Safety Margins in Zircaloy Oxidation and Embrittlement Criteria for Emergency Core Cooling System Acceptance-Reference-Cited by-同舟云学术

Safety Margins in Zircaloy Oxidation and Embrittlement Criteria for Emergency Core Cooling System Acceptance

Published:1986-09 Issue:3 Volume:74 Page:333-345
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Williford R. E.¹

Affiliation:

1. Pacific Northwest Laboratory, Physical Sciences Building Battelle Boulevard, Richland, Washington 99352

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/NT86-A33836

Reference25 articles.

1. L. BAKER and L. C. JUST, “Studies of Metal-Water Reactions at High Temperature: III. Experimental and Theoretical Studies of Zirconium-Water Reaction,” ANL-6548, Argonne National Laboratory (1962).

2. H. BETHE et al. “Report to the American Physical Society by the Study Group on Light-Water Reactor Safety,” Rev. Mod. Phys.47, Suppl. No. 1 (1975).

3. C. A. MANN et al. “Deformation of PWR Fuel in a Loss of Coolant Accident (LOCA),” Springfields Nuclear Establishment, CSNI Paper, U.K. Atomic Energy Authority (1985).

4. L. E. HOCHREITER, “FLECHT SEASET Program Final Report,” NUREG/CR-4167, Westinghouse Electric Corp. (Sep. 1985).

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