High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation
High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation
批准号:
EP/L025981/1
负责人:
Michael Preuss
金额:
$64.7万
依托单位:
依托单位国家:
英国
项目类别:
Research Grant
财政年份:
2014
资助国家:
英国
项目状态:
已结题
起止时间:
2014 至 --
中文摘要
开发新的先进核反应堆概念和延长现有轻水核反应堆寿命的前景,在很大程度上取决于了解辐射如何降解作为反应堆核心结构部件的材料。在高剂量裂变反应堆概念(Gen-4)中,结构材料必须在超过400摄氏度的温度下经受住高达200 dpa的破坏。在如此高的损伤水平下,主要的退化模式可能是由孔洞膨胀和相稳定性驱动的。由于辐射导致的材料退化既是一种限制寿命的现象,也是一种验证概念的现象,它确实是全世界核能发展和活力面临的巨大挑战。传统上,了解辐射引起的材料变化的研究是通过在测试反应堆中进行辐射效应实验,然后进行全面的辐射后表征计划来进行的。然而,测试反应堆造成辐射损害的速度不会比商业反应堆快得多,这意味着辐射损害研究往往无法在运行过程中发现的问题之前取得进展。解决这一问题的一个有希望的解决方案是使用离子辐射,这种辐射可以产生很高的损伤率,而残余放射性很少或根本没有。离子辐照有很多优点。剂量率(通常为10-3至10-4dpa/S)远高于中子照射(10-7至10-8dpa/S),这意味着200dpa可在几天或几周内达到,而不是几十年。因为几乎没有活跃性,所以样品不具有放射性。离子辐照实验的控制比反应堆实验要好得多。在反应堆中,温度、损伤率和损伤程度的测量是困难的,导致依赖于计算来确定总剂量和估计辐照温度。相比之下,离子辐照已经发展到可以非常好地控制和监测温度,并在整个辐照过程中以极高的精度连续测量损伤率和总损伤的程度。然而,离子辐照有几个潜在的缺点:辐照材料的体积,高损伤率对所产生的微观结构的影响,以及需要考虑在反应堆中发生的重要的转化反应,如产生He和H。理解和建模微观结构与性能的关系,以及微样品制备和测试的发展,虽然不能取代整体性质的确定,但有希望将有限的辐照体积的缺点降到最低。高损伤率能在多大程度上产生与反应堆条件相关的微观结构是一个重大挑战,但在解决这个问题方面正在取得重大进展。解释变形反应的策略是同时用重离子照射目标,同时用He和/或H轰击它。这样的过程需要在双束或三束设施中耦合多个加速器。最近,英国已经开始制定一项计划,在其道尔顿坎布里安设施建立这样的双束设施,拟议的项目将支持这一活动。为了使离子照射合格,有必要尽可能好地再现中子照射的微观结构和使用离子照射的中子引起的宏观性质变化。这项任务最好使用与建模紧密结合的最先进的实验技术的组合来解决,这可以产生对缺陷发展过程的机械理解,同时在实验设计和理论建模中考虑到上述可能的混杂因素。
英文摘要
The promise for developing new, advanced nuclear reactor concepts and the extension of life of existing light water nuclear reactors rests heavily on understanding how radiation degrades materials that serve as the structural components in reactor cores. In high dose fission reactor concepts (GEN-4) structural materials must survive up to 200 dpa of damage at temperatures in excess of 400C. At such high damage levels, the major degradation modes are likely to be driven by void swelling and phase stability. As materials degradation due to irradiation is both a life-limiting and a concept-validating phenomenon, it is truly the grand challenge for the growth and vitality of nuclear energy world-wide. Traditionally, research to understand radiation-induced changes in materials is conducted via radiation effects experiments in test reactors, followed by a comprehensive post-irradiation characterization plan. However, test reactors cannot create radiation damage significantly faster than that in commercial reactors, meaning that radiation damage research often cannot "get ahead" of problems discovered during operation. A promising solution to the problem is to use ion irradiation that can produce high damage rates with little or no residual radioactivity. The advantages of ion irradiation are many. Dose rates (typically 10-3 to 10-4 dpa/s) are much higher than under neutron irradiation (10-7 to 10-8 dpa/s) which means that 200 dpa can be reached in days or weeks instead of decades. Because there is little activation the samples are not radioactive. Control of ion irradiation experiments is much better than experiments in reactor. Measurement of temperature, damage rate and damage level is difficult in reactor, resulting in reliance on calculations to determine the total dose, and estimate irradiation temperature. By contrast, ion irradiations have been developed to the point where temperature is extremely well controlled and monitored, and damage rate and total