Results 31 to 40 of about 19,519 (264)

An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor [PDF]

EPJ Web of Conferences, 2019
The PETALE experimental programme in the CROCUS reactor at EPFL intends to contribute to the validation and improvement of neutron nuclear data in the MeV energy range for stainless steel, particularly in the prospect of heavy reflector elements of ...
Lamirand Vincent, Laureau Axel, Rochman Dimitri, Perret Gregory, Gruel Adrien, Leconte Pierre, Blaise Patrick, Pautz Andreas   +7 more
doaj   +1 more source

A Lab on a Chip Experiment for Upscaling Diffusivity of Evolving Porous Media

Energies, 2022
Reactive transport modelling is a powerful tool to assess subsurface evolution in various energy-related applications. Upscaling, i.e., accounting for pore scale heterogeneities into larger scale analyses, remains one of the biggest challenges of ...
Jenna Poonoosamy, Renchao Lu, Mara Iris Lönartz, Guido Deissmann, Dirk Bosbach, Yuankai Yang   +5 more
doaj   +1 more source

Computational Fluid Dynamics Modeling of Steam Condensation on Nuclear Containment Wall Surfaces Based on Semiempirical Generalized Correlations

Science and Technology of Nuclear Installations, 2012
In water-cooled nuclear power reactors, significant quantities of steam and hydrogen could be produced within the primary containment following the postulated design basis accidents (DBA) or beyond design basis accidents (BDBA).
Pavan K. Sharma, B. Gera, R. K. Singh, K. K. Vaze   +3 more
doaj   +1 more source

Amyloid adhesin production in activated sludge is enhanced in lab-scale sequencing batch reactors: Feeding regime impacts microbial community and amyloid distribution

Water Research X, 2022
Amyloid adhesins are β-sheet-rich extracellular proteins thought to contribute to bioflocculation. They are present in activated sludge to varying extent. However, it remains unclear which operational conditions promote their production. To this end, the
An-Sofie Christiaens, Manon Van Steenkiste, Koen Rummens, Ilse Smets   +3 more
doaj   +1 more source

Generalized Reich-Moore R-matrix approximation

EPJ Web of Conferences, 2017
A conventional Reich-Moore approximation (RMA) of R-matrix is generalized into a manifestly unitary form by introducing a set of resonant capture channels treated explicitly in a generalized, reduced R-matrix.
Arbanas Goran, Sobes Vladimir, Holcomb Andrew, Ducru Pablo, Pigni Marco, Wiarda Dorothea   +5 more
doaj   +1 more source

An Experimental Analysis on Nusselt Number of Natural Circulation Flow in Transient Condition Based on the Height Differences between Heater and Cooler

Atom Indonesia, 2018
A better understanding on the phenomenon of natural circulation flow for cooling systems is necessary prior to improving the safety of nuclear power plant, not only in normal operation but also in accident conditions.
M. Juarsa, J.P. Witoko, G Giarno, D. Haryanto, J.H. Purba   +4 more
doaj   +1 more source

STUDY ON MCNP6 MODEL IN THE CALCULATION OF KINETIC PARAMETERS FOR PEBBLE BED REACTOR

Acta Polytechnica, 2020
When conducting a nuclear reactor transient analysis, the most important parameter, called the kinetic parameter, is required. The calculation of kinetic parameters can be conducted using several methods.
Zuhair, Suwoto, Topan Setiadipura, Zaki Su'ud   +3 more
doaj   +1 more source

Microstructural Evolution and Vacancy Defect Formation in Mn–Mo–Ni RPV Steel Under Low Cycle Fatigue: Insights From EBSD and PALS

Advanced Engineering Materials, EarlyView.
Low‐cycle fatigue damage in Mn–Mo–Ni reactor pressure vessel steel is examined using a combined electron backscatter diffraction and positron annihilation lifetime spectroscopy approach. The study correlates texture evolution, dislocation substructure development, and vacancy‐type defect formation across uniform, necked, and fracture regions, providing
Apu Sarkar, Dhanadeep Dutta, G. Bharat Reddy   +2 more
wiley   +1 more source

Approximate model for evaluation of thermal-hydraulic transients associated with rapid power increase in research nuclear reactor [PDF]

Nuclear Technology and Radiation Protection, 2020
A simple model, for the estimation of changes in the nuclear fuel element cladding temperature as well as the conditions of the formation of the onset of nucleate boiling, is proposed.
Lipka Maciej, Madejowski Gawel, Prokopowicz Rafal, Pytelt Krzysztof   +3 more
doaj   +1 more source

Electrical Conductivities of Conductors, Semiconductors, and Their Mixtures at Elevated Temperatures

Advanced Engineering Materials, EarlyView.
This article presents a comprehensive review of temperature‐dependent electrical conductivity data for multiple material classes at elevated temperatures, highlighting a persistent conductivity gap between metals and semiconductors in the range of 102$\left(10\right)^{2}$– 107$\left(10\right)^{7}$ S/m. Metal–ceramic irregular metamaterials are proposed
Valentina Torres Nieto, Marcia A. Cooper
wiley   +1 more source