Critical Analysis of Spent Fuel Structure in Radionuclide Release

放射性核素释放中乏燃料结构的批判性分析

基本信息

  • 批准号:
    EP/N017374/1
  • 负责人:
  • 金额:
    $ 152万
  • 依托单位:
  • 依托单位国家:
    英国
  • 项目类别:
    Fellowship
  • 财政年份:
    2016
  • 资助国家:
    英国
  • 起止时间:
    2016 至 无数据
  • 项目状态:
    已结题

项目摘要

As a result of 60 years of using nuclear energy in civil and defence operations, the UK has generated a large legacy of nuclear waste, with a total volume capable of filling Wembley Stadium (450,000m3). The hazards posed to the general public from the radiation arising from this waste make its disposal extremely challenging; any solution must be long-lived as the waste will be radioactive for more than 100,000 years. For this reason, the Governments of several countries, including the UK, propose that the long-term disposal of this waste should be in a deep geological facility, several hundreds of metres below the ground. The formal term for an engineered geological disposal site is a Geological Disposal Facility (GDF). This man-made facility will be used to isolate the waste from future populations by using multiple layers of containment carefully designed to prevent radioactive elements (radionuclides) from entering the underground rock environment and eventually reaching the surface. Arguably, the most important part of the GDF is the nuclear waste itself; the release of radionuclides to the environment is controlled by the interaction of groundwater with the waste - if this material can be shown to be particularly durable in the presence of ground water, the release of radionuclides will be very small and the risk to future populations from the GDF will be low. The focus of my Fellowship is on understanding the release of radionuclides from one particular type of nuclear waste, known as spent fuel, upon contact with groundwater. Many countries are planning to dispose of spent fuel in a GDF (e.g. Sweden, Finland), however the spent fuel in the UK is unique, because it originates from nuclear reactors that only exist in the UK. This is problematic because the potential behaviour of this material when it comes into contact with groundwater is poorly understood; this gives rise to uncertainty in the long-term safety of this material in a GDF. Therefore, the goal of this Fellowship is to develop an understanding of UK spent fuel, of how its structure and chemistry affect the release of radionuclides upon contact with water, and to evaluate its performance compared to other spent fuel types. Because real spent fuel is extremely hazardous, the Fellowship research team will develop an analogue for spent fuel, known as HIP-SIMFUEL, using state-of-the-art material processing technologies. The development of HIP-SIMFUEL, which will resemble spent fuel more closely than any other analogue currently available, represents a significant advancement for scientists working in the field of spent fuel research. Using HIP-SIMFUEL and a suite of advanced, high-resolution microscopy techniques, we will build the first ever atomic-scale understanding of the structure and chemistry of UK spent fuel, and we will develop novel imaging techniques to assess the role of these features in the mechanisms and rate of radionuclide release to groundwater. The results from experiments with HIP-SIMFUEL will be compared with those from real spent fuel particles; my team will examine particles of spent fuel that were discharged to the environment during the Chernobyl accident, which have subsequently been leached by natural groundwater for many years.My Fellowship is particularly timely, given the UK Government's ongoing task of selecting a site for the disposal facility. The research represents a significant step in the understanding of the long-term performance of nuclear waste in the GDF, will enhance predictive models of future GDF behaviour and will help optimise the design of the containment system. Ultimately, this will lead to enhanced safety of the long-term management of nuclear waste in the UK and worldwide, and will increase public confidence of geological disposal concepts.
由于60年来在民用和国防行动中使用核能,英国产生了大量的核废料,其总量足以填满温布利体育场(45万立方米)。这些废物产生的辐射对公众造成的危害使其处置极具挑战性;任何解决方案都必须是长期的,因为这些废物的放射性将超过10万年。为此,包括联合王国在内的若干国家的政府提议,这种废物的长期处置应在地下数百米的深层地质设施中进行。工程地质处置场的正式术语是地质处置设施(GDF)。这一人造设施将通过使用精心设计的多层密封装置,防止放射性元素(放射性核素)进入地下岩石环境并最终到达地表,从而将废物与未来人口隔离。可以说,GDF最重要的部分是核废料本身;放射性核素向环境的释放是由地下水与废料的相互作用控制的-如果这种材料在地下水存在的情况下特别耐用,则放射性核素的释放将非常小,GDF对未来人口的风险也将很低。我的研究金的重点是了解一种特定类型的核废料(称为乏燃料)在与地下水接触时释放的放射性核素。许多国家计划在GDF中处置乏燃料(例如瑞典、芬兰),但英国的乏燃料是独一无二的,因为它来自仅在英国存在的核反应堆。这是有问题的,因为这种材料与地下水接触时的潜在行为知之甚少;这导致了GDF中这种材料的长期安全性的不确定性。因此,该研究金的目标是加深对联合王国乏燃料的了解,了解其结构和化学性质如何影响与水接触时放射性核素的释放,并评价其与其他类型乏燃料相比的性能。由于真实的乏燃料极其危险,研究金研究小组将利用最先进的材料加工技术开发一种乏燃料模拟物,称为HIP-SIMFUEL。HIP-SIMFUEL的开发将比现有的任何其他类似物更接近乏燃料,这对从事乏燃料研究领域的科学家来说是一个重大进步。使用HIP-SIMFUEL和一套先进的高分辨率显微镜技术,我们将建立英国乏燃料结构和化学的第一个原子尺度的理解,我们将开发新的成像技术,以评估这些功能的作用机制和放射性核素释放到地下水的速率。HIP-SIMFUEL的实验结果将与真实的乏燃料颗粒的实验结果进行比较;我的小组将检查切尔诺贝利事故期间排放到环境中的乏燃料颗粒,这些颗粒随后被天然地下水沥滤多年。该研究是了解GDF中核废料长期性能的重要一步,将增强未来GDF行为的预测模型,并将有助于优化安全壳系统的设计。最终,这将提高英国和世界范围内核废物长期管理的安全性,并将提高公众对地质处置概念的信心。

