Progress in Nuclear Energy最新文献_第8页

Preliminary analysis of startup and acceleration transient characteristics of helium-xenon cooled reactor direct brayton cycle system 氦氙冷却反应堆直接布雷顿循环系统的启动和加速瞬态特性初步分析

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-26 DOI: 10.1016/j.pnucene.2024.105462

Haoyang Liao , Fulong Zhao , Hui Bao , Ruibo Lu , Sichao Tan , Puzhen Gao , Ruifeng Tian

Helium-xenon cooled reactor direct Brayton cycle system has excellent application prospects in small nuclear power plants due to its light weight, high compactness and simple structure. The safe startup of reactor system is very important, so the system startup scheme is designed. In addition, reactor system may be affected by external acceleration during operation. Whether reactor system can operate normally and safely after being affected by acceleration and its influence characteristics are not clear. In order to verify the feasibility of the system startup scheme and explore the acceleration influence characteristics, the system analysis program was developed to simulate the system startup transient operating conditions and the transient operating conditions of reactor system under the influence of acceleration. In the research of acceleration influence characteristics, acceleration has different periods, amplitudes, types and directions, and the load state is divided into load change with system output power and constant load. The results show that the designed system startup scheme can start reactor system safely. Reactor system can ignore the influence of acceleration when it has load change with system output power ability. If the load remains constant, reactor system cannot ensure continuous and stable operation after being affected by acceleration, which has the risk of Loss of Flow Accident (LOFA). The relevant research results provide theoretical reference and support for the design of the reactor system startup scheme and the research on the influence characteristics of acceleration on reactor system.

氦-氙冷却反应堆直接布雷顿循环系统重量轻、结构紧凑、简单，在小型核电站中具有良好的应用前景。反应堆系统的安全启动非常重要，因此设计了系统启动方案。此外，反应堆系统在运行过程中可能会受到外部加速度的影响。反应堆系统在受到加速度影响后能否正常安全运行及其影响特性尚不清楚。为了验证系统启动方案的可行性，探讨加速度影响特性，开发了系统分析程序，模拟系统启动瞬态运行工况和反应堆系统在加速度影响下的瞬态运行工况。在加速度影响特性的研究中，加速度有不同的周期、幅值、类型和方向，负载状态分为随系统输出功率变化的负载变化和恒定负载。结果表明，所设计的系统启动方案可以安全启动反应堆系统。当反应堆系统具备随系统输出功率变化的负载能力时，可以忽略加速度的影响。如果负载恒定，反应堆系统在受到加速度影响后无法保证持续稳定运行，存在失流事故（LOFA）风险。相关研究成果为反应堆系统启动方案设计和加速度对反应堆系统影响特性的研究提供了理论参考和支持。

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引用次数: 0

Chlorination of HALEU regulus casting dross HALEU regulus 铸造渣的氯化处理

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-26 DOI: 10.1016/j.pnucene.2024.105464

Guy L. Fredrickson, Brennan C. Mohr, Michael N. Patterson

A scoping study was performed for chlorinating dross formed during uranium casting operations. The purpose is to minimize the losses of uranium to dross wastes. The dross is primarily a mixture of uranium metal and uranium oxide with a minor fraction of crucible and crucible coating materials. The reaction chemistries were performed in a carrier salt of LiCl-KCl eutectic at 500 °C. The addition of FeCl₂ chlorinated the uranium metal to UCl₃, by reducing the FeCl₂ to iron metal. After the uranium metal was chlorinated, zirconium metal was added to the salt. The residual FeCl₂ chlorinated the zirconium metal to ZrCl₄, by reducing the FeCl₂ to iron metal. In turn, the ZrCl₄ chlorinated the uranium oxide to UCl₃, by converting the ZrCl₄ to zirconium oxide. The effectiveness of the chlorination reactions was qualitatively verified by cyclic voltammograms that indicated the presence or absence of FeCl₂ and UCl₃ in the salt.

