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Volume 194

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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