Pub Date : 2022-09-14DOI: 10.3389/fnuen.2022.989361
Ioannis Tsitsimpelis, T. Alton, A. West, C. J. Taylor, F. Livens, B. Lennox, M. Joyce
A technique for the in-situ localization of radioactivity is described in which the influence of γ-radiation impinging on a high-Z collimator, by which the angular response of a scintillation detector is constrained in order to identify the corresponding angular position of the radiation source, is expressed mathematically by way of a normalized sinc transform. We test this approach by examining the utility of the sinc transform to express the angular responses derived from a slot-collimated cerium bromide detector, across a variety of energy regions. Individual spectra have been acquired as a function of angle to explore how the shape of the response of the collimator-detector arrangement changes for X-rays and γ rays. A 90% improvement in localization is observed when this is defined in terms of the area described by the variance between the known location and that indicated by the response of the collimated system. This approach has the potential to improve source location accuracy and to further optimize autonomous robot exploration routines used to characterize contaminated environments associated with nuclear legacies and radiological emergencies.
{"title":"Improved localization of radioactivity with a normalized sinc transform","authors":"Ioannis Tsitsimpelis, T. Alton, A. West, C. J. Taylor, F. Livens, B. Lennox, M. Joyce","doi":"10.3389/fnuen.2022.989361","DOIUrl":"https://doi.org/10.3389/fnuen.2022.989361","url":null,"abstract":"A technique for the in-situ localization of radioactivity is described in which the influence of γ-radiation impinging on a high-Z collimator, by which the angular response of a scintillation detector is constrained in order to identify the corresponding angular position of the radiation source, is expressed mathematically by way of a normalized sinc transform. We test this approach by examining the utility of the sinc transform to express the angular responses derived from a slot-collimated cerium bromide detector, across a variety of energy regions. Individual spectra have been acquired as a function of angle to explore how the shape of the response of the collimator-detector arrangement changes for X-rays and γ rays. A 90% improvement in localization is observed when this is defined in terms of the area described by the variance between the known location and that indicated by the response of the collimated system. This approach has the potential to improve source location accuracy and to further optimize autonomous robot exploration routines used to characterize contaminated environments associated with nuclear legacies and radiological emergencies.","PeriodicalId":400400,"journal":{"name":"Frontiers in Nuclear Engineering","volume":"39 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-09-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116744526","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2022-08-12DOI: 10.3389/fnuen.2022.969171
A. Romanchuk, V. Svitelman, P. D. Blinov, A. Larina, Lurii M. Nevolin, A. V. Egorov, E. Saveleva, S. Kalmykov
Obtaining reliable thermodynamic sorption data is essential for establishing databases that can be used for the numerical safety evaluations of radioactive waste storage and disposal facilities. For this purpose, new experimental data on the sorption of U(VI), Np(V), and Eu(III) onto synthesized goethite in a wide range of experimental conditions were collected. Thermodynamic surface complexation models based on different approaches were developed and parametrized to fit a large dataset, including experimental data from the current work as well as available literature data. The proposed heuristic optimization procedure allowed identifying and comparing different parametrization variants and their uncertainties for considered models. The developed models pass the test on additional Cd(II) and Zn(II) data, simultaneously providing a reliable description of the sorption process for five cations and could probably be extended using the obtained linear free energy relationship.