对铀铸造过程中形成的渣滓进行了范围研究。目的是尽量减少铀在渣滓废物中的损失。渣滓主要是金属铀和氧化铀的混合物，还有一小部分坩埚和坩埚涂层材料。反应化学反应是在 500 °C 的 LiCl-KCl 共晶载盐中进行的。加入氯化铁后，通过将氯化铁还原成金属铁，将金属铀氯化成 UCl3。金属铀氯化后，向盐中加入金属锆。残留的 FeCl2 通过将 FeCl2 还原成金属铁，将金属锆氯化成 ZrCl4。反过来，ZrCl4 通过将 ZrCl4 转化为氧化锆，将氧化铀氯化为 UCl3。氯化反应的有效性通过循环伏安图进行定性验证，循环伏安图显示盐中是否存在 FeCl2 和 UCl3。

引用次数: 0

Depressurization strategy of China's advanced pressurized water reactor under typical accidents 典型事故下中国先进压水堆的减压策略

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-26 DOI: 10.1016/j.pnucene.2024.105459

Ji Xing , Pei Yu , Zhaoming Meng , Dufeng Lv , Zhengrun Shang , Zhongning Sun

Advanced pressurized water reactor was simulated using system analysis program. The depressurization strategy for the automatic depressurization system (ADS) under typical ADS-triggering accidents (2-inch/10-inch cold leg break, inadvertent opening of the ADS, DVI pipeline break) was investigated. The results show that after these accidents, ADS can ensure the operation of the three types of safe injection tanks, with high redundancy and inherent safety. The multi-stage design of ADS aids the sparger in maintaining a stable critical jet state. In 10-inch cold leg break accident, the sparger cannot reached the critical jet state under all of pipeline fault conditions. From a system point of view, adjusting the pipeline design of ADS is necessary to avoid long-term condensation oscillation of the sparger in some accidents. From a design perspective of the local equipment, the nozzle structure of the sparger should attenuate the dynamic load caused by the condensation oscillation and back-attack phenomenon.

利用系统分析程序对先进压水反应堆进行了模拟。研究了自动减压系统（ADS）在典型触发事故（2 英寸/10 英寸冷腿断裂、ADS 意外打开、DVI 管线断裂）下的减压策略。结果表明，在这些事故发生后，ADS 能够确保三类安全注水罐的运行，具有较高的冗余度和固有安全性。ADS 的多级设计有助于喷射器保持稳定的临界喷射状态。在 10 英寸冷腿断裂事故中，在所有管线故障条件下，疏水阀都无法达到临界喷射状态。从系统角度看，有必要调整 ADS 的管路设计，以避免在某些事故中疏水阀出现长期冷凝振荡。从局部设备的设计角度来看，喷射器的喷嘴结构应减弱冷凝振荡和反击现象引起的动载荷。

引用次数: 0

Nuclear fuel qualification: History, current state, and future 核燃料鉴定：历史、现状和未来

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-26 DOI: 10.1016/j.pnucene.2024.105460

Mitchell Mika , Allison Probert , Assel Aitkaliyeva

The qualification of nuclear fuel is the process by which a fuel is certified for use within a reactor design. This process involves massive technical and procedural coordination across multiple private and public institutions with long project completion timelines. The current frameworks published in literature do not address the roles of private reactor developers in the qualification process, nor the regulatory requirements that form the background for fuel qualification. These roles and requirements are not static and have evolved throughout the development of the commercial nuclear industry. UO₂ fuel, the only fuel considered fully qualified today, achieved its status in large part due to its early selection and rapid deployment under a still developing regulatory landscape. Today, fuel qualification efforts must operate within modern regulatory realities, which will require extensive testing and model development. Building on the existing fuel qualification frameworks, we define the optimal roles of the parties involved with fuel qualification. We also suggest viewing experimental efforts through a data-centric perspective in which parallel improvements can be made in collection, processing, and storage to facilitate quicker qualification timelines. These efforts then promote advanced modeling efforts, such as mechanistic modeling and digital twin development.

核燃料鉴定是对反应堆设计中使用的燃料进行认证的过程。这一过程涉及多个私营和公共机构的大规模技术和程序协调，项目完成时间较长。文献中公布的现有框架并未涉及私营反应堆开发商在鉴定过程中的角色，也未涉及构成燃料鉴定背景的监管要求。这些角色和要求并不是一成不变的，在商业核工业的整个发展过程中都在不断演变。二氧化铀燃料是当今唯一一种被认为完全合格的燃料，它之所以能取得这样的地位，在很大程度上要归功于其早期的选择以及在仍在发展中的监管环境下的快速部署。如今，燃料鉴定工作必须在现代监管现实下进行，这就需要进行广泛的测试和模型开发。在现有燃料鉴定框架的基础上，我们定义了参与燃料鉴定的各方的最佳角色。我们还建议通过以数据为中心的视角来看待实验工作，在收集、处理和存储方面进行并行改进，以加快鉴定时间。这些工作将促进先进的建模工作，如机械建模和数字孪生开发。

