Din avgränsning ger 135 träffar.
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2005:37 Experience with Regulatory Strategies in Nuclear Power Oversight
Barbara Melber och Nancy E. Durbin SKI English...
Innehållstyp: Publikationer -
2005:15 Human Factors Engineering Plan for Reviewing Nuclear Plant Modernization Programs
John O'Hara, James Higgins SKI English...
Innehållstyp: Publikationer -
2005:04 Assuring Competency in Nuclear Power Plants: Regulatory Policy and Practice
Nancy E. Durbin, Barbara Melber SKI English...
Innehållstyp: Publikationer -
2005:42 Phenomenological Studies on Melt-Structure-Water Interactions (MSWI) during Postulated Severe Accidents: Year 2004 Activity
B.R. Sehgal, H.S. Park, A.K. Nayak, R.C. Hansson, D.Chiferaw, A. Stepanyan, R.S. Rao, A. Karbojian 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 -
2005:08 Scattering of SH Waves by Isolated Cracks Using a Hybrid Approach
Jonas Niklasson, Gert Persson SKI English...
Innehållstyp: Publikationer -
2005:63 Safety-Related Contractor Activities at Nuclear Power Plants - New Challenges for Regulatory Oversight
Alan Chockie SKI English...
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 -
2005:36 Reports within the Area of Nuclear Power Plant Instrumentation
Part 1: Laboratory Test of Analogue and Digital Instrument Components Part 2: Dynamic Deviations in Reactor Pressure and Water Level Signals Caused by Sensing Lines...
Innehållstyp: Publikationer
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