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.

Parameters Influencing the Secondary Hydrogenation of Zr-Sn and Zr-Nb Alloys During Steam Oxidation Under LOCA and Severe Accident Conditions

2010 ◽  
Author(s):  
Mirco K. Grosse ◽  
Martin Steinbrueck ◽  
Juri Stuckert
Keyword(s):  
Oxide Layer ◽  
Large Scale ◽  
Gas Flow ◽  
Hydrogen Diffusion ◽  
Neutron Radiography ◽  
Hydrogen Uptake ◽  
Experimental Results ◽  
Steam Oxidation ◽  
Severe Accident

The parameters influencing secondary hydrogen uptake can be divided into two groups: material properties and process parameters. The first group includes for instance the steam oxidation kinetics, the oxide morphology and the hydrogen diffusion through the oxide layer. The second group covers for instance the temperature, the total pressure, the gas flow type and rates, the cladding area and the filling of the rods. Together with a theoretical view on the influence of different parameters on the hydrogen uptake of zirconium alloys experimental results from separate-effect tests, large-scale QUENCH tests and in-situ neutron radiography investigations of the hydrogen uptake during steam oxidation will be presented. The hydrogen concentrations in specimens made from commonly used cladding materials were determined by quantitative analysis of neutron radiographs. Information obtained from ex- and in-situ steam oxidation experiments will be given. The presentation of the experimental results will be focused on the influence of oxidation time and temperature, of the oxide layer morphology, the sample geometry and of the gas flow rates on the hydrogen concentration of the remaining metal phases. Differences between Zr-Sn, Zr-Nb and Zr-Sn-Nb alloys will be discussed.

scholarly journals In Situ Neutron Radiography Investigations of Hydrogen Related Processes in Zirconium Alloys

2021 ◽  
Vol 11 (13) ◽  
pp. 5775
Author(s):  
Mirco Grosse ◽  
Burkhardt Schillinger ◽  
Anders Kaestner
Keyword(s):  
Zirconium Alloy ◽  
High Temperature Oxidation ◽  
Hydrogen Diffusion ◽  
Neutron Radiography ◽  
Zirconium Alloys ◽  
Hydrogen Uptake ◽  
Temperature Oxidation ◽  
Diffusive Processes ◽  
Kinetics Of

In situ neutron radiography experiments can provide information about diffusive processes and the kinetics of chemical reactions. The paper discusses requirements for such investigations. As examples of the zirconium alloy Zircaloy-4, the hydrogen diffusion, the hydrogen uptake during high-temperature oxidation in steam, and the reaction in nitrogen/steam and air/steam atmospheres, results of in situ neutron radiography investigations are reviewed, and their benefit is discussed.

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

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.

An in situ and ex situ TEM study of the formation of thin cobalt silicide films by molecular beam epitaxy on the silicon (100) surface

1988 ◽  
Vol 46 ◽  
pp. 884-885
Author(s):  
D. Loretto ◽  
J. M. Gibson ◽  
S. M. Yalisove ◽  
R. T. Tung
Keyword(s):  
Molecular Beam Epitaxy ◽  
Molecular Beam ◽  
Defect Density ◽  
High Vacuum ◽  
Ultra High Vacuum ◽  
Ex Situ ◽  
Metal Base ◽  
In Situ Experiments ◽  
Potential Applications

The cobalt disilicide/silicon system has potential applications as a metal-base and as a permeable-base transistor. Although thin, low defect density, films of CoSi2 on Si(111) have been successfully grown, there are reasons to believe that Si(100)/CoSi2 may be better suited to the transmission of electrons at the silicon/silicide interface than Si(111)/CoSi2. A TEM study of the formation of CoSi2 on Si(100) is therefore being conducted. We have previously reported TEM observations on Si(111)/CoSi2 grown both in situ, in an ultra high vacuum (UHV) TEM and ex situ, in a conventional Molecular Beam Epitaxy system.The procedures used for the MBE growth have been described elsewhere. In situ experiments were performed in a JEOL 200CX electron microscope, extensively modified to give a vacuum of better than 10-9 T in the specimen region and the capacity to do in situ sample heating and deposition. Cobalt was deposited onto clean Si(100) samples by thermal evaporation from cobalt-coated Ta filaments.

Sulfonated poly(benzoyl paraphenylene) as a membrane for PEMFC: Ex situ and in situ experiments of thermal and chemical stability

2013 ◽  
Vol 98 (1) ◽  
pp. 3-11 ◽  
Author(s):  
Łukasz Łańcucki ◽  
Shulamith Schlick ◽  
Marek Danilczuk ◽  
Frank D. Coms ◽  
Krzysztof Kruczała
Keyword(s):  
Chemical Stability ◽  
Ex Situ ◽  
In Situ Experiments ◽  
Thermal And Chemical Stability ◽  
Sulfonated Poly
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