Sylvie Delpech

ORCID: 0000-0002-2406-2041
Publications
Citations
Views
---
Saved
---
About
Contact & Profiles
Research Areas
  • Nuclear Materials and Properties
  • Molten salt chemistry and electrochemical processes
  • Nuclear reactor physics and engineering
  • Social Sciences and Governance
  • Aging, Elder Care, and Social Issues
  • Nuclear materials and radiation effects
  • Radioactive element chemistry and processing
  • Graphite, nuclear technology, radiation studies
  • Magnesium Oxide Properties and Applications
  • Fusion materials and technologies
  • Concrete and Cement Materials Research
  • Nuclear Physics and Applications
  • Layered Double Hydroxides Synthesis and Applications
  • Chemical Synthesis and Characterization
  • Aluminum Alloy Microstructure Properties
  • Corrosion Behavior and Inhibition
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Extraction and Separation Processes
  • Nuclear and radioactivity studies
  • Bauxite Residue and Utilization
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Advanced Memory and Neural Computing
  • Metal Extraction and Bioleaching
  • Nuclear Engineering Thermal-Hydraulics
  • Concrete Corrosion and Durability

Centre National de la Recherche Scientifique
2010-2024

Laboratoire de Physique des 2 Infinis Irène Joliot-Curie
2019-2024

Institut National de Physique Nucléaire et de Physique des Particules
2015-2024

Université Paris-Saclay
2008-2024

Institut de Physique
2012-2020

Université Paris-Sud
2012-2019

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2019

Centre de Gestion Scientifique
2017

Chimie ParisTech
2006-2010

Sorbonne Université
2006-2008

The importance of pyrochemistry is being increasingly acknowledged and becomes unavoidable in the nuclear field. Molten salts may be used for fuel processing spent recycling, heat transfer, as a homogeneous breeder material fusion systems. Fluorides that are stable at high temperature under neutron flux especially promising. Analysis several field cases reveals corrosion molten fluorides essentially due to oxidation metals by uranium fluoride and/or oxidizing impurities. thermodynamics this...

10.1016/s1369-7021(10)70222-4 article EN cc-by-nc-nd Materials Today 2010-11-27

The aim of this paper is to present methods for corrosion mitigation in molten salt environments. structural materials depends directly on the redox potential salt. When higher than standard potentials elements constituting materials, occurs. If reverse true, no observed. Herein, a methodology calculating theoretical provided and compared with experimental measurements. Three ways mitigate by modifying are proposed: (i) using soluble/soluble system; (ii) potentiostatic method; (iii) an...

10.3390/ma17030581 article EN Materials 2024-01-25

Reliable neutron-induced-reaction cross sections of unstable nuclei are essential for nuclear astrophysics and applications but their direct measurement is often impossible. The surrogate-reaction method one the most promising alternatives to access these sections. In this work, we successfully applied infer first time both neutron-induced fission radiative capture ^{239}Pu in a consistent manner from single measurement. This was achieved by combining simultaneously measured γ-emission...

10.1103/physrevlett.125.122502 article EN Physical Review Letters 2020-09-18

Portland cement is extensively used for the conditioning of radioactive waste. However, its high alkalinity a serious obstacle to stabilization waste containing aluminum metal since oxidized by pore solution with production dihydrogen. This work investigates potential an alternative binder, magnesium potassium phosphate (MKP) cement, Al–Mg alloys comprising 2 4.5 wt% Mg and other metallic impurities. The objective assess influence alloy composition on reactivity in cementitious matrix at...

10.3390/ma16155415 article EN Materials 2023-08-02

Abstract The nuclear fuel reprocessing is a prerequisite for energy to be clean and sustainable energy. In the case of molten salt reactor containing liquid fuel, pyrometallurgical way an obvious way. method treatment divided into two parts. In-situ injection helium gas leads extract gaseous fission products part noble metals. second performed by ‘batch’. It aims recover fissile material separate minor actinides from products. involves several chemical steps based on redox acido-basic...

10.1515/nuka-2015-0153 article EN cc-by-nc-nd Nukleonika 2015-12-01

Aluminum reactivity in cement-based matrices, generally used for conditioning low- and intermediate-level radioactive wastes, is a problem due to dihydrogen produced by the corrosion reaction which depends on pH of pore solution. Electrochemical impedance spectroscopy has been propose mechanism aluminum cementitious matrices based ordinary Portland cement (OPC, ≈ 13) or magnesium phosphate (MKP, ranging between 4 9) containing not LiNO3 as inhibitor. The fit diagrams recorded electrode...

10.1149/2.0211713jes article EN cc-by Journal of The Electrochemical Society 2017-01-01

10.1016/j.electacta.2023.142019 article EN publisher-specific-oa Electrochimica Acta 2023-02-09

Molten salts (MSs) such as fluoride or chloride at high temperature (400–800 °C) are solvents known for their solvation power and electroactivity range. Rare earths, lanthanides, actinides, refractory metals can be dissolved, treated, purified in MSs. The properties of these particularly interesting nuclear spent-fuel reprocessing. pyrochemical separation extraction solutes performed using several methods taking into account the effects redox and/or acidity. This paper is focused on...

10.1351/pac-con-12-04-06 article EN Pure and Applied Chemistry 2012-10-09
Coming Soon ...