Reduced Basis Approaches in Time-Dependent Non-Coercive Settings for Modelling the Movement of Nuclear Reactor Control Rods

2016 ◽  
Vol 20 (1) ◽  
pp. 23-59
Author(s):  
Alberto Sartori ◽  
Antonio Cammi ◽  
Lelio Luzzi ◽  
Gianluigi Rozza
Keyword(s):  
Nuclear Reactor ◽  
Time Dependent ◽  
Reduced Basis ◽  
Reactor Control ◽  
Element Discretization ◽  
Control Rod ◽  
Basis Method ◽  
And Control ◽  
Control Rods ◽  
Nuclear Reactor Control

AbstractIn this work, two approaches, based on the certified Reduced Basis method, have been developed for simulating the movement of nuclear reactor control rods, in time-dependent non-coercive settings featuring a 3D geometrical framework. In particular, in a first approach, a piece-wise affine transformation based on subdomains division has been implemented for modelling the movement of one control rod. In the second approach, a “staircase” strategy has been adopted for simulating the movement of all the three rods featured by the nuclear reactor chosen as case study. The neutron kinetics has been modelled according to the so-called multi-group neutron diffusion, which, in the present case, is a set of ten coupled parametrized parabolic equations (two energy groups for the neutron flux, and eight for the precursors). Both the reduced order models, developed according to the two approaches, provided a very good accuracy compared with high-fidelity results, assumed as “truth” solutions. At the same time, the computational speed-up in the Online phase, with respect to the fine “truth” finite element discretization, achievable by both the proposed approaches is at least of three orders of magnitude, allowing a real-time simulation of the rod movement and control.

A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods

2016 ◽  
Vol 2 (2) ◽  
Author(s):  
Alberto Sartori ◽  
Antonio Cammi ◽  
Lelio Luzzi ◽  
Gianluigi Rozza
Keyword(s):  
Neutron Flux ◽  
Nuclear Reactor ◽  
Voronoi Tessellation ◽  
Sampling Technique ◽  
Computational Time ◽  
High Fidelity ◽  
Reduced Basis ◽  
Reactor Control ◽  
Control Rods ◽  
Nuclear Reactor Control

This work presents a reduced order model (ROM) aimed at simulating nuclear reactor control rods movement and featuring fast-running prediction of reactivity and neutron flux distribution as well. In particular, the reduced basis (RB) method (built upon a high-fidelity finite element (FE) approximation) has been employed. The neutronics has been modeled according to a parametrized stationary version of the multigroup neutron diffusion equation, which can be formulated as a generalized eigenvalue problem. Within the RB framework, the centroidal Voronoi tessellation is employed as a sampling technique due to the possibility of a hierarchical parameter space exploration, without relying on a “classical” a posteriori error estimation, and saving an important amount of computational time in the offline phase. Here, the proposed ROM is capable of correctly predicting, with respect to the high-fidelity FE approximation, both the reactivity and neutron flux shape. In this way, a computational speedup of at least three orders of magnitude is achieved. If a higher precision is required, the number of employed basis functions (BFs) must be increased.

scholarly journals Measurement and Comparison of Control Rod Worth of BTRR using Inhour Equation and Period reactivity conversion table

2017 ◽  
Vol 41 (1) ◽  
pp. 95-103
Author(s):  
Md Iqbal Hosan ◽  
MAM Soner ◽  
Md Fazlul Huq ◽  
Khorshed Ahmad Kabir
Keyword(s):  
Doubling Time ◽  
Nuclear Reactor ◽  
Reactor Control ◽  
Control Rod ◽  
Fuel Burn ◽  
Start Up ◽  
Conversion Table ◽  
Power Operation ◽  
Academy Of Sciences ◽  
Control Rods

In a nuclear reactor, control rod is a very essential part and plays the elementary role in the reactor control during reactor start up, normal power operation, experimental research and shutdown. To perform all these operations safely, knowledge of differential and integral worth of the control rod is mandatory. In this study, the differential and integral worth curve of all control rods of BAEC TRIGA Research Reactor (BTRR) have been determined by using the positive period method. Reactor period was measured from 1.5 folding time, doubling time, 5 folding time respectively; and in the above three cases reactivity has also been calculated from INHOUR equation and period reactivity conversion table. The total worth of all control rods of BTRR are measured as 14.888 $, 14.672 $, 14.348 $ from INHOUR equation and 13.978 $, 13.672 $, 13.357 $ from period reactivity conversion table for 1.5 folding time, doubling time and 5 folding time respectively. The measured reactivity has also been compared with the previously measured reactivity and due to fuel burn up of the reactor expected lower values were observed.Journal of Bangladesh Academy of Sciences, Vol. 41, No. 1, 95-103, 2017

scholarly journals Approximation in Quantum Quadrupole at Juergen Model for Nuclear Reactor Control Rod Blade Based on \ce {Th_xDUO2} Nano Materials

2018 ◽  
Vol 4 (1) ◽  
pp. 7
Author(s):  
Moh. Hardiyanto
Keyword(s):  
Neutron Flux ◽  
Thermal Neutron ◽  
Thermal Neutron Flux ◽  
Nuclear Reactor ◽  
Hadron Collider ◽  
Reactor Control ◽  
Neutron Absorber ◽  
Control Rod ◽  
Chain Reactions ◽  
Nuclear Reactor Control

The functional of a multi purpose research nuclear reactor control rod blade nuclear reactor is stabilized and controlling devices for nuclear chain reactions, the existing of Cerenkov's radiation impact and thermal neutron flux in reactor chamber. This research was conducted in Large Hadron Collider (LHC) - Muon Hadron Division at CERN, Lyon - France under International Research between Canadian Deuterium Uranium (CANDU) - Nuclear Reactor and Betha Group Section for sub-particles for nanomaterial. Using Juergen Model with quantum states approaching and testing by Muon-Hadron Stirrer equipment had determined the \ce {Th_xDUO2} derivatives materials. This material shown the strength of thermal neutron flux absorbed about 2.56 × 10⁵ − 1.94 × 10⁶ Ci/mm, the value of Electrical Conductivity is 26.62 − 29.98 in 800° - 890° C temperature, however at 2.1 × 10⁵ Ci/mm thermal neutron flux condition is 29.44 − 37.88 in IAEA standard. At 450 tesla magnetic field and 2.1 × 10⁵ Ci/mm thermal neutron absorber, the crystalline structure reduction is 6.88% until 10.95% for 25 years period in 45.7 megawatts with \ce {UO2} more enrichment and \ce {Pu2O} also \ce {Th2O_y} nuclear fuel element matrix.

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