Website0 https://validator.w3.org/feed/docs/rss2.html Study on verification of SPACE code based on an MSGTR experiment at the ATLAS-PAFS facility About Guideline Nuclear Competence & Nuclear Safety Publications Publications Disclaimer & Copyright Notice (German) Updraft Decommissioning & Waste Treatment Home File Upload Privacy Policy Terms and conditions Cookie notice Sitemap Interim Storage & Final Disposal International Trends & Developments in Nuclear NUMERICAL AND EMPIRICAL APPROACHES TO QUANTIFY THE PROTECTIVE EFFECT OF SOIL Minimization of local dose rates by rearrangement of drums in a strongly regulated MAW/LAW storage facility A new technical approach for the minimization of secondary waste produced by water abrasive suspension cutting during disassembling of nuclear facilities Shielding Fuel Assembly Design Optimization A hybrid experimental and numerical investigation on the Cr2AlC-coated zirconium for accident-tolerant fuel systems Effect of Bulk Condensation on Containment Atmosphere Mixing Ground Control and the Principle of Minimizing Radiological Exposure as Key Drivers for the Recovery of Radioactive Waste Out of the Asse II Mine Assessment of Loss of Shutdown Cooling System Accident during Mid-Loop Operation in LSTF Experiment using SPACE Code IAEA Approach to Review the Applicability of the Safety Standards to Small Modular Reactors A zero-power facility as multi-fold opportunity to support quick progress in innovative reactor development Studies on performance and degradation stability of chemically degraded nuclear graded ion exchange materials by application of radio analytical technique Development of Safety-related Residual Heat Removal Chains from German Technology Pressure Water Reactors (Light and Heavy Water) TRIPLE C Waste Container for Increased Long-term Safety of  HHGW Disposal in Salt, Clay and Crystalline Error Reduction in Radioactivity Calculation for Retired Nuclear Power Plant Considering Detailed Plant-specific Operation History Operating Experience from Ageing Events Occurred at Nuclear Power Plants SSiC Nuclear Waste Canisters: Stability Considerations During Static and Dynamic Impact Non-destructive Radioactive tracer technique in evaluation of photo-degraded polystyrene based nuclear grade ion exchange material | Pravin U. Singare Improving Henry-Fauske Critical Flow Model in SPACE Code and Analysis of LOFT L9-3 Investigations of the Tailskin Seal During the Retrieval Concept ‘Shield Tunnelling with Partial Face Excavation’ in the Asse II Mine Preliminary CFD analysis of innovative decay heat removal system for the European Sodium Fast Reactor Concept CFD Simulations of Single Phase Pressurized Thermal Shock in the RPV of a 330MWe PWR Experimental Study of Convective Heat Transfer Through Fuel Pins of a Nuclear Power Plant Equipment Selection Methodology of Seismic Probability Safety Assessment for Nuclear Power Plant Ground Control and the Principle of Minimizing Radiological Exposure as Key Drivers for the Recovery of Radioactive Waste Out of the Asse II Mine Sample Page Imprint