damage are also measured continuously throughout the irradiation and with great accuracy. However, ion irradiation has several potential drawbacks; the volume of irradiated material, the effect of high damage rate on the resulting microstructure, and the need to account for important transmutation reactions that occur in reactor, such as the production of He and H. Understanding and modeling the microstructure-property relationship, and the development of micro-sample fabrication and testing, while not a replacement for bulk property determination, hold the promise for minimizing the drawback of limited irradiated volume. The extent to which high damage rates can produce microstructures relevant to reactor conditions is a major challenge, but significant progress is being made to address this issue.The strategy to account for transmutation reactions is to simultaneously irradiate a target with heavy ions while also bombarding it with He and/or H. Such a process requires multiple accelerators coupled in a double or triple beam facility. Recently, the UK has begun development of a plan to create such a double beam facility at its Dalton Cumbrian Facility and the proposed project will underpin this activity.To qualify ion irradiation it is necessary to reproduce as best as possible both the neutron irradiated microstructure and the neutron-induced macroscopic property changes using ion irradiation. This task is best addressed using a combination of state of the art experimental techniques closely coupled to modeling, which can yield mechanistic understanding of the defect development process, while taking into account in the experimental design and theoretical modeling the possible confounding factors mentioned above.
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Accelerated radiation damage test facility using a 5 MV tandem ion accelerator
使用 5 MV 串联离子加速器的加速辐射损伤测试设备
DOI:
10.1016/j.nima.2015.09.088
发表时间:
2016
期刊:
Accelerators, Spectrometers, Detectors and Associated Equipment
影响因子:
--
作者:
[Wady P]
通讯作者:
Wady P
DOI:
10.1017/s143192761500313x
发表时间:
2015-08
期刊:
Microscopy and Microanalysis
影响因子:
2.8
作者:
[Joven J.H. Lim;A. R. C. Malheiros;G. Bertali;C. Long;P. Freyer;M. G. Burke]
通讯作者:
Joven J.H. Lim;A. R. C. Malheiros;G. Bertali;C. Long;P. Freyer;M. G. Burke
DOI:
10.1016/j.nme.2018.05.018
发表时间:
2018-08
期刊:
Nuclear Materials and Energy
影响因子:
2.6
作者:
[A. Prasitthipayong;D. Frazer;A. Kareer;M. Abad;A. Garner;B. Jóni;T. Ungár;G. Ribárik;M. Preuss]
通讯作者:
A. Prasitthipayong;D. Frazer;A. Kareer;M. Abad;A. Garner;B. Jóni;T. Ungár;G. Ribárik;M. Preuss
Characterization of alloy 800H irradiated by neutrons and ions to 16.6 dpa
中子和离子辐照至 16.6 dpa 的 800H 合金的表征
DOI:
--
发表时间:
期刊:
影响因子:
--
作者:
[[]]
通讯作者:
[]
Heavy Ion Irradiation-induced Microstructural Evolution in the Next Generation Nuclear Material - Alloy 800H
重离子辐照引起的下一代核材料 - 合金 800H 的微观结构演化
DOI:
--
发表时间:
2016
期刊:
影响因子:
--
作者:
[[]]
通讯作者:
[]
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Zirconium alloys for high burn-up fuel in current and advanced light water-cooled reactors
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Effective Structural Unit Size in Polycrystals: Formation, Quantification and Micromechanical Behaviour
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