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%.

Simulation of a Steam Generator Tube Rupture Accident in a Lead-Cooled Accelerator Driven System

2010 ◽  
Author(s):  
Michael Flad ◽  
Shisheng Wang ◽  
Werner Maschek
Keyword(s):  
Steam Generator ◽  
Liquid Water ◽  
Water Injection ◽  
Spent Fuel ◽  
Steam Generator Tube ◽  
Damage Propagation ◽  
Core Damage ◽  
Driven System ◽  
Safety Studies ◽  
The Impact

The European Facility for Industrial Transmutation (EFIT) is developed to transmute long-lived actinides from spent fuel on an industrial scale. In this lead-cooled reactor an intermediate loop is eliminated for economic reasons. Within the framework of design and safety studies the impact of a steam generator tube rupture accident has been investigated. In this postulated event high-pressured liquid water blasts into the lead pool which could trigger various transients. As a major concern steam could be dragged into the core featuring a positive void worth. A thermal lead/water interaction could lead to in-core damage propagation; it could initiate a sloshing of the lead coolant and trigger voiding processes. Furthermore the pressurization of the cover gas needs to be considered. To prove the feasibility of the proposed design these risks are investigated and assessed. Numerical simulations are performed using the advanced safety analysis code SIMMER-III [2]. For the important issue of thermal lead/water interactions the SIMMER code has been validated against Japanese heavy-liquid/water injection experiments.

Evaluation of a steam generator tube rupture accident in an accelerator driven system with lead cooling

2008 ◽  
Vol 50 (2-6) ◽  
pp. 363-369 ◽  
Author(s):  
S. Wang ◽  
M. Flad ◽  
W. Maschek ◽  
P. Agostini ◽  
D. Pellini ◽  
...  
Keyword(s):  
Steam Generator ◽  
Steam Generator Tube ◽  
Driven System ◽  
Accelerator Driven System

Bubble Behaviors in a Fuel Assembly of Accelerator Driven System

2021 ◽  
pp. 1-6
Author(s):  
Sheng Yang ◽  
Bo Liu ◽  
Disi Wang ◽  
You-Peng Zhang ◽  
Bin Xi
Keyword(s):  
Fuel Assembly ◽  
Driven System ◽  
Accelerator Driven System

Research on Impact of Pressurizer Heater Block on SGTR Overfill Analysis

2017 ◽  
Author(s):  
Liu Lixin
Keyword(s):  
Water Level ◽  
Steam Generator ◽  
Accident Analysis ◽  
Steam Generator Tube ◽  
The Impact

Steam generator overfill due to steam generator tube rupture have been analyzed for CAP1400 plant, in which two cases were simulated, including pressurizer heater switching off available and unavailable under low pressurizer water level. The results indicate that it has a certain margin to steam generator (SG) overfill for the ruptured steam generator under steam generator tube rupture (SGTR) accident. Analysis results have also shown that the SG overfill margin will be slightly decreased in case of pressurizer heater swiching off unavailable, however, the impact is not significant.

scholarly journals NEUTRON NOISE PATTERNS FROM COUPLED FUEL-ASSEMBLY VIBRATIONS

2021 ◽  
Vol 247 ◽  
pp. 02015
Author(s):  
M. Viebach ◽  
C. Lange ◽  
M. Seidl ◽  
Y. Bilodid ◽  
A. Hurtado
Keyword(s):  
Neutron Flux ◽  
Fuel Assembly ◽  
Cross Sections ◽  
Three Dimensional ◽  
Time Dependent ◽  
Radial Dependence ◽  
Feedback Parameter ◽  
Fuel Assemblies ◽  
Neutron Noise ◽  
The Impact

The neutron flux fluctuation magnitude of KWU-built PWRs shows a hitherto unexplained correlation with the types of loaded fuel assemblies. Also, certain measured long-range neutron flux fluctuation patterns in neighboring core quadrants still lack a closed understanding of their origin. The explanation of these phenomena has recently revived a new interest in neutron noise research. The contribution at hand investigates the idea that a synchronized coolant-driven vibration of major parts of the fuel-assembly ensemble leads to these phenomena. Starting with an assumed mode of such collective vibration, the resulting effects on the time-dependent neutron-flux distribution are analyzed via a DYN3D simulation. A three-dimensional representation of the time-dependent bow of all fuel assemblies is taken into account as a nodal DYN3D feedback parameter by time-dependent variations of the fuel-assembly pitch. The impact of its variation on the cross sections is quantified using a cross-section library that is generated from the output of corresponding CASMO5 calculations. The DYN3D simulation qualitatively reproduces the measured neutron-flux fluctuation patterns. The magnitude of the fluctuations and its radial dependence are comparable to the measured details. The results imply that collective fuel-assembly vibrations are a promising candidate for being the key to understand long-known fluctuation patterns in KWU built PWRs. Further research should elaborate on possible excitation mechanisms of the assumed vibration modes.

