A5059302517- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Radiation Detection and Scintillator Technologies
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Fusion materials and technologies
- Nuclear Engineering Thermal-Hydraulics
- Nuclear physics research studies
- Probabilistic and Robust Engineering Design
- Particle Detector Development and Performance
- Optimization and Packing Problems
- Advanced Manufacturing and Logistics Optimization
- Radioactive contamination and transfer
- Reliability and Maintenance Optimization
- Masonry and Concrete Structural Analysis
- Geophysical Methods and Applications
- Influenza Virus Research Studies
- Risk and Safety Analysis
- Advanced NMR Techniques and Applications
- Non-Destructive Testing Techniques
- Iron and Steelmaking Processes
- Structural Health Monitoring Techniques
- Radiation Therapy and Dosimetry
- Optimization and Search Problems
Jožef Stefan Institute
2013-2024
National University of Distance Education
2024
European Commission
2015-2022
Joint Research Center
2014-2021
Oak Ridge National Laboratory
2018
University of Ljubljana
2009-2017
Institute of Mathematics, Physics, and Mechanics
2012
We describe the new ENDF/B-VIII.0 evaluated nuclear reaction data library. fully incorporates IAEA standards, includes improved thermal neutron scattering and uses from CIELO project for reactions on 1H, 16O, 56Fe, 235U, 238U 239Pu described in companion papers present issue of Nuclear Data Sheets. The evaluations benefit recent experimental obtained U.S. Europe, improvements theory simulation. Notable advances include updated light nuclei, structural materials, actinides, fission energy...
Abstract The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides $$^{235}\hbox {U}$$ <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:msup><mml:mrow /><mml:mn>235</mml:mn></mml:msup><mml:mtext>U</mml:mtext></mml:mrow></mml:math> , $$^{238}\hbox /><mml:mn>238</mml:mn></mml:msup><mml:mtext>U</mml:mtext></mml:mrow></mml:math> $$^{239}\hbox {Pu}$$...
Recent advancements in the neutronics activities of IFMIF-DONES project, developed within EUROfusion framework, are presented. These include updates to radiation dose maps during commissioning and normal operation accelerator systems; material irradiation analyses shielding optimization test activation inventories 7Be, 3H, activated corrosion products Li shutdown transportation storage radioactive waste, cooling water atmosphere gas activations, skyshine public, etc. The development...
The decay heat rate of five spent nuclear fuel assemblies the pressurized water reactor type were measured by calorimetry at interim storage for in Sweden. Calculations performed 20 organizations using different codes and data libraries resulting 31 results each assembly, spanning most current state-of-the-art practice. calculations based on a selected subset information, such as operating history assembly properties. relative difference between average calculated ranged from 0.6% to 3.3%...
The aim of the current bilateral project between CEA Cadarache and JSI is to improve accuracy online thermal power monitoring at TRIGA reactor. Simultaneously, a new wide range multichannel acquisition system for fission chambers, recently developed by CEA, tested. In paper, calculational experimental calibration methods are described. focus on use multiple detectors in combination with pre-calculated pre-measured control-rod-position-dependent correction factors reactor reading. will be...
Previous work done on reactor kinetics and control in load-following operation modes available open literature is reviewed. The analysis focused on, however not limited to pressurized water reactors. Different approximations of the time-dependent neutron transport problem as well different algorithms are described detail compared. Due lack published information majority comparisons was qualitative level. In order facilitate future testing intercomparisons models algorithms, two so-called...
The feasibility and the limitations of using nuclear energy as a dispatchable power source for covering daily fluctuations solar electricity are examined. In particular, perspective production in Slovenia until 2050 is investigated, focussing on projected rapid increase resulting large-scale annual fluctuations. However, study relevant any electrical grid where photovoltaics likely to become one main sources electricity. A simulation based nonlinear pressurized water reactor (PWR) model with...
Monte Carlo sampling is frequently employed for uncertainty quantification in depletion calculations. Several assumptions are needed to perform this analysis. In work, an assessment of these proposed via sample convergence studies and perturbation the distribution. The Uncertainty Analysis Best-Estimate Modeling (UAM) Pincell Hot Full Power Turkey Point reference cases were considered purpose. 235U thermal independent fission yield uncertainties evaluated JEFF-3.3 JEFF-4.0 propagated nuclide...