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引用次数: 0

Shutdown dose rate calculation for fission reactors: An application of the MS-CADIS method to OPAL 裂变反应堆的关停剂量率计算：MS-CADIS 方法在 OPAL 中的应用

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-25 DOI: 10.1016/j.pnucene.2024.105448

B. Marcinkevicius, C. Fedon

There have been considerable advances of shutdown dose rate (SDDR) calculation methods for fusion related problems, however applications of these methods in the fission reactor field have hitherto been sparse. The present study attempts to bridge this gap by investigating the applicability of SDDR calculation methods for fission reactor problems. Specifically, we aim to assess and validate whether recent advances in SDDR methods can be successfully applied in fission research reactors. To this end, we estimate the shutdown dose rate distribution at the Open Pool Australian Light water reactor (OPAL) using the rigorous two step (R2S) computational method, and we compare the calculated results with the experimental data. This method utilizes a 3D reactor model implemented in the Monte Carlo N-Particle (MCNP) transport code, the AutomeD VAriaNce reduction Generator (ADVANTG) code for geometry discretization and variance reduction calculations, and the Oak Ridge Isotope GENeration (ORIGEN) inventory code for activation calculations. To ensure robustness, we employ two variance reduction techniques, Forward Weighted Consistent Adjoint Driven Importance Sampling (FW-CADIS) and Multi-Step Consistent Adjoint Driven Importance Sampling (MS-CADIS). To the best of our knowledge, this is the first MS-CADIS method implementation for fission reactor problems. The SDDR is estimated at ten locations within the experimental hall, all situated more than 4 m away from the reactor core.

The paper shows that, the experimental observations are within the lower and upper bounds of the simulation results for 4 out of 10 locations, while the remaining observations are within a factor of 7, with one significant outlier. The calculated average dose rate is within 5% of the nominal values of the experimental observations for 3 locations. The computational results are within statistical uncertainty by using two different variance reduction techniques, with significant computational advantage of MS-CADIS over FW-CADIS for SDDR calculations. The results indicate that the combination of SDDR distribution maps, estimated dose rate energy dependance, and activation information are powerful tools in identifying the radioisotopes and reactor components dominating the SDDR. These results can contribute to better radiation safety practices in contaminated areas, by enabling the minimal dose path planning or by improving radiation shielding.

针对核聚变相关问题的停堆剂量率（SDDR）计算方法已经取得了长足的进步，但这些方法在裂变反应堆领域的应用还很少。本研究试图通过调查 SDDR 计算方法对裂变反应堆问题的适用性来弥补这一差距。具体来说，我们旨在评估和验证 SDDR 方法的最新进展能否成功应用于裂变研究反应堆。为此，我们使用严格的两步（R2S）计算方法估算了澳大利亚开式水池轻水反应堆（OPAL）的关停剂量率分布，并将计算结果与实验数据进行了比较。该方法利用蒙特卡洛 N 粒子（MCNP）传输代码中的三维反应堆模型、AutomeD VAriaNce reduction Generator（ADVANTG）代码进行几何离散化和方差缩小计算，并利用橡树岭同位素生成器（ORIGEN）库存代码进行活化计算。为确保稳健性，我们采用了两种方差缩小技术：前向加权一致邻接驱动重要度采样（FW-CADIS）和多步一致邻接驱动重要度采样（MS-CADIS）。据我们所知，这是首次针对裂变反应堆问题实施 MS-CADIS 方法。论文显示，在 10 个地点中，有 4 个地点的实验观测值在模拟结果的上下限范围内，其余观测值在 7 倍范围内，有一个显著离群点。在 3 个地点，计算得出的平均剂量率在实验观测值标称值的 5%以内。通过使用两种不同的方差缩小技术，计算结果在统计不确定性范围内，在 SDDR 计算中，MS-CADIS 比 FW-CADIS 具有显著的计算优势。结果表明，SDDR 分布图、估计剂量率能量相关性和活化信息的组合是确定主导 SDDR 的放射性同位素和反应堆成分的有力工具。这些结果可以通过最小剂量路径规划或改进辐射屏蔽，为污染区更好的辐射安全实践做出贡献。

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引用次数: 0

Verifications and applications of NECP-Bamboo2.0 for PWR whole-core multi-cycle pin-by-pin simulation NECP-Bamboo2.0 在 PWR 整核多周期逐引脚仿真中的验证和应用

