Din avgränsning ger 478 träffar.
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2007:10 DECOVALEX-THMC - Task D
The DECOVALEX project is an international cooperative project initiated by SKI, the Swedish Nuclear Power Inspectorate, with participation of about 10 international organizations. The name DECOVALEX stands for DEvelopment of COupled models and their VALidation against Experiments. The general goal of this project is to encourage multidisciplinary interactive and cooperative research on...
Innehållstyp: Publikationer -
2011:08 Workshop on Copper Corrosion and Buffer Erosion Stockholm 15-17 September 2010
In SSM:s preparation for reviewing SKB:s license application for disposal of spent nuclear fuel, a series of technical workshops have been conducted. The main purpose of this type of workshops is to get an overall understanding of the state of knowledge on interdisciplinary issues as well as of questions in the research front by inviting several experts. Previous workshops have addressed the...
Innehållstyp: Publikationer -
2007:32 Low pH Cements
Concrete and cement are used in constructions as well as in conditioning of waste in repositories for radioactive waste. The development of low pH cements for use in geological repositories for radioactive waste stem from concerns over the potential for deleterious effects upon the host rock and other EBS materials (notably bentonite) under the hyperalkaline conditions (pH > 12) of cement...
Innehållstyp: Publikationer -
2017:23 Kalibrering för bestämning av optimal beräkningsmodell
Bakgrund SSM bedömer i tillsynen avancerade datorberäkningar relaterade till drift av kärnkraftverk, utförda av extern part. Inom kärnkraft kan experimentella undersökningar vara olämpliga. Beräkningar blir därför ofta det enda alternativet att undersöka möjliga konsekvenser av planerade förändringar. Beräkningsmodeller...
Innehållstyp: Publikationer -
2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository
Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...
Innehållstyp: Publikationer -
2017:11 Extended Common Load Model: A tool for dependent failure modelling in highly redundant structures
Background The treatment of dependent failures is one of the most controversial subjects in reliability and risk analyses. The difficulties are specially underlined in the case of highly redundant systems, when the number of redundant components or trains exceeds four. The Common Load Model (CLM), originally defined in the 70’ies, differs from other CCF models, as it relies on a specific...
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 -
2015:44 Krav på funktion, konstruktion och provning av reaktorinneslutningar
Bakgrund I Sverige behöver SSM skaffa vidare kunskap inom olika områden inom nukleära byggnadskonstruktioner bl.a. reaktorinneslutningar. Syfte Syftet med projektet "Krav på funktion, konstruktion och provning av reaktorinneslutningar" är att sammanställa information för att belysa viktiga reaktorinneslutningsfrågor vid byggnation. Den sammanställda...
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 -
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