Reactor Physics and Fuel-Cycle Analyses-Reference-Cited by-同舟云学术

Reactor Physics and Fuel-Cycle Analyses

Published:1970-02 Issue:2 Volume:8 Page:208-219
ISSN:0550-3043
Container-title:Nuclear Applications and Technology
language:en
Short-container-title:Nuclear Applications and Technology

Author:

Perry A. M.¹,Bauman H. F.¹

Affiliation:

1. Oak Ridge National Laboratory, Oak Ridge, Tennessee 37830

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT70-A28626

Reference5 articles.

1. The Design and Performance Features of a Single-Fluid Molten-Salt Breeder Reactor

2. A. M. PERRY, “Influence of Neutron Data in the Design of Other Types of Power Reactors,” ORNL-TM-2157, Oak Ridge National Laboratory (March 8, 1968).

3. Engineering Development of the MSBR Fuel Recycle

4. Graphite and Xenon Behavior and their Influence on Molten-Salt Reactor Design

5. Molten-Salt Reactor Chemistry

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