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The Evaluation of a Simple Measurement Method using NaI(Tl) Scintillation Survey-Meter for Radiation Safety Management of Radioactivated Armor Tiles of LHD Vacuum Vessel 用NaI(Tl)闪烁测量仪对LHD真空容器放射性护甲瓦辐射安全管理的简单测量方法评价
Pub Date : 1900-01-01 DOI: 10.12950/rsm.210416
Makoto I. Kobayashi, N. Suzuki, T. Saze, H. Miyake, K. Nishimura, H. Hayashi, T. Kobuchi, K. Ogawa, M. Isobe, M. Osakabe
1),2) In this study, the application of a simple measurement method using NaI(Tl) scintillation survey-meter to detect the gamma-rays in the armor tiles of LHD vacuum vessel exposed to fast neutrons during deuterium plasma experiments was evaluated to control the occupational exposure for the storage of huge numbers of the armor tiles. The gamma-ray spectrometry for an activated armor tile by high-purity germanium detector (HPGe) showed the gamma-ray peaks from 58 Co, 54 Mn and 60 Co. The detection efficiencies of these nuclides for HPGe were evaluated by PHITS to estimate the concentrations of these nuclides. The radiation transport model for HPGe in PHITS were validated by the gamma-ray measurements for sealed gamma-ray sources. Then, the detection efficiencies of these nuclides for NaI(Tl) scintillation survey-meter were also evaluated by the same manner using PHITS. The predicted dose rate of the activated armor tiles in NaI(Tl) scintillation survey-meter was consistent with the actual measurement. The predicted count rate in NaI(Tl) scintillation survey-meter for 60 Co, which will be a deterministic nuclide in the armor tile due to longer half-life, in the clearance level was sufficiently higher than the minimum detectable count rate of NaI(Tl) scintillation survey-meter with a simple shielding for environmental radiation.
1)、2)本研究利用NaI(Tl)闪烁测量仪对LHD真空容器在氘等离子体实验中暴露于快中子中的装甲瓦进行了简单的测量,以控制大量装甲瓦储存的职业暴露。高纯锗探测器(HPGe)对活化装甲砖的伽马能谱分析显示了58 Co, 54 Mn和60 Co的伽马射线峰。通过PHITS评估了这些核素对HPGe的探测效率,以估计这些核素的浓度。通过密封伽玛射线源的伽玛射线测量,验证了高温锗在PHITS中的辐射输运模型。然后,用PHITS对这些核素在NaI(Tl)闪烁测量仪上的探测效率进行了同样的评价。NaI(Tl)闪烁测量仪对活性装甲片的预测剂量率与实际测量结果一致。由于具有较长的半衰期,60 Co将成为装甲层中的确定核素,在间隙水平上,NaI(Tl)闪烁测量仪的预测计数率足以高于具有简单环境辐射屏蔽的NaI(Tl)闪烁测量仪的最小可探测计数率。
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引用次数: 1
Factors affecting 137Cs concentration in wild plants and soils of different land use in Iitate village after the Fukushima nuclear power plant accident 福岛核电站事故后Iitate村不同土地利用方式野生植物和土壤中137Cs浓度的影响因素
Pub Date : 1900-01-01 DOI: 10.12950/RSM.180918
Nittaya Wakai, J. Yamashita, T. Enomoto, T. Hanafusa, T. Ono, M. Maeda
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引用次数: 2
Investigation of Radiocesium Migration from Land to Waterbody using Radiocesium Distribution and Soil to Sediment Ratio: A Case of the Steep Slope Catchment Area of Ogi Reservoir, Kawauchi Village, Fukushima 利用放射性分布和土沙比研究放射性从陆地向水体的迁移——以福岛川内村Ogi水库陡坡集水区为例
Pub Date : 1900-01-01 DOI: 10.12950/rsm.190924
Triyono Basuki, W. Bekelesi, Masaya Tsujimoto, S. Nakashima
In the present study, we reported the investigation of radiocesium migration from steep slope surrounding catchment to water body based on the radiocesium distribution and soil to sediment ratio. It was confirmed that the radiocesium was derived from the Fukushima accident by considering the 134 Cs to 137 Cs ratio corrected to the released day which is about 1. We found the higher radiocesium inventory in higher elevation area and steep slope forest catchment, revealing the atmospheric dry initial deposition-derived radiocesium and high retention of the forest zone. The radiocesium distribution data revealed that the radiocesium migrated more from the transition zone to the water body than from forest catchment, and accumulated in the deeper layer of sediment. The lower value of 137 Cs soil to sediment ratio provided an evidence of radiocesium migration from the catchment and its accumulation in the sediment. The physicochemical property of surface soil was revealed as one of the possible factors of radiocesium high retention in forest catchment.
