A5041387374- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Fusion materials and technologies
- Nuclear physics research studies
- Nuclear Physics and Applications
- Superconducting Materials and Applications
- Atomic and Molecular Physics
- Thermodynamic and Structural Properties of Metals and Alloys
- Heat transfer and supercritical fluids
- Spacecraft and Cryogenic Technologies
- Nuclear and radioactivity studies
- Thermal properties of materials
- Graphite, nuclear technology, radiation studies
- Particle accelerators and beam dynamics
- Quantum Chromodynamics and Particle Interactions
- High voltage insulation and dielectric phenomena
- Astronomical and nuclear sciences
- X-ray Diffraction in Crystallography
- Magnetic confinement fusion research
- Islanding Detection in Power Systems
- Spectroscopy and Quantum Chemical Studies
- Advanced Thermodynamic Systems and Engines
- Quantum Mechanics and Non-Hermitian Physics
- Lubricants and Their Additives
Karlsruhe Institute of Technology
2013-2023
Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas
2009-2014
Universidad Complutense de Madrid
2014
Universidad Autónoma de Madrid
2007-2010
CEA DAM Île-de-France
2009
Universidad Politécnica de Madrid
2009
Telefonica Research and Development
2009
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2008
The equal filling approximation, a procedure widely used in mean-field calculations to treat the dynamics of odd nuclei time-reversal invariant way, is justified as consequence variational principle over an average energy functional. ideas statistical quantum mechanics are employed justification. As illustration method, ground and lowest-lying states some octupole deformed radium isotopes computed.
The evolution of the ground-state nuclear shapes in neutron-rich Sr, Zr, and Mo isotopes, including both even-even odd-A nuclei, is studied within a self-consistent mean-field approximation based on D1S–Gogny interaction. Neutron separation energies charge radii are calculated compared with available data. A correlation between shape transition discontinuity those observables found microscopically. While Sr Zr isotopes steep behavior observed isotopic dependence consequence sharp...
DEMO will be a fusion power plant demonstrating the integration into grid architecture of an electric utility grid. The design conversion chain is particular importance, as it must adequately account for specifics nuclear on generation side and ensure compatibility with at all times. One special challenges foreseen pulsed operation, which affects operation entire heat transport chain. This requires time-dependant analysis different concept approaches to proof reliable efficiency obtain...
The Pre-Concept Design (PCD) of the Balance Plant (BoP) systems EU-DEMO power plant is described in this paper for both breeding blanket (BB) concepts under assessment, namely Water Cooled Lithium Lead (WCLL) BB and Helium Pebble Bed (HCPB) BB. Moreover, results a preliminary evaluation number BoP variants are discussed. This outlines steps design development, highlighting project objectives strategy their achievement very challenging requirements which include, among others, intermittent...
By using the extension of statistical Wick's theorem (Gaudin's theorem) to deal with generalized density operators (those which can be expressed as product and operator carrying out a canonical transformations times operator) appropriate limits we are able rederive in very simple way standard for overlaps mean-field wave functions. Due simplicity derivation it is now straightforward consider more involved cases some them discussed. The present also allows us obtain general compact formulas...
Theoretical tools at the level of mean field approximation are used to explore spontaneous fission properties odd-A nuclei. The rely on equal (or uniform) filling deal with unpaired nucleon in a time-reversal preserving manner. Realistic calculations have been carried out finite range Gogny force D1S, which was tailored reasonably reproduce actinides. preliminary results obtained for nucleus 235 U analyzed and physical origin hindrance factor half life is discussed.
This paper presents simulation results of the CABRI BI1 test using code ASTEC-Na, currently under development, as well a comparison with available experimental data. The EU-JASMIN project (7th FP EURATOM) centres on development and validation new severe accident analysis ASTEC-Na (Accident Source Term Evaluation Code) for sodium-cooled fast reactors whose owner developer is IRSN. A series experiments performed in past (CABRI/SCARABEE experiments) to be conducted sodium facility KASOLA have...
The EU-JASMIN project (7th FP of EURATOM) has been centred on the development and validation new severe accident analysis code ASTEC-Na (Accident Source Term Evaluation Code) for Sodium-cooled Fast Reactors (SFR). such computational tool being able to assist safety innovative reactor concepts is crucial importance. One challenging issues when modelling SFRs neutronic reactivity feedbacks. This paper presents model implemented in representing effects SFR as well benchmarking results a ULOF...
When progressing from the International Thermonuclear Experimental Reactor (ITER) to Demonstration Fusion (DEMO), a system for transferring plasma heat exhaust power conversion is necessary so-called Balance of Plant (BOP). During preconceptual phase EU-DEMO project, different BOP concepts were investigated in order identify main requirements and feasible architectures achieve that goal most efficient way. This paper comprises investigations performed during DEMO design (p-CDP) compares...
Abstract The computational codes used in the evaluation of European sodium fast reactor—safety measures assessment and research tools(ESFR-SMART) reactor performance specifically their boiling models are assessed using two KNS-37 loss flow (LOF) experiments, i.e., L22 L29 tests, where onset two-phase regime up to dry-out occurred. well-equipped experimental facility provided very valuable information for understanding physical phenomena occurring a 37-pin subassembly under LOF conditions, as...
The CABRI E7 experiment was performed to study fuel pin failure and post-failure phenomena for an industrial with annular pellet design rupture subsequent ejection into liquid sodium. used a structured Transient OverPower (TOP) starting at nominal cooling conditions leading mechanical due cavity pressure build-up still constrained clad conditions. In this work we have studied the mechanisms serving as boundary material-relocation behavior. We also evaluated SAS-SFR code's capabilities...
We discuss several aspects of the fission phenomenon studied within a mean‐field approach with two incarnations Gogny force. Results for odd‐A nuclei obtained in framework equal‐filling approximation are discussed. also analyze impact finite but moderate temperature process and finally we properties neutron rich uranium isotopes different parametrizations force, namely D1S D1N.