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
1 PUMA scalmg Methodology Flow Chart (Continued) | Download Table
20101105_PUMA-1006-D411g-Publishable_Final_Activity_Report_NRG_104869
THOR - Thermal-Hydraulics Open-access Research Facility - Nuclear Futures Bangor - Research Groups
Thermal-hydraulic test facility for nuclear reactor containment: Engineering design methodology and benchmarking - ScienceDirect
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
Thermal-hydraulic test facility for nuclear reactor containment: Engineering design methodology and benchmarking - ScienceDirect
19 Containment heat loss in PUMA with addition of fibrous-based... | Download Table
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
Resume Sidharth Paranjape
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
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
SPATIO-TEMPORAL STUDY OF INSTABILITIES IN A NATURAL CIRCULATION LOOP OF PUMA
Thermal-hydraulic test facility for nuclear reactor containment: Engineering design methodology and benchmarking - ScienceDirect
Fluids | Free Full-Text | CFD Study of Thermal Stratification in a Scaled-Down, Toroidal Suppression Pool of Fukushima Daiichi Type BWR
1 PUMA Scaling Methodology Flow Chart PUMA SCALING | Download Table
Frontiers | Modeling and Simulation of Reaction Environment in Photoredox Catalysis: A Critical Review
PUMA : Purdue University Multi-Dimensional Integral Test Assembly Scientific Design of the Scaled Facility for GE SBWR Design SBWR : Simplified Boiling. - ppt download
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
Procedures for producing a PUMA chip by replicating from a SU-8 master... | Download Scientific Diagram
Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform - ScienceDirect
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
Thermal-hydraulic test facility for nuclear reactor containment: Engineering design methodology and benchmarking - ScienceDirect
Energies | Free Full-Text | The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status
