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Journal Articles

Development of proposed guideline of flow-induced vibration evaluation for hot-leg piping in a sodium-cooled fast reactor

Sakai, Takaaki; Yamano, Hidemasa; Tanaka, Masaaki; Ono, Ayako; Ohshima, Hiroyuki; Kaneko, Tetsuya*; Hirota, Kazuo*; Sago, Hiromi*; Xu, Y.*; Iwamoto, Yukiharu*; et al.

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 13 Pages, 2013/05

The development of flow-induced vibration evaluation methodology has reached a milestone that separate-effect experimental data under a high Reynolds number regime including swirl and deflected inflow conditions are available for the validation of the methodology. On the other hand, technical standards are desirable to be documented for designers of sodium-cooled fast reactors. From such a background, the documentation of a flow-induced vibration design guideline has been made for the hot-leg piping of Japan sodium-cooled fast reactor. This paper describes the design guideline of the flow-induced vibration evaluation methodology, which has been informed from main separate-effect experiments, as well as supplemental interpretation for the guideline.

Journal Articles

Development of failure probability evaluation methodology of natural circulation heat removal function in level-1 PSA for sodium-cooled fast reactors

Yamano, Hidemasa; Sakai, Takaaki; Kurisaka, Kenichi

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 15 Pages, 2013/05

This study is aimed to develop a methodology of failure probability evaluation for the passive safety features on natural circulation heat removal. Following the identification process on failure causes using the phenomena identification and ranking table, this paper provides a failure probability of the natural circulation heat removal function that is expected to actuate only one direct reactor auxiliary cooling system assuming the loss of two primary reactor auxiliary cooling systems. The failure probability was determined above a safety criterion of the coolant boundary temperature. The failure probability of the reference case was very low, indicating a high reliability of the natural circulation decay heat removal function.

Journal Articles

LSTF test on cet performance during PWR hot leg small-break LOCA and RELAP5 analysis

Takeda, Takeshi; Otsu, Iwao; Nakamura, Hideo

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 12 Pages, 2013/05

Journal Articles

Major outcomes from OECD/NEA ROSA and ROSA-2 projects

Nakamura, Hideo; Takeda, Takeshi; Satou, Akira; Ishigaki, Masahiro; Abe, Satoshi; Irwanto, D.

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 21 Pages, 2013/05

Journal Articles

Evaluation model of bubble-type gas entrainment

Ito, Kei; Ezure, Toshiki; Ohno, Shuji; Kamide, Hideki

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 11 Pages, 2013/05

The gas entrainment (GE) is one of important issues in the study on sodium-cooled fast reactors. In this paper, the authors propose a unified evaluation model of the bubble-type GE, which can predict the onset condition in various experiments. This evaluation model consists of two equations; one is the mechanical balance equation at the gas core tip, the other shows the ratio of the critical gas core length to the specific radius of the free surface vortex. To check the validity of the proposed model, several experiments, e.g. Baum's experiment, are evaluated. As a result, the model gives the similar onset conditions to the experimental results.

Journal Articles

SAS4A analysis of CABRI experiments for validation of axial fuel expansion model

Ishida, Shinya; Sato, Ikken

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 9 Pages, 2013/05

Journal Articles

Effects of fluid viscosity on occurrence behavior of vortex cavitation; Vortex structures and occurrence condition

Ezure, Toshiki; Ito, Kei; Kimura, Nobuyuki; Onojima, Takamitsu; Kamide, Hideki; Kameyama, Yuri*

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 12 Pages, 2013/05

An experimental study on vortex cavitation was carried out in a cylindrical water tank to clarify how the viscosity of fluid influences on vortex cavitation occurrences. Vertical and horizontal velocity distributions were obtained under several experimental conditions, where the kinematic viscosity of water and the velocity of suction flow were varied as parameters. As the results, the flow patterns and the vortex structures, such as the circulation around the vortex, were grasped. And also, the acceleration behavior of vortex from the bottom of tank towards the intake of suction nozzle was clarified. Then, the occurrence map of vortex cavitation was also improved by using the present experimental data.

Journal Articles

Influence of fragmentation on jet breakup behaviour

Iwasawa, Yuzuru*; Abe, Yutaka*; Kaneko, Akiko*; Kuroda, Taihei*; Matsuo, Eiji*; Ebihara, Kenichi; Sakaba, Hiroshi*; Koyama, Kazuya*; Ito, Kazuhiro*; Nariai, Hideki*

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 12 Pages, 2013/05

In the safety design of a Fast Breeder Reactor(FBR), when it is supposed that a Core Disruptive Accident(CDA) occurs, it is strongly required that molten core materials are completely solidified and are cooled down by sodium coolant in a reactor vessel. In this study, we injected molten alloy and transparent fluid, which are a simulant of the molten core material, into water, which is a simulant of the coolant. In this study, we injected molten alloy and transparent fluid, which simulate the molten core material, into water, which simulates the coolant. In the experiment, we observed the jet breakup behavior of them using a high speed video camera, and compared the observe images with the previous theories. In addition, we simulated numerically the qualitative behavior of the liquid jet using a two-phase fluid model of the lattice Boltzmann method.

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