In-situ determination of strain during transient burst testing and the temperature dependence of Zircaloy-4 claddings

Author:

Bell S.B.ORCID,Kane K.A.ORCID,Ridley M.J.ORCID,Garrison B.E.,Johnston B.S.,Capps N.A.ORCID

Funder

U.S. Department of Energy

US Department of Energy Office of Nuclear Energy

Publisher

Elsevier BV

Reference36 articles.

1. Zirconium Cladding Deformation in a Steam Environment with Transient Heating;Chapman;Zircon. Nucl. Ind.,1979

2. Cladding Swelling and Rupture Models for LOCA Analysis, US Nuclear Regulatory Commission;Powers;NUREG,1980

3. Burst criterion of zircaloy fuel claddings in a loss-of-coolant accident;Erbacher;Zircon. Nucl. Ind.,1982

4. Zircaloy fuel cladding behavior in a loss-of-coolant accident: a review;Erbacher;Zircon. Nucl. Ind.,1987

5. Experiments on ballooning in pressurized and transiently heated zircaloy-4 tubes;Markiewicz;Karlsruhe Inst. KfK,1988

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