Nuclear Engineering and Technology最新文献_第7页

Results of the IAEA coordinated research project enhancing computer security for radiation detection systems 原子能机构加强辐射探测系统计算机安全的协调研究项目的成果

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-01-01 DOI: 10.1016/j.net.2025.103998

Rodney Busquim e Silva , Michael T. Rowland , Ricardo Paulino Marques , Isabelle Coelho Franco , Jianghai Li , Tamas Holczer , Khalil El-Khatib , Nelson Agbemava , I Putu Susila , Jacek Gajewski , David Allison , Imbaby Mahmoud , Greg White

This work presents results of the International Atomic Energy Agency's Coordinated Research Project (CRP) on Enhancing Computer Security for Radiation Detection Systems. These systems include a wide range of fixed and mobile radiation detectors used in safety and security applications. The signals and data generated by radiation detection systems are transmitted to local or remote monitoring centers through various communication channels, enhancing the effectiveness of threat detection and enabling a timely response to alarm conditions. However, during the generation, processing, transmission and display of this information, data can be compromised. This CRP brought together 11 research institutes from 10 Member States to explore various topics, including threat modeling, cloud computing, malware propagation in large radiation detection networks, intrusion detection systems, defensive computer security architecture, wireless communication security, and simulation of integrated physical protection and radiation detection systems. The participating institutes created a reference architecture, designed models for synthetic radiation data and anomaly detection methods, performed vulnerability assessments of radiation detection systems, and developed prototypes for both virtual and hardware-in-the-loop testbeds. Their research also led to the creation of simulators, including a physical protection–radiation detector simulator that incorporates a 3D hospital model.

这项工作介绍了国际原子能机构关于加强辐射探测系统计算机安全的协调研究项目（CRP）的结果。这些系统包括用于安全和安保应用的各种固定和移动辐射探测器。辐射探测系统产生的信号和数据通过各种通信渠道传送到本地或远程监测中心，提高了威胁探测的有效性，并能及时对警报情况作出反应。然而，在生成、处理、传输和显示这些信息的过程中，数据可能会受到损害。该CRP汇集了来自10个成员国的11个研究机构，探讨各种主题，包括威胁建模、云计算、大型辐射检测网络中的恶意软件传播、入侵检测系统、防御性计算机安全体系结构、无线通信安全以及综合物理防护和辐射检测系统的模拟。参与研究的机构创建了一个参考架构，设计了合成辐射数据和异常检测方法的模型，对辐射检测系统进行了脆弱性评估，并开发了虚拟和硬件在环测试平台的原型。他们的研究还导致了模拟器的创建，包括一个物理保护辐射探测器模拟器，其中包含一个3D医院模型。

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引用次数: 0

A study on process information-driven cyber threat detection for I&C systems in NPP 核电站I&C系统过程信息驱动的网络威胁检测研究

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-01-01 DOI: 10.1016/j.net.2025.103879

Jae Hwan Kim, Kwang Seop Son, Jae Gu Song, Yong Gu Lee, Young Jun Lee

The increasing digitalization of Instrumentation and Control (I&C) systems in Nuclear Power Plants (NPPs) has improved operational efficiency while introducing cybersecurity vulnerabilities. Conventional network-based intrusion detection systems (IDS) face limitations in detecting sophisticated cyber threats targeting safety-critical controllers. To address these challenges, this study proposes a process information-driven cyber threat detection methodology based on real-time process data analysis and control logic consistency, enabling non-intrusive threat identification. The proposed methodology was examined through simulation and experimental testing using an APR-1400 Reactor Protection System (RPS) testbed. A cyber attack scenario targeting the High Pressurizer Pressure (HPP) Trip function was designed to assess the effectiveness of the detection mechanism. Simulation results demonstrated the detection algorithm's ability to identify unauthorized modifications to the trip setpoint, indicating the potential to detect cyber threats affecting reactor trip logic. Furthermore, experimental testing using the Safety Data Acquisition & Detection System (SDDS) demonstrated real-time anomaly detection while maintaining system integrity. These findings suggest that the proposed process-driven detection technique can enhance the cybersecurity resilience of NPPs without disrupting operational stability.

