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Quadratic parametrization of the maximum alpha track lengths in CR-39 detector for various energies and incident angles CR-39探测器在不同能量和入射角下最大径迹长度的二次参数化
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-21 DOI: 10.1016/j.apradiso.2025.111972
Luiz Augusto Stuani Pereira , Carlos ALberto Tello Sáenz
{"title":"Quadratic parametrization of the maximum alpha track lengths in CR-39 detector for various energies and incident angles","authors":"Luiz Augusto Stuani Pereira ,&nbsp;Carlos ALberto Tello Sáenz","doi":"10.1016/j.apradiso.2025.111972","DOIUrl":"10.1016/j.apradiso.2025.111972","url":null,"abstract":"<div><div>CR-39 is a widely used solid-state nuclear track detector for alpha-particle detection. In this study, the alpha-particle range was investigated for various incident energies and angles using Geant4 Monte Carlo simulations. The maximum track length was measured and found to exhibit a quadratic dependence on the primary energy of the incident alpha particles. Additionally, the distribution of maximum longitudinal length as a function of particle energy revealed that the critical detection angle for alpha particles in CR-39 is 71° for a chemical etching solution of 6.25 N NaOH at 70 <span><math><mrow><mo>±</mo><mspace></mspace><mn>0</mn><mo>.</mo><mn>1</mn></mrow></math></span> °C. For a minimum etching time of 40 min, required for track visualization under an optical microscope, the energy threshold ranges from 0.191 ± 0.001 MeV for normally incident particles to 10.87 ± 0.02 MeV for a dip angle of 71°. In the context of radiation level monitoring using CR-39, the optimal chemical etching time for reliable track density measurement is 400 min. Under this condition, the energy threshold varies between 3.13 ± 0.01 MeV for normal incidence and 14.3 ± 0.2 MeV at 70°. Notably, for incident angles of 71° or greater, no detectable tracks are observed at this etching time.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 111972"},"PeriodicalIF":1.6,"publicationDate":"2025-06-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144366043","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Evaluation of bismuth oxide nanoparticles for enhanced gamma-ray/neutron shielding in HDPE-based composites 氧化铋纳米粒子在hdpe基复合材料中增强伽马射线/中子屏蔽的评价
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-20 DOI: 10.1016/j.apradiso.2025.112010
Mohamed Shabib , Eman K. Tawfik , A.M. Abdel Reheem , Afaf Nada , H.A. Ashry
{"title":"Evaluation of bismuth oxide nanoparticles for enhanced gamma-ray/neutron shielding in HDPE-based composites","authors":"Mohamed Shabib ,&nbsp;Eman K. Tawfik ,&nbsp;A.M. Abdel Reheem ,&nbsp;Afaf Nada ,&nbsp;H.A. Ashry","doi":"10.1016/j.apradiso.2025.112010","DOIUrl":"10.1016/j.apradiso.2025.112010","url":null,"abstract":"<div><div>In the present study the shielding efficiencies of gamma and neutron radiations for fabricated composites using high-density polyethylene (HDPE) via the sol-gel method were investigated. These lightweight, low-cost, and ductile materials incorporate xBi<sub>2</sub>O<sub>3</sub> nanoparticles (x = 4.0 %, 12.0 %, 20.0 %, 30.0 %, and 40 %) as a non-toxic nanofiller. The study employed X-ray diffraction (XRD), scanning electron microscopy (SEM), and energy-dispersive X-ray spectroscopy (EDX) to characterize the Bi<sub>2</sub>O<sub>3</sub>/HDPE nanocomposites. The effectiveness of these composites in attenuating gamma-ray was assessed by using an HPGe detector. Measurements were conducted across various gamma-ray energies (121, 244, 334, 444, 778, 963, 1112, and 1408 keV) emitted by a standard Eu-152 point source. The relationship between mass attenuation coefficients (μ<sub>m</sub>) and the Bi<sub>2</sub>O<sub>3</sub> loading was investigated at each energy level experimentally and theoretically. Using other shielding parameters, such as half-value layer (HVL) and mean free path (MFP), were also calculated. Total macroscopic neutron cross-section (ΣT) of the composites was also determined using an Am241–Be (α, n) neutron source. It was observed that gamma and neutron shielding properties were improved due to increasing amount of Bi<sub>2</sub>O<sub>3</sub> nanoparticles in the composite.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 112010"},"PeriodicalIF":1.6,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144366041","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Determination of the coincidence summing gamma spectrum of a 60Co source by Monte Carlo simulations taking into account the angular correlation γ - γ 考虑到角相关γ - γ,用蒙特卡罗模拟确定60Co源的符合和γ谱
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-19 DOI: 10.1016/j.apradiso.2025.111975
Enrique R. González
{"title":"Determination of the coincidence summing gamma spectrum of a 60Co source by Monte Carlo simulations taking into account the angular correlation γ - γ","authors":"Enrique R. González","doi":"10.1016/j.apradiso.2025.111975","DOIUrl":"10.1016/j.apradiso.2025.111975","url":null,"abstract":"<div><div>The coincidence summing effects can remove counts of the photo-peaks or eventually add spurious counts to them when two photons of lower energy interact simultaneously with the detector. Programs that simulate radiation transport generally do not consider simultaneity effects since they simulate one particle at a time. However, it is possible to obtain the coincidence summing spectrum from the simulated spectrum of the particles of each energy individually. The objective of this work is to develop a method to obtain the coincidence summing spectrum of a radioactive source that emits two (or more) photons in cascade. To do this, we have obtained an exact expression for the coincidence summing spectrum based on the probabilities of interaction with the detector of each photon. These probabilities were obtained by MC simulation and from them, the coincidence summing spectrum was obtained by convolution between them. To make the calculation more consistent with the real phenomenon we have taken into account the angular correlation between the photons. Although the method is applied to a <span><math><mrow><msup><mrow></mrow><mrow><mn>60</mn></mrow></msup><mi>C</mi><mi>o</mi></mrow></math></span> source, the methodology is valid for the case of volumetric sources of different sizes and shapes and the generalization to the case of sources that emit three or more photons in their decay is immediate.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 111975"},"PeriodicalIF":1.6,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144366042","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Characterization of a system with a 241Am-Be neutron source moderated by lead for evaluating parameters of a 252Cf source 用铅慢化241Am-Be中子源评价252Cf源参数的系统表征
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-19 DOI: 10.1016/j.apradiso.2025.111987
Angela Souza Gonçalves, Lunia Coelho de Almeida de Lima, Antonio Carlos Ferreira, Marcelo Marques Martins, Walsan Wagner Pereira
{"title":"Characterization of a system with a 241Am-Be neutron source moderated by lead for evaluating parameters of a 252Cf source","authors":"Angela Souza Gonçalves,&nbsp;Lunia Coelho de Almeida de Lima,&nbsp;Antonio Carlos Ferreira,&nbsp;Marcelo Marques Martins,&nbsp;Walsan Wagner Pereira","doi":"10.1016/j.apradiso.2025.111987","DOIUrl":"10.1016/j.apradiso.2025.111987","url":null,"abstract":"<div><div>After the 2021 revision of ISO 8529–1, discontinuation left only <sup>252</sup>Cf and <sup>241</sup>Am-Be as standard reference fields. Currently, the cost of 1 g of <sup>252</sup>Cf is approximately 27 million dollars, rendering it prohibitively expensive for widespread use compared to <sup>241</sup>Am-Be, which is readily available, cost-effective, and has a long half-life. This work describes the development of a system utilizing a<sup>241</sup>Am-Be neutron source moderated within a lead cylinder to simulate the characteristics of a<sup>252</sup>Cf field. This new setup will be instrumental for sample testing, calibrations, and irradiations required by the laboratory's demands.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 111987"},"PeriodicalIF":1.6,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144366044","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Preliminary study of 3D dose distribution evaluation in neutron capture therapy using a PVA-GTA-I radiochromic gel dosimeter 用PVA-GTA-I放射致色凝胶剂量计评价中子俘获治疗中三维剂量分布的初步研究
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-19 DOI: 10.1016/j.apradiso.2025.112008
