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Verification and Validation of the EUCLID/V2 Integrated Code’s HEFEST-FR Module EUCLID/V2集成代码HEFEST-FR模块的验证和验证
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2025-01-16 DOI: 10.1134/S0040601524700551
S. V. Tsaun, A. A. Butov, I. A. Klimonov, E. V. Moiseenko, N. A. Mosunova, V. F. Strizhov, E. V. Usov, V. I. Chukhno

For substantiating liquid metal cooled reactor plants, the EUCLID/V2 integrated code is being developed, and its verification and validation are carried out for certifying it at the Scientific and Technical Center for Nuclear and Radiation Safety (NTC NRB). One of the integrated code’s main parts is the severe accident block, which includes the SAFR module for calculating the destruction of fuel pins, fuel assemblies (FAs) and the entire core, as well as the HEFEST-FR module for calculating the melt retention and cooling down in the sodium-cooled reactor core catcher. The HEFEST-FR module implements the possibility to perform 2D simulation of the structural elements and fuel melt behavior in liquid metal cooled reactors. In accordance with the NTC NRB requirements, for the HEFEST-FR module to be used as part of the EUCLID/V2 code for analyzing the safety of fast reactors, it must be validated with the use of available experimental data; the validation shall be accompanied with an uncertainty and sensitivity analysis and assessment of the calculation result error. The article presents the results obtained from verification of the EUCLID/V2 integrated code HEFEST-FR module through solving the analytical problem of settling a stationary temperature of a homogeneous bounded cylinder uniformly heated from below with boundary conditions of the third kind and through solving the Stefan single-phase problem, as well as the results of validating the HEFEST-FR module based on the SCARABEE BF1 experiment. It is shown that the average absolute value by which the numerical calculation deviates from the analytical solution of the problem of settling a stationary temperature of a homogeneous bounded cylinder uniformly heated from below with boundary conditions of the third kind makes approximately 1.1 K. The maximum relative deviation of the results of calculations carried out using the computer program from the results of analytical solution of the Stefan problem (determination of the melt front) makes 0.46%. An assessment of the errors of modeling using the melt retention module as part of the EUCLID/V2 code (HEFEST-FR) based on the BF1 test of the SCARABEE experiment has shown that the temperature calculation error lies in the interval [‒82.3; 182.5] K, and the error of calculating the radial heat flux lies in the interval [‒55.2; 31.2] kW/m2.

为了验证液态金属冷却反应堆工厂,EUCLID/V2集成代码正在开发中,并在核与辐射安全科学技术中心(NTC NRB)进行验证和验证。集成代码的主要部分之一是严重事故模块,其中包括用于计算燃料销、燃料组件(FAs)和整个堆芯破坏的SAFR模块,以及用于计算钠冷却堆芯捕集器中的熔体保留和冷却的HEFEST-FR模块。HEFEST-FR模块实现了在液态金属冷却反应堆中对结构元件和燃料熔化行为进行二维模拟的可能性。根据NTC NRB的要求,HEFEST-FR模块作为EUCLID/V2代码的一部分用于分析快堆的安全性,必须使用可用的实验数据进行验证;验证应附有不确定度和灵敏度分析,并对计算结果误差进行评估。本文介绍了EUCLID/V2集成代码HEFEST-FR模块通过求解第三类边界条件下从下均匀加热的均匀有界圆柱体的定温解析问题和Stefan单相问题的验证结果,以及基于SCARABEE BF1实验对HEFEST-FR模块的验证结果。结果表明,在第三类边界条件下由下均匀加热的均匀有界圆柱体的定温问题的解析解与数值计算偏差的平均绝对值约为1.1 K。用计算机程序计算的结果与斯特凡问题(熔体前沿的确定)解析解的结果的最大相对偏差为0.46%。基于SCARABEE实验的BF1测试,对EUCLID/V2代码(HEFEST-FR)中熔体保持模块的建模误差进行了评估,结果表明:温度计算误差位于[-82.3;182.5] K,径向热流密度计算误差在[-55.2;31.2千瓦/ m2。
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引用次数: 0
Design Calculation and Shaping of the Hydro-Steam Turbine Flow Path with Helical Nozzles 带螺旋喷管的水轮机流道设计、计算及成形
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2025-01-16 DOI: 10.1134/S0040601524700617
B. A. Shifrin, O. O. Mil’man, A. S. Goldin, V. B. Perov

