ANS / Publications / Journals / Nuclear Science and Engineering

A Critical Review of Heat Pipe Experiments in Nuclear Energy Applications

Scott Wahlquist, Joshua Hansel, Piyush Sabharwall, Amir Ali

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 719-752

Critical Review / dx.doi.org/10.1080/00295639.2022.2082230

Design and Thermal-Hydraulic Performance Analysis of a Low-Temperature Heat Pipe Test Facility

Ilyas Yilgor, Eymon Lan, Shanbin Shi

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 753-770

Technical Paper / dx.doi.org/10.1080/00295639.2022.2087835

Pressure Drop in Seven-Pin Wire-Wrapped Rod Bundle for the Sodium Cartridge Loop in Versatile Test Reactor

Zhengting Quan, Adam Dix, Ran Kong, Seungjin Kim, Mamoru Ishii, Mitchell T. Farmer

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 771-787

Technical Paper / dx.doi.org/10.1080/00295639.2022.2082232

Flow-Induced Vibration of Solitary Wire-Wrapped Cylinders in Axial Flow

Chad A. Nixon, Wade R. Marcum

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 788-812

Technical Paper / dx.doi.org/10.1080/00295639.2022.2058846

Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR)

Haihua Zhao, Lambert Fick, Alexander Heald, Quan Zhou, Samuel Richesson, Noah Sutton, Brandon Haugh

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 813-839

Technical Paper / dx.doi.org/10.1080/00295639.2022.2106724

Simulation of the High Temperature Test Facility (HTTF) Core Using the 2D Ring Model with SAM

Zhiee Jhia Ooi, Thanh Hua, Ling Zou, Rui Hu

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 840-867

Technical Paper / dx.doi.org/10.1080/00295639.2022.2106726

Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors

Yeongshin Jeong, Koroush Shirvan, Michael Buric

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 868-885

Technical Paper / dx.doi.org/10.1080/00295639.2022.2102388

Simulation of the Axial-Flow Centrifugal Bubble Separator for Liquid-Fueled Molten Salt Reactors Using Eulerian Two-Fluid Model

Jiaqi Chen, Caleb S. Brooks

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 886-906

Technical Paper / dx.doi.org/10.1080/00295639.2022.2103347

Numerical Investigations of Molten Salt Pump Journal Bearings Under Hydrodynamic Lubrication Conditions for FHRs

Yuqi Liu, Shuai Che, Adam Burak, Daniel L. Barth, Nicolas Zweibaum, Minghui Chen

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 907-919

Technical Paper / dx.doi.org/10.1080/00295639.2022.2103343

Thermal-Hydraulic System-Level Analysis of a Molten Salt Natural Circulation Loop

Sheng Zhang, Hsun-Chia Lin, Xiaodong Sun

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 920-946

Technical Paper / dx.doi.org/10.1080/00295639.2022.2102389

Quantification of Deep Neural Network Prediction Uncertainties for VVUQ of Machine Learning Models

Mahmoud Yaseen, Xu Wu

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 947-966

Technical Paper / dx.doi.org/10.1080/00295639.2022.2123203

Validation and Uncertainty Quantification of Transient Reflood Models Using COBRA-TF and Machine Learning Techniques Based on the NRC/PSU RBHT Benchmark

Yue Jin, Stephen M. Bajorek, Fan-Bill Cheung

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 967-986

Technical Paper / dx.doi.org/10.1080/00295639.2022.2087834

Scaling, Passive Systems, and the AP-1000

F. D’Auria

Nuclear Science and Engineering / Volume 197 / Number 5 / May 2023 / Pages 987-999

Technical Paper / dx.doi.org/10.1080/00295639.2023.2178874