Improvement of steam generator tube failure propagation analysis code LEAP for evaluation of overheating rupture

2018 ◽  
Vol 56 (2) ◽  
pp. 201-209
Author(s):  
Akihiro Uchibori ◽  
Hideki Yanagisawa ◽  
Takashi Takata ◽  
Akikazu Kurihara ◽  
Hirotsugu Hamada ◽  
...  
Keyword(s):  
Steam Generator ◽  
Steam Generator Tube ◽  
Propagation Analysis ◽  
Failure Propagation ◽  
Tube Failure

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.

Investigation on droplet impingement erosion during steam generator tube failure accident

2012 ◽  
Vol 249 ◽  
pp. 132-139 ◽  
Author(s):  
Jinbiao Xiong ◽  
Seiichi Koshizuka ◽  
Mikio Sakai ◽  
Hiroyuki Ohshima
Keyword(s):  
Steam Generator ◽  
Droplet Impingement ◽  
Steam Generator Tube ◽  
Droplet Impingement Erosion ◽  
Tube Failure

Failure Analysis of Steam Generator Tubes With Dented and Wastage Configurations

1978 ◽  
Vol 100 (4) ◽  
pp. 354-359
Author(s):  
M. Reich ◽  
S. Prachuktam ◽  
T. Y. Chang
Keyword(s):  
Cyclic Loading ◽  
Failure Analysis ◽  
Steam Generator ◽  
Recent Literature ◽  
Structural Response ◽  
Loading Conditions ◽  
Steam Generator Tube ◽  
Steam Generator Tubes ◽  
Tube Failure

The occurrence of PWR steam generator tube cracking, denting, and wastage has been reported in the recent literature [1–5]. As indicated by its title, this paper concerns itself with the inelastic structural response of the tubes that result from various assumed monotonic as well as cyclic loading conditions, which ultimately could lead to the tube failure.

A Knowledge based Tool for Failure Propagation Analysis

1989 ◽  
Author(s):  
P.S. Ness ◽  
D. Bereket ◽  
M. Hakimi ◽  
T. Uthus ◽  
A. Chakravarty
Keyword(s):  
Knowledge Based ◽  
Propagation Analysis ◽  
Failure Propagation

scholarly journals Analysis of the Accelerator-Driven System Fuel Assembly during the Steam Generator Tube Rupture Accident

Materials ◽  
2021 ◽  
Vol 14 (8) ◽  
pp. 1818
Author(s):  
Di-Si Wang ◽  
Bo Liu ◽  
Sheng Yang ◽  
Bin Xi ◽  
Long Gu ◽  
...  
Keyword(s):  
Fuel Assembly ◽  
Steam Generator ◽  
Metal Flow ◽  
Maximum Temperature ◽  
Steam Generator Tube ◽  
Driven System ◽  
Fuel Assemblies ◽  
Accelerator Driven System ◽  
The Impact ◽  
Steam Bubble

China is developing an ADS (Accelerator-Driven System) research device named the China initiative accelerator-driven system (CiADS). When performing a safety analysis of this new proposed design, the core behavior during the steam generator tube rupture (SGTR) accident has to be investigated. The purpose of our research in this paper is to investigate the impact from different heating conditions and inlet steam contents on steam bubble and coolant temperature distributions in ADS fuel assemblies during a postulated SGTR accident by performing necessary computational fluid dynamics (CFD) simulations. In this research, the open source CFD calculation software OpenFOAM, together with the two-phase VOF (Volume of Fluid) model were used to simulate the steam bubble behavior in heavy liquid metal flow. The model was validated with experimental results published in the open literature. Based on our simulation results, it can be noticed that steam bubbles will accumulate at the periphery region of fuel assemblies, and the maximum temperature in fuel assembly will not overwhelm its working limit during the postulated SGTR accident when the steam content at assembly inlet is less than 15%.

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