Lars Werme

TL;DR: In this paper, an experimental study was conducted to investigate the mode of iron uptake into bentonite and the extent of changes induced in the basic physico-chemical properties of bentonite.

TL;DR: In this article, the results of the joint Japanese (Central Research Institute of Electric Power Industry, CRIEPI, Tokyo), Swiss (National Cooperative for the Storage of Radioactive Waste, NAGRA, Baden), Swedish (Swedish Nuclear Fuel and Waste Management Company, SKB, Stockholm) international "JSS" project on the determination of the chemical durability of the French nuclear waste borosilicate glass, which was completed in 1988, were summarized.

TL;DR: Similarities and differences between uraninite and UO2 in spent nuclear fuel are discussed in detail in this paper, and the behavior of fission product residues during alteration of urane to coffinite in natural fission reactors may aid in estimation of the long-term behavior of F2 from spent fuels under repository disposal conditions.

TL;DR: In this article, the main strategy for high-level radioactive waste disposal in Sweden is to enclose the spent fuel in tightly sealed copper canisters that are embedded in bentonite clay about 500m down in the Swedish bedrock.

TL;DR: In this paper, the electrochemical properties of anaerobic corrosion of carbon steel in artificial Swedish granitic groundwaters were investigated and it was shown that the corrosion rate was unaffected by hydrogen pressures up to 100 atm.