Various design versions of the rotor of hydro-steam turbines (HSTs) and their application fields are reviewed. It is shown that the design with nozzles arranged over the periphery has certain shortcomings resulting in a decreased energy efficiency, including a thermodynamically unjustified increase of pressure at the nozzle inlet, which results in excessively high velocities in the nozzle “throat,” a short period of time for which the evaporating medium resides in the nozzle divergent part, and poor aerodynamic characteristics of the peripheral area, which cause increased friction losses during the impeller rotation in a two-phase medium. A hydro-steam turbine impeller design with helical nozzle-channels is proposed. Such design has features that create prerequisites for increasing the turbine efficiency, including a longer time for which the medium resides in the nozzle, a possibility to obtain aerodynamically smooth lateral and peripheral surfaces of the impeller, and better conditions for moisture separation from the medium surrounding the rotating impeller. The conditions under which superheated water enters the impeller are considered, and statements on shaping the impeller profile part are formulated. A procedure for determining the nozzle-channel divergent part’s camber line shape is proposed proceeding from the minimal force interaction between the liquid phase fragments and channel walls. An algorithm for determining the areas of the channel divergent part’s cross sections when the velocity increase and pressure decrease patterns become monotonic in nature as the flow moves from the inlet to the outlet is developed. A solid-state 3D model of the HST four-nozzle impeller obtained in designing the turbine is presented.

综述了水蒸汽轮机转子的各种设计形式及其应用领域。结果表明,将喷嘴布置在外围的设计存在一定的缺点,导致能量效率降低,包括喷嘴入口压力的热力学不合理增加,导致喷嘴“喉部”的速度过高。蒸发介质在喷管发散部分停留时间短,外围区域气动特性差,导致叶轮在两相介质中旋转时摩擦损失增大。提出了一种带螺旋喷嘴通道的水轮机叶轮设计方案。这种设计的特点为提高涡轮效率创造了先决条件,包括介质在喷嘴内停留的时间更长,叶轮的横向和外围表面在空气动力学上光滑的可能性,以及与旋转叶轮周围介质的水分分离的更好条件。考虑了过热水进入叶轮的条件,并对叶轮外形部分的成型提出了说明。提出了一种从液相破片与流道壁面之间的最小力相互作用出发确定喷嘴-流道发散部分弧线形状的方法。提出了当气流从进口流向出口时,速度增减模式变为单调模式时,通道发散部分横截面面积的确定算法。介绍了在涡轮设计过程中获得的HST四喷嘴叶轮的三维固体模型。
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引用次数: 0
Model for the Formation of Iodine Oxide Nanoparticles within the Reactor Containment 反应堆安全壳内氧化碘纳米粒子的形成模型
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2024-11-22 DOI: 10.1134/S0040601524700496
D. S. Sinitsyn, D. A. Nazarov, N. A. Mosunova, A. A. Sorokin

A description is given of the model of formation of iodine oxide nanoparticles in the volume of the containment of a nuclear reactor during radiation-chemical reactions and clustering with subsequent formation of nanoparticles. The results of test calculations are presented. Nanoparticles of radioactive iodine oxides pose a potential hazard as a source of long-term radiation exposure to NPP personnel. They also penetrate outside the power plant through the air-ventilation system even if the enclosure remains sealed. In addition, calculations have shown that the formation of radioactive iodine oxide nanoparticles is closely related to the formation of volatile iodine compounds in the gas phase. Moreover, the intensity of formation of the latter depends significantly on air humidity. The main feature of the proposed model is the consideration of the kinetics of phenomena for processes in both the gas and aerosol phases when exposed to ionizing radiation on oxygen and water vapor in the air. The main result of the calculations is confirmation of the fundamental possibility of the formation of aerosol nanoparticles consisting of iodine oxides in a humid atmosphere even with a relatively low dose rate of radiation energy absorbed by the air. At the same time, radiolysis of water vapor has a weak effect on the size and concentration of iodine oxide nanoparticles. However, taking into account the chemical interaction of radiolysis products, in particular hydrogen radicals, induced by water vapor radiolysis, significantly affects the formation of volatile iodine compounds with hydrogen: HI and HOI. The obtained results, despite their preliminary nature, are important since they indicate the inevitability of the formation of suspended nanoparticles of iodine oxides and hydrogen iodide in the atmosphere of the reactor premises in the event of emergency situations with the release of radionuclides beyond the first circuit of the reactor. Therefore, this mechanism must be taken into account when developing models of the formation and behavior of fission product aerosols at NPPs.

