M2LFR-1000 is a medium-power modular lead-cooled fast reactor, developed by University of Science and Technology of China (USTC), aiming at achieving a reactor design fulfilling the Gen IV nuclear system requirements and meanwhile emphasizing the optimum safety and economics. In order to evaluate the safety performance of M2LFR-1000 reactor core, three typical transients are selected from initiating events, which are unprotected transient overpower (UTOP), unprotected loss of offsite power (ULOHS+ULOF) and increase of feedwater flowrate with primary pumps trip (IFW+PLOF). These three transients presented and discussed in this paper are performed with the code Analysis of THermal-hydraulics of LEaks and Transients (ATHLET), which is develope...
The object of research is the emergency operation modes of the WWER-1000 nuclear installation elemen...
LOFA is one of the most important PIE in nuclear reactors. For the pool-type research reactor, the s...
In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is c...
This report presents results of transient analyses performed for a pre-conceptual design of a Molten...
[[abstract]]Due to the potential threat of reactor coolant system (RCS) overpressurization, loss-of-...
The LEADER project aims at the development to a conceptual level of a Lead Fast Reactor Industrial s...
This paper describes the code capability related to the safety requirements in nuclear plants. The ...
Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of...
Small modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast react...
DEVELOPMENT OF THREE DIMENSIONAL ACCIDENT ANALYSIS CODE FOR Pb-Bi COOLED TANK TYPE FAST REACTORS. So...
Unprotected loss of flow (ULOF) analysis of metal (U-Pu-6% Zr) fuelled 500 MWe and 1000 MWe pool typ...
This paper summarizes the approach to safety for the LFR systems, developed on the basis of the reco...
AbstractKorea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast re...
The European Facility for Industrial Transmutation (EFIT) is aimed at demonstrating the feasibility ...
Safety analysis of a PWR fuelled with ATF (Accident-Tolerant Fuel) has been performed at LB-LOCA con...
The object of research is the emergency operation modes of the WWER-1000 nuclear installation elemen...
LOFA is one of the most important PIE in nuclear reactors. For the pool-type research reactor, the s...
In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is c...
This report presents results of transient analyses performed for a pre-conceptual design of a Molten...
[[abstract]]Due to the potential threat of reactor coolant system (RCS) overpressurization, loss-of-...
The LEADER project aims at the development to a conceptual level of a Lead Fast Reactor Industrial s...
This paper describes the code capability related to the safety requirements in nuclear plants. The ...
Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of...
Small modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast react...
DEVELOPMENT OF THREE DIMENSIONAL ACCIDENT ANALYSIS CODE FOR Pb-Bi COOLED TANK TYPE FAST REACTORS. So...
Unprotected loss of flow (ULOF) analysis of metal (U-Pu-6% Zr) fuelled 500 MWe and 1000 MWe pool typ...
This paper summarizes the approach to safety for the LFR systems, developed on the basis of the reco...
AbstractKorea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast re...
The European Facility for Industrial Transmutation (EFIT) is aimed at demonstrating the feasibility ...
Safety analysis of a PWR fuelled with ATF (Accident-Tolerant Fuel) has been performed at LB-LOCA con...
The object of research is the emergency operation modes of the WWER-1000 nuclear installation elemen...
LOFA is one of the most important PIE in nuclear reactors. For the pool-type research reactor, the s...
In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is c...