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Richard R. Trewin

Pool Boiling From Enhanced Surfaces in Pure and Binary Mixtures of R-113 and R-11
1994 · Richard Trewin, Michael K. Jensen, et al. · International Heat Transfer Conference (IHTC) · 10
Two-phase pressurized thermal shock analysis with CFD including the effects of free-surface condensation
2019 · Ingo Cremer, Alexander Mutz, et al. · Nuclear Engineering and Design · 6
Development of a one-dimensional model of a closed thermosiphon for cooling a spent-fuel pool
2021 · Richard R. Trewin · Nuclear Engineering and Design · 5
One-dimensional three-field model of condensation in horizontal countercurrent flow with supercritical liquid velocity
2011 · Richard R. Trewin · Nuclear Engineering and Design · 4
Evaluation of Uncertainties in Thermal-Hydraulic Analyses of PTS for the APAL European Project
2023 · Richard Trewin, Andrej Prošek, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) · 3
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Statistical Large-Break LOCA analysis for PWRs with combined ECC injection
2014 · G.-J. Seeberger, E.-M. Pauli, et al. · Kerntechnik · 2
Inlet-Temperature Suppression of Inlet Air for Gas-Turbine Compressors by Evaporative Cooling of Water Spray
2002 · Richard R. Trewin · ASME Turbo Expo: Turbomachinery Technical Conference and Exposition (GT) · 2
State of the Art for Thermal-Hydraulic Analysis of Pressurised Thermal Shock Scenarios
2023 · Ivor Clifford, Pavel Kral, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) · 1
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Best-Estimate-Plus-Uncertainty Analyses of PTS Using a Mixing-Analysis Program for the APAL European Project
2023 · Richard Trewin, Pavel Kral, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) · 1
Verification of Uncertainty Distributions for Thermal-Hydraulic Mixing Parameters Used in KWU-MIX for Pressurized Thermal Shock
2021 · Richard R. Trewin · Nuclear Technology · 1
Presentation of DEFI-PROSAFE Project: Probabilistic Methodology to Assess Margin in Deterministic RPV Integrity Assessment and Proposed Benchmark
2018 · Ralf Tiete, Richard Trewin, et al. · ASME Pressure Vessels and Piping Conference (PVP) · 1
Development and Validation of an Effective Screening Process for Thermal-Hydraulic Phenomena With Relevance to Thermal Loads in Nuclear Power Plants Piping System
2024 · Luciana Rudolph, Richard Trewin, et al. · ASME Pressure Vessels and Piping Conference (PVP)
LTO Modifications to Reduce the PTS Issue -- Results of TH Calculations in the Context of the APAL European Project
2023 · Markku Puustinen, Giteshkumar Patel, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH)
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XFEM and Standard Fracture-Mechanics Analyses of the Reactor Pressure Vessel Gösgen Based on Thermal-Hydraulics Input Data From KWU-MIX and CFD Analyses
2019 · Alexander Mutz, Tomas Nicak, et al. · ASME Pressure Vessels and Piping Conference (PVP)
Uncertainty quantification of RELAP5/MOD3.3 for interfacial shear stress during small break LOCA
2017 · Thanh Tung Duong, Hoang Anh Nguyen, et al. · Nuclear Science and Technology
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Fracture-Mechanics Analysis of the Reactor Pressure Vessel Beznau 1 Based on Thermal-Hydraulics Input Data From KWU-MIX and CFD Analyses
2016 · Tomas Nicak, Richard Trewin, et al. · ASME Pressure Vessels and Piping Conference (PVP)
Enhanced boiling heat transfer in horizontal test bundles
1994 · R Trewin, USDOE, Washington, DC (United States), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Works count: 17
Citation count: 36
H-index: 4
I10-index: 1
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