Nuclear waste immobilisation using glass and crystalline...
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Nuclear waste immobilisation using
glass and crystalline materials
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Michael I. Ojovan Department of Materials, Imperial College London
Immediate past – Department of Nuclear Energy, IAEA
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Contents
I. Background
II. Vitreous and
crystalline
wasteforms
II-A. Glasses
II-B. Ceramics
II-C. GCM’s
III. Radiation effects
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I. Background
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The wasteform is the waste in its physical and chemical form after treatment and/or immobilization (resulting in a solid product) prior to packaging.
Radioactive and chemically hazardous constituents of waste can be immobilized into a wasteform material through two processes: (1) Bound into the material at atomic scale (chemical incorporation), or (2) Physically surrounded and isolated by the material (encapsulation).
A number of matrices have been used for waste immobilization and those include glass, ceramic, cement, polymer and bitumen.
II. Vitreous and crystalline wasteforms
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• Radiation stability;- high tolerance to radiation effects from the decay of radioactive
constituents.
• Chemical flexibility;- able to accommodate a mixture of radioactive and chemical constituents
with minimum formation of secondary phases.
• Availability of natural analogues;- availability of natural mineral or glass analogues may provide important
clues about the long-term performance.
• Compatibility with the intended disposal environment.- compatible with the near-field environment of the disposal facility.
Important factors for wasteform materials:
• Waste loading; - able to accommodate a significant amount of waste (typically 25-45
weight %) to minimize volume.
• Ease of production;- accomplished under reasonable conditions.
• Durability;- low rate of dissolution to minimize the release of radioactive and
chemical constituents.
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Wasteform Features Limitations Secondary
waste
Glasses
Vitrification
Proven method to condition liquid HLW
as well as ILW and LLW
High flexibility in terms of the glass
formulation range
High reliability of the immobilization
process
High glass throughput
High durability of the final wasteform
Small volume of the resulting wasteform
High initial investment and
operational costs
Complex technology requiring high
qualified personnel
Generally not economical for LLW
and ILW
Need to control off-gases
Need to control variations in waste
feed
High specific energy consumption
Off-gases
Filters. Scrub
Solutions
Used Melters
Ceramics
Possible to incorporate higher levels of
actinides than borosilicate glass
Waste form is more stable and hence is
more durable than glass
Expected to be suitable for long term
isolation since it simulates natural rocks
Limited experience. Most efforts
have been research-based. There are
not known commercial installations
in operation at present. Generally
considered not economical for LLW
and ILW. The ceramivc (e.g. Synroc)
waste form must be tailored to suit
the particular characteristics of the
nuclear waste to be immobilized
Filters
Off-gases
Scrub
Solutions
Glass-
composite
materials
Combine features of both crystalline and
glassy materials. Higher waste loading.
Higher compatibility
Higher stability compared glasses
Limited experience Off-gases
Filters. Scrub
Solutions
Used Melters
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1II-A. Glasses
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Glasses are solid
amorphous materials
which transform into
liquids upon heating
through the glass
transition e.g. the
solid-like behaviour
of glasses is
separated from
liquid-like behaviour
at higher
temperatures by the
glass transition
temperature, Tg.
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Liquid-glass transition has been considered as a second order phase transition inwhich a supercooled melt yields, on cooling, a glassy structure and propertiessimilar to those of crystalline materials e.g. of an isotropic solid material.
IUPAC. Comp. Chemical Terminology. 66, 583, Royal Society of Chemistry, Cambridge (1997).
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diopside
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What is structural difference between a Glass and an Liquid?
Tg
meltingLiquid
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M.I. Ojovan. Viscosity and Glass Transition in Amorphous Oxides,
Advances in Condensed Matter Physics, 2008, Article ID 817829, 23
pages (2008). http://www.hindawi.com/journals/acmp/2008/817829/ref/
Physica B 523 (2017) 96–113: The glass transition belongs to a class of critical phenomena generically termed topological phase transitions which are amenable to the scaling approach and characterised by diverging length and time at the transition.
Tg
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Liquid phase Solid (glassy) phase
- This is a broken bond
Structurally the difference between glasses and liquids become evident
for broken bonds (configurons).
They form percolation clusters in liquids,
whereas in glasses they are point-type defects
The cluster made of broken bonds has the dimensionality Df= 2.4 – 2.8
melting
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Tg
meltingLiquid
Structurally the difference between glasses and liquids becomes evident
if we consider broken bonds!
