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Volume 198

Number 10

Table of Contents

Neutron Total Cross Sections of ²³²Th, ²³⁷Np, ^235,238U, and ²³⁹Pu from 3 to 230 MeV

P. W. Lisowski, M. S. Moore, G. L. Morgan

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 1901-1910

Research Article / dx.doi.org/10.1080/00295639.2023.2284432

An Innovational Jacobian-Split Newton-Krylov Method Combining the Advantages of the Jacobian-Free Newton-Krylov Method and the Finite Difference Jacobian-Based Newton-Krylov Method

Lixun Liu, Han Zhang, Xinru Peng, Qinrong Dou, Yingjie Wu, Jiong Guo, Fu Li

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 1911-1934

Research Article / dx.doi.org/10.1080/00295639.2023.2284447

Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code

Surian Pinem, Liem Peng Hong, Wahid Luthfi, Tukiran Surbakti, Donny Hartanto

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 1935-1949

Research Article / dx.doi.org/10.1080/00295639.2023.2284433

Calculation of Thermalized Component of Neutron Spectra in a D-D Neutron Generator

Nnaemeka Nnamani

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 1950-1957

Research Article / dx.doi.org/10.1080/00295639.2023.2284453

Development of HELIOS/BIPR/PARCS/MCNP6 Computation Route for WWER RPV Neutron Fluence Analysis and Validation Against Ex-Vessel Detector Measurement Data

S. Bznuni, A. Ugujyan, A. Amirjanyan, P. Kohut

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 1958-1964

Research Article / dx.doi.org/10.1080/00295639.2023.2284438

CFD Analysis of Effects of Grid Spacer Vane on Thermal-Hydraulic Performance of Fluid in a 5×5 Fuel Channel

Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 1965-1983

Research Article / dx.doi.org/10.1080/00295639.2023.2280350

Numerical Simulation of Turbulent Flow and Friction Characteristics Through a Loop of Narrow Rectangular Channel Under Rolling Motions

Husnain Murtaza, Muhammad Abdul Basit, Romana Basit, Wenxi Tian

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 1984-1997

Research Article / dx.doi.org/10.1080/00295639.2023.2284434

Feasibility of Using Mixed-Oxide Fuel for a Pressurized Water Reactor Instead of Traditional UO₂ Fuel Material

Mohy Sabry, Neveen S. Abed, Ahmed Omar, Moamen G. El-Samrah, Mohamed Y. M. Mohsen

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 1998-2012

Research Article / dx.doi.org/10.1080/00295639.2023.2284441

Flux Flattening Large Heavy Water Power Reactors with Accelerator-Driven Photoneutron Source

Arief Rahman Hakim, Douglas A. Fynan

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 2013-2037

Research Article / dx.doi.org/10.1080/00295639.2023.2280346

Quantifying Safety Significance: An In-Depth Analysis of Importance Measures in Level 1 PSA for the VVR 10-MW Water-Water Research Reactor

Rex Gyeabour Abrefah, Felix Ameyaw

Nuclear Science and Engineering / Volume 198 / Number 10 / October 2024 / Pages 2038-2050

Note / dx.doi.org/10.1080/00295639.2023.2284454

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