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Ensemble wind simulations using a mesh-refined lattice Boltzmann method on GPU-accelerated systems

長谷川 雄太; 小野寺 直幸; 井戸村 泰宏

Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA + MC 2020), p.236 - 242, 2020/10



Corrosion in nuclear fuel reprocessing plants; Corrosion in boiling nitric acid

加藤 千明

Comprehensive Nuclear Materials, 2nd Edition, Vol.4, p.528 - 563, 2020/08



Utilizing PUNITA experiments to evaluate fundamental delayed gamma-ray spectroscopy interrogation requirements for nuclear safeguards

Rodriguez, D.; 小泉 光生; Rossi, F.; 瀬谷 道夫; 高橋 時音; Bogucarska, T.*; Crochemore, J.-M.*; Pedersen, B.*; 高峰 潤

Journal of Nuclear Science and Technology, 57(8), p.975 - 988, 2020/08

Present safeguards verification methods of high-radioactivity nuclear material use destructive analysis techniques since passive nondestructive techniques are incapable of determining the nuclear material content. To improve this verification process, the JAEA and EC-JRC Ispra, Italy have been collaborating to develop delayed gamma-ray spectroscopy for composition analysis of the fissile nuclides as an aspect of the MEXT subsidy for improving nuclear security and the like. Multiple experiments were performed over three years using PUNITA to interrogate U and Pu samples to determine the signature from the short-lived fission products. We observed many gamma rays useful to determine the composition of a mixed nuclear material sample. Presented here are the results of these measurements with correlations to the interrogation, mass, volume, and sample homogeneity.


Computational study on the spherical laminar flame speed of hydrogen-air mixtures

Trianti, N.; 茂木 孝介; 杉山 智之; 丸山 結

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 9 Pages, 2020/08

The computational fluid dynamics (CFD) have been developed to analyze the correlation equation for laminar flame speed of hydrogen-air mixtures. This analysis was carried out on the combustion of hydrogen-air mixtures performed at the spherical bomb experiment facility consists of a spherical vessel equipped (563 mm internal diameter). The facility has been designed and built at CNRS-ICARE laboratory. The simulation was carried out using the reactingFoam solver, one of a transient chemical reaction solver in OpenFOAM 5.0. The LaunderSharmaKE model was applied for turbulent flow. The interaction of the chemical reaction with the turbulent flow was taken into account using PaSR (Partial Stirred Reactor) model with 19 elementary reactions for the hydrogen combustion. The initial condition of spherical flame analysis was set so as to be consistent with those of the experiment. The position of the flame front was detected by the steep drop of hydrogen mass fraction in the spherical radii, and the flame propagation velocity was estimated from the time-position relationship. The analysis result showed the characteristic of spherical flame acceleration was qualitatively reproduced even though it has a discrepancy with the experiment. After validating the calculation of spherical experiments, a laminar burning velocity correlation is presented using the same boundary conditions with the variation of hydrogen concentration, temperature, and pressure. The calculation of laminar flame speed of hydrogen-air mixtures by reactingFoam use reference temperature T$$_{rm ref}$$ = 293 K and reference pressure P$$_{rm ref}$$ = 1 atm with validated in the range of hydrogen concentration 6-20%; range of temperature 293-493 K; and range of pressure 1-3 atm.


Kinetic inductance neutron detector operated at near critical temperature

Vu, TheDang; 西村 和真*; 宍戸 寛明*; 原田 正英; 及川 健一; 宮嶋 茂之*; 日高 睦夫*; 奥 隆之; 曽山 和彦; 相澤 一也; et al.

Journal of Physics; Conference Series, 1590, p.012036_1 - 012036_9, 2020/07

Our CB-KID neutron imager detects high spatial resolution neutrons transmission images by using a delay-line technique. We found that the number of events was remarkably increased with increasing the detector temperature until close to the critical temperature Tc. We investigated the properties of CB-KID at near Tc. We observed systematic changes of neutron signals as a function of the detector temperature from 4 K to Tc. The simulations modeled the sequential physical processes for $$^{10}$$B(n,$$alpha$$)$$^{7}$$Li reactions and energy deposition by particles within CB-KID, including neutrons, $$^{4}$$He particles, $$^{7}$$Li particles, photon and electron transport.



