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Study on hydrogen stratification and erosion process in Chinese SMR containment under severe accident scenario

International Journal of Advanced Nuclear reactor design and technology 2020年 2卷 43-51页

作者： Fan, Yang Songwei, Li Wei, Zeng Zhifang, Qiu Jian, Deng Science and Technology on Reactor System Design Technology Laboratory NPIC China Design and Research Sub-institute NPIC China

During postulated severe accident, large amount of hydrogen-vapor mixture will be released into the containment and inflammable gas mixture may form. Once the gas will be ignited, the generated pressure loads can jeopardize the integrity of the internal structures. As the local accumulation of high content hydrogen related much to the stratification and erosion mechanism, it is therefore of interest whether a stratification of gas layers will form within small containment. In this study, a stratification/erosion experiment is performed and the criteria under which the steady stratification will be destroyed by steam jet discussed. Then the simulation method is validated by the experimental data. At last, several severe accident scenarios for Chinese SMR performed and one of them is adopted for containment hydrogen CFD analysis. It is shown that high content of hydrogen will form in the upper part of the containment, and clear gas stratification will form, such stratification will be enhanced due to the condensation effect of steel containment wall. © 2020

关键词： Hydrogen

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Experimental research on the startup and shutdown heat transfer behavior of the coupling system of multi-stage heat pipes and radiators

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Annals of Nuclear Energy 2025年 222卷

作者： Limin Liu Zhengyu Du Ziang Guo Ziyin Liu Xiaoqiang He Hanyang Gu School of Nuclear Science and Engineering Shanghai Jiao Tong University China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China China

The heat pipe cooled reactor (HPR) offers high safety and compactness for space applications. This study experimentally investigates the coupled transient thermal behavior of the primary sodium heat pipe, thermoelectric generator (TEG), and secondary potassium heat pipe radiators during startup and shutdown. The primary heat pipe reached ∼700 °C at the evaporator within 3 h, while the secondary radiators exhibited delayed activation, with most condensing sections exceeding 299 °C after 21 h. A sonic limit effect caused local thermal and pressure drops at 800 mm. 75–80 % of input power was dissipated radiatively, exhibiting a thermal lag due to system inertia. During shutdown, the primary heat pipe responded rapidly to power reduction, while secondary heat pipe radiators showed accelerated cooling after passing their transition temperature. Stepwise power reductions led to faster temperature drops in the primary pipe than constant-rate reduction conditions. These results offer insights into HPR thermal dynamics for space system design.

关键词： Space applications

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Experimental study on aerosol behavior in water pool scrubbing under severe accident conditions

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International Journal of Advanced Nuclear reactor design and technology 2020年 2卷 111-116页

作者： Xu, Youyou Deng, Jian Zou, Zhiqiang Jiang, Guangming Wu, Xiaoli Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

In severe accident of nuclear power plant, large quantities of steam and radioactive aerosol may release to the containment. Meanwhile, hydrogen may be generated by zirconium-steam reaction and released to the containment and mixed with steam and air to form a flammable mixture (H2, H2O, Air) which might combust even explode to generate mechanical and thermal load on containment. In this situation, timely containment venting strategies (CVS) is an important and effective measure to release the containment atmosphere to decrease the pressure. In order to remove the radioactive aerosol particles and cool the high temperature mixture, the containment atmosphere are vented to the water pool. This paper mainly investigated the behavior of aerosol scrubbing in water pool. The effects of submergence depth, aerosol particle diameter and aerosol concentration were preliminary studied by conducting a series of experiments. The results illustrate that the scrubbing efficiency of gas jet injection into water pool almost larger than 90%. And the aerosol particle diameter and submergence depth have significant influence on decontamination factor (DF). This paper provide data basis and reference to the subsequent work. © 2020

关键词： Aerosols

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Advancements in the research of high-temperature gas-cooled reactor fuel via additive manufacturing techniques

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International Journal of Advanced Nuclear reactor design and technology 2024年第1期6卷 14-20页

作者： Liao, Haoyu Zhang, Ting Li, Chenxi Tang, Changbin Li, Yuanming Chen, Ping Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu610200 China

Recent advances in high-temperature gas-cooled reactor fuel research have captured the global spotlight, as modern operating contexts demand innovative responses to unprecedented challenges. This article offers an overview of contemporary directions in high-temperature gas-cooled reactor fuel design worldwide, pinpointing the shared operational demands and development patterns characteristic of these advanced fuels. It presents an innovative advanced fuel design, which incorporates multi-layer coated particles to boost safety and employs high-temperature-resistant silicon carbide (SiC) ceramics, seamlessly integrated with cutting-edge additive manufacturing (AM) techniques. This design heralds a shift toward modular fuel element solutions that are easily scalable, supporting the diverse array of advanced reactors and marking a significant step forward in the quest for high-temperature gas-cooled reactor fuel technologies. © 2024 Xi'an Jiaotong University

