Development of Mechanistic Modeling Capabilities for Local Neutronically-Coupled Flow-Induced Instabilities in Advanced Water-Cooled Reactors

doi 10.2172/968647
Full Text
Abstract

Available in full text

Date
Authors

Unknown

Publisher

Office of Scientific and Technical Information (OSTI)

Related search

Sodium-Reactor Experiment Advanced Sodium-Cooled Reactors and Sodium- Component Development

1966English

Nuclear Data Analyses for Improving the Safety of Advanced Lead-Cooled Reactors

EPJ Web of Conferences
AstronomyPhysics
2019English

Investigation of Fundamental Thermal-Hydraulic Phenomena in Advanced Gas-Cooled Reactors

2006English

Three Core Concepts for Producing Uranium-233 in Commercial Pressurized Light Water Reactors for Possible Use in Water-Cooled Breeder Reactors

1979English

Mechanical and Thermal Problems of Water-Cooled Nuclear Power Reactors

1955English

Numerical Investigation of Flow in Generation IV Pebble Bed Gas Cooled Core Reactors

International Journal of Energy and Power Engineering
2013English

Review of Organic Iodide Formation Under Accident Conditions in Water- Cooled Reactors

1972English

Modeling Discharge and Surface Processes in Capacitively Coupled Reactors

English

Intergranular Stress-Assisted Corrosion Cracking of Austenitic Alloys in Water-Cooled Nuclear Reactors

Journal of Nuclear Materials
High Energy PhysicsMaterials ScienceEngineeringNuclear EnergyNuclear
1975English

Amanote Research

Note-taking for researchers

Follow Amanote

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

Privacy PolicyRefund Policy