Publikationer

Din avgränsning ger 14 träffar.

• 2015:50 Assessment of structures subject to concrete pathologies (ASCET)

  Many Nuclear Power Plants around the world are at the moment approaching, or in, their Long Term Operation stage of their operational phase. In addition, several NPPs have recently been carrying out uprate and life extension projects and comprehensive maintenance work including the exchange of components important to safety, in order to extend their lifetime. As a result, ageing management...

  Innehållstyp: Publikationer

• 2015:54 Retinal injuries from handheld lasers: An updated report

  Jörgen Thaung, Cesar Lopes and Stefan Löfgren SSM English...

  Innehållstyp: Publikationer

• 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

  Ali R. Massih, Lars Olof Jernkvist SSM English...

  Innehållstyp: Publikationer

• 2015:43 Robust structural verification of pressurized nuclear components subjected to ratcheting

  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

• 2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load

  Haverifall med kylmedelsförlust (LOCA) i lättvattenreaktorer kan leda till överhettning av bränslestavar, utvidgning av stavarnas kapslingsrör, samt axiell omflyttning av bränslekutsfragment i de delar av stavarna som expanderat. Bränsleomflyttningen kan koncentrera värmebelastningen till en begränsad del av stavarna och därigenom öka risken...

  Innehållstyp: Publikationer

• 2015:38 Evaluation of fatigue in austenitic stainless steel pipe components

  Background Transferability of experimental results obtained for smooth test specimens under constant amplitude loading to realistic components subjected to variable amplitude loading is an important issue in the design against fatigue. There is a lack of experimental fatigue data for austenitic steel components and the present study is an important contribution to fill this gap. Objective The...

  Innehållstyp: Publikationer

• 2015:25 Design Guide for Nuclear Civil Structures (DNB)

  The Swedish Radiation Safety Authority (SSM) and the Swedish licensees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as SSM Report 2014:06. To further improve DNB and to ensure that the fundamentals of the recommendations will be applied...

  Innehållstyp: Publikationer

• 2015:20 The effects of mild, acute hypoxia on cognitive performance

  Room air with reduced oxygen levels that prevent materials to ignite and combust is a cost-effective and increasingly popular fire prevention method. For system safety reasons, the effects of hypoxia, that is, the lack of sufficient oxygen (that is, less than 21% oxygen which is the approximate oxygen level of normal air), on cognitive performance of persons working under such conditions...

  Innehållstyp: Publikationer

• 2015:07 TEM-lamella lift-out from the crack tip region of Alloy 600 for high resolution electron microscopy examination

  This report contributes to the development of a method for high-quality TEM lamella preparation from crack tip regions of nuclear materials. A standard compact tension (CT) specimen of Alloy 600 previously tested for stress corrosion crack growth in simulated PWR primary water was used to demonstrate the benefit of the proposed method. This report describes the procedure for cutting the CT...

  Innehållstyp: Publikationer

• 2015:09 PROSIR - Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel

  Following an OCDE round robin proposal, 16 participants from 9 countries (USA, Japan, Korea (6 participants), Sweden, Germany, Czech Republic, Spain, EC and France (3 participants)) have been involved in a round robin study called PROSIR, Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel. The PROSIR project started already in 2003 and a final draft version of the main report...

  Innehållstyp: Publikationer