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Biological evaluation of hydroxyapatite zirconium nanoparticle as a potential radiosensitizer for lung cancer X-ray induced photodynamic therapy 羟基磷灰石锆纳米颗粒作为肺癌x射线诱导光动力治疗潜在放射增敏剂的生物学评价。
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-30 DOI: 10.1016/j.apradiso.2024.111615
Ahmad Kurniawan , Isa Mahendra , Muhamad Basit Febrian , Marhendra Satria Utama , Julia Windi Gunadi , Roro Wahyudianingsih , Ronny Lesmana , Iim Halimah , Maula Eka Sriyani , Eva Maria Widyasari , Teguh Hafiz Ambar Wibawa , Asep Rizaludin , Crhisterra Ellen Kusumaningrum , Dani Gustaman Syarif
Photodynamic therapy has been recognized as a viable approach for lung cancer treatment. Some photosensitizer agents are known as X-ray sensitive and could improve radiotherapy efficacy. The use of nanoparticles for drug delivery and as photosensitizer agents offers various advantages because of their rapid cellular accumulation and distribution into target organs. On the other hand, several nanoparticles could trigger adverse effects during cancer treatment. In this article, the biological study of hydroxyapatite zirconium nanoparticles (HApZr) as photosensitizer candidates for X-ray-induced photodynamic therapy has been demonstrated in vitro and in vivo. This nanoparticle increased the intracellular reactive oxygen species (ROS) levels after the delivery of ionizing radiation at 5 Gy to a cancer cell line and showed higher cytotoxicity compared to non-irradiated treatment. In vitro cellular uptake based on cell imaging also indicated a promising intake and an ability to kill cancer cells. Subsequently, an in vivo evaluation using orthotopic lung cancer mouse models also showed their good accumulation in target organs, with lower accumulation in normal lung tissue. Moreover, studies of acute toxicity showed that a dose of 50 μg/mL yielded minor pathological changes on histological evaluations, which were supported by a biochemical analysis. In addition, HApZr nanoparticles also increase TNF-α which enhancing the cytotoxic effect after irradiation. Finally, these findings were important for further investigation of the clinical application of these HApZr nanoparticles for the treatment of patients with lung cancer.
光动力疗法已被认为是一种可行的肺癌治疗方法。一些光敏剂被认为是x射线敏感的,可以提高放射治疗的效果。纳米粒子用于药物输送和作为光敏剂提供了各种优势,因为它们的快速细胞积累和分布到靶器官。另一方面,一些纳米颗粒可能在癌症治疗期间引发不良反应。在本文中,羟基磷灰石锆纳米颗粒(HApZr)作为x射线诱导光动力治疗的光敏剂候选物的生物学研究已经在体外和体内得到证实。这种纳米粒子在向癌细胞系传递5gy电离辐射后增加了细胞内活性氧(ROS)水平,并且与非辐照治疗相比显示出更高的细胞毒性。基于细胞成像的体外细胞摄取也显示出有希望的摄入量和杀死癌细胞的能力。随后,使用原位肺癌小鼠模型进行的体内评估也显示,它们在靶器官中蓄积良好,在正常肺组织中的蓄积较低。此外,急性毒性研究表明,50 μg/mL的剂量在组织学评价中产生轻微的病理变化,生化分析也支持这一结果。此外,HApZr纳米颗粒还能增加TNF-α,从而增强辐照后的细胞毒作用。最后,这些发现对于进一步研究这些HApZr纳米颗粒在肺癌患者治疗中的临床应用具有重要意义。
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引用次数: 0
Risk assessment and natural radionuclide content in black-sand deposits of North Sinai coast, Egypt 埃及北西奈海岸黑砂岩风险评价及天然放射性核素含量。
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-28 DOI: 10.1016/j.apradiso.2024.111601
Mostafa A. Mansor , Islam M. Nabil , Ali Y. Ellithi , A.R. Abdulghany , A.F. El Sayed
The radioactivity levels and risk factors have been assessed for twenty-eight positions of Black-Sand (BS) surface deposits along the Mediterranean Sea coast of north Sinai, Egypt. Twenty-eight surface samples were collected from six local cities: El Ressa, Abo Sakl, Ghornata, El Arish, El Masaed, and El Rommana. The activity concentration values of the nuclides of the 226Ra, 232Th, and 40K of the collected samples were measured using a P-type HPGe detector with a relative efficiency of ∼100% where it is defined at 1.33 MeV relative to a standard 3-inch diameter and 3-inch long NaI (TI) scintillator. El Ressa samples have relatively the most significant average values for 226Ra and 232Th, whereas El Rommana samples had the highest for 40K. The radiation hazard calculations for the collected BS samples indicated significantly lower values than the internationally recommended limits. The ambient dose rates of the six areas under study were monitored and found to range from 0.06 to 0.10 μSv.h−1.
