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Large eddy simulation of unsteady flow in gas-liquid separator applied in thorium molten salt reactor 被引量:2
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作者 Jing-Jing Li Ya-Lan Qian +3 位作者 Jun-Lian Yin Hua Li Wei Liu De-Zhong Wang 《Nuclear Science and Techniques》 SCIE CAS CSCD 2018年第5期10-18,共9页
Axial gas-liquid separators have been adopted in fission gas removal systems for the development of thorium molten salt reactors. In our previous study, we observed an unsteady flow phenomenon in which the flow patter... Axial gas-liquid separators have been adopted in fission gas removal systems for the development of thorium molten salt reactors. In our previous study, we observed an unsteady flow phenomenon in which the flow pattern is directly dependent on the backpressure in a gas-liquid separator; however, the underlying flow mechanism is still unknown. In order to move a step further in clarifying how the flow pattern evolves with a variation in backpressure, a large eddy simulation(LES) was adopted to study the flow field evolution. In the simulation, an artificial boundary was applied at the separator outlet under the assumption that the backpressure increases linearly. The numerical results indicate that the unsteady flow feature is captured by the LES approach, and the flow transition is mainly due to the axial velocity profile redistribution induced by the backpressure variation. With the increase in backpressure,the axial velocity near the downstream orifice transits from negative to positive. This change in the axial velocity sign forces the unstable spiral vortex to become a stable rectilinear vortex. 展开更多
关键词 SWIRL flow thorium MOLTEN SALT reactor Computational fluid dynamics Large EDDY simulation
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Gas-cooled thorium reactor at various fuel loadings and its modification by a plasma source of extra neutrons 被引量:1
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作者 Andrey Arzhannikov Sergey Bedenko +4 位作者 Vladimir Shmakov Vladimir Knyshev Igor Lutsik Vadim Prikhodko Igor Shamanin 《Nuclear Science and Techniques》 SCIE CAS CSCD 2019年第12期72-82,共11页
This work presents the results of computer simulation of neutronic processes in a high-temperature gas-cooled thorium reactor for 30 different options of core loading.To guarantee stable and long-term reactor operatio... This work presents the results of computer simulation of neutronic processes in a high-temperature gas-cooled thorium reactor for 30 different options of core loading.To guarantee stable and long-term reactor operation(7-10 years),the quantity of fuel compact dispersion phase and starting fuel composition was selected.It is demonstrated that it is possible in principle to substitute the near-axial recirculation zone of the reactor core by a long magnetic trap with a high-temperature plasma column for generating thermonuclear neutrons.The distribution of neutron yield along the length of the plasma source is also presented.Such a thorium reactor,with a near-axial source of extra neutrons,can be applied for researching thermophysical and neutronic characteristics of dispersion thorium fuel to improve its properties.The results of the work are of great interest from the perspective of future advancement of the thermonuclear power industry,by means of creation of a hybrid installation based on a thorium reactor with a long plasma column as a source of additional neutrons. 展开更多
