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.

Integration of pool scrubbing research to enhance source-term calculations (IPRESCA) project

Gupta, S.*; Herranz, L. E.*; Lebel, L. S.*; Sonnenkalb, M.*; Pellegrini, M.*; Marchetto, C.*; 丸山 結; Dehbi, A.*; Suckow, D.*; Krkel, T.*

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16 Pages, 2022/03

Pool scrubbing is a major topic in water cooled nuclear reactor technology as it is one of the means for mitigating the source-term to the environment during a severe accident. Pool scrubbing phenomena include coupled interactions between bubble hydrodynamics, aerosols and gaseous radionuclides retention mechanisms under a broad range of thermal-hydraulic conditions as per accident scenarios. Modeling pool scrubbing in some relevant accident scenarios has shown to be affected by substantial uncertainties. In this context, IPRESCA (Integration of Pool scrubbing Research to Enhance Source-term CAlculations) project aims to promote a better integration of international research activities related to pool scrubbing by providing support in experimental research to broaden the current knowledge and database, and by supporting analytical research to facilitate systematic validation and model enhancement of the existing pool scrubbing codes. The project consortium includes more than 30 organisations from 15 countries involving research institutes, universities, TSOs, and industry. For IPRESCA activities, partners join the project with in-kind contributions. IPRESCA operates under NUGENIA Technical Area 2/SARNET (Severe Accident) - Sub Technical Area 2.4 (Source-term). The present paper provides an introduction and overview of the IPRESCA project, including its objectives, organizational structure and the main outcomes of completed activities. Furthermore, key activities currently ongoing or planned in the project framework are also discussed.

Phenomena identification ranking tables for accident tolerant fuel designs applicable to severe accident conditions

Khatib-Rahbar, M.*; Barrachin, M.*; Denning, R.*; Gabor, J.*; Gauntt, R.*; Herranz, L. E.*; Hobbins, R.*; Jacquemain, D.*; 丸山 結; Metcalf, J.*; et al.

NUREG/CR-7282, ERI/NRC 21-204 (Internet), 160 Pages, 2021/04

The U.S. Nuclear Regulatory Commission (NRC) is preparing to accept anticipated licensing applications for the commercial use of accident tolerant fuel (ATF) in commercial nuclear power plants in the United States. It is the objective of the NRC to evaluate the effects of ATF designs on severe accident behavior, and to determine potential changes to the NRC severe accident analysis computer codes that would simulate plant conditions using ATFs commensurate with the accuracy in accident analyses involving conventional fuels. This report documents the development of Phenomena Identification and Ranking Tables (PIRTs) for near-term ATFs under severe accident conditions in light water reactors (LWRs). The PIRTs were developed by a panel of experts for various near-term ATF design concepts (i.e., FeCrAl cladding, zirconium alloy cladding coated with chromium, and CrO dopants in uranium dioxide fuels) in addition to the impacts from fuel enrichment and burnup. Panel members also considered the severe accident implications of the longer-term ATF concepts. The main figures-of-merit considered in this ranking process are the amount of fission products released into the containment and the quantity of combustible gases generated during an accident. Special focus is given to whether existing severe accident codes and models would be sufficient as applied to LWRs employing these fuels, and whether additional experimental studies or model development would be warranted.

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.

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。

ITER nuclear components, preparing for the construction and R&D results

伊尾木 公裕*; 秋場 真人; Barabaschi, P.*; Barabash, V.*; Chiocchio, S.*; Daenner, W.*; Elio, F.*; 榎枝 幹男; 江里 幸一郎; Federici, G.*; et al.

Journal of Nuclear Materials, 329-333(1), p.31 - 38, 2004/08

https://doi.org/10.1016/j.jnucmat.2004.04.003

ITER主要コンポーネントの発注仕様書の準備が現在進行中である。製造方法や非破壊検査法などを考慮しつつ炉構造機器(真空容器や容器内機器)の詳細設計を現在行っている。R&D開発については、20度あるいは30度の入射角の超音波試験,2チャンネルモデルによる流量配分の試験,第一壁のモックアップやパネルの製造及び試験,ハウジングを含めた全システムとしてのフレキシブル支持構造の試験,リーク試験のための予備真空領域を設けた同軸冷却管接続の試験,ダイバータの垂直ターゲットのプロトタイプの製造と試験などが行われた。こうした結果により、設計の成立性について確信を与えるとともに、低コストの代替え製造法の可能性を示すものである。

Picosecond snapshot of the speckles from ferroelectric BaTiO by means of X-ray lasers

Tai, R.; 並河 一道*; 岸本 牧; 田中 桃子; 助川 鋼太*; 長谷川 登; 河内 哲哉; 加道 雅孝; Lu, P.; 永島 圭介; et al.