本文基于放射性元素的分布和土沙比,研究了放射性元素从流域周围陡坡向水体的迁移。考虑到放射性铯与放射性铯的比值(按释放日校正后约为1),可以确定放射性铯来自福岛核事故。研究发现,高海拔地区和陡坡森林流域的放射性元素库存量较高,揭示了大气干初始沉积导致的放射性元素库存量和森林地区放射性元素的高滞留。放射性分布数据表明,放射性从过渡带向水体的迁移比从森林集水区迁移的多,并在沉积物的较深层积累。低137cs土沙比证明了放射性铯从流域迁移并在沉积物中积累。揭示了表层土壤的理化性质是森林流域放射性高滞留的可能因素之一。
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引用次数: 2
Dispersal rates of astatine-211 from aqueous solutions and chloroform 砹-211在水溶液和氯仿中的扩散速率
Pub Date : 1900-01-01 DOI: 10.12950/rsm.190423
A. Toyoshima, Kojiro Nagata, K. Ooe, Zijian Zhang, Takumi Ikeda, Soichiro Ichimura, Honoka Obata, T. Yoshimura, A. Shinohara
The dispersal rates of 211 At, which is a promising nuclide for targeted alpha therapy, from aqueous solutions and chloroform were studied to provide experimental evidence for the reasonable evaluation of its airborne concentration in a radiation-controlled area. Using a collection unit for dispersed 211 At during ventilation, radioactivity of the trapped 211 At was quantified. The dispersal rates of 211 At in chloroform as well as acidic, neutral, and alkaline solutions, in addition to a neutral solution containing ascorbic acid, were determined. Thin-layer chromatography was also performed to identify the formed chemical species of 211 At. The dispersal rate of 211 At was very low in the neutral solution containing ascorbic acid and in chloroform. The chemical forms of 211 At in aqueous solutions are also briefly discussed.
研究了211 At在水溶液和氯仿中的扩散速率,为其在辐射控制区空气中浓度的合理评价提供了实验依据。211 At是一种有前景的靶向α治疗核素。利用通风过程中分散的211 At收集装置,定量捕获的211 At的放射性。测定了211 At在氯仿、酸性、中性和碱性溶液以及含有抗坏血酸的中性溶液中的分散速率。用薄层色谱法鉴定了211 At的形成化学种类。211 At在含抗坏血酸的中性溶液和氯仿中的分散速率很低。并简要讨论了211 At在水溶液中的化学形态。
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引用次数: 5
Investigation of Concrete Radioactivation in Cyclotron Type Proton Therapy Facilities using in situ 24Na Measurement Method 用24Na原位测量法研究回旋型质子治疗设备中混凝土的放射性
Pub Date : 1900-01-01 DOI: 10.12950/rsm.200909
H. Matsumura, G. Yoshida, A. Toyoda, K. Masumoto, Hajime Nakamura, T. Miura, K. Nishikawa, K. Bessho, T. Akita, S. Katsuta, T. Akimoto, Y. Sugama, F. Nobuhara, Yoko Nagashima
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引用次数: 0
Monthly Change in Radioactivity Concentration of 137Cs, 134Cs, and 40K of Paddy Soil and Rice Plants in Fukushima Prefecture 福岛县水稻土壤和水稻137Cs、134Cs和40K放射性浓度的月变化
Pub Date : 1900-01-01 DOI: 10.12950/rsm.181219
Masaya Tsujimoto, S. Miyashita, H. Nguyen, S. Nakashima
Monthly fieldwork was conducted in the paddies of Fukushima Prefecture in 2016, to obtain samples of the paddy soil and rice plants. The monthly change in the radioactivity concentrations of 137 Cs, 134 Cs, and 40 K of the samples was investigated, using a germanium semiconductor detector. Three-phase transfer factors (TFs) of 137 Cs from the paddy soil to the roots (TF 1 ), from the roots to the leaves (TF 2 ), and from the leaves to the ears (TF 3 ) of rice plants were calculated. The results showed that the radioactivity concentration of 137 Cs and 134 Cs in the paddy soil varied seasonally, while the concentration of 40 K showed an almost opposite seasonal change compared to 137 Cs and 134 Cs. The radioactivity concentration of 137 Cs and 134 Cs in the roots increased 60 days after planting, while the concentration of 40 K decreased. Furthermore, the radioactivity concentration of 137 Cs, 134 Cs, and 40 K in the leaves and ears decreased over time. Correlations of the TFs of 137 Cs with the radioactivity concentration of 40 K suggested that 137 Cs and 40 K were competitively absorbed by the roots, however, they were transported to the leaves and ears in the same manner. In conclusion, the transportation of 137 Cs (TF 2 and TF 3 ) in rice plants was high despite the low absorption of 137 Cs (TF 1 ) in the early stage of rice growth. Therefore, it is recommended that the potassium concentration in the paddy should be high during the early stage of growth to prevent radioactive cesium contamination.