关键词 LOW-POWER thorium REACTOR thorium hybrid REACTOR NUCLEAR fuel evolution
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Transmutation of 129I in a single-fluid double-zone thorium molten salt reactor 被引量:1
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作者 Kun-Feng Ma Cheng-Gang Yu +2 位作者 Xiang-Zhou Cai Chun-Yan Zou Jin-Gen Chen 《Nuclear Science and Techniques》 SCIE CAS CSCD 2020年第1期94-101,共8页
Herein, we assess the129I transmutation capability of a 2250-MWt single-fluid double-zone thorium molten salt reactor(SD-TMSR) by considering two methods. One is realized by loading an appropriate amount of129I before... Herein, we assess the129I transmutation capability of a 2250-MWt single-fluid double-zone thorium molten salt reactor(SD-TMSR) by considering two methods. One is realized by loading an appropriate amount of129I before the startup of the reactor, and the amount of129I during operation is kept constant by online feeding129I.The other adopts only an initial loading of129I before startup, and no other129I is fed online during operation.The investigation first focuses on the effect of the loading of I on the Th-233U isobreeding performance. The results indicate that a233U isobreeding mode can be achieved for both scenarios for a 60-year operation when the initial molar proportion of LiI is maintained within 0.40% and 0.87%, respectively. Then, the transmutation performances for the two scenarios are compared by changing the amount of injected iodine into the core. It is found that the scenario that adopts an initial loading of129I shows a slightly better transmutation performance in comparison with the scenario that adopts online feeding of129I when the net233U productions for the two scenarios are kept equal. The initial loading of129I scenario with LiI = 0.87% molar proportion is recommended for129I transmutation in the SD-TMSR,and can transmute 1.88 t of129I in the233U isobreeding mode over 60 years. 展开更多
关键词 129I transmutation thorium molten salt reactor Th-U isobreeding
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First-principles study of the elastic and thermodynamic properties of thorium hydrides at high pressure
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作者 张晓林 武媛媛 +2 位作者 邵晓红 鲁勇 张平 《Chinese Physics B》 SCIE EI CAS CSCD 2016年第5期270-276,共7页
The high pressure behaviors of Th_4H_(15) and ThH_2 are investigated by using the first-principles calculations based on the density functional theory(DFT). From the energy–volume relations, the bct phase of ThH_... The high pressure behaviors of Th_4H_(15) and ThH_2 are investigated by using the first-principles calculations based on the density functional theory(DFT). From the energy–volume relations, the bct phase of ThH_2 is more stable than the fcc phase at ambient conditions. At high pressure, the bct ThH_2 and bcc Th_4H(15) phases are more brittle than they are at ambient pressure from the calculated elastic constants and the Poisson ratio. The thermodynamic stability of the bct phase ThH_2 is determined from the calculated phonon dispersion. In the pressure domain of interest, the phonon dispersions of bcc Th_4H(15) and bct ThH_2 are positive, indicating the dynamical stability of these two phases, while the fcc ThH_2 is unstable. The thermodynamic properties including the lattice vibration energy, entropy, and specific heat are predicted for these stable phases. The vibrational free energy decreases with the increase of the temperature, and the entropy and the heat capacity are proportional to the temperature and inversely proportional to the pressure. As the pressure increases, the resistance to the external pressure is strengthened for Th_4H_(15) and ThH_2. 展开更多
