Thermal-hydraulic test facility for nuclear reactor containment: Engineering design methodology and benchmarking - ScienceDirect
THOR - Thermal-Hydraulics Open-access Research Facility - Nuclear Futures Bangor - Research Groups
Multi-parameter testing machine - CRT-PUMA - Cooper Research Technology - unbound materials / for laboratories / hydraulic
Scientific Design of Purdue University Multi-Dimensional Integral Test Assembly (PUMA) for GE SBWR
Fluids | Free Full-Text | CFD Study of Thermal Stratification in a Scaled-Down, Toroidal Suppression Pool of Fukushima Daiichi Type BWR
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
Basic Research on High Temperatures Gas Reactor Thermal Hydraulics and Reactor Physics - Cooperative Program Review Meeting, Feb
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
Energies | Free Full-Text | The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status
1 PUMA Scaling Methodology Flow Chart PUMA SCALING | Download Table
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
Resume Sidharth Paranjape
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
20101105_PUMA-1006-D411g-Publishable_Final_Activity_Report_NRG_104869
1 COMPARISONS FOR MAJOR COMPONENTS AND DIMENSIONS OF DIFFERENT HEIGHT... | Download Table
Procedures for producing a PUMA chip by replicating from a SU-8 master... | Download Scientific Diagram
JNE | Free Full-Text | CFD Analysis and Optimization of the DEMO WCLL Central Outboard Segment Bottom-Cap Elementary Cell
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
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
Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform - ScienceDirect
Scaling analysis of an IBLOCA counterpart test between the ATLAS and LSTF facilities - ScienceDirect
PURDUE UNIVERSITY THERMAL HYDRAULIC EXPERIMENT FACILITY
