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Project IPAD; A Database to catalogue the analysis of Fukushima Daiichi accident fragmental release material

Martin, P.*; Alhaddad, O.*; Verbelen, Y.*; 佐藤 志彦; 五十嵐 康人*; Scott, T. B.*

Scientific Data (Internet), 7, p.282_1 - 282_8, 2020/08


The 2011 accident at Japan's Fukushima Daiichi Nuclear Power Plant released a considerable inventory of radioactive material into the local and global environments. While the vast majority of this contamination was in the form of gaseous and aerosol species, of which a large component was distributed out over the neighbouring Pacific Ocean (where is was subsequently deposited), a substantial portion of the radioactive release was in particulate form and was deposited across Fukushima Prefecture. To provide an underpinning understanding of the dynamics of this catastrophic accident, alongside assisting in the off-site remediation and eventual reactor decommissioning activities, the "International Particle Analysis Database", or "IPAD", was established to serve as an interactive repository for the continually expanding analysis dataset of the sub-mm ejecta particulate. In addition to a fully interrogatable database of analysis results for registered users (exploiting multiple search methods), the database also comprises an open-access front-end for members of the public to engage with the multi-national analysis activities by exploring a streamlined version of the data.


Assessment of the mode of occurrence and radiological impact of radionuclides in Nigerian coal and resultant post-combustion coal ash using scanning electron microscopy and gamma-ray spectroscopy

Okeme, I. C.*; Scott, T. B.*; Martin, P. G.*; 佐藤 志彦; Ojonimi, T. I.*; Olaluwoye, M. O.*

Minerals (Internet), 10(3), p.241_1 - 241_15, 2020/03

 被引用回数:0 パーセンタイル:100(Mineralogy)

Natural radionuclide concentrations in coal and associated fly ash can occur at levels well in excess of those observed in other materials; enough to raise potential human and environmental health concerns when (re)suspended or incorporated into construction materials. To evaluate such concerns, this study characterised coal and fly ash samples obtained from two Nigerian coal mines (Okaba and Omelewu) using high resolution gamma spectroscopy combined with scanning electron microscopy and energy dispersive spectroscopy. Discrete uraninite particles were observed dispersed within the fly ash samples, alongside U and Th containing mineral grains (monazite, xenotime and zircon) with monazite the most abundant radioactive mineral particles. The pitted and cracked surface morphologies of these radioactive particles (with sizes between 10$$mu$$m and 80$$mu$$m) indicates their susceptibility for disintegration into more dangerous and readily inhalable PM2.5 aerosol particles, with the potential to deliver localised dose and cause chronic respiratory diseases. While the results of activity concentrations and radiological hazard indices (radium equivalent, annual effective dose equivalent, total radium, and excess lifetime cancer risk) from Okaba and Omelewu coal samples were of no concern, results for the corresponding fly ash samples from both mines were between 3 and 5 times higher than internationally recommended safe limits. These results therefore imply that such coal-derived fly ash is not safe for incorporation in the construction of residential houses and should be properly disposed of or contained to prevent hazard due to increased risk of prolonged indoor exposure to gamma radiation, radon gas and inhalation of liberated radioactive particles.


Compositional and structural analysis of Fukushima-derived particulates using high-resolution X-ray imaging and synchrotron characterisation techniques

Martin, P. G.*; Jones, C. P.*; Cipiccia, S.*; Batey, D. J.*; Hallam, K. R.*; 佐藤 志彦; Griffiths, I.*; Rau, C.*; Richards, D. A.*; 末木 啓介*; et al.

