Publikationer

Din avgränsning ger 44 träffar.

• 2005:23 DECOVALEX III PROJECT Thermal-Chemical Modeling of the Yucca Mountain Project Drift Scale Test

  Robin N. Datta with contributions from Akira Ito, Mikazu Yui, Yutaka Sugita, Susumu Kawakami, Eric Sonnenthal, Nicholas Spycher SKI English...

  Innehållstyp: Publikationer

• 2005:19 DECOVALEX III PROJECT Mathematical Models of Coupled Thermal-Hydro-Mechanical Processes for Nuclear Waste Repositories

  L. Jing, C-F. Tsang, J-C. Mayor, O. Stephansson, F. Kautzky SKI English...

  Innehållstyp: Publikationer

• 2005:29 DECOVALEX III PROJECT Thermal-Hydro-Mechanical Coupled Processes in Safety Assessments

  Johan Andersson 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

• 2005:51 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

• 2005:61 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

• 2005:55 Application of Master Curve Methodology for Structural Integrity Assessments of Nuclear Components

  Iradj Sattari-Far, Kim Wallin SKI English...

  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