Study on Spent Fuel Pool and Storage Racks of the Advanced Nuclear Power Plant

2017 ◽  
Author(s):  
Ling Yun ◽  
Zhang Chao ◽  
Li Lei ◽  
Qian Hao ◽  
Ge Honghui ◽  
...  
Keyword(s):  
Numerical Model ◽  
Inclination Angle ◽  
Wave Amplitude ◽  
Coupling Effect ◽  
Solid Material ◽  
Spent Fuel ◽  
Scaled Model ◽  
Spent Fuel Pool ◽  
Storage Racks ◽  
And Storage

The present paper is concerned with the problem of modeling dynamic test. The study focuses on the fluid-structure interaction (FSI) in spent fuel pool, which is filled with liquid and spent fuel components. Through the comparison of the results of numerical analysis (Based on LS-DYNA) and modeling test, such as the sloshing wave amplitude; the displacement & inclination angle of the storage racks; pressure exerted on the plate of racks and the walls of the pool were obtained, This paper evaluates the seismic performance and the safety margin of the structure, and also provides the surface pressure input for the design of storage racks. The phenomena of liquid sloshing in spent fuel pool presents a great interest for civil and nuclear engineering, the dynamic effects of sloshing in spent fuel pool could affect the plates of storage racks and the wall of spent fuel pool during strong earthquakes. Study of sloshing in spent fuel pool is proved challenging due to the presence of strong flow interactions with storage racks in the pool. The movement effect caused by the sloshing load of liquid is the primary reason for the problem to become more complicated. In this study, two models were created, one is scaled model for shacking table test, another is a numerical model utilize finite element analysis code LS-DYNA. LS-DYNA command *CONSTRAINED_LAGRANGE_IN_SOLID was used to simulate the interaction between solid material and fluid material (fluid-solid coupling effect). Considering the fluid-solid coupling effect between solid and fluid, ALE (Arbitrary Lagrange Euler) element and Lagrange element were used to simulate fluid material and solid material respectively based on their different characters in the numerical model. Using the three spatial components of artificial time histories generated from the design response spectra. The following parameters should be paid attention to in both the scaled model shacking table test and the numerical simulation of time history analysis: The relative displacement between the structure of the spent fuel pool and storage racks; inclination angle of the storage racks; pressure exerted on the plate of storage racks and the wall of pool and the sloshing wave amplitude. In this paper, the integrated pressure represented by the impulsive hydrodynamic pressure on the plate of storage racks between the shacking table test model and the numerical model were calculated and compared. The analytical parameters of numerical model were corrected to make the numerical model result consistent with modeling test result. In this way, a more reasonable numerical model is obtained.

Fluid-Structure Interaction Numerical Analysis of the Spent Fuel Pool and Storage Racks Under Earthquake

2017 ◽  
Author(s):  
Ling Yun ◽  
Li Lei ◽  
Xue Rongjun ◽  
Qian Hao ◽  
Ge Honghui ◽  
...  
Keyword(s):  
Finite Element ◽  
Constitutive Model ◽  
Steel Plate ◽  
Seismic Loading ◽  
Spent Fuel ◽  
Structure Interaction ◽  
Fuel Storage ◽  
Spent Fuel Pool ◽  
Storage Racks ◽  
And Storage

Spent fuel pool and storage racks are important nuclear security structures and components. In order to prevent it from structural failure, which includes the loss of the structural integrity of the spent fuel pool and stability of the spent fuel storage racks, also includes the possibility of fallen down of storage racks under seismic loading. Besides the necessary static analysis of structures, the influence of seismic loading on the interaction between water and structure should be fully considered, Especially concerned the analysis of the shaking effect of water sloshing on the storage racks, the displacement and the possibility of fallen down of the storage racks. The present paper is concerned with the problem of modeling the fluid-structure interaction (FSI) in filled liquid and filled with spent fuel pool. The study focuses on the sloshing phenomena and on the coupling computational fluid dynamic (CFD) analysis with the finite element stress analysis (FEA) code LS-DYNA. By the results of the response of seismic, such as the displacement of the storage racks, pressure exerted on the plate of racks and the walls of the pool. This paper also evaluates the seismic performance of the structure and the safety margin. Various numerical methods can be used for analysis of liquid storage pools, among these we mention explicit finite element, implicit Lagrangian-Eulerian, hybrid finite element, Smoothed Particle Hydrodynamics volume of fluid. In this article the coupled sloshing dynamics in a rectangle pool were studied using a model developed in LS-DYNA environment. The main solution methodology is based on explicit time integration. In order to demonstrate the FSI results of the FEA models of the spent fuel pool on seismic analysis, a 3D FEA models were developed. The Finite element model composed of the spent fuel pool (steel plate concrete), spent fuel storage racks, cushion block, water and air. Solid element modeling is used in concrete, cushion block, water and air. Steel plate and storage racks employ the shell element. The constitutive model of solid element is linear elastic. And the constitutive model of fluid element is described by the Gruneisen equation. Arbitrary Lagrangian-Eulerian (ALE) formulation is thought of as algorithms that perform automatic rezoning. It realized the advection of water and air in the ALE multi-material group.

