Fuel Cycle Costs in a Graphite Moderated Slightly Enriched Fused Salt Reactor

doi 10.2172/4186501
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Office of Scientific and Technical Information (OSTI)

Related search

Fuel Elements for Ornl Graphite Reactor

1952English

A Study of Physics Parameters in Several Water-Moderated Lattices of Slightly Enriched and Natural Uranium.

1970English

Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders. Appendices

1961English

Molten-Salt Breeder Reactor Fuel Processing.

1972English

Thermodynamics in the Fused Salt Dissolution Process for Zirconium Fuel

1959English

600 MW FUSED SALT HOMOGENEOUS REACTOR POWER PLANT. Reactor Design and Feasibility Study

1956English

Power Generation Costs for Alternate Reactor Fuel Cycles

1980English

Behavior of Actinides in the Integral Fast Reactor Fuel Cycle

1994English

Temperature Coefficient of Reactivity in Light-Water Moderated and Reflected Cores Loaded With Highly-Enriched-Uranium Fuel

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
1987English

Amanote Research

Note-taking for researchers

Follow Amanote

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

Privacy PolicyRefund Policy