H原子在γ-U(100)表面吸附与扩散的密度泛函研究

采用密度泛函理论方法研究了H原子在γ-U(100)表面的吸附和扩散。结果表明：H原子在γ-U(100)表面的最佳吸附位依次为穴位、桥位和顶位,吸附能分别为2.696、2.597和2.017 eV;H原子在γ-U中的最佳间隙位为四面体间隙,其次是八面体间隙,吸附能分别为1.534 eV和0.991 eV;H原子在铀表面以及近表面层的不同吸附位之间的扩散需克服不同的势垒,相比于间隙位,H原子更倾向于在γ-U(100)表面吸附聚集。     

Si原子在CeO2(111)表面吸附与迁移的第一性原理研究

为探究Si原子在CeO₂(111)表面吸附的微观行为,采用第一性原理的方法研究了Si原子在CeO₂(111)表面的吸附作用、电子结构和迁移过程,计算了Si原子在CeO₂(111)表面的吸附能,最稳定及次稳定吸附位置的电子态密度与电荷密度分布、迁移激活能。计算结果表明：Si原子最易吸附于基底表层的O原子上,其中O桥位（O_bri）吸附作用最强,O顶位（O_t）和O三度位（O_h）吸附强度次之。Si原子仅对其最邻近的表层O原子结构影响较大,这与Si原子及其最邻近的O原子间电荷密度重叠程度增强的结果一致。Si原子最易围绕着O_t位从O_bri位向O_h位迁移,迁移所需激活能为0.849 eV。     

H原子在Zr(0001)表面吸附的第一性原理研究

结合蒙特卡洛(MC)模拟和第一性原理密度泛函理论(DFT)方法,从Zr-H体系微观结构、吸附概率、吸附能、Mulliken电荷布居数以及电子态密度等方面对H原子在α-Zr(0001)表面的吸附位点和吸附机理等进行计算分析。结果表明:H原子在Zr(0001)表面首先产生物理吸附,然后由物理吸附转变为化学吸附,吸附过程中电荷不断由Zr(0001)表面原子向H原子转移,最后趋于稳定。另外,稳定吸附后的H原子直接与Zr(0001)表面最表层原子生成化学键,且主要由H(s)、Zr(s)和Zr(d)轨道的电子态做贡献。综合分析得到H原子在Zr(0001)表面的吸附位点优先级顺序为密排六方间隙位(hcp位)>面心立方间隙位(fcc位)>桥位(bridge位),顶位(top位)不会产生吸附。     

PuGa合金中H吸附行为的第一性原理研究北大核心CSCD

在氢气氛下,PuGa合金会发生氢化腐蚀反应,这会影响材料结构,导致PuGa合金相关性能下降。由于PuGa材料的高辐射性、相关实验技术及条件的制约,难以通过大规模的实验手段对此进行研究。因此,针对H在PuGa合金(111)面及体相内的吸附行为机制进行了第一性原理模拟研究,分析H在PuGa合金中的电子结构及吸附作用过程。研究发现H原子在PuGa体相中倾向吸附于包含Ga原子的四面体间隙,其吸附能为-0.75 eV,而在(111)面上倾向吸附于Pu原子周围,其最大吸附能绝对值为0_(6)2 eV。H在Ga原子邻近吸附位具有较低的扩散能垒,尤其是在表面上其反应能垒小于0.3 eV。本工作从原子尺度理解揭示H在材料表面的吸附行为机理,为降低H对材料结构及性能的影响提供理论指导。     

锑烯表面铀、钍、钚的吸附性能研究：线性响应方法结合密度泛函理论

基于密度泛函理论（Density Functional Theory,DFT）研究了锕系元素铀（U）、钍（Th）、钚（Pu）在二维金属材料锑烯表面的吸附特性。采用线性响应法拟合得到描述铀、钚5f轨道电子强格点库仑作用的哈伯德U值分别为2.24 eV和2.84 eV。利用DFT+U计算发现，锑烯难以吸附钚原子（吸附能为负值），而对铀、钍原子具有较强的表面化学吸附以及丰富的稳定吸附位点。铀和钍原子能量上最稳定的吸附位点分别为桥位——孔位之间和孔位，吸附能分别为4.40 eV和3.62 eV。通过电子结构、电荷转移和最高占据态轨道波函数分析发现，铀、钍原子使锑烯的带隙中出现杂质态，并与锑烯之间通过强p-d轨道耦合使其稳定吸附。进一步计算了吸附率随温度的变化，得出铀和钍在锑烯表面的解吸温度分别达到837 K和660 K。结果预示锑烯是一种良好的铀、钍吸附材料，在海水提铀等领域具有潜在应用。     

O2在UC(001)表面吸附的第一性原理研究

本文使用GGA+U方法研究了O₂在UC(001)表面的吸附、解离过程。结果表明：U_eff=1.5 eV能很好地再现晶格常数a和内聚能E_coh的实验结果;经过离子弛豫,最表面的两个原子层出现分层现象,各自形成两个亚层;O₂分子的吸附构型对吸附过程影响较大,吸附能在2.21～8.55 eV之间变化。通过Bader电荷、差分电荷和态密度分析,可确定O₂分子的解离活化机理为U的5f/6d电子转移至O₂的π2p和π*2p轨道。     