核电站仪表和控制（I&；C）系统的日益数字化提高了运行效率，同时引入了网络安全漏洞。传统的基于网络的入侵检测系统（IDS）在检测针对安全关键控制器的复杂网络威胁方面面临局限性。为了应对这些挑战，本研究提出了一种基于实时过程数据分析和控制逻辑一致性的过程信息驱动的网络威胁检测方法，从而实现非侵入式威胁识别。通过APR-1400反应堆保护系统（RPS）试验台的仿真和实验测试，验证了所提出的方法。设计了一个针对高稳压器压力（HPP）脱扣功能的网络攻击场景，以评估检测机制的有效性。仿真结果表明，该检测算法能够识别对脱扣设定值的未经授权的修改，表明检测影响反应堆脱扣逻辑的网络威胁的潜力。此外，使用安全数据采集和检测系统（SDDS）进行的实验测试表明，在保持系统完整性的同时，可以实时检测异常。这些发现表明，所提出的过程驱动检测技术可以在不破坏运行稳定性的情况下增强核电站的网络安全弹性。

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引用次数: 0

Benchmark analysis of SPERT III E-core critical experiments using the STREAM neutronics code 使用STREAM中子码对SPERT III E-core临界实验进行基准分析

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-31 DOI: 10.1016/j.net.2025.104112

Anisur Rahman , Saisundar Mohanty , Deokjung Lee

This study delivers a high-fidelity neutronic analysis of the SPERT III E-Core, a pressurized-water experimental reactor designed to probe fundamental transient behavior during reactivity-initiated accidents (RIAs). Using the advanced 3D transport code STREAM, we construct a detailed full-core representation—including fuel assemblies, cruciform transient control rods, control rod followers, and flux suppressors, to simulate both steady-state operation and rapid power excursions. Eigenvalue predictions at cold and hot zero-power conditions agree with measurements within 400 pcm, while simulated RIA responses, including reactivity evolution, peak power, and energy release, remain within 10 % of experimental observations. These results demonstrate that STREAM reliably captures fast transient dynamics in complex reactor configurations. Beyond validating a modern deterministic tool against historically important pulse-reactor experiments, this work establishes a foundation for next-generation transient modeling, supporting enhanced safety assessment, performance optimization, and informed regulatory decision-making in advanced reactor systems.

这项研究提供了SPERT III E-Core的高保真中子分析，这是一种压水实验反应堆，旨在探测反应性引发事故（ria）期间的基本瞬态行为。使用先进的3D传输代码STREAM，我们构建了一个详细的全核心表示-包括燃料组件，十字形瞬态控制棒，控制棒跟随器和通量抑制器，以模拟稳态运行和快速功率漂移。冷、热零功率条件下的特征值预测与400 pcm以内的测量结果一致，而模拟的RIA响应，包括反应性演化、峰值功率和能量释放，与实验观测值的误差仍在10%以内。这些结果表明STREAM可靠地捕获了复杂反应堆结构中的快速瞬态动力学。除了通过历史上重要的脉冲反应堆实验验证现代确定性工具之外，这项工作还为下一代瞬态建模奠定了基础，支持先进反应堆系统中增强的安全评估、性能优化和知情的监管决策。

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引用次数: 0

Tracking simulation of third-integer resonant extraction for Fermilab’s Mu2e experiment Fermilab Mu2e实验中第三整数共振提取的跟踪仿真

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-31 DOI: 10.1016/j.net.2025.104097

Chong Shik Park

The Mu2e experiment at Fermilab requires acceleration and transport of intense proton beams in order to deliver stable, uniform particle spills to the production target. To meet the experimental requirement, particles will be extracted slowly from the Delivery Ring to the external beamline. Using Synergia2, we have performed multi-particle tracking simulations of third-integer resonant extraction in the Delivery Ring, including space charge effects, physical beamline elements, and apertures. A piecewise linear ramp profile of tune quadrupoles was used to maintain a constant averaged spill rate throughout extraction. To study and minimize beam losses, we implemented and introduced a number of features, beamline element apertures, and septum plane alignments. Dynamic bumps are also implemented for local orbit corrections in which septum entrance angles are controlled to reduce angular spreads of extracted beams.