对埃及西奈半岛北部地中海沿岸28个地点的黑沙(BS)表层沉积物的放射性水平和危险因素进行了评估。从El Ressa、Abo Sakl、Ghornata、El Arish、El Masaed和El Rommana六个当地城市收集了28个地表样本。所收集样品的226Ra、232Th和40K核素的活度浓度值使用p型HPGe探测器测量,相对效率为~ 100%,相对于标准3英寸直径和3英寸长的NaI (TI)闪烁体定义为1.33 MeV。El Ressa样品中226Ra和232Th的平均值相对最显著,而El Rommana样品中40K的平均值最高。对收集的BS样本进行的辐射危害计算显示,其数值明显低于国际推荐限值。监测了六个研究区域的环境剂量率,发现其范围为0.06至0.10 μ sv - h-1。
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引用次数: 0
Feasibility verification of deep-learning based collimator-less imaging system using a voxelated GAGG(Ce) single volume detector: A Monte Carlo simulation 使用体素化GAGG(Ce)单体积探测器的基于深度学习的无准直器成像系统的可行性验证:蒙特卡罗模拟
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-26 DOI: 10.1016/j.apradiso.2024.111605
Ajin Jo , Dongmyoung Hong , Wonho Lee
A 4π-field of view deep-learning-based collimator-less imaging system was designed with the Monte Carlo method and performance of the system was studied to verify the feasibility of system. A 4 × 4 × 4 voxelated single-volume GAGG(Ce) system and 57Co, 133Ba, 22Na, and 137Cs point sources at 2000 positions were modeled using Monte-Carlo N-particle transport code version 6 (MCNP6). Two types of the localized energy deposition acquired with a voxelated detector system with and without energy bins, were calculated. The F6 tally was used to provide the entire energy deposited in each voxel and the F8 tally to provide energy spectrum data for each voxel. This system utilized these energy deposition patterns depending on the source type and position to reconstruct the source distribution image. A fully convolutional network which is advantageous for the prediction of image outputs was used to estimate source distribution. The models utilizing energy deposition patterns generated on total energy deposition and energy spectrum data were trained with labels from 30° to 10 degree of full-width half-maximum (FWHM). As a result of training with single and multiple source data, types of isotopes and source locations were discriminated up to 5 sources when using energy spectral data, and the average image similarity between ground truth images and predicted ones were 0.9936 for total energy deposition model and 0.9966 for divided energy bin model. These results showed the feasibility of a collimator-less imaging system based on deep learning method that requires no filtration of any type of interaction.
采用蒙特卡罗方法设计了基于4π视场深度学习的无准直器成像系统,并对系统性能进行了研究,验证了系统的可行性。采用蒙特卡罗n粒子输运代码第6版(MCNP6)对一个4 × 4 × 4体素的单体积GAGG(Ce)体系和2000个位置的57Co、133Ba、22Na和137Cs点源进行了建模。计算了具有和不具有能量仓的体素化探测器系统所获得的两种局域能量沉积。F6计数用于提供沉积在每个体素中的全部能量,F8计数用于提供每个体素的能谱数据。该系统利用这些能量沉积模式根据源的类型和位置来重建源的分布图像。利用有利于图像输出预测的全卷积网络估计源分布。利用总能量沉积和能谱数据生成的能量沉积模式对模型进行了30°~ 10°全宽半最大值(FWHM)标签的训练。通过对单源和多源数据的训练,利用能谱数据可分辨出最多5个源的同位素类型和源位置,总能量沉积模型的真实图像与预测图像的平均相似度为0.9936,分割能量仓模型的相似度为0.9966。这些结果表明了基于深度学习方法的无准直仪成像系统的可行性,该系统不需要过滤任何类型的交互。
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引用次数: 0
Radiometric evaluation of Ouratea miersii (Planch.) Engl. From the Municipal Natural Park of Niterói, Brazilian Atlantic Rainforest remnant 乌拉提米尔斯(Planch.)的放射学评价心血管病。来自Niterói市自然公园,巴西大西洋雨林遗迹
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-26 DOI: 10.1016/j.apradiso.2024.111607
Thalhofer J.L , Silva R.L , Lima T.A , Silva G.R.A , Lima L.S , Hoffmann A , Lobão A.Q , Silva L.B , Orejuela C.O.P , Silva A.X , Lima I , Frota M , Suita J.C , Nunes R.C , Souza E.M , Lopes J.M , Kelecom A
