Power Plant Structures Research Articles

A simplified method for probabilistic seismic risk evaluation of nuclear containment structure

Damage performance and annual frequency of exceedance are the focus of probabilistic safety assessment for nuclear power plant structures. However, conventional displacement-based global damage index and classical method for calculating the annual frequency of exceedance of the nuclear containment structure suffers from some limitations and deficiencies. Based on seismic energy balance concept, an innovative energy-based global damage index is proposed in this study. Based on truncated incremental dynamic analysis (TIDA) technique, a simplified method for calculating the annual frequency of exceedance of the nuclear containment structure is developed. To verify the effectiveness of the proposed global damage index and the proposed simplified method for calculating the annual frequency of exceedance, the proposed energy-based global damage index is compared to roof displacement based damage index. The annual frequency of exceedance calculated by the simplified method is compared to a more accurate but computationally demanding approach (full incremental dynamic analysis technique based approach). Finally, statistics of the annual frequency of exceedance are estimated by the parametric bootstrap method. Results indicated that energy-based global damage index proposed in this study can well reflect the global deformation characteristics of the nuclear containment structure. The variability of the proposed global damage index is smaller than that of roof displacement based global damage index, which indicates the superiority of the proposed global damage index. In general, the proposed simplified method for calculating the annual frequency of exceedance can provide good estimation of the annual frequency of exceedance of the nuclear containment structure corresponding to different damage levels. With regard to the statistics of the annual frequency of exceedance, the mean value of the annual frequency of exceedance is not sensitive to the number of bootstrap samples, while the coefficient of variation of the annual frequency of exceedance is sensitive to the number of bootstrap samples. When the number of bootstrap samples is larger than 300, the statistics of the annual frequency of exceedance tend to be stable.

Simplified design procedure for nonconventional multiple tuned mass damper and experimental validation

SummaryA simplified design procedure, for nonconventional multiple tuned mass damper (TMD) (NC‐MTMD) system, was proposed. This system entails targeted tuning of each TMD by considering several mechanical factors (e.g., seismic excitation, TMD mass, and location). Subsequently, all TMDs are tuned to their corresponding modes by a group of semi‐empirical design formulae based on previous theoretical studies on MTMD systems, in the tuning phase. The procedure was then calibrated by numerical optimization results of an actual existing thermal power plant structure and validated in both comparative numerical study and a shaking table test. The experimental model was designed based on the thermal power plant structure configuration. Springs and eddy current dampers were adopted to model the resistance and energy dissipation of TMDs. A numerical comparative study was carried out between a traditional design method and the proposed design scheme. Six representative NC‐MTMD mass cases were investigated in the shaking table test to study the robustness of the method. The seismic mitigation efficiency was evaluated by comparison study on frequency, peak, and root mean square responses. The NC‐MTMD design was proved to be effective to help reduce seismic responses of the structure.

Geological, Geotechnical and Geophysical Aspects of Zafarana Wind Farms Sites and Their Expansion at Gabel El Zeit Sites Egypt

The growing need for sustainable power generation has led to increasing number of power plants, of fossil-fuel type and of non-conventional type. The foundation types of wind turbine towers in power plant structures are mainly depend on the geotechnical and structural considerations and other geological and geophysical considerations. The safety and economic conditions also play a vital role in the design of foundations. Such foundations must effectively be designed taken into consideration large overturning moments and dynamic loading due to extreme wind and earthquakes. The present research is focused on studying the geotechnical, geological and geophysical aspects and characterizes of soils in Zafarana Wind Farms sites and their expansion at Gabel El Zeit sites on the Suez Gulf of Egypt. The study first address and study the geological aspects of both sites Zafarana Wind Farms sites and Gabel El Zeit sites. Secondly, the geotechnical and geophysical characteristics are studied based on establishing data base from 698 borings and 8 seismic refraction profiles across Zafarana wind Farm sites and 10 borings and 2 seismic refraction profiles at Gabel El Zeit site. The geotechnical testing and geophysical profiles were compiled to determine the variation of the soil profile as well as the characteristics of the soil layers within the study sites. The results showed construction of 8 representative boring logs at Zafarana Wind Farm sites and 2 representative boring logs Gabel El Zeit sites to represent the characteristics of the soil layers and site statgerphy. Also, the study shows the result of compression wave velocity and shear wave velocity across both sites and within the studied soil layers up to 30 m. All these results from this research will help to study the foundation and the structure of wind turbine tower, where these types of tall structures are similar to chimney structures in design and other engineering considerations.

