Din avgränsning ger 1217 träffar.
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2005:04 Assuring Competency in Nuclear Power Plants: Regulatory Policy and Practice
Nancy E. Durbin, Barbara Melber SKI English...
Innehållstyp: Publikationer -
2005:08 Scattering of SH Waves by Isolated Cracks Using a Hybrid Approach
Jonas Niklasson, Gert Persson SKI English...
Innehållstyp: Publikationer -
2005:17 Litteraturstudie - Sigmafas i 316L och 304L
En litteraturstudie över förekomsten av sigmafas och dess bildande och kinetik har genomförts. Det konstaterade tidigt att utskiljningen av sigmafas och av 23-karbid var intimt förknippade och därför behandlas båda i redovisningen. De mekaniska egenskaperna hos både 304L och 316L påverkas starkt av närvaron av sigmafas. De dominerande effekterna...
Innehållstyp: Publikationer -
2005:63 Safety-Related Contractor Activities at Nuclear Power Plants - New Challenges for Regulatory Oversight
Alan Chockie SKI English...
Innehållstyp: Publikationer -
2005:51 Hot-Cell Examination of a Defect Rod from IFA-597
SKI English...
Innehållstyp: Publikationer -
2005:64 Investigating conceptual models for physical property couplings in solid solution models of cement
Steven Benbow, Claire Watson, David Savage SKI English...
Innehållstyp: Publikationer -
2005:60 Research and Service Experience with Environmentally-Assisted Cracking in Carbon and Low-Alloy Steels in High-Temperature Water
In this report, the most relevant aspects of research and service experience with environmentally assisted cracking of carbon and low-alloy steels in high-temperature water are reviewed, with special emphasis on the primary pressure-boundary components of boiling water reactors. The main factors controlling the susceptibility to environmentally assisted cracking under light water reactor...
Innehållstyp: Publikationer -
2005:43 Information om utländska kärntekniska anläggningar
Esther Jonsson SKI Svenska...
Innehållstyp: Publikationer -
2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)
Although the extent of cracking was rather surprising for a bolt-loaded specimen, the average stress corrosion crack growth rate of 0.5 mm/year over the five-year testing period does not represent an immediate concern. The overwhelming part of crack growth can have occurred during a 20 day chloride transient during the third year of exposure because of a condenser leakage after an outage. The...
Innehållstyp: Publikationer -
2005:16 Assessment of Core Failure Limits for Light Water Reactor Fuel under Reactivity Initiated Accidents
Lars Olof Jernkvist, Ali R. Massih SKI English...
Innehållstyp: Publikationer