关键词： Silicon carbide

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Verification of the 2D/1D coupling 3D transport code TIGER with C5G7 benchmarks

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International Journal of Advanced Nuclear reactor design and technology 2019年 1卷 43-50页

作者： Wu, Wenbin Yu, Yingrui Li, Qing Yao, Dong Luo, Qi Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

TIGER is a 2D/1D coupling 3D transport code developed by Nuclear Power Institute of China based on large-scale parallel computation. It employs 2D domain-decomposed parallel Matrix MOC in the radial direction and 1D finite difference diffusion in the axial direction. 2D domain-decomposed parallel Matrix MOC is accelerated with multi-group and multi-domain coupled PGMRES algorithm. Generally, 2D planar problem are solved independently and parallel degree is natural in the axial direction. Combination of the parallel degrees of both radial and axial directions is adopted in TIGER to achieve the large-scale parallel computation. In this paper, a few variations of C5G7 benchmarks were created based on the published benchmarks. Reference results of these variations were provided by the Monte Carlo code RMC. To demonstrate the accuracy and efficiency of TIGER, C5G7 benchmarks and these relevant variations were calculated by TIGER, and the comparisons were made with the published results and Monte Carlo results. © 2019 Xi'an Jiaotong University

关键词： Matrix algebra

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Investigation into the flow and heat transfer characteristics in liquid metal cooled narrow rectangular channel with rough surfaces

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Case Studies in Thermal Engineering 2025年 72卷

作者： Xue Zhang Wenpei Feng Xiaolong Yang Hongxing Yu Jian Deng Sijia Du Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610213 China College of Nuclear Technology and Automation Engineering Chengdu University of Technology Chengdu 610059 China

This study investigates the impact of roughness elements on fluid flow and heat transfer characteristics in narrow rectangular channels. The results show that when the fluid flows over roughness elements, it induces vortices near the wall, disturbing the flow and heat transfer boundary layers. This enhances heat transfer while simultaneously increasing flow resistance. Among different roughness types, cylindrical roughness elements demonstrate a more substantial improvement in both heat transfer efficiency and friction factor compared to cubic elements. The Nusselt number is found to be non-monotonic related to the height of the roughness elements, while the friction factor increases with height. Additionally, larger roughness element diameters lead to higher Nusselt numbers and friction factors. Further analysis reveals that under conditions where the spacing and height remain unchanged, an increase in the roughness elements quantity results in a diminished enhancement of heat transfer. The base edge length of the roughness elements has a more significant impact on heat transfer capacity than the additional heated area, while the additional area primarily affects the flow resistance, causing the friction factor to increase with the number of roughness elements.

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Research for the heat leakage caused by gaps on barrel insulation structure of reactor pressure vessel

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International Journal of Advanced Nuclear reactor design and technology 2019年 1卷 30-42页

作者： Tian, Qiu Ying, Luo Yang, Qiu Yu-guang, Li Guo-fu, Xie Li-cai, Yang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China ChengduSichuan Province610213 China

Due to the function requirements of the Cavity Injection and Cooling system, the barrel insulation structure of HPR1000 reactor pressure vessel has been greatly improved compared with the previous projects. In the past, the empirical formula method was used to evaluate the thermal properties of the insulation, but the influences of the support structure and the excessive gap on insulation are difficult to evaluate. In this paper, the fitting formula of the equivalent thermal conductivity and the qualitative temperature of the insulation have been obtained firstly through the heat transfer test. Then, ANSYS Fluent was used to simulate the barrel insulation structure with gaps of HPR1000. A circumferential 15° model was established to obtain evaluation method for flow leakage with gaps in hot state, and then a whole model of the barrel insulation structure with gaps was established to obtain heat loss of insulation based on calculation of flow leakage. The sensitivity of gap size and ventilation parameters to heat leakage was further analyzed. Finally, it was indicated that, by minimizing joint gap length, setting of overlaps, controlling cold gap, optimizing structure of insulation support, the effect of heat leakage caused by gaps can be reduced. © 2019 Xi'an Jiaotong University

关键词： Thermal insulation

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Rapid diagnostic method for transplutonium isotope production in high flux reactors

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Nuclear science and Techniques 2023年第3期34卷 125-142页

作者： Qing-Quan Pan Qing-Fei Zhao Lian-Jie Wang Bang-Yang Xia Yun Cai Xiao-Jing Liu School of Nuclear Science and Engineering Shanghai Jiao Tong UniversityShanghai 200240China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610200China

