Filtered generated 213 hits.
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2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
Content type: Publications -
2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...
Content type: Publications -
2023:02 Investigation of risk assessment for decommissioning waste to Fortum’s landfill at Norrtorp
Shulan Xu, Ryk Klos SSM English...
Content type: Publications -
2024:01 Stress field modelling of the Forsmark lens – Correlation of stress measurements with stress field simulations
SSM perspective Background and objective Understanding the in-situ stress field in the Forsmark tectonic lens will lay the fundamental basis to characterise the prevailing mechanical and hydraulic behaviour of the rock mass. Only with a good understanding of the geomechanical setting including the stress field an analysis of future rock mass behaviour under the evolution of conditions in a...
Content type: Publications -
2024:13 Technical Note, Review of recent research activities conducted by SKB relating to hydro geological aspects of the disposal of radioactive waste
SSM perspective Background The Swedish Radiation Safety Authority (SSM) examines the Swedish Nuclear Fuel Company’s (SKB) applications in a step-wise review and approval process according to the government’s licence conditions under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a geological disposal facilities. As part of the review, SSM commissions...
Content type: Publications -
2024:09 2024:09 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Expanded operations within Cyclife Sweden AB...
Content type: Publications -
2012:21 Technical Note, Initial Review Phase for SKBs Safety Assessment SR-Site: Corrosion of Copper
The uniform and localized corrosion treatments as well as stress corrosion cracking positions currently considered by SKB have been examined with the objective of identifying key unresolved issues or gaps, needs and opportunities. In conjunction with the review of the SKB reports listed in Appendix 1, there has been some consideration of the broader literature. This summary highlights the...
Content type: Publications -
2012:17 Technical Note, Corrosion of copper canister
It is expected that the inflow of ground water to the deposition holes and tunnels in the Forsmark repository will be very slow. Thus, it might take some few hundred years up to thousand years before the deposition holes are filled with ground water and it might take 6000 years or more before the bentonite buffer is fully water saturated and pressurized. The copper canisters will therefore...
Content type: Publications -
2011:34 Evolution of hydrogen by copper in ultrapure water without dissolved oxygen
One result from this research was that the experimental difficulties of repeating Hultqvist and co-workers work are considerable and were initially underestimated. The main challenge was to obtain satisfactory tightness of all connectors involved in the experimental set-up. The problems with leakage resulted in that the research program originally planned for in this project had to be reduced...
Content type: Publications -
2012:13 Technical Note, A review of the creep ductility of copper for nuclear waste canister application
SKB has presented insufficient evidence to justify their position that the OFP copper has an adequate creep ductility during long term storage. Their large body of experiments only serves to prove that the creep ductility is sufficient for much shorter time spans than the intended storage times. There is a clear need for a credible theory of creep brittleness of OFP copper which will permit...
Content type: Publications