International audienceHigh quality nuclear data is the most fundamental underpinning for all neutron metrology applications. This paper describes the release of version II of the International Reactor Dosimetry and Fusion File (IRDFF-II) that contains a consistent set of nuclear data for fission and fusion neutron metrology applications up to 60 MeV neutron energy. The library is intended to support: a) applications in research reactors; b) safety and regulatory applications in the nuclear power generation in commercial fission reactors; and c) material damage studies in support of the research and development of advanced fusion concepts. The paper describes the contents of the library, documents the thorough verification process used in it...
An overview is presented of recent neutron data measurements and equipment developments at IRMM. Neu...
The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for ne...
ABSTRACT: For fast neutron fluence measurement, the neutron activation detectors are covered sometim...
International audienceHigh quality nuclear data is the most fundamental underpinning for all neutron...
Spectrum-averaged cross sections (SACS) have been measured in the reference 252Cf(sf) neutron field ...
One of the main objectives of reactor dosimetry is the determination of the physical parameters char...
The evolution of validation metrics for dosimetry cross sections in neutron benchmark fields is expl...
Abstract: This document describes the contents of the International Reactor Dosimetry File IRDF-90 V...
The results of validation of the latest release of International Reactor Dosimetry and Fusion File, ...
The cross section is a fundamental quantity which affects the accuracy of Monte Carlo simulations wi...
The neutron flux-spectrum in a fusion device is frequently determined with activation foils and adju...
The MetroFission project, a Joint Research Project within the European Metrology Research Program (E...
With the need for improving existing nuclear data evaluations, (e.g., ENDF/B-VIII.0 and JEFF-3.3 rel...
In order to validate a new library of dosimetry cross section data, International Reactor Dosimetry ...
The Joint Evaluated Fission and Fusion nuclear data library 3.3 is described. New evaluations for ne...
An overview is presented of recent neutron data measurements and equipment developments at IRMM. Neu...
The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for ne...
ABSTRACT: For fast neutron fluence measurement, the neutron activation detectors are covered sometim...
International audienceHigh quality nuclear data is the most fundamental underpinning for all neutron...
Spectrum-averaged cross sections (SACS) have been measured in the reference 252Cf(sf) neutron field ...
One of the main objectives of reactor dosimetry is the determination of the physical parameters char...
The evolution of validation metrics for dosimetry cross sections in neutron benchmark fields is expl...
Abstract: This document describes the contents of the International Reactor Dosimetry File IRDF-90 V...
The results of validation of the latest release of International Reactor Dosimetry and Fusion File, ...
The cross section is a fundamental quantity which affects the accuracy of Monte Carlo simulations wi...
The neutron flux-spectrum in a fusion device is frequently determined with activation foils and adju...
The MetroFission project, a Joint Research Project within the European Metrology Research Program (E...
With the need for improving existing nuclear data evaluations, (e.g., ENDF/B-VIII.0 and JEFF-3.3 rel...
In order to validate a new library of dosimetry cross section data, International Reactor Dosimetry ...
The Joint Evaluated Fission and Fusion nuclear data library 3.3 is described. New evaluations for ne...
An overview is presented of recent neutron data measurements and equipment developments at IRMM. Neu...
The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for ne...
ABSTRACT: For fast neutron fluence measurement, the neutron activation detectors are covered sometim...