Simulation of a jet flow rectified by a grating-type structure using immersed boundary methods

廣瀬 意育; 安部 諭; 石垣 将宏*; 柴本 泰照; 日引 俊*

Progress in Nuclear Energy, 169, p.105085_1 - 105085_13, 2024/04

https://doi.org/10.1016/j.pnucene.2024.105085

Immersed boundary methods (IBMs) have been developed as complementary methods for computational fluid dynamics (CFD). They allow a flow simulation in a mock-up model that includes complex-shaped inner structures and/or boundaries with a non-body conformal mesh. Such a model might force us to create a complicated body-fitted mesh with a high cost in the conventional CFD (CCFD) approach. We focus on the Brinkman penalization (BP) method and its extended version, which we call here the extended Brinkman penalization method (EBP), among the different types of IBMs, aiming to apply them to the phenomena that occur during severe accidents in a nuclear reactor containment vessel and explore the possibility that the methods can partially replace the CCFD. In this paper, as a preliminary step to validate the applicability of these methods, we measure the jet flow rectified by a grating-type structure used for the validation of numerical techniques and apply them to simulate the behavior of an upward jet rectified by a horizontally placed grating-type structure modeled as an immersed body. This type of structure is generally used in reactor buildings, and it is crucial to evaluate their influence on gaseous flows because the behaviors of hydrogen produced during severe accidents may be influenced by them. The structure is selected as our subject because it has moderate complexity, enabling us to examine the effects of the IBMs and compare them with CCFD. We investigate whether these methods can reproduce a result of corresponding CCFD in which the grating is modeled as body-conformal mesh and show that the former can produce the latter with equivalent accuracy. All these results are also compared with the experimental data on the flow velocity distributions downstream of the grating measured using particle image velocimetry.

Numerical simulation technologies for safety evaluation in plant lifecycle optimization method, ARKADIA for advanced reactors

内堀 昭寛; 堂田 哲広; 青柳 光裕; 曽根原 正晃; 曽我部 丞司; 岡野 靖; 高田 孝*; 田中 正暁; 江沼 康弘; 若井 隆純; et al.

Nuclear Engineering and Design, 413, p.112492_1 - 112492_10, 2023/11

https://doi.org/10.1016/j.nucengdes.2023.112492

ナトリウム冷却高速炉に代表される革新炉に対し、安全性評価やそれに基づく設計最適化を自動で行うARKADIAを開発している。通常運転もしくは設計基準事象の範囲で設計最適化を行うARKADIA-Designについては、核特性-熱流動-炉心変形のマルチレベル連成解析手法等を中心技術として開発し、その基本的機能を確認した。シビアアクシデントまで含む範囲で安全性評価を行うARKADIA-Safetyの基盤技術として、炉内/炉外事象一貫解析手法の整備を進め、仮想的なシビアアクシデント事象を解析することで基本的機能を確認した。また、炉外事象に対する解析モデルの高度化、設計最適解の探索工程を合理化するAI技術の開発に着手した。

Numerical simulation of bubble hydrodynamics for pool scrubbing

岡垣 百合亜; 柴本 泰照; 和田 裕貴; 安部 諭; 日引 俊詞*

Journal of Nuclear Science and Technology, 60(8), p.955 - 968, 2023/08

https://doi.org/10.1080/00223131.2022.2161656

Pool scrubbing is an important filtering process that prevents radioactive aerosols from entering the environment in the event of severe accidents in a nuclear reactor. In this process of transporting aerosol particles using bubbles, bubble hydrodynamics plays a crucial role in modeling pool scrubbing and significantly affects particle removal in a bubble. The pool scrubbing code based on Lumped Parameter (LP) approach includes the particle removal model, and its hydrodynamic parameters are determined based on simple assumptions. We aim to apply the three-dimensional Computer Fluid Dynamics (CFD) approach to understand the detailed bubble interaction. This study validated the applicability of the CFD simulation to bubble hydrodynamics at the flow transition from a globule to a swarm region, which is critical in the stand-alone pool scrubbing code-SPARC-90. Two types of solvers based on the Volume Of Fluid (VOF) and the Simple Coupled Volume Of Fluid with Level Set (S-CLSVOF) methods were used to capture the gas-liquid interface in the CFD simulation. We used the experimental data for validation. As a result, the VOF and S-CLSVOF methods accurately predicted the bubble size and void fraction distributions. In addition, we confirmed that the bubble rise velocity of the S-CLSVOF method almost agreed with the experimental results.

Local electronic structure of interstitial hydrogen in MgH inferred from muon study

門野 良典*; 平石 雅俊*; 岡部 博孝*; 幸田 章宏*; 伊藤 孝

Journal of Physics; Condensed Matter, 35(28), p.285503_1 - 285503_13, 2023/07

https://doi.org/10.1088/1361-648X/acccc7

Magnesium hydride has great potential as a solid hydrogen (H) storage material because of its high H storage capacity of 7.6 wt%. However, its slow hydrogenation and dehydrogenation kinetics and the high temperature of 300 C required for decomposition are major obstacles to small-scale applications such as automobiles. The local electronic structure of interstitial H in MgH is an important fundamental knowledge in solving this problem, which has been studied mainly based on density functional theory (DFT). However, few experimental studies have been performed to assess the results of DFT calculations. We have therefore introduced muon (Mu) as pseudo-H into MgH and investigated the corresponding interstitial H states by analyzing their electronic and dynamical properties in detail. As a result, we observed multiple Mu states similar to those observed in wide-gap oxides, and found that their electronic states can be attributed to relaxed-excited states associated with donor/acceptor levels predicted by the recently proposed ambipolarity model. This provides an indirect support for the DFT calculations on which the model is based via the donor/acceptor levels. An important implication of the muon results for improved hydrogen kinetics is that dehydrogenation, serving as a reduction for hydrides, stabilises the interstitial H state.

