Amanote Research

Amanote Research

    RegisterSign In

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
Open PDF
Abstract

Available in full text

Categories
High Energy PhysicsNuclearEngineeringNuclear Energy
Date

April 1, 2011

Authors
Nobuo NAKAEToshikazu BABAKatsuichiro KAMIMURA
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

© 2025 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy