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Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state

山根 祐一

Journal of Nuclear Science and Technology, 14 Pages, 2022/04



Acceleration of fusion plasma turbulence simulations using the mixed-precision communication-avoiding Krylov method

井戸村 泰宏; 伊奈 拓也*; Ali, Y.*; 今村 俊幸*

Proceedings of International Conference for High Performance Computing, Networking, Storage, and Analysis (SC 2020) (Internet), p.1318 - 1330, 2020/11

5次元ジャイロ運動論モデルに基づく次世代核融合実験炉ITERのマルチスケールfull-$$f$$シミュレーションは核融合科学において最も計算コストが大きい問題の一つである。本研究では、新しい混合精度省通信クリロフ法を用いてジャイロ運動論的トロイダル5次元オイラーコードGT5Dを高速化した。演算加速環境における大域的集団通信のボトルネックを省通信クリロフ法によって解決した。これに加えて、A64FXにおいて新たにサポートされたFP16SIMD演算を用いて設計された新しいFP16前処理により、反復(袖通信)の回数と計算コストの両方を削減した。富岳とSummitにおける1,440CPU/GPUを用いた1,000億格子のITER規模シミュレーションに対して、提案手法の処理性能は従来の非省通信クリロフ法に比べてそれぞれ2.8倍, 1.9倍高速化され、5,760CPU/GPUまで良好な強スケーリングを示した。


A Linear Equation of characteristic time profile of power in subcritical quasi-steady state

山根 祐一

Journal of Nuclear Science and Technology, 57(8), p.926 - 931, 2020/08

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)



Behavior of high-burnup advanced LWR fuel cladding tubes under LOCA conditions

成川 隆文; 天谷 政樹

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.912 - 921, 2019/09

To evaluate behavior of high-burnup advanced light-water-reactor fuel cladding tubes under loss-of-coolant accident conditions, laboratory-scale isothermal oxidation tests and integral thermal shock tests were performed using the following advanced fuel cladding tubes with burnups of 73-85 GWd/t: M-MDA$textsuperscript{texttrademark}$, low-tin ZIRLO$textsuperscript{texttrademark}$, M5textregistered, and Zircaloy-2 (LK3). The isothermal oxidation tests were performed in steam-flowing conditions at temperatures ranging from 1173 to 1473 K for durations between 120 and 4000 s. The oxidation kinetics of the high-burnup advanced fuel cladding tube specimens was comparable to or slower than that of the unirradiated Zircaloy-4 cladding tube and was slower than that given by the Baker-Just oxidation rate equation. Therefore, the oxidation kinetics is considered to be not significantly accelerated by extending the burnup and changing the alloy composition. During the integral thermal shock tests, the high-burnup advanced fuel cladding tube specimens did not fracture under the oxidation condition equivalent to or lower than the fracture limit of the unirradiated Zircaloy-4 cladding tube. Therefore, the fracture limit of fuel cladding tubes is considered to be not significantly reduced by extending the burnup and changing the alloy composition, though it may slightly decrease with increasing initial hydrogen concentration.


Oxidation behavior of high-burnup advanced fuel cladding tubes in high-temperature steam

成川 隆文; 天谷 政樹

Journal of Nuclear Science and Technology, 56(7), p.650 - 660, 2019/07

 被引用回数:6 パーセンタイル:81.33(Nuclear Science & Technology)

To evaluate the oxidation behavior of high-burnup advanced fuel cladding tubes in high-temperature steam, laboratory-scale isothermal oxidation tests were conducted using the following advanced fuel cladding tubes with burnups of up to 85 GWd/t: M-MDA$textsuperscript{texttrademark}$, low-tin ZIRLO$textsuperscript{texttrademark}$, M5$textsuperscript{textregistered}$, and Zircaloy-2 (LK3). These oxidation tests were performed in steam-flowing conditions at temperatures ranging from 1173 to 1473 K for durations between 120 and 4000 s, and the oxidation kinetics was evaluated. The oxidation kinetics of the high-burnup advanced fuel cladding tube specimens estimated by assuming the parabolic rate law was comparable to or slower than that of the unirradiated Zircaloy-4 cladding tube specimens reported in a previous study. It is considered that the protective effect of the corrosion layer hindered oxidation. Furthermore, no increase in the oxidation kinetics because of the pre-hydriding was observed. The onset times of the breakaway oxidations of these cladding tube specimens were comparable to those of the unirradiated Zircaloy-4 cladding tubes reported in previous studies. Therefore, it is considered that the burnup extension up to 85 GWd/t and the use of the advanced fuel cladding tubes do not significantly increase the oxidation kinetics and do not significantly reduce the onset time of the breakaway oxidation.