介绍了核反应堆安全壳容积内氧化碘纳米粒子在辐射-化学反应过程中形成的模型,以及随后形成纳米粒子的聚类。本文介绍了试验计算的结果。放射性碘氧化物纳米粒子是核电厂人员长期暴露于辐射的潜在危险源。即使外壳保持密封,它们也会通过空气通风系统渗透到发电厂外部。此外,计算表明,放射性碘氧化物纳米粒子的形成与气相中挥发性碘化合物的形成密切相关。而且,后者的形成强度在很大程度上取决于空气湿度。所提出模型的主要特点是考虑了在电离辐射照射空气中的氧气和水蒸气时,气相和气溶胶相过程的动力学现象。计算的主要结果证实,在潮湿的大气中,即使空气吸收的辐射能量剂量率相对较低,也有可能形成由碘氧化物组成的气溶胶纳米粒子。同时,水蒸气的辐射分解对氧化碘纳米粒子的大小和浓度影响微弱。然而,考虑到水蒸气辐射分解诱发的辐射分解产物(尤其是氢自由基)的化学作用,会显著影响与氢形成的挥发性碘化合物:HI 和 HOI。所获得的结果尽管是初步的,但却非常重要,因为这些结果表明,在放射性核素释放到反应堆一回路以外的紧急情况下,不可避免地会在反应堆厂房的大气中形成碘氧化物和碘化氢的悬浮纳米粒子。因此,在开发核电厂裂变产物气溶胶的形成和行为模型时,必须考虑到这一机制。
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引用次数: 0
Mechanisms of Metal Degradation in Equipment and Pipelines of Turbo Plants of Nuclear Power Plant Units: Classification and Identification 核电站机组涡轮装置设备和管道中的金属降解机理:分类和识别
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2024-11-22 DOI: 10.1134/S0040601524700502
G. V. Tomarov, V. N. Lovchev, A. F. Gromov, A. A. Shipkov

Operation of nuclear power plant units is accompanied by the development of various metal degradation mechanisms (MDM) under the influence of the working environment. Prevention of damage and elimination of sudden destruction of equipment and pipelines (E&P) at operating nuclear power plants depends on the timely identification of those elements and units in which the preconditions for the manifestation and intensification of metal degradation mechanisms are created. In this case, the search for the causes of damage to pipeline lines and equipment parts should be based on the determination of the dominant MDM. The effectiveness of the technical measures being developed to restore and prevent similar damage in the future depends on the correct solution to these problems. Despite significant experience and accumulated statistical data on damage to the metal of the working contours of nuclear power plant units, the establishment of identification features and the detection of dominant MDM in the operating conditions of turbine installations of nuclear power plant units remain highly relevant. This is confirmed by the existing differences in approaches to the classification of MDM and the lack of a clear methodology for their identification when detecting defects and analyzing cases of damage to pipeline elements and equipment. Due to the complexity of the physical and chemical processes and patterns of MDM, their deep and fairly large-scale study is required; therefore, as a rule, the study of a specific MDM is carried out by separate specialized scientific organizations and institutes. This circumstance makes it difficult to form a unified approach to their systematization and classification in order to obtain a complete picture of the dominant mechanisms of damage to E&P turbine installations of nuclear power plant units. At the same time, the achievements of recent years in this area make it possible to formulate more advanced criteria and recommendations for classification and identification of MDM, which are advisable to use in practice, including in the development of industry guidance documentation on this topic.

