A Focusing supermirror for time-of-flight grazing-incidence small-angle neutron scattering measurement

山崎 大; 丸山 龍治; 青木 裕之; 花島 隆泰*; 阿久津 和宏*; 宮田 登*; 曽山 和彦

Quantum Beam Science (Internet), 9(2), p.20_1 - 20_12, 2024/06

https://doi.org/10.3390/qubs9020020

This study developed a neutron-beam focusing supermirror for grazing-incidence small-angle neutron scattering (GISANS) measurements. It was fabricated by depositing NiC/Ti supermirror film with ion-beam sputtering on a precise elliptic surface of fused quartz figured using the elastic emission machining technique. Neutron measurements at a pulsed neutron reflectometer BL17 of MLF, J-PARC successfully demonstrated that the focusing supermirror enhances a beam intensity twentyfold compared with an optimally collimated beam, achieving the signal-to-background ratio of the focal spot as high as 500. The mirror can be readily installed and used at BL17.

Main outputs from the OECD/NEA ARC-F Project

丸山 結; 杉山 智之*; 島田 亜佐子; Lind, T.*; Bentaib, A.*; Sogalla, M.*; Pellegrini, M.*; Albright, L.*; Clayton, D.*

Proceedings of 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) (Internet), p.4782 - 4795, 2023/08

http://dx.doi.org/10.13182/NURETH20-40302

The Analysis of Information from Reactor Buildings and Containment Vessels of Fukushima Daiichi Nuclear Power Station (FDNPS) (ARC-F) project was initiated in January 2019 for three years with 22 signatories from 12 countries. Three main tasks were implemented in the ARC-F project, which were relevant to 1) refinement of analysis for accident scenarios and associated fission product (FP) transport and dispersion, 2) compilation and management of data and information, and 3) discussion for the next-phase project. Various activities were performed in Task 1, covering improvement of analysis for accident scenarios, and in-depth analyses for specific phenomena such as in-vessel melt progression, molten core/concrete interaction, FP transport and source term, hydrogen combustion and atmospheric dispersion of FPs. Through these studies, analyses for accident scenarios with severe accident codes were refined and important phenomena with large uncertainties were clarified. In order to share well selected and organized information from the FDNPS with the project partners, two databases, information source database and sample database, were built under Task 2. The analysis techniques including the separation of iodine species were developed also in Task 2 and applied to the analysis of FPs in several samples taken from the FDNPS. The next-phase project was discussed in Task 3, resulting in launching the Fukushima Daiichi Nuclear Power Station Information Collection and Evaluation (FACE) project. The FACE project officially started in July 2022 with the participation of 23 organizations from 12 countries and the European Commission.

Sodium-cooled Fast Reactors

大島 宏之; 森下 正樹*; 相澤 康介; 安藤 勝訓; 芦田 貴志; 近澤 佳隆; 堂田 哲広; 江沼 康弘; 江連 俊樹; 深野 義隆; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

https://shop.elsevier.com/books/sodium-cooled-fast-reactors/morishita/978-0-12-824076-2

ナトリウム冷却高速炉(SFR: Sodium-cooled Fast Reactor)の歴史や、利点、課題を踏まえた安全性、設計、運用、メンテナンスなどについて解説する。AIを利用した設計手法など、SFRの実用化に向けた設計や研究開発についても述べる。

In-depth analysis for uncertain phenomena on fission product transport in the OECD/NEA ARC-F project

Lind, T.*; Herranz, L. E.*; Sonnenkalb, M.*; 丸山 結

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 15 Pages, 2022/03

The accident progression and fission product release from the three damaged units of the Fukushima Daiichi Nuclear Power Plant were systematically investigated in the OECD/NEA BSAF project phases 1 and 2. As a result of those investigations, a good progress was achieved in establishing defendable accident scenarios and the corresponding fission product releases to the environment. Nonetheless, there are some areas requiring further work, particularly concerning fission product behavior. They are addressed in the OECD/NEA project "Analysis of Information from Reactor Buildings and Containment Vessels of Fukushima Daiichi NPS" (ARC-F). Based on the outcome of the BSAF project, several focus areas were selected for further investigations in the ARC-F project, one of them being the behavior of fission products and source term. In this paper, five topics which were ranked with a high significance as open issues based on the BSAF project regarding fission product behavior are discussed: i) fission product speciation, ii) iodine chemistry, iii) pool scrubbing, iv) fission product transport and behavior in the buildings, and v) uncertainty analysis and variant calculations. Significant progress has been made in these five topics in the ARC-F project. In this paper, background is given for choosing these topics for specific investigations based on the outcome of the BSAF project. The topics are described and the approach to study them in the ARC-F given along with some exemplary, preliminary results. Finally, the readers' attention is drawn to open issues which are not included in the ARC-F work scope and could need further attention.

