Janos Bodi

Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution

Ben Lindley, Una Baker, Janos Bodi, Paul Cosgrove et autres

Abstract The objective of this paper is to quantify the coupling effect on the power distribution of sodium-cooled fast reactors (SFRs), specifically the European SFR. Calculations are performed with several state-of-the-art reactor physics and Multiphysics codes (TRACE/PARCS, DYN3D, WIMS, COUNTHER, and GeN-Foam) …

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ESFR SMART: A European Sodium Fast Reactor concept including the European feedback experience and the new safety commitments following Fukushima accident

Joël Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi

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Contributors

M. Allibert, Fatih Aydoğan, Janos Bodi, Shridhar K. Chande et autres

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Analysis of sodium boiling initiated by unprotected loss of flow in European sodium fast reactor core with different subassembly designs

Janos Bodi, Alexander N. Ponomarev, Konstantin Mikityuk

In this paper, an Unprotected Loss of Flow (ULOF) assessment has been performed on the European Sodium Fast Reactor developed in the ESFR-SMART EU project. To conduct the analysis, a simplified 42 channel thermal–hydraulic model has been established in TRACE system code, …

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Coupled Neutronic-Thermal-Hydraulic Simulations of the European SFR Core

Ben Lindley, F. Álvarez‐Velarde, Janos Bodi, Adam J. Charles et autres

Within the European SFR - Safety Measures Assessment and Research Tools (ESFR-SMART) project, steady-state coupled simulation of the ESFR core has been performed using several core analysis packages, with the objective of quantifying the coupling effect. Focus is on the fuel Doppler …

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

Joël Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi

Abstract Based on feedback from existing reactors and current projects, the European sodium fast reactor-safety measures assessment and research tools (ESFR-SMART) project proposes an optimization of the secondary circuit with the main aim of improving safety. Besides, the optimization also leads to …

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Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

Janos Bodi, Alexander N. Ponomarev, E. Bubelis, Konstantin Mikityuk

Abstract As part of the European sodium fast reactor (ESFR)-safety measures assessment and research tools (SMART) project, safety assessments are being conducted on the updated ESFR design. An important part of the study is the evaluation of the reactor's behavior within hypothetical …

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New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Joël Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi et autres

The European Sodium Fast Reactor Safety Measures Assessment and Research Tools (ESFR-SMART) project offers innovative options for a sodium fast reactor (SFR) to improve its safety. This paper explains the preliminary calculations made on the main options to roughly verify their feasibility. …

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New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Joël Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi et autres

Abstract Following up the previous collaborative project on European sodium fast reactor (CP-ESFR project), the European sodium fast reactor—safety measures assessment and research tools (ESFR-SMART project) considers the safety objectives envisaged for generation-IV reactors, taking into account the lessons learned from the …

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Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Aleksander Grah, H. Tsige-Tamirat, Joël Guidez, Antoine Gerschenfeld et autres

Abstract The decay heat removal system (DHRS) for the European sodium-cooled fast reactor (ESFR) concept consists of three cooling systems, which provide highly reliable, redundant, and diversified decay heat removal functions. Two of the systems provide a strong line of defense, whereas …

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Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

Janos Bodi, Alexander N. Ponomarev, Konstantin Mikityuk

Abstract In this article, a reactor core mechanical analysis method is introduced to provide a tool to calculate the reactivity effect of the fuel subassembly displacement in the reactor core, which is an important problem for reactor types such as the sodium-cooled …

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ESFR SMART PROJECT CONCEPTUAL DESIGN OF IN-VESSEL CORE CATCHER

Joël Guidez, Antoine Gerschenfeld, Janos Bodi, Konstantin Mikityuk et autres

Even before Fukushima accident occurred, the safety authorities have required that new power plant designs must take into account beyond design-basis accidents including possible core meltdown. Among the mitigation strategies, the corium retention must be ensured, so a core catcher is implemented …

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