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A Study on Radiation Hazard of Granite and Marble Widely Used in Jordan Using Gamma Ray Spectrometer 用伽马射线谱仪研究约旦广泛使用的花岗岩和大理石的辐射危害
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-04-11 DOI: 10.17146/aij.2022.1184
A. Akour, S. Shakhatreh
Granite and marble are widely used in building construction, so possible radioactive nuclides inside them may contribute to the exposure dose to human health. The purpose of this study was to investigate the natural radioactivity concentration and assess the radiological risk limits and health care. The samples of marble and granite were pulverized into small, fine, smooth pieces and counted with the GAMMA-X (GMX) spectrometer to measure the radioactivity concentrations of 238 U, 232 Th, and 40 K. The radiological dose, internal and external hazards, and radium equivalent activity were calculated with a standard formula. The results showed that the radioactive concentrations of 238 U, 232 Th, and 40 K in granite were higher than those in marble. The external hazard for granite samples was below unity, while its internal hazard exceeded unity. The radium equivalent activity did not exceed the critical legal level of 370 Bq/kg as a safe level. For marble, the external and internal hazards and radium equivalent activities showed good agreement with the safe construction level. Its external and internal hazards were less than unity, whereas the radium equivalent activities were less than the critical legal level.
花岗岩和大理石广泛用于建筑施工,因此其内部可能存在的放射性核素可能会增加人体健康的暴露剂量。本研究的目的是调查天然放射性浓度,评估放射性风险限值和医疗保健。大理石和花岗岩样品被粉碎成小、细、光滑的碎片,并用GAMMA-X(GMX)光谱仪计数,以测量238 U、232 Th和40 K的放射性浓度。放射性剂量、内部和外部危害以及镭当量活度用标准公式计算。结果表明,花岗岩中238U、232Th和40K的放射性浓度均高于大理石。花岗岩样品的外部危害低于统一性,而内部危害超过统一性。镭当量活度没有超过370 Bq/kg的安全临界法定水平。大理石的内外危害和镭当量活动与安全施工水平基本一致。它的外部和内部危害还不到统一,而镭当量活动还不到关键的法律水平。
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引用次数: 1
Correlations Between Body Weight and Size-Specific Dose Estimate on Thoracic Computed Tomography Examination 胸部计算机断层扫描检查中体重和尺寸比剂量估计的相关性
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-04-06 DOI: 10.17146/aij.2022.1114
A. L. Wati, C. Anam, A. Nitasari, S. Syarifudin, G. Dougherty
The dose received by a patient on CT examination is expressed in size-specific dose estimates (SSDE) which is a function of the patient diameter, x-ray attenuation, and scanner output (volume computed tomography dose index, CTDIvol). Patient diameter and x-ray attenuation are represented as water equivalent diameter (Dw). We conducted the research to analyze the relationships between body weight and Dw, CTDIvol, and size-specific dose estimates (SSDE) in contrast-enhanced thorax examinations. We used images from 100 patients (50 women and 50 men patients) whose weight range from 2.8 kg to 80 kg. The values of Dw, CTDIvol, and SSDE were automatically calculated from axial CT images using the IndoseCT software. Statistical analysis showed that the patient's body weight correlates linearly with the Dw. The linearity coefficient (R2) values for body weight and Dw is 0.43 (women) and 0.55 (men). However, weight was independent of the patient dose in terms of CTDIvol and SSDE. This was because the CT system used tube current modulation (TCM), which automatically adapted the tube current to patient size, resulting in a relatively constant dose regardless of the patient size (Dw).
患者在CT检查中接受的剂量以尺寸特异性剂量估计值(SSDE)表示,该剂量估计值是患者直径、x射线衰减和扫描仪输出(体积计算机断层扫描剂量指数,CTDIvol)的函数。患者直径和x射线衰减表示为水当量直径(Dw)。我们进行了这项研究,以分析胸部造影检查中体重与Dw、CTDIvol和大小特异性剂量估计值(SSDE)之间的关系。我们使用了100名患者(50名女性和50名男性患者)的图像,这些患者的体重范围为2.8 kg至80 kg。使用IndoseCT软件根据轴向CT图像自动计算Dw、CTDIvol和SSDE的值。统计分析表明,患者的体重与Dw呈线性相关。体重和Dw的线性系数(R2)值分别为0.43(女性)和0.55(男性)。然而,就CTDIvol和SSDE而言,体重与患者剂量无关。这是因为CT系统使用了管电流调制(TCM),它会根据患者的大小自动调整管电流,从而产生相对恒定的剂量,而与患者的大小无关(Dw)。
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引用次数: 4
Effect of Sub-energy Windows’ Parameters on the Triple Energy Window Scatter Correction Method Accuracy in 99mTc SPECT Imaging 亚能窗参数对99mTc-SPECT成像三能窗散射校正方法精度的影响
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-04-04 DOI: 10.17146/aij.2022.1119
H. Saikouk, N. Khayati, A. Matrane
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引用次数: 0
In Vitro Release of Metformin HCl from Polyvinyl Alcohol (PVA) - Gelatin Hydrogels Prepared by Gamma Irradiation 伽玛辐照制备聚乙烯醇-明胶水凝胶对盐酸二甲双胍的体外释放研究
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-04-02 DOI: 10.17146/aij.2022.1123
H. Hariyanti, E. Erizal, E. Mustikarani, I. Lestari, F. Lukitowati
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引用次数: 0
Detection of Spoilage in Canned Pasteurized Milk Using the Radiographic Imaging Technique 用射线成像技术检测巴氏灭菌乳罐头中的变质
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-04-02 DOI: 10.17146/aij.2022.1161
D. T. Thuy, H. B. Tien, H. B. Ngọc, T. T. Kim, T. T. Ngoc
After packed into sterilized containers with a closed and rigorous process, pasteurized milk has been ensured for its hygiene and safety factors. However, distortions can occur during storage and transportation, causing the container to open, allowing harmful microorganisms to enter and damage the product. This research proposed a radiographic imaging technique to detect and evaluate the spoilage of canned pasteurized milk. The X-ray images show that the milk cans, which were left open for three days at 300 K, indicated regions with abnormal density with the smallest detectable size from 100 µm or larger. Density heterogeneity would be clearer in the following days and depending on the sample. An algorithm was developed to identify spoilage products automatically with an accuracy of up to 100 % and a speed of 0.0057 s/product. This approach may be suitable for industrial scale to control the quality of dairy products.
