Euradwaste '08 - EU Bookshop - Europa
Euradwaste '08 - EU Bookshop - Europa Euradwaste '08 - EU Bookshop - Europa
Prior to NF-PRO, the question whether the process of solid state � radiation-enhanced diffusion to the release of fission products from spent fuel was unresolved. A synthesis of modelling and experimental data as part of work by NF-PRO has shown that the diffusion process is very slow and therefore will not significantly contribute to the IRF. Under NF-PRO, a new micromechanical model was developed to re-assess the impact of the ingrowth of He on the spent fuel microstructure and radionuclide diffusion processes. Conclusions from this work have shown that He accumulation may result in the formation of bubbles in the fuel matrix. For UOX fuel however, the bubble pressure will remain under the threshold value to crack the fuel. Conclusions from this work have allowed diminishing the conservatism of former IRF values of key safety relevant radionuclides for PWR UOx fuels. Until recently, few data were available on the IRF inventory for high burn up UOx fuel and MOX fuel. NF-PRO has delivered new data on the IRF of spent UOx fuel as a function of the burn-up. These data have reduced conservatism of former IRF values of key safety relevant radionuclides for PWR UOx fuels. Also, estimates of the grain boundary inventory for spent MOX fuel were made by performing leaching experiments on fragmented and powder samples of SBR MOX. NF-PRO has investigated various processes affecting the dissolution of the disposed spent fuel in the presence of near-field materials. The following results are reported: Experimental work has been performed to investigate the dissolution of �-doped UO2 under reducing conditions. Radiolysis effects were shown to be less important for fuel dissolution than previously thought. Indeed, the radiation field of 3000-10000 y old fuel has no effect on the oxidative dissolution of fuel. Isotope dilution tests have indicated that spent fuel corrosion in absence of radiolysis effects is still rate and not solubility controlled. Experiments to investigate the dissolution of UO2 in the presence hydrogen gas confirmed that hydrogen gas is an active reductant that lowers the dissolution of uranium in the presence of Volclay. This is an important result since the inhibiting effect of H2 on the dissolution of the spent fuel matrix confirms that, in the normal evolution scenario, low matrix dissolution rates are applicable as long as H2 is present. Investigation of the effect of trace constituents in groundwater on gamma radiation-induced corrosion of UO2 indicates that low concentrations of bromide in repository groundwater may offset to some degree the protective effect by hydrogen with respect to the release of certain radionuclides. Integration of the work on the Engineered Barrier System (next paragraph) has led to a better understanding at process level of the evolution of glass and spent fuel under near-field repository conditions. More specifically, due to the slow dissolution rate of the overpack, the waste may be protected much longer than previously assumed. This constitutes a non-negligible safety reserve, making the reference source term models more conservative than recognized before the start of NF-PRO. The proposed reference source term models were not fundamentally changed in the project, but the underlying processes are now better understood. 164
4.2 Advances in research related to the chemical evolution of the engineered barrier system The Engineered Barrier System (EBS) isolates the disposed radioactive waste from the geosphere. Diverse processes including the uptake of groundwater, chemical interactions between different near-field components and the formation of secondary phases and corrosion products, influence the confinement properties of the EBS and control radionuclide transport in the near-field. NF-PRO has investigated a range of processes affecting the chemical evolution of the EBS, in particular the evolution of the composition of porewater in the bentonite barrier, concrete-bentonite interactions, the corrosion of metal-based repository components including the interaction of corrosion products with bentonite, and radionuclide mobility in the bentonite barrier. Progress in research related to processes affecting the bentonite porewater composition Clay-based (bentonite) buffer materials are widely applied in repository concepts in granite and clay host rocks. The bentonite buffer will progressively hydrate and act as a low permeability barrier limiting and controlling radionuclide transport. An important part of the work by NF-PRO has been dedicated to the investigation of the porewater chemistry and processes and mechanisms having an impact on the evolution of the bentonite porewater composition. Changes in porewater composition are particularly relevant to evaluate - amongst others - the dissolution of the waste matrix, radionuclide mobility and canister corrosion rates. These compositional changes can be initiated by internal factors, for example by a thermal gradient or by chemical interactions between different repository components, or by external factors, for example changes in the composition of groundwater entering the near-field system from the host rock following alteration of the host rock. NF- PRO has investigated the mechanisms affecting porewater chemistry and radionuclide mobility to evaluate the time-dependent evolution and the overall performance of the near-field system. Eh and pH are key parameters with respect to chemical conditions in the near-field: Eh and pH have major effects on concentrations of aqueous species (for example HS - , HCO3 - and Cl - ), which may affect corrosion of metal-based engineered barriers and/or enhance radionuclide solubility. Until recently, obtaining reliable data on redox conditions in compacted bentonite was very difficult since different laboratory techniques tended to disturb the system and introduce sampling artefacts into the measured data. Major advances have been made by NF-PRO regarding the direct measurement of Eh and pH in compacted