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Assessing the durability of nuclear plant elements under high‑frequency broadband loading 评估核电站元件在高频宽带载荷下的耐久性
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2024-01-05 DOI: 10.1007/s10512-023-01025-z
O. V. Goryunov, S. V. Evropin, S. V. Slovtsov

Due to the current standards providing failing to account for the entire spectrum of loading amplitudes under broadband vibration exposure, durability can be significantly overestimated. The consideration of several harmonics in isolation is insufficient to evaluate actual maximum values and loading amplitudes, which are determined by integrating the spectral density depending on the interval width ∆f. Based on the damageability equivalence principle, a method for reducing broadband exposure to a harmonic equivalent is proposed taking into account the slope of the fatigue curve in the area with the number of cycles exceeding 107. A comparison of equivalent loading parameters obtained using the proposed approach with a shadow-method schematization demonstrated satisfactory results.

由于现行标准未能考虑到宽带振动暴露下的整个负载振幅频谱,因此可能会大大高估耐久性。孤立地考虑几次谐波不足以评估实际最大值和负载振幅,而实际最大值和负载振幅是根据区间宽度 ∆f 对频谱密度进行积分后确定的。根据损伤等效原理,考虑到疲劳曲线在循环次数超过 107 次的区域的斜率,提出了一种减少宽带接触谐波等效的方法。对使用所提方法获得的等效加载参数与阴影法示意图进行了比较,结果令人满意。
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引用次数: 0
Corrosion tests of triuran disilicide fuel pellets 三聚二硅燃料颗粒的腐蚀试验
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2024-01-05 DOI: 10.1007/s10512-023-01026-y
L. A. Karpyuk, V. I. Kuznetsov, V. V. Novikov, E. N. Mikheev, A. V. Fedotov, A. V. Lysikov, R. B. Sivov, N. M. Rysev, O. A. Bakhteev, M. A. Lutkov

The study aims to determine the corrosion stability of triuranium disilicide pellets under the conditions similar to small-nuclear plant (SNPP) modes. For this, corrosion tests were carried out in comparison with uranium dioxide in zirconium mini-autoclaves with distilled (deionized) water at a pressure of 16.2 MPa using a Nabertherm muffle furnace (Germany) at a temperature of 331 ± 3 °C and isothermal exposure of 4 and 10 h. The temperature of isothermal sections was calibrated and controlled using a rhenium-tungsten thermocouple located near the mini-autoclaves. After a 4h exposure, the surface of the triuranium disilicide sample was slightly oxidized without destruction. After 10 h, it was oxidized with a slight detachment of fine particles. The mass gain of the sample together with exfoliated fine particles comprised 0.5% (25 mg). No uranium dioxide was detected on the standard fuel pellet under these oxidation modes.

这项研究旨在确定二硅化三铀颗粒在类似小型核电厂(SNPP)模式条件下的腐蚀稳定性。为此,使用纳博热马弗炉(德国)在压力为 16.2 兆帕斯卡、温度为 331 ± 3 °C、等温暴露时间为 4 小时和 10 小时的条件下,在装有蒸馏水(去离子水)的锆迷你高压釜中与二氧化铀进行了腐蚀对比试验。等温切片的温度由微型高压灭菌器附近的铼钨热电偶校准和控制。暴露 4 小时后,二硅化三钛样品表面轻微氧化,但未被破坏。10 小时后,样品被氧化,细小颗粒轻微脱落。样品质量的增加与细颗粒的剥离合计为 0.5%(25 毫克)。在这些氧化模式下,没有在标准燃料颗粒上检测到二氧化铀。
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引用次数: 0
Flow formation features at the inlet to the fuel catridge of a ritm snpp reactor Ritm Snpp 反应堆燃料导管入口处的流动形成特征
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2023-12-22 DOI: 10.1007/s10512-023-01023-1
S. Dmitriev, T. D. Demkina, A. Dobrov, D. Doronkov, D. S. Doronkova, D. D. Kuritsyn, M. Legchanov, A. Pronin, A. Ryazanov, D. Solntsev, D. L. Shipov
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引用次数: 0
Release of radioactive cesium to the environment during standard npp operations 标准核电站运行期间向环境释放放射性铯的情况
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2023-12-21 DOI: 10.1007/s10512-023-01034-y
D. Desyatov, A. Ekidin, S. G. Goliboroda
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引用次数: 0
Development of approaches to regulatory safety in industrial water-electrolysis production of hydrogen at NPPs 制定核电厂工业水电解制氢的安全监管方法
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2023-12-21 DOI: 10.1007/s10512-023-01035-x
I. A. Kirillov, N. L. Kharitonova, V. A. Simonenko, V. M. Kryukov
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引用次数: 0
Scientific and practical aspects of a radiation inspection for a decommissioned NPP unit 退役核电厂机组辐射检查的科学和实践问题
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2023-12-21 DOI: 10.1007/s10512-023-01032-0
A. S. Gryaznov, E. A. Ivanov, A. S. Korotkov, S. S. Selkin, L. E. Sukhikh, D. A. Sharov
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引用次数: 0
Analysis of fuel cycle scenarios for a two-unit SCWR NPP 两台重水反应堆核反应堆燃料循环方案分析
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2023-12-21 DOI: 10.1007/s10512-023-01022-2
M. Kormilitsyn, L. A. Kormilitsyna, Ya. A. Kotov, V. Nevinitsa, S. B. Pustovalov, A. A. Sedov, S. S. Simonov, S. Subbotin, P. Fomichenko
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引用次数: 0
Uncertainty Assessment and Sensitivity Analysis in the Problems of Nuclide Kinetic Modeling Using the Sun Module of BPSD Software 基于BPSD软件Sun模块的核素动力学建模问题的不确定性评估与灵敏度分析
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2023-10-20 DOI: 10.1007/s10512-023-01019-x
O. I. Chertovskikh, A. A. Belov, O. N. Andrianova

