VVER-1000 fuel assembly model in CAD-based unstructured mesh for MCNP6

Kerntechnik ◽  
2019 ◽  
Vol 84 (4) ◽  
pp. 262-266
Author(s):  
M. Lovecký ◽  
J. Závorka ◽  
J. Vimpel
Keyword(s):  
Fuel Assembly ◽  
Unstructured Mesh ◽  
Assembly Model

Experimental studies of heat exchange for sodium boiling in the fuel assembly model: Safety substantiation of a promising fast reactor

2017 ◽  
Vol 64 (1) ◽  
pp. 6-14 ◽  
Author(s):  
R. R. Khafizov ◽  
V. M. Poplavskii ◽  
V. I. Rachkov ◽  
A. P. Sorokin ◽  
A. A. Trufanov ◽  
...  
Keyword(s):  
Heat Exchange ◽  
Fuel Assembly ◽  
Fast Reactor ◽  
Experimental Studies ◽  
Assembly Model

scholarly journals Analysis of Void Reactivity Coefficient for 3D BWR Assembly Model

2016 ◽  
Vol 2016 ◽  
pp. 1-9 ◽  
Author(s):  
Andrius Slavickas ◽  
Raimondas Pabarčius ◽  
Aurimas Tonkūnas ◽  
Eugenijus Ušpuras
Keyword(s):  
Monte Carlo ◽  
Fuel Assembly ◽  
Density Profile ◽  
3D Model ◽  
Functional Modules ◽  
Assembly Model ◽  
Density Values ◽  
The Difference ◽  
Reactivity Coefficient ◽  
Assembly Models

The effect of BWR fuel assembly 3D model on void reactivity coefficient (VRC) estimation is investigated. VRC values were calculated for different BWR assembly models applying deterministic T-NEWT and Monte Carlo KENO-VI functional modules of SCALE 6.1 code package. The difference between deterministic T-NEWT and Monte Carlo KENO-VI simulations is negligible (0.18 pcm/%). The influence of the assumed more detailed coolant density profile was estimated as well. VRC increases with the application of a larger number of coolant density values across fuel assembly height. It was shown that the coolant density profile described by 6 values per height could be considered sufficient from prospect of VRC estimation, as a more detailed density profile has impact below 1% on total assembly void effects. VRC values were decomposed to values for individual nodes and isotopes, since decomposition provides useful insights to describe the overall behaviour of VRC in detail.

Fuel Assembly Combined Lateral and Axial Model

2006 ◽  
Author(s):  
Sudhir J. Shah ◽  
Ben Brenneman ◽  
John H. Strumpell ◽  
Gary T. Williams
Keyword(s):  
Fuel Assembly ◽  
Test Data ◽  
Structural Model ◽  
Natural Frequencies ◽  
Mode Shapes ◽  
Axial Stiffness ◽  
Beam Model ◽  
Lateral Impact ◽  
Assembly Model ◽  
Fuel Rod

The objective of this paper is to develop a purely mechanistic fuel assembly structural model that will predict the fuel assembly’s static and dynamic characteristics from the knowledge of the fuel assembly’s geometry and component properties. This model provides a method for analyzing the static and dynamic lateral and axial properties of the fuel assembly. A comparison of various in-air fuel assembly test data such as lateral and axial stiffnesses and lateral natural frequencies is provided to demonstrate the analytical model. The fuel assembly model developed by Shah, Brenneman, etc. (1), achieved very good agreement with assembly lateral impact test data by utilizing a “3-beam” model. In that model, the fuel rod-to-spacer grid interfaces were represented by spring and friction elements. The fuel assembly was restrained at each grid position by means of rotational springs, which were benchmarked to the test frequencies. This newly developed model eliminates the need for using rotational springs at the grid locations. Hence, it fully simulates the fuel assembly lateral and axial behavior based on the fuel assembly geometric properties. The fuel assembly model is a 2-D planar model of beams in both lateral and axial directions. The grids are modeled with plate elements. At each grid location there are springs, preload, and frictional sliders representing the lateral and axial connectivity characteristics to the fuel assembly beam model. As the Zircaloy grid preloads relax from irradiation, they can be easily simulated by removing the preload. Hence, this model can represent the fuel assembly structural properties for all aspects of fuel assembly cycles. This model can be used to analyze the fuel assembly lateral static stiffness, first mode and higher order lateral natural frequencies, mode shapes, axial stiffness, in-grid stiffness, through-grid stiffness, and fuel assembly lateral and axial seismic and LOCA response. The model will also estimate the fuel rod frequencies and mode shapes. This model may eliminate the need for some expensive prototype fuel assembly testing.

scholarly journals Depletion uncertainty analysis to the MYRRHA fuel assembly model

2020 ◽  
Vol 239 ◽  
pp. 12001
Author(s):  
Augusto Hernandez Solis ◽  
Alexey Stankovskiy ◽  
Luca Fiorito ◽  
Gert Van den Eynde
Keyword(s):  
Uncertainty Analysis ◽  
Fuel Assembly ◽  
Fission Products ◽  
Nuclear Data ◽  
Assembly Model ◽  
Fission Yield ◽  
Constant Power ◽  
Constant Flux ◽  
Computational Performance ◽  
Statistical Variation

In this work, the objective is to perform an uncertainty analysis on a MYRRHA -Rev.1.6 irradiation cycle study, being applied to a depletion scenario of a single fresh fuel assembly while assuming reflective boundary conditions. Such analysis is statistically based on the application of Wilk’s method of building tolerance limits after 100 depletion calculations were performed with the SERPENT2 code. Due to the computational burden of such type of simulations, this propagation of nuclear data covariances study (allowed by the fast computational performance of SERPENT2) was done at constant power, constant flux and, in a final exercise, at constant power with the addition of fission yield uncertainties (all of these cases employed ENDF/B-VII.1 data). It was observed that while depleting at constant power, the statistical variation of key fission products such as 148Nd is almost not present because of the normalization factor applied to the flux. In contrast, the irradiation at constant flux reveals dependence on burnup. Finally, the added fission yield uncertainties make clear the fact that they directly impact the degree of final uncertainty computed for fission products exemplified by 148Nd and 135Xe important for burnup estimation and reactor operation, respectively.

Dynamic Interaction between the Coolant Flow and Fuel Assembly

Vestnik MEI ◽  
2019 ◽  
Vol 5 ◽  
pp. 11-23
Author(s):  
Konstantin N. Proskuryakov ◽  
Keyword(s):  
Fuel Assembly ◽  
Dynamic Interaction ◽  
Coolant Flow
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