Structural and compositional characteristics of Fukushima release particulate material from Units 1 and 3 elucidates release mechanisms, accident chronology and future decommissioning strategy

Martin, P. G.*; Jones, C. P.*; Bartlett, S.*; Ignatyev, K.*; Megson-Smith, D.*; 佐藤 志彦; Cipiccia, S.*; Batey, D. J.*; Rau, C.*; 末木 啓介*; et al.

Scientific Reports (Internet), 10, p.22056_1 - 22056_17, 2020/12

https://doi.org/10.1038/s41598-020-79169-2

The structural form and elemental distribution of material originating from different Fukushima Daiichi Nuclear Power Plant reactors (Units 1 and 3) is hereby examined to elucidate their contrasting release dynamics and the current in-reactor conditions to influence future decommissioning challenges. Complimentary computed X-ray absorption tomography and X-ray fluorescence data show that the two suites of Si-based material sourced from the different reactor Units have contrasting internal structure and compositional distribution. The known event and condition chronology correlate with the observed internal and external structures of the particulates examined, which suggest that Unit 1 ejecta material sustained a greater degree of melting than that likely derived from reactor Unit 3. In particular, we attribute the near-spherical shape of Unit 1 ejecta and their internal voids to there being sufficient time for surface tension to round these objects before the hot (and so relatively low viscosity) silicate melt cooled to form glass. In contrast, a more complex internal form associated with the sub-mm particulates invoked to originate from Unit 3 suggest a lower peak temperature, over a longer duration. Using volcanic analogues, we consider the structural form of this material and how it relates to its environmental particulate stability and the bulk removal of residual materials from the damaged reactors. We conclude that the brittle and angular Unit 3 particulate are more susceptible to further fragmentation and particulate generation hazard than the round, higher-strength, more homogenous Unit 1 material.

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

https://doi.org/10.1038/s41598-020-58545-y

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 (Cs, Cs and 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.

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

Dostl, 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.

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

Matthi, D.*; Ehresmann, B.*; Lohf, H.*; Khler, 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

https://doi.org/10.1051/swsc/2016008

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。

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

https://doi.org/10.1063/1.3491199

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.

Recent progress on the development and analysis of the ITPA global H-mode confinement database

McDonald, D. C.*; Cordey, J. G.*; Thomsen, K.*; Kardaun, O. J. W. F.*; Snipes, J. A.*; Greenwald, M.*; Sugiyama, L.*; Ryter, F.*; Kus, A.*; Stober, J.*; et al.

Nuclear Fusion, 47(3), p.147 - 174, 2007/03

https://doi.org/10.1088/0029-5515/47/3/001

国際トカマク物理活動(ITPA)全体的Hモード閉じ込めデーターベースの第3版(DB3)に関し1994年から2004年の期間に行われた更新と解析について、この論文は記述する。エネルギー閉じ込め時間とその制御パラメータの巨視的データを、異なったサイズと形状の次の18装置から集めた。ASDEX, ASDEX Upgrade, C-Mod CoMPASS-D, DIII-D, JET, JFT-2M, JT-60U, MAST, NSTX, PBX-M, PDX, START, T-10, TCV, TdeV, TFTR及びUMAN-3M。このDB3データベースに基づき、幅広い物理研究が行われた。特に中心部と周辺部の振る舞いの分離,無次元解析、及びデータベースと1次元輸送コードとの比較に進展があった。データーベースは、ITERのような次期装置の閉じ込め特性の基盤を評価することを主要な目的としており、この論文でも解析結果を踏まえて次期装置を議論する。

The Role of aspect ratio and beta in H-mode confinement scalings

Kaye, S. M.*; Valovic, M.*; Chudnovskiy, A.*; Cordey, J. G.*; McDonald, D.*; Meakins, A.*; Thomsen, K.*; Akers, R.*; Bracco, G.*; Brickley, C.*; et al.

Plasma Physics and Controlled Fusion, 48(5A), p.A429 - A438, 2006/05

https://doi.org/10.1088/0741-3335/48/5A/S44

NSTXとMASTからの低アスペクト比データで拡大されたHモードデータベースを用いて、アスペクト比とベータの閉じ込め比例則に対する影響を、いろいろな統計手法を適用して調べた。予測変数として工学的パラメータを用いた比例則開発から、逆アスペクト比依存性は0.38から1.29乗にあることがわかった。これらの比例則を物理変数の比例則に変換すると、規格化エネルギー閉じ込め時間はベータ増加により低下する。アスペクト比とベータの間には強い相関があるので、物理変数をもとにする比例則は不確実になっている。

A Study of fuel failure behavior in high burnup HTGR fuel; Analysis by STRESS3 and STAPLE codes

Martin, D. G.*; 沢 和弘; 植田 祥平; 角田 淳弥

JAERI-Research 2001-033, 19 Pages, 2001/05

JAERI-Research-2001-033.pdf:1.2MB

高温ガス炉燃料の安全設計においては、1次冷却材への放出量が許容値を超えないよう、核分裂生成物を被覆燃料粒子内に閉込めることが重要である。本報は、高燃焼度下における燃料挙動の研究のため、照射試験中の燃料挙動を英国のコードを用いて再現しようと試みた結果を示す。計算には、91F-1Aキャプセル及びHRB-22キャプセルで実施した照射試験結果を用いた。その結果、被覆層の破壊強度及び厚さを統計的に取り扱うと、破損挙動を再現できることがわかった。

The GTS-LTD MONOPOLE-2 experiment at grimsel; Predictive modeling and comparison with monitoring data

Soler, J. M.*; Martin, A. J.*; Lanyon, G. W.*; Havlov, V.*; Siitari-Kauppi, M.*; 舘 幸男

no journal, , 

原位置の擾乱の少ない結晶質岩中のマトリクス拡散を現実的に評価することを目的に、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)プロジェクトを進めている。現在2回目の原位置拡散試験(モノポール2)を実施中である。1回目の原位置試験(モノポール1)の結果及び室内拡散試験の結果に基づき、モノポール2試験の予測解析を実施し、トレーサー注入孔及び観察孔中のモニタリングデータと比較した。非収着性トレーサー(HTO, Cl)については、室内での透過拡散試験から導出された拡散パラメータによって、モニタリングデータ、特に注入孔のデータがより良く説明された。収着性のCsとBaの初期の濃度減少は、これらの元素の高い収着性の影響を示すものである。モノポール1試験で得られたCsのパラメータは、モノポール2にも適用可能であった。しかしながら、Baについては、予測される以上に収着の影響が大きいと評価された。