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正木 信男*; 室田 伸夫*; 加藤 亨二*; 岡村 茂樹; 山本 智彦; 内田 昌人*; 藤田 聡*
日本建築学会技術報告集, 31(78), p.687 - 692, 2025/06
実際の免震建物に55.2年設置された天然ゴム系の厚肉積層ゴムのクリープ特性を、既存測定データと新規測定データを用いて推定した。JIS K6410-2で推奨されている単回帰分析での結果、平均クループ変位特性はべき乗則で説明できることが分かった。その回帰式より、建物に設置された厚肉積層ゴムの平均クリープ量は3.4mmと推定された。その結果から、JIS K6410-2の方法は、クリープ変位の予測に役立つものと考えられる。
渡壁 智祥; 山本 智彦; 岡村 茂樹; 宮崎 真之; 宮川 高行; 内田 昌人*; 平山 智之*; 杣木 孝裕*; 湯川 正貴*; 深沢 剛司*; et al.
Proceedings of ASME 2024 Pressure Vessels & Piping Conference (PVP 2024) (Internet), 10 Pages, 2024/07
ナトリウム冷却高速炉では、薄肉の機械部品や配管の耐震安全性を厳しい設計地震レベルで確保するため、3次元免震装置を開発している。開発成果の進捗をシリーズ(Part7
Part9)発表する。Part7では、研究開発の全体概要、各要素を組み立てた状態での3次元免震装置の試験計画、および構成要素の性能について紹介する。Part8では、各要素を組み立てた状態での3次元免震装置の性能を負荷試験を通じて調査した。Part9では、試験結果で得た知見に基づき検証した解析モデルによる3次元免震装置の効果を報告する。
深沢 剛司*; 杣木 孝裕*; 湯川 正貴*; 平山 智之*; 渡壁 智祥; 山本 智彦; 岡村 茂樹; 宮崎 真之; 内田 昌人*; 宮川 高行; et al.
Proceedings of ASME 2024 Pressure Vessels & Piping Conference (PVP 2024) (Internet), 10 Pages, 2024/07
This paper elucidates the isolation performance of a newly developed three-dimensional seismic isolation system through seismic response analysis. A novel three-dimensional isolation system was developed and assessed through static loading tests, aiming to unveil the hysteresis loops for each element, labeled Part 1 to Part 6. To ascertain the design feasibility of the isolation system, static loading tests were judiciously conducted, considering a wide array of loading conditions, including the beyond-design basis ground motion. Employing the accumulated test data, a new analytical model was devised, capable of precisely capturing the hysteresis loops for each element. Evaluating the seismic isolation performance based on the static loading results of the entire system posed a notable challenge. Nevertheless, the hysteresis characteristics of the overall system in both horizontal and vertical directions were elucidated using a static loading test with a half-scale model, as detailed in Part 7 and Part 8. The authors conducted a seismic response analysis, leveraging the analytical models identified by the static loading test results obtained from the half-scale model. This paper demonstrates that our isolation system exhibits superior isolation performance against both the design basis and beyond-design basis ground motions when compared to a horizontal isolation system consisting of rubber bearings and oil dampers.
杣木 孝裕*; 湯川 正貴*; 深沢 剛司*; 平山 智之*; 内田 昌人*; 宮川 高行; 岡村 茂樹; 山本 智彦; 渡壁 智祥; 宮崎 真之; et al.
Proceedings of ASME 2024 Pressure Vessels & Piping Conference (PVP 2024) (Internet), 9 Pages, 2024/07
The authors have been developing the three-dimensional isolation system for the Sodium-cooled Fast Reactor. The three-dimensional isolation device consists of the laminated rubber bearing performing the horizontal isolation function, four-disc spring units, the sliding function, strength members such as the horizontal support function, and dampers in the horizontal and vertical directions. We carried out the half-scaled integrated seismic tests under several bi-axial severe conditions from design base loads to significantly exceeding design base loads. The test specimen was assembled elements consisting of Three-Dimensional Seismic Isolation System, but the horizontal and vertical damping devices were not modeled because of the static tests. We report tests results, focusing on the following items. Behavior of smooth operation and ensuring the independency of horizontal isolation and vertical isolation performances. Hypothesis and verification of load transfer mechanism under horizontal and vertical loads superposition. Effect of reinforcing plates on the loading force reduction of horizontal support function. Conditions of the specimen after tests and discussion.
