The joint evaluated fission and fusion nuclear data library, JEFF-3.3

AJM Plompen, O Cabellos, C De Saint Jean… - The European Physical …, 2020 - Springer
The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations
for neutron-induced interactions with the major actinides^ 235 U 235 U,^ 238 U 238 U and …

APOLLO3®: Overview of the new code capabilities for reactor physics analysis

P Mosca, L Bourhrara, A Calloo… - Nuclear Science and …, 2024 - Taylor & Francis
APOLLO3® is a French deterministic reactor code for lattice and core calculations. It has
been developed at CEA (Commissariat à l'Energie Atomique) with the financial and …

TENDL: complete nuclear data library for innovative nuclear science and technology

AJ Koning, D Rochman, JC Sublet, N Dzysiuk… - Nuclear Data …, 2019 - Elsevier
The TENDL library is now established as one of the major nuclear data libraries in the world,
striving for completeness and quality of nuclear data files for all isotopes, evaluation …

Improved sterile neutrino constraints from the STEREO experiment with 179 days of reactor-on data

H Almazán, L Bernard, A Blanchet, A Bonhomme… - Physical Review D, 2020 - APS
The STEREO experiment is a very short baseline reactor antineutrino experiment. It is
designed to test the hypothesis of light sterile neutrinos being the cause of a deficit of the …

Pointing probability driven semi-analytic Monte Carlo method (PDMC)–Part I: global variance reduction for large-scale radiation transport analysis

Q Pan, H Lv, S Tang, J Xiong, X Liu - Computer Physics Communications, 2023 - Elsevier
Abstract We propose a Pointing Probability Driven Semi-Analytic Monte Carlo Method
(PDMC) to replace the traditional Monte Carlo method for reactor physics analysis and …

Quick calculation of damage for ion irradiation: implementation in Iradina and comparisons to SRIM

JP Crocombette, C Van Wambeke - EPJ N-Nuclear Sciences & …, 2019 - cea.hal.science
Binary collision approximation (BCA) calculation allows for two types of damage calculation:
full cascade and quick calculations. Full cascade mode describes fully the cascades while in …

New kinetic simulation capabilities for Tripoli-4®: Methods and applications

M Faucher, D Mancusi, A Zoia - Annals of Nuclear Energy, 2018 - Elsevier
Thanks to the growing computer power, it is now feasible to apply Monte Carlo methods to
the solution of non-stationary transport problems in reactor physics and in criticality-safety …

Computing adjoint-weighted kinetics parameters in TRIPOLI-4® by the Iterated Fission Probability method

G Truchet, P Leconte, A Santamarina, E Brun… - Annals of Nuclear …, 2015 - Elsevier
The analysis of neutron kinetics relies on the knowledge of adjoint-weighted kinetics
parameters, which are key to safety issues in the context of transient or accidental reactor …

Effect of the geometrical parameters of an HPGe detector on efficiency calculations using Monte Carlo methods

A Subercaze, T Sauzedde, C Domergue… - Nuclear Instruments and …, 2022 - Elsevier
This paper describes a procedure for constructing a Monte Carlo model of an HPGe detector
used to measure activity. The purpose of this parametric study is to obtain a single model …

Accurate Measurement of the Electron Antineutrino Yield of Fissions from the STEREO Experiment with 119 Days of Reactor-On Data

H Almazán, L Bernard, A Blanchet, A Bonhomme… - Physical Review Letters, 2020 - APS
We report a measurement of the antineutrino rate from the fission of U 235 with the STEREO
detector using 119 days of reactor turned on. In our analysis, we perform several detailed …