Results 1 to 10 of about 157 (110)
Verification of MPACT for the APR1400 Benchmark [PDF]
This paper describes benchmark calculations for the APR1400 nuclear reactor performed using the high-fidelity deterministic whole-core simulator MPACT compared to reference solutions generated by the Monte Carlo code McCARD.
Sooyoung Choi +2 more
exaly +4 more sources
Earthquake response of a core shroud for APR1400
The core shroud is one of the most important internal components of the reactor vessel internals because it meets the neutron fluence directly emitted by the nuclear fuel.
Myung Jo Jhung +2 more
doaj +2 more sources
We performed a hydrogen combustion analysis in the Advanced Power Reactor 1400 MWe (APR1400) containment during a severe accident initiated by a small break loss of coolant accident (SBLOCA) which occurred at a lower part of the cold leg using a multi ...
Seong-Wan Hong
exaly +3 more sources
Physics study for high-performance and very-low-boron APR1400 core with 24-month cycle length
A 24-month Advanced Power Reactor 1400 (APR1400) core with a very-low-boron (VLB) concentration has been investigated for an inherently safe and high-performance PWR in this work.
Xuan Ha Nguyen, Yonghee Kim
exaly +3 more sources
Nuclear heat storage and recovery for the APR1400
Abstract Detailed here is the proposed design of the tertiary side of a Thermal Energy Storage (TES) System to be interfaced with the steam cycle of a Light Water Reactor (LWR) plant. This study extends the understanding provided by many previous investigations (i.e., beyond thermodynamic considerations) by specifically addressing real world ...
Kafilat Funmilola Amuda, Robert M. Field
exaly +2 more sources
Extended Station Blackout Coping Capabilities of APR1400 [PDF]
The Fukushima Dai-ichi nuclear power plant accident shows that an extreme natural disaster can prevent the proper restoration of electric power for several days, so-called extended SBO.
Sang-Won Lee +4 more
doaj +2 more sources
Korea Atomic Energy Research Institute (KAERI) established a multi-dimensional hydrogen analysis system to evaluate hydrogen release, distribution, and combustion in the containment of a Nuclear Power Plant (NPP), using MAAP, GASFLOW, and COM3D.
Hyung Seok Kang
exaly +3 more sources
Extended station blackout analyses of an APR1400 with MARS-KS [PDF]
The Fukushima Daiichi nuclear power plant accident shows that natural disasters such as earthquakes and the subsequent tsunamis can cause station blackout for several days.
Kim Woongbae +3 more
doaj +3 more sources
Analysis of LBLOCA of APR1400 with 3D RPV model using TRACE
It is very difficult to capture the multi-dimensional phenomena such as asymmetric flow and temperature distributions with the one-dimensional (1D) model, obviously, due to its inherent limitation.
Yunseok Lee +3 more
doaj +2 more sources
Modeling corium pool stratification and focusing effect in APR1400 using a multiphase CFD framework [PDF]
Accurately predicting molten corium behavior is critical for assessing severe accident scenarios in nuclear reactors, particularly under In-Vessel Corium Retention with Reactor Vessel External Cooling (IVCR-RVEC) strategies.
Kamran Mahboob +2 more
doaj +2 more sources

