Din avgränsning ger 1343 träffar.
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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...
Innehållstyp: Publikationer -
2017:16 Stress intensity factor solutions for circumferential cracks in cylindrical bars under axisymmetric loading and global bending
Background The case of a circumferential crack in a cylindrical bar has not been available in the ProSACC code. The need for such a geometry, especially considering nonlinear axisymmetric loading and global bending, has motivated the development of new stress intensity factor solutions, also known as K-solutions. These new K-solutions will be available in ISAAC, the successor to ProSACC.
Innehållstyp: Publikationer -
2021:01 In situ NMR condition monitoring of cable insulations in Nuclear Power Plants
SSM perspective Background As the nuclear power plants are ageing, it is important to verify that every component installed can function safely in the intended environment. Cables are among the most common components in a nuclear power plant and are required to function during normal operation as well as in the event of an accident. There is a need within the nuclear industry for...
Innehållstyp: Publikationer -
2017:36 Topical Peer Review 2017 Ageing Management Swedish National Assessment Report
Executive summary The European Union’s Nuclear Safety Directive 2014/87/EURATOM (NSD) requires the member states to undertake topical peer reviews (TPR) every 6 years with the first starting in 2017. The member states, acting through the European Nuclear Safety Regulators Group (ENSREG), have decided that the topic for the first topical peer review is ageing management. The Swedish Radiation...
Innehållstyp: Publikationer -
2022:15 Strukturer och ledarskap för organisatorisk funktionalitet som främjar säkerheten genom ett kärnkraftverks olika faser och övergångarna däremellan
SSM perspektiv Bakgrund Kärnkraftsindustrin står inför en rad utmaningar framöver, exempelvis avseende åldrande reaktorer, generationsskifte i personalstyrkan, bristande kompetensåterväxt, politiska beslut och konkurrens från andra energislag. Två svenska anläggningar står dessutom inför utmaningen att avveckla delar av verksamheten samtidigt...
Innehållstyp: Publikationer -
2021:07 Scenariourval i HFE-processen Arbetssätt och kriterier vid utvärdering av konstruktionens anpassning till människans förmåga
SSM perspektiv Bakgrund På en kärnteknisk anläggning genomförs under dess livstid så kallade anläggningsändringar i syfte att åtgärda identifierade brister, eller för att av andra skäl modernisera eller förbättra anläggningens konstruktion. Vid anläggningsändringar som påverkar arbetsuppgifter som har betydelse...
Innehållstyp: Publikationer -
2021:14 Reliability, Feasibility and Significance of Measurements of Conductivity and Transmissivity of the Rock Mass for the Understanding of the Evolution of a Repository of Radioactive Waste
SSM perspective Background The conducted research was part of the international research project DECOVALEX 2019 (DEvelopment of COupled models and their VALidation against EXperiments). DECOVALEX 2019 consisted of seven different research projects called Task A to G. SSM were involved in Task G, which were composed of three different teams from Technical University of Liberec (TUL), Seoul...
Innehållstyp: Publikationer -
2022:03 Effect of Neutron Irradiation on the Oxidation and Corrosion of Austenitic Stainless Steels
SSM perspective Background Reactor pressure vessel internal components of austenitic stainless steel located close to the core are subject to a high neutron flux. Irradiation by fast neutrons induces changes in the material that affect microstructure, mechanical properties and microchemistry. These changes eventually lead to an increased susceptibility to irradiation assisted stress corrosion...
Innehållstyp: Publikationer -
2017:09 Evaluation of the Swedish participation in the Nordic Nuclear Safety Research (NKS) collaboration
Background NKS is a Nordic collaboration promoting cooperation on nuclear safety and emergency preparedness research. The research program is primarily funded by Nordic radiation safety authorities and responsible ministries. The main purpose of NKS is to finance joint Nordic activities and initiatives, including seminars and workshops, technical reports, exercises and scientific articles.
Innehållstyp: Publikationer -
2017:05 Robust structural verification of pressurized nuclear components subjected to ratcheting, part two – stress-strain curves for cyclic elastoplastic analysis.
Background Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material...
Innehållstyp: Publikationer