{"title":"U(VI), Np(V), Eu(III) sorption on goethite: A wide-ranging multiradionuclide dataset and uncertainty-aware parametrization of surface complexation models","authors":"A. Romanchuk, V. Svitelman, P. D. Blinov, A. Larina, Lurii M. Nevolin, A. V. Egorov, E. Saveleva, S. Kalmykov","doi":"10.3389/fnuen.2022.969171","DOIUrl":"https://doi.org/10.3389/fnuen.2022.969171","url":null,"abstract":"Obtaining reliable thermodynamic sorption data is essential for establishing databases that can be used for the numerical safety evaluations of radioactive waste storage and disposal facilities. For this purpose, new experimental data on the sorption of U(VI), Np(V), and Eu(III) onto synthesized goethite in a wide range of experimental conditions were collected. Thermodynamic surface complexation models based on different approaches were developed and parametrized to fit a large dataset, including experimental data from the current work as well as available literature data. The proposed heuristic optimization procedure allowed identifying and comparing different parametrization variants and their uncertainties for considered models. The developed models pass the test on additional Cd(II) and Zn(II) data, simultaneously providing a reliable description of the sorption process for five cations and could probably be extended using the obtained linear free energy relationship.","PeriodicalId":400400,"journal":{"name":"Frontiers in Nuclear Engineering","volume":"30 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127525713","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2022-07-26DOI: 10.3389/fnuen.2022.975132
E. Buck
Any material used in a nuclear reactor facility must go through an extensive review and qualification, involving many tests and analyses. In late 2019, Alloy 617 was added to the American Society of Mechanical Engineers (ASME) code, representing the first hightemperature material cleared for commercial nuclear reactor use in the United States. since the 1990s. Without new materials, the promise of advanced fission and fusion reactor designs will not be realized (Allen et al., 2010). Similarly, the need to improve current designs and reactor components to extend reactor lifetimes may require deeper understanding of the behavior of nuclear materials under extreme conditions (Was et al., 2019). Advanced reactor concepts will require the materials and components to be resistant to 1) higher temperatures than experienced with current light water reactors, 2) corrosion with liquid salts and liquid metals, and 3) high radiation fields (neutron, ion, and gamma/beta radiation fields). Materials that need to be licensed for use in the nuclear fuel cycle from reactor operation to long-term geologic disposal undergo unparalleled scrutiny. How can this process be sped up without jeopardizing future operational safety? Modern computational predictive tools could help to accelerate development and qualification of advanced materials (Devanathan et al., 2010). However, this may not necessarily negate the requirement for extensive long-term testing of material properties to satisfy regulatory requirements. In this article, as well as discussing the role of ion irradiation studies for nuclear materials research, the potential opportunities for in-situ liquid/gas cell electron microscopy (LC-EM) and Cryo-Electron Microscopy (CryoEM) will be discussed. Ion irradiation in the transmission electron microscope (TEM) has been an important method for testing radiation damage in materials for nuclear applications, including nuclear waste forms and nuclear reactor components. Two other microscopy-based techniques, in-situ liquid/gas cell electron microscopy (LC-EM) and Cryo-Electron Microscopy (CryoEM) are currently being used in several areas in materials research, including, catalysis research, battery development, and geochemistry. Nuclear materials, whether in a nuclear reactor or disposed thousands of meters underground in a geologic repository, are subject to internal atomic displacement damage and the interaction of radiolytic species at the material’s interface. Developing the tools to OPEN ACCESS
核反应堆设施中使用的任何材料都必须经过广泛的审查和鉴定，包括许多测试和分析。2019年底，Alloy 617被添加到美国机械工程师协会(ASME)规范中，这是美国第一种获准用于商业核反应堆的高温材料。从20世纪90年代开始。没有新材料，先进裂变和聚变反应堆设计的前景将无法实现(Allen et al.， 2010)。同样，需要改进当前的设计和反应堆部件以延长反应堆寿命，可能需要更深入地了解核材料在极端条件下的行为(Was等人，2019)。先进的反应堆概念将要求材料和组件能够抵抗1)比当前轻水反应堆更高的温度，2)液态盐和液态金属的腐蚀，以及3)高辐射场(中子、离子和γ / β辐射场)。从反应堆运行到长期地质处置，需要在核燃料循环中使用的材料都要经过无与伦比的审查。如何在不危及未来操作安全的情况下加快这一过程?现代计算预测工具有助于加速先进材料的开发和鉴定(Devanathan et al.， 2010)。然而，这并不一定会否定对材料特性进行广泛的长期测试以满足法规要求的要求。在本文中，除了讨论离子辐照研究在核材料研究中的作用外，还将讨论原位液/气细胞电子显微镜(LC-EM)和低温电子显微镜(CryoEM)的潜在机会。透射电子显微镜下的离子辐照已成为检测核材料辐射损伤的重要方法，包括核废料形式和核反应堆部件。另外两种基于显微镜的技术，原位液/气电池电子显微镜(LC-EM)和低温电子显微镜(CryoEM)目前被用于材料研究的几个领域，包括催化研究、电池开发和地球化学。无论是在核反应堆中还是在地下数千米的地质储存库中处置的核材料，都受到内部原子位移损伤和材料界面上放射性溶解物质的相互作用的影响。开发开放获取的工具
