In MTR research reactors, heat removal is, safely performed by forced convection during
normal operation and by natural convection after reactor shutdown for residual decay heat …

RELAP5 code was developed at the Idaho National Environmental and Engineering
Laboratory and it is widely used for thermal hydraulic studies of commercial nuclear power …

This work describes the most complete and up-to-date thermal-hydraulics CFD model for
studying the natural circulation regime within the entire TRIGA Mark II reactor at the …

The present work is developed within the frame of the IAEA Coordinated Research Program
1496,“Innovative methods in research reactor analysis: Benchmark against experimental …

The natural convection and forced cooling experiments were conducted to confirm the
cooling capability in the IPR-R1 TRIGA® nuclear research reactor. Temperature …

This work presents the thermal hydraulic simulation of the Brazilian multipurpose reactor
(RMB) using a RELAP5/MOD3. 3 model. Beyond steady state calculations, three transient …

В данной работе рассматривается категория слов «ложные друзья переводчика».
Проанализированы трудности перевода данной категории слов и словосочетаний с …

Cases of core coolant flow blockage transient have been simulated and analysed for the
TRIGA IPR‐R1 research reactor using the RELAP5‐MOD3. 3 code. The transients are …

Deep pool nuclear reactor (DPNR) is a novel pool-type reactor, which has shown great
potential in seawater desalination and district heating. In this paper, the thermal–hydraulic …

Any events presumed to risk the safety of a nuclear reactor should be analyzed. In a
research reactor, the applicability of best estimate thermal-hydraulic codes has been …