Nuclear Research Institute Řež plc Ústav jaderného výzkumu Řež a.s. 1 Development of waste...
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Transcript of Nuclear Research Institute Řež plc Ústav jaderného výzkumu Řež a.s. 1 Development of waste...
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Nuclear Research Institute Řež plc
Ústav jaderného výzkumu Řež a.s.
Development of waste matrices for immobilization of problematic waste from Czech nuclear power
plants
RCM on CRP „Behaviour of Cementitious Materials in Multipurpose Packaging for
Transportation, Long Term Storage and Disposal
Bucharest, 24– 28 November 2008
Petr Večerník, Monika Kiselová, Antonín Vokál
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Nuclear Research Institute Řež plc
Main objectives of the project
1) Optimalization of cement composition and testing of new matrices for immobilization of ion-exchange resins, sludge and oils from Czech Nuclear Power Plants Dukovany and Temelín
2) Understanding of leaching mechanisms from cement matrices to be able to get data for advanced performance assessment codes and waste acceptance criteria (WAC) derivation
3) Starting activities for research of cementitious materials for Deep Geological Repository
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Nuclear Research Institute Řež plc
Main streams of problematic waste in Czech NPPs
Wet Ion-exchangers Sludge (often mixed with
ion-exchange resins) Oils
Solid Waste exceeding limits
for near-surface repositories – stored DGR
Dukovany near surface respository
Planned Deep Geological Repository
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Nuclear Research Institute Řež plc
Waste Acceptance Criteria for Dukovany repository
Leaching resistance of waste forms with activity higher than 2 x 107 Bq
4 % after 48 hours (test RAWRA K001b)
Compressive strength Cement – 5 MPa Geopolymer – 10 MPa
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Nuclear Research Institute Řež plc
Model waste
Organic spent ion-exchangers simulated by saturation of new ion-exchange resins (Purolite A-400 MB OH and Purolite C-100 H) Ion-exchangers were saturated from 90 % and the ratio of cationic to anionic resins was set to the ratio 2:1.
Samples were doped with Cs-137
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Nuclear Research Institute Řež plc
Cemented samples
Cements Portland cement CEM I
52,5 R Portland cement with
slag CEM II/A –S 42,5 R
Additives Plastificators (Addiment
FM 935) Fillers (silica, ash)
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Nuclear Research Institute Řež plc
Selected procedure
1) Mixing 5 minutes of water with plastificator
2) Mixing 10 minutes cement with filler
3) 28 days curing before testing
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Nuclear Research Institute Řež plc
Cement compositions Commercial cement with slag (CEM II/A-S 42,5 R of Lafarge Company) seems to be the most suitable basic materials both for cementation of spent ion-exchangers and sludge.High amount of silica (> 20 %) and water reducing admixtures (plasticizers) (about 10 %) is needed to achieve required properties, namely to withstand immersion test and to meet compression strength higher then 5 MPa. The total content of water must be less then 30 %
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Nuclear Research Institute Řež plc
volume (ml) weight (g)OPC 42.5 --- 640ionexchanger (48,8% dry mass) --- 642silikol P (powdered) --- 128water 106 106plasticizer FM 935 42 51.2
Composition of mixture for experiments
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Nuclear Research Institute Řež plc
Qualification tests of cement mixtures
Compression strength
(5 MPa cement, 10 MPa geopolymers)
Leaching characteristics (ANSI/ANS 16.1)
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Nuclear Research Institute Řež plc
WAC derivation from PAs
Data obtained from leaching experiments, such as ASNSI/ANS 16.1 are not sufficient for performance assessment purposes and WAC derivation. For advanced transport models following data are needed:
1) Effective diffusion coefficient (De)
2) Sorption coefficients
3) Formation factors
4) Solubility limits
Leaching time
Mixture No. 100
[hours]
D [cm2s-1]
Leaching index
Cumulative leaching [%]
2 2,57E-11 10,59 0,08 7 3,52E-10 9,45 0,50 24 5,22E-10 9,28 1,40 48 6,81E-10 9,17 2,59 72 4,99E-10 9,30 3,73 96 1,70E-10 9,77 4,43 120 1,67E-10 9,78 5,23 456 1,91E-10 9,72 7,73 1128 6,90E-11 10,16 9,83 2160 3,00E-11 10,52 11,55
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Nuclear Research Institute Řež plc
Evaluation methods
Batch sorption experiments
Through diffusion experiments
Electromigration experiments
wfse DFfD
Da – Apparent diffusion coefficient
De – Effective diffusion coefficients
- Porosity
d - Dry density
Kd – Distribution coefficient
Ff– Geometric (tortuosity) factor
fs – available porosity factor
dd
ea K
DD
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Nuclear Research Institute Řež plc
Sorption of 137Cs on cementKD values
0
10
20
30
40
50
0 10 20 30 40 50 60 70time (days)
KD (
ml/
g)
crushed 1:25 crushed 1:10 powdered 1:25 powdered 1:10 pieces 1:10
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Nuclear Research Institute Řež plc
Diffusion experimentsTracers
3H 125I
Through diffusion cell
increasing activity A-A0
0
100
200
300
400
500
0 500 1000 1500 2000 2500time (hours)
Al-
A0 (
cp
s)
Da = 1.2 – 1.6 x 10-11 m2s-1
De = 2.6 – 4.6 x 10-12 m2s-1
DW = 2.4 x 10-9 m2s-1
Experiments with 125I
are still running
3H experiments
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Nuclear Research Institute Řež plc
Electromigration experiments
Through
electromigration
method
(TEM)
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Nuclear Research Institute Řež plc
w
pfF
p – saturated sample conductivity, w – electrolyte conductivity
Electromigration experiments
dxdU
CCN LHe
Electromigratory flux (N): e– ion mobility, U – potential,
CH – high concentration in reservoir, CL – low concentration in reservoir, Cp concentration in pore water
F – Faraday constant, z – charge number
ee
RTD
z F
wfse DFfD
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Nuclear Research Institute Řež plc
Electromigration experiments
Advantages of TEM
-much faster than classical through diffusion method-not limited sample dimensions as in through diffusion
Disadvantages of TEM / be careful of
- possible pH changes due to electrolysis- possible changes of solution composition- possible changes in rock sample
Advantages of TEM
y = 3.277E-08x - 5.148E-06
R2 = 9.709E-01
0.00E+00
1.00E-06
2.00E-06
3.00E-06
4.00E-06
5.00E-06
6.00E-06
7.00E-06
8.00E-06
9.00E-06
1.00E-05
0 100 200 300 400 500
time [min]
Iod
ide
co
nc
en
tra
tio
n [
mo
l/l]
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Nuclear Research Institute Řež plc
Preliminary results for cesiumDa from leaching experiment = 3 x 10-14 m2/s
Da from sorption and diffusion
experiments = 1 x 10-14 m2/s (calculated from equation
De from tricium through diffusion experiments = 3.6 x 10-12 m2/s
Kd = 2 x 10-2 m3/kg
= 0.15
= 2700 kg/m3
dd
ea K
DD
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Nuclear Research Institute Řež plc
Further plans Finish through diffusion and electromigration experiments to acquire data for modelling and to get deeper understanding of transport of radionuclides in cementitios materialsTo start experiments for developing cementitios materials for use in DGR
low pH low water permeability good gas permeability good mechanical properties
To start ageing and permeability measurements of cementitious materials on special prepared equipment