A5062810305- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Radiation Detection and Scintillator Technologies
- Graphite, nuclear technology, radiation studies
- Radiation Therapy and Dosimetry
- Nuclear and radioactivity studies
- Fusion materials and technologies
- Boron Compounds in Chemistry
- Luminescence Properties of Advanced Materials
- Spectroscopy and Laser Applications
- NMR spectroscopy and applications
- Advanced X-ray and CT Imaging
- Radioactive contamination and transfer
- Particle Detector Development and Performance
- Advanced Radiotherapy Techniques
- Scientific Measurement and Uncertainty Evaluation
- Atmospheric Ozone and Climate
- X-ray Spectroscopy and Fluorescence Analysis
- Radioactivity and Radon Measurements
- Nuclear physics research studies
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2013-2024
CEA Cadarache
2013-2024
Direction des énergies
2016-2020
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.
CEA/Cadarache operates the MADERE facility dedicated to measuring activity of radionuclides generated during irradiation specific dosimeters made hyper-pure materials. This is equipped with seven spectrometers, two which are detection that emit X-rays. The laboratory processes solid-state rhodium and niobium dosimeters, X-rays 20 keV 16 respectively. In recent years, there have been significant improvements in nuclear decay data, leading better measurement these X-ray emitters. A joint LDCI...
The EOLE and MINERVE critical facilities of the CEA Cadarache play an important part in validation neutronic photonic calculation schemes associated nuclear data. In support Water Reactors studies, they are particular used for obtaining a large accurate experimental database nuclides arising plutonium waste management (heavy long lived fission products), exploring innovative systems reducing uncertainties to prediction most parameters. framework Gen-III reactors these programs supporting...
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...
The standard procedure for neutron reactor dosimetry is based on irradiation of a target and its post-irradiation analysis by Gamma and/or X-ray spectrometry. Nowadays, the spectra can be easily characterized thermal fast energies (respectively 0.025 eV <formula formulatype="inline" xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"><tex Notation="TeX">$ > 1~\hbox{MeV}$</tex></formula> ). In this paper we propose new an innovating technique in order...
The French Atomic Energy Commission CEA and the Japanese Incorporated Administrative Agency JNES (Japan Nuclear Safety Organisation) have undertaken first-of-a-kind full MOX core physics experiments, FUBILA, in EOLE critical facility of Cadarache Centre. experiments been designed to obtain data under high-burn-up 9 × 10 BWR assemblies operating conditions. experimental program, consisting eight different configurations, started January 2005 ended on September 1, 2006. analysis void increase...
The purpose of this paper is to demonstrate <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">92,94</sup> Zr application in neutron reactor dosimetry. We aim detect flux 1-keV 1-MeV energy range by irradiating samples under boron nitride (BN) filter. presence BN needed order cut off thermal contribution. This describes irradiation and experimental results that were obtained y spectrometry accelerator mass spectrometry. In parallel, modeled with...
The CEA MADERE platform (Measurement Applied to DosimEtry in REactors) is a part of the Instrumentation Sensors and Dosimetry Laboratory (LDCI). This facility dedicated specific activity measurements solid radioactive samples using Gamma X-ray spectrometry. high-performance devoted neutron dosimetry for experimental programs performed irradiation surveillance programmes PWR vessels. engaged continuous improvement process. Recently, two High Efficiency diodes have been integrated order manage...
The standard procedure for neutron reactor dosimetry is based on irradiation of a target and its post-irradiation analysis by Gamma and/or X-ray spectrometry. Nowadays, the spectra can be easily characterized thermal fast energies (respectively 0.025 eV >1 MeV). In this work we propose new an innovating postirradiation technique in order to detect within energy 1 keV MeV. This article will present calculations performed selection suitable nuclear reaction isotope, results predicted...
Reactor dosimetry is based on the analysis of activity irradiated dosimeters, such as 93mNb and 103mRh. The measurement these dosimeters conventionally performed by X-ray spectrometry, but low-energy emitted photons makes it difficult to derive reliable results with low uncertainties. Approaches improve characterisations are presented: they include high accuracy efficiency calibration a HPGe detector using both experiments Monte Carlo simulation, calculation corrective factors for geometry...
The French Atomic Energy Commission CEA and the Japanese Incorporated Administrative Agency JNES (Japan Nuclear Safety Organisation) have undertaken first-of-a-kind full MOX core physics experiments, FUBILA, in EOLE critical facility of Cadarache Centre. experiments been designed to obtain data under high-burn-up 9 × 10 BWR assemblies operating conditions. experimental program, consisting eight different configurations, started January 2005 ended on September 1, 2006. analysis void increase...
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...
<title>Abstract</title> Neutron activation dosimetry is the primary method for determination of neutron flux or fluence, and in general, it sensitive to thermal resonance energy ranges (radiative capture reactions - (n,g) reactions) fast range (threshold reactions). However, there are very few nuclear which specifically neutrons intermediate epithermal region. This region, along with range, will become particularly important development deployment new reactor technologies (Generation IV...