Din avgränsning ger 110 träffar.
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2014:48 Technical Note, Independent assessment of groundwater sulphide content in the long-te
sulphide content is a key factor in the determination of canister lifetimes because of its role in corrosion of copper. SKB has based the canister lifetime analysis on a distribution of measured sulphide ... expert judgement in the selection of samples that are regarded as representative. The objective of this report is to make an assessment of the validity of SKB’s approach. Sulphide in groundwater derives...
Innehållstyp: Publikationer -
2014:24 Technical Note, Workshop on biosphere issues
undersökts. * AEA, 2003. ”Reference Biospheres” for Solid Radioactive Waste Disposal. Report of BIOMASS Theme 1 of the BIOsphere Modelling and ASSessment (BIOMASS) Programme, International Atomic Energy Agency ... construction and operation of a repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information...
Innehållstyp: Dokument -
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 ... 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 developed...
Innehållstyp: Publikationer -
2014:59 Technical Note, Relation between earthquake magnitude, fracture length and fracture shear displacement in the KBS-3 repository at Forsmark – Main Review Phase
This study addresses one of several scenarios that could impair the physical integrity of the repository of spent nuclear fuel at the Forsmark site. Two sources of threat are: i) events due to thermal ... thermal loading on the rock mass by the heat from canisters with spent nuclear fuel, and ii) seismic events, i.e. earthquakes, at the nearby deformation zones and zones intersecting the repository area. The eff ect...
Innehållstyp: Publikationer -
2014:41 Technical Note, Review of Radionuclide Abstraction and Selection in the SKB Safety Case -Main Review Phase
As part of the Swedish Radiation Safety Authority (SSM) review of the Swedish Nuclear Fuel and Waste Management Company (SKB) SR-Site safety assessment for a spent nuclear fuel repository in Sweden, this ... documents the Center for Nuclear Waste Regulatory Analyses (CNWRA®) review of the abstraction and selection of radionuclides in the SKB safety case. Specifically, CNWRA evaluated whether the SKB approach...
Innehållstyp: Publikationer -
2014:33 Technical Note, Reproduction of SKB’s Canister Failure Calculations - What-If and ‘Residual’ Scenario to Illustrate Barrier Functions
Report number: 2014:33 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten.se Reproduction of SKB’s Canister Failure Calculations —What-If and ‘Residual’ Scenario to Illustrate Barrier Functions ... construction and operation of a repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain infor- mation...
Innehållstyp: Dokument -
2014:38 Technical Note, Detailed assessment of radionuclide Kd-values for the geosphere-main review phase
Company (SKB) in 2011 to construct and operate a deep geologic repository for spent nuclear fuel at the Forsmark site in the municipality of Östhammar, Sweden. SKB has presented details of its long-term ... long-term safety assessment, SR-Site, in a main report (SKB, 2011, TR-11-01) and in multiple supporting technical documents that are cited by the main report. In developing the safety case for SR-Site, SKB identified...
Innehållstyp: Publikationer -
2014:33 Technical Note, Reproduction of SKB’s Canister Failure Calculations - What-If and ‘Residual’ Scenario to Illustrate Barrier Functions
analysis of a range of scenarios in its SR-Site report. SKB grouped these scenarios into two categories—main and residual. The main scenario included a likely scenario (corrosion failure) and a less probable ... included two unlikely scenarios—isostatic-load and growing pinhole failures. For each of the scenarios, SKB analysed a reference case and several variations (created by altering features and processes, and...
Innehållstyp: Publikationer -
2014:46 Technical Note, QA in SKB’s Groundwater Flow Modelling
The general objective of the project is to provide review comments on SKB’s postclosure safety analysis, SR-Site, for the proposed repository at Forsmark. The specific objective is to get an understanding ... understanding and an assessment of SKB’s quality assurance of the groundwater flow modelling in connection to SR-Site. The reliability of the results of the groundwater flow modelling depends inter alia on the...
Innehållstyp: Publikationer -
2014:19 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 5, 6 and 7
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.) ... separate effects interact in the complex integrated manner. The codes are under constant development and need to be compared with actual tests. In this report simulations of three tests in Halden (IFA-650.5,6...
Innehållstyp: Publikationer