Showing 274 research reports
-
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...
Content type: Publications -
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...
Content type: Publications -
2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4
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...
Content type: Publications -
2014:09 Further Development of the Core Simulator CORE SIM: Extension to coupled capabilities for BWRs
The developed tool is fully MatLab based and requires a set of input data from a commercial static core simulator. The driving perturbation can be specified both as a perturbation in thermo-hydraulic parameters or directly as a perturbation in macroscopic cross-sections. As output, the 3-dimensional spatial distribution of the noise in coolant density, pressure, enthalpy, inlet velocity, fuel...
Content type: Publications -
2014:04 Global Non-proliferation ‘Clubs’ vs. the NPT
The study analyses the relationship between the Nuclear Non-Proliferation Treaty, NPT and various initiatives and institutions (‘clubs’) based outside the NPT framework, which aims to improve and strengthen the Treaty. The study identifies conflicts and possible synergies and proposes options for developing and improving the interaction between the NPT and ‘clubs’ in order to increase the...
Content type: Publications -
2013:30 Laser pointers and Eye injuries - An analysis of reported cases
The safety limits that exist for human exposure of laser radiation are essential to reduce the risk of injuries. These values, however, give very little information on what tissue damages that may be expected at various elevated exposure levels. Similarly, the Swedish Radiation Protection Authority (SSM) has very little information on how such tissue damage is related to the impairment of the...
Content type: Publications -
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...
Content type: Publications -
2013:28 Brine intrusion by upconing for a high-level nuclear waste repository at Forsmark. Scoping calculations
SSM currently reviews a license application for a spent nuclear fuel repository that is proposed to be located at Forsmark, Sweden. The repository is to be situated at 500 m depth in the rock and copper canisters are deposited in holes excavated from the tunnel system. To protect the canisters they are surrounded by a bentonite clay buffer, which is to swell when getting in contact with...
Content type: Publications -
2013:27 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures
The design codes for anchorage of equipment in concrete structures have been developed since the time the Swedish power plants were designed. Furthermore, the design basis has been updated and in some cases new mechanical loads have been added. As a consequence, it can be difficult for some anchorages to meet the requirements of today. In the design of anchorage equipment the beneficial effect...
Content type: Publications -
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...
Content type: Publications