在工作环境的影响下,核电站机组的运行伴随着各种金属降解机制(MDM)的发展。在运行中的核电站,防止设备和管道(E&P)损坏和消除突然破坏取决于及时识别那些为金属退化机制的显现和加剧创造先决条件的部件和装置。在这种情况下,寻找管线和设备部件损坏的原因应以确定主要的 MDM 为基础。为恢复和防止今后发生类似损坏而制定的技术措施是否有效,取决于能否正确解决这些问题。尽管在核电厂机组工作轮廓金属损坏方面积累了大量经验和统计数据,但在核电厂机组涡轮机装置运行条件下建立识别特征和检测主要 MDM 仍然非常重要。现有的 MDM 分类方法存在差异,而且在检测缺陷和分析管道元件和设备损坏情况时缺乏明确的 MDM 识别方法,这些都证实了这一点。由于 MDM 的物理和化学过程及模式非常复杂,需要对其进行深入和相当大规模的研究;因此,通常情况下,对特定 MDM 的研究是由单独的专业科学组织和机构进行的。在这种情况下,很难形成统一的系统化和分类方法,以全面了解核电站机组 E&P 涡轮机装置的主要损坏机制。与此同时,近年来在该领域取得的成就使得制定更先进的标准和建议成为可能,这些标准和建议适用于MDM的分类和识别,包括在制定有关该主题的行业指导文件时。
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引用次数: 0
Results of a Computational and Experimental Study of Wet Steam Flow through the Shroud Seal of a Stage with Long Blades 湿蒸汽流经长叶片平台护罩密封的计算和实验研究结果
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2024-11-22 DOI: 10.1134/S0040601524700484
A. V. Moskalenko, A. M. Tyukhtyaev, A. A. Ivanovskii, S. N. Kozachuk, E. Yu. Semakina, V. A. Chernikov

More accurate evaluation of the energy loss as a consequence of fluid leaks through the clearances between the rotor and stator of turbine machines is a topical problem, which can be solved through more accurately assessing the shroud clearance area by applying a leak flow normal cross section. The article presents the results obtained from measurements of gas dynamic parameters in the low-pressure cylinder (LPC) of a high-capacity steam turbine in the last stage tip zone with improved active protection of the rotor blades against erosion. Flow traversing results have confirmed that, near the stage top at the outlet from the radial clearance between the blade row cylindrical shroud and fins of a three-chamber ledgeless seal (i.e., with the same clearances), the wet steam (two-phase medium) leak direction differs from the axial direction in the turbine and is mainly governed by the working medium swirling in the diaphragm nozzle vane channels and mutually opposite influence of rotation of the shroud and of the main flow from the running cascade channels. The leak flowrate is evaluated by using the flow parameters at the seal outlet and the gas dynamics equation with taking into account the medium compressibility. In estimating the two-phase medium flowrate, the following corrections were calculated: the flowrate coefficient increment caused by the flow dispersity, a correction characterizing the influence of initial wetness and the phase slip ratio. Taking into account the coefficients and corrections is conductive to more accurate description of flow through the seals. The wet steam leak flowrate assessment is approximate in nature because it was carried out proceeding from a simplified physical model describing the two-phase medium outflow. With the jet flowing out at an angle of 35° with respect to the circumferential velocity positive direction, the leak flowrate from the shroud seal at the nominal load expressed in fractions of the wet steam medium flowrate through the LPC last state amounted to (overline {{{G}_{{{text{shr}}}}}} ) = 0.017. The obtained study results are used in designing the wet steam stages of the LPCs of advanced turbines for thermal and nuclear power plants.

更准确地评估汽轮机转子和定子之间的间隙泄漏造成的能量损失是一个热点问题,可以通过采用泄漏流量法线截面更准确地评估护罩间隙面积来解决。文章介绍了对一台大容量汽轮机末级叶尖区低压缸(LPC)内气体动态参数的测量结果,并改进了转子叶片的主动防侵蚀保护。流动穿越结果证实,在叶片排圆柱形护罩和三腔无导叶密封翅片之间的径向间隙出口处的级顶附近(即具有相同间隙),湿蒸汽(两相介质)的泄漏方向与汽轮机内的轴向方向不同,主要受隔膜喷嘴叶片通道中的工作介质漩涡以及护罩旋转和来自运行级联通道的主流动的相互相反的影响。通过使用密封出口处的流动参数和考虑到介质可压缩性的气体动力学方程来评估泄漏流量。在估算两相介质流速时,计算了以下修正值:由流动分散性引起的流速系数增量、初始湿度影响修正值和相滑移比。考虑到这些系数和修正有助于更准确地描述流经密封件的情况。湿蒸汽泄漏流量评估是近似性质的,因为它是根据描述两相介质流出的简化物理模型进行的。当射流与圆周速度正方向成 35° 角流出时,在额定负荷下,以通过 LPC 的湿蒸汽介质流量的分数表示的护罩密封泄漏流量为 (overline {{G}_{{text{shr}}}}}} ) = 0.017。获得的研究结果可用于设计火电厂和核电厂先进汽轮机 LPC 的湿蒸汽级。
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引用次数: 0
Recycling of Solid Products of Municipal Waste Pyrolysis with Production of Energy Fuel 回收城市垃圾热解固体产品并生产能源燃料
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2024-11-22 DOI: 10.1134/S0040601524700460
R. V. Kulumbegov, L. M. Delitsyn, O. S. Popel’, A. I. Karpov, N. Yu. Svechnikova, Yu. V. Ryabov