「グレーデッドアプローチに基づく合理的な安全確保検討グループ」活動状況中間報告(2019年9月2020年9月)

与能本 泰介; 中島 宏*; 曽野 浩樹; 岸本 克己; 井澤 一彦; 木名瀬 政美; 長 明彦; 小川 和彦; 堀口 洋徳; 猪井 宏幸; et al.

JAEA-Review 2020-056, 51 Pages, 2021/03

JAEA-Review-2020-056.pdf:3.26MB

「グレーデッドアプローチに基づく合理的な安全確保検討グループ」は、原子力科学研究部門、安全・核セキュリティ統括部、原子力施設管理部署、安全研究・防災支援部門の関係者約10名で構成され、機構の施設管理や規制対応に関する効果的なグレーデッドアプローチ(安全上の重要度に基づく方法)の実現を目的としたグループである。本グループは、2019年の9月に活動を開始し、以降、2020年9月末までに、10回の会合を開催するとともに、メール等も利用し議論を行ってきた。会合では、グレーデッドアプローチの基本的考え方、各施設での新規制基準等への対応状況、新検査制度等についての議論を行なうとともに、各施設での独自の検討内容の共有等を行っている。本活動状況報告書は、本活動の内容を広く機構内外で共有することにより、原子力施設におけるグレーデッドアプローチに基づく合理的で効果的な安全管理の促進に役立つことを期待し取りまとめるものである。

Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF Project

Pellegrini, M.*; Herranz, L.*; Sonnenkalb, M.*; Lind, T.*; 丸山 結; Gauntt, R.*; Bixler, N.*; Morreale, A.*; Dolganov, K.*; Sevon, T.*; et al.

Nuclear Technology, 206(9), p.1449 - 1463, 2020/09

https://doi.org/10.1080/00295450.2020.1724731

The OECD/NEA Benchmark Study at the Accident of Fukushima Daiichi Nuclear Power Station (BSAF) project, which started in 2012 and continued until 2018, was one of the earliest responses to the accident at Fukushima Daiichi. The project, divided into two phases addressed the investigation of the accident at Unit 1, 2 and 3 by Severe Accident (SA) codes until 500 h focusing on thermal-hydraulics, core relocation, Molten Corium Concrete Interaction (MCCI) and fission products release and transport. The objectives of BSAF were to make up plausible scenarios based primarily on SA forensic analysis, support the decommissioning and inform SA codes modeling. The analysis and comparison among the institutes have brought up vital insights regarding the accident progression identifying periods of core meltdown and relocation, Reactor Pressure Vessel (RPV) and Primary Containment Vessel (PCV) leakage/failure through the comparison of pressure, water level and CAMS signatures. The combination of code results and inspections (muon radiography, PCV inspection) has provided a picture of the current status of the debris distribution and plant status. All units present a large relocation of core materials and all of them present ex-vessel debris with Unit 1 and Unit 3 showing evidences of undergoing MCCI. Uncertainties have been identified in particular on the time and magnitude of events such as corium relocation in RPV and into cavity floor, RPV and PCV rupture events. Main uncertainties resulting from the project are the large and continuous MCCI progression predicted by basically all the SA codes and the leak pathways from RPV to PCV and PCV to reactor building and environment. The BSAF project represents a pioneering exercise which has set the basis and provided lessons learned not only for code improvement but also for the development of new related projects to investigate in detail further aspects of the Fukushima Daiichi accident.

Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF Project

Pellegrini, M.*; Herranz, L.*; Sonnenkalb, M.*; Lind, T.*; 丸山 結; Gauntt, R.*; Bixler, N.*; Morreale, A.*; Dolganov, K.*; Sevon, T.*; et al.