Deep Reinforcement Learning for Scenario-Based Robust Economic Dispatch Strategy in Internet of Energy

Currently, the integration of distributed energy generators through virtual power plants in the Internet of Energy is a mainstream method. The complex structure of virtual power plants and the characteristics of distributed energy make it difficult to solve the economic dispatch problems of virtual power plants. In addition, the load of a virtual power plant is unstable and uncertain and thus requires a robust economic dispatch strategy. Because the selection of the set of uncertain conditions is conservative, the traditional robust economic dispatch strategies cannot effectively reduce the cost of virtual power plants. In addition, the traditional methods for solving robust strategies cannot directly solve nonlinear and nonconvex problems. In this article, we propose a scenario-based robust economic dispatch strategy for virtual power plants, aiming to reduce the operational costs of virtual power plants. First, to reduce the conservatism of the strategy, scenario-based data augmentation is adopted for data generation. Through a generative adversarial network, a large amount of scene data are generated to extend the set of uncertain conditions. The scene data cannot only reduce the conservatism but also can be used in the determination of robust strategies. Second, deep reinforcement learning is adopted for historical data training, directly solving nonlinear and nonconvex problems to obtain a robust economic dispatch strategy. As experiments show, with the accurate generation of scene data, the proposed economic dispatch strategy is robust and effectively reduces the cost of virtual power plants.

An approach for obtaining mechanical property of austenitic stainless steel by using continuous indentation test analysis

It is importance to understand the accurate material mechanical property of local area with flaws in the structure integrity evaluation, and the plastic hardening induced by the welding or other processing would induce the change of the mechanical property of the local area in structures. To understand and obtain heterogeneous material mechanical properties in the welded joint or other local region in the core structure of nuclear power plants, a group tests of tensile work hardening and continuous ball indentation, combining with inversion analysis by using the finite element method, are used to obtain the local mechanical properties of nuclear grade 316L austenitic stainless steel, and an approach to obtain the stress–strain relationship of the stainless steel material during the plastic deformation stage under different elongations is developed based on the representative stress–strain method in this paper. The investigated results indicates that the related mechanical parameters of 316L austenitic stainless steel increase with different elongations, and the deviations of the yield strength and the tensile strength values are both within 6%. It provides a reasonable and effective method to obtain the actual material mechanical property of the local area in important structures.

Effect of aging on failure mechanism of Alloy 709 at various temperatures

Alloy 709 is a novel austenitic stainless steel with high temperature creep strength, weldability, and corrosion resistance. These properties make the material suitable for applications in the structure of next-generation nuclear power plants. Enduring high temperatures for an extended period of time in the harsh environments of a nuclear power plant results in thermal aging of the material. Therefore, it is imperative to study the effect of thermal aging on the microstructure and mechanical properties of Alloy 709 before its application in the next generation power plants. In this study, hot-processed (forged + rolled), annealed and quenched ingots of Alloy 709 are aged at 650 °C for 2000 h in air and then tested at various temperatures up to 850 °C in an in-situ heating-loading Scanning Electron Microscope (SEM) equipped with Energy Dispersive Spectroscopy (EDS) and Electron Backscatter Diffraction (EBSD). The effect of testing temperature and aging on microstructural evolutions during tensile testing of as-received and aged samples are studied. Both as-received and aged samples displayed serrations and drop in ductility at elevated temperatures, due to the effect of dynamic strain aging (DSA). The occurrence of DSA activity was found within temperatures range of 500 °C–750 °C in as-received and 550 °C - 650 °C in aged samples. The aged samples showed less elongation accompanied by shallower dimples on the fractured surface, indicating less ductile failure mechanism compared to as-received samples. Failure mechanism observations on the fracture surface using SEM fractography are correlated to the observations made on the sample surface using in-situ SEM to achieve a complementary set of information to better understand the failure mechanism of this novel alloy.