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-24 DOI: 10.1016/j.pnucene.2024.105447

Sicheng Wang, Yunzhao Li, Junwei Qin, Yilin Liang, Yuancheng Zhou, Liangzhi Cao, Hongchun Wu

In 2018, the NECP Laboratory at Xi'an Jiaotong University (XJTU) published the pin-by-pin two-step calculation code system NECP-Bamboo2.0 for the physics analysis of Pressurized Water Reactors (PWRs). Previously, NECP-Bamboo2.0 was primarily verified for its neutronics analysis capabilities. The code system has recently been enhanced for practical reactor physics analysis of commercial PWR cores. In this paper, several modifications of NECP-Bamboo2.0 regarding its improvement in functionality are introduced. Then, the pin-by-pin calculation capability of the code system was verified using the 2D and 3D VERA benchmark problems. Comparisons with reference solutions provided by high-fidelity codes demonstrated the computational accuracy of NECP-Bamboo2.0. Additionally, NECP-Bamboo2.0 was applied to the multi-cycle physics analysis of two commercial PWR cores, CNP300 and CNP1000. Comparisons with the measurements regarding the startup physics tests and the depletion processes illustrate the reliability of NECP-Bamboo2.0 in practical pin-by-pin reactor physics analysis and highlight the improvements of the pin-by-pin method over the assembly-homogenized coarse-mesh diffusion method.

2018年，西安交通大学NECP实验室发布了用于压水堆物理分析的逐针两步计算代码系统NECP-Bamboo2.0。此前，NECP-Bamboo2.0 主要验证了其中子分析能力。最近，该代码系统针对商用压水堆堆芯的实际反应堆物理分析进行了增强。本文介绍了NECP-Bamboo2.0在功能改进方面的几处修改。然后，使用二维和三维 VERA 基准问题验证了代码系统的逐针计算能力。通过与高保真代码提供的参考解进行比较，证明了NECP-Bamboo2.0的计算精度。此外，NECP-Bamboo2.0还应用于CNP300和CNP1000两个商用压水堆堆芯的多周期物理分析。与有关启动物理试验和耗竭过程的测量结果的比较说明了NECP-Bamboo2.0在实际逐针反应堆物理分析中的可靠性，并突出了逐针方法与装配均质化粗网格扩散方法相比的改进之处。

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引用次数: 0

Optical and gamma-ray shielding properties of calcium sodium borate glasses with varied equal concentrations of ZnO and BaO 含有不同等量氧化锌和氧化钡的钙钠硼酸盐玻璃的光学和伽马射线屏蔽特性

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-24 DOI: 10.1016/j.pnucene.2024.105451

M.I. Sayyed , Nabasu Seth Ezra , Iskandar Shahrim Mustafa , K.K. Dakok , M. Rashad , Yasser Maghrbi

This study presents the optical and radiation shielding characteristics of a newly developed borate glass, doped with equal quantities of ZnO and BaO, and modified with calcium and sodium. The glass samples were prepared using the melt quenching technique, with the composition formula (80-x-y)B₂O₃-10CaO-10Na₂O-xZnO-yBaO, where x and y were varied at 5, 10, 15, and 20 mol%. Comprehensive analyses of the optical and gamma shielding properties were carried out using UV–visible spectrophotometry and Phy-X software, respectively. The UV–visible spectroscopic data allowed for the calculation of various parameters including the direct and indirect optical energy band gaps, refractive index, dielectric constants, and polarizability. It was observed that the direct optical energy band gap decreased from 3.91 to 3.10 eV, while the indirect band gap fell from 3.41 to 2.91 eV with increasing ZnO and BaO content. Conversely, the refractive index rose from 2.29 to 2.42 with higher concentrations of ZnO and BaO. The linear attenuation coefficients (LACs) across the range of 0.015–15 MeV exhibited an inverse relationship. Among the glass samples, B40Zn20Ba20 exhibited the lowest tenth value layer (TVL) and the highest effective atomic number (Zeff), indicating its superior performance as a radiation shielding material. Overall, the produced glass samples demonstrate commendable properties for both optical applications and radiation shielding.

