Filtered generated 131 hits.
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2026:06 A Human Reliability Analysis (HRA) Taxonomy for Small Modular Reactors (SMR) – Part 1 of 2: Mapping the SMR landscape
SSM perspective Background Small Modular Reactors (SMRs) are typically presented as a solution for safe and reliable energy, requiring less time to construct than the traditional large reactors. The inherent safety features, higher levels of automation and increased reliance on passive safety are often held as reasons for fewer operators being needed in the daily operations and for handling...
Content type: Publications -
2025:03 APRI-11 – Final Report
SSM perspective Background The Swedish Radiation Safety Authority together with the Swedish Power companies operating nuclear power reactors in Sweden have since early 1990’s provided financial support for severe accident research at KTH and Chalmers. The research was initiated almost directly after the installation of severe accident management system and strategy, as filtered containment...
Content type: Publications -
2025:01 Safety Concept Evaluation with Failure Tolerance Analysis
SSM perspective Background One of the most important design principles to achieve high safety function dependability is the use of redundancy to be single-fault tolerant. In turn, redundancies become effective by applying additional design principles such as physical and functional separation and diversity. License holders of nuclear power reactors must demonstrate that requirements are met,...
Content type: Publications -
2024:18 Modelling Environmental Sensitization of Chromia Forming Nickel Base Alloys Toward Stress Corrosion Cracking in Light Water Reactors by Atomistic Simulations
SSM perspective Background Stress corrosion cracking (SCC) in load bearing structures has been a longstanding issue both in pressurized and boiling water reactors. The specific environment in nuclear power applications consists of high temperatures and pressures that together with the effects of the radiation field on the coolant composition provide tough conditions for the materials used in...
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 -
2024:14 Residual stress distributions in nickel-based dissimilar metal pipe welds
SSM perspective This report concerns a study which has been conducted for the Swedish Radiation Safety Authority, SSM. The conclusions and viewpoints presented in the report are those of the author/authors and do not necessarily coincide with those of the SSM. Abstract It is common for nickel-base materials to be used as filler metals in the welding of dissimilar metal welds. Dissimilar metal...
Content type: Publications -
2024:10 Computational analysis of high-burnup fuel rod behaviour in PWR large-break LOCA
SSM perspective Background Quantum Technologies AB (QT) has for many years developed computational models for the thermomechanical behaviour of nuclear fuel in events such as LOCA and RIA. The research projects have been based on evaluations of tests on nuclear fuel in Halden Reactor Project (HRP) and Studsvik Cladding Integrity Project (SCIP). The models developed by QT enable analyses and...
Content type: Publications -
2024:06 In search of lost storms: or can one infer the magnitudes of extremely rare flood events from short observational records?
Magnus Hieronymus SSM English...
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