Materials RD for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group
Materials RD for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group
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DOI：
10.1016/j.fusengdes.2013.11.007
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发表时间：
2014-10
影响因子：
1.7
通讯作者：
D. Stork;P. Agostini;J. Boutard;D. Buckthorpe;E. Diegele;S. Dudarev;C. English;G. Federici;M. Gilbert;S. Gonzalez;Á. Ibarra;C. Linsmeier;A. Puma;G. Marbach;L. Packer;B. Raj;M. Rieth;M. Tran;D. J. Ward;S. Zinkle
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文献类型：
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作者：
D. Stork;P. Agostini;J. Boutard;D. Buckthorpe;E. Diegele;S. Dudarev;C. English;G. Federici;M. Gilbert;S. Gonzalez;Á. Ibarra;C. Linsmeier;A. Puma;G. Marbach;L. Packer;B. Raj;M. Rieth;M. Tran;D. J. Ward;S. Zinkle
欧盟聚变计划的“材料评估小组”（MAG）的调查结果，评估准备的结构，等离子体面对（PF）和高热通量（HHF）材料的演示，进行了讨论。这些都被纳入欧盟聚变动力路线图[1]，并决定在21世纪30年代初建造DEMO。该方法使用基于项目和系统工程的方法，技术准备水平的概念，并考虑从裂变反应堆材料开发中吸取的经验教训。为每个演示角色确定“基线”材料，并根据与每个基线材料相关的已知限制或未知属性分析演示使命风险。制定了应对这些风险的研发方案。评估的DEMO有一个带有“启动包层”的第一阶段：包层必须承受≥2 MW yr m− 2聚变中子通量（相当于1020 dpa前壁钢损伤）。基线材料都具有显著的相关风险，因此建议开发“风险缓解材料”（RMM）。研发计划对基线和RMM进行了平行开发，直到“向下选择”点，以与DEMO包层和偏滤器工程定义的决定保持一致。ITER许可经验用于细化材料核测试的问题，并在DEMO设计最终确定之前制定论据以优化使用聚变中子（“14 MeV”）光谱的材料测试范围。一些14 MeV的测试仍然是必不可少的，路线图要求到2026年部署≥30 dpa（钢）的测试能力。沿着最低14 MeV测试计划，以及基础和面向任务的建模可以发挥的关键作用，讨论了通过在同位素或化学掺杂钢上使用裂变中子以及使用离子束进行预测试来进行的计划优化。研究方向。
The findings of the EU Fusion Programme's ‘Materials Assessment Group’ (MAG), assessing readiness of Structural, Plasma Facing (PF) and High Heat Flux (HHF) materials for DEMO, are discussed. These are incorporated into the EU Fusion Power Roadmap [1], with a decision to construct DEMO in the early 2030s.The methodology uses project-based and systems-engineering approaches, the concept of Technology Readiness Levels, and considers lessons learned from Fission reactor material development. ‘Baseline’ materials are identified for each DEMO role, and the DEMO mission risks analysed from the known limitations, or unknown properties, associated with each baseline material. R&D programmes to address these risks are developed. The DEMO assessed has a phase I with a ‘starter blanket’: the blanket must withstand ≥2 MW yr m−2fusion neutron flux (equivalent to ∼20 dpa front-wall steel damage). The baseline materials all have significant associated risks, so development of ‘Risk Mitigation Materials’ (RMM) is recommended. The R&D programme has parallel development of the baseline and RMM, up to ‘down-selection’ points to align with decisions on the DEMO blanket and divertor engineering definition. ITER licensing experience is used to refine the issues for materials nuclear testing, and arguments are developed to optimise scope of materials tests with fusion neutron (‘14 MeV’) spectra before DEMO design finalisation. Some 14 MeV testing is still essential, and the Roadmap requires deployment of a ≥30 dpa (steels) testing capability by 2026. Programme optimisation by the pre-testing with fission neutrons on isotopically- or chemically-doped steels and with ion-beams is discussed along with the minimum 14 MeV testing programme, and the key role which fundamental and mission-oriented modelling can play in orienting the research.