Uranium(VI ) Uptake by Synthetic Calcium Silicate Hydrates Jan Tits - - PowerPoint PPT Presentation

uranium vi uptake by synthetic calcium silicate hydrates
SMART_READER_LITE
LIVE PREVIEW

Uranium(VI ) Uptake by Synthetic Calcium Silicate Hydrates Jan Tits - - PowerPoint PPT Presentation

Laboratory for Waste Management Nuclear Energy and Safety Department Uranium(VI ) Uptake by Synthetic Calcium Silicate Hydrates Jan Tits (1) , N. Mac (1) , M. Eilzer (2) , E. Wieland (1) , G. Geipel (2) Paul Scherrer Institut (1)


slide-1
SLIDE 1

Laboratory for Waste Management Nuclear Energy and Safety Department

Uranium(VI ) Uptake by Synthetic Calcium Silicate Hydrates

Jan Tits(1), N. Macé(1), M. Eilzer(2), E. Wieland(1), G. Geipel(2)

Paul Scherrer Institut(1) Forschungszentrum Dresden - Rossendorf(2) 2nd International Workshop

MECHANISMS AND MODELLING OF WASTE/CEMENT INTERACTIONS

Le Croisic, October 12-16 , 2008

slide-2
SLIDE 2

Laboratory for Waste Management Nuclear Energy and Safety Department

Lay-out

  • Introduction
  • Batch sorption studies:

Sorption isotherms

  • Spectroscopic investigations:

Time-resolved Laser Fluorescence Spectroscopy

  • Conclusions
slide-3
SLIDE 3

Laboratory for Waste Management Nuclear Energy and Safety Department

Safety barrier systems of cementitious repositories

Disposal of Low- and intermediate level radioactive waste

Cementitious materials are used for conditioning of the waste and for the construction of the engineered barrier system

Waste solidification Container: concrete, mortar, steel

Mortar Mortar Construction concrete Shotcrete liner

Deep geological repository

slide-4
SLIDE 4

Laboratory for Waste Management Nuclear Energy and Safety Department

10 10

1

10

2

10

3

10

4

11 12 13 14

Incongruent dissolution

  • f CSH phases

Solution saturated w.r.t Ca(OH)2 (Na,K)OH saturated w.r.t. Ca(OH)2)

Region III Region II Region I

pH Total volume of water per unit mass

  • f anhydrous cement (L kg
  • 1)

C-S-H phases in cement

Fresh cement Altered cement Gypsum Portlandite (40%) Monosulfo– aluminate Ettringite Aluminate Ferrite CSH gels (50)% Monosulfo- aluminate Ettringite Aluminate Ferrite CSH gels Ettringite Ferrite CSH gels CSH gels Silica gel rich in Fe/Al

(Atkinson et al., 1988, Berner, 1990; Adenot & Richet, 1997)

ACW Alkali-free

Calcium Silicate Hydrate (C-S-H) phases play an important role throughout the evolution of cement

slide-5
SLIDE 5

Laboratory for Waste Management Nuclear Energy and Safety Department

Structure of C-S-H phases

Garbev et al., 2008

slide-6
SLIDE 6

Laboratory for Waste Management Nuclear Energy and Safety Department

Recrystallisation of C-S-H phases from 45Ca uptake

[ ]

45 45 recryst.solid sol recryst.solid sol

Ca Ca Ca Ca ⎡ ⎤ ⎣ ⎦ =

Assumption:

slide-7
SLIDE 7

Laboratory for Waste Management Nuclear Energy and Safety Department

N2 atmosphere C:S ratio: 0.5 – 1.60 S:L ratio: 5.0 g/L (batch sorption tests) 1.0 g/L (TRLFS measurements) [U(VI)] added: 10-3 M – 10-7 M Ageing time: 2 weeks Equilibration time: 2 weeks (batch sorption tests) 1 – 14 days (TRLFS measurements) TRLFS / measurements Alpha counting / ICP-OES analysis centrifugation