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Type of Glass Major Structural Components Comments
Alkali
Borosilicate
(SiO4)-4, (BO4)-5,
(BO3)-3 and some
(AlO4)-5 and (FeO4)-
5 structural units to
which alkali,
alkaline earth, and
waste species
bond.
Atomic structure of a French nuclear
waste glass: unshaded region shows
formation of a (Na,Cs)2MoO4 cluster.
Ease of processing, melt
temperatures 1150-
1200°C to minimize
volatility; cold cap
production if feasible
minimizes volatility; most
waste cations highly
soluble in glass; overall
waste solubility 25-40
wt%; made by Joule
Heated Melting (JHM),
Advanced JHM known as
AJHM, Cold Crucible
Induction Melting (CCIM)
or Hot Isostatic Pressing
(HIP).
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Alkali Alumino-
phosphate
(PO4)-3and (AlO4)-5
structural units to
which alkali, alkaline
earth, and waste
species bond
Atomic structure of phosphate glass with P4O10 cage
like structures which provides the basic building
block for phosphate glass formers. Melts at lower temperatures
than silicate or borosilicate
systems; most cations readily
incorporated; accommodates
>10 wt% sulfate; corrosive to
materials of construction;
tendency to devitrify;
durability comparable to
borosilicate glass if alumina
content is sufficient;
composition ~ 24-27 Na2O,
20-24, Al2O3 + MemOn, 50-52
P2O5 where MemOn is an
actinide or rare earth oxide;
JHM, AJHM, CCIM.
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February
1987February
1988January
1991January
1997June
2001January
2006December
2006August
2010December
2016 2022 …
1 000 m3 HLW 11 500 m3 HLW 8 000 m3 HLW 8 100 m3 HLW
4 MCi 282 MCi 175 MCi 182 Mci
EP-500/2
EP-500/1-р
EP-500/3
EP-500/4
EP-500/5
NEW
Vitrification
Complex
Operating
Under
development
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Aluminosilicate
glasses
and/or
alkali
aluminosilicate
glasses
(SiO4)-4 and (AlO4)-5
structural units to
which alkali,
alkaline earth, and
waste species bond
– (similar structure
to borosilicate
glasses when (BO4) -
5 are present)
Atomic structure of a simple generic M2O3(G2O3)2
glass (M is modifying cations, G represents
tetrahedral cations). The shaded regions are the
PR regions. The un-shaded regions represent the
percolation channels or DR regions (from ).
Melt temperature of
~1600°C causes
volatilization of
radionuclides; waste
loading dependent
on rapid cooling, e.g.
20 wt% UO2 if
cooled rapidly while
<10 wt% if cooled
slowly; improved
durability over
borosilicate glass;
CCIM, HIP
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Waste vitrification is attractive because of:
•High capability of glass to immobilise various elements, •Simple production technology adapted from glass production industry,•Small volume of the resulting wasteform, •High chemical durability of glasses in natural environment and •High tolerance of glasses to radiation damage.
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Facility Waste type Melting
process
Operational period Performance
R7/T7, La Hague, France HLW IHC1 1989/1992 6555 tonnes in 16885 canisters, 262106 TBq to 2012
AVM, Marcoule, France HLW IHC 1978 – 2012 1357 tonnes in 3306 canisters, 22106 TBq to 2012
R7, La Hague, France HLW CCM2 2010 – GCM: U-Mo glass
76 tonnes in 190 canisters to 2012
WVP, Sellafield, UK HLW IHC 1990 – 2200 tonnes in 5615 canisters, 33106 TBq to 2012
DWPF, Savannah River, USA HLW JHCM3 1996 – 6300 tonnes in 3591 canisters,
1.8106 TBq to 2012
WVDP, West Valley, USA HLW JHCM 1996 – 2002 570 tonnes in 570 canisters,
0.9106 TBq
EP-500, Mayak, Russia HLW JHCM 1987 – 6200 tonnes, 643 106 Ci
CCM, Mayak, Russia HLW CCM Pilot plant 18 kg/h by phosphate glass
Pamela, Mol, Belgium HLW JHCM 1985 – 1991 500 tonnes in 2201 canisters, 0.5106 TBq
Karlsruhe, Germany HLW JHCM 2009 – 2010 55 tonnes in 140 canisters,
0.8106 TBq
Tokai, Japan HLW JHCM 1995 – 70 tonnes in 241 canisters (110 L), 0.4106 Ci to 2007
Radon, Russia LILW JHCM 1987-1998 10 tonnes
Radon, Russia LILW CCM 1999 > 30 tonnes
Radon, Russia ILW SSV4 2001 – 2002 10 kg/h, incinerator ash
Bohunice, Slovakia HLW IHC 1997 – 1.53 m3 in 211 canisters
WIP, Trombay, India HLW IHPTM5 1985-2002, 2002 – 18 tonnes, 110103 Ci to 2012
AVS, Tarapur, India HLW IHPTM 2006 – 10 tonnes in 100 canisters, 0.15106 TBq
WIP, Kalpakkam, India HLW JHCM Testing
WTP, Hanford, USA LLW JHCM 1998 – 1000 tonnes to 2000
VPC, SEPEC Site, China HLW JHCM Testing
Taejon, Korea LILW CCM Testing
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• Radiation durability of glass is very high and is above orders of GGy.
