Search

Filtered generated 754 hits.

Sort on:

Relevance Date
  • 2015:18 Uranium Aerosol Characteristics at a Nuclear Fuel Manufacturing Site - Particle Size, Morphology and Chemical Composition

    Vid alla kärntekniska verksamheter krävs att strålningsmiljön kontrolleras dels genom mätningar av ytors- och luftens kontamination i anläggningen och dels med persondosimetriverksamhet inkluderat helkroppsmätning. De olika metoder som används för att beräkna intecknad effektiv stråldos från kontinuerligt intag via inandning är förknippade...

    Content type: Publications
  • 2017:12 Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik

    Background Loss of Coolant Accidents (LOCA) are among the most demanding accidents that can happen in a Light Water Reactor (LWR). The lack of cooling and the drop in pressure impose large stresses on the nuclear fuel which would increase the risk of fuel rod damage and the subsequent release of active material. But LOCA is also an accident that the nuclear power plant is designed to...

    Content type: Publications
  • 2017:32 COMRAD – Comprehensive investigation of the performance of computed and digital radiography

    Background Within the industry, there has long been a need to replace the traditional X-ray film and its handling. These both for economic and environmental considerations. Both computed radiography and digital radiography offer many advantages over the traditional use of x-ray with film. However, the transition from film-based radiography requires in-depth knowledge of the relationship...

    Content type: Publications
  • 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...

    Content type: Publications
  • 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...

    Content type: Publications
  • 00:56 The Application of State-Level Integration of Safeguards in Sweden. Final Report

    Göran Dahlin, Eric Häggblom, Mats Larsson, Ingegärd Rehn, Swedish Nuclear Power Inspectorate, SE-106 58 Stockholm, Sweden. December 2000 SKI English...

    Content type: Publications
  • 2004:16e Statement of the Situation Concerning Safety and Radiation Protection at Swedish Nuclear Plants in 2003

    The safety philosophy upon which the Swedish Nuclear Power Inspectorate’s (SKI) supervisory and regulatory activities are based assumes that multiple physical barriers will exist and that a plant-specific defence-in-depth system will be implemented at each plant. The physical barriers are situated between the radioactive material and the plant personnel and surroundings. In the case of...

    Content type: Publications
  • 2005:32e Safety and Radiation Protection at Swedish Nuclear Power Plants 2004

    The safety philosophy upon which the Swedish Nuclear Power Inspectorate’s (SKI) supervisory and regulatory activities are based assume that multiple physical barriers will exist and that a plant-specific defence-in-depth approach will be implemented at each plant. The physical barriers are situated between the radioactive material and the plant personnel and surroundings. In the case of...

    Content type: Publications
  • 2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)

    Although the extent of cracking was rather surprising for a bolt-loaded specimen, the average stress corrosion crack growth rate of 0.5 mm/year over the five-year testing period does not represent an immediate concern. The overwhelming part of crack growth can have occurred during a 20 day chloride transient during the third year of exposure because of a condenser leakage after an outage. The...

    Content type: Publications
  • 2012:70 Process Parameters Affecting Inhomogeneity of Material Microstructure

    There’s been a tremendous change in the number, product types, locations, equipment, and manufacturing capabilities of stainless steel producers from the late 1960’s to present. This reconfiguration of the global steel industry occurred between the early 1970’s to the mid 1980’s and continues today. These changes have produced a loss in manufacturing flexibility, due to the inherent...

    Content type: Publications