vitrification process
Image credit: radopactovotu/eu.com
Expanding
Nuclear Waste Vitrification Strategies with Customizable Glass
by
Rebecca Straw.
Nuclear
power plays a key role in sustainable energy generation, offering a
long-term solution with its extended operating life and low
greenhouse gas emissions. As of 2025, nuclear energy supplies
approximately 10% of the world’s electricity, with 440 power
reactors operating across 31 countries.1
Beyond
power generation, nuclear technology is also starting to play a vital
role in medical diagnostics, industrial processes, and space
exploration. With growing demand for reliable, clean energy, the
sector continues to expand, with new reactors under construction
worldwide.2 However, nuclear waste disposal remains a
critical challenge, requiring innovative solutions to ensure
long-term safety.
Vitrification and the Growing Importance of Nuclear Waste
Management
High-level
nuclear waste (HLW) is the most hazardous by-product of nuclear
energy production, consisting primarily of spent nuclear fuel and its
reprocessed liquids. Its long-lived isotopes and high radiation
levels pose significant environmental and health risks, requiring
robust containment strategies.3,4
As
unstable isotopes decay, HLW continuously emits heat and radiation,
making secure storage essential to prevent environmental
contamination.4 Certain radionuclides, such as the
actinides plutonium and curium, have extremely long half-lives,
necessitating immobilization techniques that ensure stability for
thousands of years.3 Others, like Technetium-99 and
Iodine-129, are highly soluble in water, increasing the risk of
groundwater infiltration if not properly contained. These challenges
demand a waste form that offers long-term durability, leach
resistance, and mechanical stability under repository conditions.
Vitrification—the
process of turning waste into glass—has emerged as one of the most
effective containment methods for HLW.4 Unlike
dilution or surface storage, vitrification permanently traps
hazardous materials within a stable glass matrix, preventing their
release into the environment. Additionally, vitrified waste is
compact, insoluble, and well-suited for secure long-term storage and
disposal.
Glass Selection in Nuclear Waste Immobilization
Selecting
the right glass composition is critical for the success of
vitrification. Borosilicate and phosphate-based glasses are the two
primary materials used for HLW immobilization.
Borosilicate
glass is favored for its high chemical durability, low thermal
expansion, and capacity to incorporate a wide range of
radionuclides.3 It has been the standard choice in
countries like France, the UK, and the US, where large-scale
vitrification facilities are in operation. Its success is largely due
to its compatibility with various waste cations, well-characterized
structure, and well-established processing technology.3
However,
optimizing the waste loading—the percentage of waste incorporated
per unit volume of glass—while ensuring the final product remains
stable and processable remains a persistent challenge in
vitrification processes. While increasing waste loading reduces
overall storage costs and processing time, it requires precise
control over the glass formulation to prevent crystallization or
phase separation.
Optimized
borosilicate glass is generally well suited for this purpose, but
certain waste components present in HLW, such as molybdenum and noble
metals, have low solubility in the borosilicate matrices, limiting
how much can be incorporated, and its utility as a universal HLW
matrix.
Expanding Vitrification Strategies Through Customizable and
Alternative Glass Solutions
While
borosilicate glass has long been the standard for HLW vitrification,
its limitations in incorporating certain waste components have driven
the exploration of alternative glass formulations. Phosphate-based
glasses (e.g., iron phosphate, alumino phosphate) present a promising
alternative to traditional borosilicate glass for the immobilization
of HLW, particularly in the management of actinides, lanthanides, and
other elements that are poorly soluble in borosilicate.
These
phosphate glasses offer enhanced degradation resistance and superior
tolerance to radiation, making them ideal for managing complex waste
streams.3 In particular, phosphate-based formulations
are highly relevant for next-generation reactor technologies, such as
molten salt reactors. These reactors, which utilize liquid fuel
salts, produce waste compositions that are rich in fluorine and
differ significantly from those of conventional reactors, thus
limiting the types of glasses that can effectively immobilize this
type of waste.5
Phosphate
glasses also stand out for their ability to better accommodate
halide-rich waste streams. These glasses can be processed at lower
temperatures, reducing volatility, and can accommodate higher salt
loading, making them an attractive solution for waste from advanced
reactor designs. 5 For example, fast breeder
reactors, which generate waste with high concentrations of plutonium
and actinides, require non-silicate glass forms capable of
accommodating these elements without compromising long-term
integrity.
Leading Innovation in Nuclear Waste Vitrification
MO
SCI is pioneering the development of advanced glass formulations that
improve waste loading and long-term performance while addressing the
limitations of traditional glass forms. By focusing on customizing
glass compositions to suit specific waste characteristics, MO SCI is
helping to ensure that vitrification remains a scalable and effective
solution for HLW disposal, supporting the transition to
next-generation reactor technologies.
For
further information on nuclear waste management solutions,
please contact
us today.
Rebecca
Straw
References
and Further Reading
World
Nuclear Association. Nuclear Power in the World
Today [Updated 6 Jan 2025]. Available
from: https://world-nuclear.org/information-library/current-and-future-generation/nuclear-power-in-the-world-today#:~:text=Nuclear%20energy%20now%20provides%20about,in%20about%20220%20research%20reactors.;
(Accessed on 3 Mar).
Hyatt
NC, Ojovan MI. (2019) Special Issue: Materials for Nuclear Waste
Immobilization. Materials (Basel);12(21).
Bohre
A, Avasthi K, Pet’kov VI. (2017) Vitreous and crystalline
phosphate high level waste matrices: Present status and future
challenges. Journal of Industrial and Engineering Chemistry;50:1-14.
Sanito
RC, Bernuy-Zumaeta M, You SJ, Wang YF. (2022) A review on
vitrification technologies of hazardous waste. J Environ
Manage;316:115243.
Riley
BJ, McFarlane J, DelCul GD, Vienna JD, Contescu CI, Forsberg CW.
(2019) Molten salt reactor waste and effluent management strategies:
A review. Nuclear Engineering and Design;345:94-109.