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Volume 194

Number 1 | Number 2

Number 1

Three-Dimensional Pin-Resolved Transient Diffusion Analysis of PWR Core by the Hybrid Coarse-Mesh Finite Difference Algorithm

Jaeha Kim, Yonghee Kim

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 1-13

Technical Paper / dx.doi.org/10.1080/00295639.2019.1642016

Deterministic Truncation of the Monte Carlo Transport Solution for Reactor Eigenvalue and Pinwise Power Distribution

Inhyung Kim, HyeonTae Kim, Yonghee Kim

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 14-31

Technical Paper / dx.doi.org/10.1080/00295639.2019.1654815

Development of the Assembly-Level Monte Carlo Neutron Transport Code M3C for Reactor Physics Calculations

Anek Kumar, Umasankari Kannan, S. Ganesan

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 32-43

Technical Paper / dx.doi.org/10.1080/00295639.2019.1645502

Generation of Multigroup Cross Sections with an Improved Monte Carlo Algorithm

Li Cheng, Bin Zhong, Huayun Shen, Zehua Hu, Baiwen Li

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 44-55

Technical Paper / dx.doi.org/10.1080/00295639.2019.1650520

Derivation of the Two-Exponential Probability Density Function for Rossi-Alpha Measurements of Reflected Assemblies and Validation for the Special Case of Shielded Measurements

Michael Y. Hua, Jesson D. Hutchinson, George E. McKenzie, Tony H. Shin, Shaun D. Clarke, Sara A. Pozzi

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 56-68

Technical Paper / dx.doi.org/10.1080/00295639.2019.1654327

Effects of Gamma Irradiation on the Morphological, Physical, and Thermal Properties of B4C/CF/PI/AA6061 Hybrid Composite Laminates

Xuelong Fu, Jie Tao, Dunwen Zuo

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 69-83

Technical Paper / dx.doi.org/10.1080/00295639.2019.1654328

ADDENDUM: Approximate Methods for Inverting Generating Functions from the Pál-Bell Equations for Low Source Problems

M. M. R. Williams

Nuclear Science and Engineering / Volume 194 / Number 1 / January 2020 / Pages 84-85

Addendum / dx.doi.org/10.1080/00295639.2019.1687193

Number 2

Monte Carlo Solution of k-Eigenvalue Problem Using Subspace Iteration Method

Anurag Gupta, R. S. Modak

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 87-103

Technical Paper / dx.doi.org/10.1080/00295639.2019.1668655

A Transport-Free Method for Predicting the Post-Depletion Spatial Neutron Flux Distribution

Andrew E. Johnson, Dan Kotlyar

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 120-137

Technical Paper / dx.doi.org/10.1080/00295639.2019.1661171

Systematic Measurements and Analyses for Lead Void Reactivity Worth in a Plutonium Core and Two Uranium Cores with Different Enrichments

M. Fukushima, J. Goda, A. Oizumi, J. Bounds, T. Cutler, T. Grove, D. Hayes, J. Hutchinson, G. McKenzie, A. McSpaden, R. Sanchez, J. Walker, K. Tsujimoto

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 138-153

Technical Paper / dx.doi.org/10.1080/00295639.2019.1663089

Simulation of the Nondestructive Assay of 237Np Using Active Neutron Multiplicity Counting

Michael Y. Hua, Braden Goddard, Cody Lloyd, Evan C. Leppink, Sara A. Abraham, Jordan D. Noey, Shaun D. Clarke, Sara A. Pozzi

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 154-162

Technical Paper / dx.doi.org/10.1080/00295639.2019.1654329

Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method

Mohammad Alrwashdeh, Saeed A. Alameri, Ahmed K. Alkaabi

Nuclear Science and Engineering / Volume 194 / Number 2 / February 2020 / Pages 163-167

Technical Paper / dx.doi.org/10.1080/00295639.2019.1672511

 
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