Search
Search Results
-
Effect of reprocessing on neutrons of a molten chloride salt fast reactor
Due to their unique features, such as the inherent safety, simplified fuel cycle, and continuous on-line reprocessing, molten salt reactors (MSRs)...
-
Group Constants Generation Based on NECP-MCX Monte Carlo Code
The reliability of few-group constants generated by lattice physics calculation is significant for the accuracy of the conventional two-step method...
-
Combined Neutronics Calculation of the Radiation Protection for a Nuclear Reactor with Heavy Liquid-Metal Coolant
The problem of calculating a model of the radiation protection of a monoblock reactor, having a fast neutron spectrum and cooled by a eutectic...
-
Virtual-Digital Model of NFC Closure for a Fast Reactor
Project Proryv (Breakthrough) is leading an effort to develop fast reactors with mixed uranium-plutonium nitride fuel as well as the installations...
-
On the transient models of the VITAS code: applications to the C5G7-TD pin-resolved benchmark problem
This article describes the transient models of the neutronics code VITAS that are used for solving time-dependent, pin-resolved neutron transport...
-
OKBM Afrikantov Research and Testing Complex: From Creation to the Present Day
Testing and experimental substantiation are a significant and integral part at all phases of the life cycle of reactor equipment. The Research and...
-
Introduction
In today’s industries (e.g. nuclear power industry, aerospace industry), there are various systems operating in a wide range of regimes. Since it is...
-
Analysis on the Global Competition of Digital Reactor from the Perspective of Patents
In recent years, with the rapid development of high-precision reactor simulation, big data applications and high-speed data transmission...
-
Direct Drive Laser Fusion Facility and Pilot Plant
Direct-drive laser inertial fusion is a potential producer of baseline power that has increased credibility following the achievement at the National...
-
Summary, Conclusion and Outlook
To quantify the output uncertainty, the concept of tolerance limits was applied. This technique reduced the number of runs to 93, which was...
-
The IFMIF-DONES Diagnostics and Control Systems: Current Design Status, Integration Issues and Future Perspectives Embedding Artificial Intelligence Tools
As an integral part of the European strategy for advancing fusion-generated electricity, IFMIF-DONES represents a high-intensity neutron irradiation...
-
Neutronics Calculation of Fast Reactor Using Modern Computing Systems
The possibility of using the LUCKY-A three-dimensional multiprocessor transport code as a neutronics module for the COREMELT integrated...
-
An efficient parallel algorithm of variational nodal method for heterogeneous neutron transport problems
The heterogeneous variational nodal method (HVNM) has emerged as a potential approach for solving high-fidelity neutron transport problems. However,...
-
RTM-2 Software Package for Life Cycle Modeling of Fast Reactors in Closed NFC
A complex of nuclear fuel cycle technologies based on fast reactors operating in a closed NFC is under development as part of the of the Proryv...
-
A Moose-Based Neutron Diffusion Code with Application to a LMFR Benchmark
MOOSE (Multiphysics Object-Oriented Simulation Environment) is a powerful finite element multi-physics coupling framework, whose object-oriented,...
-
Plutonium utilization in a small modular molten-salt reactor based on a batch fuel reprocessing scheme
A molten salt reactor (MSR) has outstanding features considering the application of thorium fuel, inherent safety, sustainability, and resistance to...
-
A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor
Molten salt reactors (MSRs) have gained worldwide interest in recent years due to their appealing safety and resource utilisation characteristics....
-
Introduction
At the Kyoto University Critical Assembly (KUCA), the accelerator-driven system (ADS) is composed of a solid-moderated and solid-reflected core...
-
Numerical Simulation of the Measurements Performed during the Physical Startup Tests of Unit 1 of Novovoronezh II Nuclear Power Plant
The article presents the results of numerical simulation of the experiments conducted during the physical start-up of unit 1 of the Novovoronezh II...