The purpose of the study was development of a technology for the extraction of a carbon-rich concentrate suitable for use as an energy fuel from solid products of municipal waste pyrolysis (SPMWP). To do this, the effect of reagents and different flotation conditions on the yield and quality of the carbon-rich concentrate was investigated. The results are presented of the experimental study into the features of the SPMWP flotation process. A relationship has been established between the SPMWP fraction size, the yield of carbon-rich concentrate, and its quality. The fact has been demonstrated that SPMWP flotation characteristics can be improved by ultrasonic dispersion of flotation agents in water and production of concentrates containing, depending on the size distribution of SPMWP particles, from 60 to 67% of combustible matter. Thermogravimetry and differential scanning calorimetry methods have revealed that the combustible matter of the concentrate consists of 65% carbon and 35% volatile carbon-containing compounds. According to the results of X-ray phase analysis, the main water-soluble salts of SPMWP are chlorides of potassium, sodium, and calcium sulfate. As to its heating value (q = 18.4 MJ/kg), the obtained combined concentrate is comparable to coal and can be considered as a renewable energy source since, according to forecasts, the annual increase in the amount of municipal solid wastes (MSWs) will be from 1 to 7%. A schematic diagram of material flows for processing 100 t of SPMWP has been constructed on the basis on the results of performed studies. An additional economic effect can be obtained by using hydroseparation at the stage of municipal waste sorting to separate crushed glass, as a result of which large SPMWP particles may be sent to flotation after grinding.

这项研究的目的是开发一种技术,从城市垃圾热解固体产品(SPMWP)中提取适合用作能源燃料的富碳精矿。为此,研究了试剂和不同浮选条件对富碳精矿产量和质量的影响。本文介绍了有关 SPMWP 浮选过程特点的实验研究结果。在 SPMWP 分馏粒度、富碳精矿产量及其质量之间建立了关系。事实证明,通过超声波在水中分散浮选剂,可以改善 SPMWP 的浮选特性,根据 SPMWP 颗粒的大小分布,生产出的精矿含有 60% 至 67% 的可燃物质。热重法和差示扫描量热法显示,浓缩物中的可燃物质由 65% 的碳和 35% 的挥发性含碳化合物组成。根据 X 射线相分析结果,SPMWP 的主要水溶性盐类是钾、钠和硫酸钙的氯化物。就其热值(q = 18.4 兆焦/千克)而言,获得的混合浓缩物与煤炭相当,可被视为一种可再生能源,因为根据预测,城市固体废弃物(MSW)的数量每年将增加 1%至 7%。根据已进行的研究结果,绘制了处理 100 吨 SPMWP 的物料流示意图。在城市垃圾分拣阶段使用水力分离技术分离碎玻璃,可以获得额外的经济效益。
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引用次数: 0
Results of Application of Ammonia-Ethanolamine Water Chemistry in the Secondary Circuit of Power Units with a VVER-1200 Reactor 在配备 VVER-1200 反应堆的发电机组二次回路中应用氨乙醇胺水化学的结果
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2024-11-22 DOI: 10.1134/S0040601524700459
V. G. Kritskii, A. V. Gavrilov, N. A. Prokhorov, E. A. Motkova, V. V. Bykova, A. L. Bogdanov

