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Corrosion studies of Inconel 617 in high temperature air and He-ppmO2 atmospheres 高温空气和 He-ppmO2 气体环境中 Inconel 617 的腐蚀研究
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.08.023
Haoxiang Li , Wei Zheng , Bin Du , Huang Zhang , Huaqiang Yin , Xuedong He , Tao Ma , Xingtuan Yang
Air ingress accident is one of the typical accident conditions in Very High Temperature Reactors (VHTRs). This work investigates the oxidation kinetics, corrosion behavior and mechanism of Inconel 617 alloy in different oxygen concentration atmospheres under air ingress accident. The impact of O2 concentration and oxidation time of the alloy corrosion is investigated. A gas chromatograph was used to measure the impurity content in real time during the helium experiments. After the experiments, the alloys were characterized by electronic balance, were analyzed by Scanning Electron Microscopy (SEM), Energy-Dispersive X-ray Spectroscopy (EDS), X-ray diffraction (XRD) and carbon and sulfur analyzer. The results show that: the Inconel 617 alloy undergoes similar oxidation behavior and the degree of oxidation is very close in three groups of atmospheres with large differences in oxygen content; the alloy should show two oxidation mechanisms, linear oxidation and parabolic oxidation, during the oxidation process; the parabolic rate constant kp and kt of the alloy is a constant value and does not vary with large changes in oxygen concentration, but when the experimental temperature changes, the oxidation rate constants of the alloy change, and the lowering of the temperature leads to the lowering of the oxidation rate constants; When experimental temperature is at 950 °C, the alloy continues to undergo a “microclimatic reaction” in the atmosphere of He-ppmO2, and the microclimatic reaction disappears when the experimental temperature is lowered to 750 °C; In He-ppmO2 environment, gas chromatograph can be used instead of thermogravimetric analyzer for real-time monitoring.
进气事故是超高温反应堆(VHTR)的典型事故条件之一。本研究探讨了 Inconel 617 合金在不同氧浓度气氛中发生进气事故时的氧化动力学、腐蚀行为和机理。研究了氧浓度和氧化时间对合金腐蚀的影响。在氦气实验过程中,使用气相色谱仪实时测量杂质含量。实验结束后,用电子天平对合金进行了表征,并用扫描电子显微镜(SEM)、能量色散 X 射线光谱(EDS)、X 射线衍射(XRD)和碳硫分析仪进行了分析。结果表明在氧含量差异较大的三组气氛中,Inconel 617 合金的氧化行为相似,氧化程度非常接近;合金在氧化过程中应呈现线性氧化和抛物线氧化两种氧化机理;合金的抛物线速率常数和是一个恒定值,不会随氧浓度的大幅变化而变化,但当实验温度变化时,合金的氧化速率常数会发生变化,温度的降低会导致氧化速率常数的降低;当实验温度为 950 ℃ 时,合金在 He-ppmO 气氛中继续发生 "微气候反应",当实验温度降低到 750 ℃ 时,微气候反应消失;在 He-ppmO 环境中,可使用气相色谱仪代替热重分析仪进行实时监测。
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引用次数: 0
Searching for incinerating the accumulated plutonium around the world by mixing it with thorium and using this mixture as a nuclear fuel in the CANDU-6 寻找将世界各地积累的钚与钍混合后焚化的方法,并将这种混合物用作 CANDU-6 的核燃料
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.08.022
A. Abdelghafar Galahom , Nassar Alnassar , Amr Ibrahim
This work investigates the possibility of getting rid of the accumulated plutonium around the world by mixing it with fertile materials and using it as a nuclear fuel for CANDU-6. Using plutonium isotopes with thorium as a nuclear fuel for CANDU-6 is a means of preventing the production of other Pu isotopes. MCNPX has been used to design a three dimensional model of the CANDU-6 bundle. Three fuel types including (238U, rgPu)O2, (232Th, rgPu)O2 and (232Th, wgPu)O2 have been examined as nuclear fuel in the designed model and their results were compared with UO2 as a standard fuel. The fuel burnup parameters such as kinf, fissile inventory ratio, plutonium concentration and minor actinides concentration have been analyzed for the suggested fuels. Some of the most related safety parameters such as effective delayed neutrons (βeff), moderator temperature coefficient, coolant temperature coefficient and Doppler constant have been studied. The excess thermal neutrons in the CANDU-6 maximized the benefit of using plutonium-based fuels, where a significant amount of plutonium has been burned during the fuel cycle. From the neutronic and safety point of view, thorium fuel mixed with reactor grade plutonium has proven to be the most promising candidate among the investigated fuels.