Scientific Reports (Internet), 10(1), p.1636_1 - 1636_11, 2020/01


Both the three-dimensional internal structure and elemental distribution of near-field radioactive fallout particulate material released during the March 2011 accident at the Fukushima Daiichi Nuclear Power Plant is analysed using combined high-resolution laboratory and synchrotron radiation X-ray techniques. Results from this study allow for the proposition of the likely formation mechanism of the particles, as well as the potential risks associated with their existence in the environment, and the likely implications for future planned reactor decommissioning. A suite of particles is analyzed from a locality 2 km from the north-western perimeter of the site north of the primary contaminant plume in an area formerly attributed to being contaminated by fallout from reactor Unit 1. The particles are shown to exhibit significant structural similarities; being amorphous with a textured exterior, and containing inclusions of contrasting compositions, as well as an extensive internal void volume bimodal in its size distribution. A heterogeneous distribution of the various elemental constituents is observed inside a representative particle, which also exhibited a Fukushima-derived radiocesium ($$^{134}$$Cs, $$^{135}$$Cs and $$^{137}$$Cs) signature with negligible natural Cs. We consider the structure and composition of the particle to suggest it formed from materials associated with the reactor Unit 1 building explosion, with debris fragments embedded into the particles surface. Such a high void ratio, comparable to geological pumice, suggests such material formed during a rapid depressurisation and is potentially susceptible to fragmentation through attrition.


Nuclear data sheets for A=218

Singh, B.*; Basunia, M. S.*; Martin, M.*; McCutchan, E. A.*; Bara, I.*; Caballero-Folch, R.*; Canavan, R.*; Chakrabarti, R.*; Chekhovska, A.*; Grinder, M. M.*; et al.

Nuclear Data Sheets, 160, p.405 - 471, 2019/09

 被引用回数:0 パーセンタイル:100(Physics, Nuclear)

The evaluated data are presented for 11 known A=218 nulcides (Pb, Bi, Po, At, Rn, Fr, Ra, Ac, Th, Pa and U). For $$^{218}$$Pb, $$^{218}$$Bi, $$^{218}$$At and $$^{218}$$Pa, data are available only for the ground states. For $$^{218}$$U, only the g.s. and a high-spin isomer are known, with no data on $$gamma$$-ray transitions available. For $$^{218}$$Po, ten excited states are known from $$^{218}$$Bi decay, with no knowledge on the multipolarities of gamma-ray transitions. For $$^{218}$$Th, five excited states in the g.s. band are known from an in-beam $$gamma$$-ray study. Data on level half-lives, multipolarities and mixing ratios of gamma transitions is generally lacking for A=218 nuclei. The static magnetic dipole moment has been measured for only an isomer in $$^{218}$$Fr. This evaluation was carried out as part of a joint IAEA-ICTP workshop for Nuclear Structure and Decay Data, organized and hosted by the IAEA, Vienna, and ICTP, Trieste, October 15-26, 2018.


Time-controlled synthesis of the 3D coordination polymer U(1,2,3-Hbtc)$$_{2}$$ followed by the formation of molecular poly-oxo cluster {$rm U$_{14}$$} containing hemimellitate uranium(IV)

Dufaye, M.*; Martin, N. P.*; Duval, S.*; Volkringer, C.*; 池田 篤史; Loiseau, T.*

RSC Advances (Internet), 9(40), p.22795 - 22804, 2019/07

 被引用回数:4 パーセンタイル:54.95(Chemistry, Multidisciplinary)

4価ウラン(U(IV))のヘミメリット酸との配位化合物がアセトン+水溶媒中で2種類合成され、構造同定された。水分量を調整したアセトン溶媒中では、U(IV)の加水分解はゆっくりと起こり、その結果、{$rm U$_{12}$$}$ $や{$rm U$_{14}$$}$ $といった特異なポリオキソ-U(IV)クラスターが生成していることを確認した。


Provenance of uranium particulate contained within Fukushima Daiichi Nuclear Power Plant Unit 1 ejecta material

Martin, P. G.*; Louvel, M.*; Cipiccia, S.*; Jones, C. P.*; Batey, D. J.*; Hallam, K. R.*; Yang, I. A. X.*; 佐藤 志彦; Rau, C.*; Mosselmans, J. F. W.*; et al.

Nature Communications (Internet), 10(1), p.2801_1 - 2801_7, 2019/06

 被引用回数:5 パーセンタイル:27.63(Multidisciplinary Sciences)



Comparison of sodium fast reactor core assembly seismic evaluation using the Japanese JAEA/MFBR/MHI and French CEA simulation tools

山本 智彦; 松原 慎一郎*; 原田 英典*; Saunier, P.*; Martin, L.*; Gentet, D.*; Dirat, J.-F.*; Collignon, C.*

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 8 Pages, 2019/05



OECD/NEA benchmark on pellet-clad mechanical interaction modelling with fuel performance codes; Impact of number of radial pellet cracks and pellet-clad friction coefficient