本研究介绍了一种新开发的掺杂了等量氧化锌和氧化钡并用钙和钠改性的硼酸盐玻璃的光学和辐射屏蔽特性。玻璃样品采用熔体淬火技术制备，其组成式为 (80-x-y)B2O3-10CaO-10Na2O-xZnO-yBaO ，其中 x 和 y 分别为 5、10、15 和 20 摩尔%。紫外可见分光光度法和 Phy-X 软件分别对光学和伽马屏蔽特性进行了全面分析。紫外可见光谱数据可用于计算各种参数，包括直接和间接光学能带隙、折射率、介电常数和极化性。结果表明，随着氧化锌和氧化钡含量的增加，直接光能带隙从 3.91 eV 下降到 3.10 eV，而间接能带隙则从 3.41 eV 下降到 2.91 eV。相反，随着 ZnO 和 BaO 含量的增加，折射率从 2.29 上升到 2.42。在 0.015-15 MeV 的范围内，线性衰减系数（LAC）呈反比关系。在玻璃样品中，B40Zn20Ba20 的十值层（TVL）最低，有效原子序数（Zeff）最高，表明其作为辐射屏蔽材料的性能优越。总体而言，所生产的玻璃样品在光学应用和辐射屏蔽方面都表现出了值得称道的性能。

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引用次数: 0

A Proposed Non-Intrusive System for the Verification of Sensitive Nuclear Material 用于核查敏感核材料的拟议非侵入式系统

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-24 DOI: 10.1016/j.pnucene.2024.105456

M. Ibrahim , W. El-Gammal , M. Darweesh , N. Mostafa , M. Mohsen

One of the primary challenges in negotiating treaties related to the control of Nuclear Materials (NM) is the verification process, particularly when dealing with sensitive information. Normally, in this process, the inspector utilizes a suitable measuring system to verify the declared information. The difficulty may arise whenever sensitive information related to the NM should not be released to an inspector. Simultaneously, the NM owner (operator) should remain unaware of the measuring system employed by the inspector to prevent any probable manipulation. To address this issue, a neutral third party is assumed to act as an intermediary, who matches the data declared by the operator with the results obtained by the inspector, without exchanging any information between them. In this work, a Non-Intrusive System (NIS) is proposed and tested to play this role. The system receives data and information from both the operator and the inspector in the form of CAD or Monte Carlo (MC) input files, in addition to the results of measurements performed by the inspector. Then the system performs calculations and combines the results of these calculations with the inspector's measurement result to estimate the mass of the NM. The only information automatically conveyed to the inspector is the final conclusion regarding whether the declared and the estimated masses of NM are matched or not. The proposed NIS concept is tested using samples of NMs, and the results are presented.

与核材料（NM）管制有关的条约谈判的主要挑战之一是核查过程，特别是在处理敏感信息时。通常情况下，在这一过程中，检查员利用适当的测量系统对申报的信息进行核查。当与核材料有关的敏感信息不应透露给检查员时，就会出现困难。同时，核磁共振所有者（操作者）应不知道检查员使用的测量系统，以防止任何可能的操纵。为解决这一问题，假定由中立的第三方充当中间人，将操作员申报的数据与检查员获得的结果进行比对，但两者之间不交换任何信息。在这项工作中，提出并测试了一种非侵入式系统（NIS）来扮演这一角色。该系统以 CAD 或蒙特卡洛（MC）输入文件的形式接收来自操作员和检测员的数据和信息，此外还接收检测员的测量结果。然后，系统进行计算，并将计算结果与检查员的测量结果相结合，估算出非金属的质量。自动传达给检验员的唯一信息是关于申报质量和估计质量是否匹配的最终结论。我们使用非金属矿物样本对所提出的非金属矿物检测系统概念进行了测试，并展示了测试结果。

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引用次数: 0

Understanding the effect of alkyl chain on extraction of Np4+ and Pu4+ with hexaalkyl nitrilotriacetamides into an ionic liquid vis-à-vis a molecular solvent 了解烷基链对六烷基次氮基三乙酰胺在离子液体中萃取 Np4+ 和 Pu4+ 与分子溶剂的影响

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-24 DOI: 10.1016/j.pnucene.2024.105455

