Concept
Nuclear meltdown
Related publications (142)
Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM
Andreas Pautz, Jiri Krepel, Fanny Vitullo, Horst-Michael Prasser
In the pebble-bed high-temperature reactor under construction in China, called the HTR-PM, the spherical fuel elements continuously flow downward in the cylindrical core. The burnup of each pebble is checked at the core outlet and, according to the achieve ...
ASME2020Development and verification of a methodology for neutron noise response to fuel assembly vibrations
Andreas Pautz, Hakim Ferroukhi, Abdelhamid Dokhane, Gaëtan Girardin, Dionysios Chionis
Nuclear reactors are stochastic systems, in which several parameters fluctuate even during steady-state conditions. In addition, structural components like fuel assemblies, vibrate due to strong hydraulic forces. This stochasticity is the cause of the neut ...
PERGAMON-ELSEVIER SCIENCE LTD2020In-core dosimetry for the validation of neutron spectra in the CROCUS reactor
Andreas Pautz, Vincent Pierre Lamirand, Pavel Frajtag, Axel Guy Marie Laureau, Yifeng Jiang
The present article describes the preliminary validation study of simulated in-core and reflector n eutron spectra in preparation of oncoming experimental programs in the zero-power reactor CROCUS at EPFL. For this purpose, a set of activation foils were i ...
E D P SCIENCES2020Application of causality analysis on nuclear reactor systems
Andreas Pautz, Hakim Ferroukhi, Abdelhamid Dokhane, Dionysios Chionis
Causality analysis is a substantial tool for identifying cause-and-effect links between different components of a system and has been extensively used in various areas of science such as neuroscience, climatology, and econometrics. This analysis is carried ...
AMER INST PHYSICS2019Development and Application of Data Assimilation Methods in Reactor Physics
Simulations of nuclear reactor physics can disagree significantly from experimental evidence, even when the most accurate models are used. An important part of this bias from experiment is caused by nuclear data. The nuclear data have inherent uncertaintie ...
EPFL2019High-Temperature Water Effects on the Fracture Behaviour of Low-Alloy Reactor Pressure Vessel Steels
The structural integrity of the reactor pressure vessel (RPV) of light water reactors (LWR) is of utmost importance regarding operation safety and lifetime. High-temperature water (HTW) and hydrogen absorbed from environment, in synergy with irradiation em ...
EPFL2019Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments
Philippe Spätig, Hans-Peter Seifert, Zaiqing Que
Elastic plastic fracture mechanics tests on different low-alloy reactor pressure vessel (RPV) steels in air and various simulated light water reactor environments revealed a clear, but moderate reduction of the fracture initiation resistance of RPV steels ...
2019Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contents
Philippe Spätig, Hans-Peter Seifert, Zaiqing Que
The fracture behaviour of low-alloy reactor pressure vessel steels with various sulphur and phosphorus contents, different environmentally-assisted cracking (EAC) and temper embrittlement (TE) susceptibilities was evaluated by elastic plastic fracture mech ...
2019Towards the validation of neutron noise simulators: qualification of data acquisition systems
Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Oskari Ville Pakari, Axel Guy Marie Laureau, Adolfo Rais
This paper deals with the processes involved in the generation of reliable experimental data for the validation of computer simulations. In the field of neutron noise, the analysis of results is based on spectral features of the detector signals in the fre ...
2019Extension of the nodal code DYN3D to SFR applications
DYN3D is a well-established Light Water Reactor (LWR) simulation tool and is being extended for safety analyses of Sodium cooled Fast Reactors (SFRs) at the Helmholtz-Zentrum Dresden-Rossendorf. This thesis focuses on the first stage of the development pro ...
EPFL2019