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Book cover for Zirconium in the Nuclear Industry
ASTM Selected Technical Papers
Zirconium in the Nuclear Industry
By
RB Adamson
RB Adamson
1
General Electric Company
,
Pleasanton, California
;
symposium chairman and co-editor
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LFP Van Swam
LFP Van Swam
2
Exxon Nuclear Company, Inc.
,
Richland, Washington
;
symposium editorial chairman and co-editor
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ISBN-10:
0-8031-0935-0
ISBN:
978-0-8031-0935-3
No. of Pages:
846
DOI:
https://doi.org/10.1520/STP939-EB
Publisher:
ASTM International
Publication date:
1987
eBook Chapter

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

By
FJ Erbacher
FJ Erbacher
1Kernforschungszentrum Karlsruhe,
Institut für Reaktorbauelemente, Projekt Nukleare Sicherheit
,
7500 Karlsruhe 1,
Federal Republic of Germany
.
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,
S Leistikow
S Leistikow
2Kernforschungszentrum Karlsruhe,
Institut für Material- und Festkörperforschung, Projekt Nukleare Sicherheit
,
7500 Karlsruhe 1,
Federal Republic of Germany
.
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Doi:
https://doi.org/10.1520/STP28138S
Page Count:
38
  • Published:
    1987

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.

Keywords:
zirconium alloys, pressurized water reactors, loss-of-coolant accident, oxidation, embrittlement, plastic deformation, cooling

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