关键词 first-principles calculations thermodynamic properties phonon spectra thorium hydrides
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Defect stability in thorium monocarbide:An ab initio study
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作者 王昌英 韩晗 +2 位作者 邵宽 程诚 怀平 《Chinese Physics B》 SCIE EI CAS CSCD 2015年第9期424-429,共6页
The elastic properties and point defects of thorium monocarbide(ThC) have been studied by means of density functional theory based on the projector-augmented-wave method. The calculated electronic and elastic proper... The elastic properties and point defects of thorium monocarbide(ThC) have been studied by means of density functional theory based on the projector-augmented-wave method. The calculated electronic and elastic properties of ThC are in good agreement with experimental data and previous theoretical results. Five types of point defects have been considered in our study, including the vacancy defect, interstitial defect, antisite defect, schottky defect, and composition-conserving defect. Among these defects, the carbon vacancy defect has the lowest formation energy of 0.29 eV. The second most stable defect(0.49 eV) is one of composition-conserving defects in which one carbon is removed to another carbon site forming a C2 dimer. In addition, we also discuss several kinds of carbon interstitial defects, and predict that the carbon trimer configuration may be a transition state for a carbon dimer diffusion in Th C. 展开更多
关键词 thorium monocarbide ab initio study bulk properties DEFECTS
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Burnup optimization of once-through molten salt reactors using enriched uranium and thorium
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作者 Meng-Lu Tan Gui-Feng Zhu +5 位作者 Zheng-De Zhang Yang Zou Xiao-Han Yu Cheng-Gang Yu Ye Dai Rui Yan 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2022年第1期44-59,共16页
The advantages of once-through molten salt reactors include readily available fuel,low nuclear proliferation risk,and low technical difficulty.It is potentially the most easily commercialized fuel cycle mode for molte... The advantages of once-through molten salt reactors include readily available fuel,low nuclear proliferation risk,and low technical difficulty.It is potentially the most easily commercialized fuel cycle mode for molten salt reactors.However,there are some problems in the parameter selection of once-through molten salt reactors,and the relevant burnup optimization work requires further analysis.This study examined once-through graphitemoderated molten salt reactor using enriched uranium and thorium.The fuel volume fraction(VF),initial heavy nuclei concentration(HN_(0)),feeding uranium enrichment(E_(FU)),volume of the reactor core,and fuel type were changed to obtain the optimal conditions for burnup.We found an optimal region for VF and HN_(0) in each scheme,and the location and size of the optimal region changed with the degree of E_(FU),core volume,and fuel type.The recommended core schemes provide a reference for the core design of a once-through molten salt reactor. 展开更多
关键词 Once-through fuel cycle Molten salt reactor Enriched uranium thorium
