ANS / Publications / Journals / Nuclear Science and Engineering

Whole-Core Transport Solutions with 2-D/1-D Fusion Kernel via p-CMFD Acceleration and p-CMFD Embedding of Nonoverlapping Local/Global Iterations

Seungsu Yuk, Nam Zin Cho

Nuclear Science and Engineering / Volume 181 / Number 1 / September 2015 / Pages 1-16

Technical Paper / dx.doi.org/10.13182/NSE14-88

Whisper: Sensitivity/Uncertainty-Based Computational Methods and Software for Determining Baseline Upper Subcritical Limits

Brian C. Kiedrowski, Forrest B. Brown, Jeremy L. Conlin, Jeffrey A. Favorite, Albert C. Kahler, Alyssa R. Kersting, D. Kent Parsons, Jessie L. Walker

Nuclear Science and Engineering / Volume 181 / Number 1 / September 2015 / Pages 17-47

Technical Paper / dx.doi.org/10.13182/NSE14-99

Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Difficult Shielding Problems

Ahmad M. Ibrahim, Paul P. H. Wilson, Mohamed E. Sawan, Scott W. Mosher, Douglas E. Peplow, John C. Wagner, Thomas M. Evans, Robert E. Grove

Nuclear Science and Engineering / Volume 181 / Number 1 / September 2015 / Pages 48-59

Technical Paper / dx.doi.org/10.13182/NSE14-94

Computing More Consistent Multigroup Nuclear Data Covariances

Risto Vanhanen

Nuclear Science and Engineering / Volume 181 / Number 1 / September 2015 / Pages 60-71

Technical Paper / dx.doi.org/10.13182/NSE14-105

An Implicit Correlation Method for Cross-Correlation Sampling, with MCNPX-PoliMi Validation

Matthew J. Marcath, Shaun D. Clarke, Brian M. Wieger, Enrico Padovani, Edward W. Larsen, Sara A. Pozzi

Nuclear Science and Engineering / Volume 181 / Number 1 / September 2015 / Pages 72-81

Technical Paper / dx.doi.org/10.13182/NSE14-89

Analysis of Local Void Coefficients of Reactivity in the Reduced-Moderation BWR

Jeffrey E. Seifried, Ehud Greenspan

Nuclear Science and Engineering / Volume 181 / Number 1 / September 2015 / Pages 82-95

Technical Paper / dx.doi.org/10.13182/NSE14-104

Experimental Study of Neutron Initiation Probability at CFBR-II with Pulsed Neutrons

Liu Xiaobo, Peng Xianjue, Lei Jiarong, Fan Xiaoqiang, Du Jinfeng, Gao Hui

Nuclear Science and Engineering / Volume 181 / Number 1 / September 2015 / Pages 96-104

Technical Paper / dx.doi.org/10.13182/NSE14-100

Burnup Credit Implementation for PWR UOX Used Fuel Assemblies in France: From Study to Practical Experience

L. Jutier, C. Riffard, A. Santamarina, E. Guillou, G. Grassi, D. Lecarpentier, F. Lauvaud, A. Coulaud, M. Hampartzounian, M. Tardy, S. Kitsos

Nuclear Science and Engineering / Volume 181 / Number 2 / October 2015 / Pages 105-136

Technical Paper / dx.doi.org/10.13182/NSE14-51

Computation of Aerosol Evolution Under Coagulation

Shawn A. Campbell, Sudarshan K. Loyalka

Nuclear Science and Engineering / Volume 181 / Number 2 / October 2015 / Pages 137-159

Technical Paper / dx.doi.org/10.13182/NSE14-91

Uncertainty Quantification of LWR Core Characteristics Using Random Sampling Method

Akio Yamamoto, Kuniharu Kinoshita, Tomoaki Watanabe, Tomohiro Endo, Yasuhiro Kodama, Yasunori Ohoka, Tadashi Ushio, Hiroaki Nagano

Nuclear Science and Engineering / Volume 181 / Number 2 / October 2015 / Pages 160-174

Technical Paper / dx.doi.org/10.13182/NSE14-152

Cobalt Radioactivity Behaviors in a BWR Environment and Countermeasures for Dose Rate Reduction

Motomasa Fuse, Makoto Nagase, Naoshi Usui, Yoshiteru Sato, Motohiro Aizawa, Tsuyoshi Ito, Hideyuki Hosokawa, Yoichi Wada, Kazushige Ishida

Nuclear Science and Engineering / Volume 181 / Number 2 / October 2015 / Pages 175-190

Technical Paper / dx.doi.org/10.13182/NSE14-101

The Oxidation Behavior of Iodide Ion Under Gamma Irradiation Conditions

Sang-Hyuk Jung, Jei-Won Yeon, Sue Young Hong, Yong Kang, Kyuseok Song

Nuclear Science and Engineering / Volume 181 / Number 2 / October 2015 / Pages 191-203

Technical Paper / dx.doi.org/10.13182/NSE14-87

Influence of Local Spectral Variations on Control-Rod Homogenization in Fast Reactor Environments

M. Andersson, D. Blanchet, H. Nylén, R. Jacqmin

Nuclear Science and Engineering / Volume 181 / Number 2 / October 2015 / Pages 204-215

Technical Paper / dx.doi.org/10.13182/NSE14-106

Fabrication of Uniform Ce/Eu Oxide Microparticles by a Microfluidic Co-Sol-Gel Process as an Analog Preparation of MA-Bearing Ceramic Nuclear Fuel Particles

Ya-Ting Yang, Xiang Li, Cao-Fei Fu, Tong Song, Zhen-Qi Chang, Da-Qiao Meng, Christophe A. Serra

Nuclear Science and Engineering / Volume 181 / Number 2 / October 2015 / Pages 216-224

Technical Paper / dx.doi.org/10.13182/NSE14-117

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