池末 俊一*; 岩崎 晃久*; 佐郷 ひろみ*; 横井 忍*; 山本 智彦
Proceedings of ASME 2024 Pressure Vessels and Piping Conference (PVP 2024) (Internet), 9 Pages, 2024/07
During an earthquake, sloshing occurs in a cylindrical tank when a frequency component close to the natural frequency of sloshing is included in the seismic wave. When high amplitude sloshing occurs, the free liquid surface level fluctuates greatly in the tank, and the liquid surface collides with the roof of the tank. In tank design, it is important to evaluate the sloshing load acting on the roof. In this study, we extended this method to deal with seismic wave excitation. In seismic wave excitation, the tank is excited by irregular wave, and the phenomenon of sloshing becomes more complicated than sinusoidal excitation. To simplify this complicated phenomenon, we proposed a concept of equivalent growth wave number. This number represents the magnitude of the increase in the peak of liquid surface level, during seismic wave excitation. We proposed a method to quantitatively evaluate this number from seismic response analysis. In addition, we proposed a method to evaluate the vertical load on the roof during seismic wave excitation, by introducing this number into the predictive evaluation method.
山本 智彦; 渡壁 智祥; 宮崎 真之; 岡村 茂樹; 宮川 高行; 横井 忍*; 深沢 剛司*; 藤田 聡*
Mechanical Engineering Journal (Internet), 11(2), p.23-00393_1 - 23-00393_21, 2024/04
A sodium-cooled fast reactor (SFR) considers adopting 3-dimensional seismic isolation devices for withstanding seismic loads not only horizontal but also vertical direction. A seismic isolation device consists of a laminated rubber bearing and horizontal oil dampers for horizontal direction, coned disc springs and vertical oil dampers for vertical direction, respectively. In order to investigate the performance of each component and the feasibility of integrated system for SFR, the experiments such as load-displacement tests, vibrating tests, etc., to each component of seismic isolation devices and seismic response analysis are carried out. As those experimental results, the mechanical characteristics of each component and the devices are grasped, then it is demonstrated that components and devices have expected performances to reduce the seismic loading within the design range. As the analytical results of seismic response, it is indicated that this 3-dimesional seismic isolation device and system can reduce the seismic response on horizontal and vertical simultaneously. Based on the analytical studies and experimental results, the feasibility of newly developed 3-dimensional seismic isolation system is obtained and the prospect of practical application of 3D seismic isolation system for fast reactor is implied in this paper.
山本 智彦; 加藤 篤志; 早川 雅人; 下山 一仁; 荒 邦章; 畠山 望*; 山内 和*; 江田 優平*; 由井 正弘*
Nuclear Engineering and Technology, 56(3), p.893 - 899, 2024/03
被引用回数：1 パーセンタイル：43.12(Nuclear Science & Technology)In a secondary cooling system of a sodium-cooled fast reactor (SFR), rapid detection of hydrogen due to sodium-water reaction (SWR) caused by water leakage from a heat exchanger tube of a steam generator (SG) is important in terms of safety and property protection of the SFR. For hydrogen detection, the hydrogen detectors using atomic transmission phenomenon of hydrogen within Ni-membrane were used in Japanese proto-type SFR "Monju." However, during the plant operation, detection signals of water leakage were observed even in the situation without SWR concerning temperature up and down in the cooling system. For this reason, the study of a new hydrogen detector has been carried out to improve stability, accuracy and reliability. In this research, the authors focus on the difference in composition of hydrogen and the difference between the background hydrogen under normal plant operation and the one generated by SWR and theoretically estimate the hydrogen behavior in liquid sodium by using ultra-accelerated quantum chemical molecular dynamics (UA-QCMD). Based on the estimation, dissolved H or NaH, rather than molecular hydrogen (H
), is the predominant form of the background hydrogen in liquid sodium in terms of energetical stability. On the other hand, it was found that hydrogen molecules produced by the sodium-water reaction can exist stably as a form of a fine bubble concerning some confinement mechanism such as a NaH layer on their surface. In parallel, we observed experimentally that the fine bubbles of H stably existed in the liquid sodium than expected before. This paper describes the comparison between the theoretical estimation and experimental results based on hydrogen form in sodium in the development of the new hydrogen detector in Japan.