HTTR1次ヘリウム循環機フィルタの差圧上昇事象,1; 差圧上昇事象の原因調査

根本 隆弘; 荒川 了紀; 川上 悟; 長住 達; 横山 佳祐; 渡部 雅; 大西 貴士; 川本 大樹; 古澤 孝之; 猪井 宏幸; et al.

JAEA-Technology 2023-005, 33 Pages, 2023/05

JAEA-Technology-2023-005.pdf:5.25MB

HTTR (High Temperature engineering Test Reactor) RS-14サイクルの原子炉出力降下において、ヘリウムガス循環機のフィルタ差圧が上昇傾向となった。この原因を調査するため、1次ヘリウム純化設備のガス循環機の分解点検等を実施した結果、ガス循環機内のシリコンオイルミストがチャコールフィルタの性能低下で捕集できなくなり、1次系統に混入したためと推定された。今後は、フィルタ交換を実施するとともに、さらなる調査を進め、再発防止対策を策定する予定である。

Short-range spin order in paramagnetic AgCrSe

中村 惇平*; 川北 至信; 岡部 博孝*; Li, B.*; 下村 浩一郎*; 末益 崇*

Journal of Physics and Chemistry of Solids, 175, p.111199_1 - 111199_8, 2023/04

https://doi.org/10.1016/j.jpcs.2022.111199

Muon spin rotation (SR) experiments were performed to directly investigate the temperature dependence of the short-range order or correlations of chromium spins in the paramagnetic phase of AgCrSe. The detailed investigation of the SR spectra over a wide temperature range from low to high temperatures revealed that the short-range spin correlations developed below about 184 K. It also confirmed no short-range correlations at high temperatures, which had been controversial in previous quasi-elastic neutron scattering studies. In addition, the muon spin relaxation was qualitatively changed and showed large missing asymmetry below about 89 K, where the correlation clearly implied short-range spin order. There could be a preparative phenomenon of the phase transition or an anisotropic short-range spin correlation.

Fact-finding survey on the competencies and literacy of radiological technologists regarding radiation disasters

新井 知大*; 村田 歩*; 渡邊 雄一*; 石原 敏裕*; 深水 良哉*; 武田 聡司*; 江端 清和*; 渡邊 裕貴; 高島 良生*; 金子 順一*

Journal of X-Ray Science and Technology, 31(2), p.237 - 245, 2023/03

https://doi.org/10.3233/XST-221341

診療放射線技師は、放射線に関する専門的な教育を受けており、医療領域における放射線業務に従事するとともに、患者が抱える放射線被ばくに関する不安の軽減に努めるリスクコミュニケーターとしての役割も担っている。また、2011年3月の福島第一原子力発電所事故の際、避難者の体表面及び携行物品の放射性物質の汚染検査要員として、全国各地域の診療放射線技師が派遣された。本研究では、国立病院機構に所属する診療放射線技師を対象として放射線災害に関する知識及び意識に関する実態調査を実施することにより、放射線災害に関する診療放射線技師のリテラシー及びコンピテンシーを明らかにした。また、日本の診療放射線技師の放射線災害に関する知識及び意識を、原子力発電所の立地地域(隣接地域含む)と非立地地域で比較し、放射線災害に対応可能な診療放射線技師の人材育成の在り方について検討した。

Development of plant lifecycle optimization method, ARKADIA for advanced reactors

内堀 昭寛; 曽我部 丞司; 岡野 靖; 高田 孝*; 堂田 哲広; 田中 正暁; 江沼 康弘; 若井 隆純; 浅山 泰; 大島 宏之

Proceedings of Technical Meeting on State-of-the-art Thermal Hydraulics of Fast Reactors (Internet), 10 Pages, 2022/09

ナトリウム冷却高速炉に代表される革新炉に対し、安全性評価やそれに基づく設計最適化を自動に行うARKADIAを開発している。通常運転もしくは設計基準事象の範囲で設計最適化を行うARKADIA-Designについては、核特性-熱流動-炉心変形の連成解析手法等を中心技術として開発し、その基本的機能を確認した。シビアアクシデントまでの範囲で安全性評価を行うARKADIA-Safetyの基盤技術として、炉内/炉外事象一貫解析手法の整備を進め、仮想的なシビアアクシデント事象を解析することで基本的機能を確認した。

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。

適合細分化格子ボルツマン法に基づく都市風況解析コードのNVIDIA及びAMDのGPUにおける性能移植性評価

朝比 祐一; 小野寺 直幸; 長谷川 雄太; 下川辺 隆史*; 芝 隼人*; 井戸村 泰宏

計算工学講演会論文集(CD-ROM), 27, 5 Pages, 2022/06

都市風況解析コードCityLBMをAMD社のMI100 GPUへと移植し、CityLBMの性能をNVIDIA P100, V100, A100およびAMD MI100において測定した。ホスト間でのMPI通信を利用した場合、CityLBMの性能はMI100においてV100と比べ20%程度向上した。適合細分化格子法に起因する補間カーネルを除く演算カーネルでは、MI100においてV100と比べ性能向上を確認した。