Vojtěch Smolík , Mikhail Khokhlov , Axel Lorenz , Samuel Lazerson , Victor Bykov , Paul McNeely , W7-X team
{"title":"W-7X初壁石墨瓦在直接NBI载荷下的热结构分析","authors":"Vojtěch Smolík , Mikhail Khokhlov , Axel Lorenz , Samuel Lazerson , Victor Bykov , Paul McNeely , W7-X team","doi":"10.1016/j.fusengdes.2025.115178","DOIUrl":null,"url":null,"abstract":"<div><div>Thermo-mechanical analysis of the Wendelstein 7-X neutral beam dump is presented focusing on failure phenomena resulting from strong impulsive thermal loading of the graphite tiles. One of the plasma heating systems of the Wendelstein 7-X stellarator is Neutral Beam Injection (NBI). There are two NBI boxes with currently a total injected hydrogen beam power of 7 MW and a pulse length up to 5 s. Each NBI box can be operated with four positive ion neutral injectors (PINI). A total of three PINIs were used simultaneously in the last operation campaign in 2022. NBI is highly important for the W7-X physics program, thus increasing NBI power is planned in the next operation phase. A portion of the NBI power passes through the plasma, creating a region of the first wall (FW) with a significantly increased heat load. This region, called the beam dump, could be a limiting factor for the NBI pulse length and thus it requires a precise remodeling of all constituents before the 2024/2025 operation phases to prevent repeated structural damage to this area. Since the graphite tiles are attached by multiple bolts to the CuCrZr heat sinks, the thermal expansion of graphite can induce significant stress in the graphite. The safety limiting factor is the induced thermal stress in the graphite tile due to the NBI beam power load. ANSYS Mechanical model was developed, including the bolted connections, and analyzed to examine the effect of the heat load on the FW components and to evaluate the maximal allowed duration of the NBI beam. A coupled transient simulation of the thermal and structural analysis is performed. The calculation used the NBI heat loads on the FW surfaces estimated by the BEAMS3D code. This paper presents the results of the numerical analysis and the related operating limits.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115178"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Thermal and structural analysis of W-7X first wall graphite tiles under direct NBI loads\",\"authors\":\"Vojtěch Smolík , Mikhail Khokhlov , Axel Lorenz , Samuel Lazerson , Victor Bykov , Paul McNeely , W7-X team\",\"doi\":\"10.1016/j.fusengdes.2025.115178\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Thermo-mechanical analysis of the Wendelstein 7-X neutral beam dump is presented focusing on failure phenomena resulting from strong impulsive thermal loading of the graphite tiles. One of the plasma heating systems of the Wendelstein 7-X stellarator is Neutral Beam Injection (NBI). There are two NBI boxes with currently a total injected hydrogen beam power of 7 MW and a pulse length up to 5 s. Each NBI box can be operated with four positive ion neutral injectors (PINI). A total of three PINIs were used simultaneously in the last operation campaign in 2022. NBI is highly important for the W7-X physics program, thus increasing NBI power is planned in the next operation phase. A portion of the NBI power passes through the plasma, creating a region of the first wall (FW) with a significantly increased heat load. This region, called the beam dump, could be a limiting factor for the NBI pulse length and thus it requires a precise remodeling of all constituents before the 2024/2025 operation phases to prevent repeated structural damage to this area. Since the graphite tiles are attached by multiple bolts to the CuCrZr heat sinks, the thermal expansion of graphite can induce significant stress in the graphite. The safety limiting factor is the induced thermal stress in the graphite tile due to the NBI beam power load. ANSYS Mechanical model was developed, including the bolted connections, and analyzed to examine the effect of the heat load on the FW components and to evaluate the maximal allowed duration of the NBI beam. A coupled transient simulation of the thermal and structural analysis is performed. The calculation used the NBI heat loads on the FW surfaces estimated by the BEAMS3D code. This paper presents the results of the numerical analysis and the related operating limits.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"218 \",\"pages\":\"Article 115178\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-05-24\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625003758\",\"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":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625003758","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}
Thermal and structural analysis of W-7X first wall graphite tiles under direct NBI loads
Thermo-mechanical analysis of the Wendelstein 7-X neutral beam dump is presented focusing on failure phenomena resulting from strong impulsive thermal loading of the graphite tiles. One of the plasma heating systems of the Wendelstein 7-X stellarator is Neutral Beam Injection (NBI). There are two NBI boxes with currently a total injected hydrogen beam power of 7 MW and a pulse length up to 5 s. Each NBI box can be operated with four positive ion neutral injectors (PINI). A total of three PINIs were used simultaneously in the last operation campaign in 2022. NBI is highly important for the W7-X physics program, thus increasing NBI power is planned in the next operation phase. A portion of the NBI power passes through the plasma, creating a region of the first wall (FW) with a significantly increased heat load. This region, called the beam dump, could be a limiting factor for the NBI pulse length and thus it requires a precise remodeling of all constituents before the 2024/2025 operation phases to prevent repeated structural damage to this area. Since the graphite tiles are attached by multiple bolts to the CuCrZr heat sinks, the thermal expansion of graphite can induce significant stress in the graphite. The safety limiting factor is the induced thermal stress in the graphite tile due to the NBI beam power load. ANSYS Mechanical model was developed, including the bolted connections, and analyzed to examine the effect of the heat load on the FW components and to evaluate the maximal allowed duration of the NBI beam. A coupled transient simulation of the thermal and structural analysis is performed. The calculation used the NBI heat loads on the FW surfaces estimated by the BEAMS3D code. This paper presents the results of the numerical analysis and the related operating limits.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.