OC Ondwasi, N Ihn - Nuclear Engineering and Design, 2024 - Elsevier
Reactor internals are installed in the reactor vessel and are subsequently removed during periodic inspections. To facilitate this process, a gap is maintained between the outlet of the …
The bypass flow in a prismatic very high temperature reactor (VHTR) core is an important parameter in reactor design, which has not been well assessed in publications to date. To …
JH Lee, HK Cho, GC Park - Nuclear Engineering and Design, 2016 - Elsevier
The core of the very high temperature reactor (VHTR) PMR200 (a prismatic modular reactor rated at 200 MW of thermal power) consists of hexagonal prismatic fuel blocks and reflector …
Modeling and simulation tools play an important role in the design and licensing of reactors, but models alone are insufficient for licensing reactors. As advanced reactors approach …
CS Kim, BH Park, ES Kim, MH Kim - Nuclear Technology, 2020 - Taylor & Francis
Abstract The Korea Atomic Energy Research Institute (KAERI) has developed the Core Reliable Optimization and thermofluid Network Analysis (CORONA) code for core …
C Chen, J Yan, Y Xi, Y Zhang… - International …, 2022 - asmedigitalcollection.asme.org
Fuel assembly bypass flow is the coolant flow through the guide thimble and the instrument. The fuel assembly bypass flow should be limited to ensure that there is sufficient coolant in …
AW Parker, BL Smith - Journal of Verification …, 2022 - asmedigitalcollection.asme.org
This paper documents a computational fluid dynamics (CFD) validation benchmark experiment for flow through three parallel, heated channels from one plenum to another. The …
CS Kim, BH Park, NI Tak, ES Kim - … of the Korean Nuclear Society Autumn …, 2018 - kns.org
Korea Atomic Energy Research Institute (KAERI) has developed CORONA (Core Reliable Optimization and thermo-fluid Network Analysis) code for thermofluid analysis of prismatic …