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Corrosion mechanisms of candidate structural materials for supercritical water-cooled reactor

Lefu ZHANG, Fawen ZHU, Rui TANG

《能源前沿（英文）》 2009年第3卷第2期页码 233-240 doi: 10.1007/s11708-009-0024-y

摘要： Nickel-based alloys, austenitic stainless steel, ferritic/martensitic heat-resistant steels, and oxide dispersion strengthened steel are presently considered to be the candidate structural or fuel-cladding materials for supercritical water-cooled reactor (SCWR), one of the promising generation IV reactor for large-scale electric power production. However, corrosion and stress corrosion cracking of these candidate alloys still remain to be a major problem in the selection of nuclear fuel cladding and other structural materials, such as water rod. Survey of literature and experimental results reveal that the general corrosion mechanism of those candidate materials exhibits quite complicated mechanism in high-temperature and high-pressure supercritical water. Formation of a stable protective oxide film is the key to the best corrosion-resistant alloys. This paper focuses on the mechanism of corrosion oxide film breakdown for SCWR candidate materials.

关键词： supercritical water-cooled reactor general corrosion oxide film corrosion mechanism

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Studies on advanced water-cooled reactors beyond generation III for power generation

CHENG Xu

《能源前沿（英文）》 2007年第1卷第2期页码 141-149 doi: 10.1007/s11708-007-0018-6

摘要： China s ambitious nuclear power program motivates the country s nuclear community to develop advanced reactor concepts beyond generation III to ensure a long-term, stable, and sustainable development of nuclear power. The paper discusses some main criteria for the selection of future water-cooled reactors by considering the specific Chinese situation. Based on the suggested selection criteria, two new types of water-cooled reactors are recommended for future Chinese nuclear power generation. The high conversion pressurized water reactor utilizes the present PWR technology to a large extent. With a conversion ratio of about 0.95, the fuel utilization is increased about 5 times. This significantly improves the sustainability of fuel resources. The supercritical water-cooled reactor has favorable features in economics, sustainability and technology availability. It is a logical extension of the generation III PWR technology in China. The status of international R&D work is reviewed. A new supercritical water-cooled reactor (SCWR) core structure (the mixed reactor core) and a new fuel assembly design (two-rows FA) are proposed. The preliminary analysis using a coupled neutron-physics/thermal-hydraulics method is carried out. It shows good feasibility for the new design proposal.

关键词： Chinese situation selection generation water-cooled feasibility

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Feasibility analysis of modified AL-6XN steel for structure component application in supercritical water-cooled

Xinggang LI, Qingzhi YAN, Rong MA, Haoqiang WANG, Changchun GE

《能源前沿（英文）》 2009年第3卷第2期页码 193-197 doi: 10.1007/s11708-009-0030-0

摘要： Modified AL-6XN austenite steel was patterned after AL-6XN superaustenitic stainless steel by introducing microalloy elements such as zirconium and titanium in order to adapt to recrystallizing thermo-mechanical treatment and further improve crevice corrosion resistance. Modified AL-6XN exhibited comparable tensile strength, and superior plasticity and impact toughness to commercial AL-6XN steel. The effects of aging behavior on corrosion resistance and impact toughness were measured to evaluate the qualification of modified AL-6XN steel as an in-core component and cladding material in a supercritical water-cooled reactor. Attention should be paid to degradation in corrosion resistance and impact toughness after aging for 50 hours when modified AL-6XN steel is considered as one of the candidate materials for in-core components and cladding tubes in supercritical water-cooled reactors.

关键词： supercritical water cooled reactor tensile impact toughness corrosion aging

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Experimental study of critical flow of water at supercritical pressure

Yuzhou CHEN, Chunsheng YANG, Shuming ZHANG, Minfu ZHAO, Kaiwen DU, Xu CHENG

《能源前沿（英文）》 2009年第3卷第2期页码 175-180 doi: 10.1007/s11708-009-0029-6

摘要： Experimental studies of the critical flow of water were conducted under steady-state conditions with a nozzle 1.41 mm in diameter and 4.35 mm in length, covering the inlet pressure range of 22.1-26.8 MPa and inlet temperature range of 38-474°C. The parametric trend of the flow rate was investigated, and the experimental data were compared with the predictions of the homogeneous equilibrium model, the Bernoulli correlation, and the models used in the reactor safety analysis code RELAP5/MOD3.3. It is concluded that in the near or beyond pseudo-critical region, thermal-dynamic equilibrium is dominant, and at a lower temperature, choking does not occur. The onset of the choking condition is not predicted reasonably by the RELAP5 code.