Synergy of turbulent and neoclassical transport through poloidal convective cells

朝比 祐一*; Grandgirard, V.*; Sarazin, Y.*; Donnel, P.*; Garbet, X.*; 井戸村 泰宏; Dif-Pradalier, G.*; Latu, G.*

Plasma Physics and Controlled Fusion, 61(6), p.065015_1 - 065015_15, 2019/05

 被引用回数:3 パーセンタイル:40.69(Physics, Fluids & Plasmas)



Thorium oxide dissolution in HNO$$_{3}$$-HF mixture; Kinetics and mechanism

Simonnet, M.; Barr$'e$, N.*; Drot, R.*; Le Naour, C.*; Sladkov, V.*; Delpech, S.*

Radiochimica Acta, 107(4), p.289 - 297, 2019/04

 被引用回数:1 パーセンタイル:23.13(Chemistry, Inorganic & Nuclear)

This paper is an attempt to find out thorium oxide dissolution mechanism in HNO$$_{3}$$-HF mixture. In a previous paper, several parameters effects on thorium oxide dissolution have been described, with specific focus on hydrofluoric acid effect, which can lead to an increase of the dissolution rate if present in small amount, but precipitates as ThF$$_{4}$$ at higher content. Based on this previous study, experimental data were fitted using several dissolution models in order to find out the best one. Finally, a revisited model based on literature and considering the ThF$$_{4}$$ formation was proposed. It describes the main steps of dissolution and is able to fit the experimental data for a wide range of solution compositions. This point is crucial since it allows considering an extrapolation of the established model to not-yet-studied conditions.


The Influence of the air fraction in steam on the growth of the columnar oxide and the adjacent $$alpha$$-Zr(O) layer on Zry-4 fuel cladding at 1273 and 1473 K

Negyesi, M.; 天谷 政樹

Annals of Nuclear Energy, 114, p.52 - 65, 2018/04

 被引用回数:3 パーセンタイル:45.99(Nuclear Science & Technology)

The growth kinetics of the columnar oxide and $$alpha$$-Zr(O) layers of Zry-4 under mixed steam-air conditions at temperatures of 1273 and 1473 K were investigated in this study be means of post-test metallographic measurements. The hydrogen uptake was also determined by the inert gas fusion technique. The kinetics of the columnar oxide layer obeyed a parabolic law for all air fractions at both temperatures. The kinetics of $$alpha$$-Zr(O) layer appeared to deviate slightly from the parabolic law. The parabolic oxidation rate constant of the columnar oxide increased with increasing air fraction, whereas the parabolic oxidation rate constant of $$alpha$$-Zr(O) layer seemed to be independent of the air fraction. Mixed steam-air conditions appeared to enhance hydrogen absorption substantially, especially after the columnar oxide lost its protectiveness.


Evaluation of feedback reactivity coefficients by inverse kinetics in Monju

北野 彰洋; 中島 健*

Proceedings of 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) (CD-ROM), p.1205 - 1210, 2018/04



Oxidation kinetics of Zry-4 fuel cladding in mixed steam-air atmospheres at temperatures of 1273 - 1473 K

Negyesi, M.; 天谷 政樹

Journal of Nuclear Science and Technology, 54(10), p.1143 - 1155, 2017/10

 被引用回数:5 パーセンタイル:58.67(Nuclear Science & Technology)

This paper deals with the oxidation behavior of Zry-4 nuclear fuel cladding tubes in mixed steam_air atmospheres at temperatures of 1273 and 1473 K. The main goal is to study the oxidation kinetics of Zry-4 fuel cladding in dependence on the air fraction in steam in the range from 0 up to 100%. The purpose of this study is to provide experimental data suitable for an oxidation correlation applicable for thermomechanical analysis codes of nuclear power reactor under severe accidents. The influence of the air addition in steam on parameters of Zry-4 kinetic equation has been quantified using the results of weight gain measurements. At 1273 K, both pre-transient and post-transient regimes were treated. The results of weight gain measurements showed a strong dependence of the Zry-4 oxidation kinetics on the air fraction in steam, especially at 1473 and at 1273 K in the post-transient regime.


Development of experimental and analytical technologies for fission product chemistry under LWR severe accident condition

宮原 直哉; 三輪 周平; 中島 邦久; 逢坂 正彦

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 9 Pages, 2017/09



Determination of reactivity and neutron flux using modified neural network for HTGR

Subekti, M.*; 工藤 和彦*; 鍋島 邦彦; 高松 邦吉

Atom Indonesia, 43(2), p.93 - 102, 2017/08

HTTR炉心の中心制御棒を引き抜く反応度添加抜試験を評価する際、1点炉近似の動特性モデルを用いた解析手法は、最も汎用的である。一方、制御棒が引き抜かれると同時に、将来の反応度および中性子束の変化予測値を速やかに出力するには、非常に速い処理速度を持つ別の解析手法を必要とする。そこで、Time Delayed Neural Network (TDNN)とJordan Recurrent Neural Network (JordanRNN)を組み合わせ、新たにTD-Jordan RNNというニューラルネットワーク・モデルを作成し、HTTRの試験データをオフラインで十分学習させた。その結果、反応度添加試験時の反応度および中性子束の変化予測値を速やかに出力することができた。


