{"title":"Study on acceptable air concentration limit in helium gas inside the test cell in fusion neutron source A-FNS","authors":"Shunsuke Kenjo , Shogo Honda , Hideya Nakanishi , Saerom Kwon , Makoto Oyaidzu , Kentaro Ochiai , Satoshi Sato , Kai Masuda","doi":"10.1016/j.fusengdes.2025.115445","DOIUrl":null,"url":null,"abstract":"<div><div>Fusion Neutron Source A-FNS, which accelerates a deuteron beam on a liquid lithium (Li) target, aims to acquire material properties under neutron irradiation—essential for the realization of the JApan’s DEMOnstration fusion reactor. Neutron irradiation is performed in a Test Cell (TC) surrounded by thick concrete shielding. Since the atmospheric condition inside the TC consists of helium gas at negative pressure, some air in-leakage into the TC is inevitable. In this study, we evaluated acceptable air concentrations in helium gas within the TC and air in-leak rates to prevent Li ignition and atmospheric activation. Based on our recent R&D activity, we established an air concentration limit in helium gas as 5 vol.% to prevent Li ignition in the event of a Li leak. Air activation calculations using the FISPACT code reveal that the tritium production amount (2.8 × 10<sup>6</sup> Bq/h) is the main contribution to the tritium inventory in the TC. This tritium is primarily produced via the <sup>14</sup>N (n,t) reactions. The air in-leak rates were determined by modeling the helium purification process and developing start-up procedures for the liquid Li target system and TC. Based on these findings, we proposed the design requirements for the TC, interlock (Machine Protection System), and detritiation system in the circulating helium purifier.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115445"},"PeriodicalIF":2.0000,"publicationDate":"2025-09-18","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/S0920379625006416","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
Fusion Neutron Source A-FNS, which accelerates a deuteron beam on a liquid lithium (Li) target, aims to acquire material properties under neutron irradiation—essential for the realization of the JApan’s DEMOnstration fusion reactor. Neutron irradiation is performed in a Test Cell (TC) surrounded by thick concrete shielding. Since the atmospheric condition inside the TC consists of helium gas at negative pressure, some air in-leakage into the TC is inevitable. In this study, we evaluated acceptable air concentrations in helium gas within the TC and air in-leak rates to prevent Li ignition and atmospheric activation. Based on our recent R&D activity, we established an air concentration limit in helium gas as 5 vol.% to prevent Li ignition in the event of a Li leak. Air activation calculations using the FISPACT code reveal that the tritium production amount (2.8 × 106 Bq/h) is the main contribution to the tritium inventory in the TC. This tritium is primarily produced via the 14N (n,t) reactions. The air in-leak rates were determined by modeling the helium purification process and developing start-up procedures for the liquid Li target system and TC. Based on these findings, we proposed the design requirements for the TC, interlock (Machine Protection System), and detritiation system in the circulating helium purifier.
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.