R.B. Gujar , S.A. Ansari , P.K. Mohapatra , R.J.M. Egberink , W. Verboom

Extraction of actinides using exotic ligands in room temperature ionic liquids is one of the most preferred areas of research these days. Though the amides are well studied for the extraction of actinides from nitric acid feeds, multiple amides (such as tripodal amides) are of recent origin, and reports on solvent extraction with these ligands in room temperature ionic liquids are very rare. In this work, the extraction of Np⁴⁺ and Pu⁴⁺ was studied with a series of N,N,N′,N′,N″,N″-hexaalkyl nitrilotriacetamides (NTAamides) in an ionic liquid with an objective to understand the effect of the alkyl chains length on their extraction ability. Bumim⋅Tf₂N was chosen as ionic liquid due to its favourable viscosity for distribution studies. The extraction of tetravalent actinides Np⁴⁺ and Pu⁴⁺ increased linearly with increasing the alkyl chain of the NTAamides from n-butyl via n-hexyl to n-octyl. The extraction pattern was surprisingly opposite to the most observed extraction patterns in an ionic liquid, where the extraction generally decreases sharply upon increasing the feed acidity. The extracted species were ascertained as M(NO₃)₅⋅L (LH), where M = Np⁴⁺ or Pu⁴⁺, for each ligand. Consequent to the formation of an entirely divergent extracted complex, the extraction pattern is completely different than that expected in an ionic liquid.

利用室温离子液体中的特殊配体萃取锕系元素是当今最热门的研究领域之一。虽然酰胺类配体在从硝酸进料中萃取锕系元素方面的研究较多，但多重酰胺类配体（如三元酰胺类配体）是最近才出现的，而且在室温离子液体中使用这些配体进行溶剂萃取的报告非常罕见。在这项工作中，研究了在离子液体中使用一系列 N,N,N′,N′,N″,N″-六烷基三硝基乙酰胺（NTAamides）萃取 Np4+ 和 Pu4+，目的是了解烷基链长度对其萃取能力的影响。由于 Bumim⋅Tf2N 的粘度适于分布研究，因此被选为离子液体。四价锕系元素 Np4+ 和 Pu4+ 的萃取随着 NTAamides 烷基链从正丁基到正己基再到正辛基的增加而线性增加。这种萃取模式与在离子液体中观察到的大多数萃取模式截然相反，在离子液体中，当进料酸度增加时，萃取率通常会急剧下降。对每种配体而言，萃取的物种被确定为 M(NO3)5⋅L (LH)，其中 M = Np4+ 或 Pu4+。由于形成了完全不同的萃取复合物，萃取模式与离子液体中的预期模式完全不同。

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引用次数: 0

Optimization of pure elemental and oxide-based shielding materials for cost 优化纯元素和氧化物屏蔽材料，降低成本

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy

Pub Date : 2024-09-24 DOI: 10.1016/j.pnucene.2024.105444

Banks Peete, Stephen Trainor, Robert Hayes

A common aspect to shielding material research is the combination of high atomic number inclusions with binders although the costs of the inclusions will vary with chemical form and have associated density and atomic number dependencies on attenuation properties. As most metals are cheaper in their oxide forms (sometimes drastically) we considered oxide forms to substantially reduce potential cost. This study then investigates the combined shielding and cost optimization of pure elemental and oxide-based shielding materials as well as steel, water and concrete. This focus on shielding effectiveness per cost and weight basis also incorporates contributions from scattered radiation in the form of radiation buildup for these comprehensive materials. In this sense, we define a new metric which incorporates cost, weight and scatter radiation for assessing shielding material attractiveness. We used MicroShield to calculate the shielding ability of each material. Our findings revealed that water, concrete, and lead demonstrated superior performance in terms of cost-effectiveness. This research contributes to the understanding of affordable and efficient shielding materials and has implications for industries reliant on radiation protection, such as nuclear power generation, medical imaging, and space exploration.

屏蔽材料研究的一个常见方面是将高原子序数夹杂物与粘合剂结合起来，尽管夹杂物的成本会因化学形态而异，并与衰减特性的密度和原子序数相关。由于大多数金属的氧化物形态比较便宜（有时甚至非常便宜），我们考虑采用氧化物形态来大幅降低潜在成本。然后，本研究调查了纯元素和氧化物屏蔽材料以及钢、水和混凝土的综合屏蔽和成本优化。这项研究的重点是按成本和重量计算的屏蔽效果，同时还考虑了这些综合材料以辐射积聚形式产生的散射辐射。从这个意义上说，我们定义了一个新的指标，它包含了成本、重量和散射辐射，用于评估屏蔽材料的吸引力。我们使用 MicroShield 计算了每种材料的屏蔽能力。我们的研究结果表明，水、混凝土和铅在成本效益方面表现出色。这项研究有助于人们了解经济、高效的屏蔽材料，对核能发电、医学成像和太空探索等依赖辐射防护的行业具有重要意义。

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引用次数: 0