A5006702485- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Fusion materials and technologies
- Nuclear Engineering Thermal-Hydraulics
- Nuclear and radioactivity studies
- Nuclear Physics and Applications
- Graphite, nuclear technology, radiation studies
- Heat transfer and supercritical fluids
- Combustion and Detonation Processes
- Magnetic confinement fusion research
- Risk and Safety Analysis
- Wind and Air Flow Studies
- Subcritical and Supercritical Water Processes
- Competency Development and Evaluation
- Network Security and Intrusion Detection
- Superconducting Materials and Applications
- Peer-to-Peer Network Technologies
- Evacuation and Crowd Dynamics
- Video Analysis and Summarization
- Internet Traffic Analysis and Secure E-voting
- Multimedia Communication and Technology
- Fuel Cells and Related Materials
- Smart Grid Security and Resilience
- Interstitial Lung Diseases and Idiopathic Pulmonary Fibrosis
Research Centre Rez
2014-2024
National Radiation Protection Institute
2020-2023
Universitat Politècnica de Catalunya
2016
University of Pisa
2009
Consorzio Interuniversitario per la Ricerca Tecnologica Nucleare
2008
The conceptual design studies for a European DEMO, include safety and analyses, to help guide the process start preparation eventual licensing. A approach has been adopted that is expected satisfy nuclear regulator, but at this early stage it difficult anticipate concerns may be raised. Potential issues DEMO have listed by regulatory technical body decay heat removal following an accidental loss of cooling or during blanket module replacement, minimization occupational radiation exposure,...
Nowadays nuclear is the only greenhouse‐free source that can appreciably respond to increasing worldwide energy demand. The use of Thorium in production may offer some advantages accomplish this task. Extensive R&D on thorium fuel cycle has been conducted many countries around world. Starting from current waste policy, EU‐PUMA project focuses potential benefits using HTR core as a Pu/MA transmuter. In paper following aspects have analysed: (1) state‐of‐the‐art studies Th different...
The topic of Nuclear Safety Culture touches several different aspects with contributions from the main organizations involved in nuclear projects and belonging to vendors, utility regulators. Two safety directives issued by European Commission emphasize fundamental principle national responsibility for are implemented each member country’s legislation. An example fission implementation is highlighted, referring Czech Republic legislation; an application fusion technology ITER project,...
One of the most important environmental and safety concerns in nuclear fusion plants is confinement radioactive substances into reactor buildings during both normal operations accidental conditions. For this reason, hydrogen build-up subsequent ignition must be avoided, since pressure energy generated may threaten integrity structures, causing dispersion toxic products toward public environment. Potentially dangerous sources are related to exothermal oxidation reactions between steam...
The safety features of the future nuclear fusion reactors are one key issues for their attractiveness if compared with fission plants. In devices, accidents high release radioactive materials have low probabilities because most part abnormal transients lead to passive plasma shutdown. It does not mean that radiological source terms such tritium and activated dust generated released, but inventory increase during events. Therefore, term has be assessed normal operation traced when occur. For...
To ensure the applicability of accident-tolerant fuels, their behaviors under various accidental conditions must be assessed. While dependences behavior single physical parameters can investigated in single- or separate-effect experiments, and more complex phenomena using integral-effect tests, an entire system as a nuclear power plant core computer code modeling. One most commonly used codes for assessment severe accidents is MELCOR 2.2. In version 18019, authors enabled modeling fuel with...
Abstract In this paper is described the concept of a 20 MW microreactor cooled by molten salts with registered trademark Energy Well. Well reactor designed to supply either electricity or heat, in remote areas into populated areas. The description includes context, main design features, safety systems, thermohydraulic analysis RELAPS 3D, logistic, and transport reactor.
This paper aims to compare the behaviour of VVER-1000 Nuclear Power Plants (NPPs) under DEC-A/B conditions, contemplating different fuel assemblies considered in mixed cores. The main characteristics both are described this paper, with a focus on highlighting key differences mass composition. There three models consideration: Model A, B and C. A consists core entirely filled equipped grids made Zr-1 %Nb, referred as "Type A" through paper. comprises that have Alloy 718 (aka Inconel), B"....
This paper reports the results of a comparison among JEFF and ENDF/B datasets when used by SERPENT MONTEBURNS codes on GFR-like configuration. Particularly, it shows between two Monte Carlo based codes, each one adopting three different cross sections dataset, namely JEFF-3.1, JEFF-3.1.2 ENDF/B-VII.1. Calculations have been carried out Allegro reactor, i.e. an experimental facility that should be built in EU as GFR demonstrator. Results concern nuclear parameters effective multiplication...
This work describes the computer model development of water–water energetic reactor (VVER) 1000 nuclear power plant (NPP) in methods for estimation leakages and consequences releases (MELCOR) 1.8.6 code its subsequent use accident scenarios analysis leading to core melting. The baseline scenario was a stress test case—the station blackout (SBO, complete loss alternating current electric plant). In addition this, four other were analyzed which SBO combined with technological failures—the...
This paper reports the results of a comparison among JEFF and ENDF/B data sets when used by SERPENT MONTEBURNS codes on gas-cooled fast reactor (GFR)-like configuration. Particularly, it shows between two Monte Carlo-based codes, each one adopting three different cross-section sets, namely, JEFF-3.1, JEFF-3.1.2, ENDF/B-VII.1. Calculations have been carried out Allegro reactor, i.e., an experimental GFR-like facility that could be built in European Union as GFR demonstration. Results include...
The rod ejection (RE) is a design basis accident in accordance with NUREG-0800 and usually studied using point kinetics. In this paper methodology 3D kinetic model prepared (PARCS), coupled thermal hydraulic system code (TRACE) for simulating scenario general VVER 1000 technology.
In the Czech Republic, as a follow-up, consortium of research organizations and universities has decided to simulate selected stress tests’ scenarios, in station blackout (SBO) loss ultimate heat sink (LoUHS), with aim verify national report analyze time response respective source term releases. These activities are carried out frame project prevention, preparedness, mitigation consequences severe accident (SA) at NPPs relation lessons learned from tests after Fukushima, financed by Ministry...
LVR-15 is a light-water-tank-type research reactor placed in stainless-steel vessel under shielding cover located the Research Centre Rez (CVR) near Prague. It operated at steady-state power of up to 10 MWt atmospheric pressure and cooled by forced circulation. In 2011, fuel was replaced, going from high-enriched uranium (HEU) low-enriched (LEU). After 2017, State Office for Nuclear Safety (SUJB) asked CVR evaluate Design Extended Conditions B (DEC-B). For this reason, new model developed...