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Cladding Failure Modelling for Lead-Based Fast Reactors: A Review and Prospects.
Publication Type: Academic Journal
Source(s): Metals (2075-4701). Sep2023, Vol. 13 Issue 9, p1524. 24p.
Abstract: Lead-cooled fast reactors (LFRs) are considered one of the most promising technologies to meet the requirements introduced for advanced nuclear systems. LFRs have higher neutron doses, higher temperatures, higher burnup and an extremely corrosive envir...
Preliminary Design and Study of a Small Modular Chlorine Salt Fast Reactor Cooled by Supercritical Carbon Dioxide.
Publication Type: Academic Journal
Source(s): Energies (19961073). Jul2023, Vol. 16 Issue 13, p4862. 18p.
Abstract: Small modular reactors with power below 300 MW have the advantages of small specific mass, long lifetime, and flexible power supply, and they are suitable for providing power support for small and medium-sized towns with small populations and remote ar...
Fast Calibration Method for Base Coordinates of the Dual-Robot Based on Three-Point Measurement Calibration Method.
Publication Type: Academic Journal
Source(s): Applied Sciences (2076-3417). Aug2023, Vol. 13 Issue 15, p8799. 16p.
Abstract: Multi-robot systems can perform more complex tasks with high precision and large loads than single-robot systems. The calibration of the base coordinate system is the basis and premise to ensure the collaborative operation between the dual-robot. In th...
Ambient Melting Behavior of Stoichiometric Uranium-Plutonium Mixed Oxide Fuel †.
Publication Type: Academic Journal
Source(s): Applied Sciences (2076-3417). May2023, Vol. 13 Issue 10, p6303. 16p.
Abstract: Mixed oxides of uranium and plutonium (MOX) are currently considered as a reference fuel for the new generation of fast breeder reactors such as ASTRID. The key factor determining the performance and safety of a fuel such as MOX is its operational limi...
Characteristics and Mechanisms of Debris Bed Formation Behavior in Severe Accidents of Sodium-Cooled Fast Reactors: Experimental and Modeling Studies.
Publication Type: Academic Journal
Source(s): Applied Sciences (2076-3417). Jun2023, Vol. 13 Issue 11, p6329. 35p.
Abstract: A Sodium-cooled Fast Reactor (SFR) is one of the optimized candidates in Generation IV nuclear reactor systems, but safety is an essential issue for SFR development and application. Most knowledge was accumulated through SFR safety investigations, espe...
Comparative Study on the Neutronic Performance of Thermal and Fast Molten Salt Reactors under Once-Through Fuel Cycle.
Publication Type: Academic Journal
Source(s): International Journal of Energy Research. 3/22/2023, Vol. 2023, p1-18. 18p.
Abstract: Once-through molten salt reactors have the advantages of easy availability of fuel, nuclear nonproliferation, and low technical difficulty. It is expected to be the earliest commercial molten salt reactor fuel cycle mode. The current research on the ne...
THEFIS Test Simulation to Validate a Freezing Model of ASTERIA-SFR Core Disruptive Accident Analysis Code.
Publication Type: Academic Journal
Source(s): Journal of Nuclear Engineering (JNE). Mar2023, Vol. 4 Issue 1, p154-164. 11p.
Abstract: The mechanical consequences of core disruptive accidents (CDAs) are a major safety concern in sodium-cooled fast reactors. Once core disruption occurs, liquefied core materials rapidly disperse vertically and radially. The dispersed materials penetrate...
Demonstration of Pronghorn's Subchannel Code Modeling of Liquid-Metal Reactors and Validation in Normal Operation Conditions and Blockage Scenarios.
Publication Type: Academic Journal
Source(s): Energies (19961073). Mar2023, Vol. 16 Issue 6, p2592. 31p.
Abstract: Pronghorn-SC is a subchannel code within the Multiphysics Object-Oriented Simulation Environment (MOOSE). Initially designed to simulate flows in water-cooled, square lattice, subchannel assemblies, Pronghorn-SC has been expanded to simulate liquid-met...
A Design and Optimization Methodology for Liquid Metal Fast Reactors.
Publication Type: Academic Journal
Source(s): International Journal of Energy Research. 3/8/2023, Vol. 2023, p1-15. 15p.
Abstract: A liquid metal fast reactor (LMFR) design and optimization methodology (DOM) has been developed. The methodology effectively explores a search space by initially sampling the search space, excluding invalid design samples prior to performing expensive ...
Tailoring Microstructure of Austenitic Stainless Steel with Improved Performance for Generation-IV Fast Reactor Application: A Review.
Publication Type: Academic Journal
Source(s): Crystals (2073-4352). Feb2023, Vol. 13 Issue 2, p268. 18p.
Abstract: Austenitic stainless steels are selected as candidate materials for in-core and out-of-core components of Generation-IV fast reactors due to their excellent operating experience in light-water reactors over several decades. However, the performance of ...