Dost$'a$l, M.*; Rossiter, G.*; Dethioux, A.*; Zhang, J.*; 天谷 政樹; Rozzia, D.*; Williamson, R.*; Kozlowski, T.*; Hill, I.*; Martin, J.-F.*

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 10 Pages, 2018/10

The benchmark on PCMI was initiated by OECD/NEA Expert Group on Reactor Fuel Performance (EGRFP) in June 2015 and is currently in the latter stages of compiling results and preparing the final report. The aim of the benchmark is to improve understanding and modelling of PCMI amongst NEA member organisations. This is being achieved by comparing PCMI predictions of different fuel performance codes for a number of cases. Two of these cases are hypothetical cases aiming to facilitate understanding of the effects of code-to-code differences in fuel performance models. The two remaining cases are actual irradiations, where code predictions are compared with measured data. During analysis of participants' results of the hypothetical cases, the assumptions for number of radial pellet cracks and the pellet-clad friction coefficient (which can be zero, finite or infinite) were identified to be important factors in explaining differences between predictions once pellet-cladding contact occurs. However, these parameters varied in the models and codes used originally by the participants. This fact led to the extension of the benchmark by inclusion of two additional cases, where the number of radial pellet cracks and three different values of the friction coefficient were prescribed in the case definition. Seven calculations from six organisations contributed results were compared and analysed in this paper.


Super-absorbent polymer valves and colorimetric chemistries for time-sequenced discrete sampling and chloride analysis of sweat via skin-mounted soft microfluidics

Kim, S. B.*; Zhang, Y.*; Won, S. M.*; Bandodkar, A. J.*; 関根 由莉奈; Xue, Y.*; Koo, J.*; Harshman, S. W.*; Martin, J. A.*; Park, J. M.*; et al.

Small, 14(12), p.1703334_1 - 1703334_11, 2018/03

 被引用回数:31 パーセンタイル:5.67(Chemistry, Multidisciplinary)

This paper introduces super absorbent polymer valves and colorimetric sensing reagents as enabling components of soft, skin-mounted microfluidic devices designed to capture, store and chemically analyze sweat released from eccrine glands. The valving technology enables robust means for guiding the flow of sweat from an inlet location into a collection of isolated reservoirs, in a well-defined sequence. Analysis in these reservoirs involves a color responsive indicator of chloride concentration with a formulation tailored to offer stable operation with sensitivity optimized for the relevant physiological range. Evaluations on human subjects with comparisons against ex situ analysis illustrate the practical utility of these advances.


The Martian surface radiation environment; A Comparison of models and MSL/RAD measurements

Matthi$"a$, D.*; Ehresmann, B.*; Lohf, H.*; K$"o$hler, J.*; Zeitlin, C.*; Appel, J.*; 佐藤 達彦; Slaba, T. C.*; Martin, C.*; Berger, T.*; et al.

Journal of Space Weather and Space Climate (Internet), 6, p.A13_1 - A13_17, 2016/03

 被引用回数:36 パーセンタイル:4.68(Astronomy & Astrophysics)

2012年8月6日以降、Mars Science Laboratory (MSL)に搭載された複合型放射線検出器(RAD)を用いて火星表面による放射線環境の測定が続けられている。本研究では、GEANT4, PHITS, HZETRN/OLTARISなど様々なコードを用いて火星表面における放射線環境を推定し、その結果とRADによる測定値を比較した。その結果、計算結果は測定値と概ねよい一致を示すものの、場合によっては大きく解離することが分かった。また、RADのデータは放射線輸送計算について、最適なインプットパラメータや物理モデルの最適な選択に役立つことも確認された。今回の解析結果は、今後、有人火星ミッションを計画する際、その被ばく線量評価や宇宙機遮へい設計などに活用することができる。


Comparative modeling of an in situ diffusion experiment in granite at the Grimsel Test Site

Soler, J. M.*; Landa, J.*; Havlova, V.*; 舘 幸男; 蛯名 貴憲*; Sardini, P.*; Siitari-Kauppi, M.*; Eikenberg, J.*; Martin, A. J.*

Journal of Contaminant Hydrology, 179, p.89 - 101, 2015/08

 被引用回数:30 パーセンタイル:10.01(Environmental Sciences)