这项工作研究了将世界各地积累的钚与肥沃的材料混合并用作 CANDU-6 的核燃料,从而消除这些钚的可能性。将钚同位素与钍一起用作 CANDU-6 的核燃料是防止产生其他钚同位素的一种手段。MCNPX 被用来设计 CANDU-6 燃料束的三维模型。在所设计的模型中,包括(铀、rgPu)O、(钍、rgPu)O 和(钍、wgPu)O 在内的三种燃料已作为核燃料进行了检验,并将其结果与作为标准燃料的氧化铀进行了比较。对建议燃料的燃烧参数,如 k、裂变库存比、钚浓度和次要锕系元素浓度进行了分析。研究了一些最相关的安全参数,如有效延迟中子(β)、慢化剂温度系数、冷却剂温度系数和多普勒常数。CANDU-6 中过剩的热中子最大限度地提高了使用钚基燃料的效益,在燃料循环过程中燃烧了大量的钚。从中子和安全角度来看,与反应堆级钚混合的钍燃料已被证明是所研究燃料中最有前途的候选燃料。
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引用次数: 0
Methodology for risk assessment of multi-event scenarios on radioactive waste repository 放射性废物储存库多事件情景风险评估方法
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.08.014
Karyoung Choi, Minseok Kim, Kibeom Son, Gyunyoung Heo
Deep geological disposal, which is a permanent method that isolates a storage facility in rocks 200 to 1000 m deep underground, plays a role in safely disposing spent nuclear fuel to prevent excessive radioactive species from leaking out and its safety should be primarily proved. Risk for various radionuclide leakage scenarios should be calculated to be used as a safety indicator. One of the scenarios that significantly affects the safety of repository is the occurrence of external events such as an earthquake scenario. Several occurrences of such external disasters are expected over a long period of time which the safety functions of the deep disposal site must be maintained. Rather than performing a conservative single event evaluation, we expected that performing a more realistic evaluation, such as considering the number of events, is preferrable for design and operation optimization, particularly in an early project phase. This paper suggests a need for assessing multi-event scenarios and the methodology for simulation of several external disasters using earthquakes as an example. The methodology and algorithm of simulating multiple earthquakes and assessing risk distribution under those events at repository site is introduced in GoldSim software, and its results are expected to be used at simulating other event scenarios.
深层地质处置是将贮存设施隔离在地下 200 至 1000 米深处岩石中的一种永久性方法,在安全处置乏核燃料以防止过量放射性物质泄漏方面发挥着作用,其安全性应首先得到证实。应计算各种放射性核素泄漏情况下的风险,将其作为安全指标。严重影响储存库安全的情况之一是外部事件的发生,如地震。在深层处置场必须保持安全功能的很长一段时间内,预计会发生多次此类外部灾害。我们认为,与其进行保守的单一事件评估,不如进行更现实的评估,如考虑事件的数量,以优化设计和运行,尤其是在项目早期阶段。本文以地震为例,提出了评估多事件情景的需求以及模拟多种外部灾害的方法。本文在 GoldSim 软件中介绍了模拟多种地震和评估这些事件下风险分布的方法和算法,其结果有望用于模拟其他事件情景。
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引用次数: 0
Development and experimental validation of conceptual models for solenoid-based in-vessel two-channel control rod position indicator 基于电磁阀的舱内双通道控制杆位置指示器概念模型的开发与实验验证
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.08.018
Soonwoo Han, Jae-Seon Lee
In this study, we proposed in-vessel two-channel control rod positioner models for small nuclear reactors and carried out performance tests to evaluate applicability of the models. Embedding control rod positioners in reactors reduces the volume of small reactors and minimizes the penetration parts of reactor. In this study, two models having two physically separated solenoids were developed for measuring the position of the control rod by using the inductance change of a solenoid. First, the principle of measuring the position of a ferromagnetic rod by using a solenoid was formulated, and the change in solenoid inductance with the rod position was calculated through finite element analysis. Based on the proposed models, test products were manufactured and tested on three items to confirm the feasibility of the proposed solenoid-based two-channel control rod position indicator.