山本 智彦; 岡村 茂樹; 平山 智之*; 杣木 孝裕*
配管技術, 65(13), p.1 - 4, 2023/11
将来のナトリウム冷却高速炉の耐震性向上に向けて、3次元免震装置の研究開発を実施している。本稿においては、装置の概要とその利用方法について紹介する。
深沢 剛司*; 山本 智彦; 内田 昌人*; 平山 智之*
第10回構造物の安全性・信頼性に関する国内シンポジウム(JCOSSAR2023)講演論文集(インターネット), p.135 - 142, 2023/10
ナトリウム冷却高速炉の耐震性を向上させるために、水平免震システムが研究されている。しかし、水平方向だけでなく垂直方向の地震力を軽減するには課題が生じる。著者らはこの問題を解決するために、新しい三次元免震システムを開発した。この設計の実現可能性を評価するために、1/2スケールの試験体を製作し、最大軸力8000kNの静荷重試験を使用して力と変位の関係が評価した。また、水平方向の減衰要素として水平オイルダンパーを製作し、最大速度2.7m/sの加振試験により減衰力を評価した。この論文では、これらのテストの結果を報告する。
深沢 剛司*; 平山 智之*; 横井 忍*; 廣田 昭彦*; 杣木 孝裕*; 湯川 正貴*; 宮川 高行; 内田 昌人*; 山本 智彦; 宮崎 真之; et al.
日本機械学会論文集(インターネット), 89(924), p.23-00023_1 - 23-00023_17, 2023/08
ナトリウム冷却高速炉の耐震性向上の観点で研究開発を進めている3次元免震装置開発に関して、そのシステムの概要を述べるとともに、1/2縮尺試験体を用いた静的載荷試験結果について、その知見を述べる。
池末 俊一*; 森田 英之*; 佐郷 ひろみ*; 横井 忍*; 山本 智彦
Proceedings of ASME 2023 Pressure Vessels and Piping Conference (PVP 2023) (Internet), 10 Pages, 2023/07
When a cylindrical tank is excited by seismic waves, the motion of free liquid surface, called sloshing, may occur inside the tank. When the high-amplitude sloshing occurs, the free liquid surface collides with the roof of cylindrical tank, and the impulsive vertical load acts on the roof. In this study, the cause of this extremely large load was discussed by analyzing the CFD analysis result. As a result, it was showed that the previous weak roof collision deformed the liquid surface into a flat shape and the flat liquid surface collided with the roof. The phenomenon caused the extremely large load acting on the roof. From this result, it was clarified that the history of roof collision has a large influence on the vertical load acting on the roof.
森 隆*; 島田 貴弘*; 甲斐 聡流*; 大谷 章仁*; 山本 智彦; Yan, X.