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II-B. Ceramics
B.E. Burakov, M.I Ojovan, W.E. Lee. Crystalline Materials for Actinide Immobilisation, Imperial College Press, London, 198 pp. (2010).
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In Australia the ‘SyMo’ Facility (Synroc-Molybdenum) will operate a world first process line utilising a fully integrated HIP based technology; https://www.neimagazine.com/news/newsansto-to-complete-new-mo-99-waste-facility-in-2020-7156356
Wet
mixerDryer Calciner
Liquid
waste
HIP can
evacuation
& sealing
HIP
CAN PROCESSING
Powder
filling
POWDER PROCESSING
Waste
form
additives
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Zone I Zone II
Zone III
©
G Triani, R.L. Holmes, D.T. Chavara, E.R. Vance, M Smith, A Abboud, B Bigrigg, N Scales, D.J. Gregg. Synroc Waste Treatment Plant for fission-based Molybdenum-99 Production. Report presented at MRS Symposium on Scientific Bases for Nuclear Waste Management. Sydney 2017.
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See: https://mo99.ne.anl.gov/2018/pdfs/presentations/S8-P1.pdfhttps://mo99.ne.anl.gov/documents/Feasibility_Review_Report030914.pdf
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21 versus
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1 2II-C. GCM’s
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Glass composite materials (GCM’s) are used to immobilise glass-immiscible waste components such as sulphates, chlorides, molybdates and refractory materials requiring unacceptably high melting temperatures. GCM’s comprise both vitreous and crystalline components.
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GCM via Self-Sustaining Vitrification
Waste
PMF+
Additives
Contaminants
Cold mixing
Waste
Form
SSV produces Waste Forms without external power supply
ensuring minimisation of emission of contaminants (carry
over).
MelterEnergy Supply
Complex off gas purification
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Waste + PMF (+Additives) → Wasteform + Heat
Waste: a mixture of metal oxides including
contaminants.
PMF: a specially designed blend of heat
generating components.
Additives can be required to enhance the
efficiency of process and to obtain a high quality wasteform
Suitable PMF composition ensures an efficient immobilising process and a qualitative wasteform.
Wasteform
Waste + PMF
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The waste should be:
1. In a powder form to enable good mixing with PMF; 2. Dry enough to avoid release of large amounts of gas on
melting.
Examples: Ashes produced by incinerating hazardous (toxic and radioactive)
waste, Soils contaminated both by heavy metals and radionuclides,Spent inorganic ion-exchangers.
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Thermodynamic simulation is applied to design PMF and model immobilisation process.
These result in determining the appropriate PMF composition and PMF/waste ratio.
Equilibrium temperatures in a composition of ash and PMF.
K2.88Ca1.70Al3.37Si10.5
2Fe1.63Mn2.87 O11.50
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Self-sustaining immobilisation was performed for waste to PMF ratios of 0.82 – 1.50. Double wall crucible-containers made of carbon steel of 3, 5 and 10 dm3 volumes were used.
1-carbon steel drum, 2-refractory backfill, 3-waste+PMF mixture, 4-lid.
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Container ready for ignition.
Propagation velocity of the combustion wave is about 1 mm/s.
SSV Process.
Initiating ofthe process
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0
200
400
600
800
1000
1200
1400
1600
1800
0 10 20 30
t, min
T,
°C
50%
56%
60%
Thermograms of self-sustaining vitrification. Left for ash residue for PMF/ash wt. ratios as 1 - 50/50, 2 - 44/56, 3 - 40/60.