小野寺 直幸; 井戸村 泰宏; Ali, Y.*; 下川辺 隆史*; 青木 尊之*

第25回計算工学講演会論文集(CD-ROM), 4 Pages, 2020/06



Self-shielding effect of double heterogeneity for plutonium burner HTGR design

深谷 裕司; 後藤 実; 大橋 弘史

Annals of Nuclear Energy, 138, p.107182_1 - 107182_9, 2020/04

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)




青木 尊之*; 長谷川 雄太

自動車技術, 74(4), p.18 - 23, 2020/04



Development of experimental technology for simulated fuel-assembly heating to address core-material-relocation behavior during severe accident

阿部 雄太; 山下 拓哉; 佐藤 一憲; 中桐 俊男; 石見 明洋

Journal of Nuclear Engineering and Radiation Science, 6(2), p.021113_1 - 021113_9, 2020/04

The authors are developing an experimental technology for simulating severe accident (SA) conditions using simulate fuel material (ZrO$$_{2}$$) that would contribute, not only to Fukushima Daiichi (1F) decommissioning, but also to enhance the safety of worldwide existing and future nuclear power plants through clarification of accident progression behavior. Nontransfer (NTR) type plasma, which has been in practical use with a large torch capacity as high as 2 MW, has the potential to heat subject materials to very high temperatures without selecting the target to be heated. When simulating 1F with SA code, the target of this core-material-melting and relocation (CMMR) experiment was to confirm that NTR plasma has a sufficient heating performance realizing large temperature gradients ($$>$$ 2000 K/m) expected under 1F conditions. The authors selected NTR-type plasma-heating technology that has the advantage of continuous heating in addition to its high-temperature level. The CMMR-2 experiments were carried out in 2017 applying the improved technology (higher heating power and controlled oxygen concentration). The CMMR-2 experiment adopted a 30-min heating period, wherein the power was increased to a level where a large temperature gradient was expected at the lower part of the core under actual 1F accident conditions. Most of the control blade and channel box migrated from the original position. After heating, the simulated fuel assembly was measured by X-ray computed tomography (CT) technology and by electron probe micro-analyzer (EPMA). CT pictures and elemental mapping demonstrated its excellent performance with rather good precision. Based on these results, an excellent perspective, in terms of applicability of the NTR-type plasma-heating technology to the SA experimental study, was obtained.


放射性微粒子の基礎物性解明による廃炉作業リスク低減への貢献(委託研究); 平成30年度英知を結集した原子力科学技術・人材育成推進事業

廃炉国際共同研究センター; 茨城大学*

JAEA-Review 2019-041, 71 Pages, 2020/03


日本原子力研究開発機構(JAEA)廃炉国際共同研究センター(CLADS)では、平成30年度英知を結集した原子力科学技術・人材育成推進事業(以下、「本事業」という)を実施している。本事業は、東京電力ホールディングス福島第一原子力発電所の廃炉等をはじめとした原子力分野の課題解決に貢献するため、国内外の英知を結集し、様々な分野の知見や経験を、従前の機関や分野の壁を越えて緊密に融合・連携させた基礎的・基盤的研究及び人材育成を推進することを目的としている。平成30年度の新規採択課題から実施主体を文部科学省からJAEAに移行することで、JAEAとアカデミアとの連携を強化し、廃炉に資する中長期的な研究開発・人材育成をより安定的かつ継続的に実施する体制を構築した。本研究は、研究課題のうち、平成30年度「放射性微粒子の基礎物性解明による廃炉作業リスク低減への貢献」について取りまとめたものである。福島第一原発事故にて放出された放射性微粒子が廃炉手順の確立(溶融燃料等の回収、炉内除染、作業員の安全確保等)に関し重要な炉内事故事象解明のための情報源ともなっている。本研究は、これら粒子の基礎的な物性(粒径, 組成, 電気的性質, 光学的性質など)につき詳細な知見を得るとともに、日英のシナジー研究により$$alpha$$放射体の量的評価を含む放射性微粒子の諸特性をさらに解明して、「廃炉」計画のリスク低減にむけた作業全般に寄与する研究・開発を行う。


Overlapping communications in gyrokinetic codes on accelerator-based platforms

朝比 祐一*; Latu, G.*; Bigot, J.*; 前山 伸也*; Grandgirard, V.*; 井戸村 泰宏

Concurrency and Computation; Practice and Experience, 32(5), p.e5551_1 - e5551_21, 2020/03

 被引用回数:0 パーセンタイル:100(Computer Science, Software Engineering)

2つのジャイロ運動論コード、GYSELA, GKVを最新のアクセラレータ環境、Xeon Phi KNL, Tesla P100 GPUに移植した。一台のSkylakeプロセッサーに比べ、KNLにおけるGYSELAの逐次計算カーネルは1.3x、P100 GPUにおけるGKVの逐次計算カーネルは7.4x高速化された。GYSELAとGKVのスケーリングテストをそれぞれ16-512 KNLおよび32-256 P100 GPUで実施し、GYSELAのセミラグランジアンカーネルおよびGKVの畳み込みカーネルにおけるデータ転置通信が主要なボトルネックとなることがわかった。この通信コストを削減するために、これらのコードにパイプライン法およびタスク並列法に基づく通信オーバーラップを実装した。


