High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation
高剂量中子辐照的高保真离子束模拟
基本信息
- 批准号:EP/L025981/1
- 负责人:
- 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
- 起止时间:2014 至 无数据
- 项目状态:已结题
- 来源:
- 关键词:
项目摘要
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.
开发新的、先进的核反应堆概念和延长现有轻水核反应堆寿命的希望,在很大程度上取决于对辐射如何降解反应堆堆芯结构部件材料的理解。在高剂量裂变反应堆概念(GEN-4)中,结构材料必须在超过400摄氏度的温度下承受200dpa的损伤。在如此高的损伤水平下,主要的降解模式可能是由空洞膨胀和相稳定性驱动的。由于辐照引起的材料降解既是一种限制寿命的现象,也是一种验证概念的现象,因此它确实是对全世界核能发展和活力的重大挑战。传统上,了解辐射引起的材料变化的研究是通过在试验堆中进行辐射效应实验,然后进行全面的辐照后表征计划。然而,试验反应堆产生辐射损伤的速度不会比商业反应堆快得多,这意味着辐射损伤研究往往无法“走在”运行过程中发现的问题之前。一个很有希望的解决方案是使用离子辐照,它可以产生高的损伤率,很少或没有残余放射性。离子辐照的优点很多。剂量率(通常为10-3至10- 4dpa /s)远高于中子辐照(10-7至10- 8dpa /s),这意味着200 dpa可在几天或几周内达到,而不是几十年。因为几乎没有活化,所以样品没有放射性。离子辐照实验的控制要比反应堆实验好得多。在反应堆中,温度、损伤率和损伤程度的测量是困难的,导致依靠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很好地控制和监测温度,并且可以在整个辐照过程中连续测量损伤率和总损伤,并且精度很高。然而,离子辐照有几个潜在的缺点;辐照材料的体积,高损伤率对所得微观结构的影响,以及考虑反应堆中发生的重要嬗变反应的需要,例如He和h的产生。理解和建模微结构-性能关系,以及微样品制造和测试的发展,虽然不能取代整体性能测定,但有望最大限度地减少有限辐照体积的缺点。高损伤率能在多大程度上产生与反应堆条件相关的微结构是一项重大挑战,但在解决这一问题方面正在取得重大进展。解释嬗变反应的策略是同时用重离子照射目标,同时用He和/或h轰击目标。这样的过程需要在双束或三束设备中耦合多个加速器。最近,英国已经开始制定一项计划,在其道尔顿坎布里亚设施建立这样一个双梁设施,拟议的项目将支持这一活动。为了使离子辐照合格,必须尽可能地再现中子辐照后的微观结构和中子引起的宏观性质变化。这项任务最好是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制理解,同时在实验设计和理论建模中考虑到上述可能的混淆因素。
项目成果
期刊论文数量(5)
专著数量(0)
科研奖励数量(0)
会议论文数量(0)
专利数量(0)
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:
- 影响因子:0
- 作者:Wady P
- 通讯作者:Wady P
Comparison of Additive Manufactured and Conventional 316L Stainless Steels
- DOI:10.1017/s143192761500313x
- 发表时间:2015-08
- 期刊:
- 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
Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors
- DOI:10.1016/j.nme.2018.05.018
- 发表时间:2018-08
- 期刊:
- 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:0
- 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:0
- 作者:[]
- 通讯作者:[]
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Michael Preuss其他文献
Tracking the onset of plasticity in a Ni-base superalloy using in-situ High-Resolution Digital Image Correlation
使用原位高分辨率数字图像相关技术跟踪镍基高温合金中塑性的开始
- DOI:
10.1016/j.matchar.2024.114654 - 发表时间:
2025-02-01 - 期刊:
- 影响因子:5.500
- 作者:
Dongchen Hu;Albert D. Smith;David Lunt;Rhys Thomas;Michael D. Atkinson;Xiaodong Liu;Ömer Koç;Jack M. Donoghue;Zhenbo Zhang;João Quinta da Fonseca;Michael Preuss - 通讯作者:
Michael Preuss
17. BRIDGEPRS: A POWERFUL MULTI-ANCESTRY POLYGENIC RISK SCORE METHOD
- DOI:
10.1016/j.euroneuro.2022.07.108 - 发表时间:
2022-10-01 - 期刊:
- 影响因子:
- 作者:
Paul O'Reilly;Clive Hoggart;Shing Wan Choi;Michael Preuss - 通讯作者:
Michael Preuss
Evolution of Zr(Fe,Cr)<sub>2</sub> second phase particles in Zircaloy-2 under heavy ion irradiation
- DOI:
10.1016/j.jnucmat.2024.155081 - 发表时间:
