Evaluation of the correlation model for the contact areas concentration between sodium and steam with the particle interaction method

Horie, Hideki*; Yamamoto, Yuichi*; Oue, Masaya*; Shirakawa, Noriyuki*

JNC TJ9400 2005-007, 135 Pages, 2004/02

JNC-TJ9400-2005-007.pdf:7.19MB

In a LMFR steam generator, liquid sodium flows through the component vessel, which has a manifold of heat transfer tubes through which water or steam flows under very high pressure. If the water or steam is issued as a jet into sodium pool by the high pressure due to tube failure, sodium-water reaction occurs and affects the component integrity. The phenomena are strongly nonlinear processes in multi-phase flow. To evaluate contact areas concentration between fluid components is essential to analyze the phenomena. In this work, the correlation model for the contact areas concentration between two different liquids developed with the particle interaction method, which method is capable of evaluating the mixing layer between two kinds of fluid, was applied to a gasjet issued into a liquid pool to investigate its applicability. This investigation involves the analysis to consider the mole change of steam and generated gas due to the sodium-water chemical reaction and the analysis of the effect of a rod on the correlation model.

Analysis of the flow with sodium-water chemical reaction by the particle interaction method

Shirakawa, Noriyuki*; Horie, Hideki*; Yamamoto, Yuichi*

JNC TJ9400 2005-006, 183 Pages, 2002/02

JNC-TJ9400-2005-006.pdf:10.61MB

To evaluate the effect of accidents induced by sodium-water chemical reaction on a LMFR component, the numerical thermo-hydraulic analysis should involve the whole boundary of the component. Therefore, the thermo-hydraulic code is required to model the chemically reactive fluids dynamics with constitutive correlations.Both thermal and chemical reaction rate largely depends on the binary contact areas between components such as continuous liquids, droplets, solid particles, and bubbles. The contact areas change sharply according to the interface state between components. Since no experiment to investigate the jet flow with sodium-water chemical reaction has been done, the purpose of this study is to develop the evaluation method for flow regimes and contact areas by analyzing the fluid dynamics of multi-phase and reactive components mechanistically with the particle interaction method. In this fiscal year, following works were performed:(1) investigation to link the mesoscopic information of contact areas obtained by the particle interaction method with the macroscopic fluid dynamics code, (2) development of the correlation of contact areas, (3) investigation of the effect of the water-leak conditions on contact areas, and (4) analysis of contact areas for a slug flow.

Transient heat transfer from a wire inserted into a vertically mounted pipe to forced-flow subcooled liquid hydrogen

Tatsumoto, Hideki; Shirai, Yasuyuki*; Shiotsu, Masahiro*; Horie, Yuki*; Yoneda, Kazuya*; Matsuzawa, Takayuki*; Kobayashi, Hiroaki*; Naruo, Yoshihiro*; Inatani, Yoshifumi*

no journal, , 

no abstracts in English

R&D for introducing silicon carbide materials to safety improvement of BWR's core, 3; Plant transient analysis with SiC cladding fuel for RIA accident

Horie, Hideki*; Takeuchi, Yutaka*; Kakiuchi, Kazuo*; Sato, Hisaki*; Shirasu, Noriko; Saito, Hiroaki; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

The problem in the accident tolerance fuel development was considered in comparison the fuel behavior of SiC/SiC composite cladding tube with current Zry cladding tube. In this study, Reactivity Initiated Accident (RIA) was evaluated using the plant excess security analysis code TRACTTM and the fuel performance code FEMAXI.