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ICP-MS measurement of uranium and thorium contents in minerals in China 被引量:4
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作者 Liang-Liang Yin Qing Tian +3 位作者 Xian-Zhang Shao Bao-Ming Shen Xu Su Yan-Qin Ji 《Nuclear Science and Techniques》 SCIE CAS CSCD 2016年第1期166-169,共4页
The activity levels of long-lived radionuclides in minerals have received more and more concern for the public health. The inductively coupled plasma mass spectrometry was used to measure the content of uranium and th... The activity levels of long-lived radionuclides in minerals have received more and more concern for the public health. The inductively coupled plasma mass spectrometry was used to measure the content of uranium and thorium in 60 mineral samples collected from 16 mines of seven provinces in China. The contents of uranium and thorium ranged0.17 ± 0.04 lg g^(-1)to 15.3 ± 2.39 lg g^(-1), and 0.19 ± 0.04 lg g^(-1)to 19.6 ± 7.56 lg g^(-1), respectively. The highest levels of U and Th contents were found in aluminum ore,whereas the lowest was found in antimony and copper ores. 展开更多
关键词 铀含量 ICP-MS 电感耦合等离子体质谱法 矿产 测量 放射性核素 公众健康
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Transition toward thorium fuel cycle in a molten salt reactor by using plutonium 被引量:5
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作者 De-Yang Cui Shao-Peng Xia +2 位作者 Xiao-Xiao Li Xiang-Zhou Cai Jin-Gen Chen 《Nuclear Science and Techniques》 SCIE CAS CSCD 2017年第10期103-112,共10页
The molten salt reactor(MSR), as one of the Generation Ⅳ advanced nuclear systems, has attracted a worldwide interest due to its excellent performances in safety, economics, sustainability, and proliferation resistan... The molten salt reactor(MSR), as one of the Generation Ⅳ advanced nuclear systems, has attracted a worldwide interest due to its excellent performances in safety, economics, sustainability, and proliferation resistance. The aim of this work is to provide and evaluate possible solutions to fissile 233 U production and further the fuel transition to thorium fuel cycle in a thermal MSR by using plutonium partitioned from light water reactors spent fuel. By using an in-house developed tool, a breeding and burning(B&B) scenario is first introduced and analyzed from the aspects of the evolution of main nuclides, net 233 U production, spectrum shift, and temperature feedback coefficient. It can be concluded that such a Th/Pu to Th/^(233)U transition can be accomplished by employing a relatively fast fuel reprocessing with a cycle time less than 60 days. At the equilibrium state, the reactor can achieve a conversion ratio of about 0.996 for the 60-day reprocessing period(RP) case and about 1.047 for the 10-day RP case.The results also show that it is difficult to accomplish such a fuel transition with limited reprocessing(RP is 180 days),and the reactor operates as a converter and burns the plutonium with the help of thorium. Meanwhile, a prebreeding and burning(PB&B) scenario is also analyzed briefly with respect to the net 233 U production and evolution of main nuclides. One can find that it is more efficient to produce 233 U under this scenario, resulting in a double time varying from about 1.96 years for the 10-day RP case to about 6.15 years for the 180-day RP case. 展开更多
关键词 钍燃料循环 反应器 熔盐堆 先进核能系统 循环时间 轻水反应堆 燃料后处理
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Neutron excess method for performance assessment of thoriumbased fuel in a breed-and-burn reactor with various coolants 被引量:4
