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Volume 182

Number 4

The Collision Probability Method in Today’s Computer Environment

Dimitar Altiparmakov, Robert Wiersma

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 395-416

Technical Paper / dx.doi.org/10.13182/NSE15-28

Discrete Ordinates Method for the Transport Equation Preserving One-Dimensional Spherical Symmetry in Two-Dimensional Cylindrical Geometry

F. Chaland, G. Samba

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 417-434

Technical Paper / dx.doi.org/10.13182/NSE15-38

A Multilevel Quasi-Static Kinetics Method for Pin-Resolved Transport Transient Reactor Analysis

Ang Zhu, Yunlin Xu, Thomas Downar

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 435-451

Technical Paper / dx.doi.org/10.13182/NSE15-39

A Heat Conduction and Convection Analytical Benchmark for Adjoint Solution Verification of Computational Fluid Dynamics Codes Used in Reactor Design

Dan G. Cacuci, Ruixian Fang, Milica Ilic, Madalina C. Badea

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 452-480

Technical Paper / dx.doi.org/10.13182/NSE15-69

Neutron Multiplicity Counting: Credible Regions for Reconstruction Parameters

Jérôme M. Verbeke

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 481-501

Technical Paper / dx.doi.org/10.13182/NSE15-35

Nuclear Fuel Cycle Transition Analysis Under Uncertainty

U. B. Phathanapirom, E. A. Schneider

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 502-522

Technical Paper / dx.doi.org/10.13182/NSE15-25

Accident-Tolerant-Fuel Performance Analysis of APMT Steel Clad/UO2 Fuel and APMT Steel Clad/UN-U3Si5 Fuel Concepts

Jack Galloway, Cetin Unal

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 523-537

Technical Paper / dx.doi.org/10.13182/NSE15-7

CriSAA: A Simulation Code for Evaluation of Criticality Transients Involving Low Source Start-Up

Jun-Yun Yang, Xiao Gang, Yang-Jun Ying

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 538-554

Technical Paper / dx.doi.org/10.13182/NSE15-44

Uniform Tally Density–Based Strategy for Efficient Global Tallying in Monte Carlo Criticality Calculation

Danhua ShangGuan, Gang Li, Baoyin Zhang, Li Deng, Yan Ma, Yuanguan Fu, Rui Li,Xiaoli Hu

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 555-562

Technical Paper / dx.doi.org/10.13182/NSE15-32

Estimation of Double-Differential Angle-Dependent Neutron Production Cross Sections from Tritons on 197Au at Energies from 5.97 to 19.14 MeV

Manfred Drosg, Bernard Hoop

Nuclear Science and Engineering / Volume 182 / Number 4 / April 2016 / Pages 563-570

Technical Note / dx.doi.org/10.13182/NSE15-57

 
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