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Journal Articles

Provision of laser irradiation conditions for melting and solidification processes using computational science simulation code SPLICE

Muramatsu, Toshiharu

Nippon Kikai Gakkai 2018-Nendo Nenji Taikai Koen Rombunshu (DVD-ROM), 5 Pages, 2018/09

A general-purpose three-dimensional thermohydraulics computer science simulation code SPLICE was developed at JAEA and designed to deal with gas-liquid-solid consolidated incompressible viscous flows with a phase change process in various laser applications. The results obtained from various numerical simulations using the SPLICE code are very encouraging in the sense that the SPLICE code would be used as one of the efficient front-loading tools to reduce overhead loads in laser processing.

Journal Articles

Improvement of penetrate crack length evaluation method for LBB assessment of sodium-cooled fast reactor components

Wakai, Takashi; Machida, Hideo*; Arakawa, Manabu*

Nippon Kikai Gakkai 2018-Nendo Nenji Taikai Koen Rombunshu (DVD-ROM), 5 Pages, 2018/09

According to the fitness for service code of Sodium-Cooled fast Reactor (SFR), the volumetric tests as in-service inspection can be replaced with continuous leak monitoring, where the Leak Before Break (LBB) is demonstrated, because the primary stress caused by internal pressure is not significant in SFR components. Basically, if the detectable crack length and the penetrated crack length are sufficiently smaller than the unstable critical crack length, it can be concluded that LBB is successfully demonstrated. The authors had already proposed a simplified method to calculate the penetrated crack length both of the circumferential and axial cracks in the pipe as a function of pipe geometry, fatigue crack growth characteristics and loading conditions. However, some problems in the method have been pointed out in the process of the reviewing by the JSME code committee. This study describes an improved method to calculate the penetrated crack length.

Oral presentation

Development of hydrogen behavior simulation system for safety management

Terada, Atsuhiko; Hino, Ryutaro

no journal, , 

To further improve the safety performance of the Nuclear Power Station, especially on the hydrogen safety under severe accident conditions, a simulation code system has been developed to analyze hydrogen behaviors including diffusion, combustion, explosion and structural integrity evaluation. As one of validation test of a numerical simulation system for leaked hydrogen gas behavior, we compared calculated results by some calculation methods and time histories of hydrogen gas concentration etc at sensor positions of leaking hydrogen gas in large scale container. The calculated results using SAS and LES turbulence model show good agreement with experimental results.

Oral presentation

Study on radiation model of combustion droplets in a multi-dimensional sodium fire analysis code

Aoyagi, Mitsuhiro; Takata, Takashi; Uno, Masayoshi*

no journal, , 

Multi-dimensional sodium fire analysis code AQUA-SF have been developed in order to analyze consequence of the sodium fire event. In this study, radiation heat transfer model for sodium droplets is newly implemented to the AQUA-SF code. As the result of a benchmark analysis of an upward spray combustion experiment, the experimental results is simulated reasonably by the improved model.

Oral presentation

Characteristics of two-phase pressure drop in a simulated debris bed

Ito, Daisuke*; Kurisaki, Tatsuya*; Ito, Kei*; Saito, Yasushi*; Aoyagi, Mitsuhiro; Matsuba, Kenichi; Kamiyama, Kenji

no journal, , 

In order to evaluate characteristics of debris-bed coolability in the core region, characteristics of the pressure loss in the debris-bed under liquid-gas two phase flow is required to be understood. In this study, effects of porosity distribution on pressure loss and void-fraction distribution in the test section are presented.

Oral presentation

Development of analysis method for long-time event progress under tube failure accident in steam generator of sodium-cooled fast reactor

Uchibori, Akihiro; Yanagisawa, Hideki*; Takata, Takashi; Ohshima, Hiroyuki

no journal, , 

Evaluation of occurrence possibility of tube failure propagation under sodium-water reaction accident is an important issue. In this study, a numerical analysis method to predict occurrence of failure propagation by overheating rupture was constructed to expand application range of an existing computer code. Applicability of the method was constructed through the numerical analysis of the experiment on water vapor discharging in liquid sodium.

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