Hydrogen uptake during oxidation of zirconium alloys

1997 ◽  
Vol 256 (1-2) ◽  
pp. 244-246 ◽  
Author(s):  
B. Cox
Keyword(s):  
Zirconium Alloys ◽  
Hydrogen Uptake

scholarly journals H2 PERMEATION BEHAVIOR OF Cr2AlC AND Ti2AlC MAX PHASE COATED ZIRCALOY-4 BY NEUTRON RADIOGRAPHY

2018 ◽  
Vol 58 (1) ◽  
pp. 69 ◽  
Author(s):  
Chongchong Tang ◽  
Mirco Karl Grosse ◽  
Pavel Trtik ◽  
Martin Steinbrück ◽  
Michael Stüber ◽  
...  
Keyword(s):  
Hydrogen Diffusion ◽  
Hydrogen Permeation ◽  
Neutron Radiography ◽  
Zirconium Alloys ◽  
Hydrogen Uptake ◽  
Hydrogen Release ◽  
Max Phase ◽  
Normal Operation ◽  
Temperature Oxidation ◽  
Design Basis

Hydrogen uptake by nuclear fuel claddings during normal operation as well as loss of coolant during design basis and severe accidents beyond design basis has a high safety relevance because hydrogen degrade the mechanical properties of the zirconium alloys applied as cladding material. Currently, claddings with enhanced accident tolerance are under development. One group of such accident tolerant fuel (ATF) claddings are zirconium alloys with surface coatings reducing corrosion and high-temperature oxidation rate, as well as the chemical heat and hydrogen release during hypothetical accidents. The hydrogen permeation through the coating is an important parameter ensuring material safety. In this work, the hydrogen permeation of Ti2AlC and Cr2AlC MAX phase coatings on Zircaloy-4 is investigated by means of neutron radiography. Both coatings are robust hydrogen diffusion barriers that effectively suppress hydrogen permeation into the matrix.

scholarly journals In Situ Investigations of the Hydrogen Uptake of Zirconium Alloys during Steam Oxidation

2018 ◽  
pp. 1114-1135 ◽  
Author(s):  
Mirco Grosse ◽  
Martin Steinbrueck ◽  
Burkhard Schillinger ◽  
Anders Kaestner
Keyword(s):  
Zirconium Alloys ◽  
Hydrogen Uptake ◽  
Steam Oxidation

Hydrogen Uptake of Zirconium And Its Alloys During Early Stages Of Corrosion in Steam

CORROSION ◽  
1965 ◽  
Vol 21 (4) ◽  
pp. 137-142 ◽  
Author(s):  
D. W. FREER ◽  
D. R. SILVESTER ◽  
J. N. WANKLYN
Keyword(s):  
Zirconium Alloys ◽  
Hydrogen Uptake ◽  
Atmosphere Pressure ◽  
Early Stages ◽  
Weight Gains

Abstract Hydrogen uptakes during initial stages of corrosion of Van Arkel zirconium and of two zirconium alloys in steam at 500 C (932 F) and 1 atmosphere pressure are reported. Percentage uptake remains low down to the lowest weight gains examined (~1 mg/sq dm), suggesting that control of hydrogen entry resides in reactions at the oxide/steam interface.

Neutron Imaging Investigations of the Hydrogen Related Degradation of the Mechanical Properties of Zircaloy-4 Cladding Tubes

2013 ◽  
Vol 1528 ◽  
Author(s):  
M. Grosse ◽  
S. Valance ◽  
J. Stuckert ◽  
M. Steinbrueck ◽  
M. Walter ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Oxide Layer ◽  
Zirconium Alloys ◽  
Hydrogen Uptake ◽  
Mechanical Tests ◽  
Neutron Imaging ◽  
Ex Situ ◽  
Loss Of Coolant Accident ◽  
Local Enrichment

ABSTRACTThe hydrogen uptake and redistribution in Zircaloy-4 specimens applied to loss of coolant accident (LOCA) simulation experiments and in mechanical pre-loaded samples were investigated by means of ex-situ and in-situ neutron imaging. The results of these investigations were compared with results from mechanical tests. Hydrogen absorption may have a strong influence on the mechanical properties of zirconium alloys. A local enrichment of the absorbed hydrogen may result in brittle fracture at these positions in the tensile test. On the other hand, stress fields in the material affect the hydrogen uptake as well as its distribution in the material. In-situ investigations confirmed the existence of an initial oxide layer formed at room temperature by contact with air. This oxide layer suppresses the hydrogen uptake until dissolution in the zirconium matrix.

Ex-situ and in-situ Neutron Radiography Investigations of the Hydrogen Uptake of Nuclear Fuel Cladding Materials During Steam Oxidation at 1000°C and Above

2010 ◽  
Vol 1262 ◽  
Author(s):  
Mirco Grosse ◽  
Marius van den Berg ◽  
Eberhard Helmar Lehmann ◽  
Burkhard Schillinger
Keyword(s):  
Hydrogen Diffusion ◽  
Neutron Radiography ◽  
Zirconium Alloys ◽  
Hydrogen Uptake ◽  
Steam Oxidation ◽  
Ex Situ ◽  
In Situ Experiments ◽  
Nuclear Fuel Cladding ◽  
Non Destructive

AbstractNeutron radiography is a powerful tool for the investigation of the hydrogen uptake of zirconium alloys. It is fast, fully quantitative, non-destructive and provides a spatial resolution of 30 μm. The non-destructive character of neutron radiography provides the possibility of in-situ investigations. The paper describes the calibration of the method and delivers results of ex-situ measurements of the hydrogen concentration distribution after steam oxidation, as well as in-situ experiments of hydrogen diffusion in β-Zr and in-situ investigations of the hydrogen uptake during steam oxidation.

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