Din avgränsning ger 748 träffar.
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02:4 Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing
The work was finished and reported in Swedish in a limited publication 2000, Ingemansson Rapport H-14061-r-I. As the performed work was regarded to be of more general interest it is published again as a research report by the Swedish Nuclear Power Inspectorate. To be used in the international cooperation in nuclear safety it was also translated into English by the inspectorate, which is this...
Innehållstyp: Publikationer -
2007:02 Strålmiljön i Sverige
Rapporten beskriver, och redovisar resultat från, den strålmiljöövervakning som bedrivits i Sverige sedan 1950-talet. Genomsnittliga doser till befolkningen och till speciella befolkningsgrupper redovisas också. En stor del av övervakningen har rört nedfallet och spridningen i ekosystemen av radioaktiva ämnen från de atmosfäriska kärnvapenproven...
Innehållstyp: Publikationer -
2007:07 Inquiry into the radiological consequences of power uprates at light-water rectors worldwide
In Sweden, most of the nuclear power plants are planning power uprates within the next few years. The Department of Occupational and Medical Exposures at the Swedish Radiation Protection Agency, SSI, has initiated a research project to investigate the radiological implications of power uprates on light-water reactors throughout the world. The project was divided into three tasks: A compilation...
Innehållstyp: Publikationer -
2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository
PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...
Innehållstyp: Publikationer -
2008:05 International Expert Review of SR-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can
In 2006, SKB published a safety assessment (SR-Can) as part of its work to support a licence application for the construction of a final repository for spent nuclear fuel. The report represented the culmination of work conducted by SKB over several years, focusing on the goal of making the licence application in late 2009. Results from the SR-Can project have been documented in several...
Innehållstyp: Publikationer -
2008:01 Myndigheternas granskning av SKB:s preliminära säkerhetsbedömningar för Forsmark och Laxemar
Detta dokument redovisar SKI:s och SSI:s granskning av SKB:s preliminära säkerhetsbedömningar för Forsmark och Laxemar. Myndigheternas syfte med denna granskning är att bedöma om SKB:s inledande platsundersökningar har tillräcklig omfattning, håller tillräckligt hög kvalitet och omfattar de data som behövs för kommande säkerhetsanalyser.
Innehållstyp: Publikationer -
2001:23 Interactions of Severe Accident Researchand Regulatory Positions (ISARRP)
This project, started on April 1, 1999, had the specific objectives of determining whether; (i) the focus of the severe accidents (SA) research is consistent with that of the regulatory authorities, (ii) the results obtained so far by SA research satisfy the regulatory concerns, (iii) the future programs, envisaged will address the potential regulatory needs into next century, and (iv) how...
Innehållstyp: Publikationer -
2014:15 Multivariatanalys av radioaktivitetsdata från utsläpp till luft och vatten från Studsviksanläggningarna och i omgivningen av Studsvik
Syftet med denna studie var att undersöka korrelationer mellan uppmätt utsläppt radioaktivitet från Studsviksanläggningarna och uppmätta halter radioaktivitet i omgivningen av Co-60, Cs-134, Cs-137, Eu-152, Eu-154 och Mn-54. Ett mål var att se hur olika provslag i omgivningen av Studsvik fungerar som indikatorer för den uppmätta utsläppta radioaktiviteten.
Innehållstyp: Publikationer -
1994:14 Evaluation of acceptance criteriafor data on environmentally assistedcracking in light water reactors
The assessment of possible sub-critical crack growth through environmentally assisted cracking (EAC) is a commonly encountered problem in safety evaluations of light water reactor components. The numerous factors influencing EAC fall into three main groups (material, medium and loading), but their interactions are highly complex. Field assessments usually rely on the evaluation of...
Innehållstyp: Publikationer -
1995:70 Crack Characterisation for In-service
During in-service inspection by non destructive testing the reliability is highly dependent on how the equipment is adjusted to the specific object and to the anticipated crack features. The crack feature and morphology vary widely between different cracking mechanisms and between material types, in which the cracks appear. The major objective of this study was to characterise a number of...
Innehållstyp: Publikationer