Physical Review Letters, 89(25), p.257602_1 - 267602_4, 2002/12

https://doi.org/10.1103/PhysRevLett.89.257602

温度に対する無秩序表面ドメイン構造の振舞を調べるためにピコ秒X線レーザースペックル計測が初めて行われた。フェロエレクトリックドメインによって引き起こされた過渡的な表面構造はキューリー温度へ向かっての温度増加に伴い減少し、キューリー温度以上で完全に消滅する。c/aドメインの空間的な配置の急激な変化は、キューリー温度より2度以下から始まることが観測された。そしてそこでは、平気的なドメインの大きさは(Tc-T)により減少することがわかった。キューリー温度近くのパラ状態において存在すると考えられていながら、従来の手法では不可能であった分極クラスターの観察を遂行できる見通しが得られた。

Anion-exchange behavior of Rf in HCl and HNO solutions

羽場 宏光; 塚田 和明; 浅井 雅人; 後藤 真一*; 豊嶋 厚史; 西中 一朗; 秋山 和彦; 平田 勝; 市川 進一; 永目 諭一郎; et al.

Journal of Nuclear and Radiochemical Sciences, 3(1), p.143 - 146, 2002/06

https://doi.org/10.14494/jnrs2000.3.143

われわれの研究グループでは、超アクチノイド元素である104番元素ラザホージウム(Rf)の溶液化学実験を進めている。まず、Rfの同族元素Zr並びにHfに加え擬4族元素Thの放射性トレーサーを製造し、バッチ法により1.1-13.1M HNO並びに1.0-11.5M HCl系における陰イオン交換分配係数を系統的に測定した。また、Rfの単一原子の化学実験を行うために、繰り返し実験が可能な迅速イオン交換分離装置(AIDA)を開発した。原研タンデム加速器を用いて、Ge(O,xn),Gd(O,xn)並びにCm(O,5n)反応によってそれぞれ Zr,Hf並びにRfを製造し、4.0-11.5M HCl並びに8.0M HNO系における陰イオン交換実験を行った。塩酸系では、7.0-11.5Mの範囲でRfの分配係数は塩酸濃度の増加とともに急激に増加し、陰イオン塩化物錯体([Rf(OH)Cl],[RfCl])の形成を示唆した。また、樹脂への吸着性の強さは、RfZrHfの順であることがわかった。一方、8.0M HNO系では、Rfは同族元素ZrとHfと同様に陰イオン交換樹脂に対して低い吸着性を示し、ThやPuと全く異なることがわかった。

Nucleon-induced preequilibrium reactions in terms of the quantum molecular dynamics

千葉 敏; Chadwick, M. B.*; 仁井田 浩二*; 丸山 敏毅; 丸山 智幸*; 岩本 昭

Physical Review C, 53(4), p.1824 - 1832, 1996/04

https://doi.org/10.1103/PhysRevC.53.1824

QMD理論を用いて、90~200MeV領域におけるAl、NiとZrの核子入射・核子放出反応における前平衡過程の角度分布の解析を行った。QMDはパラメータ調整なしに測定された(p,xp')及び(p,xn)反応の微分断面積を再現できることが分かった。次いで、前平衡過程のより詳しい研究を行った。さらに、多重前平衡過程の検討を1GeVまで行った。

MeVイオンマイクロビーム技術の開発; 原研・早稲田大学共同研究成果報告

神谷 富裕; 水橋 清; 峰原 英介; 宇都宮 伸宏*; 田中 隆一; 丸山 倫夫*; M.Koh*; 則武 克誌*; 松川 貴*; 杉森 正章*; et al.

JAERI-M 94-033, 108 Pages, 1994/03

JAERI-M-94-033.pdf:4.24MB

早稲田大学と原研は、MeV領域のマイクロビーム技術の開発を目的として、マイクロビーム形成装置を共同で設計・製作し、同大学理工学研究所の1.7MVタンデム加速器のビームラインに設置した。同加速器から引出された3MeV、Heのビームを用いてビーム集束化の実験を行い、ターゲットにおいて1.71.9mのサイズのビームスポットを得た。また、ビーム集束研究の基盤技術として、加速器、特にイオン源の電流安定化の検討・精密二連四重極電磁石レンズ(Qレンズ)の磁場解析、振動測定等を行うとともに、マイクロビーム技術開発研究に必要な実験の基礎となるデータを得た。本報告は本装置の概要及び共同研究の成果について述べる。