マトリクス拡散現象は結晶質岩中の核種移行遅延プロセスとして重要である。スイスのグリムゼル原位置試験場において花崗岩マトリクス中の原位置長期拡散(LTD)試験を行った。試験孔内にHTO, Na $$^{+}$$, Cs $$^{+}$$を含むトレーサ溶液を循環させ、2年半の間、トレーサ濃度の減衰が観測された。拡散期間終了後に、オーバーコアリングによって、岩石中のトレーサ分布が分析された。岩石中の拡散深さは、HTOで20cm、Na $$^{+}$$で10cm、Cs $$^{+}$$で1cm程度であった。これらのデータセットに対し、拡散・収着モデルによる解釈が、複数のチームによって、異なるコードを用いて実施され、実効拡散係数(De)と岩石容量因子($$alpha$$)が導出された。複数のチームによる評価結果は、観測データを概ね再現可能であり、掘削影響による表面部分のDeと$$alpha$$の値が、岩石マトリックス部に比べて大きいことを示唆した。一方で、HTOの結果は実験データと解析結果に大きな乖離が認められ、この点は今後の詳細な検討が必要である。


IAEA NAPRO Coordinated Research Project; Physical properties of sodium

Passerini, S.*; Carardi, C.*; Grandy, C.*; Azpitarte, O. E.*; Chocron, M.*; Japas, M. L.*; Bubelis, E.*; Perez-Martin, S.*; Jayaraj, S.*; Roelofs, F.*; et al.

Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.780 - 790, 2015/05

The IAEA recently established a CRP on "Sodium properties and safe operation of experimental facilities in support of the development and deployment of Sodium Cooled Fast Reactors - NAPRO", to be carried out in the period 2013 - 2017. The first phase of the CRP is focused on the collection and assessment of sodium properties, and it will lead to a consistent property data set which will be published in the form of a handbook. This work is carried out by the 11 participating organizations from 10 Member States through the review and evaluation of the existing available data, the identification of the data gaps and the development of recommendations for experimental programmes to support closing these data gaps. A specific work package (WP 1.1), under the leadership of Argonne National Laboratory, is focused on the analysis of physical properties of sodium: thermodynamic properties and transport properties. The expected outcome includes the improved understanding of the availability, accuracy and range of applications of sodium properties centered on fast reactors and other technological applications. The implemented methodology for WP 1.1 is described and so the properties included in WP 1.1 and their classification. Major findings to date related to WP 1.1 are presented in this work, including detailed analysis of two selected properties.


Modeling of an in-situ diffusion experiment in granite at the Grimsel Test Site

Soler, J. M.*; Landa, J.*; Havlova, V.*; 舘 幸男; 蛯名 貴憲*; Sardini, P.*; Siitari-Kauppi, M.*; Martin, A. J.*

Materials Research Society Symposium Proceedings, Vol.1665, p.85 - 91, 2014/09

マトリクス拡散現象は結晶質岩中の核種移行遅延プロセスとして重要である。スイスのグリムゼル原位置試験場において花崗岩マトリクス中の原位置長期拡散(LTD)試験を行った。試験孔内にHTO, Na$$^{+}$$, Cs$$^{+}$$を含むトレーサ溶液を循環させ、2年半の間、トレーサ濃度の減衰が観測された。拡散期間終了後に、オーバーコアリングによって、岩石中のトレーサ分布が分析された。岩石中の拡散深さは、HTOで20cm、Na$$^{+}$$で10cm、Cs$$^{+}$$で1cm程度であった。これらのデータセットに対し、拡散・収着モデルによる解釈が、複数のチームによって、異なるコードを用いて実施され、実効拡散係数(De)と岩石容量因子($$alpha$$)が導出された。複数のチームによる評価結果は、観測データをおおむね再現可能であり、掘削影響による表面部分の$$D$$eと$$alpha$$の値が、岩石マトリクス部に比べて大きいことを示唆した。一方で、HTOの結果は実験データと解析結果に大きな乖離が認められ、この点は今後の詳細な検討が必要である。


LTD experiment; Postmortem modelling of monopole I

Soler, J. M.*; Landa, J.*; Havlov$'a$, V.*; 舘 幸男; 蛯名 貴憲*; Sardini, P.*; Siitari-Kauppi, M.*; Martin, A.*