Measurement of prompt neutron decay constant with spallation neutrons at Kyoto University Critical Assembly using linear combination method

方野 量太; 山中 正朗*; Pyeon, C. H.*

Journal of Nuclear Science and Technology, 57(2), p.169 - 176, 2020/02

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)



Study on plutonium burner high temperature gas-cooled reactor in Japan; Introduction scenario, reactor safety and fabrication tests of the 3S-TRISO fuel

植田 祥平; 水田 直紀; 深谷 裕司; 後藤 実; 橘 幸男; 本田 真樹*; 齋木 洋平*; 高橋 昌史*; 大平 幸一*; 中野 正明*; et al.

Nuclear Engineering and Design, 357, p.110419_1 - 110419_10, 2020/02

 被引用回数:1 パーセンタイル:21.8(Nuclear Science & Technology)



Monte Carlo radiation transport modelling of the current-biased kinetic inductance detector

Malins, A.; 町田 昌彦; Vu, TheDang; 相澤 一也; 石田 武和*

Nuclear Instruments and Methods in Physics Research A, 953, p.163130_1 - 163130_7, 2020/02

 被引用回数:2 パーセンタイル:7.15(Instruments & Instrumentation)

Radiation transport simulations were used to analyse neutron imaging with the current-biased kinetic inductance detector (CB-KID). The PHITS Monte Carlo code was applied for simulating neutron, $$^{4}$$He, $$^{7}$$Li, photon and electron transport, $$^{10}$$B(n,$$alpha$$)$$^{7}$$Li reactions, and energy deposition by particles within CB-KID. Slight blurring in simulated CB-KID images originated $$^{4}$$He and $$^{7}$$Li ions spreading out in random directions from the $$^{10}$$B conversion layer in the detector prior to causing signals in the $$X$$ and $$Y$$ superconducting Nb nanowire meander lines. 478 keV prompt gamma rays emitted by $$^{7}$$Li nuclei from neutron-$$^{10}$$B reactions had negligible contribution to the simulated CB-KID images. Simulated neutron images of $$^{10}$$B dot arrays indicate that sub 10 $$mu$$m resolution imaging should be feasible with the current CB-KID design. The effect of the geometrical structure of CB-KID on the intrinsic detection efficiency was calculated from the simulations. An analytical equation was then developed to approximate this contribution to the detection efficiency. Detection efficiencies calculated in this study are upper bounds for the reality as the effects of detector temperature, the bias current, signal processing and dead-time losses were not taken into account. The modelling strategies employed in this study could be used to evaluate modifications to the CB-KID design prior to actual fabrication and testing, conveying a time and cost saving.




JAEA-Review 2019-017, 182 Pages, 2020/01





相原 純; 後藤 実; 植田 祥平; 橘 幸男

JAEA-Data/Code 2019-018, 22 Pages, 2020/01




Inner and outer-layer similarity of the turbulence intensity profile over a realistic urban geometry

稲垣 厚至*; Wangsaputra, Y.*; 神田 学*; Y$"u$cel, M.*; 小野寺 直幸; 青木 尊之*

SOLA (Scientific Online Letters on the Atmosphere) (Internet), 16, p.120 - 124, 2020/00

 被引用回数:0 パーセンタイル:100(Meteorology & Atmospheric Sciences)



PARaDIM; A PHITS-based Monte Carlo tool for internal dosimetry with tetrahedral mesh computational phantoms

Carter, L. M.*; Crawford, T. M.*; 佐藤 達彦; 古田 琢哉; Choi, C.*; Kim, C. H.*; Brown, J. L.*; Bolch, W. E.*; Zanzonico, P. B.*; Lewis, J. S.*

Journal of Nuclear Medicine, 60(12), p.1802 - 1811, 2019/12

 被引用回数:2 パーセンタイル:43.67(Radiology, Nuclear Medicine & Medical Imaging)



Application of linear combination method to pulsed neutron source measurement at Kyoto University Critical Assembly

方野 量太; 山中 正朗*; Pyeon, C. H.*

Nuclear Science and Engineering, 193(12), p.1394 - 1402, 2019/12

 被引用回数:2 パーセンタイル:31.52(Nuclear Science & Technology)



GPU acceleration of communication avoiding Chebyshev basis conjugate gradient solver for multiphase CFD simulations

Ali, Y.*; 小野寺 直幸; 井戸村 泰宏; 伊奈 拓也*; 今村 俊幸*

Proceedings of 10th Workshop on Latest Advances in Scalable Algorithms for Large-Scale Systems (ScalA 2019), p.1 - 8, 2019/11

 被引用回数:3 パーセンタイル:3.08


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