Multiphysics Analysis System for Tube Failure Accident in Steam Generator of Sodium-Cooled Fast Reactor

2013 ◽  
Author(s):  
Akihiro Uchibori ◽  
Shin Kikuchi ◽  
Akikazu Kurihara ◽  
Hirotsugu Hamada ◽  
Hiroyuki Ohshima
Keyword(s):  
Heat Transfer ◽  
Steam Generator ◽  
Chemical Reaction ◽  
Numerical Models ◽  
Stress Evaluation ◽  
Transfer Tube ◽  
Failure Propagation ◽  
Computer Codes ◽  
Analysis System ◽  
Tube Failure

Multiphysics analysis system was newly developed to evaluate possibility of failure propagation occurrence under heat transfer tube failure accident in a steam generator of sodium-cooled fast reactors. The analysis system consists of the computer codes, SERAPHIM, TACT, RELAP5, which are based on the mechanistic numerical models. The SERAPHIM code calculates the multicomponent multiphase flow involving sodium-water chemical reaction. In this study, numerical models for the chemical reaction about production of a sodium monoxide and its transport process were constructed to enable evaluation of a wastage environment. The TACT code was developed to calculate heat transfer from the reacting jet to the adjacent tube and to predict the tube failure occurrence. The TACT code was integrated by the numerical models of the fluid-structure thermal coupling, the temperature and stress evaluation, the wastage evaluation and the failure judgment. The RELAP5 code evaluates thermal hydraulic behavior of water inside the tube. The original heat transfer correlations were corrected for the rapidly heated tube in the present work.

Study on Flow Induced Vibration Analysis and Evaluation for Heat Transfer Tube of Steam Generator

2018 ◽  
Author(s):  
Xuan Huang ◽  
Huan-Huan Qi ◽  
Feng-Chun Cai ◽  
Zhi-Peng Feng ◽  
Shuai Liu
Keyword(s):  
Heat Transfer ◽  
Steam Generator ◽  
Vibration Analysis ◽  
Two Phase Flow ◽  
Phase Flow ◽  
Flow Induced Vibration ◽  
Two Phase ◽  
Heat Transfer Tube ◽  
Analysis And Evaluation ◽  
Transfer Tube

The heat transfer tube of steam generator is an important part of the primary loop boundary, the integrity is crucial to the safe operation of the whole reactor system; the flow induced vibration is one of the main factors leading to the failure of heat transfer tube in steam generator. Both ASME and RG1.20 have made a clear requirement for the analysis and evaluation of the flow induced vibration of steam generator. The flow induced vibration of heat transfer tube in two-phase flow is the difficult and important content in the analysis. In this paper, the finite element model of heat transfer tube is established and the modal analysis is carried out. Then in order to evaluate the influence of two-phase flow in the secondary side and support boundary constraint, the analytical results are compared with the natural frequencies of the heat transfer tube measured in the two-phase flow test. On the basis of accurate simulation of the dynamic characteristics of heat transfer tube in two-phase flow, the paper calculate the turbulent excitation response and the fluidelastic instability ratio aiming at the main mechanism causing the flow induced vibration of heat transfer tube in two-phase flow. Firstly, the modified PSD of turbulent excitation is proposed on the foundation of root mean square displacement amplitude of heat transfer tube measured in two-phase flow test. The calculation result of the amplitude of heat transfer tube with different void fraction can envelope the test result by using the modified PSD as input, and the safety margin is reasonable. Then we also verify whether the analysis conclusion of fluidelastic instability is in agreement with the test. Finally, the analytical technique is applied to the analysis of flow induced vibration of steam generator to verify the design of structure. The paper studies on flow induced vibration analysis and evaluation a heat transfer tube of steam generator in two-phase flow. The analysis program of flow induced vibration on the basis of the test results. The investigation can be used for the risk prediction and evaluation of flow induced vibration of heat transfer tube in two-phase flow, solve the technical difficulties of flow induced vibration analysis in two-phase flow, and provide the technical support for the flow induced vibration analysis of steam generator.

Dynamic Characteristics Analysis of Steam Generator Tube of Nuclear Power Plant by Finite Elements

2014 ◽  
Vol 577 ◽  
pp. 149-153
Author(s):  
Shuang Jiang ◽  
Jun Cai ◽  
Jing Wei Zhang ◽  
Qiao Zhi Sun ◽  
Xin Guo ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Modal Analysis ◽  
Steam Generator ◽  
Nuclear Power ◽  
Power Plants ◽  
Primary Circuit ◽  
Harmonic Load ◽  
Heat Transfer Tube ◽  
Finite Element Software ◽  
Transfer Tube

In nuclear power plants, the steam generator heat transfer tube is the weakest part of the primary circuit pressure boundary. Flow induced vibration is one of the main reasons for the failure of the heat transfer tube. In this paper, an ANSYS finite element software is used to carry out the modal analysis of the heat transfer tube, and to simulate the dynamic response of the heat transfer tube in the harmonic load based on the modal analysis.