Nagra NAB 12-53, 80 Pages, 2013/02

スイスのグリムゼル原位置試験場において原位置長期拡散(LTD)試験が行われた。パッカーで区切られた試験孔内にHTO, $$^{22}$$Na$$^{+}$$, $$^{134}$$Cs$$^{+}$$を含むトレーサ溶液を循環させ、2年半の間、トレーサ濃度の減衰が観測された。拡散期間終了後に、オーバーコアリングによって、岩石中のトレーサ分布が分析された。溶液中のトレーサ濃度変化はCsの減衰が顕著であった。また、濃度分布の進展深さは、HTOで20cm、Na$$^{+}$$で10cm、Cs$$^{+}$$で1cm程度であった。これらのデータセットに対し、拡散・収着モデルによる解釈が、複数のチームによって、異なるコードを用いて実施され、実効拡散係数($$D$$$$_{e}$$)と岩石容量因子($$alpha$$)が導出された。複数のチームによる評価結果は、観測データをおおむね再現可能であり、掘削影響による表面部分の$$D$$$$_{e}$$$$alpha$$の値が、岩石マトリクス部に比べて大きいことを示唆した。一方で、HTOの結果は実験データと解析結果に大きな乖離が認められ、この点は今後の詳細な検討が必要である。



小原 智史; 高屋 茂; 若井 隆純; 浅山 泰; 鈴木 裕士; 齊藤 徹; Martin, L.*

検査技術, 16(3), p.24 - 30, 2011/03



Overview of high priority ITER diagnostic systems status

Walsh, M.*; Andrew, P.*; Barnsley, R.*; Bertalot, L.*; Boivin, R.*; Bora, D.*; Bouhamou, R.*; Ciattaglia, S.*; Costley, A. E.*; Counsell, G.*; et al.

Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2011/03

The ITER device is currently under construction. To fulfil its mission, it will need a set of measurement systems. These systems will have to be robust and satisfy many requirements hitherto unexplored in Tokamaks. Typically, diagnostics occupy either a removable item called a port plug, or installed inside the machine as an intricate part of the overall construction. Limited space availability has meant that many systems have to be grouped together. Installation of the diagnostic systems has to be closely planned with the overall schedule. This paper will describe some of the challenges and systems that are currently being progressed.


Defining the infrared systems for ITER

Reichle, R.*; Andrew, P.*; Counsell, G.*; Drevon, J.-M.*; Encheva, A.*; Janeschitz, G.*; Johnson, D. W.*; 草間 義紀; Levesy, B.*; Martin, A.*; et al.

Review of Scientific Instruments, 81(10), p.10E135_1 - 10E135_5, 2010/10

 被引用回数:19 パーセンタイル:31.3(Instruments & Instrumentation)

ITER will have wide angle viewing systems and a divertor thermography diagnostic which shall provide infrared coverage of the divertor and large parts of the first wall surfaces with spatial and temporal resolution adequate for operational purposes and higher resolved details of the divertor and other areas for physics investigations. We propose specifications for each system such that they jointly respond to the requirements. Risk analysis driven priorities for future work concern mirror degradation, interfaces with other diagnostics, radiation damage to refractive optics, reflections and the development of calibration and measurements methods for varying optical and thermal target properties.



小原 智史; 高屋 茂; 若井 隆純; 浅山 泰; 鈴木 裕士; 齊藤 徹*; Martin, L.*

保全学, 9(1), p.32 - 38, 2010/04



Power requirement for accessing the H-mode in ITER

Martin, Y. R.*; 滝塚 知典; ITPA CDBM H-mode Threshold Database Working Group*

Journal of Physics; Conference Series, 123, p.012033_1 - 012033_11, 2008/00

 被引用回数:278 パーセンタイル:0.06



Space environmental effects on MoS$$_{2}$$ and diamond-like carbon lubricating films; Atomic oxygen-induced erosion and its effect on tribological properties

田川 雅人*; 横田 久美子*; 松本 康司*; 鈴木 峰男*; 寺岡 有殿; 北村 晃*; Belin, M.*; Fontaine, J.*; Martin, J. M.*

Surface & Coatings Technology, 202(4-7), p.1003 - 1010, 2007/12

 被引用回数:43 パーセンタイル:14.79(Materials Science, Coatings & Films)


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