American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 181 / Number 3

Volume 181

Number 3

Time Evolving Fission Chain Theory and Fast Neutron and Gamma-Ray Counting Distributions

K. S. Kim, L. F. Nakae, M. K. Prasad, N. J. Snyderman, and J. M. Verbeke

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 225-271

Technical Paper / dx.doi.org/10.13182/NSE14-120

Calculations and Evaluations of n + 113,115,nat.In Reactions up to 200 MeV

Xinwu Su, Zhengjun Zhang, Yinlu Han

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 272-288

Technical Paper / dx.doi.org/10.13182/NSE15-1

Sensitivity of Prompt Neutron Multiplicity to Fission Fragment Characteristics

A. Tudora, F.-J. Hambsch, S. Oberstedt, G. Giubega, I. Visan

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 289-301

Technical Paper / dx.doi.org/10.13182/NSE14-108

The Impact of Neutron Cross Section Group Structures on the Accuracy of Radiological Source Models

A. P. J. Hodgson, R. W. Grimes, M. J. D. Rushton, O. J. Marsden

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 302-309

Technical Paper / dx.doi.org/10.13182/NSE14-156

Impact of Magnesium Oxide Preparation Conditions on Iodine Adsorption Capacity

Pengcheng Li, Matthew T. Bernards

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 310-317

Technical Paper / dx.doi.org/10.13182/NSE15-2

Computation of Fission Product Condensation on Chainlike Aerosols and Agglomerates

Nathan E. White, Sudarshan K. Loyalka

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 318-330

Technical Paper / dx.doi.org/10.13182/NSE15-10

On the Convergence of the Eigenvalue Response Matrix Method

Jeremy A. Roberts, Matthew S. Everson, Benoit Forget

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 331-341

Technical Paper / dx.doi.org/10.13182/NSE14-132

Using Anderson Acceleration to Accelerate the Convergence of Neutron Transport Calculations with Anisotropic Scattering

Jeffrey Willert, H. Park, William Taitano

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 342-350

Technical Paper / dx.doi.org/10.13182/NSE15-16

Applying Nonlinear Diffusion Acceleration to the Neutron Transport k-Eigenvalue Problem with Anisotropic Scattering

Jeffrey Willert, H. Park, William Taitano

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 351-360

Technical Paper / dx.doi.org/10.13182/NSE14-131

Evaluation of Spatial Correction Factors for BRAHMMA Subcritical Assembly

Shefali Bajpai, Tushar Roy, Nirmal Ray, Yogesh Kashyap, Mayank Shukla, Tarun Patel, Amar Sinha

Nuclear Science and Engineering / Volume 181 / Number 3 / November 2015 / Pages 361-367

Technical Paper / dx.doi.org/10.13182/NSE14-137

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement