Wet-Chemical Dissolution of TRISO-coated Simulated High-Temperature-Reactor Fuel Particles

Journal of Nuclear Materials - Netherlands
doi 10.1016/j.jnucmat.2011.09.016
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Elsevier BV

Related search

Simulated Fission Product Oxide Behavior in Triso-Coated HTGR Fuel

1979English

Irradiation Test OF-2: High-Temperature Irradiation Behavior of LASL-made Fuel Rods and LASL-made Coated Particles. [ZrC Coated Particles]

1977English

High-Temperature Fracture Strength of a CVD-SiC Coating Layer for TRISO Nuclear Fuel Particles by a Micro-Tensile Test

Journal of the Korean Ceramic Society
CompositesCeramics
2015English

Sample Preparation Techniques for Grain Boundary Characterization of Annealed TRISO-Coated Particles

Nuclear Technology
High Energy PhysicsNuclearEngineeringNuclear EnergyCondensed Matter Physics
2016English

The Effect of Coating Parameters and Annealing on the Crushing Strength of TRISO Coated Particles

Nuclear Technology
High Energy PhysicsNuclearEngineeringNuclear EnergyCondensed Matter Physics
2013English

Ignition of Wet Wood Particles in the Stream of High-Temperature Gases

MATEC Web of Conferences
Materials ScienceEngineeringChemistry
2016English

Irradiation Test HT-31: High-Temperature Irradiation Behavior of LASL-made Extruded Fuel Rods and LASL-made Coated Particles

1977English

Fabrication of the First-Loading Fuel of the High Temperature Engineering Test Reactor

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
1999English

Modeling of the Repository Behavior of TRISO Fuel.

2006English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2024 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy