Impact of mesh points number on the accuracy of deterministic calculations of control rods worth for Tehran research reactor
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E. Boustani
Abstract
In this paper two different computational approaches, a deterministic and a stochastic one, were used for calculation of the control rods worth of the Tehran research reactor. For the deterministic approach the MTR_PC package composed of the WIMS code and diffusion code CITVAP was used, while for the stochastic one the Monte Carlo code MCNPX was applied. On comparing our results obtained by the Monte Carlo approach and those previously reported in the Safety Analysis Report (SAR) of Tehran research reactor produced by the deterministic approach large discrepancies were seen. To uncover the root cause of these discrepancies, some efforts were made and finally was discerned that the number of spatial mesh points in the deterministic approach was the critical cause of these discrepancies. Therefore, the mesh optimization was performed for different regions of the core such that the results of deterministic approach based on the optimized mesh points have a good agreement with those obtained by the Monte Carlo approach.
Kurzfassung
In diesem Beitrag werden zwei verschiedene Rechenansätze, ein deterministischer und ein stochastischer, zur Berechnung des Reaktivitätswerts der Steuerstäbe am Teheraner Forschungsreaktor verwendet. Für den deterministischen Ansatz wurde das MTR_PC-Programmpaket bestehend aus WIMS-Code und Diffusion-Code CITVAP verwendet, für den stochastischen Ansatz der Monte-Carlo-Code MCNPX. Beim Vergleich der mit dem Monte-Carlo-Ansatz erhaltenen Ergebnisse mit den früher im Safety-Analysis-Report berichteten Ergebnissen auf der Grundlage des deterministischen Ansatzes zeigten sich große Unterschiede. Ursache dafür ist die Anzahl der räumlichen Ortspunkte. Es wurde deshalb eine Optimierung dieser Anzahl für verschiedene Kernregionen durchgeführt, so dass die Ergebnisse des deterministischen Ansatzes auf der Grundlage der optimierten Ortspunkte gut übereinstimmen mit den nach dem Monte-Carlo-Ansatz erhaltenen Ergebnissen.
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© 2016, Carl Hanser Verlag, München
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- Contents/Inhalt
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Use of molybdenum as a structural material of fuel elements for improving nuclear reactors safety
- Effect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code
- Spatial distribution of nanoparticles in PWR nanofluid coolant subjected to local nucleate boiling
- Impact of mesh points number on the accuracy of deterministic calculations of control rods worth for Tehran research reactor
- Dependence of neutron rate production with accelerator beam profile and energy range in an ADS-TRIGA RC1 reactor
- Effects of the wallpaper fuel design on the neutronic behavior of the HTR-10
- Loss of flow Accident (LOFA) analyses using LabView-based NRR simulator
- Basket criticality design of a dual purpose cask for VVER 1000 spent fuel assemblies
- Simulation of polycarbonate-CNT nanocomposite dosimeter based on electrical characteristics
- Thermoluminescence properties of micro and nano structure hydroxyapatite after gamma irradiation
- Equilibrium based analytical model for estimation of pressure magnification during deflagration of hydrogen air mixtures
- Polynomial approach method to solve the neutron point kinetics equations with use of the analytic continuation
- The slab albedo problem for the triplet scattering kernel with modified FN method
- Calculation of the fuel composition and the deterministic reloading pattern in the second cycle of the BUSHEHR VVER-1000 reactor using the weighting factor method
