期刊： NUCLEAR TECHNOLOGY, 2020; 206 (1)
The development of a model for mental workload (MWL) prediction of an operator in nuclear power plants (NPPs) is necessary but challenging. In this st......
期刊： NUCLEAR TECHNOLOGY, 2020; 206 (1)
With large-scale molecular dynamics, we investigate displacement cascades in monocrystalline silicon with regard to the effects of temperature, strain......
期刊： NUCLEAR TECHNOLOGY, 2020; 206 (3)
Since the Pd/Ag membrane has a permselectivity for hydrogen isotopes, a permeator with a Pd/Ag membrane is developed to separate tritium from inert ga......
期刊： NUCLEAR TECHNOLOGY, 2020; 206 (10)
An electromagnetic flow meter (EMFM) has been used in the main cooling loop of the fast reactor, but the large-sized magnet structure of conventional ......
期刊： NUCLEAR TECHNOLOGY, 2020; 206 (10)
Sodium combustion oxide aerosols are the main carriers of radioactive materials in a sodium-cooled fast reactor (SFR) during sodium fire accidents. Th......
期刊： NUCLEAR TECHNOLOGY, 2020; 206 (12)
Membranes have been widely used in low-level radioactive wastewater (LLRW) treatment and are under irradiation as a result of radioactive nuclides pre......
期刊： NUCLEAR TECHNOLOGY, 2020; 206 (8)
Nuclear thermal propulsion (NTP) could be an advanced technology to facilitate a new and excellent rocket engine that would at least double the perfor......
期刊： NUCLEAR TECHNOLOGY, 2020; 206 (9)
Subchannel code analysis is one of the key thermal-hydraulic approaches for nuclear reactor design and safety analysis. At present, subchannel codes a......
期刊： NUCLEAR TECHNOLOGY, 2019; 205 (1-2)
The CTF code is a subchannel thermal-hydraulic code developed based on the COBRA-TF code. In this work, the CTF code is used to predict the single-and......
期刊： NUCLEAR TECHNOLOGY, 2019; 205 (1-2)
In most subchannel analysis codes, spacer grids are simulated using an effective loss coefficient that can account only for the spacer grid's mean axi......
期刊： NUCLEAR TECHNOLOGY, 2019; 205 (1-2)
Mixing vanes attached to a space grid play an important role in heat transfer enhancement, thus increasing critical heat flux. Subchannel analysis and......
期刊： NUCLEAR TECHNOLOGY, 2019; 205 (1-2)
Bottom reflooding is the third phase when a large-break loss-of-coolant accident occurs. Due to the complexity and importance, especially in a distinc......
期刊： NUCLEAR TECHNOLOGY, 2019; 205 (1-2)
The gas-liquid separator is a key component in the gas removal system of the Thorium Molten Salt Reactor. Phase separation is driven by a swirling flo......
期刊： NUCLEAR TECHNOLOGY, 2019; 205 (1-2)
The Risk Informed Safety Margin Characterization methodology combines traditional probabilistic safety assessment (PSA) and the best-estimate plus unc......
期刊： NUCLEAR TECHNOLOGY, 2019; 205 (1-2)
The Venturi-type bubble generator proposed by Oak Ridge National Laboratory is used to produce micro-sized bubbles. In this paper, a numerical simulat......
