Development and Irradiation Performance of Uranium Aluminide Fuels in Test Reactors-Reference-Cited by-同舟云学术

Development and Irradiation Performance of Uranium Aluminide Fuels in Test Reactors

Published:1980-06 Issue:1 Volume:49 Page:136-149
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Beeston J. M.¹,Hobbins R. R.¹,Gibson G. W.¹,Francis W. C.¹

Affiliation:

1. EG&G Idaho, Inc., P.O. Box 1625, Idaho Falls, Idaho 83401

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT80-A32515

Reference32 articles.

1. D. O. HOBSON, R. L. HEESTAND, and C. F. LEITTEN, Jr. “Fabrication Development of U3O8-Aluminum Composite Fuel Plate for the Advanced Test Reactor,” ORNL-3644, Oak Ridge National Laboratory (1964).

2. G. W. GIBSON and W. C. FRANCIS, “Annual Progress Report on Fuel Element Development for FY-1962,” IDO-16799, Idaho Operations Office Atomic Energy Commission (1962).

3. G. W. GIBSON, M. J. GRABER, and W. C. FRANCIS, “Annual Progress Report on Fuel Element Development for FY-1963,” IDO-16934, Idaho Operations Office, Atomic Energy Commission (1963).

4. W. C. FRANCIS, Ed. “Annual Progress Report on Reactor Fuels and Materials Development for FY-1965,” IDO-17154, Idaho Operations Office, Atomic Energy Commission (1966).

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