Din avgränsning ger 427 träffar.
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2011:30 A fatigue analysis including environmental effects for a pipe system in a Swedish BWR
The effect of the environment on fatigue design has been the subject of intense study in USA, Japan and elsewhere. Several reports indicate a potentially large influence of the environment, leading to the proposal of entirely new analysis procedures. SSM has in an earlier project sponsored research to evaluate the technical basis for these proposals, see SSM Research Report 2011:04. In the...
Innehållstyp: Publikationer -
2014:31 Degradering i betong och armering med avseende på bestrålning och korrosion
De primära egenskaperna för betongstrukturer i ett kärnkraftverk är dess strukturella styrka och möjlighet att avskärma joniserande strålning. Skade- och belastningsbilden kan komma att påverkas av genomförda och planerade effekthöjningar samt planerade driftsförlängningar av de svenska reaktorerna. Kunskap om huruvida betongen i kärnkraftverk...
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 -
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 -
2014:21 Effects of additives on uranium dioxide fuel behavior
This report will form a basis for the reviews that SSM does when the license holders applies for use of nuclear fuel with additives. The report is also intended as a reference to the models that Quantum Technologies AB has developed. The report and the models will be a valuable source of information for SSM and other parties when discussing the performance of doped fuel. Ali Massih SSM...
Innehållstyp: Publikationer -
2019:25 Maskulinitet, risk och säkerhet vid ett svenskt kärnkraftverk
SSM perspektiv Bakgrund Likt anställda vid ett järnverk, ett pappersbruk eller en oljeplattform omges även personalen vid ett kärnkraftverk av olika slags risker som hanteras genom ett mer eller mindre lyckosamt säkerhetsarbete. Kärnkraften är en högriskbransch och riskerna för de personer som arbetar inom den har inte enbart med reaktorn och den radioaktiva...
Innehållstyp: Publikationer -
2019:27 Effect of residual stress on ductile fracture at low primary loads – Numerical study
SSM perspective Background Present report is a continuation of earlier work reported in SSM2009:27 regarding an analysis strategy for fracture assessment of defects in ductile material and SSM2011:19 on the influence from residual stresses on crack initiation and ductile crack growth at high primary loads. The Swedish procedure for safety assessment of components with defects is documented in...
Innehållstyp: Publikationer -
2011:06 Reliability Data Handbook for Piping Components in Nordic Nuclear Power Plants – R Book, Phase 2
The Nordic PSA Group (NPSAG) has undertaken to develop a piping reliability parameter handbook for use in risk-informed applications that involve the consideration of structural integrity of piping systems. The scope of the handbook is to establish high quality reliability parameters that account for the Nordic and worldwide service experience with safety-related and non-safety-related piping...
Innehållstyp: Publikationer