费米实验室的Mu2e实验需要加速和传输强质子束，以便向生产目标提供稳定、均匀的粒子泄漏。为了满足实验要求，粒子将从输送环缓慢地提取到外部光束线。利用协同效应a2，我们在传递环中进行了第三整数共振提取的多粒子跟踪模拟，包括空间电荷效应、物理光束线元素和孔径。在整个提取过程中，采用分段线性四极斜坡剖面来保持恒定的平均泄漏率。为了研究和最小化光束损耗，我们实现并引入了许多功能，光束线元件孔径和隔膜平面对齐。动态颠簸也实现了局部轨道修正，其中隔膜入口角被控制，以减少提取光束的角扩散。

引用次数: 0

A multi-node-upset-resilient 14T SRAM with high read stability for space applications 具有高读取稳定性的多节点抗扰14T SRAM，适用于空间应用

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-30 DOI: 10.1016/j.net.2025.104111

Sung-Jun Lim , Sung-Hun Jo

This paper proposes a voltage-booster read-decoupled radiation-hardened 14T (BDRH14T) SRAM cell. In harsh environments such as space, radiation can flip the stored data in memory cells, resulting in soft errors, including single-event upset (SEU) and single-event multi-node upset (SEMNU). Moreover, with the continued scaling of CMOS technology, the reduced spacing between transistors lowers the critical charge, increasing the vulnerability of SRAM cells to radiation-induced faults. The proposed BDRH14T cell is designed to recover its original stored data at all sensitive nodes even under a high injected charge of 150 fC. Additionally, it is capable of self-recovery from SEMNU occurring at storage node pairs. In addition to its radiation hardness, the BDRH14T exhibits enhanced read stability and reduced power consumption, achieving high read static noise margin (RSNM) and hold static noise margin (HSNM), along with low hold power (HPWR). All simulations were conducted using a 90 nm CMOS technology, considering variations over a wide range of supply voltages (0.9–1.1 V) and temperatures (−30 °C–120 °C). The superior performance of BDRH14T is attributed to the adoption of a voltage booster, a read-decoupled architecture, and deliberate a trade-off in read and write access times (RAT and WAT).

提出了一种电压升压读解耦抗辐射14T (BDRH14T) SRAM单元。在太空等恶劣环境中，辐射会翻转存储在存储单元中的数据，导致软错误，包括单事件破坏（SEU）和单事件多节点破坏（SEMNU）。此外，随着CMOS技术的不断缩小，晶体管之间的间距降低了临界电荷，增加了SRAM单元对辐射诱发故障的脆弱性。所提出的BDRH14T电池被设计为即使在150 fC的高注入电荷下也能在所有敏感节点恢复其原始存储数据。此外，它还能够从存储节点对上发生的SEMNU中自我恢复。除了具有辐射硬度外，BDRH14T还具有更高的读取稳定性和更低的功耗，实现了高读取静态噪声裕度（RSNM）和保持静态噪声裕度（HSNM）以及低保持功率（HPWR）。所有模拟均采用90nm CMOS技术进行，考虑了电源电压（0.9-1.1 V）和温度（- 30°C - 120°C）范围内的变化。BDRH14T的卓越性能归功于采用了电压增强器、读去耦架构，以及有意在读写访问时间（RAT和WAT）上进行权衡。

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引用次数: 0

New method for estimating uranium and plutonium masses using differential die-away signals 用微分渐逝信号估计铀和钚质量的新方法

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-30 DOI: 10.1016/j.net.2025.104110