Concern about radiation exposure to non-human biota and the environment has increased since the 1990s, resulting in several publications by UNSCEAR, IAEA, ICRP, among other agencies, which highlighted significant gaps in knowledge regarding non-human biota and resulted in the establishment of Reference Animals and Plants (RAPs). In Brazil, the Atlantic Forest biome has vast biodiversity, but there is a lack of information on the radiometric profile of plant species growing there. Thus, the objective of this study was to evaluate the radiometric profile of Ouratea miersii (Malpighiales), endemic to the Atlantic Rainforest, collected in the State of Rio de Janeiro, city of Niterói, at the Municipal Natural Park (PARNIT), which covers a region of protected Atlantic Rainforest. The specimen was completely collected (root, stem, leaf and soil including organic matter around the root), and each sample analyzed individually by gamma spectrometry using a HPGe detector (Canberra). The calculated activity concentrations (AC) indicated the presence of 40K, 226Ra and 228Ra, with significant AC of 40K in the soil (3901 Bq·kg−1). The 40K soil-plant transfer was 11.6%, being limited by some physiological mechanism and/or osmotic saturation, while the transfer factor for 226Ra was 45.3%. The dose rate in non-human biota due to AC's of 226Ra and 228Ra in soil was estimated by modeling with the ERICA Tool, which indicated the absence of adverse effect on non-human biota due to exposure. The radiological hazard index values (Raeq, ADR, AEDR, and ELCR) obtained from the soil AC collected at PARNIT were significantly higher than those from other locations in Brazil, and about three times the value reported by UNSCEAR (2000) due to a ⁴⁰K anomaly in the soil. For this reason, a more extensive environmental monitoring was necessary in the PARNIT region.
自1990年代以来,对非人类生物群和环境的辐射暴露的关注有所增加,导致科委会、原子能机构、国际生物保护委员会和其他机构发表了几份出版物,其中强调了关于非人类生物群的知识方面的重大差距,并导致建立了参考动物和植物。在巴西,大西洋森林生物群落具有巨大的生物多样性,但缺乏关于生长在那里的植物物种的辐射剖面的信息。因此,本研究的目的是评估大西洋雨林特有的Ouratea miersii (Malpighiales)的辐射学特征,该特征采集于Niterói市里约热内卢de Janeiro州的市政自然公园(PARNIT),该公园覆盖了受保护的大西洋雨林区域。样品被完整地收集(根、茎、叶和土壤,包括根周围的有机物),每个样品都使用HPGe探测器(堪培拉)进行伽马能谱分析。计算的活性浓度(AC)表明土壤中存在40K、226Ra和228Ra,其中40K在土壤中的AC显著(3901 Bq·kg−1)。40K土壤-植株转换率为11.6%,受生理机制和渗透饱和的限制,而226Ra的转换率为45.3%。利用ERICA工具建立模型,估算了土壤中226Ra和228Ra的接触对非人类生物群的剂量率,表明接触对非人类生物群没有不良影响。从PARNIT收集的土壤AC中获得的放射性危害指数值(Raeq, ADR, AEDR和ELCR)明显高于巴西其他地点的辐射危害指数值,并且由于土壤中的⁴⁰K异常,大约是UNSCEAR(2000)报告值的三倍。因此,有必要在PARNIT区域进行更广泛的环境监测。
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引用次数: 0
Theoretical predictions to produce medical 89Zr radionuclide via the 89Y(p, n)89Zr route at ≈ 5–60 MeV: Comparison of experimental and theoretical production data 在≈5-60 MeV下通过89Y(p, n)89Zr路线生产医用89Zr放射性核素的理论预测:实验和理论生产数据的比较。
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-26 DOI: 10.1016/j.apradiso.2024.111599
F.K. Amanuel
Theoretical investigations were carried out for the production of the medically important 89Zr radionuclide. This radionuclide is produced in the interaction of a proton projectile with 89Y-target, a readily available target with greater purity at ≈ 5–60 MeV. The 89Y (p, n)89Zr production route, a promising avenue in the fields of medical imaging and radiopharmaceutical development, is of significant interest due to its potential to produce 89Zr, a radionuclide with a half-life of 78.41 h, suitable for various applications.