关键词： critical flow supercritical water-cooled reactor(SCWR) reactor safety loss of coolant accident(LOCA)

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Experience gained in analyzing severe accidents for WWER RP using CC SOCRAT

《能源前沿（英文）》 2021年第15卷第4期页码 872-886 doi: 10.1007/s11708-021-0796-2

摘要： The current Russian regulatory documents on the safety of nuclear power plant (NPP) specify the requirements regarding design basis accidents (DBAs) and beyond design basis accidents (BDBAs), including severe accidents (SAs) with core meltdown, in NPP design (NP-001-15, NP-082-07, and others). For a rigorous calculational justification of BDBAs and SAs, it is necessary to develop an integral CC that will be in line with the requirements of regulatory documents on verification and certification (RD-03-33-2008, RD-03-34-2000) and will allow for determining the amount of data required to provide information within the scope stipulated by the requirements for the structure of the safety analysis report (SAR) (NP-006-16). The system of codes for realistic analysis of severe accidents (SOCRAT) (formerly, thermohydraulics (RATEG)/coupled physical and chemical processes (SVECHA)/behavior of core materials relocated into the reactor lower plenum (HEFEST)) was developed in Russia to analyze a wide range of SAs at NPP with water-cooled water-moderated power-generating reactor (WWER) at all stages of the accident. Enhancements to the code and broadening of its applicability are continually being pursued by the code developers (Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN)) with OKB Gidropress JSC and other organizations. Currently, the SOCRAT/1 code can be used as a base tool to obtain realistic estimates for all parameters important for computational justification of the reactor plant (RP) safety at the in-vessel stage of SAs with fuel melting. To perform analyses using CC SOCRAT/1, the experience gained during execution of thermohydraulic codes is applied, which allows for minimizing the uncertainties in the results at the early stage of an accident scenario. This study presents the results of the work performed in 2010–2020 in OKB Gidropress JSC using the CC SOCRAT/1. Approaches have been considered to develop calculational models and analyze SAs using CC SOCRAT. This process, which is clearly structured in OKB Gidropress JSC, provides a noticeable reduction in human involvement, and reduces the probability of erroneous results.

关键词： system of codes for realistic analysis of severe accidents (SOCRAT) design basis accidents (DBAs) severe accidents (SAs) computer code (CC) nuclear power plant (NPP) design water-cooled water-moderated (WWER) modeling model safety requirements

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A thermoelectric generator and water-cooling assisted high conversion efficiency polycrystalline silicon

Zekun LIU, Shuang YUAN, Yi YUAN, Guojian LI, Qiang WANG

《能源前沿（英文）》 2021年第15卷第2期页码 358-366 doi: 10.1007/s11708-020-0712-1

摘要： Solar energy has been increasing its share in the global energy structure. However, the thermal radiation brought by sunlight will attenuate the efficiency of solar cells. To reduce the temperature of the photovoltaic (PV) cell and improve the utilization efficiency of solar energy, a hybrid system composed of the PV cell, a thermoelectric generator (TEG), and a water-cooled plate (WCP) was manufactured. The WCP cannot only cool the PV cell, but also effectively generate additional electric energy with the TEG using the waste heat of the PV cell. The changes in the efficiency and power density of the hybrid system were obtained by real time monitoring. The thermal and electrical tests were performed at different irradiations and the same experiment temperature of 22°C. At a light intensity of 1000 W/m , the steady-state temperature of the PV cell decreases from 86.8°C to 54.1°C, and the overall efficiency increases from 15.6% to 21.1%. At a light intensity of 800 W/m , the steady-state temperature of the PV cell decreases from 70°C to 45.8°C, and the overall efficiency increases from 9.28% to 12.59%. At a light intensity of 400 W/m , the steady-state temperature of the PV cell decreases from 38.5°C to 31.5°C, and the overall efficiency is approximately 3.8%, basically remain unchanged.