S. Hayashi , R. Narita , Y. Sakurai , K. Fujino , R. Kurihara , S. Ikeda , K. Ono , G. Wakabayashi
{"title":"Preliminary study of 3D dose distribution evaluation in neutron capture therapy using a PVA-GTA-I radiochromic gel dosimeter","authors":"S. Hayashi ,&nbsp;R. Narita ,&nbsp;Y. Sakurai ,&nbsp;K. Fujino ,&nbsp;R. Kurihara ,&nbsp;S. Ikeda ,&nbsp;K. Ono ,&nbsp;G. Wakabayashi","doi":"10.1016/j.apradiso.2025.112008","DOIUrl":"10.1016/j.apradiso.2025.112008","url":null,"abstract":"<div><div>Boron neutron capture therapy (BNCT) is a promising cancer treatment method that utilizes the nuclear reaction between <sup>10</sup>B and thermal neutrons. Three-dimensional (3D) gel dosimeters are gaining attention for their potential to assess 3D dose distributions in BNCT. In this study, a PVA-GTA-I (polyvinyl alcohol crosslinked by glutaraldehyde, and iodide) radiochromic gel dosimeter, which develops a red color due to complex formation between PVA and iodide, was investigated. A PVA-GTA-I gel dosimeter, enhanced with neutron sensitizers <sup>10</sup>B and <sup>6</sup>Li, was irradiated with neutrons from a nuclear reactor. As a preliminary experiment for future evaluation of 3D dose distribution, we assessed a pseudo-one-dimensional depth dose distribution by measuring absorbance changes in a system of small gel dosimeters. The results showed that the PVA-GTA-I gel dosimeter could detect increased doses resulting from neutron capture reactions when neutron sensitizers were present. The shape of the pseudo-one-dimensional depth-dose distribution correlated well with a simple simulation. These findings suggest the potential for future 3D dose distribution measurements using large gel dosimeters and 3D optical computed tomography devices.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 112008"},"PeriodicalIF":1.6,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144366040","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Double-filter monitor for simultaneous measurement of Radon and its progeny 同时测量氡及其子体的双滤式监测仪
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-18 DOI: 10.1016/j.apradiso.2025.112006
Rosaline Mishra , R. Prajith , R.P. Rout , S. Jalaluddin , A. Khan , B.K. Sapra
{"title":"Double-filter monitor for simultaneous measurement of Radon and its progeny","authors":"Rosaline Mishra ,&nbsp;R. Prajith ,&nbsp;R.P. Rout ,&nbsp;S. Jalaluddin ,&nbsp;A. Khan ,&nbsp;B.K. Sapra","doi":"10.1016/j.apradiso.2025.112006","DOIUrl":"10.1016/j.apradiso.2025.112006","url":null,"abstract":"<div><div>For simultaneous measurement of radon and its progeny, double filter monitor based on Direct progeny sensors (DRPS) was developed. DRPS is an absorber mounted LR115 detector which measures the progeny concentration. Double filter consisted of two filters, inlet and exit filter, which were utilised in the monitor for progeny atom deposition such that the ambient progeny atoms get deposited on the inlet filter and the progeny formed due to decay of radon sampled inside the delay volume get deposited on the exit filter. DRPS facing the inlet filter would detect the alpha particles emitted during decay of progeny on inlet filter and that will correspond to ambient progeny concentration. Similarly DRPS placed facing the exit filter will detect the alpha particles emitted during the decay of progeny on exit filter, which is related to ambient radon concentration. Thus the system has two filters and two progeny sensors. The loss of progeny atoms formed during the decay of ingressed radon inside the delay chamber may be lost due to plate-out on the walls of the delay chamber. The plate-out loss is characterised by diffusion parameter. Theoretical calculations of transit time of progeny atoms in the delay volume at different flow rates were also used to study the effect of volume of the chamber at different flow rates. The system was calibrated in known activities of radon and its progeny and the calibration factors were measured. Additional advantage of the system is that in-situ equilibrium factor can be measured.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 112006"},"PeriodicalIF":1.6,"publicationDate":"2025-06-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144329579","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Study of dose component discrimination method using micelle gel dosimeters for quality assurance in boron neutron capture therapy 胶束凝胶剂量计剂量成分鉴别法在硼中子俘获治疗质量保证中的应用研究