Optimization of fusion kernels on accelerators with indirect or strided memory access patterns

朝比 祐一*; Latu, G.*; 伊奈 拓也; 井戸村 泰宏; Grandgirard, V.*; Garbet, X.*

IEEE Transactions on Parallel and Distributed Systems, 28(7), p.1974 - 1988, 2017/07

 被引用回数:4 パーセンタイル:50.79(Computer Science, Theory & Methods)

セミ・ラグランジュ法における間接メモリアクセス、有限差分法におけるストライドメモリアクセスといった複雑なメモリアクセスパターンを有する核融合プラズマ乱流コードの高次元ステンシル計算をGPGPUやXeon Phiプロセッサ等の演算加速器上で最適化した。どちらのデバイスでも、Array of Structure of Array (AOSOA)データレイアウトが連続的なメモリアクセスに有効である。Xeon Phiでは時空間データ局所性の向上によるローカルキャッシュの効率的利用が必要不可欠である。GPGPUではテクスチャメモリの利用がセミ・ラグランジュ法の間接メモリアクセス性能を向上する。これらの最適化により、アクセラレータ用核融合カーネルはCPU用カーネルに比べてSandy Bridge (CPU)用最適化コードに比べて1.4x - 8.1x高速化した。


Formation and release of molecular iodine in aqueous phase chemistry during severe accident with seawater injection

城戸 健太朗; 端 邦樹; 丸山 結; 西山 裕孝; 星 陽崇*

NEA/CSNI/R(2016)5 (Internet), p.204 - 212, 2016/05

Seawater injection into the degraded core is one of the measures of accident management as it has been performed at Fukushima Daiichi Nuclear Power Plant. The constituents of seawater deeply relates to the iodine chemistry in the water pool of the suppression chamber, which indicates that it is important to assess their effect on the source term in a severe accident. In the present study, by employing a four-component seawater (SW) model we try to simulate the I$$_2$$ molecules yielding in aqueous solution as the function of time, based on several datasets about chemical reaction kinetics and to evaluate its fraction of the initial inventory released from the solution to gas phase. The amount of I$$_2$$ molecule in gas phase was in proportion as the SW mixing ratio. The combination of bromide and hydrogen-carbonate anions considerably contributes to the behavior of the history of producing I$$_2$$ gas. The oxygen molecules solved from air drastically reduced yielding I$$_2$$ gas by catalytically consuming hydroxyl radicals, while the I$$_2$$ gas increased by the carbon dioxide gas contained in air. The effects of SW and carbon dioxide gas are recommended to be considered in the quantitative discussion about I$$_2$$ gas released from aqueous solution.


Boron release kinetics from mixed melts of boron carbide, stainless steel and Zircaloy; A Literature review on the behavior of control rod materials under severe accidents

Di Lemma, F. G.; 三輪 周平; 逢坂 正彦

JAEA-Review 2016-007, 27 Pages, 2016/03




Development of fast reactor containment safety analysis code, CONTAIN-LMR, 3; Improvement of sodium-concrete reaction model

河口 宗道; 土井 大輔; 清野 裕; 宮原 信哉

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05



Experiments and validation analyses of HTTR on loss of forced cooling under 30% reactor power

高松 邦吉; 栃尾 大輔; 中川 繁昭; 高田 昌二; Yan, X.; 沢 和弘; 坂場 成昭; 國富 一彦

Journal of Nuclear Science and Technology, 51(11-12), p.1427 - 1443, 2014/11

 被引用回数:9 パーセンタイル:65.28(Nuclear Science & Technology)



Global profile effects and structure formations in toroidal electron temperature gradient driven turbulence

井戸村 泰宏; 徳田 伸二; 岸本 泰明

Nuclear Fusion, 45(12), p.1571 - 1581, 2005/12

 被引用回数:38 パーセンタイル:76.55(Physics, Fluids & Plasmas)



微視的乱流の$$delta f$$シミュレーション

井戸村 泰宏

プラズマ・核融合学会誌, 81(8), p.581 - 592, 2005/08

ジャイロ運動論的粒子シミュレーションはトカマクプラズマの微視的乱流を研究するための有効な手段である。ジャイロ運動論的粒子シミュレーションにおける標準的な手法となっている$$delta f$$法は、粒子ノイズの低減により粒子シミュレーションの効率を大幅に向上させ、完全トーラス配位の乱流シミュレーションを可能にした。本稿では$$delta f$$法を概説し、完全トーラス配位のジャイロ運動論的粒子シミュレーションにおける問題点を議論する。


Recent advances in nonlinear gyrokinetic PIC simulations in tokamak geometry

Bottino, A.*; Angelino, P.*; Allfrey, S. J.*; Brunner, S.*; Hatzky, R.*; 井戸村 泰宏; Jolliet, S.*; Sauter, O.*; Tran, T. M.*; Villard, L.*

Theory of Fusion Plasmas, ISPP21, p.75 - 86, 2004/00


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