The potential scope of application of the ammonia-ethanolamine water chemistry in the secondary circuit of a nuclear power plant (NPP) with a VVER-1200 reactor during pilot commercial operation and normal operation is examined. The water chemistry conditions during pilot commercial operation is controlled by an individual scenario for preparing the power unit for commissioning. An initial high content of iron in the steam generator feedwater is observed at all nuclear power plants. Dosing corrective reagents (such as ammonia, hydrazine, and ethanolamine) at NPP power units VVER-1200 reactors maintains their recommended concentrations and the pH range in the feedwater and blowdown water of the steam generators. A comparative analysis of the water chemistries at NPPs with VVER-1000 and VVER-1200 reactors has revealed no considerable differences between corresponding water chemistries as to the regularities of mass transfer of corrosion products, previously identified dependences of iron concentrations on pH, and their changes with time. A new factor is a sharp decrease in the iron concentrations in the steam generator feedwater (below 1 μg/dm3) at рН25 above 9.45 and in an electrical conductivity of the H-cation treated feedwater sample below 0.3 μS/cm. With the selected water-chemistry and the temperature and heat flux maintained at the VVER-reactor, the factors limiting formation of deposits on the heat-transfer tubes of the steam generator are the concentration of iron products and pH of the working fluid. Data on the fouling of heat-transfer tubes of the steam generator suggest that a stable water chemistry in the secondary circuit allows us to schedule much longer washing intervals for the VVER-1200 steam generators in comparison with those for other VVER-reactors. A further reduction in the mass transfer of corrosion products can be attained by replacing pearlitic steels with low-alloy steels having a chromium content of 1.5 to 2.5% for the manufacture of steam pipelines and individual sections of the feedwater path downstream of the deaerator. The results of operation comply with the main conclusions that were made in developing a model for prediction of corrosion and mass transfer in the secondary circuit of a VVER-reactor and corroborate the feasibility of its application in the design and analysis of water chemistry data during operation of the power unit.

研究了在商业试运行和正常运行期间,氨-乙醇胺水化学在配有 VVER-1200 反应堆的核电站(NPP)二次回路中的潜在应用范围。商业试运行期间的水化学条件由机组调试准备的个别方案控制。所有核电厂的蒸汽发生器给水中最初都会出现较高的铁含量。在核电厂 VVER-1200 反应堆机组中投放的纠正试剂(如氨、联氨和乙醇胺)可保持其推荐浓度以及蒸汽发生器给水和排污水中的 pH 值范围。对装有 VVER-1000 和 VVER-1200 反应堆的国家核电厂的水化学成分进行比较分析后发现,相应的水化学成分在腐蚀产物传质的规律性、以前确定的铁浓度对 pH 值的依赖性及其随时间的变化方面没有显著差异。一个新的因素是,当 рН25 高于 9.45 时,蒸汽发生器给水中的铁浓度急剧下降(低于 1 μg/dm3),而且经过 H 阳离子处理的给水样品的电导率低于 0.3 μS/cm。在 VVER 反应堆中保持选定的水化学性质、温度和热流量的情况下,限制蒸汽发生器传热管上沉积物形成的因素是铁产品的浓度和工作流体的 pH 值。有关蒸汽发生器传热管污垢的数据表明,二次回路中稳定的水化学特性使我们能够为 VVER-1200 型蒸汽发生器安排比其他 VVER 反应堆更长的清洗间隔。在制造蒸汽管道和除氧器下游给水路径的个别部分时,用铬含量为 1.5%至 2.5%的低合金钢代替珠光体钢,可以进一步减少腐蚀产物的传质。运行结果符合在开发 VVER 反应堆二次回路腐蚀和传质预测模型时得出的主要结论,并证实了将其应用于设计和分析动力装置运行期间水化学数据的可行性。
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引用次数: 0
Renewable Energy Sources: Contribution to Decarbonization of Russian Energy 可再生能源:对俄罗斯能源去碳化的贡献
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2024-11-22 DOI: 10.1134/S0040601524700423
M. A. Arapov, O. S. Popel, A. B. Tarasenko, S. P. Filippov

The role of solar and wind energy in the current processes of decarbonization of the Russian electric power industry is considered. The issues of the formation and further development of renewable energy, which can make up a significant share of the country’s energy balance thanks to the legislation introduced to stimulate its implementation, are discussed. The rates of commissioning of renewable energy-generation facilities (hereinafter referred to as renewable generation) by region are analyzed, and trends towards reducing capital expenditures in the construction of both solar and wind grid power plants are assessed. An important feature of renewable generation is its stochastic nature, which can cause certain problems when transmitting energy to electrical networks and requires the adoption of special measures to increase the share of renewable energy sources in electrical networks and additional costs to ensure it. Abroad, where a significantly greater path has been taken in the development of the industry, the introduction of grid energy-storage devices, methods for converting surplus energy generated by renewable sources into various useful products and other measures are widely discussed as such measures. In Russia, the overall share of RES in the energy balance is still quite small, but it has already reached threshold values in some regions, at which several pilot projects are being implemented using electric energy-storage devices in both network and autonomous systems. The article provides estimates of the contribution of grid solar and wind power plants to replacing energy from traditional sources and reducing greenhouse gas emissions, and examines the problems and prospects for further development of the industry, primarily from the point of view of the need to reconstruct the grid infrastructure.