关键词： photovoltaic (PV) thermoelectric generator conversion efficiency hybrid energy systems water-cooled plate (WCP)

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Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle

《能源前沿（英文）》 2021年第15卷第4期页码 916-929 doi: 10.1007/s11708-021-0757-9

摘要： Space nuclear reactor power (SNRP) using a gas-cooled reactor (GCR) and a closed Brayton cycle (CBC) is the ideal choice for future high-power space missions. To investigate the safety characteristics and develop the control strategies for gas-cooled SNRP, transient models for GCR, energy conversion unit, pipes, heat exchangers, pump and heat pipe radiator are established and a system analysis code is developed in this paper. Then, analyses of several operation conditions are performed using this code. In full-power steady-state operation, the core hot spot of 1293 K occurs near the upper part of the core. If 0.4 $ reactivity is introduced into the core, the maximum temperature that the fuel can reach is 2059 K, which is 914 K lower than the fuel melting point. The system finally has the ability to achieve a new steady-state with a higher reactor power. When the GCR is shut down in an emergency, the residual heat of the reactor can be removed through the conduction of the core and radiation heat transfer. The results indicate that the designed GCR is inherently safe owing to its negative reactivity feedback and passive decay heat removal. This paper may provide valuable references for safety design and analysis of the gas-cooled SNRP coupled with CBC.

关键词： gas-cooled space nuclear reactor power closed Brayton cycle system startup and shutdown positive reactivity insertion accident

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An old issue and a new challenge for nuclear reactor safety

F. D’AURIA

《能源前沿（英文）》 2021年第15卷第4期页码 854-859 doi: 10.1007/s11708-021-0729-0

摘要： Nuclear reactor safety (NRS) and the branch accident analysis (AA) constitute proven technologies: these are based on, among the other things, long lasting research and operational experience in the area of water cooled nuclear reactors (WCNR). Large break loss of coolant accident (LBLOCA) has been, so far, the orienting scenario within AA and a basis for the design of reactors. An incomplete vision for those technologies during the last few years is as follows: Progress in fundamentals was stagnant, namely in those countries where the WCNR were designed. Weaknesses became evident, noticeably in relation to nuclear fuel under high burn-up. Best estimate plus uncertainty (BEPU) techniques were perfected and available for application. Electronic and informatics systems were in extensive use and their impact in case of accident becomes more and more un-checked (however, quite irrelevant in case of LBLOCA). The time delay between technological discoveries and applications was becoming longer. The present paper deals with the LBLOCA that is inserted into the above context. Key conclusion is that regulations need suitable modification, rather than lowering the importance and the role of LBLOCA. Moreover, strengths of emergency core cooling system (ECCS) and containment need a tight link.

关键词： large break loss of coolant accident (LBLOCA) nuclear reactor safety (NRS) licensing perspectives basis for design of water cooled nuclear reactors (WCNR)

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Preliminary design of an SCO conversion system applied to the sodium cooled fast reactor

《能源前沿（英文）》 2021年第15卷第4期页码 832-841 doi: 10.1007/s11708-021-0777-5

摘要： The supercritical carbon dioxide (SCO₂) Brayton cycle has become an ideal power conversion system for sodium-cooled fast reactors (SFR) due to its high efficiency, compactness, and avoidance of sodium-water reaction. In this paper, the 1200 MW_e large pool SFR (CFR1200) is used as the heat source of the system, and the sodium circuit temperature and the heat load are the operating boundaries of the cycle system. The performance of different SCO₂ Brayton cycle systems and changes in key equipment performance are compared. The study indicates that the inter-stage cooling and recompression cycle has the best match with the heat source characte-ristics of the SFR, and the cycle efficiency is the highest (40.7%). Then, based on the developed system transient analysis program (FR-Sdaso), a pool-type SFR power plant system analysis model based on the inter-stage cooling and recompression cycle is established. In addition, the matching between the inter-stage cooling recompression cycle and the SFR during the load cycle of the power plant is studied. The analysis shows that when the nuclear island adopts the flow-advanced operation strategy and the carbon dioxide flowrate in the SCO₂ power conversion system is adjusted with the goal of maintaining the sodium-carbon dioxide heat exchanger sodium side outlet temperature unchanged, the inter-stage cooling recompression cycle can match the operation of the SFR very well.