The TALYS-1.95(G) predicted production cross-sections were in very good agreement with the experimental cross-sections. This successful alignment was further confirmed by a strong positive Pearson's correlation between the TALYS-1.95(G) predicted and experimentally measured production cross-sections for 89Zr radionuclide produced via the 89Y (p, n)89Zr route.
Furthermore, the calculations of thick target yields have provided crucial information. It was confirmed that up to ≈38 MBq/μAh maximum production yield of 89Zr radionuclide, free from radio-isotopic impurities, can be achieved in the ≈5–13 MeV energy window. This information is not just essential, but it's profoundly enlightening for understanding the potential production capacity of the 89Y (p, n)89Zr route. It also guides us in planning practical supply options for medical applications using a small-sized cyclotron at proton-energies ≤13 MeV, enhancing our collective knowledge.
对医用重要放射性核素89Zr的生产进行了理论研究。这种放射性核素是在质子抛射与89y靶的相互作用中产生的,89y靶是一种易于获得的目标,纯度更高,约5-60 MeV。89Y (p, n)89Zr生产路线是医学成像和放射性药物开发领域的一条有前途的途径,由于它有可能生产89Zr,一种半衰期为78.41 h的放射性核素,适用于各种应用,因此引起了人们的极大兴趣。TALYS-1.95(G)预测生产截面与实验截面吻合较好。通过89Y (p, n)89Zr路径产生的89Zr放射性核素,预测的TALYS-1.95(G)与实验测量的生成截面之间存在强烈的Pearson正相关,进一步证实了这一成功的对准。此外,厚靶产量的计算也提供了重要的信息。结果表明,在≈5-13 MeV的能量窗内,89Zr核素的最大产率可达≈38 MBq/μAh,且不含放射性同位素杂质。这些信息不仅是必不可少的,而且对了解89Y (p, n)89Zr路线的潜在产能具有深远的启发意义。它还指导我们规划使用质子能量≤13兆电子伏的小型回旋加速器的医疗应用的实际供应选择,增强我们的集体知识。
{"title":"Theoretical predictions to produce medical 89Zr radionuclide via the 89Y(p, n)89Zr route at ≈ 5–60 MeV: Comparison of experimental and theoretical production data","authors":"F.K. Amanuel","doi":"10.1016/j.apradiso.2024.111599","DOIUrl":"10.1016/j.apradiso.2024.111599","url":null,"abstract":"<div><div>Theoretical investigations were carried out for the production of the medically important <sup>89</sup>Zr radionuclide. This radionuclide is produced in the interaction of a proton projectile with <sup>89</sup>Y-target, a readily available target with greater purity at ≈ 5–60 MeV. The <sup>89</sup>Y (p, n)<sup>89</sup>Zr production route, a promising avenue in the fields of medical imaging and radiopharmaceutical development, is of significant interest due to its potential to produce <sup>89</sup>Zr, a radionuclide with a half-life of 78.41 h, suitable for various applications.</div><div>The TALYS-1.95(G) predicted production cross-sections were in very good agreement with the experimental cross-sections. This successful alignment was further confirmed by a strong positive Pearson's correlation between the TALYS-1.95(G) predicted and experimentally measured production cross-sections for <sup>89</sup>Zr radionuclide produced via the <sup>89</sup>Y (p, n)<sup>89</sup>Zr route.</div><div>Furthermore, the calculations of thick target yields have provided crucial information. It was confirmed that up to ≈38 MBq/μAh maximum production yield of <sup>89</sup>Zr radionuclide, free from radio-isotopic impurities, can be achieved in the ≈5–13 MeV energy window. This information is not just essential, but it's profoundly enlightening for understanding the potential production capacity of the <sup>89</sup>Y (p, n)<sup>89</sup>Zr route. It also guides us in planning practical supply options for medical applications using a small-sized cyclotron at proton-energies ≤13 MeV, enhancing our collective knowledge.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111599"},"PeriodicalIF":1.6,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142779180","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
Potential of boron neutron capture therapy (BNCT) for myxofibrosarcoma 硼中子俘获治疗黏液纤维肉瘤的潜力。
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-26 DOI: 10.1016/j.apradiso.2024.111603
Takuya Fujimoto , Tooru Andoh , Tamotsu Sudo , Ikuo Fujita , Yoshinori Sakurai , Takushi Takata , Hiroki Tanaka , Teruya Kawamoto , Shunsuke Yahiro , Shotaro Nakamura , Hitomi Hara , Naomasa Fukase , Toshihiro Akisue , Hideki Ichikawa , Ryosuke Kuroda , Minoru Suzuki
Myxofibrosarcoma, a rare malignant tumor, predominantly affects the extremities of the elderly. Because of its invasive nature amputation is sometimes required, resulting in serious deterioration of quality of life. Therefore, cell lines established from amputated surgical specimens of myxofibrosarcoma in the upper limbs of elderly patients were used to create a myxofibrosarcoma-bearing animal model and to investigate the therapeutic effect of BNCT thereon. The results demonstrated selective destruction of tumor cells, suggesting the anti-tumor efficacy of BNCT on myxofibrosarcoma.