UO2

2+

ageing supernatant sampling of

Aerosil-300 CaO

H2O ACW equilibration

Batch sorption experiments

Sorption tests Experimental set-up

slide-8
SLIDE 8

Laboratory for Waste Management Nuclear Energy and Safety Department

Batch sorption experiments

Sorption isotherms 10

  • 11 10
  • 10 10
  • 9 10
  • 8 10
  • 7 10
  • 6 10
  • 5 10
  • 4

10

  • 6

10

  • 5

10

  • 4

10

  • 3

10

  • 2

10

  • 1

C:S = 0.75; alkali-free, pH=10.1

C:S = 1.07; alkali-free, pH=12.1

C:S = 1.65; alkali-free, pH=12.5 C:S = 0.74 ACW, pH=13.3 C:S = 1.07 ACW, pH=13.3 C:S = 1.25 ACW, pH=13.3

UO2 (sorbed) [mol kg

  • 1]

UO2 equilibrium concentration [M]

Non-linear sorption: 2-site langmuir isotherm: Site 1: 1.5x10-3 mol/kg; site 2: > 0.6 mol/kg Effect of U(VI) speciation (pH) and C:S ratio (aqueous Ca concentration)

slide-9
SLIDE 9

Laboratory for Waste Management Nuclear Energy and Safety Department

Batch sorption experiments

Sorption isotherms

10

  • 11 10
  • 10

10

  • 9

10

  • 8

10

  • 7

10

  • 6

10

  • 5

10

  • 6

10

  • 5

10

  • 4

10

  • 3

10

  • 2

10

  • 1

10 10

1

Ca; C:S=1.65 Si; C:S=1.65 Ca; C:S=1.07 Si; C:S=1.07 Ca; C:S=0.65 Si; C:S=0.65

Cation equilibrium concentration(M)

UO2+ 2 equilibrium concentration (M)

Alkali-free conditions

10

  • 9

10

  • 8

10

  • 7

10

  • 6

10

  • 5

10

  • 4

10

  • 5

10

  • 4

10

  • 3

10

  • 2

10

  • 1

Ca; C:S = 1.07 Si; C:S = 1.07 Ca; C:S = 0.75 Si; C:S = 0.75

Cation concentration (M)

UO

2+ 2 equilibrium concentration (M)

in ACW

Solution composition is independent of the U(VI) sorption

slide-10
SLIDE 10

Laboratory for Waste Management Nuclear Energy and Safety Department

  • C-S-H phases have a high recrystallisation rate providing
  • pportunities for incorporation (SS formation)
  • U(VI) sorption on C-S-H phases:

– Is non-linear – Depends on the U(VI) aqueous speciation (influence of pH) – Depends on the C-S-H composition (Ca concentration?)

Batch sorption experiments

summary of the observations

Can these observations be described by a solid solution model?

slide-11
SLIDE 11

Laboratory for Waste Management Nuclear Energy and Safety Department

Batch sorption experiments

Requirements to model solid – solutions :

Mixing model: ideal or non-ideal Amount of recrystallized solid

From recrystallisation experiments with 45Ca

End-members and end-member stoichiometries:

C-S-H end-members: (see e.g. presentations of D. Kulik and B.

Lothenbach, S. Churakov,…)

U(VI) containing end-members ??

Indications from spectroscopic investigations (EXAFS, TRLFS,…)

slide-12
SLIDE 12

Laboratory for Waste Management Nuclear Energy and Safety Department

Time Time-

  • resolved laser fluorescence spectroscopy

resolved laser fluorescence spectroscopy of uranyl

  • f uranyl

Fluorescence process Fluorescence process

Vibrational relaxation Fluorescence emission Excitation λ = 266 nm

ligand σμ (axial oxygen 2p orbital)- to-metal δu (5f orbital) charge- transfer

Non-radiative relaxation e.g. via O-H stretch vibrations

ν=1 ν=n ν=2

slide-13
SLIDE 13

Laboratory for Waste Management Nuclear Energy and Safety Department

The position (↓ ), spacing (Δ), relative intensities (Pi/Pi+1) of the vibronic bands, lifetime, are sensitive to geometry of the uranyl and local chemical environment O=U=O axial bond length, RUO: RUO = 10650·[Δ]-2/3+57.5 (Bartlett &

Cooney, 1989)

Uranyl compounds fluoresce above

470 nm with characteristic vibronic progressions originating mainly from the symmetric stretch vibration of the O= U= O moiety (minor contributions from assymetric stretch- and bending vibration)

460 480 500 520 540 560 580 600

Time-resolved laser fluorescence spectroscopy

P6 P5 P4 P3 P2

Luminescence intensity (A.U.) Wavelength (nm)

