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Volume 197

Number 10

Table of Contents
Foreword: Selected papers from the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)(Elia Merzari, Ferry Roelofs, W. David Pointer, Chul-Hwa Song)

A Perspective on Data-Driven Coarse Grid Modeling for System-Level Thermal Hydraulics

Arsen S. Iskhakov, Cheng-Kai Tai, Igor A. Bolotnov, Nam T. Dinh

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2527-2542

Research Article / dx.doi.org/10.1080/00295639.2022.2107864

myMUSCLE, a New Multiphysics, Multiscale Simulation Coupling Environment

H. J. Uitslag-Doolaard, K. Zwijsen, F. Roelofs, M. M. Stempniewicz

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2543-2560

Research Article / dx.doi.org/10.1080/00295639.2022.2148809

Coupled Monte Carlo Transport and Conjugate Heat Transfer for Wire-Wrapped Bundles Within the MOOSE Framework

A. J. Novak, P. Shriwise, P. K. Romano, R. Rahaman, E. Merzari, D. Gaston

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2561-2584

Research Article / dx.doi.org/10.1080/00295639.2022.2158715

Two-Phase Turbulent Kinetic Energy Budget Computation in Co-Current Taylor Bubble Flow

E. M. A. Frederix, S. Tajfirooz, J. A. Hopman, J. Fang, E. Merzari, E. M. J. Komen

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2585-2601

Research Article / dx.doi.org/10.1080/00295639.2022.2141517

Euler-Euler Model of Bubbly Flow Using Particle-Center-Averaging Method

Hongmei Lyu, Fabian Schlegel, Roland Rzehak, Dirk Lucas

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2602-2619

Research Article / dx.doi.org/10.1080/00295639.2022.2131344

OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model

Fabian Schlegel, Richard Meller, Benjamin Krull, Ronald Lehnigk, Matej Tekavčič

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2620-2633

Research Article / dx.doi.org/10.1080/00295639.2022.2120316

Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor

Tri Nguyen, Elia Merzari

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2634-2659

Research Article / dx.doi.org/10.1080/00295639.2023.2186200

Code Benchmark of the HTTF Pressurized Conduction Cooldown Test Using SAM

Thanh Hua, Ling Zou, Rui Hu

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2660-2672

Research Article / dx.doi.org/10.1080/00295639.2023.2186163

Analyses of Critical Hydrogen Enrichment in PWR Containment Compartments

E. Schmidt, N. Reinke, M. Freitag, M. Sonnenkalb

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2673-2685

Research Article / dx.doi.org/10.1080/00295639.2022.2146994

Measurements of Droplet Size and Velocity Distributions During Rod Bundle Core Reflood

Grant R. Garrett, Brian R. Lowery, Molly K. Hanson, Douglas J. Miller, Turki Almudhhi, Fan-Bill Cheung, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2686-2710

Research Article / dx.doi.org/10.1080/00295639.2022.2157189

Experimental Analysis of Fast-Transient Flow Boiling in Various Flow Conditions Using Inverse Heat Conduction Calculation Method

Yong-Seok Choi, Dong-Hoon Kam, Byong-Guk Jeon, Jong-Kuk Park, Sang-Ki Moon

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2711-2722

Research Article / dx.doi.org/10.1080/00295639.2022.2132100

Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms

Fred Gelbard, Bradley A. Beeny, Larry L. Humphries, Kenneth C. Wagner, Lucas I. Albright, Max Poschmann, Markus H. A. Piro

Nuclear Science and Engineering / Volume 197 / Number 10 / October 2023 / Pages 2723-2741

Research Article / dx.doi.org/10.1080/00295639.2022.2161277