在这项研究中,我们提出了用于小型核反应堆的舱内双通道控制棒定位器模型,并进行了性能测试,以评估模型的适用性。将控制棒定位器嵌入反应堆可减小小型反应堆的体积,并最大限度地减少反应堆的贯穿件。在这项研究中,开发了两个具有两个物理分离螺线管的模型,利用螺线管的电感变化测量控制棒的位置。首先,提出了利用螺线管测量铁磁杆位置的原理,并通过有限元分析计算了螺线管电感随铁磁杆位置的变化。根据所提出的模型,制造了测试产品,并在三个项目上进行了测试,以确认所提出的基于螺线管的双通道控制杆位置指示器的可行性。
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引用次数: 0
Influence of dissolved hydrogen and IG Cr carbide on the oxidation behavior of Alloy 600 in hydrogenated primary water 溶解氢和 IG 碳化铬对合金 600 在氢化原水中氧化行为的影响
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.08.003
Yun Soo Lim, Dong Jin Kim, Sung Woo Kim, Seong Sik Hwang, Sung Hwan Cho, Hong Pyo Kim
The internal oxidation (IO) and preferential intergranular oxidation (PIO) behavior of Alloy 600 depending on the dissolved hydrogen (DH) content and the IG Cr carbide in hydrogenated primary water were characterized in detail using analytical electron microscopy techniques. The oxidation layer was unstable when the DH concentration was such that Ni was in the vicinity of Ni/NiO equilibrium and it could easily be peeled off. Hence, the grain boundaries of the bare metal were attacked. PIO occurred and Cr-rich oxide identified as Cr2O3 was formed at the oxidized grain boundary. NiO emerged when the DH concentration was such that Ni was in an oxidizing state, whereas Ni enrichment occurred inside the oxidized grain boundary when the DH concentration was such that Ni was in a reducing state with respective to Ni/NiO equilibrium. The IG Cr carbide strongly affected the PIO behavior by means of the consumption of oxygen penetrating into the grain boundary. The depth of the IO layer decreased as the DH concentration increased. The different oxidation behaviors depending on the DH content and IG Cr carbide are believed to affect the PWSCC resistance of Alloy 600 significantly.
