Effects of Zr-hydride distribution of irradiated Zircaloy-2 cladding in RIA-simulating pellet-clad mechanical interaction testing

Author:

Magnusson Per,Alvarez-Holston Anna-Maria,Ammon Katja,Ledergerber Guido,Nilsson Marcus,Schrire David,Nissen Klaus,Wright Jonathan

Funder

Vattenfall AB

OKG AB

Westinghouse Electric Sweden AB

Studsvik AB

AREVA GmbH

Teollisuuden Voima Oyj

Kernkraftwerk Leibstadt AG

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference23 articles.

1. J. Papin, F. Lemoine, E. Federici, Main outcomes from the CABRI test results, in: Proc. NEA CSNI Topical Meeting on RIA Fuel Safety Criteria, Aix-en-Provence, France, May 13–15, 2002, Report NEA/CSNI/R(2003)8/Vol. 2, pp. 61–81.

2. Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO2 fuel (VVR Type) under reactivity accident conditions;Yegorova,1999

3. T. Nakamura, FK test series with high burnup BWR fuel and analytical test program, in: Proc. of the 23rd NSRR Technical Review Meeting, Tokyo, Japan, November 11–12, 1999.

4. Boiling water reactor fuel behaviour at burnup of 26 MWd/kgU under reactivity-initiated accident conditions;Nakamura;Nucl. Technol.,1994

5. High burnup BWR fuel behavior under simulated reactivity-initiated accident conditions;Nakamura;Nucl. Technol.,2002

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