Simulated Fission Product Oxide Behavior in Triso-Coated HTGR Fuel

doi 10.2172/5803794
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Office of Scientific and Technical Information (OSTI)

Related search

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

Journal of Nuclear Materials
High Energy PhysicsMaterials ScienceEngineeringNuclear EnergyNuclear
2012English

Fission Product Control in HTGR Plants

1974English

Measurement and Modelling of Postirradiation Fission Product Release From HTGR Fuel Particles Under Accident Conditions

1978English

Modeling of the Repository Behavior of TRISO Fuel.

2006English

Experimental Test of the Frevap-8 Code for Calculating Metal Fission Product Release From HTGR Fuel Elements.

1968English

(Fuel, Fission Product, and Graphite Technology)

1990English

Fission Product Inventory and Decay Heat Associated With FTR Fuel.

1969English

Some Fire and Fission Product Release Possibilities for Discharged Fuel Slugs

1961English

Behavior of Fission Gases in Nuclear Fuel: XAS Characterization of Kr in UO2

Journal of Nuclear Materials
High Energy PhysicsMaterials ScienceEngineeringNuclear EnergyNuclear
2015English

Amanote Research

Note-taking for researchers

Follow Amanote

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

Privacy PolicyRefund Policy