ODS FeCrAl Alloys for Accident-Tolerant Fuel Cladding

This set of vocabulary flashcards covers the development, requirements, and material properties of ODS FeCrAl alloys as accident-tolerant fuel cladding for nuclear reactors.

Three Mile Island and Chernobyl

Nuclear power plant accidents mentioned as occurring before the 1990s that prompted research into third generation reactors to mitigate serious accidents.

11 March 2011

The date of the Fukushima nuclear accident in Japan, which involved second-generation nuclear power units.

Accident-tolerant fuel cladding

A material combination designed to replace the zircaloy-clad-$UO_2$ system with an oxidation-resistant cladding to improve safety margins in Light Water Reactors ($LWR$).

Supercritical Pressurized Water Reactor (SPWR)

A type of $IV$ generation nuclear power system for which accident-tolerant cladding development is a key issue for high burnup operation.

Lead Bismuth-Budding Fast Reactor (LFR)

An additional example of a $IV$ generation nuclear power system mentioned in the context of high burnup operation requirements.

$$Cr_2O_3$$

An oxide layer that can provide protection up to $1000\,^{\circ}C$ in dry air for longer than $1000\,h$.

$$Al_2O_3$$

An oxide layer that can provide protection up to $1400\,^{\circ}C$ in dry air for longer than $1000\,h$.

$$SiO_2$$

An oxide layer that can provide protection up to $1700\,^{\circ}C$ in dry air for longer than $1000\,h$, depending on factors like thickness and exposure.

Volatile hydroxides

Compounds formed by $Cr_2O_3$ and $SiO_2$ oxide scales in high-temperature steam environments, which reduce their service limit by several hundred degrees.

FeCrAl alloys

Alloys exhibiting very low reaction kinetics up to $1200\,^{\circ}C$ in high-pressure steam, making them desirable candidates for accident-tolerant fuel cladding.

Fuel cladding

The shell used to seal nuclear fuel, serving as a safety barrier to prevent the escape of fission products, prevent fuel corrosion by coolant, and export thermal energy.

Oxide dispersion strengthened (ODS) alloys

Materials containing ultra-high density dispersed nanosized oxides that pin dislocations and grain boundaries to improve high-temperature strength.

Point defect recombination

A process promoted by high-density nanosized oxides in $ODS$ alloys that involves the recombination of vacancies and self-interstitial atoms to reduce radiation damage.

ODS FeCrAl alloy

A promising candidate material that combines the mechanical properties and radiation resistance of $ODS$ Fe-Cr alloys with the optimized corrosion resistance of FeCrAl alloys.

Tungsten (W)

In the context of $ODS$ FeCrAl alloy composition design, it serves as a solid solution strengthening element.

Y–Ti–O, Y–Al–O, and Y–Zr–O phases

The three typical types of oxides and their formation mechanisms discussed in the study of $ODS$ FeCrAl alloy systems.