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.1147 - 1162, 2019/08

The OECD/NEA Benchmark Study at the Accident of the Fukushima Daiichi NPS project (BSAF) has started in 2012 until 2018 as one of the earliest responses to the accident at Fukushima Daiichi NPS. The project addressed the investigation of the accident at Units 1, 2 and 3 by severe accident (SA) codes focusing on thermal-hydraulics, core relocation, molten core/concrete interaction (MCCI) and fission products release and transport. The objectives of BSAF were to make up plausible scenarios based primarily on SA forensic analysis, support the decommissioning and inform SA codes modeling. The analysis and comparison among the institutes have brought up vital insights regarding the accident progression identifying periods of core meltdown and relocation, reactor vessel (RV) and primary containment vessel (PCV) leakage/failure through the comparison of pressure, water level and CAMS measurement. The combination of code results and inspections has provided a picture of the current state of the debris distribution and plant state. All units present a large relocation of core materials and all of them present ex-vessel debris with units 1 and 3 showing evidences of undergoing MCCI. Uncertainties have been identified in particular on the time and magnitude of events such as corium relocation in RV and into cavity floor, RV and PCV rupture events. Main uncertainties resulting from the project are the large and continuous MCCI progression predicted by basically all the SA codes and the leak pathways from RV to PCV and PCV to reactor building and environment. The BSAF project represents a pioneering exercise which has set the basis and provided lessons learned not only for code improvement but also for the development of new related projects to investigate in details further aspects of the Fukushima Daiichi NPS accident.

Development of high-polarization Fe/Ge neutron polarizing supermirror; Possibility of fine-tuning of scattering length density in ion beam sputtering

丸山 龍治; 山崎 大; 阿久津 和宏*; 花島 隆泰*; 宮田 登*; 青木 裕之; 武田 全康; 曽山 和彦

Nuclear Instruments and Methods in Physics Research A, 888, p.70 - 78, 2018/04

https://doi.org/10.1016/j.nima.2018.01.068

イオンビームスパッタ法で成膜されたFe/Si及びFe/Ge多層膜に対して、X線及び偏極中性子反射率、走査型透過電子顕微鏡と組み合わされたエネルギー分散型X線分光分析等のプローブによって層構造や局所元素分析を行った。その結果、Fe/Ge多層膜のGe層に含まれたスパッタリングガスであるArが含まれることにより、Ge層の散乱長密度が減少し、(-)スピンの中性子に対するFeとGeの散乱長密度のコントラストがほぼ消失し偏極中性子反射において高偏極率となることがわかった。Ge層に含まれるArは、成膜時においてAeがGeターゲットで後方散乱することに起因することが知られており、偏極スーパーミラーの高偏極率化に必要な(-)スピン中性子に対する散乱長密度コントラストを微調整する新たな手法となる可能性を示すものである。この結果を基に、Niの5倍の全反射臨界角をもつFe/Ge偏極スーパーミラーを成膜し偏極反射率測定を行った結果、(+)スピン中性子の反射率が0.70以上、偏極率はビームラインの偏極性能が正しく補正されている領域においては0.985以上という高い偏極率を達成した。

Accessible length scale of the in-plane structure in polarized neutron off-specular and grazing-incidence small-angle scattering measurements

丸山 龍治; Bigault, T.*; Wildes, A. R.*; Dewhurst, C. D.*; Saerbeck, T.*; Honecker, D.*; 山崎 大; 曽山 和彦; Courtois, P.*

Journal of Physics; Conference Series, 862(1), p.012017_1 - 012017_6, 2017/06

https://doi.org/10.1088/1742-6596/862/1/012017

中性子偏極スーパーミラーを偏極中性子散乱測定に用いる際には、試料の磁化や中性子ビームの偏極率への影響を小さく抑えるために、これを構成する多層膜が磁気的にソフトであることが重要である。これらの多層膜は交換結合長(数十nm)よりもサイズの小さい結晶粒から構成され、磁気特性はバルクとは異なり隣り合うスピン間での交換相互作用による結晶磁気異方性の平均化(ランダム異方性モデル)によって理解される。本研究では、磁化の過程における多層膜の面内磁気構造を偏極中性子非鏡面反射及び斜入射小角散乱を用いて測定し、散乱データの歪曲波ボルン近似による散乱強度分布シミュレーションを行うことにより面内方向の長さスケールの異なる非鏡面反射と斜入射小角散乱で得られたデータの比較を行った。本発表では2つの散乱手法の特徴や適応可能な面内構造の長さスケールの範囲に関する議論を行う。

Demonstration of the high collection efficiency of a broadband Mo/Si multilayer mirror with a graded multilayer coating on an ellipsoidal substrate

市丸 智*; 竹中 久貴*; 並河 一道*; Gullikson, E. M.*; 圓山 桃子; 奥 哲*

Review of Scientific Instruments, 86(9), p.093106_1 - 093106_7, 2015/09

https://doi.org/10.1063/1.4929708

EUV分光のための広帯域Mo/Siグレーディッド多層膜ミラーを製作した。このミラーは、波長15nm17nm、有効エリア11001500mmにおいて平均16%という、直径1インチの標準的なMo/Si多層鏡より約4倍大きい反射率を有しており、この波長領域でのEUV蛍光計測に使用可能であることを示している。