2024-08-01 - 期刊:
- 影响因子:
- 作者:
Kieran Lynch;Ömer Koç;Graeme Greaves;Alexander Carruthers;Mia Maric;Michael Preuss;Aidan Cole-Baker;Philipp Frankel;Joseph Robson - 通讯作者:
Joseph Robson
Identification, classification and characterisation of hydrides in Zr alloys
Zr合金中氢化物的识别、分类和表征
- DOI:
- 发表时间:
2024 - 期刊:
- 影响因子:6
- 作者:
Mia Maric;R. Thomas;Alec Davis;D. Lunt;Jack Donoghue;Ali Gholinia;Marc De Graef;T. Ungár;Pierre Barberis;F. Bourlier;P. Frankel;P. Shanthraj;Michael Preuss - 通讯作者:
Michael Preuss
Architecting new materials with strength-ductility synergy through interphase engineering
通过界面工程构建具有强韧性协同作用的新材料
- DOI:
10.1016/j.jmst.2025.02.092 - 发表时间:
2026-01-01 - 期刊:
- 影响因子:14.300
- 作者:
Zhenbo Zhang;Emmanouil Stavroulakis;David Stewart;Michael Preuss - 通讯作者:
Michael Preuss
Michael Preuss的其他文献
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{{ truncateString('Michael Preuss', 18)}}的其他基金
MIDAS - Mechanistic understanding of Irradiation Damage in fuel Assemblies
MIDAS - 燃料组件中辐照损伤的机理理解
- 批准号:
EP/S01702X/1 - 财政年份:2019
- 资助金额:
$ 64.7万 - 项目类别:
Research Grant
Silicide-Strengthened Steel - A New Method of Wear Protection within Nuclear Environments
硅化物强化钢——核环境中磨损防护的新方法
- 批准号:
EP/R000956/1 - 财政年份:2017
- 资助金额:
$ 64.7万 - 项目类别:
Research Grant
From Processing to Simulated In-Reactor Performance of Zr Cladding.
从锆熔壳的加工到模拟反应堆内性能。
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EP/M018369/1 - 财政年份:2016
- 资助金额:
$ 64.7万 - 项目类别:
Research Grant
Dislocation-Microstructure Interaction at a Crack Tip - In Search of a Driving Force for Short Crack Growth
裂纹尖端的位错-微观结构相互作用 - 寻找短裂纹扩展的驱动力
- 批准号:
EP/M000737/1 - 财政年份:2014
- 资助金额:
$ 64.7万 - 项目类别:
Research Grant
Engineered Zircaloy Cladding Modifications for Improved Accident Tolerance of LWR Fuel
工程锆合金包壳改进可提高轻水堆燃料的事故耐受性
- 批准号:
EP/K034650/1 - 财政年份:2013
- 资助金额:
$ 64.7万 - 项目类别:
Research Grant
New Nuclear Manufacturing (NNUMAN)
新核制造(NNUMAN)
- 批准号:
EP/J021172/1 - 财政年份:2012
- 资助金额:
$ 64.7万 - 项目类别:
Research Grant
Enhancing nuclear fuel efficiency through improved understanding of irradiation damage in zirconium cladding
通过加深对锆包壳辐照损伤的了解来提高核燃料效率
- 批准号:
EP/I005420/1 - 财政年份:2011
- 资助金额:
$ 64.7万 - 项目类别:
Fellowship
Irradiation Effects on Flow Localisation in Zirconium Alloys
辐照对锆合金流动局域化的影响
- 批准号:
EP/I012346/1 - 财政年份:2011
- 资助金额:
$ 64.7万 - 项目类别:
Research Grant
Performance and Reliability of Metallic Materials for Nuclear Fission Power Generation
核裂变发电用金属材料的性能和可靠性
- 批准号:
EP/I003290/1 - 财政年份:2010
- 资助金额:
$ 64.7万 - 项目类别:
Research Grant
Strain mapping of individual grains using diffraction contrast tomography
使用衍射对比断层扫描技术绘制单个晶粒的应变图
- 批准号:
EP/F020910/1 - 财政年份:2008
- 资助金额:
$ 64.7万 - 项目类别:
Research Grant
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