巴氏杀菌奶经过封闭、严格的包装,装入灭菌容器后,保证了其卫生和安全系数。然而,在储存和运输过程中会发生变形,导致容器打开,使有害微生物进入并损坏产品。本研究提出了一种射线成像技术来检测和评价罐装巴氏杀菌牛奶的腐败。x射线图像显示,在300 K下打开三天的牛奶罐显示密度异常区域,最小可检测尺寸在100µm或更大。在接下来的几天里,密度的不均匀性会更明显,这取决于样品。开发了一种自动识别腐败产品的算法,准确率高达100%,速度为0.0057 s/个产品。该方法适用于工业规模的乳制品质量控制。
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引用次数: 0
Systematic Projected Shell Model Study of Even-Even Dysprosium Isotopes 偶偶镝同位素的系统投影壳模型研究
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-03-30 DOI: 10.17146/aij.2022.1190
H. Aghahasani, S. Mohammadi, Z. Sajjadi
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引用次数: 0
The Effects of High Level Natural Radiation in Mamuju - Indonesia on the Immune System of Its Residents 印尼马穆朱高水平自然辐射对居民免疫系统的影响
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-03-30 DOI: 10.17146/aij.2022.1118
D. Darlina, T. Rahardjo, H. N. E. Surniyantoro, N. Rahajeng, M. Syaifudin
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引用次数: 0
The Evaluation of Fission Barrier Height by Fission Toy Model Approach 用裂变玩具模型法评价裂变势垒高度
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-03-28 DOI: 10.17146/aij.2022.1154
R. Kurniadi, Z. Suud, Y. S. Perkasa
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引用次数: 0
Skin Dosimetric Comparison of 3DCRT and IMRT Planning for Post-Mastectomy Breast Radiotherapy 乳腺切除术后3DCRT和IMRT皮肤放射治疗方案的剂量比较
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-03-24 DOI: 10.17146/aij.2022.1105
F. K. Hentihu, A. Anto, R. S. Nugroho
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引用次数: 1
Assessment of TMSR-500 Shutdown Capability TMSR-500关机能力评估
IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2022-03-15 DOI: 10.17146/aij.2022.1145
A. Khakim, F. R. Firmanda, Y. Pramono, S. Suharyana
The molten salt reactor (MSR) is a generation IV reactor with liquid fuel having nearly zero excess reactivity. Due to the very low excess reactivity, it requires a small number of control rods worth to shut down the reactor. However, as it operates at high temperatures, the core reactivity increases as the fuel temperature cools down during shutdown. In such a case, the control rods might not be able to keep the reactor at a subcritical state, and consequently, the fuel must be removed from the core for long-term shutdown into a fuel drain tank (FDT) below the core. This paper is intended to assess the shutdown capability of the first active shutdown system and fuel drain tank of ThorCon MSR by doing neutronic calculations with MCNP6. The results indicated that the control rods having reactivity worth -1.699 %dk/k are unable to maintain the core at a subcritical state as the core excess reactivity increases to +7.760 %dk/k when the fuel reaches room temperature. Therefore, the fuel must be drained to FDT to be cooled down and kept subcritical. Evaluation for various cases of FDT produced the highest multiplication factor of 0.57008 ± 0.00004 at the most conservative condition. The multiplication factor is well below the critical state of 1.0. The evaluations suggest that soon after the control rods shut the reactor down, the fuel has to be drained to FDT to maintain shutdown condition and dissipate the decay heat.
熔盐堆(MSR)是采用液体燃料的第四代反应堆,其反应性几乎为零。由于极低的过量反应性,它需要少量的控制棒来关闭反应堆。然而,当它在高温下运行时,堆芯的反应性随着燃料温度的降低而增加。在这种情况下,控制棒可能无法将反应堆保持在亚临界状态,因此,燃料必须从堆芯中取出,并长期关闭到堆芯下方的燃料排放罐(FDT)中。本文利用MCNP6进行中子计算,对ThorCon MSR第一次主动停堆系统和燃料箱的停堆能力进行了评估。结果表明,反应性为- 1.699% dk/k的控制棒无法将堆芯维持在亚临界状态,当燃料达到室温时堆芯的超反应性增加到+7.760 %dk/k。因此,必须将燃料排至FDT以冷却并保持亚临界状态。在最保守的情况下,各种FDT病例的乘法系数最高,为0.57008±0.00004。乘法系数远低于1.0的临界状态。评估表明,在控制棒关闭反应堆后不久,燃料必须排到FDT以维持关闭状态并消散衰变热。
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引用次数: 1
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