Gamma ray shielding properties of composites doped with rice bran wax and waste polyethylene [0.03%]
稻糠蜡和废聚乙烯掺杂复合材料的γ射线屏蔽性能研究
Yakup Kurucu,Sedanur Kalecik,Abdul Fatah Pathman et al.
Yakup Kurucu et al.
This work investigates the gamma-ray shielding properties of composites based on recycled polyethylene. The designed shielding materials are low-cost and sustainable plastic wastes with different percentages of rice bran wax. Composite samp...
Assessment of gross alpha, gross beta, 210Po, and 210Pb in rice and their associated health risks in Tamil Nadu, India: A baseline study [0.03%]
印度泰米尔纳德邦大米中总α、总β、210Po和210Pb的评估及对人体健康的影响：一项基础研究
Marckasagayam Priyadharshini,Bharathi Santhanabharathi,A Chandrasekaran et al.
Marckasagayam Priyadharshini et al.
The natural radioactivity content of rice is a critical factor in assessing the public's exposure to natural radionuclides through dietary intake. This study investigated the activity concentrations of gross alpha, gross beta, 210Po, and 21...
A study of the effect of water content on radon mass exhalation rate in sandy soil, sandy clay loamy soil and loamy sand soil samples collected from the strike - slip fault region in Mizoram, India [0.03%]
印度米佐拉姆走滑断层地区砂土、壤质砂土和砂质壤土样品中水分含量对氡气质量排放率影响的研究
Eliazar F Lalfakmawia,Wycliff Lalchhandama,Z Pachuau et al.
Eliazar F Lalfakmawia et al.
Variation of radon mass exhalation rate in relation to water content was conducted for two years in sandy soil, sandy clay loamy, and loamy sand soil sample collected from the strike - slip fault region in Mizoram using scintillation based ...
A dosimetric and biological model for neutron capture therapy (NCT) experiments [0.03%]
neutron捕获疗法实验的剂量学和生物模型
A Kalamara,I E Stamatelatos,K L Stefanopoulos et al.
A Kalamara et al.
A hybrid Monte Carlo approach using MCNP in combination with the cell-level code Monte Carlo Damage Simulation (MCDS) is presented to support the design and analysis of experiments for the evaluation of gadolinium (Gd) based agents in neutr...
Corrigendum to "Groundwater residence time in alluvial aquifer using emanation from Rn-222(222Rn) and its health impact in different aquifers" [Appl. Radiat. Isot. 226 112222] [0.03%]
“用222Rn的emanation估算冲积含水层中的地下水龄及其对不同含水层健康影响的研究”一文的勘误[应用辐射和同位素（第226卷，112222页）]
P Arjun,Girish Gopinath,T R Resmi et al.
P Arjun et al.
Preliminary study of indoor radon, thoron and their progeny in Bijnor and nearby places, U.P., India [0.03%]
印度联合省比恩县及附近地区室内氡、钍射气及其子体的初步研究
Lalit Rajpoot,Tarun Kumar,R B S Rawat et al.
Lalit Rajpoot et al.
Radon (222Rn), Thoron (220Rn) and their progeny are well-known contributors to indoor radiation exposure, particularly through inhalation in confined living spaces. This study presents preliminary results of indoor radon, thoron and progeny...
Measurement of a cold neutron cross section for the 40Ca(n, α)37Ar reaction [0.03%]
测量钙40Ca（n，α）反应产生氩37Ar的冷中子截面
Khiloni A Shah,Sarah T Castro,Kohlton D Mathis et al.
Khiloni A Shah et al.
The production of 37Ar gas through the neutron activation of 40Ca is important for underground nuclear explosion monitoring. Some of the activation occurs with thermal neutrons, but the thermal neutron cross section for the 40Ca(n, α)37Ar ...
Evaluation of cyclotron production parameters for 44Sc using Monte Carlo simulation [0.03%]
基于蒙特卡洛模拟的44Sc回旋生产参数研究
Fuqiu Ma,Enhua Xu,Dacan Yang et al.
Fuqiu Ma et al.
As a positron-emitting nuclide that can be co-labeled with therapeutic nuclides such as 47Sc and 177Lu, 44Sc holds significant promise for applications in theranostics in clinical nuclear medicine. To optimize its production, it is essentia...
Rapid and efficient preparation of uranium layers by electrodeposition from aqueous and organic solution systems [0.03%]
一种由水相和有机相电沉积快速制备铀膜的方法
Chao Peng,Guoyan Qi,Huitao Lv et al.
Chao Peng et al.
Targets containing high-density uranium layers are the primary material to produce 99Mo for medical use. Herein, the optimal parameters for the preparation of uranium deposited layers by different methods were obtained by comparing the dire...
Accelerating VVER-440 decommissioning by shortening spent-fuel cooling time for dry-cask storage [0.03%]
通过缩短干式储存的乏燃料冷却时间来加快VVER-440反应堆的退役进程
O Bůžek,M Lovecký,R Škoda
O Bůžek
This study focuses on optimizing the cooling time of spent nuclear fuel in the spent nuclear fuel pool before its placement into a dual-purpose dry cask to reduce the overall cooling duration required to safely store fuel discharged from th...