Proceedings of ASME 2023 Pressure Vessels and Piping Conference (PVP 2023) (Internet), 8 Pages, 2023/07
Experiment of a floating seismic isolation technology for application to small modular reactor (SMR) is conducted on a small-scale apparatus. The SMR is assumed to be located on land rather than offshore, and installed on a newly proposed floating structure in a pool. The floating structure is designed acts to mitigate the propagation of the horizontal component of seismic motion between the ground and the SMR buildings, and to reduce the excitation force on the buildings caused by the vertical wave propagation through water of vertical seismic motion. The floating structure was designed to have a gaseous space called Air Cavity and orifice at the bottom of the structure. Experiment is conducted to verify the effect of the floating structure on reduction to vertical seismic motions. The results demonstrate the effectiveness of the Air Cavity and orifice to reduce response during vertical earthquake motion, and those method is more reduce response than Compared to using only Air Cavity. Thus these method were founds an isolating effect against vertical seismic motion, and it is considered that result in this study will help SMR.
山本 智彦; 渡壁 智祥; 宮崎 真之; 宮川 高行*; 横井 忍*; 岡村 茂樹*; 深沢 剛司*; 藤田 聡*
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 7 Pages, 2023/05
A sodium-cooled fast reactor (SFR) considers adopting 3-dimensional seismic isolation devices for withstanding seismic loads not only horizontal but also vertical direction. In order to investigate the performance of each component and the feasibility of integrated system for SFR, the experiments to each component of seismic isolation devices and seismic response analysis are carried out. As those experimental results, the mechanical characteristics of each component and the devices are grasped. As the analytical results of seismic response, it is indicated that this 3-dimesional seismic isolation device and system can reduce the seismic response on horizontal and vertical simultaneously. Based on the analytical studies and experimental results, the feasibility of newly developed 3-dimensional seismic isolation system is obtained and the prospect of practical application of 3D seismic isolation system for fast reactor is implied in this paper.
森 隆*; 島田 貴弘*; 甲斐 聡流*; 大谷 章仁*; 山本 智彦; Yan, X.
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 8 Pages, 2023/05
Experiment of a floating seismic isolation technology for application to small modular reactor (SMR) is conducted on a small-scale apparatus. The SMR is assumed to be located on land rather than offshore, and installed on a newly proposed floating structure in a pool. The floating structure is designed acts to mitigate the propagation of the horizontal component of seismic motion between the ground and the SMR buildings, and to reduce the excitation force on the buildings caused by the vertical wave propagation through water of vertical seismic motion. The floating structure was designed to have a gaseous space called Air Cavity at the bottom of the structure. Experiment is conducted to verify the effect of the floating structure on reduction to horizontal and vertical seismic motions. The results demonstrate the effectiveness of the Air Cavity to reduce response during vertical earthquake motion, thus providing an isolating effect against vertical seismic motion. Furthermore, the reduction in response during vertical seismic motion varies with the air volume in the Air Cavity, indicating that the volume modulus of elasticity is an important parameter to determining the seismic reduction performance of the floating structure.
山本 智彦; 加藤 篤志; 早川 雅人; 下山 一仁; 荒 邦章; 畠山 望*; 山内 和*; 江田 優平*; 由井 正弘*
Proceedings of 2023 International Congress on Advanced in Nuclear Power Plants (ICAPP 2023) (Internet), 6 Pages, 2023/04
In the secondary cooling system of sodium-cooled fast reactor (SFR), a rapid detection of hydrogen explosion due to sodium-water reaction by water leakage from heat exchanger tube is steam generator (SG) is important in terms of safety and property protection. For the hydrogen detection, Ni-membrane hydrogen detectors using atomic transmission phenomenon were used in Japanese proto-type sodium-cooled fast reactor "Monju". However, during the plant operation, many alarms of water leakage were occurred without sodium-water reaction in relation to temperature up and down. The authors focus on the difference in composition of hydrogen and the difference between the background hydrogen under normal operation and the hydrogen generated by the sodium-water reaction and theoretically estimate the hydrogen behavior in liquid sodium by using ultra-accelerated quantum chemical molecular dynamics (UA-QCMD). As the results of theoretical estimation, dissolved H or NaH, rather than H, is the predominant form of the background hydrogen in liquid sodium, and hydrogen produced in large amounts by sodium-water reaction can exist stably as fine bubbles with a NaH layer on their surface. Currently, the authors study the new hydrogen detector system focusing on the difference between the background hydrogen (dissolved H) and the hydrogen by sodium-water reaction (fine bubbles H). This paper describes the comparison between the theoretical estimation and experimental results based on hydrogen form in sodium.
