Filtered generated 374 hits.
-
In case of an alarm from Ringhals nuclear power plant – What you need to know
SSM English...
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 -
2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents
In this report, simple hydrodynamic models are used for studying the effects of coolant inertia on fuel-to-coolant heat transfer and coolant flow under reactivity initiated accidents in light water reactors. The objective is to assess if the inertia effects are important enough to warrant modification of QT-COOL, a coolant channel module for two-phase flow that has recently been implemented as...
Content type: Publications -
2020:13 Core data Research at Uppsala University
SSM perspective Background This project is to support a research group at Uppsala University in the research field of nuclear data for applications. Nuclear data research is about measuring microscopic cross-sections and developing theoretical nuclear models to create evaluated nuclear data libraries. These nuclear data libraries are used in different applications such as, nuclear technology,...
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 -
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 -
2017:11 Extended Common Load Model: A tool for dependent failure modelling in highly redundant structures
Background The treatment of dependent failures is one of the most controversial subjects in reliability and risk analyses. The difficulties are specially underlined in the case of highly redundant systems, when the number of redundant components or trains exceeds four. The Common Load Model (CLM), originally defined in the 70’ies, differs from other CCF models, as it relies on a specific...
Content type: Publications -
2008:18 Concerns when designing a safeguards approach for the back-end of the Swedish nuclear fuel cycle
Sweden has for many years collected the spent nuclear fuel originating from nuclear power plants. This fuel must at all times be kept under supervision to render a diversion impossible; this is of course due to the possibility to make weapons from the material. One idea is to keep the nuclear material in a repository deep under the ground; this is not only to keep the material safe from theft...
Content type: Publications -
2014:56 Seismic design and analysis of safety-related nuclear structures in Sweden
The report presents the historical development of the seismic design for the U.S., France and Sweden with special focus on issues related to severe earthquakes beyond the design basis as well as important aspects concerning the design basis ground motions for the Swedish nuclear facilities. The report provides recommendations on a revised model for seismic hazard assessments, on minimum...
Content type: Publications -
2014:19 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 5, 6 and 7
The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...
Content type: Publications