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Pub Date : 2022-07-13DOI: 10.3389/fnuen.2022.945270
S. Dudarev
The 1992 United Nations Rio de Janeiro declaration (United Nations, 1992) states that “Human beings are at the centre of concerns for sustainable development. They are entitled to a healthy and productive life in harmony with nature.” This brief affirmation highlights the implications from the impact of growing human population on the environment (Cartledge, 1995; MacKay, 2009), manifested in the notion of climate emergency (Ripple et al., 2020). Nuclear power offers progressive options to mitigate global warming and other effects of climate change, with the International Energy Agency (IEA) suggesting that the nuclear energy generation currently eliminates between 1.3 and 2.6 giga-tonnes of CO2 emissions from the power sector each year, depending on whether it is assumed that it replaces gasor coal-fired power plants. The IEA’s 2015Technology Roadmap (IEA, 2015) report noted that tomeet the Paris Agreement target of global temperature not rising by more than 2°C, the world nuclear power generation capacity needs to increase to 930 GW in 2050. For comparison, the Smart Energy Europe analysis projected the European nuclear power generation capacity in 2050 to the level of 105 GW (Connolly et al., 2016), against the current levels of 61.3 GW in France, 9 GW in the United Kingdom, raising to 24 GW by 2050 (UK Government, 2022), and 4.3 GW in Germany, down from the 2021 level of 7.4 GW. Comparing these figures and the data for other geographical areas with the projected world total nuclear generation capacity, we observe that many new power plants are expected to be constructed in the countries where nuclear power generation technology and engineering have so far been largely unknown. This expected expansion will involve a broad range of engineering and technological challenges spanning the manufacturing of reactor components, the fabrication and extraction of fuel, the development of efficient coolant and heat transfer technology, the reactor assembly schedules, the establishment of supporting hot cell and waste processing facilities, and the technology for scheduled and unscheduled remote maintenance and operation, enabling the reactor systems to reliably function over long periods of time. All the presently operating commercial nuclear reactors use fissile nuclear fuel, containing isotopes of uranium and other actinide elements. On the other hand, fusion power generation, an area of active development and innovation worldwide, aims to use light fusable chemical elements, for example the deuterium and tritium isotopes of hydrogen (Pearson and Takeda, 2020; Prager and Najmabadi, 2020). Fusion technology presents a range of scientific and engineering challenges that need to be addressed to enable the construction of a fusion power plant (Chapman and Walkden, 2020). These include the development of a reliable and safe tritium and deuterium extraction and handling technology, the integration of structural and functional materials in a power plant desig
1992年《联合国里约热内卢宣言》(United Nations, 1992)指出:“人类处于可持续发展问题的中心。他们有权享受与自然和谐相处的健康和富有成效的生活。”这一简短的肯定强调了人口增长对环境影响的影响(Cartledge, 1995;MacKay, 2009)，表现在气候紧急情况的概念上(Ripple et al.， 2020)。核能为缓解全球变暖和气候变化的其他影响提供了渐进的选择，国际能源署(IEA)表示，目前核能发电每年从电力部门消除1.3至2.6千兆吨的二氧化碳排放，具体取决于它是假设取代天然气发电厂还是燃煤发电厂。国际能源署2015年技术路线图(IEA, 2015)报告指出，要实现《巴黎协定》规定的全球气温上升不超过2°C的目标，到2050年，世界核电装机容量需要增加到930吉瓦。相比之下，智能能源欧洲分析预测2050年欧洲核电装机容量将达到105吉瓦(Connolly等人，2016年)，而法国目前的水平为61.3吉瓦，英国为9吉瓦，到2050年将提高到24吉瓦(英国政府，2022年)，德国为4.3吉瓦，低于2021年的7.4吉瓦水平。将这些数字和其他地理区域的数据与预计的世界总核能发电能力进行比较，我们注意到，许多新电厂预计将在迄今为止对核能发电技术和工程基本上一无所知的国家建造。这一预期的扩建将涉及广泛的工程和技术挑战，包括反应堆部件的制造、燃料的制造和提取、高效冷却剂和传热技术的开发、反应堆组装时间表、支持热电池和废物处理设施的建立，以及计划和非计划远程维护和操作的技术。使反应堆系统能够长时间可靠地运行。目前运行的所有商业核反应堆都使用含有铀和其他锕系元素同位素的可裂变核燃料。另一方面，核聚变发电是全球积极发展和创新的一个领域，其目的是利用可轻聚变的化学元素，例如氢的氘和氚同位素(Pearson和Takeda, 2020;Prager and Najmabadi, 2020)。核聚变技术提出了一系列需要解决的科学和工程挑战，以实现核聚变发电厂的建设(Chapman和Walkden, 2020)。其中包括开发可靠和安全的氚和氘提取和处理技术，在发电厂设计中整合结构和功能材料，以及在发电厂维护中广泛使用远程处理和机器人技术。但最重要的是，它是发展强大的手段来控制高温等离子体(Kodama et al.， 2001;Hender et al.， 2007)，无论是在磁约束装置中还是在脉冲(例如激光驱动)的聚变系统中，这对聚变发电厂的工程提出了突出的挑战。核电评估所涉及的基本考虑因素是其相对于使用煤炭和天然气的电力来源或太阳能和风能等可再生能源的经济竞争力(Alonso等人，2016)，以及其环境影响(Pigford, 1974;Danish et al.， 2022)。编辑和评审:Edgar C. Buck，美国太平洋西北国家实验室(DOE)