2016年每个月在福岛县稻田进行实地调查,获取水稻土壤和水稻植株样本。利用锗半导体探测器,研究了样品中137cs、134cs和40k放射性浓度的月变化。计算了水稻土壤向根系(TF 1)、根系向叶片(TF 2)和叶片向穗部(TF 3)的137cs三相传递系数。结果表明,水稻土中137cs和134cs的放射性浓度呈季节变化,而40k的放射性浓度与137cs和134cs的放射性浓度的季节变化几乎相反。种植后60 d,根内137cs和134cs的放射性浓度升高,40k浓度降低。叶片和穗中137cs、134cs和40k的放射性浓度随时间的增加而降低。137cs的TFs与40k放射性浓度的相关性表明,137cs和40k被根系竞争性吸收,但它们以相同的方式被输送到叶片和穗。综上所述,水稻生长前期对137cs (tf1)的吸收较低,但对137cs (TF 2和TF 3)的运输量较高。因此,建议在水稻生长初期提高钾浓度,防止放射性铯污染。
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引用次数: 3
Dispersion of Alpha-Nuclides during Animal Experiments α -核素在动物实验中的分散
Pub Date : 1900-01-01 DOI: 10.12950/rsm.210519
K. Kaneda-Nakashima, Zijian Zhang, Kojiro Nagata, K. Shirasaki, H. Kikunaga, T. Yamamura, K. Ooe, T. Watabe, A. Toyoshima, T. Yoshimura, A. Shinohara
The dispersions of short-lived radionuclides emitting a -particles, such as 223 Ra, 211 At, and 225 Ac, during animal experiments were measured for radiation safety management. These three radionuclides dispersed from mice were trapped using charcoal-impregnated filters, and those in feces were collected directly, and those in urine were recovered with bedding in a breeding cage. For all the radionuclides, uptakes by tissues were also further examined after dissection. The radioactivity of each radionuclide was evaluated with a g -ray scintillation counter using daughter nuclide. In tumor bearing mice, 211 At and 223 Ra accumulated in tumor tissues with high affinity and less accumulated in other tissues. It was noted that all the three radionuclides were not exhausted or evaporated from the breeding cages and the peak of excretions of the radionuclides in the animal experiments was observed within twenty-four hours.
在动物实验中测量了释放a -粒子(如223 Ra、211 At和225 Ac)的短寿命放射性核素的扩散,用于辐射安全管理。这三种放射性核素分散在小鼠体内,采用炭浸透过滤器捕获,粪便中的放射性核素直接收集,尿液中的放射性核素在饲养笼中垫料回收。对于所有放射性核素,解剖后还进一步检查了组织的摄取情况。利用子核素用g射线闪烁计数器对每种放射性核素的放射性进行了评价。在荷瘤小鼠中,211 At和223 Ra在肿瘤组织中有高亲和力积累,在其他组织中积累较少。注意到这三种放射性核素并没有全部从饲养笼中排出或蒸发,并且在动物实验中观察到放射性核素的排泄高峰是在24小时内。
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引用次数: 0
Cleaning Materials and Methods for Effective Removal of Indoor Radioactive Contamination 有效清除室内放射性污染的清洁材料和方法
Pub Date : 1900-01-01 DOI: 10.12950/rsm.200213
T. Takemoto, K. Ohsawa, N. Matsuda
To support the safe return of residents after the TEPCO Fukushima Daiichi Nuclear Power Plant accident, cleaning methods and materials for the removal of radiocesium (Cs) from household surfaces were compared. A spot contaminated with Cs on a vinyl floor sheet or a glass plate was wiped in different moisture conditions with different cleaning materials, including a paper sheet, cellulose sponge, polyester sheet, and a polyesterpolyamide sheet. Radioactive solid particles on a vinyl sheet were wiped with miniature mops made of cellulose sponge, polyester microfiber, or cotton yarn. There was little difference in the removal of radioactivity among cleaning materials when the contaminated spot was wiped in wet conditions. The removal of contaminated particles depended on the structure of the mop. The use of an abrasive and a detergent worked well for the vinyl sheet and the glass plate, respectively. These observations suggested that, in appropriate conditions, effective decontamination was achievable by regular indoor cleaning with commercially available cleaning devices.