Physiological Responses of Marine Macroalgae to Chlorine Dioxide Treatment

Chlorination is a widespread fouling control practice in water intake structures of power plants and desalination plants. Chlorine dioxide is used as an alternative to chlorine gas and sodium hypochlorite for controlling biofilms and biofouling. In this study, the physiological responses of two macroalgal species Ulva reticulata and Hypnea musciformis to chlorine dioxide treatment was studied under laboratory conditions. The algal samples were exposed to 0.05, 0.1 and 0.5 mg l−1 of chlorine dioxide for 5 days. The chlorophyll-a, carotenoid content and total polyphenol levels were analysed. The algal extracts were also analysed using GC-MS to understand the changes in the biochemical profile of the algae after treated with chlorine dioxide. Results indicated an increase in chlorophyll-a, carotenoid and total polyphenol content during initial exposure duration and further treatment showed a decrease in these parameters. The chlorine dioxide treatment also affected the fatty acids composition of the macroalgae. The physiological responses observed in this study indicate that chlorine dioxide as an antifouling biocide has toxic effects on these macroalgae.

Effect of Reinforcing Steel on the Impact Resistance of Reinforced Concrete Panel Subjected to Hard-Projectile Impact

Experimental and numerical studies were conducted to investigate the effect of reinforcing steel on the impact resistance of reinforced concrete structures and to reveal its mechanism. Hard-projectile impact tests using a single-stage gas gun were performed with reinforced concrete panels to simulate a nuclear power plant structure. Parametric analysis was conducted with a numerical model that applied a finite element method coupled with smoothed particle hydrodynamics using the following four variables: the impact velocity of the projectile as well as yield strength, spacing and diameter of the reinforcing steel. The experimental and numerical analysis results indicated that the impact resistance was significantly affected by the spacing of the reinforcing steel, but not by the yield strength or the diameter of the reinforcing steel. Narrower rebar spacing improved the impact resistance due to the enhanced confining and fragment trapping effects.

World experience and development prospects of mechanization scheme of nuclear power plants construction

Introduction. Improvement of construction methods for the main structures of nuclear power plants (NPP) is impossible without updating the old and developing fundamentally new schemes for mechanization of construction production. Based on the analysis of world experience in using various types of lifting mechanisms at NPP construction sites, it is proposed to assess the current state and perspective for the development of organizational and technological approaches to the development of effective mechanization of construction production in the construction of atomic energy facilities.
 Materials and methods. Review of domestic and world (UK, USA, Japan) experience in NPP construction allows us to assert that despite the technological and organizational and managerial difficulties, the construction of NPP power units by enlarged units of high factory readiness still remains promising and feasible. The implementation of this approach involves the design and manufacture of unique hoisting mechanisms, the most popular of which are currently crawler or rail-mounted mast cranes. At the same time, the experience of constructing nuclear power plants of the USSR and Great Britain using gantry cranes was undeservedly forgotten.
 Results. The performed comparative analysis of the applicability of tower, mast and bridge (gantry) types of cranes allows us to recognize the high complexity of using gantry cranes in the construction of NPPs and the structural limitations of other types of cranes. The main disadvantages of gantry cranes lie in their use of a rail track, the replacement of which with a pneumatic-wheeled chassis, which has undergone significant development in the last 20 years, can open up new perspective for the reengineering of previously used mechanization schemes for NPP construction.
 Conclusions. Using main lifting mechanism of an overhead crane equipped with a pneumatic wheel chassis in the construction of nuclear power becomes one of the most promising options in the development of nuclear energy construction. The development and implementation of new schemes for the mechanization of construction production based on experience and advanced technologies in mechanical engineering can provide a qualitative improvement of the ongoing investment and construction activities in the field of nuclear energy.

Разработка и обоснование пространственной механической модели основания сооружений с приведенными расчетными характеристиками грунтов с учетом конечной жесткости фундаментных конструкций

Предложена и обоснована новая пространственная ме­ханическая динамическая модель оснований сооружений атомных станций.
 В настоящее время при выполнении практических расчётов широко применяется модель оснований соору­жений атомных станций, приведённая в [1]. В этой модели мгновенные жёсткости основания при вращательных движениях жёсткого невесомого штампа функционально зависят от массы сооружения и от моментов инерции масс сооружения относительно координатных осей, что противоречит физической сути понятия мгновенных жёст­костей основания при вращательных движениях жёсткого невесомого штампа на поверхности инерционного полу­пространства.
 В свете вышеизложенного разработка динамической механической модели основания, устраняющей упомянутые несоответствия, представляется важной задачей, имеющей несомненную научную и практическую ценность
 Для обоснования проектных решений фундаментных конструкций сооружений необходимо определить величи­ны внутренних усилий, возникающих в их сечениях. При учёте конечной жёсткости фундаментных конструкций с применением метода конечных элементов необходимо установить закон распределения квазистатических и мгновенных жёстокостей грунтов основания по подошве фундаментной плиты.
 Известно, что параметры модели основания по существу должны имитировать параметры реакции основания жёст­кого невесомого штампа при его единичных смещениях и скоростях (линейных и угловых) по и относительно коор­динатных осей.
 В работе определены и обоснованы параметры модели основания, закон распределения интегральных жёсткостей по поверхности контакта. На примере сопоставления расчётов систем реакторного отделения совместно с основаниями, параметры которых были установлены по [1; 2], обоснована достоверность предлагаемой модели.

