Redaktionsteam atw-scientific

Ground Control and the Principle of Minimizing Radiological Exposure as Key Drivers for the Recovery of Radioactive Waste Out of the Asse II Mine

Ground Control and the Principle of Minimizing Radiological Exposure as Key Drivers for the Recovery of Radioactive Waste Out of the Asse II Mine Geology The Asse salt structure is located in the Southwest of the Hercynian Mountains in Northern Germany. In geological times, compressive tectonic movements ruptured the overlying Read more

By Redaktionsteam atw-scientific, ago

Equipment Selection Methodology of Seismic Probability Safety Assessment for Nuclear Power Plant

Equipment Selection Methodology of Seismic Probability Safety Assessment for Nuclear Power Plant 1. Introduction A typical seismic probability safety assessment (SPSA) requires geological, structural, and systems analysts. In the case of probabilistic seismic hazard analysis (PSHA), geological experts can independently perform the analysis, but structural experts performing seismic fragility analysis Read more

By Redaktionsteam atw-scientific, ago

Experimental Study of Convective Heat Transfer Through Fuel Pins of a Nuclear Power Plant

Experimental Study of Convective Heat Transfer Through Fuel Pins of a Nuclear Power Plant Cylindrical heat sources are used to model the fuel pins in the reactor core of a nuclear power plant and also in the spent fuel storage. This research was aimed at studying convection through slender cylinders Read more

By Redaktionsteam atw-scientific, ago

CFD Simulations of Single Phase Pressurized Thermal Shock in the RPV of a 330MWe PWR

Authors Co-Authors Category Institution Contact Authors Numan Iqbal1 Rab Nawaz2 Kamran Rasheed Qureshi1 Ammar Ahmed1 R. Khan2,3 Co-Authors – Category International Trends & Developments in Nuclear Institution 1 Department of Mechanical Engineering, Pakistan Institute of Engineering and Applied Sciences (PIEAS). 2 Department of Nuclear Engineering, Pakistan Institute of Engineering and Read more

By Redaktionsteam atw-scientific, ago

Preliminary CFD analysis of innovative decay heat removal system for the European Sodium Fast Reactor Concept

Preliminary CFD analysis of innovative decay heat removal system for the European Sodium Fast Reactor Concept 1           Introduction Sodium-cooled Fast Reactors (SFRs) are among the most advanced concept of the Generation-IV reactor systems [1] with extensive design, construction, operation and decommissioning experience. Several experimental, prototype and power reactors have been Read more

By Redaktionsteam atw-scientific, ago

Investigations of the Tailskin Seal During the Retrieval Concept ‘Shield Tunnelling with Partial Face Excavation’ in the Asse II Mine

Author Co-Authors Category Institution Contact Author Birte Froebus Co-Authors – Category Decommissioning and Waste Management Institution Research Assistant at Karlsruhe Institute of Technology, Karlsruhe, Germany Contact birte.froebus@kit.edu Content Keywords Published on DOI Other Content Article Keywords – Published on – DOI – Other – Investigations of the Tailskin Seal During Read more

By Redaktionsteam atw-scientific, ago

Improving Henry-Fauske Critical Flow Model in SPACE Code and Analysis of LOFT L9-3

Author Co-Authors Category Institution Contact Author BumSoo Youn Senior Researcher Nuclear Safety Analysis Group Co-Authors – Category International Trends & Developments in Nuclear Institution Central Research Institute, Korea Hydro and Nuclear Power Co., LTD., Republic of Korea Contact bsyoun81@khnp.co.kr Content Keywords Published on DOI Other Content Article Keywords – Published Read more

By Redaktionsteam atw-scientific, ago

Non-destructive Radioactive tracer technique in evaluation of photo-degraded polystyrene based nuclear grade ion exchange material | Pravin U. Singare

Non-destructive Radioactive tracer technique in evaluation of photo-degraded polystyrene based nuclear grade ion exchange material Non-destructive Radioactive tracer technique in evaluation of photo-degraded polystyrene based nuclear grade ion exchange material Non-destructive Radioactive tracer technique in evaluation of photo-degraded polystyrene based nuclear grade ion exchange material Introduction Poly styrene-divinyl benzene type Read more

By Redaktionsteam atw-scientific, ago

SSiC Nuclear Waste Canisters: Stability Considerations During Static and Dynamic Impact

SSiC Nuclear Waste Canisters: Stability Considerations During Static and Dynamic Impact Introduction High-level radioactive waste (HLW) is mainly a by-product of technical nuclear reactions. It has the highest radioactivity and longest decay time (millions of years with significant radiation). Most HLW (more than 90%) comes from spent nuclear fuel. The Read more

By Redaktionsteam atw-scientific, ago
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