ANS / Publications / Journals / Nuclear Science and Engineering

Post-Neutron Mass Yield Distribution in the Thermal Neutron–Induced Fission of ²³⁵U

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

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 485-509

Technical Paper / dx.doi.org/10.1080/00295639.2022.2133947

Measurements of the ²⁷Al(α,n) Thick Target Yield near Threshold

K. Brandenburg, G. Hamad, Z. Meisel, C. R. Brune, D. E. Carter, J. Derkin, D. C. Ingram, Y. Jones-Alberty, B. Kenady, T. N. Massey, M. Saxena, D. Soltesz, S. K. Subedi, J. Warren

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 510-516

Technical Paper / dx.doi.org/10.1080/00295639.2022.2118483

Convergence Properties of a Linear Diffusion-Acceleration Method for k-Eigenvalue Transport Problems

Anthony P. Barbu, Marvin L. Adams

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 517-533

Technical Paper / dx.doi.org/10.1080/00295639.2022.2123205

Variance Reduction and Noise Source Sampling Techniques for Monte Carlo Simulations of Neutron Noise Induced by Mechanical Vibrations

Hunter Belanger, Davide Mancusi, Amélie Rouchon, Andrea Zoia

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 534-557

Technical Paper / dx.doi.org/10.1080/00295639.2022.2126719

Introduction of the Adding and Doubling Method for Solving Bateman Equations for Nuclear Fuel Depletion

Olin W. Calvin, Barry D. Ganapol, R. A. Borrelli

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 558-588

Technical Paper / dx.doi.org/10.1080/00295639.2022.2129950

An Improved Dual Asymmetric Penalized Least Squares Baseline Correction Method for High-Noise Spectral Data Analysis

Shuangbao Shu, Ziqiao Yu, Jiaxin Zhang, Zhiqiang Chen, Huajun Liang, Jingjing Chen

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 589-600

Technical Paper / dx.doi.org/10.1080/00295639.2022.2132101

Physics-Informed Neural Network Method and Application to Nuclear Reactor Calculations: A Pilot Study

Mohamed H. Elhareef, Zeyun Wu

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 601-622

Technical Paper / dx.doi.org/10.1080/00295639.2022.2123211

Investigation of the Inhomogeneous Mechanical and Crack Driving Force of Low Alloy Steel SA508 and Its Welded 309L/308L Stainless Steel Cladding

Shuai Wang, He Xue, Guiyi Wu, Zheng Wang, Kuan Zhao, Chenqiang Ni

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 623-632

Technical Paper / dx.doi.org/10.1080/00295639.2022.2123210

Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts

Lance Davis, Ralph Hania, Dennis Boomstra, Dillon Rossouw, Florence Charpin-Jacobs, Jan Uhlir, Martin Maracek, Helmut Beckers, Sebastian Riedel

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 633-646

Technical Paper / dx.doi.org/10.1080/00295639.2022.2129951

Effects of Vent Size and Wind on Dispersion of Hydrogen Leaked in a Partially Open Space: Studies by Numerical Analysis

Atsuhiko Terada, Ryuji Nagaishi

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 647-659

Technical Paper / dx.doi.org/10.1080/00295639.2022.2126689

LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies

Shifa Wu, Jiashuang Wan, Zhi Chen, Longtao Liao, Kai Xiao, Pengfei Wang

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 660-675

Technical Paper / dx.doi.org/10.1080/00295639.2022.2123204

Mixcoatl Software (Part 1): Coupled Thermal Physics and Mechanics for Efficient Engineering Design

Ross Pivovar, Rebecca Owston

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 676-685

Computer Code Abstract / dx.doi.org/10.1080/00295639.2022.2154114

Mixcoatl Software (Part 2): Verification of 1D Fluid Flow Methods Coupled to 3D FEM Thermal Diffusion Models

Ross Pivovar, Rebecca Owston

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 686-702

Computer Code Abstract / dx.doi.org/10.1080/00295639.2022.2126718

Analysis of Integral Experiment of the AHWR Critical Facility with Diffusion-Based Monte Carlo Method

Argala Srivastava, Deep Bhandari, K. P. Singh, Umasankari Kannan

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 703-710

Technical Note / dx.doi.org/10.1080/00295639.2022.2131343

Core Concept of Small Rotational Fuel-Shuffling Breed-and-Burn Fast Reactor with Nitride Fuel and Sodium Coolant

Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 711-718

Technical Note / dx.doi.org/10.1080/00295639.2022.2129952