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-18 DOI: 10.1016/j.apradiso.2025.112007
Ryosuke Narita , Shin-ichiro Hayashi , Yoshinori Sakurai
{"title":"Study of dose component discrimination method using micelle gel dosimeters for quality assurance in boron neutron capture therapy","authors":"Ryosuke Narita ,&nbsp;Shin-ichiro Hayashi ,&nbsp;Yoshinori Sakurai","doi":"10.1016/j.apradiso.2025.112007","DOIUrl":"10.1016/j.apradiso.2025.112007","url":null,"abstract":"<div><div>As a new tool for quality assurance in boron neutron capture therapy, we focused on gel dosimeters that can estimate three-dimensional dose distribution. To establish a method that combines multiple types of radiochromic gel dosimeters sensitive to specific dose components for the discrimination of the dose components, the neutron and gamma-ray responses of leucocrystal violet micelle gel dosimeters were characterized. For the estimation of boron or nitrogen dose components, dosimeters containing boric acid or urea as a sensitizer were prepared, while for hydrogen dose components, light-water-based and heavy-water-based dosimeters were prepared. For investigating the neutron and gamma-ray response characteristics, the Heavy Water Neutron Irradiation Facility installed at the Kyoto University Reactor and the Co-60 gamma-ray irradiation facility were used. Based on the characterization results, a dose component discrimination method using four different types of gel dosimeter compositions was proposed.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 112007"},"PeriodicalIF":1.6,"publicationDate":"2025-06-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144338276","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Measurement of the 10B(d,n)11C reaction cross-section in the energy range of 0.05–0.57 MeV in inverse kinematics 在0.05-0.57 MeV能量范围内10B(d,n)11C反应截面的逆运动学测量
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-16 DOI: 10.1016/j.apradiso.2025.111999
P.S. Prusachenko , A.F. Gurbich, T.L. Bobrovskiy, M.V. Bokhovko
{"title":"Measurement of the 10B(d,n)11C reaction cross-section in the energy range of 0.05–0.57 MeV in inverse kinematics","authors":"P.S. Prusachenko ,&nbsp;A.F. Gurbich,&nbsp;T.L. Bobrovskiy,&nbsp;M.V. Bokhovko","doi":"10.1016/j.apradiso.2025.111999","DOIUrl":"10.1016/j.apradiso.2025.111999","url":null,"abstract":"<div><div>The excitation function for the <sup>10</sup>B(d,n)<sup>11</sup>C reaction was measured in the energy range of 0.05–0.57 MeV. The measurements were performed using the inverse kinematic reaction <sup>2</sup>H(<sup>10</sup>B,n)<sup>11</sup>C to reduce the background specific to the experiments with deuteron beams and to prevent the leakage of <sup>11</sup>C recoil nuclei from the target. Two scintillation detectors based on NaI(Tl) crystals operating in coincidence mode were used to detect γ-rays with an energy of 0.511 MeV produced during the β<sup>+</sup> decay of <sup>11</sup>C. The cross-section of the <sup>2</sup>H(<sup>10</sup>B,n)<sup>11</sup>C reaction was obtained from the analysis of the decay curve of <sup>11</sup>C after irradiation taking into account the detection efficiency of the system, the concentration of deuterium atoms in the target and the stopping power for boron ions. Then the cross-section of the <sup>10</sup>B(d,n)<sup>11</sup>C reaction was calculated using known kinematic equations. The obtained cross-section data are generally in agreement with the data previously reported for deuteron energies less than 0.2 MeV and are inconsistent with the data corresponding to energies greater than 0.5 MeV. The experimental data in the energy range of 0.2–0.5 MeV were obtained for the first time.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 111999"},"PeriodicalIF":1.6,"publicationDate":"2025-06-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144290586","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Assessing the role of SiPM number on energy resolution in radiation detection using bismuth germanate crystals 锗酸铋晶体辐射探测中SiPM数对能量分辨率的影响
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-16 DOI: 10.1016/j.apradiso.2025.111958
