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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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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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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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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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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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核电先进堆型与我国核电发展

胡亚蕾

《中国工程科学》 2005年第7卷第11期页码 98-102

摘要：

介绍了核电堆型发展的四个阶段和第一、二代核电堆型的发展历史；论述了第三代先进堆型的发展、设计特点和第四代先进堆的开发目标。

关键词：核电先进堆型中国核电

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A numerical study of helium-heated inorganic membrane reformer coupling to HTGR

YIN Huaqiang, JIANG Shengyao, JU Huaiming, ZHANG Youjie

《能源前沿（英文）》 2007年第1卷第4期页码 446-450 doi: 10.1007/s11708-007-0065-3

摘要： Based on one-dimensional quasi-homogeneous model, a steady-state model and its computer program were developed for helium-heated inorganic membrane reformer coupling to high temperature gas-cooled reactor (HTGR). The results show

关键词： temperature gas-cooled one-dimensional quasi-homogeneous steady-state helium-heated

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A perspective of “Nuclear Hot Spring” for long-term sustainable economy of the world

Yingzhong LU

《能源前沿（英文）》 2011年第5卷第4期页码 349-357 doi: 10.1007/s11708-011-0168-4

摘要： The rapid growth of human economy in the late 20th century gave rise to great concern over sustainability of the world. A pessimistic “Full World Model” forecasts that human economy could not develop further. The nuclear fission (and fusion later), however, could release huge amount of energy to create sufficient useful material resources and turn the said pessimistic modelinto a new optimistic “Sustainable World Model”.The dilemma of nuclear energy (Military Giant vs. Civil Dwarf) jeopardizes its performance as a “Technologic Fixer”. According to Mother Nature’s teachings, the elimination of the root-causes of the design-based risk factors could solve this problem. Recent technology break-through from inherent safety to natural safety has been made in China. The proposed full-power natural circulation “Nuclear Hot Spring (NHS)” reactor could operate solely on natural forces without complex man-made coolant circulation equipment and human-operated control systems. The cheap, unlimited supply of energy from nuclear energy could change the geopolitics forever, and finally eliminate the root-causes of most international and regional conflicts.

关键词： natural safety reactor full power natural circulation sustainable world economy

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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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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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致力项目开发点燃发展引擎——多种核能与核技术新项目开发概要

毛晓明

《中国工程科学》 2012年第14卷第8期页码 14-16

摘要：

作为中国核工程开发海外市场的旗舰，中原对外工程有限公司将项目开发作为发展引擎，在百万千瓦级核电项目开发、研究性核反应堆项目开发、多功能医院中子照射器开发研究及多用途模块式小型反应堆项目开发工作中不懈努力，为和平利用核能、核技术做出贡献。

关键词：百万千瓦级核电项目研究性核反应堆医院中子照射器模块式小型反应堆

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秦山三期（重水堆）核电站工程建设和重大技术创新

中核集团秦山第三核电有限公司

《中国工程科学》 2008年第10卷第3期页码 73-86

摘要：

秦山三期重水堆核电站是我国首座商用重水堆核电站，也是中国和加拿大两国政府间迄今最大的贸易项目。业主秦山第三核电有限公司在工程建设、调试及自主运行的过程中，坚持自主创新管理，有效实施工程质量、进度和投资三大控制；并在消化吸收CANDU-6技术的基础上进行改进，提高机组的安全性和可靠性。工程的建设实践，使我国核电工程管理在已有的基础上，基本实现了程序化、信息化的规范管理并与国际接轨。工程建成后，在保证机组安全稳定运行的基础上又进行了多项技术改进和创新，使机组性能持续提高。在人才培养方面，注重培育企业文化，强化人员培训，建立起员工培训与工程建设互相促进的良性循环机制。秦山三期工程在核电项目管理水平的提高和发展，可为推动我国核电发展和大型引进工程的规范化管理提供借鉴。

关键词：秦山三期重水堆核电站工程建设技术创新

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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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美国高温气冷堆现状 Review

Andrew C. Kadak

《工程（英文）》 2016年第2卷第1期页码 119-123 doi: 10.1016/J.ENG.2016.01.026

摘要：

2005 年，美国国会通过了《2005年能源政策法案》，该法案授权在2021年之前建造和运行一个高温气冷堆(HTGR)。在美国国内专家对未来核技术发展方向进行了多年的研究后，该法案才得以通过。作为该法案的结果，美国国会设立了名为“下一代核电站”的项目，这是一种为制氢提供工艺用热的HTGR。尽管HTGR被寄予了很高的期望，但其现状仅限于完成关于先进燃料、石墨和其他材料的研究计划，并不是如国会在2005年提出的建造一个示范电站。HTGR 发展目标降低背后有许多原因，包括：用于研究的政府资金不足，对反应堆不切实际的高温要求，对“氢”经济需求的延迟，来自轻水冷却的小型模块反应堆的竞争，业主公司对新技术的兴趣较低，美国天然气价格过低，以及美国对非水冷反应堆许可证申请的具有挑战性的流程等。

关键词：高温气冷堆下一代核电站许可证申请 (美国) 核管理委员会《2005年能源政策法案》研究现状

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中国新一代核能核燃料总体发展战略研究

李冠兴,周邦新,肖岷,焦拥军,任忠鸣

《中国工程科学》 2019年第21卷第1期页码 6-11 doi: 10.15302/J-SSCAE-2019.01.002

摘要：

本文深入分析和研究了国内外压水堆燃料和材料技术，快堆及其他先进堆燃料技术以及核燃料循环相关材料技术发展的现状和趋势，提出了我国压水堆、快堆及其他先进堆核燃料与材料，以及核燃料循环材料发展的目标、发展路线图和重点任务。压水堆是我国21世纪相当长时间内核能发电及能源结构转型的主力堆型。作为压水堆发展重要支撑的核燃料及材料基本实现了国产化，但还没有实现品牌自主化。我国的快堆及快堆核燃料发展面临机遇和挑战，核燃料循环产业面临重大历史性发展机遇和巨大挑战。最后对我国的压水堆、快堆、其他先进堆型核燃料及材料，以及我国核燃料循环材料的发展提出了建议。

关键词：核燃料核材料轻水堆压水堆快堆燃料循环