V. Chatzikos , M.I. Savva , T. Vasilopoulou , I.E. Stamatelatos , D. Terentyev , A. Stankovskiy , N. Patronis , K. Mergia
{"title":"Experimental validation of transmutation products calculations in neutron irradiated tungsten","authors":"V. Chatzikos , M.I. Savva , T. Vasilopoulou , I.E. Stamatelatos , D. Terentyev , A. Stankovskiy , N. Patronis , K. Mergia","doi":"10.1016/j.fusengdes.2025.115012","DOIUrl":null,"url":null,"abstract":"<div><div>Neutron irradiation can significantly alter the elemental composition of a material by generating transmutation products through nuclear reactions between neutrons and atomic nuclei. These changes in composition can substantially impact the material's physical and mechanical properties. Therefore, accurately assessing the buildup of transmutation products in neutron-irradiated materials is essential for understanding and predicting these effects. Tungsten (W) is particularly critical for the first wall and divertor components in fusion reactors. As such, an accurate assessment of transmutation products in neutron-irradiated tungsten is crucial for the safety and lifespan of future fusion power plants. The scope of the present work is to experimentally validate calculations of transmutation products buildup in tungsten after neutron irradiation at the Materials Test Reactor (MTR) BR-2 at SCK CEN, Belgium. Tungsten specimens were irradiated to doses of 0.12 and 0.19 displacements per atom (dpa) within the temperature range of 600 to 1200 °C. Nuclide inventory calculations were performed using the FISPACT-II code and the TENDL-2019 cross-section library. <em>γ</em>-ray spectroscopy was employed to determine the specific activity levels of <span><math><mrow><msup><mrow></mrow><mn>181</mn></msup><mi>W</mi></mrow></math></span>, <span><math><mrow><msup><mrow></mrow><mn>185</mn></msup><mi>W</mi></mrow></math></span>, <span><math><mrow><msup><mrow></mrow><mn>188</mn></msup><mi>W</mi></mrow></math></span>, <span><math><mrow><msup><mrow></mrow><mn>188</mn></msup><mi>R</mi><mi>e</mi></mrow></math></span> and <span><math><mrow><msup><mrow></mrow><mn>182</mn></msup><mi>T</mi><mi>a</mi></mrow></math></span> in order to validate the transmutation products calculations for rhenium (Re), osmium (Os) and tantalum (Ta). It is shown that the theoretical calculations for Re and Os concentrations are in good agreement with the experimental data, while the Ta concentration is underestimated by a factor of approximately 1.5.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115012"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-09","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/S0920379625002121","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
Neutron irradiation can significantly alter the elemental composition of a material by generating transmutation products through nuclear reactions between neutrons and atomic nuclei. These changes in composition can substantially impact the material's physical and mechanical properties. Therefore, accurately assessing the buildup of transmutation products in neutron-irradiated materials is essential for understanding and predicting these effects. Tungsten (W) is particularly critical for the first wall and divertor components in fusion reactors. As such, an accurate assessment of transmutation products in neutron-irradiated tungsten is crucial for the safety and lifespan of future fusion power plants. The scope of the present work is to experimentally validate calculations of transmutation products buildup in tungsten after neutron irradiation at the Materials Test Reactor (MTR) BR-2 at SCK CEN, Belgium. Tungsten specimens were irradiated to doses of 0.12 and 0.19 displacements per atom (dpa) within the temperature range of 600 to 1200 °C. Nuclide inventory calculations were performed using the FISPACT-II code and the TENDL-2019 cross-section library. γ-ray spectroscopy was employed to determine the specific activity levels of , , , and in order to validate the transmutation products calculations for rhenium (Re), osmium (Os) and tantalum (Ta). It is shown that the theoretical calculations for Re and Os concentrations are in good agreement with the experimental data, while the Ta concentration is underestimated by a factor of approximately 1.5.
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.