Results 41 to 50 of about 110,724 (75)

Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches

Nuclear science and engineering, 2023
This work describes the research of high-fidelity multiphysics models for the MegaPower nuclear reactor, a megawatt-level heat pipe reactor. Combining the Monte Carlo neutronics model, the heat pipe analysis model, the fuel analysis model, and the ...
Junda Zhang, Tao Li, Zhirui Shen, Xiangyue Li, Jinbiao Xiong, Xiang Chai, Xiaojing Liu, Tengfei Zhang   +7 more
semanticscholar   +1 more source

A Review of Maritime Nuclear Reactor Systems

Journal of Nuclear Engineering
Marine reactors have been applied to floating nuclear power plants, naval vessels such as submarines, and civilian ships such as icebreakers. Nuclear-powered shipping is gaining increased interest because of decarbonization goals motivated by climate ...
K. Holbert
semanticscholar   +1 more source

Experimental Study of Transient Behavior of a Passive Air-Cooled Containment System Relevant to Advanced Nuclear Reactor

Nuclear science and engineering
In advanced water-cooled nuclear reactors, the passive safety systems are preferably used to achieve enhanced safety during accidental conditions. The passive containment air cooling system (PCACS) is one of the safety systems used to remove heat from ...
Yogesh R. Pawar, A. K. Nayak, A. K. Dureja, P. P. Kulkarni   +3 more
semanticscholar   +1 more source

Public-Private Partnering in Nuclear Reactor Development - Historical Review and Implications for Today

Journal of Nuclear Engineering and Radiation Science, 2023
The dominant nuclear reactor technologies that comprise the current global operating fleet were developed and deployed over a relatively short, mid-twentieth century, period spanning the 1950s and 60s.
Steven Krahn, Andrew Sowder
semanticscholar   +1 more source

Generation IV Nuclear Reactor: Coolant Materials in the Supercritical State

Nuclear science and engineering, 2023
On the basis of the generalized van der Waals equations of state, the quasispinodal and the supercritical-point parameters of the Generation IV nuclear reactor coolant materials, namely, sodium, lead and bismuth, have been determined. To improve accuracy,
A. Ramesh, R. Balasubramanian
semanticscholar   +1 more source

Mechanistic Interpretability of LoRA-Adapted Language Models for Nuclear Reactor Safety Applications

Nuclear Technology
The integration of Large Language Models (LLMs) into safety-critical domains, such as nuclear engineering, necessitates a deep understanding of their internal reasoning processes.
Yoon Pyo Lee
semanticscholar   +1 more source

Geant4 Extension for Neutronic Calculation of Nuclear Reactor Core

Nuclear Technology, 2023
The computerized simulation of the reactor core is one of the significant steps necessary for designing a nuclear power plant. So far, very suitable Monte Carlo–based codes have been developed (e.g., MCNP, TRIPOLI, KENO, OpenMC, etc.) for the neutronic ...
Hossein Hashemi-Jozani, K. Moshkbar-Bakhshayesh, S. Mohtashami, Behzad Rokhbin   +3 more
semanticscholar   +1 more source

Optimizing the Fixed Number Detector Placement for the Nuclear Reactor Core Using Reinforcement Learning

Nuclear science and engineering
Monitoring three-dimensional flux distribution in a nuclear reactor core is essential for improving safety and economics, which requires strategically placed in-core detectors.
Kai Tan, Fan Zhang
semanticscholar   +1 more source

Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface

Nuclear Technology
Heat rejection radiators of nuclear reactor power systems for space exploration and for planetary surface power are the largest component by volume and mass, depending on the radiator’s design and surface average temperature.
M. El-Genk, T. Schriener
semanticscholar   +1 more source

Enhancing Monte Carlo Workflows for Nuclear Reactor Analysis with Metamodel-Driven Modeling

Nuclear science and engineering, 2023
Monte Carlo codes are essential components of many reactor physics simulation workflows as high-fidelity continuous-energy neutron transport solvers. Among Monte Carlo radiation transport codes, MCNP is particularly notable due to its diverse simulation ...
P. Kowal, Camden E. Blake, K. Dominesey, R. Lefebvre, F. Brown, W. Ji   +5 more
semanticscholar   +1 more source