NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 2021.

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.

Date: 14-17 November 2023

Dates: 19-22 November 2024
Minimum enrollment: 12 participants
Maximum enrollment: 20 participants
Registration fee: 750 EUR
Registration deadline: 27 September 2024
Contact: hedvig.nahon@oecd-nea.org wit...

Dates: 7-11 April 2025
Time: 17:00-21:00 (CEST, Paris time)/10:00-14:00 (CDT USA/Mexico)/12:00-16:00 (UTC-3, Argentina)
Minimum enrollment: 12 participants
Maximum enrollment: 15 participants
Registratio...

Dates:  27-31 May 2024
Time: 17:00-21:00 (CEST, Paris time)/10:00-14:00 (CDT USA/Mexico)/12:00-16:00 (UTC-3, Argentina)
Minimum enrollment: 12 participants
Maximum enrollment: 15 participants
Registration...

Twelfth Workshop Proceedings, Batavia, Illinois, United States, 28-30 April 2014

Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.

A sodium-cooled fast reactor (SFR) is a fast neutron reactor that uses molten sodium metal as a coolant. Sodium-cooled Fast Reactors (SFRs) are the most promising type of reactors to achieve Generati...

Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...

The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.

In this benchmark exercise the goal is to test the current state-of-the-art two-dimensional methods of calculating neutron flux to reactor components against the measured data of the VENUS-1 critical...

Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...