{"title":"Grand Challenges in Nuclear Engineering","authors":"S. Dudarev","doi":"10.3389/fnuen.2022.945270","DOIUrl":"https://doi.org/10.3389/fnuen.2022.945270","url":null,"abstract":"The 1992 United Nations Rio de Janeiro declaration (United Nations, 1992) states that “Human beings are at the centre of concerns for sustainable development. They are entitled to a healthy and productive life in harmony with nature.” This brief affirmation highlights the implications from the impact of growing human population on the environment (Cartledge, 1995; MacKay, 2009), manifested in the notion of climate emergency (Ripple et al., 2020). Nuclear power offers progressive options to mitigate global warming and other effects of climate change, with the International Energy Agency (IEA) suggesting that the nuclear energy generation currently eliminates between 1.3 and 2.6 giga-tonnes of CO2 emissions from the power sector each year, depending on whether it is assumed that it replaces gasor coal-fired power plants. The IEA’s 2015Technology Roadmap (IEA, 2015) report noted that tomeet the Paris Agreement target of global temperature not rising by more than 2°C, the world nuclear power generation capacity needs to increase to 930 GW in 2050. For comparison, the Smart Energy Europe analysis projected the European nuclear power generation capacity in 2050 to the level of 105 GW (Connolly et al., 2016), against the current levels of 61.3 GW in France, 9 GW in the United Kingdom, raising to 24 GW by 2050 (UK Government, 2022), and 4.3 GW in Germany, down from the 2021 level of 7.4 GW. Comparing these figures and the data for other geographical areas with the projected world total nuclear generation capacity, we observe that many new power plants are expected to be constructed in the countries where nuclear power generation technology and engineering have so far been largely unknown. This expected expansion will involve a broad range of engineering and technological challenges spanning the manufacturing of reactor components, the fabrication and extraction of fuel, the development of efficient coolant and heat transfer technology, the reactor assembly schedules, the establishment of supporting hot cell and waste processing facilities, and the technology for scheduled and unscheduled remote maintenance and operation, enabling the reactor systems to reliably function over long periods of time. All the presently operating commercial nuclear reactors use fissile nuclear fuel, containing isotopes of uranium and other actinide elements. On the other hand, fusion power generation, an area of active development and innovation worldwide, aims to use light fusable chemical elements, for example the deuterium and tritium isotopes of hydrogen (Pearson and Takeda, 2020; Prager and Najmabadi, 2020). Fusion technology presents a range of scientific and engineering challenges that need to be addressed to enable the construction of a fusion power plant (Chapman and Walkden, 2020). These include the development of a reliable and safe tritium and deuterium extraction and handling technology, the integration of structural and functional materials in a power plant desig","PeriodicalId":400400,"journal":{"name":"Frontiers in Nuclear Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131174133","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2022-06-24DOI: 10.3389/fnuen.2022.919541
Jaime Garibay-Rodriguez, Chaofan Chen, H. Shao, L. Bilke, O. Kolditz, V. Montoya, R. Lu
In the context of nuclear waste disposal, a pre-requisite to assure their long term safety is the need for safety assessment studies aided by computational simulations, in particular, radionuclide migration from the waste to the geosphere. It is established that underground repositories for nuclear waste will provide retardation barriers for radionuclides. However, the understanding of the sorption mechanisms of radionuclides onto mineral surfaces (i.e., illite, montmorillonite) is essential for modelling their migration. On the other hand, mechanistic-based radionuclide migration simulations, typically for 1 million years, poses a computational challenge. Surrogate-based simulations can be useful to enable sensitivity/uncertainty analysis that would be prohibitive otherwise. Considering the current challenges in modelling radionuclide migration and the importance of the results and implications of these simulations (i.e., for the public and nuclear waste management agencies), it is necessary to provide appropriate computational tools in a transparent and easy-to-use way. In this work, we aim to provide such tools in a framework that combines the simulation capabilities of OpenGeoSys6 for radionuclide migration and the approachable nature of Project Jupyter (i.e., JupyterLab), which provides a modular web-based environment for development, simulation and data. In this way, we aim to promote the collaborative research of radionuclide migration assessment and, at the same time, to guarantee the availability and reproducibility of the scientific outcome through the OpenGeoSys initiative.
