American Nuclear Society

/Create an Account

Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 197 / Number 2

Volume 197

Number 2

Table of Contents
Foreword: Selected papers from the 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2021)(Patrick S. Brantley, Dmitriy Y. Anistratov, Todd J. Urbatsch)

Asymptotic Diffusion Limits of the Multigroup Neutron Transport Equations

Edward W. Larsen

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 145-163

Technical Paper / dx.doi.org/10.1080/00295639.2022.2058847

Toward a More Realistic Analysis of Neutron Clustering

Thomas M. Sutton

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 164-175

Technical Paper / dx.doi.org/10.1080/00295639.2022.2065872

Theoretical Derivation of a Unique Combination Number Hidden in the Higher-Order Neutron Correlation Factors Using the Pál-Bell Equation

Tomohiro Endo, Fuga Nishioka, Akio Yamamoto, Kenichi Watanabe, Cheol Ho Pyeon

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 176-188

Technical Paper / dx.doi.org/10.1080/00295639.2022.2049992

A Stochastic Transport Model for the Cumulative Number of Fissions and Deposited Fission Energy

Anil K. Prinja, Patrick F. O’Rourke

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 189-211

Technical Paper / dx.doi.org/10.1080/00295639.2022.2087830

A Limited-Memory Framework for Conditional Point Sampling for Radiation Transport in 1D Stochastic Media

Emily H. Vu, Aaron J. Olson

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 212-232

Technical Paper / dx.doi.org/10.1080/00295639.2022.2116378

Parametric Model-Order Reduction for Radiation Transport Simulations Based on an Affine Decomposition of the Operators

Patrick Behne, Jan Vermaak, Jean Ragusa

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 233-261

Technical Paper / dx.doi.org/10.1080/00295639.2022.2112901

The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems

Nickolas J. Adamowicz, Annalisa Manera, Edward W. Larsen

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 262-278

Technical Paper / dx.doi.org/10.1080/00295639.2022.2112900

Frequency Transform Method for Transient Analysis of Nuclear Reactors in Monte Carlo

Miriam A. Kreher, Samuel Shaner, Benoit Forget, Kord Smith

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 279-290

Technical Paper / dx.doi.org/10.1080/00295639.2022.2067739

The Legendre Polynomial Axial Expansion Method

Nicholas F. Herring, Benjamin S. Collins, Thomas J. Downar, Aaron M. Graham

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 291-307

Technical Paper / dx.doi.org/10.1080/00295639.2022.2082231

A Multigroup Homogeneous Flux Reconstruction Method Based on the ANOVA-HDMR Decomposition

Pavel M. Bokov, Danniell Botes, Rian H. Prinsloo, Djordje I. Tomašević

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 308-332

Technical Paper / dx.doi.org/10.1080/00295639.2022.2108654

Spatially Dependent Resonance Self-Shielding in CASMO5

Rodolfo M. Ferrer, Joshua M. Hykes

Nuclear Science and Engineering / Volume 197 / Number 2 / February 2023 / Pages 333-350

Technical Paper / dx.doi.org/10.1080/00295639.2022.2053491

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use