利用分析电子显微镜技术详细描述了合金 600 的内部氧化(IO)和优先晶间氧化(PIO)行为,这取决于氢化原水中的溶解氢(DH)含量和 IG 碳化铬。当 DH 浓度使 Ni 处于 Ni/NiO 平衡附近时,氧化层不稳定,很容易剥离。因此,裸金属的晶界受到侵蚀。发生了 PIO,在氧化的晶界处形成了富铬氧化物,即 CrO。当 DH 浓度使镍处于氧化状态时,会出现 NiO;而当 DH 浓度使镍处于还原状态时,氧化晶界内会出现镍/NiO 平衡。通过消耗渗入晶界的氧气,IG 碳化铬对 PIO 行为产生了强烈影响。IO 层的深度随着 DH 浓度的增加而减小。不同的氧化行为取决于 DH 含量和 IG 碳化铬,相信这将对合金 600 的耐 PWSCC 性能产生重大影响。
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引用次数: 0
Role of Nd (III) ions on B2O3–TeO2-GeO2-MgO glass composition for optical and ionizing protection application 钕 (III) 离子对 B2O3-TeO2-GeO2-MgO 玻璃成分在光学和电离防护应用中的作用
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.08.031
M.H.A. Mhareb , M.I. Sayyed , Rahman I. Mahdi , Kawa M. Kaky , M. Kh Hamad , Abed Jawad Kadhim
In this investigation, we reported three glass samples of Nd (III) ions doped boro-tellurite-germanite glasses. The chemical composition of (35-x) B2O3–20TeO2-10GeO2-35MgO-xNd2O3 where x = 2.5, 5, and 7.5, all in mol%, was used to synthesize an optical glass. XRD, FTIR, and optical absorption were utilized to evaluate the structural and optical properties of Nd2.5, Nd5.0, and Nd7.5. X-ray diffraction was measured in the spectra range of 10–80°. Additionally, spectra of FT-IR in the wavenumber range of 400–4000 cm−1 were reported to investigate all structural groups. Several absorption peaks related to the transitions from ground level 4I9/2 to the other excited state were investigated. Various mechanical, optical, and physical properties were calculated theoretically and analyzed to determine the role of the rare earth ions (Nd3+). The optical electronegativity (χ) and optical basicity (Λ) results showed a reduction in the strength of the bond and formed an ionic bond in the glass structure due to adding Nd2O3. These results align with the reduction in the elastic modulus results by adding Nd2O3 instead of B2O3. Radiation shielding parameters like HVL, TVL, MFP, and Zeff were thoroughly reported for all Nd2.5, Nd5.0, and Nd7.5, which showed slight improvement when Nd2O3 was added instead of B2O3.
在这项研究中,我们报告了三种掺杂钕 (III) 离子的硼碲锗石玻璃样品。我们采用 (35-x) BO-20TeO-10GeO-35MgO-xNdO 的化学成分合成了一种光学玻璃,其中 x = 2.5、5 和 7.5,均为 mol%。利用 X 射线衍射、傅立叶变换红外光谱和光学吸收来评估 Nd2.5、Nd5.0 和 Nd7.5 的结构和光学特性。X 射线衍射的光谱范围为 10-80°。此外,还报告了波长范围为 400-4000 厘米的傅立叶变换红外光谱,以研究所有结构基团。研究了与从基态 I 到其他激发态跃迁有关的几个吸收峰。对各种机械、光学和物理特性进行了理论计算和分析,以确定稀土离子(钕)的作用。光学电负性(χ)和光学碱性(Λ)结果表明,加入氧化钕后,玻璃结构中的键强度降低,形成了离子键。这些结果与添加氧化钕而不是氧化银后弹性模量降低的结果一致。对所有 Nd2.5、Nd5.0 和 Nd7.5 的辐射屏蔽参数(如 HVL、TVL、MFP 和 Z)进行了详细报告,结果表明,添加 NdO 而不是 BO 后,辐射屏蔽参数略有改善。
{"title":"Role of Nd (III) ions on B2O3–TeO2-GeO2-MgO glass composition for optical and ionizing protection application","authors":"M.H.A. Mhareb ,&nbsp;M.I. Sayyed ,&nbsp;Rahman I. Mahdi ,&nbsp;Kawa M. Kaky ,&nbsp;M. Kh Hamad ,&nbsp;Abed Jawad Kadhim","doi":"10.1016/j.net.2024.08.031","DOIUrl":"10.1016/j.net.2024.08.031","url":null,"abstract":"<div><div>In this investigation, we reported three glass samples of Nd (III) ions doped boro-tellurite-germanite glasses. The chemical composition of (35-x) B<sub>2</sub>O<sub>3</sub>–20TeO<sub>2</sub>-10GeO<sub>2</sub>-35MgO-xNd<sub>2</sub>O<sub>3</sub> where x = 2.5, 5, and 7.5, all in mol%, was used to synthesize an optical glass. XRD, FTIR, and optical absorption were utilized to evaluate the structural and optical properties of Nd2.5, Nd5.0, and Nd7.5. X-ray diffraction was measured in the spectra range of 10–80°. Additionally, spectra of FT-IR in the wavenumber range of 400–4000 cm<sup>−1</sup> were reported to investigate all structural groups. Several absorption peaks related to the transitions from ground level <sup>4</sup>I<sub>9/2</sub> to the other excited state were