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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    

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    

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    

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    

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)    

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)    

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)    

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NOx 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NOx 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    

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    

水·水资源·农业节水

刘更另

《中国工程科学》 2000年 第2卷 第7期   页码 39-42

摘要:

文章从水性质特点谈到中国水资源的问题,认为不能单纯用年平均降雨量的多少来判定中国水资源的状况,水资源开发利用的好坏决定于人类社会的调节和管理。中国水资源总的来说是够用的,最大问题是降水量的时空分布不平衡。

中国农民几千年来创造了许多治水蓄水用水的经验。农业节水非常重要,关键在"分散蓄水,分散使用",以减少径流在汇集和分散过程中的损失和污染,在提高水的利用效率方面有一系列的科研和实际工作要做。

关键词:     水资源     农业节水     分散蓄水    

Managing water for life

Daniel P. LOUCKS, Haifeng JIA

《环境科学与工程前沿(英文)》 2012年 第6卷 第2期   页码 255-264 doi: 10.1007/s11783-011-0359-6

摘要: Water is essential for life. In spite of the entire engineering infrastructure devoted to the treatment, regulation and beneficial uses of water, occasionally sufficient quantities and qualities of water become scarce. When this happens, just how do we decide how much less water to allocate to all of us and the activities we engage in to sustain and enhance our quality of life? This paper addresses some of the complexities of answering such a question, especially as society increasingly recognizes the need to provide flow regimes that will maintain healthy aquatic and floodplain ecosystems that also impact the economic, physical and even the spiritual quality of our lives. For we depend on these ecosystems to sustain our wellbeing. We are indeed a part of our ecosystems. We depend upon on aquatic ecosystems to moderate river flow qualities and quantities, reduce the extremes of floods and droughts, reduce erosion, detoxify and decompose waterborne wastes, generate and preserve flood plain soils and renew their fertility, regulate disease carrying organisms, and to enhance recreational benefits of river systems. This question of deciding just how much water to allocate to each water user and for the maintenance of viable aquatic ecosystems, especially when there is not enough, is a complex, and largely political, issue. This issue is likely to become even more complex and political and contentious in the future as populations grow and as water quantities and their qualities become even more variable and uncertain.

关键词: water stress     aquatic ecosystems     sustainable water resource allocations     ecosystem water requirements    

The effect of different agricultural management practices on irrigation efficiency, water use efficiencyand green and blue water footprint

La ZHUO, Arjen Y. HOEKSTRA

《农业科学与工程前沿(英文)》 2017年 第4卷 第2期   页码 185-194 doi: 10.15302/J-FASE-2017149

摘要: This paper explores the effect of varying agricultural management practices on different water efficiency indicators: irrigation efficiency (IE), crop water use efficiency (WUE), and green and blue water footprint (WF). We take winter wheat in an experimental field in Northern China as a case study and consider a dry, average and wet year. We conducted 24 modeling experiments with the AquaCrop model, for all possible combinations of four irrigation techniques, two irrigation strategies and three mulching methods. Results show that deficit irrigation most effectively improved blue water use, by increasing IE (by 5%) and reducing blue WF (by 38%), however with an average 9% yield reduction. Organic or synthetic mulching practices improved WUE (by 4% and 10%, respectively) and reduced blue WF (by 8% and 17%, respectively), with the same yield level. Drip and subsurface drip irrigation improved IE and WUE, but drip irrigation had a relatively large blue WF. Improvements in one water efficiency indicator may cause a decline in another. In particular, WUE can be improved by more irrigation at the cost of the blue WF. Furthermore, increasing IE, for instance by installing drip irrigation, does not necessarily reduce the blue WF.

关键词: field management     irrigation efficiency     water footprint     water productivity     water use efficiency    

Emergency drinking water treatment in source water pollution incident-technology and practice in China

Xiaojian ZHANG , Chao CHEN ,

《环境科学与工程前沿(英文)》 2009年 第3卷 第3期   页码 364-368 doi: 10.1007/s11783-009-0027-2

摘要: An investigation into emergency potable water treatment technologies was conducted to investigate China’s water pollution situation. In order to confirm optimum parameters, the technological efficiency of each pollutant was obtained. About 100 contaminants were tested to find the emergency treatment technologies, most of which were found to be positive. This paper presents the three largest and most significant water pollution incidents in China to date, analyzing cases such as the nitrobenzene pollution incident in the Songhua River in November 2005, the cadmium pollution incident in the Beijiang River in December 2005, and the water crisis with odorous tap water in Wuxi City in May 2007.

关键词: emergency drinking water treatment     water pollution     adsorption     oxidation     precipitation    

标题 作者 时间 类型 操作

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

期刊论文

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

Lefu ZHANG, Fawen ZHU, Rui TANG

期刊论文

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

CHENG Xu

期刊论文

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

期刊论文

Experimental study of critical flow of water at supercritical pressure

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

期刊论文

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

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

期刊论文

An old issue and a new challenge for nuclear reactor safety

F. D’AURIA

期刊论文

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

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

期刊论文

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

期刊论文

巨晓洁:用于水处理和水检测的新型功能材料(2022年4月16日)

2022年06月09日

会议视频

水·水资源·农业节水

刘更另

期刊论文

王光谦:全球水循环与水资源利用(2019年10月17日)

王光谦(院士)

2021年01月20日

会议视频

Managing water for life

Daniel P. LOUCKS, Haifeng JIA

期刊论文

The effect of different agricultural management practices on irrigation efficiency, water use efficiencyand green and blue water footprint

La ZHUO, Arjen Y. HOEKSTRA

期刊论文

Emergency drinking water treatment in source water pollution incident-technology and practice in China

Xiaojian ZHANG , Chao CHEN ,

期刊论文