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作者 Kun Yang Wei Qin +1 位作者 Jin-Gen Chen Xiang-Zhou Cai 《Nuclear Science and Techniques》 SCIE CAS CSCD 2016年第4期167-173,共7页
Fertile fuel, such as thorium or depleted uranium, can be bred into fissile fuel and burnt in a breed-andburn(B&B) reactor. Modeling a full core with fertile fuel can assess the performance of a B&B reactor wi... Fertile fuel, such as thorium or depleted uranium, can be bred into fissile fuel and burnt in a breed-andburn(B&B) reactor. Modeling a full core with fertile fuel can assess the performance of a B&B reactor with exact quantitative estimates, but costs too much computation time. For simplicity, performing the recently developed neutron balance method with a zero-dimensional(0-D)model can also provide a reasonable result. Based on the0-D model, the feasibility of the B&B mode for thorium fuel in a fast reactor cooled by sodium was investigated by considering the(n, 2n) and(n, 3n) reaction rates of fuel and coolant in this work, and compared with that of depleted uranium fuel. Afterward, the performance of the same thorium-based fuel core, but cooled by helium, lead-bismuth, and FLi Be, respectively, is discussed. It is found that the(n, 2n) and(n, 3n) reactions should not be neglected for the neutron balance calculation for thorium-based fuel to sustain the B&B mode of operation. 展开更多
关键词 性能评估 钠燃料 冷却剂 反应器 中子 燃烧 零维模型 化学反应速率
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Biosorption behavior and mechanism of thorium on Bacillus sp. dwc-2 isolated from soil 被引量:3
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作者 兰图 丁聪聪 +12 位作者 廖家莉 李晓龙 李兴亮 张杰 张东 杨吉军 罗顺忠 安竹 邬琦琦 杨远友 冯甦 唐军 刘宁 《Nuclear Science and Techniques》 SCIE CAS CSCD 2015年第6期35-45,共11页
To develop a microbe-based bioremediation strategy for cleaning up thorium-contaminated sites, we have investigated the biosorption behavior and mechanism of thorium on Bacillus sp. dwc-2, one of the dominant species ... To develop a microbe-based bioremediation strategy for cleaning up thorium-contaminated sites, we have investigated the biosorption behavior and mechanism of thorium on Bacillus sp. dwc-2, one of the dominant species of bacterial groups isolated from soils in Southwest China. Thorium biosorption depended on the p H of environment, and its rapid biosorption reached a maximum of up to 10.75 mg Th per gram of the bacteria(wet wt.) at pH 3.0. The biosorption agreed bettter with Langmuir isotherm model than Freundlich model, indicating that thorium biosorption was a monolayer adsorption. The thermodynamic parameters, negative change in Gibbs free energy and positive value in enthalpy and entropy, suggested that the biosorption was spontaneous,more favorable at higher temperature and endothermic process with an increase of entropy. Scanning electron microscopy(SEM) indicated that thorium initially binded with the cell surface, while transmission electron microscopy(TEM) revealed that Th deposited in the cytoplasm and served as cores for growth of element precipitation(e.g., phosphate minerals) or by self-precipitation of hydroxides, which is probably controlled by ion-exchange, as evidenced by particle induced X-ray emission(PIXE) and enhanced proton backscattering spectrometry(EPBS). Fourier Transform Infrared(FTIR) further indicated that thorium biosorption involved carboxyl and phosphate groups and protein in complexation or electrostatic interaction. Overall results indicated that a combined electrostatic interaction-complexation-ion exchange mechanism could be involved in thorium biosorption by Bacillus sp. dwc-2. 展开更多
