An investigation for the fuel temperature of the Tehran Research Reactor during a complete loss of coolant accident

E Boustani, S Khakshournia - Progress in Nuclear Energy, 2020 - Elsevier
Safety in a nuclear research reactor such as the Tehran Research Reactor (TRR) is a
significant concern mainly after the Fukushima nuclear accident and satisfied by a …

[HTML][HTML] Simulation and transient analyses of a complete passive heat removal system in a downward cooling pool-type material testing reactor against a complete …

A Hedayat - Nuclear Engineering and Technology, 2017 - Elsevier
In this paper, a complete station blackout (SBO) or complete loss of electrical power supplies
is simulated and analyzed in a downward cooling 5-MW pool-type Material Testing Reactor …

Derivation of the source term, dose results and associated radiological consequences for the Greek Research Reactor–1

C Pappas, A Ikonomopoulos, A Sfetsos… - … Engineering and Design, 2014 - Elsevier
The estimated source term, dose results and radiological consequences of selected
accident sequences in the Greek Research Reactor–1 are presented and discussed. A …

Consideration on hydrogen explosion scenario in APR 1400 containment building during small breakup loss of coolant accident

K Park, CL Khor - Nuclear engineering and design, 2015 - Elsevier
This paper describes the analytical result of the potential risk of hydrogen gas up to 15 h
after the failure takes place. The major cause of the disaster occurred in Fukushima Daiichi …

Natural convection cooling characteristics in a plate type fuel assembly of Kyoto University Research Reactor during loss of coolant accident

D Ito, Y Saito - Annals of Nuclear Energy, 2016 - Elsevier
The transient behavior of nuclear fuel during loss of coolant accident (LOCA) must be
evaluated not only for power reactors but also for research reactors. Kyoto University …

Transient analysis of the Brazilian Multipurpose Reactor by the coupled neutronics and thermal hydraulics code NTHC1

ERGD Ribeiro, DAP Palma, E Henrice Jr, J Su - Annals of Nuclear Energy, 2020 - Elsevier
Dynamical behavior of the Brazilian Multipurpose Reactor (RMB) is investigated by using
the coupled neutronics and thermal hydraulics code NTHC1, which consists of the neutron …

Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3. 2 code

A Hedayat - Kerntechnik, 2019 - degruyter.com
In this paper, a 5 MW open pool type research reactor is simulated and analyzed to check
and pass a complete and practical safety assessment against various LOFA scenarios …

Validation of the RELAP5 Code for Loss of Heat Sink Events in the McMaster Nuclear Reactor

K Ruiz - 2024 - macsphere.mcmaster.ca
Open pool research reactors play a crucial role in industry, medicine, scientific research and
training. Ensuring its safety involves the use of widely accepted computer codes, such as …

Optimized flux trap dimensions in a research reactor core

P Savva, S Chatzidakis, M Varvayanni… - Nuclear …, 2014 - Taylor & Francis
Research reactors are used for many applications: material testing; radioisotope production;
beam-line applications for material research; nuclear transmutation do**; neutron …

[HTML][HTML] Reactor dynamic simulation to analyze possible scenarios after a spurious opening of the safety flapper valve of TRR during the normal operation regarding …

A Hedayat - International Journal of Advanced Nuclear Reactor …, 2021 - Elsevier
LOFA is one of the most important PIE in nuclear reactors. For the pool-type research
reactor, the safety flapper valve is usually located below the reactor core and have a very …