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Volume 177

Number 3

A Point Kinetics Model of the Medical Isotope Production Reactor Including the Effects of Boiling

C. M. Cooling, M. M. R. Williams, E. T. Nygaard, and M. D. Eaton

Nuclear Science and Engineering / Volume 177 / Number 3 / July 2014 / Pages 233-259

Technical Paper / dx.doi.org/10.13182/NSE13-55

Control Rod Depletion in Sodium-Cooled Fast Reactor: Models and Impact on Reactivity Control

David Blanchet and Bruno Fontaine

Nuclear Science and Engineering / Volume 177 / Number 3 / July 2014 / Pages 260-274

Technical Paper / dx.doi.org/10.13182/NSE13-59

Validation Study of Pin Heat Transfer for UO2 Fuel Based on the IFA-432 Experiments

Aaron M. Phillippe, James E. Banfield, Kevin T. Clarno, Larry J. Ott, Bobby Philip, Mark A. Berrill, Rahul S. Sampath, Srikanth Allu, and Steven P. Hamilton

Nuclear Science and Engineering / Volume 177 / Number 3 / July 2014 / Pages 275-290

Technical Paper / dx.doi.org/10.13182/NSE13-18

Inventory Simulations Under Neutron Irradiation: Visualization Techniques as an Aid to Materials Design

M. R. Gilbert, L. W. Packer, J.-Ch. Sublet, and R. A. Forrest

Nuclear Science and Engineering / Volume 177 / Number 3 / July 2014 / Pages 291-306

Technical Paper / dx.doi.org/10.13182/NSE13-76

Smoothing and Time Series Modeling of Nuclear Material Accounting Data for Protracted Diversion Detection

Tom Burr and Michael S. Hamada

Nuclear Science and Engineering / Volume 177 / Number 3 / July 2014 / Pages 307-320

Technical Paper / dx.doi.org/10.13182/NSE13-86

UO2 Versus MOX: Propagated Nuclear Data Uncertainty for keff, with Burnup

Petter Helgesson, Dimitri Rochman, Henrik Sjöstrand, Erwin Alhassan, and Arjan Koning

Nuclear Science and Engineering / Volume 177 / Number 3 / July 2014 / Pages 321-336

Technical Paper / dx.doi.org/10.13182/NSE13-48

Efficient Use of Monte Carlo: Uncertainty Propagation

D. Rochman, W. Zwermann, S. C. van der Marck, A. J. Koning, H. Sjöstrand, P. Helgesson, and B. Krzykacz-Hausmann

Nuclear Science and Engineering / Volume 177 / Number 3 / July 2014 / Pages 337-349

Technical Paper / dx.doi.org/10.13182/NSE13-32

High-Dimensional Model Representations for the Neutron Transport Equation

Zhengzheng Hu, Ralph C. Smith, Jeffrey Willert, and C. T. Kelley

Nuclear Science and Engineering / Volume 177 / Number 3 / July 2014 / Pages 350-360

Technical Paper / dx.doi.org/10.13182/NSE13-52

Analysis of Example Problems for Monte Carlo Surface Flux Tallies

Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 177 / Number 3 / July 2014 / Pages 361-366

Technical Note / dx.doi.org/10.13182/NSE13-66

 
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