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2019:14 IAEA Safeguards: Staying Ahead of the Game
SSM perspective Background The Swedish Radiation Safety Authority (SSM) called for research proposals relating to non-proliferation. This call resulted in SSM accepting a proposal from the Vienna Center for Disarmament and Non-Proliferation (VCDNP) on “Improving IAEA Safeguards for Non-Proliferation and Disarmament: Assessing the Options for, and Feasibility of, Further Strengthening...
Content type: Publications -
2019:04 Dosimetry in environments surrounding a laser-plasma accelerator
SSM perspective Background Modern laser technology makes it possible to generate ultrashort pulses with a very high peak power. At the Lund Laser Centre, a high-power laser facility in Lund, Sweden, laser pulses having a duration of approximately 30 femtoseconds are generated with a maximum peak power of up to 40 terawatts. When these pulses are focused, extreme light intensity is achieved.
Content type: Publications -
2019:07 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Decommissioning of the Barsebäck nuclear power plant in Sweden.
Content type: Publications -
2019:09 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Decommissioning of the nuclear reactor Ågesta in Sweden.
Content type: Publications -
2008:11 Discrete-Feature Modelling of Groundwater Flow and Solute Transport for SR-Can Review
Review External review contribution in support of SKI's and SSI's review of SR-Can. The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for...
Content type: Publications -
2008:08 Review of SKB:s Work on Coupled THM Processes Within SR-Can External review contribution in support of SKI:s and SSI:s
The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety...
Content type: Publications -
2008:48E Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Co´s (SKB) RD&D Programme 2007
The review of the RD&D Programmes (Research, Development, Demonstration) prepared by the Swedish Nuclear Fuel and Waste Management Co (SKB) is a recurrent task that the Swedish Nuclear Power Inspectorate (SKI) must carry out as a regulatory authority with the support of reviewing bodies of which the most important is the Swedish Radiation Protection Authority (SSI). The review statement for...
Content type: Publications -
2008:47 Selected Models for Key Processes in a Nuclear Waste Repository
The conceptual design of the disposal of spent nuclear fuel in Sweden is based on a multibarrier system. In the KBS-3 concept, the bentonite buffer is a barrier with the primary purpose of surrounding and protecting the canister. The bentonite buffer is expected to prevent or minimise the water exchange with the surrounding rock and protect the canister against mechanical damages caused by...
Content type: Publications -
2019:24 SSM's external experts' review of SKB's analysis of long-term safety of 1BMA (SFR)
SSM perspective Background Fractures in the concrete barrier of the rock vault 1BMA in the final repository for low and intermediate level waste (SFR) have been observed. The Swedish Radiation Safety Authority (SSM) enforced Swedish Nuclear Fuel and Waste Management Company (SKB) to assess the long-term radiological consequences of 1BMA (SSM2015-2432-26) given the present state of the rock...
Content type: Publications -
2007:30 Modelling the Interaction of Low pH Cements and Bentonite
Concrete and cement are used in constructions as well as in conditioning of waste inrepositories for radioactive waste. It is well known that in the hyperalkaline conditions (pH > 12) of standard cement pore fluids, there is potential for deleterious effects upon the host rock and other EBS materials, notably bentonite, in geological repositories. Low pH cements are beginning to be considered...
Content type: Publications