本文探讨了太阳能和风能在当前俄罗斯电力行业去碳化进程中的作用。讨论了可再生能源的形成和进一步发展问题,由于出台了促进可再生能源发展的法律,可再生能源在国家能源平衡中占据了重要份额。分析了各地区可再生能源发电设施(以下简称可再生能源发电)的投产率,并评估了太阳能和风能并网发电厂建设中减少资本支出的趋势。可再生能源发电的一个重要特点是其随机性,这可能会在向电网传输能源时造成一定的问题,因此需要采取特别措施来增加可再生能源在电网中的比例,并增加成本以确保这一点。在国外,可再生能源产业的发展已经有了长足的进步,人们广泛讨论的措施包括引进电网储能装置、将可再生能源产生的剩余能源转化为各种有用产品的方法以及其他措施。在俄罗斯,可再生能源在能源平衡中所占的总体比例仍然很小,但在一些地区已经达到了临界值,在这些地区正在实施一些试点项目,在电网和自治系统中使用电力储能装置。文章估算了电网太阳能和风能发电厂在替代传统能源和减少温室气体排放方面的贡献,并主要从重建电网基础设施的必要性角度,探讨了该行业进一步发展的问题和前景。
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引用次数: 0
Erratum to: Directions for Increasing Thermal Efficiency of an NPP with PWR 勘误:提高使用压水堆的核电厂热效率的方向
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2024-11-22 DOI: 10.1134/S0040601524110016
Yu. G. Sukhorukov, Yu. V. Smolkin, G. I. Kazarov, E. N. Kulakov, E. P. Kondurov, A. V. Popov
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引用次数: 0
Approximation Formula for Calculating the Heat Capacity of Liquid Lead from the Melting Point to the Boiling Point 计算液态铅从熔点到沸点的热容量的近似公式
IF 0.9 Q4 ENERGY & FUELS Pub Date : 2024-11-22 DOI: 10.1134/S0040601524700514
E. V. Usov, N. A. Mosunova, S. I. Lezhnin

Abstract—An analysis of the relationships for calculating the thermal properties of liquid lead (hereinafter referred to as lead) was carried out, and the method for determining its heat capacity over a wide range of temperatures, including at high values, was chosen. This is especially important for numerical studies to justify the safety of designed reactor installations with liquid metal coolants, such as BREST-OD-300 and BR-1200. Measuring the properties of lead at temperatures close to the boiling point is often difficult due to the lack of reliable methods and materials that can withstand temperatures above 2273 K. At present, theoretical approaches to calculating the properties of simple liquids based on phonon theory are being actively developed. Such approaches can be used to derive semiempirical relations for the heat capacity of liquid lead that would allow physically correct extrapolation of the data to the high-temperature region. In this regard, the aim of this work is to obtain a relationship for calculating the heat capacity of liquid lead from its melting point to its boiling point based on modern theoretical approaches. To achieve the set goal, the following tasks were solved. Firstly, an analysis of the works of various authors was carried out and empirical formulas were selected that make it possible to reliably calculate the heat capacity at a constant volume cv (isochoric heat capacity) for a lead coolant from the melting point to 1500 K. Secondly, based on them, using phonon theory, an approximating formula was constructed, thanks to which it is possible to physically correctly extrapolate the properties of lead to the boiling point (2022 K).

摘要--对计算液态铅(以下简称 "铅")热特性的关系进行了分析,并选择了在包括高值在内的广泛温度范围内确定其热容量的方法。这对于数值研究尤为重要,因为数值研究可以证明使用液态金属冷却剂(如 BREST-OD-300 和 BR-1200)设计的反应堆装置的安全性。由于缺乏可靠的方法和可承受 2273 K 以上温度的材料,在接近沸点的温度下测量铅的特性 通常比较困难。这些方法可用于推导液态铅热容量的半经验关系,从而将数据正确推断到高温区域。为此,这项工作的目的是根据现代理论方法,获得液态铅从熔点到沸点的热容量计算关系。为了实现既定目标,我们解决了以下任务。首先,对不同作者的著作进行了分析,选出了经验公式,可以可靠地计算出铅冷却剂在恒定体积 cv 下从熔点到 1500 K 的热容量(等时热容量);其次,在此基础上,利用声子理论构建了一个近似公式,从而可以从物理角度正确推断出铅到沸点(2022 K)的特性。
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引用次数: 0
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Thermal Engineering
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