Website0 https://validator.w3.org/feed/docs/rss2.html Publications Decommissioning & Waste Treatment Home IN-SITU MOISTURE MEASURING IN CONCRETE STRUCTURES OF NUCLEAR REACTOR BUILDINGS DURING DECOMMISSIONING Vorstellung des Forschungsprojekts zur Entwicklung eines Beprobungssystems inklusive qualitätsgesichertem Beprobungsverfahren für nicht zugängliche Kunststoffrohrleitungen (Bero) DEVELOPMENT OF A DECONTAMINATION TOOL FOR INNER EDGES AND CORNERS (EKONT-2) Einfluss innovativer kerntechnischer Rückbaumethoden auf Schwebstoff-Filtersysteme RADIOLOGICAL CHARACTERIZATION OF SOLID WASTE: FROM FREE RELEASE MEASUREMENTS UP TO THE MEASUREMENT OF HIGH RADIOACTIVE WASTE Fort Calhoun Station Decommissioning and Demolition Project Reactor Vessel Segmentation Laser-based measurement system for the detection of subsurface anomalies Material clearance measurement under the influence of natural occurring radioactive material Schritte zur Freigabe des Sicherheitsbehälters im KKS Application of Weight Parameters generated via Recursive Monte Carlo Method for Optimized Shielding Calculations NUMERICAL AND EMPIRICAL APPROACHES TO QUANTIFY THE PROTECTIVE EFFECT OF SOIL AUSLEGUNG EINER TRANSPORTBEREITSTELLUNGSHALLE UND DESSEN BEHÄLTERSTAPEL GEGEN EINWIRKUNG VON AUßEN AUS ERDBEBEN UND EXPLOSIONSDRUCKWELLE Aktueller Stand des Standortauswahlverfahrens aus der Sicht der Vorhabenträgerin KONZEPTE FÜR ENDLAGERBEHÄLTER IN KRISTALLINEM WIRTSGESTEIN IN DEUTSCHLAND MUON IMAGING OF TRANSPORT AND STORAGE CASKS AUSLEGUNG UND BERECHNUNG DER OBERIRDISCHEN GEBÄU- DETEILE EINES ENDLAGERS FÜR DEN LASTFALL ERDBEBEN AUF GRUNDLAGE DER KTA RADIOLOGISCHE BETRACHTUNGEN ZUR FESTLEGUNG VON MINDESTABSTÄNDEN FÜR STANDORTE VON ABFALL- UND/ODER BRENNELEMENTE-ZWISCHENLAGERN DER BGZ THE MUTOMCA PROJECT – AN OVERVIEW ESTABLISHING A NEW CASK FAMILY – 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 SUPERCRITICAL CO2 RECUPERATED CYCLE PART LOAD OPERATIONS EMPLOYING TURBINE THROTTLE VALVE DEVELOPMENT OF A HEAT PIPE MODEL FOR ATHLET Neutronic modelling of the Special Purpose Reactor MMR with Serpent as a part of the MISHA project EXPERIMENTAL INVESTIGATION OF HEAT TRANSFER AT AND POST CRITICAL HEAT FLUX IN CO2 FLOW AT HIGH SUBCRITICAL PRESSURES Advancing Micro Modular Reactor Safety: Experimental Analysis on Liquid Metal Heat Pipe Prototypes in the MISHA Project Entwicklung und Validierung einer Rechenkette zur Simulation von Micro Modular Reactors CREATING OPERATION MANUALS FOR A WASTE MANAGEMENT ORGANIZATION Schacht Konrad 1 – Austausch des Führungsgerüstes PRACTICAL CYBERSECURITY HARDENING FOR INTERIM STORAGE AND FINAL DISPOSAL FACILITIES NUMERISCHE MODELLIERUNG ZUR BEWERTUNG DER EXPOSITION ÜBER DEN GRUNDWASSERPFAD BEI DER DEPONIERUNG FREIGEGEBENER RADIOAKTIVER ABFÄLLE