{"title":"Computational Framework for Radionuclide Migration Assessment in Clay Rocks","authors":"Jaime Garibay-Rodriguez, Chaofan Chen, H. Shao, L. Bilke, O. Kolditz, V. Montoya, R. Lu","doi":"10.3389/fnuen.2022.919541","DOIUrl":"https://doi.org/10.3389/fnuen.2022.919541","url":null,"abstract":"In the context of nuclear waste disposal, a pre-requisite to assure their long term safety is the need for safety assessment studies aided by computational simulations, in particular, radionuclide migration from the waste to the geosphere. It is established that underground repositories for nuclear waste will provide retardation barriers for radionuclides. However, the understanding of the sorption mechanisms of radionuclides onto mineral surfaces (i.e., illite, montmorillonite) is essential for modelling their migration. On the other hand, mechanistic-based radionuclide migration simulations, typically for 1 million years, poses a computational challenge. Surrogate-based simulations can be useful to enable sensitivity/uncertainty analysis that would be prohibitive otherwise. Considering the current challenges in modelling radionuclide migration and the importance of the results and implications of these simulations (i.e., for the public and nuclear waste management agencies), it is necessary to provide appropriate computational tools in a transparent and easy-to-use way. In this work, we aim to provide such tools in a framework that combines the simulation capabilities of OpenGeoSys6 for radionuclide migration and the approachable nature of Project Jupyter (i.e., JupyterLab), which provides a modular web-based environment for development, simulation and data. In this way, we aim to promote the collaborative research of radionuclide migration assessment and, at the same time, to guarantee the availability and reproducibility of the scientific outcome through the OpenGeoSys initiative.","PeriodicalId":400400,"journal":{"name":"Frontiers in Nuclear Engineering","volume":"329 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133748547","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2022-06-21DOI: 10.3389/fnuen.2022.901818
S. Pervin, S. Yeasmin, Mayeen Uddin Khandaker, A. Begum
Realizing the non-negligible health hazards due to radon exposure, the present study was carried out to measure the radon concentrations in indoor and outdoor environments of Atomic Energy Centre Dhaka (AECD), Bangladesh. A portable electrostatic radon-measuring device (RAD7) was used to determine the indoor radon levels in different laboratories of AECD, and a RAD7 detector with a stainless steel soil probe was employed to measure the soil gas radon in the surrounding areas of the AECD campus. The indoor radon concentration in various laboratories was found to vary from 11 ± 7 Bq/m3 to 360 ± 180 Bq/m3 with an average of 63 ± 33 Bq/m3. Overall, the average indoor radon level shows below the action level (300 Bq/m3) recommended by ICRP publication-126 for homes and workplaces. However, the laboratories having poor ventilation show a relatively higher radon level. The average soil gas radon concentration at different depths of 15 cm, 35 cm, and 55 cm was found to be 0.07 ± 0.01 kBq/m3, 2.31 ± 0.31 kBq/m3, and 22.5 ± 1.4 kBq/m3, respectively. The calculated average annual effective dose due to the inhalation of indoor radon in home and workplaces was found to be below the ICRP recommended value of 10 mSv/y. The present results could serve as a reference radon level in the indoor and outdoor environment in Dhaka city, Bangladesh.
