are located at the tank cover of reactors, in front of the reactor core covered with biological shielding, and in front of the horizontal experimental channel. The spectrum average neutron energy ranges from 0.01 MeV (RBT-6) to 1.0 MeV (SM-3). The fluence-to-ambient dose conversion coefficient varies from 15 pSv cm2 (RBT-6) to 260 pSv cm2 (SM-3). The spectra at the other measurement points exhibit the energy distribution characteristics of the neutron radiation flux density behind the biological shielding.
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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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