Filtered generated 375 hits.
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2020:16 Estimates ofJ-integral and COD for circumferential through wall cracks under global bending including the effect of pipe end restraint
SSM perspective Background Leak-before-break (LBB) piping assessments have shown that piping systems can withstand long through-wall cracks before pipe rupture is expected. This is somewhat because pipe ends are restrained. In LBB assessments analyses are often performed for a pipe segment uncoupled from the piping system, as pipe ends are assumed unrestrained. This assumption is conservative...
Content type: Publications -
2020:02 Models for axial gas flow and mixing in LWR fuel rods
SSM perspective Background Fission gases inside a fuel rod plays an important role in the behaviour of the fuel, both during normal operation and during events and accidents. Fission gases are released from inside the fuel pellets to the gap between the pellet and the cladding tube and then flow to the plenum volume at the top of the fuel rod. In high burnup fuel, this axial flow to the...
Content type: Publications -
2020:05 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Decommissioning of the nuclear reactors Ringhals 1 and Ringhals 2 in Sweden...
Content type: Publications -
2022:09 Assessment of modelling approaches for axial gas flow inside LWR fuel rods
SSM perspective Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. The development and administration...
Content type: Publications -
2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2
Background In the design of anchorage equipment in concrete structures the beneficial effects of reinforcement are, in most cases, not considered. The American ASCI 349-06 code opens up for a more detailed analysis where the beneficial impact of reinforcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly described in the code. The...
Content type: Publications -
2022:14 Weld residual stress and strain measurements on a mock-up with single layer strip cladding common in reactor pressure vessels
Summary Residual stress and strain measurements were performed on a mock-up consisting of a 160 mm thick low-alloy ferritic steel plate of type SA-508 Class 3 with a single layer weld deposited strip cladding of austenitic stainless steel E308L. The cladding was manufactured with submerged arc strip welding adapted to a procedure used for reactor pressure vessels in the 1970s. Comprehensive...
Content type: Publications -
2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022
The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...
Content type: Publications -
In case of an alarm from Forsmark's nuclear power plant – What you need to know
SSM English...
Content type: Publications -
Fitness for work certificate – Work involving ionising radiation
You need Adobe Acrobat Reader in order to read and fill out PDF forms. SSM Svenska You need Adobe Acrobat Reader in order to read and fill out PDF forms.
Content type: Publications -
2024:17 Atomistic studies on the adsorption and desorption of radionuclides on fuel crud and system surfaces in Light Water Reactors
SSM perspective Background Radiation safety is of particular concern during power plant maintenance. Radionuclides produced by the neutron bombardment in the core during operation may accumulate on system surfaces such as the filter system or piping and contribute to the radiation field. Some ions that are prone to neutron capture often become trapped in the deposits on the fuel cladding...
Content type: Publications