为了支持东京电力公司福岛第一核电站事故后居民的安全返回,比较了家用表面去除放射性铯的清洁方法和材料。在不同的湿度条件下,使用不同的清洁材料,包括纸张、纤维素海绵、聚酯片材和聚酯聚酰胺片材,擦拭乙烯基地板或玻璃板上的Cs污染点。用纤维素海绵、聚酯微纤维或棉纱制成的微型拖把擦拭乙烯基薄片上的放射性固体颗粒。当污染点在潮湿条件下擦拭时,不同的清洁材料在去除放射性方面差别不大。污染颗粒的清除取决于拖把的结构。使用磨料和清洁剂分别对乙烯基板和玻璃板效果很好。这些观察结果表明,在适当的条件下,使用市售清洁设备定期进行室内清洁可以实现有效的去污。
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引用次数: 0
Survey Methodology for the Activation of Beamline Components in an Electrostatic Proton Accelerator 静电质子加速器中光束线元件活化的测量方法
Pub Date : 1900-01-01 DOI: 10.12950/RSM.200813
G. Yoshida, H. Matsumura, Hajime Nakamura, A. Toyoda, K. Masumoto, T. Miura, K. Sasa, T. Moriguchi
To establish a systematic guideline for accelerator decommissioning, as a case study, beamline activation of 12 MeV-proton electrostatic accelerator was investigated employing a survey meter and g -ray spectrometers. Beam loss points where reflected as high dose-rate area were identified, and generated nuclides and their activities were determined. Almost beamline components are made from stainless steel and 52 Mn and 56 Co were detected as principal induced activities. It was found that the 56 Co activity significantly contribute to the dose rate value denoted on the survey meter. From the beam operation history and the monitor currents of Faraday-cups, we revealed the beam loss on a certain point significantly reflects the 52 Mn activity on there. Induced activities of 52 Mn and 56 Co on the certain point of the beamline could be reproduced by the contact dose-rate on that point.
为了建立系统的加速器退役指导方针,以12 mev质子静电加速器为例,采用测量仪和g射线能谱仪对其束流激活进行了研究。确定了反映为高剂量率区域的光束损耗点,并确定了产生的核素及其活性。几乎束线成分由不锈钢制成,检测到52 Mn和56 Co为主要诱导活性。结果发现,56 Co的活性对测量仪上所示的剂量率值有显著影响。从法拉第杯的束流运行历史和监测电流来看,我们发现某一点上的束流损耗显著地反映了该点上的52mn活度。52 Mn和56 Co在光束线某一点上的诱导活性可以用该点上的接触剂量率来再现。
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引用次数: 2
Transfer Rates of 225Ac to Exhaust Air, Surface, and Waste Water under Chemical Operations 在化学操作下,225Ac向废气,表面和废水的传输速率
Pub Date : 1900-01-01 DOI: 10.12950/rsm.191219
T. Yamamura, K. Shirasaki, H. Kikunaga, Kojiro Nagata, Zijian Zhang, K. Washiyama, A. Toyoshima, T. Yoshimura, A. Shinohara
1) Laboratory of Alpha-ray Emitters, Institute for Materials Research, Tohoku University, Miyagi 980-8577, Japan 2) Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka 590-0494, Japan 3) Research Center for Electron Photon Science, Tohoku University, Miyagi 982-0826, Japan 4) Radioisotope Research Center, Institute for Radiation Sciences, Osaka University, Osaka 565-0871, Japan 5) Department of Chemistry, Graduate School of Science, Osaka University, Osaka 560-0043, Japan 6) Advanced Clinical Research Center, Fukushima Medical University, Fukushima 960-1295, Japan 7) Division of Science, Institute for Radiation Sciences, Osaka University, Osaka 560-0043, Japan
1)东北大学材料研究所α射线发射体实验室,日本宫城980-8577 2)京都大学综合辐射与核科学研究所,日本大阪590-0494 3)东北大学电子光子科学研究中心,日本宫城982-0826 4)大阪大学辐射科学研究所放射性同位素研究中心,日本大阪565-0871 5)大阪大学理学院化学系,大阪560-0043日本福岛医科大学先进临床研究中心,福岛960-1295;大阪大学放射科学研究所科学部,大阪560-0043
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引用次数: 2
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Radiation Safety Management
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