As a new type of reactor fuel assembly, helical-cruciform fuel (HCF) assembly has some advantages. The cruciform section shortens heat conduction path and the twist structure strengthens inter-channel mixing, which can upgrade core power density with enough safety margin. The periodic self-supporting structure fixes the assembly instead of spacer grid to reduce flow resistance. However, because of the small contact area at self-supporting structure the stress concentration is prone in contact position, which has a negative effect on the integrity of cladding. To solve this problem, the thermal-fluid-force coupling characteristics of typical HCF assembly were studied in this research. The flow and heat transfer of coolant were simulated by A...
The thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity sim...
An innovative core with an increased energy resource was used when designing RITM-200 reactor unit. ...
International audienceThe Sodium-cooled Fast Reactor (SFR) fuel sub-assembly irradiation leads to a ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
In nuclear reactors, the research of conjugated heat transfer between the fuel and coolant in the fu...
International audienceThe pressure and velocity distribution within and between full cross-section f...
Annular fuel element is a new type of fuel element proposed by Massachusetts Institute of Technology...
This paper proposes the new pattern of wire wrap spacer, called U-pattern to enhance coolant mixing ...
Dual cooled annular fuel is a novel fuel design, which has the potential to improve the reactor powe...
One of the safety concerns in reactor operation is the temperature of the fuel elements, which are c...
This paper looks into detailed investigation of thermal-hydraulic characteristics of the flow field ...
The paper presents a HPC calculation of a conjugate heat transfer simulation in fuel assembly as tho...
Thermal-hydraulic analysis was conducted of a 7-pin fuel bundle by using CFD. Currently, wire-wrappe...
This paper presents the findings from a numerical simulation of the flow in 37-rod fuel assembly mod...
AbstractThe fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles s...
The thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity sim...
An innovative core with an increased energy resource was used when designing RITM-200 reactor unit. ...
International audienceThe Sodium-cooled Fast Reactor (SFR) fuel sub-assembly irradiation leads to a ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
In nuclear reactors, the research of conjugated heat transfer between the fuel and coolant in the fu...
International audienceThe pressure and velocity distribution within and between full cross-section f...
Annular fuel element is a new type of fuel element proposed by Massachusetts Institute of Technology...
This paper proposes the new pattern of wire wrap spacer, called U-pattern to enhance coolant mixing ...
Dual cooled annular fuel is a novel fuel design, which has the potential to improve the reactor powe...
One of the safety concerns in reactor operation is the temperature of the fuel elements, which are c...
This paper looks into detailed investigation of thermal-hydraulic characteristics of the flow field ...
The paper presents a HPC calculation of a conjugate heat transfer simulation in fuel assembly as tho...
Thermal-hydraulic analysis was conducted of a 7-pin fuel bundle by using CFD. Currently, wire-wrappe...
This paper presents the findings from a numerical simulation of the flow in 37-rod fuel assembly mod...
AbstractThe fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles s...
The thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity sim...
An innovative core with an increased energy resource was used when designing RITM-200 reactor unit. ...
International audienceThe Sodium-cooled Fast Reactor (SFR) fuel sub-assembly irradiation leads to a ...