Filtered generated 375 hits.
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2012:38 Technical Note, Radiological effects on non-human biota - initial review
The focus of this review was SKB’s assessment of radiological effects on non-human biota in SR-Site according to present regulations and guidance from SSM and it was conducted by Karolina Stark at the Department of Systems Ecology, Stockholm University. In short, the results from this review show that the completeness of the safety assessment can be questioned regarding considered...
Content type: Publications -
2012:30 Technical Note, Initial review of physical properties and processes of the buffer and backfill. THM and other physical processes
The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information on specific issues. The...
Content type: Publications -
2012:28 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill – Geochemical processes
This report consists of a Technical Note in SSM’s initial review phase of SKB’s safety analysis SR-Site. The aim of the initial review of issues concerning geochemical processes in buffer and backfill in a final repository is to make a broad illustration and review of SR-Site together with its subordinate references, as well as to identify potential needs for complementary information or...
Content type: Publications -
2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock
SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...
Content type: Publications -
2018:24 Structural equation modelling for analysis of human and organizational factors in nuclear power plant control rooms
SSM perspective Background During the supervisory work of the Swedish Radiation Safety Authority (SSM), a need was identified to develop the methods used when evaluating control room work in the central control rooms of nuclear power plants. Benchmarking is commonly used today, with reference values from earlier Integrated System Validation (ISV), when ISV is available. Often, ISV performs...
Content type: Publications -
2018:18 Procedure for Safety Assessment of Components with Defects
Background SSM and the Swedish nuclear power plant owners have financed Kiwa Inspecta Technology in Sweden to develop a new version of the handbook for assessment of defects. This represents a major update of the former fracture mechanics handbook that was published at SSM as Research 2008:01. The procedure in the handbook is based on the British R6-method where the failure mechanisms...
Content type: Publications -
2018:17 Assessment of structures subject to concrete pathologies (ASCET), phase 2
Background ASCET is an international research project initiated by WGIAGE1 OECD2 / NEA3. WGIAGE4 Concrete subgroup is a working group within the OECD / NEA whose task is to address issues concerning the maintenance of the integrity of concrete structures, proposals for general principles to optimally handle the challenges of integrity, especially with regard to aging of concrete structures.
Content type: Publications -
1995:60 Reliability of Piping System Components -Volume 3: A Bibliography of Technical Papers and Reports Related to Piping Reliability
Reflecting on older analysis practices, passive components failures seldom receive explicit treatment in PSA. to expand the usefulness of PSA and to raise the realism in plant and system models the Swedish Nuclear power Inspectorate has undertaken a multi-year research project to establish a comprehensive passive components database, validate failure rate parameter estimates and model...
Content type: Publications -
96:40 Status and Use of PSA in Sweden
The performance and use of PSA:s in Sweden goes back about two decades. During all of this time, the field of PSA has been developing intensively, both internationally and within Sweden. The latest years have been characterised by an increased use of PSA models and results, and by major extensions of existing PSA models. The aim of this document is to describe PSA in Sweden with respect to...
Content type: Publications -
2012:50 Fatigue Margins for Austenitic Stainless Steels in ASME Boiler and Pressure Vessel Code – A Literature Study
Knowledge about the margins against fatigue failure in nuclear piping systems is essential. Therefore, the margins in the ASME Boiler and Pressure Vessel Code (section III) fatigue design procedure for austenitic steels, type 304/316, as applied to real components have been investigated in this literature study. It is concluded that the current knowledge about the margins in ASME for...
Content type: Publications