PDF) INL Experimental Program Roadmap for Thermal Hydraulic Code Validation
Experimental determination of correlations for average heat transfer coefficients in heat exchangers on both fluid sides | SpringerLink
Scientific design of a large-scale sodium thermal–hydraulic test facility for KALIMER—Part I: Scientific facility design - ScienceDirect
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
Advances in Mechanical Processing and Design | springerprofessional.de
Thermal hydraulics activities for consolidating HCPB breeding blanket of the European DEMO - IOPscience
Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform - ScienceDirect
Precision Unbound Material Analyser - Cooper Research Technology
Full article: Scaling Methodology for Integral Effects Tests in Support of Fluoride Salt–Cooled High-Temperature Reactor Technology
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) THERMAL HYDRAULIC MODELS FOR NEUTRONIC AND THERMALY HYDRAULIC FEEDBACK IN CITVAP CODE
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
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
Input Calibration and Validation of RELAP5 Against CIRCUS-IV Single Channel Tests on Natural Circulation Two-Phase Flow Instability
PDF) The three-level scaling approach with application to the Purdue University MultiDimensional Integral Test Assembly (PUMA | Himanshu Pokharna - 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
Development of neutronic-thermal hydraulic-mechanic-coupled platform for WCCB blanket design for CFETR - ScienceDirect
Html - About PUMA
PDF) Design and Thermo-Hydraulic Analysis of Upgraded PUMA System for the Development of a Test Facility of Superconducting CICCs
PASI – A test facility for research on passive heat removal - ScienceDirect