关键词 离子交换机理 吸附行为 芽孢杆菌 FREUNDLICH模型 分离 土壤 静电相互作用
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Adsorption characteristics of thorium on silica-based anion exchange resins
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作者 陈彦良 赵龙 +2 位作者 韦悦周 何林锋 唐方东 《Nuclear Science and Techniques》 SCIE CAS CSCD 2015年第6期55-62,共8页
To isolate and separate thorium from nitric acid solutions, three silica-based anion exchange resins were synthesized. Batch experiments were carried out to investigate adsorption behavior of thorium in nitric acid so... To isolate and separate thorium from nitric acid solutions, three silica-based anion exchange resins were synthesized. Batch experiments were carried out to investigate adsorption behavior of thorium in nitric acid solutions. Adsorption at different concentrations of nitric acid and thorium, influence of contact time and coexisting metal ions, and effect of NO3– were investigated in detail. It was found that at high HNO3 concentrations,the resins exhibited higher adsorption capacity and better affinity towards thorium. The adsorption kinetics could be described by the pseudo-second order model equation, while the adsorption isotherms were well correlated by the Langmuir model. The maximum capacity towards thorium species on SiPyR-N4 was evaluated at 27–28 mg/g-resin. The thermodynamic parameters indicated the adsorption was an exothermic reaction. The presence of NO3– was found to promote the retention of the thorium species. 展开更多
关键词 阴离子交换树脂 二氧化硅基 吸附特性 硝酸钍 硝酸溶液 模型方程 吸附动力学 吸附等温线
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Synthesis of thorium sol for fabricating fuel kernels
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作者 Feng-Xia Wang Chao Yan +6 位作者 Chang-Qing Cao Peng Wang He Huang Hai-Tao Jiang Jun Lin Zhi-Xuan Cheng Zhi-Yong Zhu 《Nuclear Science and Techniques》 SCIE CAS CSCD 2017年第7期53-58,共6页
To fabricate thorium-based fuel kernel for solid fuel molten salt reactor,a component of tri-structural isotropic fuel particles is mostly based on sol-gel method.The preparation of thorium sol is an important step fo... To fabricate thorium-based fuel kernel for solid fuel molten salt reactor,a component of tri-structural isotropic fuel particles is mostly based on sol-gel method.The preparation of thorium sol is an important step for fabrication of thorium-based fuel kernels,such as thorium carbide and thorium oxide.The gel quality affects the gel particle dispersion and the final products.In this work,thorium sols were prepared using Th(NO_3)_4 and NH_3·H_2O by sol-gel method.The effects of thorium concentration,mole ratio of NH_4^+/NO_3^- and reaction temperature on the pH,viscosity,turbidity,particle size and the thorium sol distribution were investigated.The results show that the viscosity and turbidity increased with the NH_4^+/NO_3^- ratio;the turbidity and colloidal particle size increased with the reaction temperature,which affected little the sol viscosity;the sol viscosity increased with the thorium concentration,which virtually did not change the turbidity;and the particle size decreased and the size distribution narrowed with increasing thorium concentration.The sol could be stored at room temperature for one day without significant property changes.Thorium gel spheres of good quality were prepared at 60℃ with the NH_4^+/NO_3^- ratio of 75-85% and the thorium concentration of 1.2-1.4 mol/L. 展开更多