池末 俊一*; 森田 英之*; 石井 秀和*; 佐郷 ひろみ*; 横井 忍*; 山本 智彦
Proceedings of ASME 2022 Pressure Vessels and Piping Conference (PVP 2022) (Internet), 10 Pages, 2022/07
When cylindrical tanks installed in the ground receive strong seismic waves, motion of the free liquid surface inside the tank called sloshing may occur. If the high-amplitude sloshing occurs and the waves collide with the tank roof, it may lead to accidents such as damage of the tank roof or outflow of internal liquid of the tank. Therefore the Predictive Evaluation Method is important. This paper describes that the evaluation method is reconstructed for improving these underestimation and overestimation. In this method, the impact pressure model is reconstructed by direct evaluation model of liquid spreading velocity focused on circumferential direction, which is derived from the simplified evaluation model of nonlinear sloshing liquid surface. The validity of this method was confirmed by comparing them with experiments. And future issues on the improvement of the method were clarified from the result.
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
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。
加藤 篤志; 山本 智彦; 安藤 将人; 近澤 佳隆; 村上 久友*; 大山 一弘*; 金子 文彰*; 日暮 浩一*; Chanteclair, F.*; Chenaud, M.-S.*; et al.
EPJ Nuclear Sciences & Technologies (Internet), 8, p.11_1 - 11_10, 2022/06
本稿はナトリウム冷却炉のプラントシステムに採用する技術について、仏国のアストリッド炉等を基にして日仏の技術仕様共通化を検討し、共通プラントの構築に係る検討の成果をまとめている。特に地震条件の違いに対応した原子炉構造設計では、日本側で採用している高周波設計を日仏で共有し、適応を試みている。その他、蒸気発生器、崩壊熱除去システム、燃料取り扱いシステム、および格納容器の仕様共通化の検討を紹介する。
深沢 剛司*; 杣木 孝裕*; 宮川 高行*; 内田 昌人*; 山本 智彦; 石塚 太*; 鈴野 哲司*; 岡村 茂樹*; 藤田 聡*
構造工学論文集,B, 68B, p.462 - 475, 2022/04
The authors developed a three-dimensional seismic isolation system to ensure isolation performance in the vertical and horizontal directions. This isolation system is required for a large-scale disc spring to achieve both the support and isolation functions. This paper describes an optimal combination method of disc springs to absorb the variance caused by the manufacturing process by calibrating the combination using a metaheuristic algorithm. Moreover, a method to identify the variables of the hysteresis loops caused by the combined disc springs is proposed using the metaheuristic algorithm. The applicability of these methods is verified using the static loading tests data obtained by a large-scale disc spring that expands the dimensions defined by the JIS B 2706:2013 and the ISO 19690-1:2017. This paper demonstrates that the proposed method can control the restoring force and identify the variables required for hysteresis loops accurately and efficiently.
正木 信男*; 加藤 亨二*; 山本 智彦; 宮川 高行*; 藤田 聡*; 岡村 茂樹*
日本建築学会技術報告集, 28(68), p.81 - 84, 2022/02
高速炉等の新型炉では機器の耐震性を確保するため、厚肉積層ゴムの採用が検討されているが、厚肉積層ゴムのもつ柔らかな上下剛性は、経年によるゴム物性の変化とクリープに大きく影響されると考える。われわれはゴム物性の変化を考慮できるクリープ評価方法を検討しているが、参照すべき実大かつ実環境下の長期クリープ特性がない。本報告では、厚肉積層ゴムの新たなクリープ評価方法を検討するための第1段階として、この形式の初めての建物である1966年に竣工した厚肉積層ゴム支持の英国防振建物の測定データを集約し厚肉積層ゴムの約47年間のクリープ特性推定の試みについて述べる。