Crack Initiation Factor by Impact Fretting Wear at INCONEL Alloy for Steam Generator Tube in Nuclear Power Plants

2007 ◽  
Vol 26-28 ◽  
pp. 1269-1272
Author(s):  
Chi Yong Park ◽  
Jeong Kun Kim ◽  
Tae Ryong Kim ◽  
Sun Young Cho ◽  
Hyun Ik Jeon
Keyword(s):  
Steam Generator ◽  
Wear Mechanism ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Operating Conditions ◽  
Fretting Wear ◽  
Steam Generator Tube ◽  
Inconel Alloy ◽  
The Impact

Inconel alloy such as alloy 600 and alloy 690 is widely used as the steam generator tube materials in the nuclear power plants. The impact fretting wear tests were performed to investigate wear mechanism between tube alloy and 409 stainless steel tube support plates in the simulated steam generator operating conditions, pressure of 15MPa, high temperature water of 290°C and low dissolved oxygen(<10 ppb). From investigation of wear test specimens by the SEM and EDS analysis, hammer imprint, which is known to be an actual damaged wear pattern, has been observed on the worn surface, and fretting wear mechanism was investigated. Wear progression of impact-fretting wear also has been examined. It was observed that titanium rich phase contributes to the formation of voids and cracks in sub-layer of fretting wear damage by impact fretting wear.

scholarly journals Impact of Thorium Capture Cross Section Uncertainty on the Thorium Utilized ADS Reactivity Calculation

2014 ◽  
Vol 2014 ◽  
pp. 1-4
Author(s):  
Thanh Mai Vu ◽  
Takanori Kitada
Keyword(s):  
Cross Section ◽  
Capture Cross Section ◽  
Design Calculation ◽  
Capture Cross ◽  
Fast System ◽  
Driven System ◽  
Accelerator Driven System ◽  
Cross Section Uncertainty ◽  
The Impact ◽  
Fast Neutron Spectrum

Recently, the researches on fast neutron spectrum system utilized thorium fuel are widely conducted. However, the recent thorium cross section libraries are limited compared to uranium cross section libraries. The impact of thorium cross section uncertainty on thorium fuel utilized accelerator driven system (ADS) reactivity calculation is estimated in this study. The uncertainty of thekeffcaused by232Th capture cross section of JENDL-4.0 is about 1.3%. The uncertainty of JENDL-4.0 is needed to be enhanced to provide more reliable results on reactivity calculation for the fast system. The impact of uncertainty of  232Th capture cross section of ENDF/B-VII is small (0.1%). Therefore, it will cause no significant impact of the thorium cross section library on the thorium utilized ADS design calculation.

scholarly journals Comparative Analysis of Isotopic Composition of VVER-1000 Westinghouse and TVEL Spent Fuel

2016 ◽  
pp. 33-37
Author(s):  
Yu. Kovbasenko
Keyword(s):  
Comparative Analysis ◽  
Isotopic Composition ◽  
Boric Acid ◽  
Fuel Assembly ◽  
Spent Fuel ◽  
Operational Conditions ◽  
Manufacturing Tolerance ◽  
Fuel Assemblies ◽  
The Impact

The paper considers the impact of different operational conditions on VVER-1000 spent fuel isotopic composition. Such operational conditions include the presence or absence of absorber rods in guide tubes of fuel assemblies, changing the concentration of boric acid dissolved in the moderator (water) during the campaign, fuel and/or moderator temperature. Moreover, the impact caused by manufacturing tolerance applied while manufacturing fuel assembly was analyzed by weight of fuel and by its enrichment. Calculations were made for reactor cells of fuel assemblies for VVER-1000. They were composed of the new fuel assemblies of Westinghouse Company and the typical fuel assemblies of Russian TVEL suppliers.

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