[HTML][HTML] A review of existing SuperCritical Water reactor concepts, safety analysis codes and safety characteristics
P Wu, Y Ren, M Feng, J Shan, Y Huang… - Progress in Nuclear …, 2022 - Elsevier
Abstract SuperCritical Water Reactor (SCWR) applies water beyond the thermodynamic
critical point as the coolant, which aims to achieve high efficiency around 45% compared to …
critical point as the coolant, which aims to achieve high efficiency around 45% compared to …
Verification of stress-intensity factor solutions by uncertainty quantification
JC Sobotka, R Craig McClung - Journal of …, 2019 - asmedigitalcollection.asme.org
This paper summarizes an emerging process to establish credibility for surrogate models
that cover multidimensional, continuous solution spaces. Various features lead to …
that cover multidimensional, continuous solution spaces. Various features lead to …
Computational models for predicting cooling tower fill performance in cross-counterflow configuration
HCR Reuter, DG Kröger - 2012 - asmedigitalcollection.asme.org
In cooling towers packed with trickle or splash fills, which have anisotropic flow resistance,
the air flow through the fill is oblique or in cross-counterflow to the water flow, particularly at …
the air flow through the fill is oblique or in cross-counterflow to the water flow, particularly at …
Development of a dynamics model for graphite-moderated channel-type molten salt reactor
L He, CG Yu, RM Ji, W Guo, Y Dai, XZ Cai - Nuclear Science and …, 2019 - Springer
A molten salt reactor (MSR) is one of the six advanced reactor concepts selected by the
generation IV international forum because of its advantages of inherent safety, and the …
generation IV international forum because of its advantages of inherent safety, and the …
Transient Modeling of Advanced High Temperature Reactor (AHTR) in RELAP5/SCDAPSIM/MOD 4.0
The Advanced High Temperature Reactor (AHTR) is a fluoride-salt-cooled high-temperature
reactor (FHR) design concept that is currently being developed at Oak Ridge National …
reactor (FHR) design concept that is currently being developed at Oak Ridge National …
Modeling of DRACS test facility and Advanced High Temperature Reactor (AHTR) using RELAP5/SCDAPSIM/MOD 4.0
Lin, HC; Zhang, S.; Lv, Q.; Shi, S.; Sun, X.; Yoder, G.; Perez, M.; Allison, CM, E-mail:
hsunlin@ umich. edu, E-mail: shengzh@ umich. edu, E-mail: qlv@ anl. gov, E-mail …
hsunlin@ umich. edu, E-mail: shengzh@ umich. edu, E-mail: qlv@ anl. gov, E-mail …
Code validation of a scaled-down DRACS model in RELAP5/SCDAPSIM/MOD 4.0
Abstract Direct Reactor Auxiliary Cooling System (DRACS) is a passive safety system
proposed for Fluoride-salt-cooled High-temperature Reactors (FHRs). Benchmark study of …
proposed for Fluoride-salt-cooled High-temperature Reactors (FHRs). Benchmark study of …
Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations
F Salaun, DR Novog - Journal of Nuclear …, 2018 - asmedigitalcollection.asme.org
The Canadian supercritical water-cooled reactor (SCWR) design is part of Canada's
Generation IV reactor development program. The reactor uses batch fueling, light water …
Generation IV reactor development program. The reactor uses batch fueling, light water …
Development and analysis of a novel scaling methodology for stability appraisal of supercritical flow channels
The prospect of achieving higher thermal efficiency with simpler plant design, projects
Supercritical water reactor as a better futuristic option compared to its boiling water …
Supercritical water reactor as a better futuristic option compared to its boiling water …