黏液纤维肉瘤是一种罕见的恶性肿瘤,主要影响老年人的四肢。由于其侵入性,有时需要截肢,导致生活质量严重下降。因此,我们利用老年患者上肢黏液纤维肉瘤手术切除标本建立细胞系,建立载黏液纤维肉瘤动物模型,并研究BNCT对其治疗效果。结果显示BNCT对黏液纤维肉瘤具有选择性破坏作用,提示BNCT对黏液纤维肉瘤具有抗肿瘤作用。
{"title":"Potential of boron neutron capture therapy (BNCT) for myxofibrosarcoma","authors":"Takuya Fujimoto ,&nbsp;Tooru Andoh ,&nbsp;Tamotsu Sudo ,&nbsp;Ikuo Fujita ,&nbsp;Yoshinori Sakurai ,&nbsp;Takushi Takata ,&nbsp;Hiroki Tanaka ,&nbsp;Teruya Kawamoto ,&nbsp;Shunsuke Yahiro ,&nbsp;Shotaro Nakamura ,&nbsp;Hitomi Hara ,&nbsp;Naomasa Fukase ,&nbsp;Toshihiro Akisue ,&nbsp;Hideki Ichikawa ,&nbsp;Ryosuke Kuroda ,&nbsp;Minoru Suzuki","doi":"10.1016/j.apradiso.2024.111603","DOIUrl":"10.1016/j.apradiso.2024.111603","url":null,"abstract":"<div><div>Myxofibrosarcoma, a rare malignant tumor, predominantly affects the extremities of the elderly. Because of its invasive nature amputation is sometimes required, resulting in serious deterioration of quality of life. Therefore, cell lines established from amputated surgical specimens of myxofibrosarcoma in the upper limbs of elderly patients were used to create a myxofibrosarcoma-bearing animal model and to investigate the therapeutic effect of BNCT thereon. The results demonstrated selective destruction of tumor cells<strong>,</strong> suggesting the anti-tumor efficacy of BNCT on myxofibrosarcoma.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111603"},"PeriodicalIF":1.6,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142779119","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 fission product yields in the quasi-mono-energetic neutron-induced fission of 238U 准单能中子诱导238U裂变产物产率的测量
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-26 DOI: 10.1016/j.apradiso.2024.111608
H. Naik , Meghna Karkera , Vibha Vansola , Santhi Sheela Yeraguntla , Mayur Mehta , S.V. Suryanarayana , R. Makwana , S.C. Sharma
The cumulative yield of the fission products within the mass range of 83–117 and 123–153 have been measured in the 6.61and 10.92 MeV quasi-mono-energetic neutron-induced fission of 238U by using an off-line γ-ray spectrometric technique. The neutron beams were obtained from the 7Li(p,n) reactions with the proton energies of 11 and 18.8 MeV. The mass chain yields were obtained from the cumulative yields by using charge distribution correction. The peak-to-valley (P/V) ratio, the average value of light mass (⟨AL⟩), heavy mass (⟨AH⟩) and the average number of neutrons (<ν>) were obtained from the mass yield data. The data in the 238U(n, f) reaction from the present work and literature at various energies were compared with the similar data in the 238U(γ, f) reaction and following observations were obtained. (i) In both the reactions, the mass yield distributions are double humped. (ii) The yield of fission products for A = 133–134, A = 138–139, and A = 143–144 and their complementary products are higher than those of other fission products due to the nuclear structure effect. (iii) The yield of symmetric product increases and thus the peak-to-valley (P/V) ratio decreases with excitation energy. (iv) With the increase of excitation energy, the <ν> vale increases in a similar way in both the reactions. (v) The changing trend of ⟨AL⟩ and ⟨AH⟩ values with the increase of excitation energy are entirely different in between the two reactions.