Emre Iren , Taylan Yetkin , Onur Bugra Kolcu , Ferhat Ozok , Mustafa Nizamettin Erduran
{"title":"Assessing the role of SiPM number on energy resolution in radiation detection using bismuth germanate crystals","authors":"Emre Iren ,&nbsp;Taylan Yetkin ,&nbsp;Onur Bugra Kolcu ,&nbsp;Ferhat Ozok ,&nbsp;Mustafa Nizamettin Erduran","doi":"10.1016/j.apradiso.2025.111958","DOIUrl":"10.1016/j.apradiso.2025.111958","url":null,"abstract":"<div><div>In this study, we present a simple statistical model to show the relationship between the number of Silicon Photomultipliers (SiPMs) and the energy resolution of the detector. We used bismuth germanate (BGO) crystals in combination with varying numbers of SiPMs to examine the effect of photodetector count on energy resolution. We compared our results with Photomultiplier Tube-based measurements to determine the advantage of SiPMs in terms of energy resolution. We also performed a simulation study with the GEANT4 simulation package to investigate the energy resolution that can be achieved under ideal conditions by using a higher number of SiPMs. The experimental measurements showed that for a photopeak energy of 511 keV, an energy resolution of 29.9% was achieved using five SiPMs covering only 3.25% of the scintillator area, whereas a Photomultiplier Tube (PMT) covering 37% of the same area resulted in an energy resolution of about 23.4%. As a result of the simulation study, it is predicted that the energy resolution can be achieved up to 14.8% for a photopeak energy of 511 keV by using 21 symmetrically distributed SiPM.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 111958"},"PeriodicalIF":1.6,"publicationDate":"2025-06-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144322176","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Novel insights into GaN-HEMT behaviour under multi-particle irradiation 多粒子辐照下GaN-HEMT行为的新见解
IF 1.6 3区 工程技术
Applied Radiation and Isotopes Pub Date : 2025-06-15 DOI: 10.1016/j.apradiso.2025.111971
Rijin N.T. , Dinesh Kumar Sharma , M.M. Musthafa , Midhun C.V.
{"title":"Novel insights into GaN-HEMT behaviour under multi-particle irradiation","authors":"Rijin N.T. ,&nbsp;Dinesh Kumar Sharma ,&nbsp;M.M. Musthafa ,&nbsp;Midhun C.V.","doi":"10.1016/j.apradiso.2025.111971","DOIUrl":"10.1016/j.apradiso.2025.111971","url":null,"abstract":"<div><div>This study investigates the effects of photon, neutron, and <span><math><mi>α</mi></math></span>-irradiation on the electrical characteristics of a 30<!--> <!-->A GaN-HEMT (Gallium Nitride High Electron Mobility Transistor). Photon irradiation leads to a noticeable decrease in the drain current (<span><math><msub><mrow><mi>I</mi></mrow><mrow><mi>D</mi></mrow></msub></math></span>) across all gate voltages, with nonlinear deviations increasing with gate voltage. This phenomenon is attributed to photon-induced <span><math><mi>δ</mi></math></span>-rays, which generate crystal defects and alter the band structure. Neutron irradiation primarily causes a significant shift in the saturation region of the <span><math><msub><mrow><mi>I</mi></mrow><mrow><mi>D</mi></mrow></msub></math></span>-<span><math><msub><mrow><mi>V</mi></mrow><mrow><mi>D</mi></mrow></msub></math></span> characteristics, highlighting unique interactions through neutron capture reactions and scattering events. <span><math><mi>α</mi></math></span>-particles induce combined atomic, nuclear, and <span><math><mi>δ</mi></math></span>-ray effects, along with heating. The lack of significant shifts in knee voltage across different irradiations indicates that damage primarily affects the crystal lattice and electron transport mechanisms without altering fundamental operational thresholds. A quantum mechanical methodology is devised to elucidate the physics underlying radiation stress measurements, focusing on displacement damage, radiation-induced transmutation doping effects, and the significance of radiation-induced reactions within the device.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"225 ","pages":"Article 111971"},"PeriodicalIF":1.6,"publicationDate":"2025-06-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144314451","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
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