Din avgränsning ger 335 träffar.
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2009:12 Evaluating safety-critical organizations – emphasis on the nuclear industry
The regulator identified a few years ago a need for a better understanding of and a deeper knowledge on methods for evaluating safety critical organisations. There is a need for solid assessment methods in the process of management of organisational changes as well as in continuously performed assessment of organisations such as nuclear power plants. A considerable body of literature exists...
Innehållstyp: Publikationer -
1996:70 Risks from Nuclear Waste
The first part of this review discusses the importance of risk. Man seems to have a longing for risks, like a part of the human nature. If risks are missing, they have to be invented, as needed parts in the emotional attraction of sports, amusement parks, traveling, etc.; this is the emotional part of risk. There is also a rational part of risk, in selecting such objects in ordinary life big...
Innehållstyp: Publikationer -
2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures
The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...
Innehållstyp: Publikationer -
2018:25 UO2 fuel oxidation and fission gas release
Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that has been the main question of several research projects is the fragmentation of fuel pellets during abnormal heat up. In this project the oxidation of UO2 is scrutinized and its effect on pellet fragmentation, fission gas release and damage of fuel rods has been...
Innehållstyp: Publikationer -
2013:25 Anpassning av utbildning till följd av anläggningsförändringar
Studien baseras på dokumentstudier och intervjuer av personer inom kärnkraftindustrin men även med motsvarande roller inom flyg, petrokemi och massaindustri. De intervjuade har nyckelroller inom simulatorträningen i respektive industri. Inom kärnkraften har personer från ett verk samt från verkens gemensamma utbildningsorganisation intervjuats. De undersökta...
Innehållstyp: Publikationer -
2013:29 Regulatory Approaches in Nuclear Power Supervision
The objective of this follow-up study was to support SSM in further understanding regulatory approaches and how they can be combined as part of effective strategies. The survey was intended to assist SSM in identifying current standards, experiences, and practices in the regulation of nuclear power plants. The results will also be valuable for the participating authorities as well as other...
Innehållstyp: Publikationer -
2014:13 Förutsättningar för att upprätthålla och utveckla en välfungerande verksamhet kring erfarenhetsåterföring
Studien har bland annat omfattat att utreda eventuella hinder för tillståndshavarna att upprätthålla och utveckla en effektiv verksamhet kring erfarenhetsåterföring. Studien visade att de största hindren inom de studerade kärnkraftverken ligger i tids- och resursbrist samt i avsaknad av systemstöd och metoder för utvärdering. Processerna förefaller...
Innehållstyp: Publikationer -
2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models
In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...
Innehållstyp: Publikationer