Boglarka Babcsany

Boglarka Babcsany
Budapest University of Technology and Economics · Department of Nuclear Techniques

Doctor of Philosophy

About

28
Publications
1,178
Reads
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32
Citations
Introduction
Finite-element neutron transport modeling; Reactor physics characterization of SCW-SMRs
Additional affiliations
September 2017 - September 2020
Budapest University of Technology and Economics
Position
  • Research Assistant
Description
  • Teaching: Thermal-hydraulics of nuclear power plants, Reactor physics calculations; Research: Computational reactor physics, finite element neutron transport modeling
Education
September 2014 - September 2017
January 2013 - June 2014
September 2009 - January 2013
Budapest University of Technology and Economics
Field of study
  • Energy Engineering

Publications

Publications (28)
Article
Full-text available
The C-PORCA reactor physics code of the Paks Nuclear Power Plant performs three-dimensional, two-group diffusion calculations applying parametrized group constants generated by the HELIOS code. To improve the accuracy of the calculations, the C-PORCA code was extended with a simplified spherical harmonics module. This paper presents the applied fin...
Article
Full-text available
This paper describes steady-state reactor physics measurements and calculations that were performed for the Training Reactor of Budapest University of Technology and Economics (BME TR) with the purpose of benchmarking. Based on the available geometry specifications and material compositions a model of BME TR was created with the well-validated, gen...
Thesis
Full-text available
After a brief theoretical overview on the aspects of neutron transport modeling, semi-analytical solutions to the one-group SP3 equations are provided to extend existing SP3 benchmark problems with up to third-order scattering anisotropy and two- and three-dimensional test cases. Then, the continuous Galerkin finite element solution of the SP3 equa...
Article
Full-text available
As a follow-up to the paper previously published by the authors detailing the hybrid finite element (HYBFEM) solution of the SP3 equations, in this paper, besides a semi-analytical solver verification with an analysis on the applied source fitting polynomial order, three-dimensional VVER-440, and VVER-1000 benchmarks are reproduced with the continu...
Conference Paper
A joint European Canadian Chinese development of a supercritical water-cooled small modular reactor (SCW-SMR) technology is in progress since September 2020 in the framework of a Horizon 2020 project called ECC-SMART. As a main purpose of the project, proper estimates of energy deposition and its spatial distribution are prerequisites for the accur...
Conference Paper
The majority of the codes available for homogenized group constant generation for deterministic transport calculations apply the approximation of scalar flux weighting during energy group condensation of higher-order anisotropic scattering matrices. In this paper, we discuss the effect of scalar flux weighting of the linearly anisotropic scattering...
Article
Full-text available
Although diffusion theory is still the most widely applied deterministic method in reactor physics calculations, due to the increasing complexity of material composition and geometric structures in today's reactor design, and as a result of rapid development of computational technologies, neutronics codes based on higher-order transport approximati...
Article
A coupled thermal-hydraulics and reactor physics code system is being developed at the Institute of Nuclear Techniques of the Budapest University of Technology and Economics based on a higher-order transport approximation, the simplified spherical harmonics theory. The advantage of this method is that with a small increase in computational demand,...
Article
Full-text available
A Budapesti Műszaki és Gazdaságtudományi Egyetem Nukleáris Technikai Intézetében 2014 óta folynak aktív, a neutrontranszport állandósult és időbeli folyamatának diffúziós és magasabb rendű közelítésein alapuló végeselem-modellezését célzó, algoritmus- és programfejlesztési kutatások. Ezen reaktorfizikai kutatások egyik eredménye, hogy kifejlesztett...
Conference Paper
Today's computational technology and its rapid development more and more enable the application of higher-order transport approximations and advanced numerical solution techniques even in reactor dynamic calculations. In view of this, a coupled thermal-hydraulics and reactor physics code system is being developed at the Institute of Nuclear Techniq...
Technical Report
The purpose of this report is to provide Member States with information concerning the assessment of particle induced activation source terms for reactors and accelerators by focusing on: (i) a review of approaches and practices currently available for use in performing activation calculations; and (ii) providing guidance in the selection of an app...
Article
ATHLET-CD is the severe accident module of the code system AC² that is designed to simulate the core degradation phenomena including fission product release and transport in the reactor circuit, as well as the late phase processes in the lower plenum. In case of a severe accident degradation of the reactor core occurs, the fuel assemblies start to...
Article
Full-text available
The reliable operation of the emergency coolant pumps and passive gravitational injection systems are an important safety issue during accident scenarios with coolant loss in pressurized water reactors. Because of the pressure drop and flow disturbances surface vortices develops at the pump intakes if the water level decreasing below a critical val...
Conference Paper
Full-text available
The neutron physics background of the reactor physics code system currently applied at the Paks Nuclear Power Plant is based on the HELIOS two-dimensional transport code. The two group cross-sections generated by the HELIOS code are applied by the C-PORCA reactor physics code for three dimensional diffusion calculations with a spatial resolution of...
Article
Activation calculations for two nuclear power plants of WWER-440 type have been performed by the authors in order to assist the decommissioning planning by assessing the radioactive inventory present at the time of and at different times after the final shutdown. According to related international literature and studies performed earlier by the aut...
Conference Paper
Full-text available
Preliminary decommissioning plans constitute vital parts of the licensing documentation of nuclear power plants. On the other hand, a reasonable estimate of the amount and radiological characteristics of the radioactive waste born during the operational life of a power plant is crucial. Since the largest activities are created by neutron activation...
Conference Paper
In this paper, the new German energy policy is analyzed. The main objective of this analysis is to find an answer to the question mentioned in the title of the paper by conducting a multidimensional investigation concerning the sustainability of the current energy policy of the German government. This document also contains information about the ev...

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Cited By

Projects

Projects (3)
Archived project
Determine the activation of steel components and concrete structures of VVER-type nuclear reactors and estimate the amount and radiological characteristics of the radioactive waste born during the operational life of the NPP.
Project
Development of a flexible, multi-group, 3D diffusion and SPN code for steady-state and transient reactor physics simulations with different solver modules based on finite element and variational nodal methods
Project
Define the design requirements for the future SCW-SMR technology, to develop the pre-licensing study and guidelines for the demonstration of the safety in the further development stages of the SCW-SMR concept including the methodologies and tools to be used and to identify the key obstacles for the future SMR licencing and propose strategy for this process. Find out more: https://cordis.europa.eu/project/id/945234