investigated. Various mechanical, optical, and physical properties were calculated theoretically and analyzed to determine the role of the rare earth ions (Nd<sup>3+</sup>). The optical electronegativity (χ) and optical basicity (Λ) results showed a reduction in the strength of the bond and formed an ionic bond in the glass structure due to adding Nd<sub>2</sub>O<sub>3</sub>. These results align with the reduction in the elastic modulus results by adding Nd<sub>2</sub>O<sub>3</sub> instead of B<sub>2</sub>O<sub>3</sub>. Radiation shielding parameters like HVL, TVL, MFP, and Z<sub>eff</sub> were thoroughly reported for all Nd2.5, Nd5.0, and Nd7.5, which showed slight improvement when Nd<sub>2</sub>O<sub>3</sub> was added instead of B<sub>2</sub>O<sub>3</sub>.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 1","pages":"Article 103162"},"PeriodicalIF":2.6,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207247","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Pressurized Water reactor power level control: A nonlinear generalized predictive control with extended Kalman filter method 压水反应堆功率水平控制:采用扩展卡尔曼滤波法的非线性广义预测控制
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.08.016
Yuanjie Fang , Minrui Fei , Hong Qian
Reactor power level control is an effective way to achieve load tracking of Pressurized Water Reactor (PWR) in a nuclear power station. A novel Nonlinear Generalized Predictive Control with Extended Kalman Filter (NGPC + EKF) is proposed to solve the problem that discrete predictive model mismatch in noisy environment. In this paper, an NGPC controller is developed to realize the reactor load tracking, and an EKF is used to estimate reactor states and suppress noise. Finally, the control methods of PID, MPC, NGPC and NGPC + EKF are compared by two simulation experiments, load tracking experiment and step response experiment. The load tracking experiment results show that NGPC + EKF method obtains better noise suppression ability and tracking effect. In the step response experiment, the proposed NGPC + EKF scheme is also proved to have better step response performance than others.
反应堆功率水平控制是实现核电站压水堆(PWR)负荷跟踪的有效方法。为了解决噪声环境下离散预测模型不匹配的问题,提出了一种新的非线性广义预测控制与扩展卡尔曼滤波器(NGPC + EKF)。本文开发了一种 NGPC 控制器来实现电抗器负荷跟踪,并使用 EKF 来估计电抗器状态和抑制噪声。最后,通过负载跟踪实验和阶跃响应实验两种仿真实验比较了 PID、MPC、NGPC 和 NGPC + EKF 的控制方法。负载跟踪实验结果表明,NGPC + EKF 方法具有更好的噪声抑制能力和跟踪效果。在阶跃响应实验中,所提出的 NGPC + EKF 方案也被证明比其他方案具有更好的阶跃响应性能。
{"title":"Pressurized Water reactor power level control: A nonlinear generalized predictive control with extended Kalman filter method","authors":"Yuanjie Fang ,&nbsp;Minrui Fei ,&nbsp;Hong Qian","doi":"10.1016/j.net.2024.08.016","DOIUrl":"10.1016/j.net.2024.08.016","url":null,"abstract":"<div><div>Reactor power level control is an effective way to achieve load tracking of Pressurized Water Reactor (PWR) in a nuclear power station. A novel Nonlinear Generalized Predictive Control with Extended Kalman Filter (NGPC + EKF) is proposed to solve the problem that discrete predictive model mismatch in noisy environment. In this paper, an NGPC controller is developed to realize the reactor load tracking, and an EKF is used to estimate reactor states and suppress noise. Finally, the control methods of PID, MPC, NGPC and NGPC + EKF are compared by two simulation experiments, load tracking experiment and step response experiment. The load tracking experiment results show that NGPC + EKF method obtains better noise suppression ability and tracking effect. In the step response experiment, the proposed NGPC + EKF scheme is also proved to have better step response performance than others.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 1","pages":"Article 103147"},"PeriodicalIF":2.6,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207264","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Corrosive behavior of copper canisters under air and aerobic groundwater at early stages of deep geological disposal 深层地质弃置初期铜罐在空气和有氧地下水条件下的腐蚀行为