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Ash Soil
Clinoptilolite
MP
MP
MP
SEM SEM
SEM
GCM’S
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Evidence of high temperature interaction between components of the PMF
1– soil 45 %, 2– 50 %, 3– 56 %
С– corundum, К– calcilite,L- leicite , S– sillimanite, N–nagelshmidtite, Q– quartz.
4– clinoptilolite 50 %, 5–55 %,
6 – ash residue 60 %,7 –56 %, 8 –50 %.
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Additives were found to incorporate long-lived isotopes of carbon, uranium, plutonium (actinides) in the target crystalline phases
(e.g. carbides, zirconolite, zirconia).
Waste + PMF +Additives → Waste Form + Heat
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GCM OBTAINED VIA SINTERING
Microstructural Analysis•Scanning Electron Microscopy (SEM)
and Energy Dispersive X-Ray
Spectroscopy (EDS) analysis.
Impregnation of Cs on natural
clinoptilolite and characterisation•DTA, XRD and ICP-AES analysis
Host Borosilicate Glass melting and
Characterisation•DTA, XRD and ICP-AES analysis
Sintering of pellets • Sintered at 750oC for 2 hours with 2oC/min heating and cooling rate.
• Both Cs-Clino and glass size<75m.
• 13mm diameter pellet using 78.3 Mpa.
• Glass to Cs-clino ranging from 1:1 up to 1:10 glass to Cs-clino vol. ratio
Leaching Test•Based on ASTM C1220-98 standard.
• In deionized water, at 40oC for 7 days.
• surface area to volume ratio
(S/V)=10.0m-1.
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Glass:Cs-clino volume ratio
(Waste loading, mass %)
Phases
1:1(37%) Glass,Wollastonite, Clinoptilolite
1:2(58%) Glass, Wollastonite, Sodalite, Clinoptilolite, CsCl
1:4(73%) Glass, Wollastonite, Sodalite, Clinoptilolite, CsCl
1:5(80%) Glass,Clinoptilolite
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•Up to waste loading ~73% mass
microstructure of the GCM ensures
complete encapsulation of clinoptilolite
particles and NRCs of the GCM below
6.35·10-6g/cm2day.
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III. Radiation effects
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1016 -decays/g
2 1017 -decays/g 5 1017 -decays/g
22 1017 -decays/g 51 1017 -decays/g
I. Zircon (Zr0.977Pu0.023)SiO4 containing 2.4 wt.% 238Pu
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II. Pu-monazite, PuPO4
containing 7.2 wt. % 238Pu
is very unstable under self-irradiation.
Strong swelling was seen and even breaking into separate pieces.
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Mechanical destruction: Is that a result of alpha-decay?What is the mechanism of aerosol/colloid formation ?
Single crystals Eu-monazite, (Eu0.937Pu0.063)PO4 with4.9 wt.% 238Pu.
7 years after synthesis at accumulated dose 52∙1017 -decay/g
M.I. Ojovan, B.E. Burakov, W.E. Lee. Radiation-induced Microcrystal Shape Change as a Mechanism of Wasteform Degradation. Journal of Nuclear Materials 501C (2018) 162-171.
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Irradiation
K. Zheng et.al., Nature Communications, 1:24, 1 (2011).
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Irradiation
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Phase separation, bubble formation in nuclear glasses …
➢ Modification of the glass viscosity
o Very high dose rate (10
orders of magnitude higher
than expected in HLW glass)
o Bond Breaking
Favors oxygen bubbles and phase
separation
(T) viscosity of an non-irradiated material, αe efficiency of electron beam bond breaking and annihilation Αe Ie dimensionless electron flux density
Ojovan, Mater. Res. Soc. Symp. Proc. Vol. 1193 (2009)
MÖbus, JNM 396 (2010)
STABILITY OF THE METASTABLE GLASSY STATE
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References:1. An Introduction to Nuclear Waste Immobilisation, M.I.
Ojovan, W.E. Lee, S.N. Kalmykov. Elsevier, Amsterdam, 3rd
Edition (2019). 2. Waste Immobilisation in Glass and Ceramic Based Hosts.
I.W. Donald Wiley, Chichester (2010).3. Crystalline Materials for Actinide Immobilisation, B.E.
Burakov, M.I Ojovan, W.E. Lee. Imperial College Press, London (2010).
4. New Developments in Glassy Nuclear Wasteforms. M.I. Ojovan, W.E. Lee. Nova Science Publishers, New York, 131p. (2007).
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