Features and capabilities of the SUN BPSD module for assessing the error in fuel burnup calculations due to the uncertainty of nuclear data and reactor plant process parameters, as well as fuel irradiation conditions, are described. Using the SUN module, two different methods for estimating the uncertainty of irradiated fuel characteristics were implemented. The post-reactor studies of fuel rods irradiated in a BN-350 reactor with mixed uranium-plutonium oxide fuel were considered as a demonstration calculation test using the SUN module.

描述了SUN BPSD模块的特点和功能,用于评估由于核数据和反应堆工厂过程参数以及燃料辐照条件的不确定性而导致的燃料燃耗计算误差。利用太阳模块,实现了两种不同的方法来估计辐照燃料特性的不确定度。在BN-350反应堆中使用混合铀-钚氧化物燃料辐照燃料棒的堆后研究被认为是使用SUN模块进行的示范计算试验。
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引用次数: 0
Study of Effects Caused by the Neutron Value Function on Kinetic Functionals Using the MCU Software 利用单片机软件研究中子值函数对动力学泛函的影响
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2023-10-20 DOI: 10.1007/s10512-023-01007-1
D. M. Arkhangelsky, D. S. Oleynik

The results of calculating the βeff effective fraction of delayed neutrons and the Λ lifetime of prompt neutrons, both when taking into account and excluding the value function, are presented. The analysis, concerning the effects of accounting for the neutron value function at various degrees of its expansion, as well as depending on the physical and geometric parameters of the system, is conducted. The calculations were performed for twelve experiments from the ICSBEP collection. The analysis of the results states the necessity of accounting for the value function in small systems with a reflector and a large number of neutrons. No accounting for the value function is required for estimating the kinetic functionals in systems that are close to infinite.

给出了考虑值函数和不考虑值函数时,延迟中子βeff有效分数和提示中子Λ寿命的计算结果。分析了中子值函数在膨胀的不同程度上的影响,以及系统的物理和几何参数的影响。对ICSBEP收集的12个实验进行了计算。对结果的分析表明,在具有反射器和大量中子的小型系统中,必须考虑值函数。在接近无穷大的系统中,估计动力学泛函不需要考虑值函数。
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引用次数: 0
Effects of Tectonic Faults on the Safety of a Geological Repository at the Yeniseysky Site 构造断裂对叶尼塞斯基场址地质储存库安全的影响
IF 0.5 4区 工程技术 Q3 Energy Pub Date : 2023-10-20 DOI: 10.1007/s10512-023-01011-5
V. I. Malkovsky

The paper analyzes the effect of tectonic activity on the safety of the geological repository at the Yeniseisky radioactive waste (RW) repository (Nizhnekansky massif, Krasnoyarsk Krai) in the event of the formation of faults in the host rocks following the loading of wastes into the repository. A 3D model of the radioactive contamination transfer from the repository by groundwater is considered, taking into account the inhomogeneous permeability of rocks. The orientation and location of the faults are set based on the modeled stress-strain state of the rocks in this area, as well as data obtained from field and spatial surveys on contemporary tectonic activity in the considered area. Submeridional faults were demonstrated to have no significant effect on the spread rate of the radioactive contamination. However, the activation of the most probable latitudinal fault may lead to the rapid movement of contaminated groundwater in the fault zone towards the Yenisei. The efficacy of plugging various areas in the sublatitudinal fault zone to reduce the migration rate of contaminating radionuclides is considered.

本文分析了在叶尼泽斯基放射性废物(RW)储存库(克拉斯诺亚尔斯克边疆区尼日涅坎斯基地块)装载废物进入储存库后,在宿主岩中形成断层的情况下,构造活动对储存库安全性的影响。考虑到岩石渗透性的不均匀性,建立了放射性污染通过地下水从储存库转移的三维模型。断层的方位和位置是根据模拟的本区岩石应力-应变状态,以及本区当代构造活动的野外和空间调查数据确定的。潜水断层对放射性污染的扩散速率没有显著影响。然而,最可能的纬向断层的激活可能导致断裂带中受污染的地下水迅速向叶尼塞移动。考虑了对亚垂直断裂带各区域进行封堵以降低污染核素迁移速率的效果。
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引用次数: 0
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