Transplutonium isotopes are scarce and need to be produced by irradiation in high flux ***,their production is inefficient,and optimization studies are *** study analyzes the physical nature of transplutonium isotope produc-tion using ^(252)Cf,^(244)Cm,^(242)Cm,and ^(238)Pu as *** methods based on the Monte Carlo burnup calculation have the limitations of many calculations and cannot analyze the individual energy intervals in detail;thus,they cannot sup-port the refined evaluation,screening,and optimization of the irradiation *** understanding the physical nature and simplifying the complexity of the production process,we propose a rapid diagnostic method for evaluating radiation schemes based on the concepts“single energy interval value(SEIV)”and“energy spectrum total value(ESTV)”.The rapid diagnostic method not only avoids tedious burnup calculations,but also provides a direction for *** optimal irradiation schemes for producing ^(252)Cf,^(244)Cm,^(242)Cm,and ^(238)Pu are determined based on a rapid diagnostic *** irradiation schemes can significantly improve production *** with the initial scheme,the optimal scheme improved the production efficiency of ^(238)Pu by 7.41 times;^(242)Cm,11.98 times;^(244)Cm,65.20 times;and ^(252)Cf,15.08 ***,a refined analysis of transplutonium isotope production is conducted and provides a theoretical basis for improving production efficiency.

关键词： Transplutonium isotope Rapid diagnostic method Production optimization Single energy interval value Energy spectrum total value

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High-resolution neutronics model for ^(238)Pu production in high-flux reactors

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Nuclear science and Techniques 2024年第5期35卷 226-236页

作者： Qing-Quan Pan Qing-Fei Zhao Lian-Jie Wang Bang-Yang Xia Yun Cai Jin-Biao Xiong Xiao-Jing Liu School of Nuclear Science and Engineering Shanghai Jiao Tong UniversityShanghai 200240China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610200China

We proposed and compared three methods(filter burnup,single energy burnup,and burnup extremum analysis)to build a high-resolution neutronics model for 238Pu production in high-flux *** filter burnup and single energy burnup methods have no theoretical approximation and can achieve a spectrum resolution of up to~1 eV,thereby constructing the importance curve and yield curve of the full energy *** burnup extreme analysis method combines the importance and yield curves to consider the influence of irradiation time on production efficiency,thereby constructing extreme *** three curves,which quantify the transmutation rate of the nuclei in each energy region,are of physical significance because they have similar distributions.A high-resolution neutronics model for ^(238)Pu production was established based on these three curves,and its universality and feasibility were *** neutronics model can guide the neutron spectrum optimization and improve the yield of ^(238)Pu by up to 18.81%.The neutronics model revealed the law of nuclei transmutation in all energy regions with high spectrum resolution,thus providing theoretical support for high-flux reactor design and irradiation production of ^(238)Pu.

关键词： ^(238)Pu Neutronics model High-flux reactor Spectrum resolution Spectrum optimization

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Optimizing near-carbon-free nuclear energy systems:advances in reactor operation digital twin through hybrid machine learning algorithms for parameter identification and state estimation

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Nuclear science and Techniques 2024年第8期35卷 177-203页

作者： Li‑Zhan Hong He‑Lin Gong Hong‑Jun Ji Jia‑Liang Lu Han Li Qing Li Paris Elite Institute of Technology Shanghai Jiao Tong UniversityShanghai 200240China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610041China

Accurate and efficient online parameter identification and state estimation are crucial for leveraging digital twin simulations to optimize the operation of near-carbon-free nuclear energy *** previous studies,we developed a reactor operation digital twin(RODT).However,non-differentiabilities and discontinuities arise when employing machine learning-based surrogate forward models,challenging traditional gradient-based inverse methods and their *** study investigated deterministic and metaheuristic algorithms and developed hybrid algorithms to address these *** efficient modular RODT software framework that incorporates these methods into its post-evaluation module is presented for comprehensive *** methods were rigorously assessed based on convergence profiles,stability with respect to noise,and computational *** numerical results show that the hybrid KNNLHS algorithm excels in real-time online applications,balancing accuracy and efficiency with a prediction error rate of only 1%and processing times of less than 0.1 ***,algorithms such as FSA,DE,and ADE,although slightly slower(approximately 1 s),demonstrated higher accuracy with a 0.3%relative L_2 error,which advances RODT methodologies to harness machine learning and system modeling for improved reactor monitoring,systematic diagnosis of off-normal events,and lifetime management *** developed modular software and novel optimization methods presented offer pathways to realize the full potential of RODT for transforming energy engineering practices.

关键词： Parameter identification State estimation reactor operation digital twin Reduced order model Inverse problem

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