Nonlinear Seismic Response Characteristics of CAP1400 Nuclear Island Structure on Soft Rock Sites

CAP1400 nuclear island structure is an advanced and novel nuclear power plant structure. In order to explore the seismic response characteristics of CAP1400 nuclear island structure on soft rock sites, a three-dimensional refined nonlinear seismic response analysis model was established for a soft rock foundation-nuclear island structure system using ABAQUS software. The influences of the input ground motion intensity and the frequency spectrum characteristics on the acceleration, relative displacement, and floor response spectrum, as well as the critical shear wave velocity of nonbedrock sites for CAP1400 nuclear island structure, were proposed. The results suggested that the increasing amplitude of the peak acceleration and relative displacement of nuclear island structure decreased as the soft rock site entered a nonlinear state, and the high-frequency components of the input ground motion became more abundant. Specifically, the earthquake response was the largest at the cooling water tank on the top of the shield building, which was the focus of the seismic research on nuclear island structure. Due to the influence of the ground motion frequency spectrum characteristics and the nonbedrock site effect, the peak acceleration, peak relative displacement, and acceleration response spectrum of the nuclear island structure showed different changing trends for the near-field and far-field ground motions. Based on the influence of the site shear wave velocity on the seismic response of nuclear island structure, it was recommended that the critical shear wave velocity of nonbedrock sites for CAP1400 nuclear island structure should be 1250 m/s, and the nuclear island structure-foundation dynamic interaction could be ignored at this time. The research conclusions could provide some technical support and theoretical basis for the construction and seismic performance research of CAP1400 and other nuclear power plants.

Damage Evaluation of Composite Beams Under Fire Conditions

This paper presents a numerical method for damage evaluation of steel structures under fire conditions based on degraded material property values. As the measure of structural damage to fire, a damage index is proposed which indicates how much a structure loses its material strength when exposed to fire. The index is formulated with the ratio of a volume-weighted average of material strength at elevated temperatures to that of the strength at room temperature. To investigate the feasibility of proposed damage index, fire testing and the corresponding structural fire analysis of steel–concrete composite beams are performed using a design fire load. The fire is modeled using a standard fire curve proposed in American Society for Testing and Materials E119. A regular real-scale composite beam and the beam protected by a fire-resistant material layer, the latter of which is typical of structural members used in nuclear power plant buildings in Korea, are considered for the fire damage evaluation. The damage state of the composite beams is evaluated using the fire damage index at each time the fire progresses, and it is compared with the value of the post-fire damage index of the beams. By the use of the proposed damage index, the effect of fire-resistant materials on structural integrity is quantified, and it is investigated whether the damage state of each beam at the end of the fire load satisfies the design performance of composite beams used for nuclear power plant structures.

Torsional Stability Assessment of Columns Using Photometry and FEM

This paper presents a numerical analysis of the load-carrying capacity of steel open-section columns of a coal power plant structure. The structure was subjected to soil subsidence, which led to considerable structural deformations and damages. As a result, additional stresses appeared in the structure, and the static scheme of the structure was changed. To assess the influence of structural changes on the safety of the structure, a detailed investigation was necessary. Laser scanning was used to collect information concerning the geometry of structural elements. Results of the scanning were implemented in a numerical model of the structure. A complex finite element method (FEM) shell model of the column in ABAQUS software was developed. Torsional buckling stability analysis of column members was carried out. Different boundary conditions depending on the type of column connections to other elements were considered. Torsional deformations were treated as imperfections. Analysis showed that the connections of bracing elements, e.g., beams in multilevel frame, directly affected the collapse mechanism and load-bearing capacity of the investigated element. Finally, the paper showed that an appropriate change in the connections between the analyzed column and multilevel frame beams prevents the column from twisting, thereby increasing the critical force and load-bearing capacity of the analyzed industrial structure.

Bathymetric Monitoring of Alluvial River Bottom Changes for Purposes of Stability of Water Power Plant Structure with a New Methodology for River Bottom Hazard Mapping (Wloclawek, Poland).

