Characterization of neutron spectrum of polyethylene-moderated AmBe neutron source using a passive single-cylindrical neutron spectrometer

IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Radiation Measurements Pub Date : 2024-09-07 DOI:10.1016/j.radmeas.2024.107294
Rasito Tursinah , Sidik Permana , Zaki Su'ud , Alan Maulana , Tri C. Laksono , Afida Ikawati , Satrio A. Setiawan , Wahyudi Wahyudi , Bunawas Bunawas
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Abstract

The changes in the neutron spectrum produced by the AmBe neutron source moderated in the polyethylene sphere need to be characterized. A passive single-moderator neutron spectrometer with indium foil activation neutron detector has been developed to characterize the neutron spectrum of an AmBe source inside a polyethylene sphere. The detector response function was calculated using the MCNPX 2.7 program with IRDFF-II nuclear data library. Measurements were conducted by placing the Single-Cylindrical Neutron Spectrometer (SCNS) on the outer surface of the sphere for 5 h. The 116mIn activity due to neutron activation in each indium foil was measured using a gamma spectrometer with an HPGe detector. By identifying the count value at the peak energy of 1294 KeV and considering an HPGe detector efficiency of 3.2% at the foil position 1 mm above the detector surface, the activity of 116mIn was obtained. The activity value of 116mIn from each indium foil was compared with the MCNPX simulation results. The neutron spectrum was unfolded using the UMG 3.3 program with activity data input of 116mIn for each foil and detector response. A neutron spectrum was obtained with a total neutron flux of 634 ± 60 n/cm2·s, consisting of 25% thermal neutrons, 16% epithermal neutrons, and 61% fast neutrons. When compared with the simulation results, the total neutron flux in the spectrum produced by SCNS-In showed only a small difference of 1%. Based on these neutron spectrum measurements, it was determined that placing the AmBe neutron source inside a 15″ diameter PE-sphere will reduce the fast neutron flux by 78%.

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使用被动式单圆柱中子能谱仪确定聚乙烯慢化 AmBe 中子源的中子能谱特征
需要对在聚乙烯球内缓和的 AmBe 中子源产生的中子谱变化进行表征。我们开发了一种带有铟箔活化中子探测器的被动式单慢化剂中子能谱仪,用于表征聚乙烯球内 AmBe 中子源的中子能谱。探测器响应函数是利用 MCNPX 2.7 程序和 IRDFF-II 核数据库计算得出的。将单圆柱中子能谱仪(SCNS)置于球体外表面 5 小时后进行测量。通过确定峰值能量为 1294 KeV 时的计数值,并考虑到铟箔在探测器表面上方 1 毫米处的 HPGe 探测器效率为 3.2%,从而得出 116mIn 的放射性活度。每个铟箔的 116mIn 活度值都与 MCNPX 模拟结果进行了比较。使用 UMG 3.3 程序展开了中子能谱,并为每块铟箔和探测器响应输入了 116mIn 的放射性数据。得到的中子能谱总中子通量为 634 ± 60 n/cm2-s,其中热中子占 25%,表热中子占 16%,快中子占 61%。与模拟结果相比,SCNS-In 产生的频谱中的总中子通量仅有 1% 的微小差异。根据这些中子频谱测量结果,可以确定将 AmBe 中子源置于直径为 15 英寸的 PE 球内将使快中子通量减少 78%。
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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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