Hao Ding , Daogang Lu , Danting Sui , Xiao Luo , Kunjun Han
{"title":"采用简化控制策略的超临界二氧化碳直接冷却微反应器系统的瞬态特性和关键参数调整范围","authors":"Hao Ding , Daogang Lu , Danting Sui , Xiao Luo , Kunjun Han","doi":"10.1016/j.pnucene.2024.105533","DOIUrl":null,"url":null,"abstract":"<div><div>The combination of supercritical carbon dioxide (SCO<sub>2</sub>) Brayton cycle and microreactor is a promising technology. SCO<sub>2</sub> direct-cooled microreactor system takes advantages of compact system design and high efficiency, which can be applied in various scenes. Although the design SCO<sub>2</sub> Brayton cycle system is already compact, the control rods in reactor core still results in relatively large design size of the reactor. Considering relatively high negative temperature coefficient of reactor core and fast response characteristics of SCO<sub>2</sub> Brayton cycle, simplified control strategies are proposed in this paper to reduce the number of control rods in the reactor, thus decreasing the diameter of the reactor. Aimed towards the design of SCO<sub>2</sub> cooled floating nuclear power plant (SCFNP),the simplified control strategies are proposed. Then, adjustment ranges of system key parameters with different control strategies are simulated, and comparisons between them in various aspects are performed. According to the results, inventory control, shaft speed control and bypass valve control are proved to be able to adjust reactor power effectively instead of control rods. When applied shaft speed control and bypass valve control, system maximum temperature obviously exceeds the design temperature, which is about 12% and 20% respectively. What's more, inventory control and shaft speed control take about six times longer than bypass control to stabilized the system parameters. Besides, advantages and disadvantages are concluded of the three different control strategies, which can be used as reference of the control system design for SCO<sub>2</sub> direct-cooled microreactor system.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"179 ","pages":"Article 105533"},"PeriodicalIF":3.3000,"publicationDate":"2024-11-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Transient characteristics and adjustment ranges of key parameters in supercritical CO2 direct-cooled microreactor system with simplified control strategies\",\"authors\":\"Hao Ding , Daogang Lu , Danting Sui , Xiao Luo , Kunjun Han\",\"doi\":\"10.1016/j.pnucene.2024.105533\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The combination of supercritical carbon dioxide (SCO<sub>2</sub>) Brayton cycle and microreactor is a promising technology. SCO<sub>2</sub> direct-cooled microreactor system takes advantages of compact system design and high efficiency, which can be applied in various scenes. Although the design SCO<sub>2</sub> Brayton cycle system is already compact, the control rods in reactor core still results in relatively large design size of the reactor. Considering relatively high negative temperature coefficient of reactor core and fast response characteristics of SCO<sub>2</sub> Brayton cycle, simplified control strategies are proposed in this paper to reduce the number of control rods in the reactor, thus decreasing the diameter of the reactor. Aimed towards the design of SCO<sub>2</sub> cooled floating nuclear power plant (SCFNP),the simplified control strategies are proposed. Then, adjustment ranges of system key parameters with different control strategies are simulated, and comparisons between them in various aspects are performed. According to the results, inventory control, shaft speed control and bypass valve control are proved to be able to adjust reactor power effectively instead of control rods. When applied shaft speed control and bypass valve control, system maximum temperature obviously exceeds the design temperature, which is about 12% and 20% respectively. What's more, inventory control and shaft speed control take about six times longer than bypass control to stabilized the system parameters. Besides, advantages and disadvantages are concluded of the three different control strategies, which can be used as reference of the control system design for SCO<sub>2</sub> direct-cooled microreactor system.</div></div>\",\"PeriodicalId\":20617,\"journal\":{\"name\":\"Progress in Nuclear Energy\",\"volume\":\"179 \",\"pages\":\"Article 105533\"},\"PeriodicalIF\":3.3000,\"publicationDate\":\"2024-11-20\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Progress in Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0149197024004839\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197024004839","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Transient characteristics and adjustment ranges of key parameters in supercritical CO2 direct-cooled microreactor system with simplified control strategies
The combination of supercritical carbon dioxide (SCO2) Brayton cycle and microreactor is a promising technology. SCO2 direct-cooled microreactor system takes advantages of compact system design and high efficiency, which can be applied in various scenes. Although the design SCO2 Brayton cycle system is already compact, the control rods in reactor core still results in relatively large design size of the reactor. Considering relatively high negative temperature coefficient of reactor core and fast response characteristics of SCO2 Brayton cycle, simplified control strategies are proposed in this paper to reduce the number of control rods in the reactor, thus decreasing the diameter of the reactor. Aimed towards the design of SCO2 cooled floating nuclear power plant (SCFNP),the simplified control strategies are proposed. Then, adjustment ranges of system key parameters with different control strategies are simulated, and comparisons between them in various aspects are performed. According to the results, inventory control, shaft speed control and bypass valve control are proved to be able to adjust reactor power effectively instead of control rods. When applied shaft speed control and bypass valve control, system maximum temperature obviously exceeds the design temperature, which is about 12% and 20% respectively. What's more, inventory control and shaft speed control take about six times longer than bypass control to stabilized the system parameters. Besides, advantages and disadvantages are concluded of the three different control strategies, which can be used as reference of the control system design for SCO2 direct-cooled microreactor system.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.