{"title":"Multi-dimensional condensation behavior during ingress of coolant event experiments for fusion reactors with TRACE code","authors":"Shun Nukaga, Masahiro Furuya","doi":"10.1016/j.fusengdes.2025.115107","DOIUrl":null,"url":null,"abstract":"<div><div>An Ingress of Coolant (ICE) event is defined as the intrusion of high-temperature, high-pressure coolant water into the plasma chamber of a nuclear fusion reactor. This phenomenon constitutes a critical safety concern, as it has the potential to result in the release of radioactive materials into the surrounding environment. Consequently, a proper assessment of an ICE must be made in the design of fusion reactors. Prior to the construction of ITER, the Integrated ICE Facility was constructed at the Naka Laboratory of the Japan Atomic Energy Research Institute (JAERI) in Japan to validate the computational code for the pressure suppression system in ITER against the obtained experimental data. This study examined the Integrated ICE Facility utilizing the TRACE code for two wall-thermal boundary conditions. By comparing the calculated and experimental values, it was found that the TRACE code could adequately evaluate the injected flow rate and pressure inside the plasma chamber. The discrepancy was partly attributed to the number of cells required to capture multidimensional water levels. Furthermore, it was determined that the timestep size exhibited a close relationship with the pressure within the suppression tank.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"217 ","pages":"Article 115107"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-07","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/S0920379625003047","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}
引用次数: 0
Abstract
An Ingress of Coolant (ICE) event is defined as the intrusion of high-temperature, high-pressure coolant water into the plasma chamber of a nuclear fusion reactor. This phenomenon constitutes a critical safety concern, as it has the potential to result in the release of radioactive materials into the surrounding environment. Consequently, a proper assessment of an ICE must be made in the design of fusion reactors. Prior to the construction of ITER, the Integrated ICE Facility was constructed at the Naka Laboratory of the Japan Atomic Energy Research Institute (JAERI) in Japan to validate the computational code for the pressure suppression system in ITER against the obtained experimental data. This study examined the Integrated ICE Facility utilizing the TRACE code for two wall-thermal boundary conditions. By comparing the calculated and experimental values, it was found that the TRACE code could adequately evaluate the injected flow rate and pressure inside the plasma chamber. The discrepancy was partly attributed to the number of cells required to capture multidimensional water levels. Furthermore, it was determined that the timestep size exhibited a close relationship with the pressure within the suppression tank.
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.