P1

Δ Δ Δ Δ Δ

Aqueous uranyl 0.001 M Ca(OH)2

slide-14
SLIDE 14

Laboratory for Waste Management Nuclear Energy and Safety Department

Time-resolved laser fluorescence spectroscopy

Comparison of spectra from sorbed and aqueous uranyl species

Increasing red shift (lower energy): Indication of weakening of the axial U= O bond, (lower stretch frequency ) Stronger interaction between U(VI) and the equatorial ligands Change in geometry of uranyl moiety

λex= 266 nm, T= 150 K 480 500 520 540 560 580 600 620

U(VI)-CSH; C:S= 1.07 low loading U(VI) in ACW Free Uranyl in 1 M HClO4 U(VI)-CSH; C:S= 1.07 high loading

Luminescence intensity (A.U.) Wavelength (nm)

Red shift

slide-15
SLIDE 15

Laboratory for Waste Management Nuclear Energy and Safety Department

Time-resolved laser fluorescence spectroscopy

Sorption isotherm

450 480 510 540 570 600 630 Wavelength (nm)

1.0 mol kg

  • 1

0.1 mol kg

  • 1

5x10

  • 2 mol kg
  • 1

10

  • 2 mol kg
  • 1

2x10

  • 3 mol kg
  • 1

10

  • 3 mol kg
  • 1

3x10

  • 4 mol kg
  • 1

10

  • 4 mol kg
  • 1

Fluorescence emission (A.U.)

S:L = 1.0 g L-1; equilibration time = 1 day U(VI) sorbed on CSH at pH 12.0; C:S = 1.07

λex= 266 nm, T= 150 K

U(VI) loading

slide-16
SLIDE 16

Laboratory for Waste Management Nuclear Energy and Safety Department

Time-resolved laser fluorescence spectroscopy

Comparison with spectra of reference compounds

440 480 520 560 600

α α β β

Wavelength (nm)

β α

Luminescence intensity (A.U.)

Room temperature T=150 K

Uranophane α and β

480 500 520 540 560 580 600 620

U(VI )-CSH; C:S= 1.65 alkali-free; all loadings U(VI )-CSH; ACW C:S= 1.07; all loadings Soddyite U(VI )-CSH; C:S= 1.07 alkali-free; low loading Uranophane (α and β) U(VI )-CSH; C:S= 0.75; alkali-free; all loadings

Luminescence intensity (A.U.) Wavelength (nm)

λex= 266 nm, T= 293 K or 150 K

slide-17
SLIDE 17

Laboratory for Waste Management Nuclear Energy and Safety Department

Time-resolved laser fluorescence spectroscopy

Comparison with spectra of reference compounds

Axial U – O distance (Å) XRD EXAFS TRLFS Soddyite K-boltwoodite Uranophane α Uranophane β C-S-H (alkali-free) C-S-H (ACW) 1.78 (Demartin et al. 1983) 1.80 (Burns et al. 1998) 1.80 (Ginderow, et al. 1988) 1.82 (Viswanathan et al. 1986) 1.77(2) 1.80(2) 1.83(2) 1.81(2) 1.80(5)

  • 1.86(5)

1.84(5) 1.9(1) 1.9(1)

TRLFS: RUO = 10650·[Δ] -2/ 3+ 57.5 (Bartlett & Cooney, 1989)

slide-18
SLIDE 18

Laboratory for Waste Management Nuclear Energy and Safety Department

Summary

  • C-S-H phases have a high recrystallisation rate
  • U(VI) sorption onto C-S-H phases is non-linear (at least 2 sorbed species)
  • increases with increasing C:S ratio
  • decreases with increasing pH
  • TRLFS can give indications about possible U(VI) containing end-members:
  • Luminescence spectra of U(VI) sorbed on C-S-H phases are all similar

similar geometry of the uranyl moiety (1 sorbed species)

In contrast to information from batch sorption experiments

  • Geometry of the sorbed uranyl is similar to the uranyl geometry in

α-uranophane (derived from spectral shape and peak position)

  • Uncertainies on axial oxygen distances is still high

(Future experiments at 4 K may improve the quality of this kind of information)

slide-19
SLIDE 19

Laboratory for Waste Management Nuclear Energy and Safety Department

Acknowledgements

Partial financial support was provided by the Swiss National Cooperative for the Disposal

  • f Radioactive Waste (Nagra) and by the European Communities (Actinet and MISUC)

Thank you for your attention