Clément Fausser

ORCID: 0000-0002-0334-4445
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About
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Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear Physics and Applications
  • Graphite, nuclear technology, radiation studies
  • Nuclear Materials and Properties
  • Radiation Detection and Scintillator Technologies
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Scientific Measurement and Uncertainty Evaluation
  • Radioactivity and Radon Measurements
  • Superconducting Materials and Applications
  • Radiation Therapy and Dosimetry
  • Nuclear and radioactivity studies
  • Scientific Computing and Data Management

CEA Cadarache
2013-2024

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2011-2024

Direction des énergies
2011-2018

CEA Paris-Saclay
2011-2015

A demonstration power plant (DEMO) will be the next step for fusion energy following ITER. Some of key design questions can addressed by simulations using system codes. System codes aim to model whole with all its subsystems and identify impact their interactions on choices. The SYCOMORE code is a modular developed address relevant tokamak reactor design. being within European Integrated Tokamak Modelling framework provides global view (technology physics) plant. It includes modules plasma...

10.1088/0029-5515/55/7/073011 article EN Nuclear Fusion 2015-06-15

The epithermal to fast neutron domain lacks reactions enhance the knowledge of spectrum in this energy range (1 keV 1 MeV). Previous studies on topic focused 94 Zr ( n , γ) capture and 117 Sn ′) inelastic reactions. In framework a research collaboration between French Atomic Alternative Energies Commission (CEA) Jožef Stefan Institute (JSI), new project consists finding suitable for dosimetry. This paper describes selection process be tested an experimental campaign at JSI.

10.1051/epjconf/202430801009 article EN cc-by EPJ Web of Conferences 2024-01-01

FLUOLE-2 is a benchmark-type experiment dedicated to 900 and 1450 MWe PWR vessels surveillance dosimetry. This two-year program started in 2014 will end 2015. It provide precise experimental data for the validation of neutron spectrum propagation calculation from core vessel. composed square surrounded by stainless steel baffe internals: barrel simulated structures leading different steel-water slides; two components stand capsule holder part pressure Measurement locations are available on...

10.1051/epjconf/201610602015 article EN cc-by EPJ Web of Conferences 2016-01-01

CALMAR, a new library for adjustment has been developed. This code performs simultaneous shape and level of an initial prior spectrum from measured reactions rates activation foils. It is written in C++ using the ROOT data analysis framework,with all linear algebra classes. STAYSL also reimplemented this library. Use very flexible : stand-alone, inside code, or driven by scripts. Validation test cases are under progress. Theses will be included package that available to community. Future...

10.1051/epjconf/201610607006 article EN cc-by EPJ Web of Conferences 2016-01-01

Since 1981, the French Alternative Energies and Atomic Energy Commission has been measuring dosimeters of surveillance capsules pressurized water reactors assessing their neutron fluence. This represents more than 250 PWR capsules, i.e. 4 thousands dosimeters. Started in Grenoble, this work continued Cadarache with creation “Measurement Applied to DosimEtry Reactors” (MADERE) platform within Dosimetry, Sensors Instrumentation Laboratory (LDCI). 1998, all measurements (i.e. Al-Co, 238 U, 237...

10.1051/epjconf/202430803003 article EN cc-by EPJ Web of Conferences 2024-01-01

Knowledge of neutron induced embrittlement reactor vessel or experimental devices is a key issue for the operating time management material test nuclear reactors, in particular pressurized water reactors.Experimental determination thermal and fast fluences dpa (displacement per atoms) often technically impossible with standard dosimetry techniques. The retrospective technique can enable this fluence evaluation by measuring activity sample taken from chosen device radio-isotope which...

10.1109/animma.2013.6727970 article EN 2013-06-01

Constant improvements of the computational power and methods as well demands accurate reliable measurements for reactor operation safety require a continuous upgrade instrumentation. In particular, nuclear sensors used in fission reactors (research or reactors) fusion facilities are operated under intense mixed neutron gamma-ray fields, need to be calibrated modeled provide selective measurements. The French Atomic Energy Alternative Energies Commission (CEA) Jožef Stefan Institute (JSI)...

10.1051/epjconf/202125304018 article EN cc-by EPJ Web of Conferences 2021-01-01

The aim of this paper is to present the capability TRIPOLI-4 ® , CEA Monte Carlo code, model a large-scale fusion reactor with complex neutron source and geometry. In past, numerous benchmarks were conducted for assessment on applications. Experiments (KANT, OKTAVIAN, FNG) analysis numerical (between MCNP5) HCLL DEMO2007 ITER models carried out successively. previous benchmark, nevertheless, only wall loading was analyzed, its main purpose MCAM (the FDS Team CAD import tool) extension ....

10.1051/snamc/201405115 article EN 2014-01-01
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