Andere Kunden interessierten sich auch für
![Benchmark Analysis for Condition Monitoring Test Techniques of Aged Low Voltage Cables in Nuclear Power Plants]( "Benchmark Analysis for Condition Monitoring Test Techniques of Aged Low Voltage Cables in Nuclear Power Plants")
Benchmark Analysis for Condition Monitoring Test Techniques of Aged Low Voltage Cables in Nuclear Power Plants25,99 €![Benchmark Analysis of Numerical Models for Tsunami Simulation]( "Benchmark Analysis of Numerical Models for Tsunami Simulation")
Benchmark Analysis of Numerical Models for Tsunami Simulation30,99 €![Supporting Sampling and Sample Preparation Tools for Isotope and Nuclear Analysis]( "Supporting Sampling and Sample Preparation Tools for Isotope and Nuclear Analysis")
Supporting Sampling and Sample Preparation Tools for Isotope and Nuclear Analysis36,99 €![Attributes of Full Scope Level 1 Probabilistic Safety Assessment (Psa) for Applications in Nuclear Power Plants]( "Attributes of Full Scope Level 1 Probabilistic Safety Assessment (Psa) for Applications in Nuclear Power Plants")
Attributes of Full Scope Level 1 Probabilistic Safety Assessment (Psa) for Applications in Nuclear Power Plants30,99 €![Criteria for Radionuclide Activity Concentrations for Food and Drinking Water]( "Criteria for Radionuclide Activity Concentrations for Food and Drinking Water")
Criteria for Radionuclide Activity Concentrations for Food and Drinking Water36,99 €![Utilization of a Network of Small Magnetic Confinement Fusion Devices for Mainstream Fusion Research]( "Utilization of a Network of Small Magnetic Confinement Fusion Devices for Mainstream Fusion Research")
Utilization of a Network of Small Magnetic Confinement Fusion Devices for Mainstream Fusion Research30,99 €![Use of Low Enriched Uranium Fuel in Accelerator Driven Subcritical Systems]( "Use of Low Enriched Uranium Fuel in Accelerator Driven Subcritical Systems")
Use of Low Enriched Uranium Fuel in Accelerator Driven Subcritical Systems25,99 €
Presents the results and main achievements of an IAEA coordinated research project to verify and validate system and safety codes used in the analyses of liquid metal thermal hydraulics and neutronics phenomena in sodium cooled fast reactors. The publication will be of use to the researchers and professionals currently working on relevant fast reactors programmes.
Hinweis: Dieser Artikel kann nur an eine deutsche Lieferadresse ausgeliefert werden.
Hinweis: Dieser Artikel kann nur an eine deutsche Lieferadresse ausgeliefert werden.