Basis of Technical Standard on Fuel for Sodium-Cooled Fast Breeder Reactor

Journal of Nuclear Science and Technology - United Kingdom
doi 10.1080/18811248.2011.9711729
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Informa UK Limited

Related search

Analysis of the Conceptual Shielding Design for the Upflow Gas-Cooled Fast Breeder Reactor

1981English

SODIUM-AIR ACCIDENT STUDY FOR a SODIUM COOLED REACTOR. Technical Memorandum No. 20

1959English

Fast Breeder Reactor Studies

1980English

Liquid Salt - Very High Temperature Reactor : Survey of Sodium-Cooled Fast Reactor Fuel Handling Systems for Relevant Design and Operating Characteristics.

2006English

Uranium Nitride--Sodium Paste Fuel for Fast-Reactor Blankets.

1968English

Engineering Review of the Core Support Structure of the Gas Cooled Fast Breeder Reactor

1978English

Gas-Cooled Fast Reactor

Nature
Multidisciplinary
1968English

Gas Cooled Fast Reactor

1972English

Liquid Metal Cooled Fast Breeder Reactor Development and Its Mechanical-Structural Requirements and Problems

Nuclear Engineering and Design
Materials ScienceRiskMechanical EngineeringWaste ManagementNuclearNuclear EnergyHigh Energy PhysicsEngineeringReliabilitySafetyDisposalQuality
1972English

Amanote Research

Note-taking for researchers

Follow Amanote

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

Privacy PolicyRefund Policy