Zn／δ-MnO2吸附结构的EXAFS研究

用EXAFS方法研究了重金属Zn(Ⅱ)在δ-MnO2上吸附的微观结构及吸附机制。在pH5．50，0．1M硝酸钠介质中，吸附-解吸实验表明Zn(Ⅱ）在δ-MnO2上的吸附可逆性很高．EXAFS结果表明，δ-MnO2表面上吸附态Zn2 以六配位的水合离子八面体形式存在。八面体的水合Zn^2 离子与δ-MnO2的结构单元MnO6八面体通过共用O原子结合，形成角-角结合的弱吸附．Zn-O平均原子间距为2．071A，Zn-Mn平均原子间距为3．528A。同一条等温线上随着吸附量增加，角-角结合的弱吸附形式基本上没有变化。Zn(Ⅱ)在δ-MnO2上较高的吸附可逆性是由于吸附态Zn(Ⅱ)与δ-MnO2以弱吸附的角-角形式结合所导致的。     

针铁矿和赤铁矿吸附As(V)的EXAFS研究

砷是一种有毒污染物,其在铁氧化物表面的吸附是影响其迁移转化行为的重要因素。针铁矿和赤铁矿是自然界中广泛存在的稳定氧化铁矿物,它们具有粒径小、比表面积大、活性基团多等特性,可用做吸附剂。在不同pH和不同铁砷摩尔比的实验条件下,用针铁矿和赤铁矿吸附五价砷As(V),结果表明:实验所用的两种吸附剂均呈现吸附量随铁砷摩尔比升高而降低的现象,而在酸性pH条件下的砷吸附量均大于其在碱性pH条件下的吸附量;在相同的实验条件下,针铁矿对砷的吸附量要大于赤铁矿对砷的吸附量。进一步通过扩展X射线吸收精细结构光谱(Extended X-ray Absorption Fine Structure Spectroscopy,EXAFS)观测砷在针铁矿和赤铁矿上吸附后形成的络合物的分子结构,结果显示:砷与针铁矿和赤铁矿中的铁氧八面体之间的配位数均接近1,不同样品中As-Fe键的长度范围为3.29～3.31?,表明As(V)在针铁矿和赤铁矿表面吸附后主要形成单齿单核络合物,且该结构与吸附p H和铁砷摩尔比无关。     

Eu(Ⅲ)在针铁矿及磷酸根改性针铁矿上的吸附

采用静态法研究了Eu(Ⅲ)在针铁矿及磷酸根改性的针铁矿上的吸附行为,测定了（25±1）℃下的吸附边界及吸附等温线,探讨了FA的存在对吸附的影响。实验结果表明,pH对吸附的影响较大,pH＝4～6为Eu(Ⅲ)在针铁矿上的吸附边界,磷酸根改性的针铁矿的吸附边界明显向低pH移动。Eu(Ⅲ)在针铁矿及磷酸根改性的针铁矿上的吸附更符合Freundlich等温线。Eu(Ⅲ)在针铁矿上的吸附主要是通过表面配位进行的。     

铯在钨(110)表面吸附行为的第一性原理研究

通过基于密度泛函理论的第一性原理计算方法,研究了铯原子在钨(110)表面上的吸附行为。计算结果表明,通过原子数之比定义的最大单层铯原子吸附率为0.4,铯原子的吸附位置随吸附率的增加而变化。铯原子吸附率为0.25时,最可能的吸附位置是长桥,而铯原子吸附率达0.4时,铯原子在钨(110)表面形成完整的单原子层,并呈现-ABA′B′-结构形式。随铯原子吸附率的增加,表面功函数先减小后增大,最终稳定在2.134 eV,其中最小值1.524 eV出现在吸附率为0.25时,该最小值低于纯铯(110)表面的功函数。偶极子模型和分态密度计算结果表明,铯原子向钨基体表面的电子转移机制和铯原子电子能量分布的变化是造成表面功函数降低的原因。     

稀有气体原子与Pu（100）表面相互作用的第一性原理研究

采用第一性原理研究了稀有气体原子在Pu（100）表面上的吸附。计算结果表明：除He原子外,其他稀有气体原子在桥位处的吸附能均为最大;稀有气体原子在Pu（100）表面吸附后,稀有气体原子失去电荷,而Pu原子得到电荷,稀有气体原子中Xe原子的电荷转移数最大。差分电荷密度的计算结果表明,对位于Pu（100）表面穴位和桥位处的Xe原子,可观察到较明显的电荷再分布现象,这表明Xe原子具有一定极化效应,能与Pu（100）表面发生相互作用,从He到Xe,原子的极化效应越来越明显。     

Theory of He trapping, diffusion, and clustering in UO2

We have performed ab initio total energy calculations to investigate the behavior of helium and its diffusion properties in uranium dioxide (UO₂). Our investigations are based on the density functional theory within the generalized gradient approximation (GGA). The trapping behavior of He in UO₂ has been modeled with a supercell containing 96-atoms as well as uranium and oxygen vacancy trapping sites. The calculated incorporation energies show that for He a uranium vacancy is more stable than an oxygen vacancy or an octahedral interstitial site (OIS). Interstitial site hopping is found to be the rate-determining mechanism of the He diffusion process and the corresponding migration energy is computed as 2.79 eV at 0 K (with the spin-orbit coupling (SOC) included), and as 2.09 eV by using the thermally expanded lattice parameter of UO₂ at 1200 K, which is relatively close to the experimental value of 2.0 eV. The lattice expansion coefficient of He-induced swelling of UO₂ is calculated as 9 × 10⁻². For two He atoms, we have found that they form a dumbbell configuration if they are close enough to each other, and that the lattice expansion induced by a dumbbell is larger than by two distant interstitial He atoms. The clustering tendency of He has been studied for small clusters of up to six He atoms. We find that He strongly tends to cluster in the vicinity of an OIS, and that the collective action of the He atoms is sufficient to spontaneously create additional point defects around the He cluster in the UO₂ lattice.     

Crystal chemistry of uranium (V) and plutonium (IV) in a titanate ceramic for disposition of surplus fissile material

We report X-ray absorption near-edge structure (XANES) and extended X-ray absorption fine-structure (EXAFS) spectra for the plutonium LIII and uranium LIII edges in titanate pyrochlore ceramic. The titanate ceramics studied are of the type proposed to serve as a matrix for the immobilization of surplus fissile materials. The samples studied contain approximately 10 wt% fissile plutonium and 20 wt% natural uranium, and are representative of material within the planned production envelope. Based upon natural analogue models, it had been previously assumed that both uranium and plutonium would occupy the calcium site in the pyrochlore crystal structure. While the XANES and EXAFS signals from the plutonium LIII are consistent with this substitution into the calcium site within pyrochlore, the uranium XANES is characteristic of pentavalent uranium. Furthermore, the EXAFS signal from the uranium has a distinct oxygen coordination shell at 2.07 Å and a total oxygen coordination of about 6, which is inconsistent with the calcium site. These combined EXAFS and XANES results provide the first evidence of substantial pentavalent uranium in an octahedral site in pyrochlore. This may also explain the copious nucleation of rutile (TiO₂) precipitates commonly observed in these materials as uranium displaces titanium from the octahedral sites.     

Quantum mechanical calculations of uranium phases and niobium defects in γ-uranium

Depleted uranium (U) from fuel enrichment processes has a variety of applications due to its high density. With the addition of a small concentration of niobium (Nb), U becomes stainless. Nb is fully miscible with the high-temperature γ phase of U and tends to segregate upon cooling below 1050 K. The starting point of segregation is the configuration of Nb substitutional or interstitial defects. Using quantum mechanical calculations, the authors find that the formation energy of a single vacancy is 1.08 eV, that of Nb substitution 0.59 eV, that of Nb interstitial at octahedral site 1.58 eV, and that of Nb interstitial at tetrahedral site 2.35 eV in the dilute limit of isolated defects; all with reference to a reservoir of the pure γ phase U and pure Nb. The analysis of electronic structures reveals the correlation of formation energies of Nb defects with the local perturbations of electron distribution. Higher formation energy of Nb defects correlates with larger perturbation. Based on this study, Nb atoms thermodynamically prefer to occupy substitutional sites in the γ phase U.     

Ab initio energetics of some fission products (Kr, I, Cs, Sr and He) in uranium dioxide

A computational study of some fission products (FP) energetics in uranium dioxide is presented. Krypton, iodine, caesium, strontium and helium are considered. Calculations are made within the density functional theory in the local density approximation with the plane wave pseudopotential method. Three insertion sites are considered: the octahedral interstitial position and the oxygen and uranium substitution sites. The importance of atomic relaxations is estimated on the He and Kr cases. They prove quantitatively important but can be neglected to draw qualitative trends. For each fission product incorporation and solution energies are calculated. The obtained values of the solutions energies of the various FP are in good agreement with their experimental behaviour: Kr, Cs and I atoms are insoluble in uranium dioxide, Sr solubility depends on the stoichiometry of urania. He atoms are found to have little interaction with their environment in uranium doxide.     

Study on C-W interactions by molecular dynamics simulations

By means of molecular dynamics simulations using bond-order potential (BOP), we have investigated the interactions between carbon (C) atoms and bcc tungsten (W). At finite temperature (T = 300 K) with incident energy of C atoms ranging from 0.5 to 100 eV at normal incidence, the projected range distribution as a function of incident energy and the average depth have been depicted. The properties of vacancy, vacancy migration, interstitial and substitutional C atoms in W have been determined. The most stable configuration for an interstitial C atom in W is in octahedral position and the lattice distortion around the C atom in octahedral interstitial configuration occurs along 〈1 0 0〉 and 〈1 1 0〉 directions. The mutual interaction between a vacancy and near interstitial C atom is also studied.