1 PUMA scalmg Methodology Flow Chart (Continued) | Download Table
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
Thermal-hydraulic test facility for nuclear reactor containment: Engineering design methodology and benchmarking - ScienceDirect
Frontiers | Modeling and Simulation of Reaction Environment in Photoredox Catalysis: A Critical Review
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
JNE | Free Full-Text | Experimental Thermal–Hydraulic Testing of a Mock-Up of the Fuel-Breeder Pin Concept for the EU-DEMO HCPB Breeding Blanket
The Use of System Codes in Scaling Studies: Relevant Techniques for Qualifying NPP Nodalizations for Particular Scenarios – topic of research paper in Physical sciences. Download scholarly article PDF and read for
Energies | Free Full-Text | The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status
Multi-parameter testing machine - CRT-PUMA - Cooper Research Technology - unbound materials / for laboratories / hydraulic
Experimental investigation on thermal hydraulic interaction of RCS (reactor coolant system) and containment for intermediate break loss-of-coolant accident (IBLOCA) scenario in ATLAS-CUBE test facility - ScienceDirect
PUMA : Purdue University Multi-Dimensional Integral Test Assembly Scientific Design of the Scaled Facility for GE SBWR Design SBWR : Simplified Boiling. - ppt download
Fluids | Free Full-Text | CFD Study of Thermal Stratification in a Scaled-Down, Toroidal Suppression Pool of Fukushima Daiichi Type BWR
Basic Research on High Temperatures Gas Reactor Thermal Hydraulics and Reactor Physics - Cooperative Program Review Meeting, Feb
THOR - Thermal-Hydraulics Open-access Research Facility - Nuclear Futures Bangor - Research Groups
Experimental investigation on thermal hydraulic interaction of RCS (reactor coolant system) and containment for intermediate break loss-of-coolant accident (IBLOCA) scenario in ATLAS-CUBE test facility - ScienceDirect
20101105_PUMA-1006-D411g-Publishable_Final_Activity_Report_NRG_104869
Li Puma - Advanced Projects Homepage
Scientific Design of Purdue University Multi-Dimensional Integral Test Assembly (PUMA) for GE SBWR
Experimental investigation on thermal hydraulic interaction of RCS (reactor coolant system) and containment for intermediate break loss-of-coolant accident (IBLOCA) scenario in ATLAS-CUBE test facility - ScienceDirect
Scaling analysis of an IBLOCA counterpart test between the ATLAS and LSTF facilities - ScienceDirect
Thermal-hydraulic test facility for nuclear reactor containment: Engineering design methodology and benchmarking - ScienceDirect
