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ASME 2012 Pressure Vessels and Piping Conference | 2012

Experimental Study on Free Standing Rack Loading Full Fuel Assembly

Akihisa Iwasaki; Yoshitsugu Nekomoto; Hideyuki Morita; Katsuhiko Taniguchi; Daisaku Okuno; Toshihiro Matsuoka; Naoki Chigusa

The spent fuel storage rack of a nuclear plant stores the spent fuel temporarily before it can be moved to a reprocessing facility. Therefore, the spent fuel storage rack must have a high tolerance against large seismic loads. So, the free standing rack is developed in Japan as other countries. The free standing rack structure incorporates the effect of the friction force on the spent fuel pool floor, and the fluid effect.Under earthquake condition, the free standing rack sliding and rocking motions are induced and the spent fuels rattle in the cells.In this paper, sliding and rocking motions of full-scale rack model having full loading fuel assembly subjected to the seismic excitation are studied. To develop an analysis evaluation method for rack motions, we carried out seismic test of a full-scale rack model using a shaking table, and obtained the fundamental data about the free standing rack.Copyright


ASME 2012 Pressure Vessels and Piping Conference | 2012

Experimental Parameter Study on Free Standing Rack

Akihisa Iwasaki; Yoshitsugu Nekomoto; Hideyuki Morita; Katsuhiko Taniguchi; Daisaku Okuno; Toshihiro Matsuoka; Naoki Chigusa

The spent fuel rack of a nuclear plant stores the spent fuel temporarily before it can be moved to a reprocessing facility. Therefore, the spent fuel rack must have a high tolerance against big seismic loads. Sliding and rocking motions of full-scale rack model having full loading fuel assembly subjected to the seismic excitation are studied [1]. We carried out the seismic test of the free standing rack under some conditions. The distribution of the fuel assembly affects the sliding and rocking motions of the rack, and the outer plate reduces the rack response level by fluid effect. We made sure of them by seismic experiment using a shaking table.In this paper, sliding and rocking motions of full-scale rack model under some conditions are studied. To develop an analysis evaluation method of the rack sliding and rocking motions, we obtained the fundamental data about the free standing rack by seismic test using a shaking table.© 2012 ASME


ASME 2017 Pressure Vessels and Piping Conference | 2017

Core Seismic Experiment and Analysis of Full Scale Single Model for Fast Reactor

Akihisa Iwasaki; Shinichiro Matsubara; Tomohiko Yamamoto; Seiji Kitamura; Hidenori Harada

To design fast reactor (FR) core components, seismic response must be evaluated in order to ensure structural integrity. Generally, the fast reactor core is made of several hundred core elements in hexagonal arrangement. When a big earthquake occurs, large horizontal displacement, vertical displacement (raising) and impact force of each core element may cause a trouble for control rod insertability, reactivity insertion and core element intensity. Therefore, a seismic analysis method of a fast reactor core considering three-dimensional nonlinear behavior, such as bouncing, impact, fluid-structure interaction, etc. was developed. This paper presents a validation of the core element vibration analysis code in three dimensions (REVIAN-3D) for a full scale model. In this validation, the vertical behavior (rising displacement) and horizontal behavior (Impact force, horizontal response) as a single core element of the analysis result agreed very well with the experiments.Copyright


ASME 2016 Pressure Vessels and Piping Conference | 2016

Development of a Core Seismic Analysis Method for a Fast Reactor

Akihisa Iwasaki; Kazuo Hirota; Masatsugu Monde; Shinichiro Matsubara; Iwao Ikarimoto

A fast reactor core consists of several hundreds of core assemblies, which are hexagonal flexible beams embedded at the lower support plate in a hexagonal arrangement, separated by small gaps, and immersed in a fluid. Core assemblies have no support for vertical fixing in order to avoid the influence of thermal expansion and swelling. These days, in Japan, it has become necessary to postulate huge earthquakes in seismic evaluations. If a great earthquake occurs, the large displacement and impact force in each core assembly may cause problems with control rod insertability and core assembly strength. So, it is necessary to grasp the vibration behavior of the core elements during an earthquake in order to appropriately design the core support structures and core elements of a fast reactor. Thus, considering horizontal and vertical forces (impact forces and fluid forces) acting on the core elements during an earthquake, a core seismic analysis method has been developed to evaluate 3D core vibration behavior considering fluid structure interaction and vertical displacements (rising). This paper summarizes the details of the core element vibration analysis code in 3D (REVIAN-3D) that has been developed.Copyright


Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems | 2012

Experimental and Analysis Study of Free Standing Rack Under Seismic Excitation

Katsuhiko Taniguchi; Daisaku Okuno; Akihisa Iwasaki; Yoshitsugu Nekomoto; Toshihiro Matsuoka

For high earthquake resistance and ease of installation, free standing racks which are not anchored to the pool floor or walls has been adopted in many countries.Under the earthquake, the response of the free standing rack is highly nonlinear and involves a complex combination of motions (sliding, rocking, twisting, and turning) and impacts between the fuel assemblies and the fuel cell walls, rack-to-rack, and the pit floor and rack pedestals. To obtain an accurate simulation of the free standing rack, the seismic analysis requires careful considerations of these complex phenomena (sliding, rocking, twisting, and turning), fluid coupling effects and frictional effects.We carried out seismic experiments on the full-scale rack model in water and dry conditions to obtain the fundamental data about free standing rack (sliding, rocking and turning motions). We have developed the nonlinear dynamic analysis method to predict seismic response for the free standing rack utilizing the full-scale test result and verified the analysis evaluation method of the rack by comparison of test result.Copyright


ASME 2011 Pressure Vessels and Piping Conference: Volume 8 | 2011

Evaluation of the Sliding Behavior of the Rack Using CAV Concept

Akihisa Iwasaki; Yoshitsugu Nekomoto; Hideyuki Morita; Shingo Nishida; Mitsuru Nagaya; Daisaku Okuno; Naoki Chigusa

The spent fuel taken out of a nuclear plant reactor is temporarily stored in spent fuel racks. This fuel will often have to be stored in the long periods before it can be moved to a reprocessing facility. Therefore, the spent fuel rack must have a large capacity with a high tolerance against big seismic loads. So, the free standing rack is developed as the optimal equipment meeting these requirements. The free standing fuel rack is installed on the floor in the spent fuel pool and it can have the simple structure, as it needs no supports on the floor or the wall of the spent fuel pool. The free standing spent fuel rack structure actively incorporates the effects of the friction force generated on the spent fuel pool floor, and the fluid effect. So, seismic analysis is performed by nonlinear dynamic time history analysis. In this study, we applied CAV concept (CAV: Cumulative Absolute Velocity) to evaluate of nonlinear rack response. And it was confirmed that the CAV concept using the low-pass filter is useful to evaluate the sliding and rocking behavior of the rack by simulation analysis.Copyright


Archive | 2011

Nuclear fuel storage rack connection structure and connection method thereof

Akihisa Iwasaki; Hideyuki Morita; Yoshitsugu Nekomoto; Kazuo Hirota; Daisaku Okuno; Masaaki Nakamura


ASME 2012 Pressure Vessels and Piping Conference | 2012

Analysis Study on Free Standing Rack Under the Earthquake Excitation

Akihisa Iwasaki; Yoshitsugu Nekomoto; Hideyuki Morita; Katsuhiko Taniguchi; Daisaku Okuno; Toshihiro Matsuoka; Naoki Chigusa


Archive | 2010

STRUCTURE AND METHOD FOR CONNECTING RACK FOR STORING NUCLEAR FUEL

Kazuo Hirota; Akihisa Iwasaki; Hideyuki Morita; Masaaki Nakamura; Yoshitsugu Nekomoto; Daisaku Okuno; 正明 中村; 大作 奥野; 晃久 岩崎; 和生 廣田; 英之 森田; 善続 猫本


Archive | 2015

HEAT EXCHANGER TUBE VIBRATION SUPPRESSION DEVICE AND STEAM GENERATOR

Tomohito Nakamori; Yoshitsugu Nekomoto; Jun Hirai; Toshihiro Kojima; Akihisa Iwasaki; Hideyuki Morita; Kazuo Hirota; Kengo Shimamura; Takaya Kusakabe; Ryoichi Kawakami; Katsuyoshi Nishioka

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Hideyuki Morita

Mitsubishi Heavy Industries

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Daisaku Okuno

Mitsubishi Heavy Industries

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Kazuo Hirota

Mitsubishi Heavy Industries

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Toshihiro Matsuoka

Mitsubishi Heavy Industries

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Seiji Kitamura

Japan Atomic Energy Agency

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Tomohiko Yamamoto

Japan Atomic Energy Agency

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