Development of Hafnium and Comparison with Other Pressurized Water Reactor Control Rod Materials
Author:
Affiliation:
1. Westinghouse Electric Corporation, Water Reactor Divisions P.O. Box 3912, Pittsburgh, Pennsylvania 15230
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/NT82-A33005
Reference6 articles.
1. J. M. BEESTON, “Hafnium Irradiation Damage,” TREE-1140, EG&G Idaho (June 1977).
2. Hafnium Control Rod Behavior in the Shipping port Pressurized Water Reactor
3. G. E. KORTH, C. R. BRINKMAN, and J. M. BELSTON, “The Effect of Fast Neutron Irradiation of the Mechanical Properties of Hafnium,” IN-1440, Idaho Nuclear Corp. (Oct. 1970).
4. W. K. ANDERSON and J. S. THEILACKER, “Neutron Absorber Materials for Reactor Control,” U.S. Atomic Energy Commission (1962).
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