关键词： sodium-cooled fast reactor (SFR) supercritical carbon dioxide (SCO₂) brayton cycle load cycle

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冷热电联产系统中气冷式微型透平机的发电耗水、空气污染物排放及成本影响：亚特兰大地区案例研究 Article

Jean-Ann James, Valerie M. Thomas, Arka Pandit, Duo Li, John C. Crittenden

《工程（英文）》 2016年第2卷第4期页码 470-480 doi: 10.1016/J.ENG.2016.04.008

摘要：

城市化进程的加快意味着城市和国际组织需要去寻找各种能够提高能源效率和减少空气中污染物排放的方法。冷热电联产(CCHP) 系统可以同时供暖、制冷和发电，具有提高城市或城市区域能源发电效率的潜力。本研究的目的是在满足建筑热需求(供热和制冷) 的各种运行条件下，对亚特兰大大都市区内的五种常见建筑类型在采用CCHP 系统时的发电耗水、CO₂ 和NO_x 排放，及其经济性进行评价。对于大多数采用或不采用净计量策略的建筑类型来说，以满足每小时热需求去运行CCHP 系统均可减少CO₂ 的排放量。该系统能否对这些建筑类型产生经济效益，主要取决于天然气的价格、净计量策略的采用和假定的CCHP 系统的成本结构。当建筑物采用净计量策略并且CCHP 系统是以满足建筑物每年的最大热需求而运行时，CCHP 系统的发电耗水量和NO_x 的排放量均有最大限度的减少，尽管此时该运行情景会增加温室气体排放和发电成本。CCHP 系统对中型办公楼、大型办公楼和多户型住宅建筑更经济、实用。

关键词：冷热电联产（CCHP）气冷式微型透平机分布式能源发电发电耗水净计量

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A novel cryogenic insulation system of hollow glass microspheres and self-evaporation vapor-cooled shield

Jianpeng ZHENG, Liubiao CHEN, Ping WANG, Jingjie ZHANG, Junjie WANG, Yuan ZHOU

《能源前沿（英文）》 2020年第14卷第3期页码 570-577 doi: 10.1007/s11708-019-0642-y

摘要： Liquid hydrogen (LH ) attracts widespread attention because of its highest energy storage density. However, evaporation loss is a serious problem in LH storage due to the low boiling point (20 K). Efficient insulation technology is an important issue in the study of LH storage. Hollow glass microspheres (HGMs) is a potential promising thermal insulation material because of its low apparent thermal conductivity, fast installation (Compared with multi-layer insulation, it can be injected in a short time.), and easy maintenance. A novel cryogenic insulation system consisting of HGMs and a self-evaporating vapor-cooled shield (VCS) is proposed for storage of LH . A thermodynamic model has been established to analyze the coupled heat transfer characteristics of HGMs and VCS in the composite insulation system. The results show that the combination of HGMs and VCS can effectively reduce heat flux into the LH tank. With the increase of VCS number from 1 to 3, the minimum heat flux through HGMs decreases by 57.36%, 65.29%, and 68.21%, respectively. Another significant advantage of HGMs is that their thermal insulation properties are not sensitive to ambient vacuum change. When ambient vacuum rises from 10 Pa to 1 Pa, the heat flux into the LH tank increases by approximately 20%. When the vacuum rises from 10 Pa to 100 Pa, the combination of VCS and HGMs reduces the heat flux into the tank by 58.08%–69.84% compared with pure HGMs.

关键词： liquid hydrogen storage hollow glass microspheres (HGMs) self-evaporation vapor-cooled shield (VCS) thermodynamic optimization

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我国高温气冷堆发展战略研究

张作义,吴宗鑫,王大中,童节娟

《中国工程科学》 2019年第21卷第1期页码 12-19 doi: 10.15302/J-SSCAE-2019.01.003

摘要：

高温气冷堆和在此基础上发展起来的超高温气冷堆是第四代核能系统研发重点的6种堆型之一。本文介绍了高温气冷堆的特点，对高温气冷堆技术在国内外的最新研发进展进行了简要综述，对高温气冷堆的发展定位等问题进行了讨论。在此基础上对我国高温气冷堆发展路线进行了展望。我国高温气冷堆技术历经跟踪、跨越和自主创新，目前在商业规模模块式高温气冷堆核电站技术上处于世界领先地位。在此基础上，我国正在启动部署后续60万千瓦级模块式高温气冷堆核电机组的研发和配套关键技术的攻关工作，以进一步推动高温气冷堆技术的产业化，保持我国在该领域的国际领先优势。