The aim of this research was to produce a new methodology for a special river bottom hazard mapping for the stability purposes of the biggest Polish water power plant: Włocławek. During the operation period of the water power plant, an engineering-geological issue in the form of pothole formation on the Wisła River bed in the gravel-sand alluvium was observed. This was caused by increased fluvial erosion resulting from a reduced water level behind the power plant, along with frequent changes in the water flow rates and water levels caused by the varying technological and economic operation needs of the power plant. Data for the research were obtained by way of a 4-year geodetic/bathymetric monitoring of the river bed implemented using integrated GNSS (Global Navigation Satellite System), RTS (Robotized Total Station) and SBES (Single Beam Echo Sounder) methods. The result is a customized river bottom hazard map which takes into account a high, medium, and low risk levels of the potholes for the water power plant structure. This map was used to redevelop the river bed by filling. The findings show that high hazard is related to 5% of potholes (capacity of 4308 m3), medium with 38% of potholes (capacity of 36,455 m3), and low hazard with 57% of potholes (capacity of 54,396 m3). Since the construction of the dam, changes due to erosion identified by the monitoring have concerned approximately 405,252 m3 of the bottom, which corresponds to 130 Olympic-size pools. This implies enormous changes, while a possible solution could be the construction of additional cascades on the Wisła River.

Analysis of full-scale aircraft impact to reinforced concrete and steel plate reinforced concrete multiple barriers protecting nuclear power plants

This paper investigates the effectiveness of multiple barriers employed in safety-related concrete structures of nuclear power plants against aircraft impact. These barriers are constructed using reinforced concrete (RC) and steel plate reinforced concrete (SC) structural panels. The performance of such multiple barriers against the impact of a missile or an aircraft is found in many published studies. However, the influence of aircraft impact on the second barriers needs further study. To evaluate the impact resistance of multiple barriers, analysis of full-scale aircraft against RC and SC as the first panel with two different thicknesses (60 cm and 75 cm) are investigated by using finite element code LS-DYNA. The fracture process of aircraft and target panels, damage to the first panel, residual velocities, plastic strain of rebars, impact loads to second panel and energy balance histories are evaluated. The comparison of LS-DYNA analysis results indicates that the maximum force on the second rigid panels is reduced to a maximum of 61% owing to the SC panels. The SC panels experienced fewer residual velocities and impact loads thus showing better performance as compared to the conventional RC panels having the same thicknesses. Resultantly, it is possible to reduce the thickness and cost of safety-related RC structures by adopting steel plates in the design. The finite element-based methodology adopted in this study may be employed to predict the precise response of safety-related structures (barriers) against military and commercial aircraft impacts.

Seismic Qualification of Safety-Related Electrical Equipment in Nuclear Power Plant

Nuclear power plants are critical facility with safety being major concern. Equipment installed in nuclear power plant should have absolute reliability and guaranteed operation under extreme environmental conditions. Earthquake is one of the devastating natural environmental condition. Nuclear power plant equipment and structures should perform its safety related function during and/or after an earthquake. Motor control centres, Distribution boards, Power cum motor control centres, LT panels are part of safety related equipment in nuclear power plant, normal functioning of these panels during and/or after earthquake is highly essential for safe power plant operation. Designing of equipment for seismic dynamic loading and validating design by shake table testing will ensure safe functioning of nuclear power plant in the event of earthquake. Based on geographical location of nuclear power plant seismic loading details are estimated, site specific and floor specific earthquake loads are used for design. Central Power Research Institute (CPRI) is equipped with state-of-the-art tri-axial shake table facility for simulating true earthquake vibration. Seismic qualification methods, codal provisions and seismic qualification of Power cum Motor Control Centre (PMCC) Panel used in nuclear power plant by shake table method is discussed in this paper.