用脱机γ射线谱技术测量了238U准单能中子诱导裂变6.61和10.92 MeV的83 ~ 117和123 ~ 153质量范围内的裂变产物的累积产额。7Li(p,n)反应产生的中子束,质子能量分别为11和18.8 MeV。利用电荷分布校正,由累积产率得到质量链产率。峰谷比(P/V),轻质量(⟨AL⟩),重质量(⟨AH⟩)的平均值和中子数(<ν>)是从质量产率数据中获得的。本文将不同能量下238U(n, f)反应的数据与238U(γ, f)反应的类似数据进行了比较,得到了以下观察结果:(1)两种反应的质量产率分布均呈双峰状。(ii)由于核结构效应,A = 133-134、A = 138-139、A = 143-144及其互补产物的裂变产物产率高于其他裂变产物。(iii)随着激发能的增加,对称产物的产率增加,峰谷比(P/V)减小。(iv)随着激发能的增大,在两种反应中Vale以相似的方式增加。(v)在两个反应之间,⟨AL⟩和⟨AH⟩的值随着激发能的增加而变化的趋势是完全不同的。
{"title":"Measurement of fission product yields in the quasi-mono-energetic neutron-induced fission of 238U","authors":"H. Naik ,&nbsp;Meghna Karkera ,&nbsp;Vibha Vansola ,&nbsp;Santhi Sheela Yeraguntla ,&nbsp;Mayur Mehta ,&nbsp;S.V. Suryanarayana ,&nbsp;R. Makwana ,&nbsp;S.C. Sharma","doi":"10.1016/j.apradiso.2024.111608","DOIUrl":"10.1016/j.apradiso.2024.111608","url":null,"abstract":"<div><div>The cumulative yield of the fission products within the mass range of 83–117 and 123–153 have been measured in the 6.61and 10.92 MeV quasi-mono-energetic neutron-induced fission of <sup>238</sup>U by using an off-line γ-ray spectrometric technique. The neutron beams were obtained from the <sup>7</sup>Li(p,n) reactions with the proton energies of 11 and 18.8 MeV. The mass chain yields were obtained from the cumulative yields by using charge distribution correction. The peak-to-valley (P/V) ratio, the average value of light mass (⟨A<sub>L</sub>⟩), heavy mass (⟨A<sub>H</sub>⟩) and the average number of neutrons (&lt;ν&gt;) were obtained from the mass yield data. The data in the <sup>238</sup>U(n, f) reaction from the present work and literature at various energies were compared with the similar data in the <sup>238</sup>U(γ, f) reaction and following observations were obtained. (i) In both the reactions, the mass yield distributions are double humped. (ii) The yield of fission products for A = 133–134, A = 138–139, and A = 143–144 and their complementary products are higher than those of other fission products due to the nuclear structure effect. (iii) The yield of symmetric product increases and thus the peak-to-valley (P/V) ratio decreases with excitation energy. (iv) With the increase of excitation energy, the &lt;<em>ν</em>&gt; vale increases in a similar way in both the reactions. (v) The changing trend of ⟨<em>A</em><sub>L</sub>⟩ and ⟨<em>A</em><sub>H</sub>⟩ values with the increase of excitation energy are entirely different in between the two reactions.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111608"},"PeriodicalIF":1.6,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142756775","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 non-thermoluminescent CaSO4:Dy dosimeters 新型非热释光CaSO4:Dy剂量计
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-24 DOI: 10.1016/j.apradiso.2024.111606
A.I. Castro-Campoy , C. Cruz-Vázquez , R. Pérez-Salas , V.M. Castaño , R. Bernal
The non-thermoluminescence afterglow-based dosimetry performance of self-agglomerating pellet-shaped CaSO4:Dy phosphors synthesized through a low-cost, environmentally friendly method is first reported. Thermoluminescence (TL) and afterglow (AG) were analyzed in samples exposed to beta particle irradiation in the dose range from 0.06 to 8.0 Gy. Characteristic TL glow curves consist of an intense TL maximum at 134 °C, a shoulder at 200 °C, and a maximum at 447 °C. CaSO4:Dy exhibits a highly sensitive AG response for 24 h with linear behavior from 0.06 Gy to 8.0 Gy. A remarkable reproducibility of both the TL and the AG response was observed in repeated irradiation–readout cycles with no need for pre-irradiation annealing. The synthesized CaSO4:Dy exhibits promising properties to be used as an AG-based dosimeter for real-time radiation detection and dosimetry. Moreover, this phosphor might be applied as a long persistent phosphor (LPP), being a cost-effective alternative to other available LPPs.