关键词：高温气冷堆高温技术路线

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中国高温气冷堆制氢发展战略研究

张平,徐景明,石磊,张作义

《中国工程科学》 2019年第21卷第1期页码 20-28 doi: 10.15302/J-SSCAE-2019.01.004

摘要：

核能制氢是一种有应用前景的高效、大规模、无排放的制氢技术，有望在氢气大规模集中供应的场景中起到重要作用。高温气冷堆是最适于核能制氢的堆型，在我国已有几十年的研发基础，目前正在国家科技重大专项支持下建造高温气冷堆示范电站。本文介绍了核能制氢技术的特点和主流的核能制氢工艺包括热化学碘硫循环、混合硫循环和高温蒸汽电解的原理，对国际上核能制氢技术发展现状进行了简要综述，并概述了清华大学在该领域的研发现状。此外对核能制氢的安全性、技术经济评价等问题进行了讨论，在此基础上对与高温气冷堆耦合的制氢技术进行了评价，并以氢气直接还原炼铁为例探讨了高温气冷堆制氢在工业领域的应用前景。最后对我国高温气冷堆制氢技术的发展路线进行了探讨。

关键词：高温气冷堆能制氢热化学循环高温电解技术路线

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山东石岛湾200 MW_e 球床模块式高温气冷堆(HTR-PM) 核电站示范工程 Review

张作义, 董玉杰, 李富, 张征明, 王海涛, 黄晓津, 李红, 刘兵, 吴莘馨, 王宏, 刁兴中, 张海泉, 王金华

《工程（英文）》 2016年第2卷第1期页码 112-118 doi: 10.1016/J.ENG.2016.01.020

摘要：

世界首台球床模块式高温气冷堆(HTR-PM) 核电站示范工程于2012 年12 月9日在中国山东省荣成市石岛湾厂区完成第一罐混凝土的浇筑，2015年6月完成反应堆厂房建设，然后进入设备安装阶段。目前正在向着在2017年年底实现并网发电的目标顺利推进。1个HTR-PM反应堆模块的热功率是250 MWth，反应堆堆芯氦气的进出口温度分别是250 °C 和750 °C。蒸汽发生器出口的蒸汽参数是13.25 MPa/567 °C。2个球床反应堆模块连接1台蒸汽轮机，形成一座210 MWe的核电站。项目团队克服了巨大困难，利用中国现有的工业制造技术研制出世界首台设备，实现了一系列重大技术创新。在研发的规划和实施、工业合作伙伴关系的建立、主设备制造、燃料生产、安全审查、站址选择以及安全性和经济性的平衡等方面取得了令人欣慰的进展，为世界同行积累了可以借鉴的经验。

关键词：核能高温气冷堆球床模块式高温气冷堆球床模块式高温气冷堆

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A fully solid-state cold thermal energy storage device for car seats using shape-memory alloys

《能源前沿（英文）》 2023年第17卷第4期页码 504-515 doi: 10.1007/s11708-022-0855-3

摘要： Thermal energy storage has been a pivotal technology to fill the gap between energy demands and energy supplies. As a solid-solid phase change material, shape-memory alloys (SMAs) have the inherent advantages of leakage free, no encapsulation, negligible volume variation, as well as superior energy storage properties such as high thermal conductivity (compared with ice and paraffin) and volumetric energy density, making them excellent thermal energy storage materials. Considering these characteristics, the design of the shape-memory alloy based the cold thermal energy storage system for precooling car seat application is introduced in this paper based on the proposed shape-memory alloy-based cold thermal energy storage cycle. The simulation results show that the minimum temperature of the metal boss under the seat reaches 26.2 °C at 9.85 s, which is reduced by 9.8 °C, and the energy storage efficiency of the device is 66%. The influence of initial temperature, elastocaloric materials, and the shape-memory alloy geometry scheme on the performance of car seat cold thermal energy storage devices is also discussed. Since SMAs are both solid-state refrigerants and thermal energy storage materials, hopefully the proposed concept can promote the development of more promising shape-memory alloy-based cold and hot thermal energy storage devices.

关键词： shape-memory alloy (SMA) elastocaloric effect (eCE) cooled seat cold thermal energy storage