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Number 1

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE14-100

Number 2

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE14-117

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE14-137

Volume 181

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