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.08.012
Junhyuk Jang , Minsoo Lee , Gha-Young Kim , Seok Yoon
Copper oxidation at low temperatures below 140 °C and its effects on corrosive behavior in aerobic groundwater are investigated to estimate the intactness of canisters at early stages of disposal. The Cu coupon surface is covered by fine particles that form thin oxide layers after 30 d of oxidation; a thin Cu2O layer of thickness <100 nm is formed after oxidation at 40 °C; after oxidation at 140 °C, the Cu2O surface changes to a CuO layer of thickness <500 nm. The thickness of the Cu surface oxidized at 90 °C is between those of the surfaces oxidized at 40 and 140 °C. All Cu coupons exhibit similar current densities ranging from 0.77 to 1.87 μA cm−2, although the corrosion potential of the Cu coupon layered with Cu2O is higher than that of the others. Long-term oxidation tests for 406 d reveal no significant changes in the Cu surface at temperatures below 90 °C, indicating no significant change in the electrochemical behavior. The results of this study suggest that the storage of canisters at temperatures below 90 °C has no significant effect on the degradation of canister performance in long-term disposal.
研究了铜在低于 140 °C 的低温下的氧化及其对好氧地下水中腐蚀行为的影响,以估计早期处置阶段滤毒罐的完好性。铜券表面被细颗粒覆盖,氧化 30 d 后形成薄氧化层;40 °C 氧化后形成厚度小于 100 nm 的薄 CuO 层;140 °C 氧化后,CuO 表面变为厚度小于 500 nm 的 CuO 层。在 90 °C 下氧化的铜表面厚度介于在 40 °C 和 140 °C 下氧化的表面厚度之间。所有的铜试样都显示出类似的电流密度,范围在 0.77 到 1.87 μA cm 之间,但层状 CuO 铜试样的腐蚀电位高于其他试样。406 d 的长期氧化测试显示,在低于 90 °C 的温度下,铜表面没有发生明显变化,这表明电化学行为没有发生重大变化。这项研究的结果表明,在低于 90 °C 的温度下储存滤毒罐对滤毒罐在长期处置过程中的性能退化没有明显影响。
{"title":"Corrosive behavior of copper canisters under air and aerobic groundwater at early stages of deep geological disposal","authors":"Junhyuk Jang ,&nbsp;Minsoo Lee ,&nbsp;Gha-Young Kim ,&nbsp;Seok Yoon","doi":"10.1016/j.net.2024.08.012","DOIUrl":"10.1016/j.net.2024.08.012","url":null,"abstract":"<div><div>Copper oxidation at low temperatures below 140 °C and its effects on corrosive behavior in aerobic groundwater are investigated to estimate the intactness of canisters at early stages of disposal. The Cu coupon surface is covered by fine particles that form thin oxide layers after 30 d of oxidation; a thin Cu<sub>2</sub>O layer of thickness &lt;100 nm is formed after oxidation at 40 °C; after oxidation at 140 °C, the Cu<sub>2</sub>O surface changes to a CuO layer of thickness &lt;500 nm. The thickness of the Cu surface oxidized at 90 °C is between those of the surfaces oxidized at 40 and 140 °C. All Cu coupons exhibit similar current densities ranging from 0.77 to 1.87 μA cm<sup>−2</sup>, although the corrosion potential of the Cu coupon layered with Cu<sub>2</sub>O is higher than that of the others. Long-term oxidation tests for 406 d reveal no significant changes in the Cu surface at temperatures below 90 °C, indicating no significant change in the electrochemical behavior. The results of this study suggest that the storage of canisters at temperatures below 90 °C has no significant effect on the degradation of canister performance in long-term disposal.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 1","pages":"Article 103143"},"PeriodicalIF":2.6,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207267","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Accounting for dependencies among performance shaping factors in SPAR-H using a regularized autoencoder and WINGS-AISM 利用正则化自动编码器和 WINGS-AISM 考虑 SPAR-H 中性能塑造因素之间的依赖关系