本文首次报道了一种低成本、环境友好的方法合成的自凝聚球团状CaSO4:Dy荧光粉的非热释光余辉剂量学性能。研究了在0.06 ~ 8.0 Gy剂量范围内β粒子辐照样品的热释光(TL)和余辉(AG)。特征TL发光曲线包括134°C时的强烈TL最大值,200°C时的肩部和447°C时的最大值。CaSO4:Dy在0.06 Gy ~ 8.0 Gy范围内表现出高度敏感的24 h AG响应。在不需要辐照前退火的情况下,在重复辐照-读出循环中观察到TL和AG响应的显著再现性。合成的CaSO4:Dy具有良好的性能,可作为基于ag的剂量计用于实时辐射检测和剂量测定。此外,该荧光粉可以作为长持久性荧光粉(LPP)应用,是其他可用的长持久性荧光粉的一种具有成本效益的替代品。
{"title":"Novel non-thermoluminescent CaSO4:Dy dosimeters","authors":"A.I. Castro-Campoy ,&nbsp;C. Cruz-Vázquez ,&nbsp;R. Pérez-Salas ,&nbsp;V.M. Castaño ,&nbsp;R. Bernal","doi":"10.1016/j.apradiso.2024.111606","DOIUrl":"10.1016/j.apradiso.2024.111606","url":null,"abstract":"<div><div>The non-thermoluminescence afterglow-based dosimetry performance of self-agglomerating pellet-shaped CaSO<sub>4</sub>:Dy phosphors synthesized through a low-cost, environmentally friendly method is first reported. Thermoluminescence (TL) and afterglow (AG) were analyzed in samples exposed to beta particle irradiation in the dose range from 0.06 to 8.0 Gy. Characteristic TL glow curves consist of an intense TL maximum at 134 °C, a shoulder at 200 °C, and a maximum at 447 °C. CaSO<sub>4</sub>:Dy exhibits a highly sensitive AG response for 24 h with linear behavior from 0.06 Gy to 8.0 Gy. A remarkable reproducibility of both the TL and the AG response was observed in repeated irradiation–readout cycles with no need for pre-irradiation annealing. The synthesized CaSO<sub>4</sub>:Dy exhibits promising properties to be used as an AG-based dosimeter for real-time radiation detection and dosimetry. Moreover, this phosphor might be applied as a long persistent phosphor (LPP), being a cost-effective alternative to other available LPPs.</div></div>","PeriodicalId":8096,"journal":{"name":"Applied Radiation and Isotopes","volume":"217 ","pages":"Article 111606"},"PeriodicalIF":1.6,"publicationDate":"2024-11-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142746261","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
Investigating cross-section effects on HPGe detector response through computational and empirical approaches 通过计算和经验方法研究横截面对 HPGe 探测器响应的影响。
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-23 DOI: 10.1016/j.apradiso.2024.111596
Ghada Mellak , Wassila Boukhenfouf , Fatma Zohra Dehimi , Adnane Messai , Nour Eddine Hebboul
The combination of experimental measurements and simulations provides valuable insights into the performance and limitations of gamma-ray spectrometry, especially within a specified energy range. This study investigates the impact of cross-section variations on the response of high-purity germanium (HPGe) detectors, focusing on the energy range from 53 keV to 1408 keV.
Monte Carlo simulations using the MCNP5 code with two different cross-section libraries, ENDF/B.VI and JENDL-5, are conducted alongside a semi-empirical method utilizing ANGLE 4.0 software. This approach allows for a comprehensive exploration of how cross-section variations affect HPGe detector response.
