A5017433011- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Nuclear and radioactivity studies
- Graphite, nuclear technology, radiation studies
- Nuclear Engineering Thermal-Hydraulics
- Nuclear physics research studies
- Probabilistic and Robust Engineering Design
- Particle Accelerators and Free-Electron Lasers
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Heat transfer and supercritical fluids
- Radioactive element chemistry and processing
- Laser-Plasma Interactions and Diagnostics
- Electromagnetic Compatibility and Measurements
- Radiation Effects in Electronics
- Thermodynamic and Structural Properties of Metals and Alloys
- Quantum Information and Cryptography
- Quantum Computing Algorithms and Architecture
- Particle physics theoretical and experimental studies
- Fusion materials and technologies
- Electrostatic Discharge in Electronics
- Diverse Industrial Engineering Technologies
- Quantum-Dot Cellular Automata
Paul Scherrer Institute
2015-2024
Nuclear Safety Institute
2011-2023
Kazan State Power Engineering University
2023
Institute for High Energy Physics
1989-2022
Kurchatov Institute
2001-2022
Moscow Engineering Physics Institute
2017
Oak Ridge National Laboratory
2014
École Polytechnique Fédérale de Lausanne
2014
Nuclear Research and Consultancy Group
2014
Capabilities for uncertainty quantification (UQ) with respect to nuclear data have been developed at PSI in the recent years and applied UAM benchmark. The guiding principle UQ development has implement nonintrusive “black box” techniques state-of-the-art, production-quality codes used already routine analyses. Two complimentary thus far: (i) direct perturbation (DP) (ii) stochastic sampling (SS). DP technique is, first foremost, a robust versatile sensitivity coefficient calculation,...
The TALYS Evaluated Nuclear Data Library (TENDL) has now 8 releases since 2008. Considerable experience been acquired for the production of such general-purpose nuclear data library based on feedback from users, evaluators and processing experts. backbone this achievement is simple robust: completeness, quality reproducibility. If TENDL extensively used in many fields applications, it necessary to understand its strong points remaining weaknesses. Alternatively, essential knowledge not...
Abstract In this work, we explore the use of an iterative Bayesian Monte Carlo (iBMC) method for nuclear data evaluation within a TALYS Evaluated Nuclear Data Library (TENDL) framework. The goal is to probe model and parameter space code system find optimal sets that reproduces selected experimental data. involves simultaneous variation many reaction models as well their parameters included in code. ‘best’ set with its was obtained by comparing calculations Three types were used: (1) cross...
The use of Monte-Carlo (MC) simulations for neutronic reactor core physics has been high interest since long. Resulting MC models would be relevant, e.g., high-resolution assessments the local neutron flux and power gradients, generally beyond modeling capabilities engineering deterministic codes regular full simulations. Such particular importance advancement operation safety or, example, to support designing new materials testing experimental programs at operational reactors, advanced...
This paper presents a study of the impact nuclear data (cross sections, neutron emission and spectra) on different quantities for spent fuels (SNF) from Swiss power plants: activities, decay heat, gamma sources isotopic vectors. Realistic irradiation histories are considered using validated core follow-up models based CASMO SIMULATE. Two Pressurized one Boiling Water Reactors (PWR BWR) over large number operated cycles. All assemblies at end cycles studied, being reloaded or finally...
Abstract This paper presents an approach for the optimisation of geological disposal canister loadings, combining high resolution simulations used nuclear fuel characteristics with articial neural network and a genetic algorithm. The fuels (produced in open cycle without reprocessing) considered this work come from Swiss Pressurised Water Reactor, taking into account their realistic lifetime reactor core cooling periods, up to final repository. case 212 representative assemblies is analysed,...
This paper presents a Bayesian approach based on integral experiments to create correlations between different isotopes which do not appear with differential data. A simple set of equations is presented random nuclear data, similarly the usual methods applied As consequence, updated data (cross sections, [see formula in PDF], fission neutron spectra and covariance matrices) are obtained, leading better results. An example for 235 U 238 proposed taking into account Bigten criticality benchmark.
This paper presents a Bayesian approach based on integral experiments to create correlations which do not appear with differential data. Some quantities such as the fission cross section (σ), neutron multiplicity (ν̅p), spectra (χ), etc. are usually neither modeled together nor measured in coincidence, thus there is no correlation matrices evaluated nuclear data libraries. One can nevertheless use information from fast criticality-safety benchmarks correlate for possible inclusion A simple...
The "blackbox" approach of stochastic sampling (SS) methods for simultaneous nuclear data uncertainty quantification is powerful except it reveals little the individual contributions. In this work, SS-based tool "NUSS" (nuclear sampling) developed at PSI updated to "NUSS- RF" which estimates contributions total output uncertainty. new capability based on Random balance design and Fourier amplitude sensitivity testing methods, both belonging so-called global analysis. First, implementation...
In this study, an optimization of the canister loading for used nuclear fuels is performed, solely based on their decay heat values. By taking into account individual irradiation history each fuel assembly, as well with a number assumptions to be disposed, study indicates that filling fraction 94% achievable both PWR and BWR fuel, thus lowering required canisters compared previous study. This work emphasized need precise accounting, including reprocessed ones, considering all assemblies....