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Nuclear Materials and Energy 中科院2区 JCR:Q1 SCIE EI JST
发文量 2,096
被引量 28,777
影响因子(2025版) 2.609

The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. The emphasis of the journal is on materials employed in reactors where they are exposed to extreme environments in terms of radiation, temperature and corrosive conditions. The main topics are: Fusion reactor materials, including plasma-facing components, such as divertors, limiters blankets, and the first wall. Material erosion and transport in the boundary of fusion plasmas and its effect on the incident plasma conditions. Interaction of plasmas, ion beams, electron beams and intense heat fluxes with materials with emphasis on lifetime, tritium retention and permeation, and structural stability. Fission reactor materials, including fuels, cladding, moderator, control rods, core structures, pressure vessels, but excluding fuel cycle from mining to nuclear waste. Fusion and fission reactor materials enduring radiation doses at very high temperature far beyond the capability of materials now available for components. Materials behaviour in the interaction with reactor coolants during normal operation and in accidental conditions. Materials behaviour addressing the release of fuel, activated dust and reaction products during accidental conditions, and the physical and chemical interactions of reactor core and containment materials. Neutron and charged particle radiation effects in materials, including defects, gas retention and permeation, transmutations, microstructural changes, phase changes and macroscopic properties.

  • 主办单位: ELSEVIER
  • 出版地区: AMSTERDAM
  • 出版周期: 季刊
  • 别名: NUCL MATER ENERGY;Nucl. Mater. Energy;NUCLEAR MATERIALS AND ENERGY
  • 创刊时间: 2015年
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期刊信息

  • 主办单位:ELSEVIER
  • 主  编:Marjorie Bertolus
  • 地  址: AMSTERDAM

期刊简介

The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. The emphasis of the journal is on materials employed in reactors where they are exposed to extreme environments in terms of radiation, temperature and corrosive conditions. The main topics are: Fusion reactor materials, including plasma-facing components, such as divertors, limiters blankets, and the first wall. Material erosion and transport in the boundary of fusion plasmas and its effect on the incident plasma conditions. Interaction of plasmas, ion beams, electron beams and intense heat fluxes with materials with emphasis on lifetime, tritium retention and permeation, and structural stability. Fission reactor materials, including fuels, cladding, moderator, control rods, core structures, pressure vessels, but excluding fuel cycle from mining to nuclear waste. Fusion and fission reactor materials enduring radiation doses at very high temperature far beyond the capability of materials now available for components. Materials behaviour in the interaction with reactor coolants during normal operation and in accidental conditions. Materials behaviour addressing the release of fuel, activated dust and reaction products during accidental conditions, and the physical and chemical interactions of reactor core and containment materials. Neutron and charged particle radiation effects in materials, including defects, gas retention and permeation, transmutations, microstructural changes, phase changes and macroscopic properties.