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Overview on PANDA and ISP-42, T18 / / Aksan, 1 Laboratory for Thermal-Hydraulics Nuclear Energy and Safety Department IAEA-ICTP Natural Circulation. - ppt download
Overview on PANDA and ISP-42, T18 / / Aksan, 1 Laboratory for Thermal-Hydraulics Nuclear Energy and Safety Department IAEA-ICTP Natural Circulation. - ppt download
1 PUMA scalmg Methodology Flow Chart (Continued) | Download Table
PPT - M amoru Ishii Thermal-Hydraulics and Reactor Safety Laboratory School of Nuclear Engineering Purdue University West Laf PowerPoint Presentation - ID:764190
Nea Csni R (2016) 14 | PDF | Scalability | Nuclear Power
PPT - M amoru Ishii Thermal-Hydraulics and Reactor Safety Laboratory School of Nuclear Engineering Purdue University West Laf PowerPoint Presentation - ID:764190
Simulation and uncertainty analysis of main steam line break accident on an integral test facility - ScienceDirect
Energies | Free Full-Text | The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status | HTML
Energies | Free Full-Text | Numerical Simulations with RELAP5-3D and RELAP5/mod3.3 of the Second Experimental Campaign on In-Box LOCA Transients for HCLL TBS | HTML
PPT - PUMA PROGRAM PowerPoint Presentation, free download - ID:4139660
PUMA : Purdue University Multi-Dimensional Integral Test Assembly Scientific Design of the Scaled Facility for GE SBWR Design SBWR : Simplified Boiling. - ppt download
Energies | Free Full-Text | Numerical Simulations with RELAP5-3D and RELAP5/mod3.3 of the Second Experimental Campaign on In-Box LOCA Transients for HCLL TBS | HTML
16 Automatic Depressurization System (ADS) for PUMA Facility | Download Table
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) Scaling in nuclear reactor system thermal-hydraulics
Simulation and uncertainty analysis of main steam line break accident on an integral test facility - ScienceDirect
![PDF] PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations | Semantic Scholar](https://d3i71xaburhd42.cloudfront.net/462d84b0bc2c91f5de32bd40692937e1214c74ae/2-Table1-1.png "PDF] PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations | Semantic Scholar")
PDF] PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations | Semantic Scholar
19 Containment heat loss in PUMA with addition of fibrous-based... | Download Table
Energies | Free Full-Text | Modelling of Passive Heat Removal Systems: A Review with Reference to the Framatome BWR Reactor KERENA: Part II | HTML
Full article: Scaling Methodology for Integral Effects Tests in Support of Fluoride Salt–Cooled High-Temperature Reactor Technology
PPT - M amoru Ishii Thermal-Hydraulics and Reactor Safety Laboratory School of Nuclear Engineering Purdue University West Laf PowerPoint Presentation - ID:764190
PPT - M amoru Ishii Thermal-Hydraulics and Reactor Safety Laboratory School of Nuclear Engineering Purdue University West Laf PowerPoint Presentation - ID:764190
