Multi-parameter testing machine - CRT-PUMA - Cooper Research Technology - unbound materials / for laboratories / hydraulic
Heterogeneous design and mechanical analysis of HELIAS 5‐B helium‐cooled pebble bed breeding blanket concept - Bongiovì - - International Journal of Energy Research - Wiley Online Library
PDF) Scaling in nuclear reactor system thermal-hydraulics
Development of neutronic-thermal hydraulic-mechanic-coupled platform for WCCB blanket design for CFETR - ScienceDirect
Li Puma - Advanced Projects Homepage
Precision Unbound Material Analyser - Cooper Research Technology
Advances in Mechanical Processing and Design | springerprofessional.de
Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform - ScienceDirect
PDF) Design and Thermo-Hydraulic Analysis of Upgraded PUMA System for the Development of a Test Facility of Superconducting CICCs
PDF) Design and Thermo-Hydraulic Analysis of Upgraded PUMA System for the Development of a Test Facility of Superconducting CICCs
Full article: Scaling Methodology for Integral Effects Tests in Support of Fluoride Salt–Cooled High-Temperature Reactor Technology
PDF) Design and Thermo-Hydraulic Analysis of Upgraded PUMA System for the Development of a Test Facility of Superconducting CICCs
Research on scaling design and applicability evaluation of integral thermal-hydraulic test facilities: A review - ScienceDirect
Html - About PUMA
Overview on PANDA and ISP-42, T18 / / Aksan, 1 Laboratory for Thermal- Hydraulics Nuclear Energy and Safety Department IAEA-ICTP Natural Circulation. - ppt download
PDF) Design development and manufacturing sequence of the European water-cooled Pb-17Li test blanket module | Claudio Nardi - Academia.edu
PUMA : Purdue University Multi-Dimensional Integral Test Assembly Scientific Design of the Scaled Facility for GE SBWR Design SBWR : Simplified Boiling. - ppt download
Thermal hydraulics activities for consolidating HCPB breeding blanket of the European DEMO - IOPscience
Experimental research on double-hole steam jets dcc heat transfer characteristics under stable condensation pattern - ScienceDirect
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 | HTML
PDF) Design and Thermo-Hydraulic Analysis of Upgraded PUMA System for the Development of a Test Facility of Superconducting CICCs
PDF) Design and Thermo-Hydraulic Analysis of Upgraded PUMA System for the Development of a Test Facility of Superconducting CICCs
