EFFECT OF STAINLESS STEEL PLATE POSITION ON NEUTRON MULTIPLICATION FACTOR IN SPENT FUEL STORAGE RACKS

2011 ◽  
Vol 43 (1) ◽  
pp. 75-82 ◽  
Author(s):  
Hee-Dong Sohn ◽  
Jong-Kyung Kim
Keyword(s):  
Stainless Steel ◽  
Steel Plate ◽  
Multiplication Factor ◽  
Spent Fuel ◽  
Stainless Steel Plate ◽  
Neutron Multiplication ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Storage Racks

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.

Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants

2017 ◽  
Author(s):  
You Shi ◽  
Dong Ning ◽  
Yi-zhong Yang
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Spent Fuel ◽  
Absorber Plate ◽  
Neutron Absorber ◽  
Absorber Material ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Storage Racks

Boron Carbide (B4C) particle-reinforced aluminum matrix composite is the key material for use as neutron absorber plate in spent fuel storage racks as well as new fuel and in-containment fuel storage racks for GENIII advanced passive nuclear power plants in China. This material has once depended upon importing with high expense and restricted delivery schedule by foreign supplier. Therefore it has meaningful practical significance to realize the localized manufacturing for this material in China. More importantly, since it’s the first time for this material to be used in domestic plant, particular care should be taken to assure the formal supplied neutron absorber material products exhibit high stabilized and reliable service in domestic nuclear engineering. This paper initiates and proposes a principle design framework from technical view in qualification requirements for this neutron absorber material so as to guide the practical engineering application. Aiming at neutron absorber materials supplied under practical manufacturing condition in engineering delivery, the qualification requirements define B4C content, matrix chemistry, 10B isotope, bulk density, 10B areal density, mechanical property and microstructure as key criteria for material performance. The uniformity assessment as to different locations of this material is also required from at least three lots of material. Only qualified material meeting all of the qualification requirements should proceed to be verified by lifetime testing such as irradiation, corrosion and thermal aging testing. Systematic and comprehensive performance assessments and verification for process stabilization could be achieved through the above qualification. The long-term service for this neutron absorber material in reliable and safe way could be convincingly expected in spent fuel storage application in China.

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