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JAEA Reports

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.

JAEA Reports

Advanced modeling of the contact area correlation between sodium and water with the particle interaction method

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

JNC TJ9400 2005-005, 103 Pages, 2003/02

JNC-TJ9400-2005-005.pdf:6.41MB

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 in very high pressure. If the water or steam is issued in 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 compute the phenomena. In our previous investigations, mesoscopic and direct analysis method has been developed by using the particle interaction method in order to compute multi-phase, multi-component, and chemically interactive fluids. With this method, flow regime and contact areas concentration were investigated and a correlation model for a liquid jet flow issued into another liquid was made. In this fiscal year, the correlation model was investigated in detail to give higher accuracy prior to developing the correlation for a gas jet flow issued into liquid. Furthermore, the experiment of gas jet flow issued into liquid was analyzed with the particle interaction method to confirm applicability to gas-liquid system.

JAEA Reports

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.

JAEA Reports

Analysis of the flow with phase change and chemical reaction with the paticle interaction method (Report under the contract between JNC and toshiba Corporation)

Shirakawa, Noriyuki*; *; *

JNC TJ9400 2001-006, 93 Pages, 2001/02

JNC-TJ9400-2001-006.pdf:3.27MB

The numerical thermohydraulic analysis of a LMFR component should involve its whole boundary in order to evaluate the effect of chemical reaction within it. Therefore, it becomes difficult mainly due to computing time to adopt microscopic approach for the chemical reaction directly. Thus, the thermohydraulic code is required to model the chemically reactive fluid dynamics with constitutive correlations. The reaction rate 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 experiments to study the jet flow with sodium-water chemical reaction have been done, the goal of this study is to obtain the knowledge of flow regimes and contact areas by analyzing the fluid dynamics of multi-pahse and reactive components mechanistically with the particle interaction method. In this fiscal year, following works were performed: (1)Development and coding of the interfacial area model, (2)Development and coding of the phase change model, (3)Verification of the fundamental functions of the models, and (4)Literature investigation of the related experiments.

JAEA Reports

A feasibility study of the particle interaction method for the flow regimes with the chemical reaction; (Report under the contract between JNC and Toshiba Corporation)

Shirakawa, Noriyuki*; *; *; *

JNC TJ9440 2000-008, 47 Pages, 2000/03

JNC-TJ9440-2000-008.pdf:1.96MB

The numerical thermohydraulic analysis of a LMFR component should involve its whole boundaly in order to evaluate the effect of chemical reaction within it. Therefore, it becomes difficult mainly due to computing time to adopt microscopic approach for the chemical reaction directly. Thus, the thermohydraulic code is required to model the chemically reactive fluid dynamics with constitutive correlations. The reaction rate denpends 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 experiments to study the jet flow with sodium-water chemical reaction have been done, the goal of this study is to obtain the knowledge of flow regimes and contact areas by analyzing the fluid dynamics of multi-pahse and reactive components mechanistically with the particle interaction method. For the first stage of the study, the applicability of this method to the nalysis of a liquid jet into the other liquid pool was investigated. Based on the literatures, we investigated the jet flow mechanisms and analyzed the experiment of a water jet into a gasoline pool. We also analyzed SWAT3/Run19 test, the jet flow in a rod bundle, to study the applicability of the method to a complicated boundary without a chemical reaction model. The calculated fluid dynamics was in good agreement with the experiment. Furthermore, we studied and formulated the paths of phase change and chemical reaction, and conceptually designed the adopting the heat-transfer-limited phase change model and the synthesizd reaction model with a water-hydrogen conversion ratio.

JAEA Reports

Improvement of the sodium-water chemical reaction analysis code SIMMER-SW (2); (Report under the contract between JNC and Toshiba Corporation)

Shirakawa, Noriyuki*; *; *; *

JNC TJ9440 99-009, 195 Pages, 1999/03

JNC-TJ9440-99-009.pdf:5.93MB

It is necessary for the evaluation of the design base flow rate of water leakage out of the steam generator heat transfer tubes to evaluate the possibility of a tube-failure propagation quantitatively, which needs development of the followings, (1)Blow down model of the steam generator heat transfer tube, (2)Rupture model at high temperature of the steam generator heat transfer tube, and (3)Sodium-water chemical reaction model to analyze the temperature distribution around a leakage point. In this study, development effort is focused on the item (3)that is most important to the evaluation of failure propagation. The FBR safety aalysis code SIMMER-III is used as a reference to realize the analysis and is named SIMMER-SW. The followings were done in this work: (a)Coding of the chemical reaction model, and verification of the model functions, (b)Coding of the rod bundle pressure drop model, and verification of the model functions, (3)Coding of the preprocessor to prepare the input for a rod bundle, (4)Data production of the EOS(Equation-of-State) and TPP(Thermo Physical Properties), (5)Investigation of the interaction between sodium and jet out of a leak hole, (6)Modeling of the thermocouple, (7)SWAT1/P06 test analysis, and (8)SWAT3/Run19 test analysis. The following knowledge was obtained: (a)The results of the SWAT1/P06 test analysis which can be done in two-dimension agree well with that of the experiment at least qualitatively, (b)Thermocouple model is very useful in the analysis such that various kinds of components contact a thermocouple, (c)The constant K in the chemical reaction model is likely to be 0.01$$<$$K$$<$$0.1, and (d)The results of the SWAT3/Run19 test analysis which should be done in three-dimension do not agree with that of the experiment.

Oral presentation

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.

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