Thermal Influence on Steam Generator Heat Transfer Tube During Sodium-Water Reaction Accident of Sodium-Cooled Fast Reactor

2009 ◽  
Vol 167 (1) ◽  
pp. 118-126 ◽  
Author(s):  
Akira Yamaguchi ◽  
Takashi Takata ◽  
Hiroyuki Ohshima ◽  
Akikazu Kurihara
Keyword(s):  
Heat Transfer ◽  
Steam Generator ◽  
Fast Reactor ◽  
Heat Transfer Tube ◽  
Transfer Tube ◽  
Thermal Influence

Mixing Behavior of Argon Jet With Liquid Sodium Around a Single Rod: A Basic Study on Sodium-Water Reaction

2008 ◽  
Author(s):  
Hokuto Tsuruoka ◽  
Takeshi Tamura ◽  
Ken-Ichiro Sugiyama ◽  
Tadashi Narabayashi ◽  
Hiroyuki Ohshima
Keyword(s):  
Heat Transfer ◽  
Surface Tension ◽  
Void Fraction ◽  
Gas Jet ◽  
Water Pool ◽  
Argon Gas ◽  
Heat Transfer Tube ◽  
Transfer Tube ◽  
Jet Velocity ◽  
Tube Failure

The occurrence of secondary heat transfer tube failure due to overheating by sodium-water reaction in LMFBR steam generators has been concerned from the viewpoint of public acceptance. To evaluate the phenomena for the secondary heat transfer tube failure, a sophisticated computer code SERAPHIM has been developed by JAEA. The comparison of simulation results with experimental data to verify the adequacy of SERAPHIM code or to upgrade it are now required. In our paper at ICONE15, we report the void fraction and the entrainment pattern of water around a single rod set in a water pool using the probes developed for sodium experiment. In addition to these results, the reliability of the developed probe was verified by the experiment with gas jet velocity more than 340m/s accompanying oscillation. In the present paper, we reported the void fraction around a single rod in a diameter of 20mm set in a sodium pool without sodium-water reaction. The velocity of argon gas jet changed from 17.3m/s to 173m/s, which was lower velocity than that in the water experiment from the safety consideration and the void fraction was measured at every 30°. The void fraction was observed to somewhat increase with increasing the gas jet velocity. The increase rate was clearly smaller compared with that in the water experiment. The void fraction also showed more monotonous distribution from the stagnation point to the rear point than that in water pool. These results reflect the difference of surface tension between water and sodium. Because sodium has about three times surface tension as large as water, the argon gas jet column with oscillation in the sodium pool causes easily break-up than that in the water pool. It is concluded that the entrainment of ambient sodium is easily caused and this leads monotonous distribution of void fraction in the sodium pool.

Entrainment of Water Around a Single Rod Immersed in Water Pool with Gas Jet Impingement

2006 ◽  
Author(s):  
Kazuo Soga ◽  
Hideto Niikura ◽  
Ken-ichiro Sugiyama ◽  
Tadashi Narabayashi ◽  
Hiroyuki Ohshima ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Chemical Reaction ◽  
Jet Impingement ◽  
Gas Jet ◽  
Water Pool ◽  
Transfer Coefficients ◽  
Heat Transfer Tube ◽  
Heat Transfer Coefficients ◽  
Transfer Tube ◽  
Ar Gas

In a steam generator of liquid sodium cooled fast breeder reactor, the occurrence of secondary heat transfer tube failure has been considered due to overheating in sodium-water reaction. A computer code SERAPHIM has been developed to analyze this kind of secondary heat transfer tube failure due to steam jet with heat generation and chemical reaction by Japan Atomic Energy Agency (JAEA). The detailed experimental data that verify the adequacy of SERAPHIM code and upgrade it, are now required. In ICONE13, the local and mean heat transfer coefficients around a horizontal heated rod (φ 15mm) immersed in a water pool and in a sodium pool with gas jet impingement without chemical reaction, were reported as the first step. It was confirmed in the water pool experiment that the local and mean heat transfer coefficients slowly increase with increasing the Ar jet velocity from 8.7m/s to 78m/s The local and mean Nusselt numbers almost keeps same values independent on the Ar gas velocity in the sodium pool experiment. From these results, we inferred that the ambient liquid is entrained inside and contributes to high heat transfer rates. A series of experiments that investigate the entrainment process of ambient liquid toward jet interior are carried out by using a laser-sheet visualization and a void meter in water pool in the present work. It was observed that the entrainment of water into Ar gas jet is constantly caused in two regions just above the nozzle and just below the single rod. In the region just above the nozzle, negative pressure causes the entrainment of water. In the region below the rod, the entrainment of water is caused because the preceding Ar gas jet is caught up by the succeeding gas jet. The basic behavior of Ar gas jet causing the entrainment of water was confirmed to be almost same over the Reynolds number range of Ar gas jet, 2.17×103 to 2.17×104, in the present study. In addition, the measurement of void fraction was performed to investigate the entrainment of water quantitatively and the behavior of local heat transfer coefficients around a single rod with gas jet impingement in water pool was made clear.

Numerical simulation of micro-crack leakage on steam generator heat transfer tube

2021 ◽  
Vol 382 ◽  
pp. 111385
Author(s):  
Xiaohan Zhao ◽  
Yixiang Liao ◽  
Mingjun Wang ◽  
Kui Zhang ◽  
G.H. Su ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Numerical Simulation ◽  
Steam Generator ◽  
Heat Transfer Tube ◽  
Transfer Tube
Sign in / Sign up

Export Citation Format

Share Document