Neutronic and fuel cycle performance of VVER-1000 for dual cooled annular fuel with coated burnable poison
The feasibility of the dual cooled annular fuel rod with coated burnable absorber in the
hexagonal assembly of the VVER-1000 reactor was studied. The models consist of a 4.5 …
hexagonal assembly of the VVER-1000 reactor was studied. The models consist of a 4.5 …
Assessment of an integral small modular reactor during rod ejection accident by using DRAGON/PARCS codes
R Akbari-Jeyhouni, DR Ochbelagh, A Gharib - Progress in Nuclear Energy, 2018 - Elsevier
Small modular reactors (SMRs) have benefits like lower initial costs and investment risks,
higher safety features, longer refueling cycle and also beside than electricity production …
higher safety features, longer refueling cycle and also beside than electricity production …
Simulation of the dynamic behavior of a rectangular single-phase natural circulation vertical loop with asymmetric heater
M Hashemi-Tilehnoee, N Sahebi, AS Dogonchi… - International Journal of …, 2019 - Elsevier
The critical capability of Natural circulation flow for the removing heat has been
demonstrated and are widely used in the industry particularly received notable attention to …
demonstrated and are widely used in the industry particularly received notable attention to …
Forced reflood modeling in a 2× 2 rod bundle with a 90% partially blocked region
M Hashemi-Tilehnoee, S Tashakor, SM Seyyedi… - Annals of Nuclear …, 2019 - Elsevier
Reflooding is a complicated thermal-hydraulic process in a loss of coolant accident (LOCA)
related to the nuclear reactor safety issues. Due to the physical nature of multi-scale behind …
related to the nuclear reactor safety issues. Due to the physical nature of multi-scale behind …
Safety analysis of LBLOCA in BDBA scenarios for the Bushehr's VVER-1000 nuclear power plant
A Pirouzmand, A Ghasemi, F Faghihi - Progress in Nuclear Energy, 2016 - Elsevier
This paper presents the results of thermal-hydraulic calculations of a large break loss of
coolant accident (LBLOCA) analysis for a VVER-1000/V446 unit at Bushehr nuclear power …
coolant accident (LBLOCA) analysis for a VVER-1000/V446 unit at Bushehr nuclear power …
Thermal-hydraulic modeling for deterministic safety analysis of portable equipment application in the VVER-1000 nuclear reactor during loss of ultimate heat sink …
Z Tabadar, GR Ansarifar, A Pirouzmand - Annals of Nuclear Energy, 2019 - Elsevier
Thermal-hydraulic model is an important tool in deterministic safety analysis of the Nuclear
Power Plant (NPP) which would confirm the adequacy and efficiency of provisions in the …
Power Plant (NPP) which would confirm the adequacy and efficiency of provisions in the …
Probabilistic safety assessment of portable equipment applied in VVER-1000/V446 nuclear reactor during loss of ultimate heat sink accident for stress test program …
Z Tabadar, GR Ansarifar, A Pirouzmand - Progress in nuclear energy, 2019 - Elsevier
Abstract After the Fukushima Daiichi nuclear accident, all EU nuclear power plants became
subject to safety assessments as stress test programs. The objective was to check and …
subject to safety assessments as stress test programs. The objective was to check and …
[HTML][HTML] Thermal-hydraulic analysis of VVER-1000 residual heat removal system using RELAP5 code, an evaluation at the boundary of reactor repair mode
Z Tabadar, S Aghajanpour, M Jabbari… - Alexandria engineering …, 2018 - Elsevier
Removing the residual heat from a nuclear reactor is an important safety aspect of thermal
hydraulic analysis. In this study, a typical VVER-1000 reactor residual heat removal system …
hydraulic analysis. In this study, a typical VVER-1000 reactor residual heat removal system …
Research on flow resistance characteristics of reactor coolant pump under large break LOCA at inlet
C An, H Li, Y Chen, R Zhu, Q Fu, X Wang - Nuclear Engineering and …, 2022 - Elsevier
In the event of a large break loss-of-coolant accident (LBLOCA) at the inlet of the nuclear
Reactor Coolant Pump (RCP), the RCP is likely to enter an extreme working condition of the …
Reactor Coolant Pump (RCP), the RCP is likely to enter an extreme working condition of the …
Advanced method for neutronics and system code coupling RELAP, PARCS, and MATLAB for instrumentation and control assessment
The operation of current nuclear power plants (NPP) and the deployment of advanced
nuclear reactors rely on digital instrumentation and control (I&C) and information technology …
nuclear reactors rely on digital instrumentation and control (I&C) and information technology …