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Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis - ScienceDirect
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![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
Euratom FP6 Research Projects and Training Activities Volume III
PDF) Design and Thermo-Hydraulic Analysis of Upgraded PUMA System for the Development of a Test Facility of Superconducting CICCs
PUMA : Purdue University Multi-Dimensional Integral Test Assembly Scientific Design of the Scaled Facility for GE SBWR Design SBWR : Simplified Boiling. - ppt download
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3 Decay Power in SBWR and PUMA | Download Table
19 Containment heat loss in PUMA with addition of fibrous-based... | 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
10 PUMA Drywell Design 7-17 | Download Table
C1_HTGR_design_safety_JCK
PASI – A test facility for research on passive heat removal - ScienceDirect
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Perspective on Thermal Hydraulic Researches in the Nuclear Field - ppt download
Energies | Free Full-Text | The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status | HTML
Full article: Scaling Methodology for Integral Effects Tests in Support of Fluoride Salt–Cooled High-Temperature Reactor Technology
18 PUMA component heat loss estimation | 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
FHR and MSR Thermal Hydraulics Research at UC Berkeley
Nea Csni R (2016) 14 | PDF | Scalability | Nuclear Power
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