Sehwan Seol, Jae Chang Kim, Junehyung Lee Bernaski, Yong Kyun Kim, Ser Gi Hong

This study presents a novel method for estimating the masses of uranium-235 and total plutonium in spent nuclear fuel assemblies using only Differential Die-Away (DDA) analysis results and cooling time without relying on passive or delayed neutron measurements. A database of DDA signals was generated through MCNP6 simulations based on spent nuclear fuel compositions derived from ORIGAMI depletion calculations under a wide range of initial enrichments, burnups, and cooling times. The correlations were developed between DDA results (i.e., die-away time and total neutron counts) and the isotopic masses. For ²³⁵U, a linear function of the signal ratio was used with the coefficients depending on cooling time. For Pu, a separate correlation was introduced using the die-away time difference between spent and fresh fuels, which required an estimation of initial enrichment. A Gaussian Process Regression (GPR) model was trained for this purpose, achieving high accuracy. Validation with 50 independent SNFs showed high prediction performance with maximum relative errors of 7.52 % and 2.41 % for ²³⁵U and Pu, respectively. This method provides a non-destructive and efficient technique for characterizing spent nuclear fuel assemblies, offering potential applications in nuclear safeguards, spent fuel management, and nuclear material accountancy.

本研究提出了一种新的方法来估计乏核燃料组件中铀-235和总钚的质量，仅使用差分死亡（DDA）分析结果和冷却时间，而不依赖于被动或延迟中子测量。通过MCNP6模拟，在广泛的初始浓缩、燃烧和冷却时间下，基于ORIGAMI耗尽计算得出的乏燃料成分生成了DDA信号数据库。开发了DDA结果（即死亡时间和总中子数）与同位素质量之间的相关性。对于235U，使用信号比的线性函数，其系数取决于冷却时间。对于铀，使用乏燃料和新燃料之间的死亡时间差引入了一个单独的相关性，这需要对初始富集进行估计。为此训练了高斯过程回归（GPR）模型，达到了较高的精度。50个独立snf的验证结果表明，235U和Pu的最大相对误差分别为7.52%和2.41%。该方法为表征乏燃料组件提供了一种非破坏性和高效的技术，在核保障、乏燃料管理和核材料会计方面具有潜在的应用前景。

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引用次数: 0

Pseudo-random pattern design and Monte Carlo evaluation of an active coded-aperture gamma-ray imager 有源编码孔径伽玛射线成像仪的伪随机图样设计与蒙特卡罗评价

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-29 DOI: 10.1016/j.net.2025.104109

Dukwoo Kim, Manhee Jeong

This study presents the development of an active coded-aperture gamma-ray imager based on pseudo-random patterns. Unlike conventional systems with mechanical collimators, the proposed design eliminates physical collimators by enabling the scintillator array to serve as the coding element. Pseudo-random patterns were optimized using the Great Deluge Algorithm to maximize a figure of merit incorporating cosine similarity, correlation, mean squared error, and peak-to-sidelobe ratio. The optimized patterns were implemented in a cylindrical GAGG(Ce) detector geometry, and responses were simulated using MCNPX-PoliMi. System matrices were constructed from omnidirectional photon incidence, and images were reconstructed with the maximum likelihood expectation maximization algorithm. Simulations demonstrated reliable reconstruction of single and multiple point sources as well as shaped sources. Angular resolution was measured as 5.436° vertically and 7.238° horizontally, comparable to the EPSILON-G system. Performance across 59.54–1836.07 keV achieved peak signal-to-noise ratio values above 30 dB and structural similarity index above 0.9. Although higher energies introduced more noise due to photon penetration and scattering, the results confirm the feasibility of lightweight, collimator-free, omnidirectional imaging suitable for unmanned platforms. Future work will focus on prototype fabrication and experimental validation.

