专题：Graphite, nuclear technology, radiation studies

This cluster of papers focuses on the characterization, behavior, and properties of nuclear graphite materials used in high temperature gas-cooled reactors. It covers topics such as oxidation behavior, microstructural characterization, irradiation damage, thermal properties, Raman spectroscopy, pore structure analysis, fracture behavior, and decontamination methods.
最新文献
Introductory Nuclear Physics

book-chapter Full Text OpenAlex

An extensive benchmark analysis of advanced ceramic-concretes towards strategic material selection for nuclear applications and waste management

article Full Text OpenAlex

Monte Carlo multiphysics simulation on adaptive unstructured mesh geometry

article Full Text OpenAlex

Melting properties of lunar regolith simulant for in-situ construction

article Full Text OpenAlex

CH4 and CO2 Reductions from Methanol Production Using Municipal Solid Waste Gasification with Hydrogen Enhancement

article Full Text OpenAlex

Synthesis and characterization of multi-component borosilicate glass beads for radioactive liquid waste immobilisation

article Full Text OpenAlex

Overview of Small Modular and Advanced Nuclear Reactors and Their Role in the Energy Transition

article Full Text OpenAlex

Core design optimization of a 200 MWt pressurized water SMR using evolutionary simulated annealing

article Full Text OpenAlex

Improved data analysis techniques for calculating more accurate radon and thoron exhalation rates from building interior solid walls

article Full Text OpenAlex

Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory

article Full Text OpenAlex

近5年高被引文献
IOP Conference Series: Materials Science and Engineering

article Full Text OpenAlex 10376 FWCI801.93478261

Past, present and future prospective of global carbon fibre composite developments and applications

article Full Text OpenAlex 695 FWCI85.93625055

Polymeric composite materials for radiation shielding: a review

review Full Text OpenAlex 549 FWCI33.27341281

A review of CO2 emissions reduction technologies and low-carbon development in the iron and steel industry focusing on China

review Full Text OpenAlex 451 FWCI29.94746844

Introductory Nuclear Physics

book-chapter Full Text OpenAlex 419 FWCI116.01959451

Composite Material Recycling Technology—State-of-the-Art and Sustainable Development for the 2020s

article Full Text OpenAlex 348 FWCI30.35907621

Decarbonizing the iron and steel industry: A systematic review of sociotechnical systems, technological innovations, and policy options

review Full Text OpenAlex 313 FWCI38.70222507

Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33

article Full Text OpenAlex 256 FWCI133.10726866

Molten salt for advanced energy applications: A review

review Full Text OpenAlex 244 FWCI82.51610572

Radiation attenuation properties of some commercial polymers for advanced shielding applications at low energies

article Full Text OpenAlex 184 FWCI12.57181844