关键词 溶胶-凝胶法 固体燃料 钍基 制造 合成 凝胶颗粒 反应温度 燃料组件
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Solvent extraction of nitric acid, uranium(VI) and thorium(IV) by N,N,N',N'-tetrahexylsuccinylamide
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作者 TAN Xufang WANG Youshao +1 位作者 TAN Taizhe (Laiyang Agricultural College, Laiyang 265200) YANG Yanzhao BAO Borong (Shanghai Institute of Nuclear Research, the Chinese Academy of Sciences, Shanghai 201800) SUN Sixiu (Department of Chemistry, Shandong University, 《Nuclear Science and Techniques》 SCIE CAS CSCD 1999年第1期19-23,共5页
A new kind of diamide N,N,N’,N’-tetrahexylsuccinylamide(THSA) was synthesized, characterized and used for the extraction of HNO3, U(VI) and TI(IV) in a diluent composed of 0.5 volume fraction 1,2,4-trimethy be... A new kind of diamide N,N,N’,N’-tetrahexylsuccinylamide(THSA) was synthesized, characterized and used for the extraction of HNO3, U(VI) and TI(IV) in a diluent composed of 0.5 volume fraction 1,2,4-trimethy benzene(TMB) and 0.5 volume fraction kerosene(OK). Extraction distribution coefficients of U(VI) and TI(IV) as functions of aque- ous nitric acid concentration, extractant concentration, temperature and salting-out agent (LiNO3 ) have been studied, and it is found that THSA as an extractant is superior to TBP for extraction of U(VI) and TI(IV). Back extraction was also studied. At low acidity, the main adduct of THSA and HNO3 is HNO3.THSA. THSA.(HNO3)2 and THSA.(HNO3)3 are also found at high acidity. The compositions of extracted species, apparent equilibrium constants and enthalpies of extraction reactions have also been calculated. 展开更多
关键词 硝酸溶剂提取
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伴生放射性稀土渣资源化过程铀与钍的浸出特性及风险评估
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作者 罗明标 董云雅 +3 位作者 康长安 李烨玲 刘星宇 徐小江 《东华理工大学学报(自然科学版)》 北大核心 2025年第1期84-93,共10页
我国伴生放射性稀土废渣大量堆存,所含放射性源头U、Th易释放进入生态系统,隐患巨大,废渣的综合利用研究迫在眉睫。以江西某稀土冶炼厂堆存的伴生放射性稀土酸溶渣为研究对象,将部分废渣用作水泥生料,再烧制成熟料,分析稀土渣和水泥熟... 我国伴生放射性稀土废渣大量堆存,所含放射性源头U、Th易释放进入生态系统,隐患巨大,废渣的综合利用研究迫在眉睫。以江西某稀土冶炼厂堆存的伴生放射性稀土酸溶渣为研究对象,将部分废渣用作水泥生料,再烧制成熟料,分析稀土渣和水泥熟料中放射性U、Th的浸出特性及产生的环境风险。结果表明,酸溶渣中U、Th浸出毒性超标,对环境危害大,制成熟料后,U、Th的浸出毒性满足国标《稀土工业污染物排放标准》限值。BCR形态提取结果表明,高温烧制有利于U、Th的形态向残渣态转化,迁移性显著降低。U、Th的浸出含量随浸提剂酸度增大、浸泡时间延长而增加,在浸提剂pH值为2.0时,酸溶渣中U、Th浸出质量浓度远高于国标规定的限值,而熟料中的浸出质量浓度则远小于国标限值。地累积指数和潜在生态风险指数结果表明,酸溶渣中U、Th产生混合极重度污染,风险水平为高风险,掺渣比例≤1.5%的熟料中U、Th浸出含量小,潜在生态风险水平较低,内外照射指数皆小于1。 展开更多
关键词 稀土酸溶渣 资源化 环境风险评估
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一种钍-铁金属氧簇的合成、结构、磁性及在催化苄胺偶联反应中的应用
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作者 王春晖 张洋 +4 位作者 韩哲 高原 何普涌 范超越 邱杰 《高等学校化学学报》 北大核心 2025年第3期1-10,共10页
采用溶剂热法合成了一种新型带负电的钍-铁金属氧簇[Th_(2)Fe_(10)O_(4)(C_6H_(5)PO_(3))_(12)(CH_(3)O)_(8)Cl_(4)]^(6-)(Th_(2)Fe_(10)),并表征了其晶体结构、化学组成、磁性质和催化性能.单晶X射线衍射数据显示,Th_(2)Fe_(10)为一种... 采用溶剂热法合成了一种新型带负电的钍-铁金属氧簇[Th_(2)Fe_(10)O_(4)(C_6H_(5)PO_(3))_(12)(CH_(3)O)_(8)Cl_(4)]^(6-)(Th_(2)Fe_(10)),并表征了其晶体结构、化学组成、磁性质和催化性能.单晶X射线衍射数据显示,Th_(2)Fe_(10)为一种新型十二核Th-Fe金属氧簇,Th(Ⅳ)和Fe(Ⅲ)离子的协同水解、醇解和缩聚反应以及苯基膦酸根的钝化作用促进了该簇合物的形成.Th_(2)Fe_(10)不仅是第二例被报道的Th-Fe氧簇,也是为数不多的锕系-过渡金属氧簇之一.光性质和磁性质表征结果表明,Th_(2)Fe_(10)晶体具有显著的吸收可见光的特性,且Fe(Ⅲ)离子间展现出强的反铁磁交换作用.催化反应结果表明,Th_(2)Fe_(10)具有优良的催化苄胺偶联反应的性能,实现了高达94%的转化率和96%的选择性,且经过多次循环使用后,仍保持良好的催化性能.活性物种清除实验表明,电子、空穴、^(1)O_(2)和·OH在催化过程中具有重要作用,并通过电化学测试和电子顺磁共振谱(EPR)进行了验证.基于以上实验结果推测了催化反应机理. 展开更多
关键词 异金属氧簇 钍-铁氧簇 磁性 催化性能 苄胺偶联反应
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钍基熔盐反应堆内化学研究进展和展望