The flexibility in library selection highlights the adaptability of MCNP to cater to specific energy requirements. The calculated efficiencies are then compared with experimental data to evaluate accuracy and reliability. The results reveal an agreement within [2–3%] between experimental and simulated values, particularly for energies above 121 keV. Notably, for low-energy ranges (53–121 keV), the ENDF/B.VI library achieves an accuracy within [3–5%], making it effective at capturing low-energy interactions and enhancing prediction precision. This accuracy highlights its suitability for capturing low-energy interactions and enhances prediction precision.
Overall, this study provides valuable insights into detector performance and underscores the significance of library choice in ensuring simulation accuracy.
实验测量和模拟相结合,为了解伽马射线光谱仪的性能和局限性,特别是在特定能量范围内的性能和局限性提供了宝贵的见解。本研究调查了截面变化对高纯锗(HPGe)探测器响应的影响,重点是 53 keV 至 1408 keV 的能量范围。在使用 MCNP5 代码和两个不同的截面库(ENDF/B.VI 和 JENDL-5)进行蒙特卡罗模拟的同时,还利用 ANGLE 4.0 软件进行了半经验法模拟。这种方法可以全面探索截面变化如何影响 HPGe 探测器的响应。库选择的灵活性凸显了 MCNP 满足特定能量要求的适应性。然后将计算出的效率与实验数据进行比较,以评估准确性和可靠性。结果表明,实验值和模拟值的一致性在 [2-3%] 以内,特别是在 121 keV 以上的能量范围。值得注意的是,对于低能范围(53-121 千伏),ENDF/B.VI 库的精确度在 [3-5%] 以内,这使它能有效捕捉低能相互作用并提高预测精度。这一精确度突出了ENDF/B.VI库在捕捉低能相互作用和提高预测精确度方面的适用性。总之,这项研究为探测器的性能提供了宝贵的见解,并强调了选择库在确保模拟精度方面的重要性。
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引用次数: 0
Detection of β-ray from 3H with back illuminated sCMOS imager 背照sCMOS成像仪对3H β射线的检测
IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Pub Date : 2024-11-23 DOI: 10.1016/j.apradiso.2024.111604
Makoto Sasano , Masateru Hayashi , Nobukazu Teranishi
Tritium occurs in nuclear power plants. The energy of beta-rays from tritium is so low that detecting the beta-rays is challenging. Therefore, method of measuring tritium surface contamination is required. Liquid scintillators are generally used to measure the beta-rays. However, this method is complicated to use on-site. To measure tritium surface contamination on-site, we attempted to detect tritium using the GSENSE2020BSI back-illuminated sCMOS imager.
We used a tritium areal radiation source to validate the detection of beta rays from tritium. The beta-rays cause bright spots in images and spread to multipixel. The average number of the pixels by the beta-rays was 4.6 and covered within a 3x3 pixel region. The energy spectrum from 10,000 images with 3x3 binning patterns showed a continuous shape spectrum. The spectra shape was characteristic of beta-ray spectra, demonstrating that the energy spectrum could be obtained with low-energy beta rays from tritium using the back-illuminated sCMOS image sensor. The spectral shape was produced from a radiation simulation using Geant4. From the simulation, the sCMOS sensor was able to measure tritium contamination of 10 becquerels (Bq)/cm2 within 100 s and 4 Bq/cm2 within 480 s.
氚存在于核电站中。氚射线的能量很低,探测到射线是很有挑战性的。因此,需要一种测量氚表面污染的方法。液体闪烁体通常用于测量射线。然而,这种方法在现场使用起来很复杂。为了在现场测量氚表面污染,我们尝试使用GSENSE2020BSI背光sCMOS成像仪检测氚。我们使用氚面辐射源来验证从氚中检测到的射线。射线会在图像中产生亮点,并扩散到多个像素。射线的平均像素数为4.6,覆盖在3x3像素区域内。1万张3 × 3分形图像的能谱显示出连续的形状谱。光谱形状具有β射线谱的特征,表明利用背照式sCMOS图像传感器可以获得氚低能β射线的能谱。光谱形状是通过使用Geant4进行辐射模拟产生的。模拟结果表明,该传感器能够在100秒内测量到10贝克勒尔(Bq)/cm2的氚污染,在480秒内测量到4贝克勒尔/cm2的氚污染。
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Applied Radiation and Isotopes
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