The Criticality Safety Analysis of the Spent Fuel Storage Pool Area I in Small Modular Reactor

2014 ◽  
Vol 986-987 ◽  
pp. 589-592
Author(s):  
Xiang Zhen Han ◽  
Guo Shun You
Keyword(s):  
Geometric Model ◽  
Spent Fuel ◽  
Storage Pool ◽  
Small Modular Reactor ◽  
Accident Condition ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Spent Fuel Pool ◽  
Storage Racks ◽  
Pool Area

Based on the Monte Carlo calculation method, geometric model of spent fuel storage pool Area I of small modular reactor is established, assuming infinite 6×6 type storage racks. Calculation results show that the reactivity is maximal when the water density is 1.0g/cm3. The value of keff is 0.8729 in normal storage condition. The spacing of storage racks in spent fuel pool would change in an earthquake accident condition. The values of reactivity of spent fuel pool in the assumed earthquake accident condition are also calculated. The values of keff are between 0.872 and 0.876. Both in normal condition and assumed earthquake accident condition, the values of keff are less than 0.95, to meet nuclear safety regulatory requirements.

Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask

2018 ◽  
Vol 114 ◽  
pp. 495-509 ◽  
Author(s):  
Jaerim Jang ◽  
Wonkyeong Kim ◽  
Sanggeol Jeong ◽  
Eun Jeong ◽  
Jinsu Park ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Safety Analysis ◽  
Monte Carlo Code ◽  
Spent Fuel ◽  
Spent Fuel Pool ◽  
And Storage ◽  
Criticality Safety

scholarly journals INTRODUCING BURNUP CREDIT FOR EXPANSION STAGE 2 OF THE EXTERNAL SPENT FUEL POOL AT GÖSGEN NPP

2021 ◽  
Vol 247 ◽  
pp. 17007
Author(s):  
Axel Hoefer ◽  
Martin Basler ◽  
Oliver Buss ◽  
Gaëtan Girardin ◽  
Fabian Jatuff ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Multiplication Factor ◽  
Spent Fuel ◽  
Statistical Confidence ◽  
Fuel Assemblies ◽  
Neutron Multiplication ◽  
Expansion Stage ◽  
Spent Fuel Pool ◽  
Storage Racks ◽  
Criticality Safety

We present a summary of the actinide-plus-fission-product burnup credit criticality safety licensing analysis for Expansion Stage 2 (ES2) of the external spent fuel pool at Gösgen nuclear power plant. In ES2, the nine Expansion Stage 1 storage racks currently installed in the external spent fuel pool are going to be supplemented by nine ES2 storage racks with a significantly reduced fuel assembly pitch. They are designed for loadings with fuel assemblies above a well-defined minimum required burnup. The objective of the criticality safety analysis is to calculate the minimum required burnup values for the uranium and MOX fuel assemblies to be stored in the ES2 storage racks. We use a methodology that allows us to take into account the reactivity effects due to variabilities and uncertainties of all relevant parameters involved in a burnup credit criticality safety assessment in a bounding manner. These include manufacturing tolerances of the fuel assemblies and storage racks, the irradiation histories and burnup profiles of the spent fuel assemblies, the bias of the depletion code used to calculate the isotopic inventories of the irradiated fuel, and the bias of the criticality code used to calculate the neutron multiplication factor of the considered storage configuration. A combination of different statistical procedures is used to evaluate and propagate the uncertainty information on the input parameters and translate it into statistical confidence statements about the neutron multiplication factor. It should be noted that the presented analysis is related to the first implementation of a significant burnup credit for wet storage of PWR fuel in Switzerland.

