Cold Spray Technology for Oxidation-Resistant Nuclear Fuel Cladding

2021 ◽  
Author(s):  
Tyler Dabney ◽  
Hwasung Yeom ◽  
Kyle Quillin ◽  
Nick Pocquette ◽  
Kumar Sridharan
Keyword(s):  
Cold Spraying ◽  
Light Water Reactors ◽  
Fuel Cladding ◽  
Fuel Pellets ◽  
Loss Of Coolant Accident ◽  
Design Basis Accident ◽  
Oxidation Resistant ◽  
Water Reactors ◽  
Excellent Adhesion ◽  
Zr Alloy

Abstract Light water reactors (LWR) use zirconium-alloy fuel claddings; the tubes that hold the uranium-dioxide fuel pellets. Zr-alloys have very good neutron transparency; but during a loss of coolant accident or beyond design basis accident (BDBA) they can undergo excessive oxidation in reaction with the surrounding steam environment. Relatively thin oxidationresistant coatings on Zr-alloy fuel cladding tubes can potentially buy coping time in these off-normal scenarios. In this study; cold spraying; solid-state powder-based materials deposition technology has been developed for deposition of oxidation-resistant Cr coatings on Zr-alloy cladding tubes; and the ensuing microstructure and properties of the coatings have been investigated. The coatings when deposited under optimum conditions have very good hydrothermal corrosion resistance as well as oxidation resistance in air and steam environments at temperatures in excess of 1100 °C; while maintaining excellent adhesion to the substrate. These and other results of this study; including mechanical property evaluations; will be presented.

Using Small X-Ray Beams to Understand Corrosion in Nuclear Fuel Cladding

2004 ◽  
Author(s):  
Arthur T. Motta ◽  
Aylin Yilmazbayhan ◽  
Robert J. Comstock ◽  
Barry Lai ◽  
Zhonghou Cai
Keyword(s):  
Primary Circuit ◽  
Light Water Reactors ◽  
Fuel Cladding ◽  
Protective Oxide ◽  
X Ray ◽  
Engineering Problems ◽  
Small X ◽  
Nuclear Fuel Cladding ◽  
Water Reactors ◽  
Zr Alloy

Uniform oxidation by the primary circuit water and associated may soon limit the service of Zr alloy fuel cladding in Light Water reactors. Understanding the differences in corrosion rate between alloys based on the microstructure of the protective oxide may allow us to design better alloying materials for severe duty cycle applications. The use of synchrotron radiation microbeam at APS allows the study of these oxide layers with an unique combination of the wealth of diffraction and fluorescence information and the level of spatial resolution obtained. We will discuss some of our experimental results and the potentials of these techniques in solving engineering problems.

Stratified Flow Experiments Pertaining to Advanced LWR Reactor Passive Safety System Designs

2004 ◽  
Author(s):  
Jim C. P. Liou ◽  
Alan G. Stephens ◽  
Richard R. Schultz
Keyword(s):  
Flow Behavior ◽  
Stratified Flow ◽  
Water Hammer ◽  
Test Facility ◽  
Light Water Reactors ◽  
Loss Of Coolant Accident ◽  
Passive Safety System ◽  
Water Reactors ◽  
Lower Temperature ◽  
System Designs

During a loss-of-coolant-accident in advanced light water reactors, outside coolant enters the cold leg by gravity to cool the core. This coolant is at a substantially lower temperature and thus is heavier than the liquid in and from the reactor. Consequently, stratified flow may occur. A stratified flow may cause condensation-induced water hammer, and will influence the coolant flow behavior. Two sets of experiments are in progress to better understand stratified flow conditions that lead to water hammer, and the density stratification behavior. The first set uses air-oil-water as the test media. Its purposes are to conduct exploratory tests and to provide instruction an apparatus for education purposes. The second set of tests will use steam and water and, later, the refrigerant R123. This paper describes the exploratory test facility, gives a brief description of the facility that will be used for the steam-water and refrigerant tests, describes the overall test plan, and finally gives some preliminary results on the intrusion of a lighter liquid into a pipe against flow.

Development of Cold Spray Coatings for Accident-Tolerant Fuel Cladding in Light Water Reactors

JOM ◽  
2017 ◽  
Vol 70 (2) ◽  
pp. 198-202 ◽  
Author(s):  
Benjamin Maier ◽  
Hwasung Yeom ◽  
Greg Johnson ◽  
Tyler Dabney ◽  
Jorie Walters ◽  
...  
Keyword(s):  
Cold Spray ◽  
Light Water Reactors ◽  
Fuel Cladding ◽  
Light Water ◽  
Spray Coatings ◽  
Water Reactors

Evaluation and Prediction of Critical Overhang Length Under Pipe Whip Accident

1986 ◽  
Vol 108 (2) ◽  
pp. 182-187
Author(s):  
T. Yano ◽  
N. Miyazaki ◽  
S. Miyazono
Keyword(s):  
Estimation Method ◽  
Plastic Collapse ◽  
Light Water Reactors ◽  
Pipe Length ◽  
Loss Of Coolant Accident ◽  
Overhang Length ◽  
Water Reactors ◽  
The Moment ◽  
Accident Conditions ◽  
Good Agreement

When the pipe length between break exit and restraint is long in the pipe whip accident, the pipe will undergo a plastic collapse as the moment increases. The length at which plastic collapse may occur is called the critical overhang length, (OH)cr. The experimental results of (OH)cr show good agreement with the prediction by a static simplified estimation method for (OH)cr although the pipe whipping is a dynamic phenomenon. The diagrams of (OH)cr are also described for a range of sizes of stainless steel pipe under the loss of coolant accident conditions of light water reactors.

Silicon carbide encapsulated fuel pellets for light water reactors

2001 ◽  
Vol 38 (3-4) ◽  
pp. 411-414 ◽  
Author(s):  
Z. Alkan ◽  
K. Kugeler ◽  
R. Kaulbarsch ◽  
C. Manter
Keyword(s):  
Silicon Carbide ◽  
Light Water Reactors ◽  
Light Water ◽  
Fuel Pellets ◽  
Water Reactors

scholarly journals Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

2015 ◽  
Vol 467 ◽  
pp. 703-716 ◽  
Author(s):  
Y. Yamamoto ◽  
B.A. Pint ◽  
K.A. Terrani ◽  
K.G. Field ◽  
Y. Yang ◽  
...  
Keyword(s):  
Nuclear Grade ◽  
Light Water Reactors ◽  
Fuel Cladding ◽  
Light Water ◽  
Property Evaluation ◽  
Water Reactors
Sign in / Sign up

Export Citation Format

Share Document