本文介绍了一种基于伪随机模式的有源编码孔径伽玛射线成像仪的研制。与传统的机械准直器系统不同，该设计通过使闪烁体阵列作为编码元件来消除物理准直器。伪随机模式使用大洪水算法进行优化，以最大限度地利用余弦相似度、相关性、均方误差和峰旁瓣比。优化后的模式在圆柱形的GAGG（Ce）探测器几何结构中实现，并使用MCNPX-PoliMi对响应进行了模拟。利用全向光子入射构造系统矩阵，利用最大似然期望最大化算法重构图像。仿真结果表明，该方法可以可靠地重建单点源和多点源以及异形源。测量的角分辨率为垂直5.436°和水平7.238°，与EPSILON-G系统相当。在59.54-1836.07 keV范围内，峰值信噪比达到30 dB以上，结构相似指数达到0.9以上。尽管由于光子穿透和散射，更高的能量会带来更多的噪声，但结果证实了适用于无人平台的轻量化、无准直器、全向成像的可行性。未来的工作将集中在原型制造和实验验证上。

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引用次数: 0

Optimal control of reliability failure risk contagion dynamics in nuclear power systems 核电系统可靠性失效风险传染动力学的最优控制

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-26 DOI: 10.1016/j.net.2025.104108

Meirong Zhang , Jianyong Dai , Shangqing Gong , Jindao Huang

Risks originating from technology, management, and the external environment are a concern during the operation of nuclear power systems. The spread of these risks can impact the safe operation of nuclear power, especially when a component failure accelerates the risk impact, potentially leading to accidents and disasters. This paper develops a risk contagion dynamics model for nuclear power systems using epidemic dynamics mechanisms. The risk contagion coefficient due to reliability failure is utilized to adjust the reliability degradation equation. The SEIQRS model and Hamiltonian equation for nuclear power reliability risk contagion dynamics are reconstructed by introducing maintenance strategies like preventive maintenance, isolation maintenance, and defect maintenance. Optimal control methods are applied to mitigate the impact of reliability risk. Using a nuclear power plant operation system as an example shows how reliability failures amplify risks. Implementing maintenance strategies enhances reliability while reducing failures. Comparative analysis results underscore the effectiveness of addressing risk contagion impact through reliability degradation failure, thereby improving the reliability risk dynamic mechanism of nuclear power. The optimal maintenance strategy significantly boosts the reliability of nuclear power systems while mitigating the risk of contagion, providing valuable insights for optimal decision-making in nuclear power safety management.

在核电系统运行过程中，技术风险、管理风险和外部环境风险是一个值得关注的问题。这些风险的扩散会影响核电的安全运行，特别是当组件故障加速风险影响时，可能导致事故和灾难。利用流行动力学机制建立了核电系统风险传染动力学模型。利用可靠性失效的风险传染系数来调整可靠性退化方程。通过引入预防性维修、隔离维修和缺陷维修等维修策略，重构了核电可靠性风险传染动力学的SEIQRS模型和hamilton方程。采用最优控制方法减轻可靠性风险的影响。以某核电站运行系统为例，说明可靠性故障对风险的放大作用。实施维护策略可以提高可靠性，同时减少故障。对比分析结果强调了通过可靠性退化失效解决风险传染影响的有效性，从而完善核电可靠性风险动态机制。最优维护策略显著提高了核电系统的可靠性，同时降低了传染风险，为核电安全管理的最优决策提供了有价值的见解。

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引用次数: 0

Redox-controlled sorption behavior of Re(VII) on bulk solid and colloidal bentonite 稀土（VII）在大块固体和胶体膨润土上的氧化还原控制吸附行为

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-25 DOI: 10.1016/j.net.2025.104102