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.08.034
Xin Liu, Shengyuan Yan, Xiaodan Zhang
The standardized plant analysis risk human reliability analysis (SPAR-H) method is widely used for human reliability analysis to adjust the nominal human error probability (HEP) by assigning different multipliers to the performance shaping factors (PSFs). Nevertheless, SPAR-H suffers from assuming PSFs to be independent without considering any overlaps and dependencies. Therefore, this study introduces a new systematic method to analyze the relationships among the PSFs in SPAR-H qualitatively and quantitatively to obtain more reasonable HEP estimation results. The proposed method comprises three primary aspects: 1) a regularized autoencoder for the denoising and feature extraction of expert evaluation results, 2) the weighted influence non-linear gauge system-based adversarial interpretive structure modeling (WINGS-AISM) method to analyze the relationships among the PSFs and construct their causal hierarchy, and 3) a new relative weighting system to modify the PSF multipliers based on this hierarchy. The results of experiments comparing the proposed method with conventional methods highlight that our method effectively reduces the double counting of overlapping PSFs in SPAR-H, providing more reasonable and accurate HEP estimation results.
标准化工厂分析风险人体可靠性分析(SPAR-H)方法被广泛用于人体可靠性分析,通过为性能影响因素(PSF)分配不同的乘数来调整标称人体出错概率(HEP)。然而,SPAR-H 方法存在假设 PSFs 独立而不考虑任何重叠和依赖关系的问题。因此,本研究引入了一种新的系统方法,对 SPAR-H 中 PSF 之间的关系进行定性和定量分析,以获得更合理的 HEP 估算结果。所提出的方法主要包括三个方面:1) 正则化自动编码器,用于对专家评估结果进行去噪和特征提取;2) 基于加权影响非线性规整系统的对抗解释结构建模(WINGS-AISM)方法,用于分析 PSF 之间的关系并构建其因果层次结构;3) 新的相对权重系统,用于根据该层次结构修改 PSF 乘数。将所提出的方法与传统方法进行比较的实验结果表明,我们的方法有效地减少了 SPAR-H 中重叠 PSF 的重复计算,提供了更合理、更准确的 HEP 估算结果。
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引用次数: 0
Rapid determination of the migration parameters of nuclides in intact granite rock under the action of electric field 在电场作用下快速测定完整花岗岩石中核素的迁移参数
IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-01-01 DOI: 10.1016/j.net.2024.07.062
Xinyu Wang , Xiaojie Li , Yongmei Li , Longcheng Liu , Shuo Meng , Chunguang Li , Zhenzhong Liu , Xiaodong Li , Kaixuan Tan
Deep geologic disposal has been widely accepted as a strategy for long-term disposal of the high-level radioactive waste. It is principal to obtain the migration parameters of radionuclides in natural barrier, such as granite, of a high-level radioactive waste repository for safety assessment of the repository. To quickly determine the diffusion and sorption properties of nuclides in intact granite, two tracers, I and ReO4, were tested with a modified electromigration device, by imposing a constant voltage over an intact Beishan granitic rock sample. The breakthrough curves of I and ReO4 were obtained under condition of five different voltages. To interpret the electromigration experimental results with more confidence, an advection-dispersion model based on first-order adsorption kinetics was developed in this study. Data analysis of the breakthrough curves by this model suggest that the effective diffusion coefficients of I and ReO4 in intact Beishan granodiorite rock are (6.81 ± 0.53) × 10−13 m2/s and (6.45 ± 0.07) × 10−13 m2/s, respectively. While the distribution coefficient of the two ions are (9.06 ± 1.13) × 10−7 m3/kg and (9.81 ± 0.13) × 10−7 m3/kg, respectively. This indicates that I and ReO4 hardly adsorb in Beishan granodiorite rock.
