Assessment of the research reactors in opposition to severe accidents

R Gharari, R Ahangari, H Esmaili… - Nuclear Engineering and …, 2023 - Elsevier
Abstract Occurrence of the Severe Accidents (SAs) in Research Reactors (RRs) according to
the safety standards of the International Atomic Energy Agency (IAEA), despite the low …

[HTML][HTML] Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor

AS Ványi, M Hursin, S Czifrus - Annals of Nuclear Energy, 2023 - Elsevier
This paper presents nuclear reactor transient measurements with thermal feedback and
corresponding coupled neutronic–thermohydraulic simulations performed for the natural …

Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor

SED El-Morshedy, M Moawed, MA Abdelrahman… - Kerntechnik, 2024 - degruyter.com
A thermal-hydraulic model has been developed by RELAP5 code to simulate the thermal-
hydraulic behavior of a WWR-S research reactor under loss of flow accident (LOFA). The …