Two-scale CFD analysis of a spent fuel pool involving partially uncovered fuel storage racks

2019 ◽  
Vol 341 ◽  
pp. 432-450 ◽  
Author(s):  
Ronald Oertel ◽  
T. Hanisch ◽  
E. Krepper ◽  
D. Lucas ◽  
F. Rüdiger ◽  
...  
Keyword(s):  
Cfd Analysis ◽  
Spent Fuel ◽  
Fuel Storage ◽  
Spent Fuel Pool ◽  
Storage Racks

The holistic risk analysis of spent fuel pool considering the fuel route risk

2021 ◽  
pp. 1748006X2199851
Author(s):  
Zhixin Xu ◽  
Ming Wang ◽  
Binyan Song ◽  
WenYu Hou ◽  
Chao Wang
Keyword(s):  
Nuclear Power ◽  
Comprehensive Evaluation ◽  
Point Of View ◽  
Spent Fuel ◽  
Nuclear Disaster ◽  
Evaluation Approach ◽  
Fuel Assemblies ◽  
Spent Fuel Pool ◽  
Large Water ◽  
Fukushima Nuclear Disaster

The Fukushima nuclear disaster has raised the importance on the reliability and risk research of the spent fuel pool (SFP), including the risk of internal events, fire, external hazards and so on. From a safety point of view, the low decay heat of the spent fuel assemblies and large water inventory in the SFP has made the accident progress goes very slow, but a large number of fuel assemblies are stored inside the spent fuel pool and without containment above the SFP building, it still has an unignored risk to the safety of the nuclear power plant. In this paper, a standardized approach for performing a holistic and comprehensive evaluation approach of the SFP risk based on the probabilistic safety analysis (PSA) method has been developed, including the Level 1 SFP PSA and Level 2 SFP PSA and external hazard PSA. The research scope of SFP PSA covers internal events, internal flooding, internal fires, external hazards and new risk source-fuel route risk is also included. The research will provide the risk insight of Spent Fuel Pool operation, and can help to make recommendation for the prevention and mitigation of SFP accidents which will be applicable for the SFP configuration risk management.

Influence of Gap Size on Added Mass for Spent Fuel Storage Rack

2018 ◽  
Author(s):  
Daogang Lu ◽  
Yu Liu ◽  
Shu Zheng
Keyword(s):  
Vibration Frequency ◽  
Input Parameter ◽  
Added Mass ◽  
Water Tank ◽  
Spent Fuel ◽  
Free Standing ◽  
Fluid Force ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Spent Fuel Pool

Free standing spent fuel storage racks are submerged in water contained with spent fuel pool. During a postulated earthquake, the water surrounding the racks is accelerated and the so-called fluid-structure interaction (FSI) is significantly induced between water, racks and the pool walls[1]. The added mass is an important input parameter for the dynamic structural analysis of the spent fuel storage rack under earthquake[2]. The spent fuel storage rack is different even for the same vendors. Some rack are designed as the honeycomb construction, others are designed as the end-tube-connection construction. Therefore, the added mass for those racks have to be measured for the new rack’s design. More importantly, the added mass is influenced by the layout of the rack in the spent fuel pool. In this paper, an experiment is carried out to measure the added mass by free vibration test. The measured fluid force of the rack is analyzed by Fourier analysis to derive its vibration frequency. The added mass is then evaluated by the vibration frequency in the air and water. Moreover, a two dimensional CFD model of the spent fuel rack immersed in the water tank is built. The fluid force is obtained by a transient analysis with the help of dynamics mesh method.

scholarly journals Microbial enrichment and gene functional categories revealed on the walls of a spent fuel pool of a nuclear power plant

PLoS ONE ◽  
2018 ◽  
Vol 13 (10) ◽  
pp. e0205228 ◽  
Author(s):  
Rosane Silva ◽  
Darcy Muniz de Almeida ◽  
Bianca Catarina Azeredo Cabral ◽  
Victor Hugo Giordano Dias ◽  
Isadora Cristina de Toledo e Mello ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Spent Fuel ◽  
Functional Categories ◽  
Spent Fuel Pool
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