深部地质处置作为一种长期处置高放射性废物的策略已被广泛接受。获取放射性核素在高放射性废物处置库天然屏障(如花岗岩)中的迁移参数是对处置库进行安全评估的关键。为了快速确定核素在完整花岗岩中的扩散和吸附特性,利用改进的电迁移装置,在完整的北山花岗岩样本上施加恒定电压,对 I 和 ReO 两种示踪剂进行了测试。在五种不同电压条件下获得了 I 和 ReO 的突破曲线。为了更有把握地解释电迁移实验结果,本研究建立了一个基于一阶吸附动力学的平流-分散模型。根据该模型对突破曲线进行的数据分析表明,I 和 ReO 在完整北山花岗闪长岩中的有效扩散系数分别为 (6.81 ± 0.53) × 10 m/s 和 (6.45 ± 0.07) × 10 m/s。而这两种离子的分布系数分别为(9.06 ± 1.13)×10 m/kg和(9.81 ± 0.13)×10 m/kg。这表明 I 和 ReO 在北山花岗闪长岩中几乎不吸附。
{"title":"Rapid determination of the migration parameters of nuclides in intact granite rock under the action of electric field","authors":"Xinyu Wang ,&nbsp;Xiaojie Li ,&nbsp;Yongmei Li ,&nbsp;Longcheng Liu ,&nbsp;Shuo Meng ,&nbsp;Chunguang Li ,&nbsp;Zhenzhong Liu ,&nbsp;Xiaodong Li ,&nbsp;Kaixuan Tan","doi":"10.1016/j.net.2024.07.062","DOIUrl":"10.1016/j.net.2024.07.062","url":null,"abstract":"<div><div>Deep geologic disposal has been widely accepted as a strategy for long-term disposal of the high-level radioactive waste. It is principal to obtain the migration parameters of radionuclides in natural barrier, such as granite, of a high-level radioactive waste repository for safety assessment of the repository. To quickly determine the diffusion and sorption properties of nuclides in intact granite, two tracers, I<sup>−</sup> and ReO<sub>4</sub><sup>−</sup>, were tested with a modified electromigration device, by imposing a constant voltage over an intact Beishan granitic rock sample. The breakthrough curves of I<sup>−</sup> and ReO<sub>4</sub><sup>−</sup> were obtained under condition of five different voltages. To interpret the electromigration experimental results with more confidence, an advection-dispersion model based on first-order adsorption kinetics was developed in this study. Data analysis of the breakthrough curves by this model suggest that the effective diffusion coefficients of I<sup>−</sup> and ReO<sub>4</sub><sup>−</sup> in intact Beishan granodiorite rock are (6.81 ± 0.53) × 10<sup>−13</sup> m<sup>2</sup>/s and (6.45 ± 0.07) × 10<sup>−13</sup> m<sup>2</sup>/s, respectively. While the distribution coefficient of the two ions are (9.06 ± 1.13) × 10<sup>−7</sup> m<sup>3</sup>/kg and (9.81 ± 0.13) × 10<sup>−7</sup> m<sup>3</sup>/kg, respectively. This indicates that I<sup>−</sup> and ReO<sub>4</sub><sup>−</sup> hardly adsorb in Beishan granodiorite rock.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 1","pages":"Article 103131"},"PeriodicalIF":2.6,"publicationDate":"2025-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141940108","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
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Nuclear Engineering and Technology
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