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作者 李晴暖 窦强 +2 位作者 赵中奇 耿俊霞 李文新 《原子能科学技术》 EI CAS CSCD 北大核心 2024年第S02期256-264,共9页
熔盐反应堆是第四代核能系统中唯一使用液态燃料的反应堆,在钍基熔盐反应堆研制和运行中有许多直接与化学相关的关键问题,堪比“化学堆”。于是,因熔盐反应堆研发和运行的需要诞生了放射化学在裂变能利用中的一门新分支学科——熔盐反... 熔盐反应堆是第四代核能系统中唯一使用液态燃料的反应堆,在钍基熔盐反应堆研制和运行中有许多直接与化学相关的关键问题,堪比“化学堆”。于是,因熔盐反应堆研发和运行的需要诞生了放射化学在裂变能利用中的一门新分支学科——熔盐反应堆化学。本实验室利用加速器驱动的中子源和γ能谱分析技术开展了钍基熔盐反应堆化学研究。本文介绍了钍铀转换中间核素~(233)Pa和裂变产物~(131)I及~(95)Nb在熔盐反应堆模拟燃料盐中分布和行为的研究进展。基于对美国橡树岭国家实验室(ORNL)的熔盐反应堆实验装置运行中的燃料盐、锕系元素和裂变产物等相关若干问题分析,提出了在钍基熔盐反应堆框架内熔盐反应堆内化学方面应该进一步开展的研究内容,包括钍基熔盐反应堆运行的化学检测和诊断、影响熔盐氧化还原电势的因素、熔盐氧化还原电势检测的新技术等。熔盐反应堆化学研究的进一步深入将拓展熔盐反应堆化学实践和理论,使钍基熔盐反应堆化学水平提升到新高度,为未来钍基熔盐反应堆高效安全运行提供科学技术方面的支撑和保障。 展开更多
关键词 钍基熔盐反应堆 熔盐反应堆化学 锕系和裂变产物 检测和诊断 氧化还原电势
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新型钍-喹啉金属有机框架材料的制备、性质表征及其碘吸附性能研究
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作者 韩哲 刘一鸣 +3 位作者 王春晖 高原 何普涌 邱杰 《原子能科学技术》 EI CAS CSCD 北大核心 2024年第10期2095-2105,共11页
为了开发一种新型的钍基碘吸附材料,本文通过溶剂热法合成了一种含喹啉配体的钍基金属有机框架(MOF)材料——[Th(C_(9)H_(5)NOCOO)_(4)]·12H_(2)O(Th-HQCA),表征分析了其结构、组分、光谱性质,并探究了该MOF材料对碘的吸附性能及... 为了开发一种新型的钍基碘吸附材料,本文通过溶剂热法合成了一种含喹啉配体的钍基金属有机框架(MOF)材料——[Th(C_(9)H_(5)NOCOO)_(4)]·12H_(2)O(Th-HQCA),表征分析了其结构、组分、光谱性质,并探究了该MOF材料对碘的吸附性能及其影响因素。结果表明:钍离子与4个喹啉上的羧基氧和另外4个喹啉上的羟基氧配位后,形成了Th-HQCA的2,8-连接的新型框架结构。荧光光谱显示Th-HQCA受紫外光激发后,展现出发射蓝光的特性。碘吸附的实验结果表明Th-HQCA可从气相和环己烷溶液中捕获碘的最大吸附容量分别为535、295 mg/g。 展开更多
关键词 钍基金属有机框架材料 晶体结构 荧光性质 碘吸附
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铀钍混合氧化物点阵参数及溶解性研究
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作者 袁波 王溢华 +4 位作者 李明鑫 李佳 许崎伟 李鑫浩 杨卓颖 《核科学与工程》 CAS CSCD 北大核心 2024年第4期954-959,共6页
为了回收不合格铀钍混合氧化物燃料中的铀,研究了铀钍混合氧化物的晶格常数以及在硝酸中的溶解性。考察了反应时间、反应温度及钍含量对铀溶解率的影响。采用熔盐辅助焙烧法对高钍含量的铀钍混合氧化物进行活化,对比了不同焙烧助剂的活... 为了回收不合格铀钍混合氧化物燃料中的铀,研究了铀钍混合氧化物的晶格常数以及在硝酸中的溶解性。考察了反应时间、反应温度及钍含量对铀溶解率的影响。采用熔盐辅助焙烧法对高钍含量的铀钍混合氧化物进行活化,对比了不同焙烧助剂的活化效果。结果表明:铀钍混合氧化物的晶格常数与钍含量之间满足Vegard定律;铀钍混合氧化物的溶解性随钍含量增加而降低,适合直接使用硝酸溶解的钍含量上限为24.5%;硝酸钠、氢氧化钠、碳酸钠三种焙烧助剂均能活化铀钍混合氧化物,硝酸钠的活化效果最佳,在金属摩尔比为4,温度850℃下焙烧4.0 h后,铀溶解率≥98%。 展开更多
关键词 铀钍混合氧化物 点阵参数 溶解 熔盐焙烧
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偶氮胂Ⅲ快速比色法测定二氧化钍溶解液中的Th(Ⅳ)
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作者 赵鹏飞 吴久伟 +2 位作者 王宇 李勇 官国英 《同位素》 CAS 2024年第2期146-152,共7页
ThO_(2)经加速器轰击后可以产生多种核素,如^(225)Ac、^(223)Ra、^(99)Mo、^(131)I、^(90)Sr等。钍等重元素的测量方法众多,但大多操作复杂。分光光度法具有制样简单、操作难度小的优点,可作为钍等重元素的定量分析手段。采用HNO_(3)/H... ThO_(2)经加速器轰击后可以产生多种核素,如^(225)Ac、^(223)Ra、^(99)Mo、^(131)I、^(90)Sr等。钍等重元素的测量方法众多,但大多操作复杂。分光光度法具有制样简单、操作难度小的优点,可作为钍等重元素的定量分析手段。采用HNO_(3)/HF体系对ThO_(2)进行溶解,以偶氮胂Ⅲ为显色剂定量分析ThO_(2)溶解液中Th(Ⅳ)的浓度。在2 mol/L盐酸溶液和0.1 g/L偶氮胂Ⅲ溶液的环境下,确定了在本法所确定的实验条件下偶氮胂Ⅲ与Th(Ⅳ)的配位比为5∶2,显色前后的最大吸收波长分别为534.0 nm和663.2 nm,对比度为129.2 nm。该方法在0.2~5.0 mg/L符合朗伯-比尔定律,标准曲线方程为y=0.06641x+0.00176,R^(2)=0.99981,摩尔吸光系数为1.64×10^(4),方法检出限为0.31μg/L,定量限为0.97μg/L。该方法在4 h以内稳定,回收率为97.33%~104.03%,最大标准偏差为0.32%。本方法与GB/T 12690.12-2003相比,流程简化且测定结果基本一致。 展开更多
关键词 偶氮胂Ⅲ 二氧化钍 定量分析
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全球熔盐堆发展现状与趋势
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作者 马荣芳 江舸帆 +2 位作者 房勇汉 仇若萌 付玉 《核科学与工程》 CSCD 北大核心 2024年第6期1239-1246,共8页
熔盐堆是第四代核能系统中一种重要的核反应堆堆型,能够在接近大气压的条件下运行,具有独特的固有安全特性,且冷却剂出口温度更高,具有广阔的工业应用前景。本文从熔盐堆的分类与技术方向、国际研究进展和当前研发重点等三个方面针对熔... 熔盐堆是第四代核能系统中一种重要的核反应堆堆型,能够在接近大气压的条件下运行,具有独特的固有安全特性,且冷却剂出口温度更高,具有广阔的工业应用前景。本文从熔盐堆的分类与技术方向、国际研究进展和当前研发重点等三个方面针对熔盐堆的发展现状进行了综述。目前,包括中国在内的主要核能国家正在开展熔盐堆技术研究与堆型开发工作,有关研究机构和企业在结构材料与石墨、熔盐、燃料与燃料循环、模拟程序开发等领域进行重点研究。熔盐堆技术有可能成为核反应堆技术未来发展的重要方向之一。 展开更多
关键词 熔盐堆 钍资源利用 第四代核能技术
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