bentonite. Electrodes capable of producing accurate measurements of Eh and pH in compacted bentonite were developed and used to assess the response of the bentonite buffer to changes in pH (pH 11.7) and redox potential (aerobic) of contacting external groundwater. Using cells with a total length of 20 mm, oxidising and alkaline perturbations were measured only in the first 5 mm of the cells. pH-values re-established to values around 9 (the initial pH value was equal to ~8.5) in the first cm of the bentonite and the extent of redox pertubations is limited. These experimental observations indicate that redox and pH conditions are buffered very effectively in compacted bentonite. NF-PRO has investigated the interaction between saline porewater and the bentonite buffer. In particular, the amount of water absorbed in different types of bentonite (MX-80 and FEBEX bentonite) was measured as a function of porewater salinity. It was confirmed that the distribution of the water among external and internal (interlamellar) sites depends on the pore water salinity. Results from experimental work indicate that the amount of internal water decreases with increasing salinity. Additional experiments have led to the conclusion that the amount of water absorbed in bentonite depends on the dominant cation in the smectite exchanger. Experimental results with homoionised FEBEX bentonite show that maximum water absorption occurs with magnesium or calcium as the dominant exchangeable cations. Minimum water absorption was observed with potassium as domi- 165
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4.2 Advances in research related to the chemical evolution of the engineered barrier system<br />
The Engineered Barrier System (EBS) isolates the disposed radioactive waste from the geosphere.<br />
Diverse processes including the uptake of groundwater, chemical interactions between different<br />
near-field components and the formation of secondary phases and corrosion products, influence the<br />
confinement properties of the EBS and control radionuclide transport in the near-field. NF-PRO has<br />
investigated a range of processes affecting the chemical evolution of the EBS, in particular the evolution<br />
of the composition of porewater in the bentonite barrier, concrete-bentonite interactions, the<br />
corrosion of metal-based repository components including the interaction of corrosion products<br />
with bentonite, and radionuclide mobility in the bentonite barrier.<br />
Progress in research related to processes affecting the bentonite porewater composition<br />
Clay-based (bentonite) buffer materials are widely applied in repository concepts in granite and<br />
clay host rocks. The bentonite buffer will progressively hydrate and act as a low permeability barrier<br />
limiting and controlling radionuclide transport. An important part of the work by NF-PRO has<br />
been dedicated to the investigation of the porewater chemistry and processes and mechanisms having<br />
an impact on the evolution of the bentonite porewater composition. Changes in porewater composition<br />
are particularly relevant to evaluate - amongst others - the dissolution of the waste matrix,<br />
radionuclide mobility and canister corrosion rates. These compositional changes can be initiated by<br />
internal factors, for example by a thermal gradient or by chemical interactions between different<br />
repository components, or by external factors, for example changes in the composition of groundwater<br />
entering the near-field system from the host rock following alteration of the host rock. NF-<br />
PRO has investigated the mechanisms affecting porewater chemistry and radionuclide mobility to<br />
evaluate the time-dependent evolution and the overall performance of the near-field system.<br />
Eh and pH are key parameters with respect to chemical conditions in the near-field: Eh and pH have<br />
major effects on concentrations of aqueous species (for example HS - , HCO3 - and Cl - ), which may<br />
affect corrosion of metal-based engineered barriers and/or enhance radionuclide solubility. Until<br />
recently, obtaining reliable data on redox conditions in compacted bentonite was very difficult since<br />
different laboratory techniques tended to disturb the system and introduce sampling artefacts into<br />
the measured data. Major advances have been made by NF-PRO regarding the direct measurement<br />
of Eh and pH in compacted bentonite. Electrodes capable of producing accurate measurements of<br />
Eh and pH in compacted bentonite were developed and used to assess the response of the bentonite<br />
buffer to changes in pH (pH 11.7) and redox potential (aerobic) of contacting external groundwater.<br />
Using cells with a total length of 20 mm, oxidising and alkaline perturbations were measured only<br />
in the first 5 mm of the cells. pH-values re-established to values around 9 (the initial pH value was<br />
equal to ~8.5) in the first cm of the bentonite and the extent of redox pertubations is limited. These<br />
experimental observations indicate that redox and pH conditions are buffered very effectively in<br />
compacted bentonite.<br />
NF-PRO has investigated the interaction between saline porewater and the bentonite buffer. In particular,<br />
the amount of water absorbed in different types of bentonite (MX-80 and FEBEX bentonite)<br />
was measured as a function of porewater salinity. It was confirmed that the distribution of the water<br />
among external and internal (interlamellar) sites depends on the pore water salinity. Results from<br />
experimental work indicate that the amount of internal water decreases with increasing salinity.<br />
Additional experiments have led to the conclusion that the amount of water absorbed in bentonite<br />
depends on the dominant cation in the smectite exchanger. Experimental results with homoionised<br />
FEBEX bentonite show that maximum water absorption occurs with magnesium or calcium as the<br />
dominant exchangeable cations. Minimum water absorption was observed with potassium as domi-<br />
165