SYMPOSIA PAPER Published: 01 January 1987
STP28138S

Zircaloy Fuel Cladding Behavior in a Loss-of-Coolant Accident: A Review

Source

This paper reviews the state-of-the-art experimental work performed in several countries with respect to the acceptance criteria established for the emergency core cooling (ECC) in a loss-of-coolant accident (LOCA) of light water reactors (LWRs). It covers in detail oxidation, embrittlement, plastic deformation, and coolability of deformed rod bundles.

The main test results are discussed on the basis of research work performed at the Karlsruhe Nuclear Research Center (KfK) within the framework of the Nuclear Safety Project (PNS). Reference is made to test data obtained in other countries.

The paper concludes that the major mechanisms and consequences of oxidation, deformation, and emergency core cooling are sufficiently investigated in order to provide a reliable data base for safety assessments and licensing of LWRs. All test data prove that the ECC criteria are conservative and that the coolability of a LWR and the public safety in a LOCA can be maintained.

Author Information

Erbacher, FJ
Institut für Reaktorbauelemente, Projekt Nukleare Sicherheit, Federal Republic of Germany
Leistikow, S
Institut für Material- und Festkörperforschung, Projekt Nukleare Sicherheit, Federal Republic of Germany
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Details
Developed by Committee: B10
Pages: 451–488
DOI: 10.1520/STP28138S
ISBN-EB: 978-0-8031-5004-1
ISBN-13: 978-0-8031-0935-3