Possible Modeling of Small Biomass Power Plant

The framework under investigation right now one of driving 6 MW biomass power plant in Maharashtra, India. The last force yield of the plant was affected without anyone else decisive occasions, for example, gear dissatisfactions. There are three force plants, for example, Thermal, Wind and Biomass is connected with electrical system through appropriated age thought. At whatever point earth inadequacies are going on electrical network, considering wind power plant, by then the issue stream gives to biomass power plant structure to turbo-generator set and such eccentric occasions because the force regard be underneath the eagerness of the electrical framework. It is communicated; there is spur of the moment separation of supply. Spur of the moment inaccessibility recommends shorter age and more modest points of interest and ought to right now restrict. This issue can be managed by a preoccupation model, which might be utilized to see the issue spaces in the plant. The appearing and beguilement approach has central focuses when showed up distinctively according to other choice assistance gadgets, unequivocally intelligent models. The critical information are gathered for evaluation of issue and the model is made utilizing expansion programming rather than general programming language under the action reenactment perspective. The model is composed, confirmed and certified. The model is then overhauled by including a qualification decrease methodology and by utilizing the occasion amusement perspective. At long last, the fundamental outcomes are examined and the most.

Seismic fragility analysis of nuclear power plant structure under far-field ground motions

This manuscript presents a fragility assessment to evaluate the effects of far-field earthquakes on the damage of the AP1000 nuclear island building (NIB), by using Incremental Dynamic Analysis (IDA) and Multiple Stripes Analysis (MSA) methods. Five categories of performance levels (PL), four limit states (LS) and the relative intensity measure (IM) having a high relation with the ground motion are defined to calculate the fragility of the AP1000 NIB under 15 earthquake sequences. A comparison of the results shows that the probabilities of minor damage, severe damage, and collapse damage for concrete are much higher than the reinforcement bar, which indicates that the fragility of concrete dominates the damage probability of the NIB. The fragility curves of the auxiliary building (AB) and shield building (SB) obtained by IDA and MSA are consistent with each other, but the distinction is mainly on the peak values or increasing ratio. Additionally, the probabilities of minor damage, moderate damage, severe damage and collapse damage of AB are less than the cases of SB. Lastly, the results also indicate that fragility curves are efficiently assessed and essential for risk assessments of the NIB.

Seismic Response Amplification Factors of Nuclear Power Plants for Seismic Performance Evaluation of Structures and Equipment due to High-frequency Earthquakes

Analysis of the 2016 Gyeongju earthquake and the 2017 Pohang earthquake showed the characteristics of a typical high-frequency earthquake with many high-frequency components, short time strong motion duration, and large peak ground acceleration relative to the magnitude of the earthquake. Domestic nuclear power plants were designed and evaluated based on NRC's Regulatory Guide 1.60 design response spectrum, which had a great deal of energy in the low-frequency range. Therefore, nuclear power plants should carry out seismic verification and seismic performance evaluation of systems, structures, and components by reflecting the domestic characteristics of earthquakes. In this study, high-frequency amplification factors that can be used for seismic verification and seismic performance evaluation of nuclear power plant systems, structures, and equipment were analyzed. In order to analyze the high-frequency amplification factor, five sets of seismic time history were generated, which were matched with the uniform hazard response spectrum to reflect the characteristics of domestic earthquake motion. The nuclear power plant was subjected to seismic analysis for the construction of the Korean standard nuclear power plant, OPR1000, which is a reactor building, an auxiliary building assembly, a component cooling water heat exchanger building, and an essential service water building. Based on the results of the seismic analysis, a high-frequency amplification factor was derived upon the calculation of the floor response spectrum of the important locations of nuclear power plants. The high-frequency amplification factor can be effectively used for the seismic verification and seismic performance evaluation of electric equipment which are sensitive to high-frequency earthquakes.

AlN Single Crystal Accelerometer for Nuclear Power Plants

Reliable vibration sensing is essential to the immediate detection of unusual vibrations, ensuring the safety of nuclear power plant structures. For nuclear power plant applications, the sensor element must endure the harsh environment while retaining reliable performance. Aluminum nitride (AlN) single crystal is considered a promising candidate for the sensing unit due to its robustness to high temperature (HT) and irradiation conditions. However, there are few efforts in developing industrial accelerometers using AlN bulk-machined materials. This article aims to develop a shear-type accelerometer with AlN single crystal plates. The accelerometer's design is based on the numerical simulation results, followed by the fabrication of the sensor and the extensive validation under HT (~1000 °C). The sensitivity of the accelerometer was about 9.2 pC/g. The prototype sensor showed stable performance at varying temperatures from room temperature to 1000 °C. Furthermore, the sensitivity of the accelerometer was successfully sustained for 10 h under HT exposure of 1000 °C, and no obvious mechanical damage was detected after the test. After gamma irradiation for 1 month, the sensor performed stably, without any significant change in sensitivity. The developed AlN accelerometer can be a promising option to monitor the structural integrity of nuclear power plant structures.