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Home / Publications / Journals / Nuclear Science and Engineering / Volume 197 / Number 6

Volume 197

Number 6

Review of the Fluid Dynamics and Heat Transport Phenomena in Packed Pebble Bed Nuclear Reactors

Rahman S. Almusafir, Ahmed A. Jasim, Muthanna H. Al-Dahhan

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1001-1037

Critical Review / dx.doi.org/10.1080/00295639.2022.2146993

Numerical Simulation of Subcooled Flow Boiling in a Vertical Annulus Channel Under Near Atmospheric Pressure Conditions

Sachin Tom, P. Mangarjuna Rao, B. Venkatraman, S. Raghupathy

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1038-1070

Technical Paper / dx.doi.org/10.1080/00295639.2022.2133948

Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)

Muhammad Ishaq, Muhammad Ilyas, Alam Nawaz Khan Wardag, Muhammad Zaman, Mansoor H. Inayat

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1071-1099

Technical Paper / dx.doi.org/10.1080/00295639.2022.2139565

Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box

N. L. Scuro, G. Angelo, E. Angelo, M. H. A. Piro, P. E. Umbehaun, W. M. Torres, D. A. Andrade

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1100-1116

Technical Paper / dx.doi.org/10.1080/00295639.2022.2142437

Numerical Investigation on the Thermal-Hydraulic Characteristics near a Corroded Lower Head of the Reactor Vessel During IVR-ERVC

Cheng Peng, Youya Song, Jian Deng, Sen Mao, Jiang Wu

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1117-1132

Technical Paper / dx.doi.org/10.1080/00295639.2022.2143208

Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced Fission of 233U

H. Naik, S. P. Dange, R. J. Singh, W. Jang

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1133-1158

Technical Paper / dx.doi.org/10.1080/00295639.2022.2142433

A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations

Sam Pasmann, Ilham Variansyah, C. T. Kelley, Ryan McClarren

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1159-1173

Technical Paper / dx.doi.org/10.1080/00295639.2022.2143704

High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled Reactor by Three-Dimensional Linear Source Method of Characteristics

Kaijie Zhu, Boran Kong, Han Zhang, Jiong Guo, Fu Li

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1174-1196

Technical Paper / dx.doi.org/10.1080/00295639.2022.2143706

A Novel Core Design with Movable Moderator for a Fluoride Salt–Cooled High-Temperature Reactor

Zuolong Zhu, Dean Wang, Valmor de Almeida, Charles Forsberg, Eugene Shwageraus

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1197-1212

Technical Paper / dx.doi.org/10.1080/00295639.2022.2146436

Demonstrating Computational Equivalence Between Continuous and Discrete Adjoint Methods by Calculating Time-Dependent Adjoint Solutions with Neutron Diffusion Models

Zeyun Wu, Cihang Lu, Tao Liu

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1213-1238

Technical Paper / dx.doi.org/10.1080/00295639.2022.2143207

Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation

Derjew Ayele Ejigu, Xiaojing Liu

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1239-1254

Technical Paper / dx.doi.org/10.1080/00295639.2022.2138688

Wigner-Wilkins Neutron/Nucleus Scattering Kernel Quantum Mechanically Derived

J. A. Grzesik

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1255-1263

Technical Note / dx.doi.org/10.1080/00295639.2022.2138064

 

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