项目成果

期刊论文数量(10)
专著数量(0)
科研奖励数量(0)
会议论文数量(0)
专利数量(0)
A new approach to the immobilisation of technetium and transuranics: Co-disposal in a zirconolite ceramic matrix
固定锝和超铀的新方法:在锆英石陶瓷基质中的共同处置
  • DOI:
    10.1016/j.jnucmat.2019.151885
  • 发表时间:
    2020
  • 期刊:
  • 影响因子:
    3.1
  • 作者:
    Bailey D
  • 通讯作者:
    Bailey D
Ce and U speciation in wasteforms for thermal treatment of plutonium bearing wastes, probed by L 3 edge XANES
通过 L 3 边缘 XANES 探测含钚废物热处理废物中 Ce 和 U 的形态
Investigation of the role of Mg and Ca in the structure and durability of aluminoborosilicate glass
  • DOI:
    10.1016/j.jnoncrysol.2019.03.003
  • 发表时间:
    2019-05
  • 期刊:
  • 影响因子:
    3.5
  • 作者:
    D. Backhouse;C. Corkhill;N. Hyatt;R. Hand
  • 通讯作者:
    D. Backhouse;C. Corkhill;N. Hyatt;R. Hand
An Investigation of Iodovanadinite Wasteforms for the Immobilisation of Radio-Iodine and Technetium
  • DOI:
    10.3390/ceramics6030111
  • 发表时间:
    2023-09-01
  • 期刊:
  • 影响因子:
    2.8
  • 作者:
    Bailey,Daniel J.;Johnstone,Erik V.;Hyatt,Neil C.
  • 通讯作者:
    Hyatt,Neil C.
Synthesis, characterisation and corrosion behaviour of simulant Chernobyl nuclear meltdown materials
  • DOI:
    10.1038/s41529-020-0108-z
  • 发表时间:
    2020-01-30
  • 期刊:
  • 影响因子:
    5.1
  • 作者:
    Barlow, Sean T.;Bailey, Daniel J.;Corkhill, Claire L.
  • 通讯作者:
    Corkhill, Claire L.
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Claire Louise Corkhill其他文献

Claire Louise Corkhill的其他文献

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{{ truncateString('Claire Louise Corkhill', 18)}}的其他基金

Platform for Long-term Experimental Investigation of Alteration in Disposal Environments and Storage - PLEIADES
处置环境和储存改变的长期实验研究平台 - PLEIADES
  • 批准号:
    EP/V035215/1
  • 财政年份:
    2021
  • 资助金额:
    $ 152万
  • 项目类别:
    Research Grant
HADES: A User Facility for High Activity Decommissioning Engineering Science
HADES:高活性退役工程科学的用户设施
  • 批准号:
    EP/T011424/1
  • 财政年份:
    2020
  • 资助金额:
    $ 152万
  • 项目类别:
    Research Grant
Isolation of 14C species from spent ion exchange resins and their stabilisation
从废离子交换树脂中分离 14C 物质及其稳定化
  • 批准号:
    EP/S032959/1
  • 财政年份:
    2019
  • 资助金额:
    $ 152万
  • 项目类别:
    Research Grant
Simulated Used Nuclear Fuel Dissolution as a Function of Fuel Chemistry and Near Field Conditions
模拟用过的核燃料溶解作为燃料化学和近场条件的函数
  • 批准号:
    EP/R006075/1
  • 财政年份:
    2018
  • 资助金额:
    $ 152万
  • 项目类别:
    Research Grant
CHaracterisation, Imaging and MaPping of fuel debris for safe retrieval (CHIMP)
用于安全检索的燃料碎片的表征、成像和绘图 (CHIMP)
  • 批准号:
    EP/R01924X/1
  • 财政年份:
    2017
  • 资助金额:
    $ 152万
  • 项目类别:
    Research Grant

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