{"title":"Radon Concentrations in Indoor and Outdoor Environments of Atomic Energy Centre Dhaka, Bangladesh, and Concomitant Health Hazards","authors":"S. Pervin, S. Yeasmin, Mayeen Uddin Khandaker, A. Begum","doi":"10.3389/fnuen.2022.901818","DOIUrl":"https://doi.org/10.3389/fnuen.2022.901818","url":null,"abstract":"Realizing the non-negligible health hazards due to radon exposure, the present study was carried out to measure the radon concentrations in indoor and outdoor environments of Atomic Energy Centre Dhaka (AECD), Bangladesh. A portable electrostatic radon-measuring device (RAD7) was used to determine the indoor radon levels in different laboratories of AECD, and a RAD7 detector with a stainless steel soil probe was employed to measure the soil gas radon in the surrounding areas of the AECD campus. The indoor radon concentration in various laboratories was found to vary from 11 ± 7 Bq/m3 to 360 ± 180 Bq/m3 with an average of 63 ± 33 Bq/m3. Overall, the average indoor radon level shows below the action level (300 Bq/m3) recommended by ICRP publication-126 for homes and workplaces. However, the laboratories having poor ventilation show a relatively higher radon level. The average soil gas radon concentration at different depths of 15 cm, 35 cm, and 55 cm was found to be 0.07 ± 0.01 kBq/m3, 2.31 ± 0.31 kBq/m3, and 22.5 ± 1.4 kBq/m3, respectively. The calculated average annual effective dose due to the inhalation of indoor radon in home and workplaces was found to be below the ICRP recommended value of 10 mSv/y. The present results could serve as a reference radon level in the indoor and outdoor environment in Dhaka city, Bangladesh.","PeriodicalId":400400,"journal":{"name":"Frontiers in Nuclear Engineering","volume":"14 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-06-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123934464","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2013-06-01DOI: 10.3389/fnuen.2023.1127504
K. Webb, C. Gregson, J. Holt, Bliss McLuckie, R. Orr, H. Sims, D. Woodhead, J. Hobbs, H. Steele, F. Currell, Luke Jones, S. Pimblott, R. Taylor
Over 60 samples of plutonium dioxide (PuO2) powders of varying provenance have been exposed to humid atmospheres and the hydrogen (H2) generation rates measured by gas chromatography. The effects of relative humidity (RH), specific surface area (SSA), plutonium isotopic composition (absorbed dose), and overlying atmosphere have been investigated for ‘as received’ PuO2 powders from the United Kingdom’s Thorp and Magnox reprocessing plants, high surface area powder produced in the laboratory and Magnox PuO2 that was recalcined at 800, 900 or 950°C. Hydrogen generation was shown to be susceptible to subtle influences with the most consistent results observed at 95% RH. However, it was shown that the measured (net) hydrogen decreases with decreasing RH and with atmosphere in the order: Air > argon > nitrogen. There was no clear effect of SSA, apart from with the highest SSA samples (∼40 m2.g−1) but these powders also have very different morphology, porosity, and carbon content to the rest. The results presented substantially enhance the growing body of literature on the factors that determine hydrogen and gas generation from PuO2 that has significant implications for long term safe storage of plutonium globally.
{"title":"Effects of relative humidity, surface area and production route on hydrogen yields from water on the surface of plutonium dioxide","authors":"K. Webb, C. Gregson, J. Holt, Bliss McLuckie, R. Orr, H. Sims, D. Woodhead, J. Hobbs, H. Steele, F. Currell, Luke Jones, S. Pimblott, R. Taylor","doi":"10.3389/fnuen.2023.1127504","DOIUrl":"https://doi.org/10.3389/fnuen.2023.1127504","url":null,"abstract":"Over 60 samples of plutonium dioxide (PuO2) powders of varying provenance have been exposed to humid atmospheres and the hydrogen (H2) generation rates measured by gas chromatography. The effects of relative humidity (RH), specific surface area (SSA), plutonium isotopic composition (absorbed dose), and overlying atmosphere have been investigated for ‘as received’ PuO2 powders from the United Kingdom’s Thorp and Magnox reprocessing plants, high surface area powder produced in the laboratory and Magnox PuO2 that was recalcined at 800, 900 or 950°C. Hydrogen generation was shown to be susceptible to subtle influences with the most consistent results observed at 95% RH. However, it was shown that the measured (net) hydrogen decreases with decreasing RH and with atmosphere in the order: Air > argon > nitrogen. There was no clear effect of SSA, apart from with the highest SSA samples (∼40 m2.g−1) but these powders also have very different morphology, porosity, and carbon content to the rest. The results presented substantially enhance the growing body of literature on the factors that determine hydrogen and gas generation from PuO2 that has significant implications for long term safe storage of plutonium globally.","PeriodicalId":400400,"journal":{"name":"Frontiers in Nuclear Engineering","volume":"122 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2013-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128022850","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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