Junhyuk Ha , Sang-Ho Lee , Jun-Yeop Lee

This study investigates the sorption behavior of Re(VII) onto bulk solid and colloidal phases of Bentonil-WRK bentonite under various reducing conditions. Reducing systems were established with Na₂S₂O₄, disodium anthraquinone-2,6-disulfonate, and DB-3 groundwater from the KAERI Underground Research Tunnel (KURT). Batch sorption experiments were conducted for 2500 h with an initial Re(VII) concentration of 10^−6.5 M and a solid-to-liquid ratio of 0.5 g/L. Measured pH and E_h values indicated the reduction of Re(VII) to Re(IV), consistent with thermodynamic predictions and confirmed by X-ray photoelectron spectroscopy. Sorption efficiency increased markedly after 500 h, highlighting the governing role of Re redox chemistry in such conditions. Faster sorption occurred in the DB-3 system, where Fe(II) ions and sulfur-bearing colloids enhanced Re retention. Sorption kinetic analysis indicated a redox-controlled sorption behavior of Re(VII) onto bulk solid and colloidal bentonite under the investigated reducing conditions. The results are expected to support more reliable predictions of the migration and retardation of redox-sensitive anionic radionuclides (e.g., Tc, for which Re serves as a chemical surrogate) in the reducing subsurface environment.

研究了不同还原条件下，Re（VII）在膨润土- wrk膨润土固体相和胶体相上的吸附行为。利用KAERI地下研究隧道（KURT）的Na2S2O4、蒽醌-2,6-二磺酸二钠和DB-3地下水建立了还原体系。间歇式吸附实验2500 h，初始Re（VII）浓度为10 ~ 6.5 M，料液比为0.5 g/L。测量的pH和Eh值表明Re（VII）还原为Re(IV)，与热力学预测一致，并经x射线光电子能谱证实。500h后吸附效率显著提高，表明在此条件下稀土氧化还原化学的调控作用。DB-3体系的吸附速度更快，其中Fe（II）离子和含硫胶体增强了Re的保留。吸附动力学分析表明，在所研究的还原条件下，稀土（VII）在大块固体和胶体膨润土上具有氧化还原控制的吸附行为。这些结果有望支持更可靠的预测氧化还原敏感阴离子放射性核素（例如，稀土作为化学替代物的Tc）在还原性地下环境中的迁移和阻滞。

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引用次数: 0

Technical analysis for optimum hydrogen production using nuclear–renewable hybrid energy system 核能-可再生混合能源系统最佳制氢技术分析

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-25 DOI: 10.1016/j.net.2025.104094

Faiza Sohail , Wahab Mubashir , Inamul Haq , Muhammad Zubair , Ali Mansoor , Haseeb ur Rehman

This paper provides detailed technical analysis of a hybrid energy system (HES) that integrates nuclear and solar energy sources, specifically focusing on optimizing electricity production and hydrogen generation. The study explores the potential of small modular reactors (SMRs), which are designed for flexibility of load following and frequency following modes. In this analysis, high temperature gas cooled SMR (design parameters are taken according to gas turbine high-temperature reactor (GT-HTR)), is thermodynamically coupled with a concentrated solar power (CSP) system, optimize in a way to enhance the performance and efficiency of the overall system. Solar thermal energy from CSP is used to reheat the gas in the second stage of a Brayton cycle, improving efficiency and regulating electricity output. During low-demand periods, surplus energy is diverted to hydrogen production using a solid oxide electrolysis cell (SOEC). In this study, the integration of CSP and hydrogen co-generation significantly improve the efficiency of the HTR with an electrical output of ranging from 225 to 450 MWe, and hydrogen production capacity of up to 130 tonnes/day.

本文对核能和太阳能相结合的混合能源系统（HES）进行了详细的技术分析，重点是优化发电和制氢。该研究探索了小型模块化反应堆（smr）的潜力，该反应堆设计具有负载跟随和频率跟随模式的灵活性。在本分析中，将高温气冷SMR（设计参数参照燃气轮机高温堆（GT-HTR））与聚光太阳能（CSP）系统进行热力学耦合，优化以提高整个系统的性能和效率。来自CSP的太阳能热能在布雷顿循环的第二阶段用于再加热气体，提高效率并调节电力输出。在低需求时期，多余的能量被转移到使用固体氧化物电解电池（SOEC）制氢。在本研究中，CSP和氢热电联产的整合显著提高了HTR的效率，其电力输出范围为225至450兆瓦，氢气生产能力高达130吨/天。

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引用次数: 0