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Volume 189

Number 1 | Number 2 | Number 3

Number 1

Energy Dependent Transport Model of the Neutron Number Probability Distribution in a Subcritical Multiplying Assembly

J. E. M. Saxby, Anil K. Prinja, M. D. Eaton

Nuclear Science and Engineering / Volume 189 / Number 1 / January 2018 / Pages 1-25

Technical Paper / dx.doi.org/10.1080/00295639.2017.1367569

Acceleration and Real Variance Reduction in Continuous-Energy Monte Carlo Whole-Core Calculation via p-CMFD Feedback

YuGwon Jo, Nam Zin Cho

Nuclear Science and Engineering / Volume 189 / Number 1 / January 2018 / Pages 26-40

Technical Paper / dx.doi.org/10.1080/00295639.2017.1373517

Diffusion-Based Finite Element Method to Estimate the Reactivity Changes due to Core Deformation in an SFR

Woong Heo, Yonghee Kim

Nuclear Science and Engineering / Volume 189 / Number 1 / January 2018 / Pages 41-55

Technical Paper / dx.doi.org/10.1080/00295639.2017.1373516

Development, Automation, and Validation of a Numerical Methodology to Assess the TOP Onset for the RIA CABRI Experiments

L. Pantera, P. Querre

Nuclear Science and Engineering / Volume 189 / Number 1 / January 2018 / Pages 56-68

Technical Paper / dx.doi.org/10.1080/00295639.2017.1373519

Thermomechanical Assessment of Fuel Rod Cladding Made of Zirconium Alloy and Silicon Carbide Material During Reactivity-Initiated Accident

David Halabuk, Tomas Navrat

Nuclear Science and Engineering / Volume 189 / Number 1 / January 2018 / Pages 69-81

Technical Paper / dx.doi.org/10.1080/00295639.2017.1373518

Predicting Large Deflections of Multiplate Fuel Elements Using a Monolithic FSI Approach

Franklin G. Curtis, James D. Freels, Kivanc Ekici

Nuclear Science and Engineering / Volume 189 / Number 1 / January 2018 / Pages 82-92

Technical Paper / dx.doi.org/10.1080/00295639.2017.1379304

Lead Void Reactivity Worth in Two Critical Assembly Cores with Differing Uranium Enrichments

M. Fukushima, J. Goda, J. Bounds, T. Cutler, T. Grove, J. Hutchinson, M. James, G. McKenzie, R. Sanchez, A. Oizumi, H. Iwamoto, K. Tsujimoto

Nuclear Science and Engineering / Volume 189 / Number 1 / January 2018 / Pages 93-99

Technical Note / dx.doi.org/10.1080/00295639.2017.1373520

Number 2

A New Collision Probability Approach for Solution of the Transport Equation in the Random Medium of High-Plutonium-Content HTR Lattice Cells

Indrajeet Singh, S. B. Degweker, Anurag Gupta

Nuclear Science and Engineering / Volume 189 / Number 2 / February 2018 / Pages 101-119

Technical Paper / dx.doi.org/10.1080/00295639.2017.1388092

Goal-Oriented Regional Angular Adaptive Algorithm for the SN Equations

Bin Zhang, Liang Zhang, Cong Liu, Yixue Chen

Nuclear Science and Engineering / Volume 189 / Number 2 / February 2018 / Pages 120-134

Technical Paper / dx.doi.org/10.1080/00295639.2017.1394085

Flow Simulations in a Pebble Bed Reactor by a Combined DEM-CFD Approach

Sijun Zhang, Xiang Zhao, Zhi Yang

Nuclear Science and Engineering / Volume 189 / Number 2 / February 2018 / Pages 135-151

Technical Paper / dx.doi.org/10.1080/00295639.2017.1388090

Monte Carlo Methods for Reactor Kinetic Simulations

Argala Srivastava, K. P. Singh, S. B. Degweker

Nuclear Science and Engineering / Volume 189 / Number 2 / February 2018 / Pages 152-170

Technical Paper / dx.doi.org/10.1080/00295639.2017.1388091

Development of Generalized Perturbation Theory Algorithms for Monte Carlo Eigenvalue Calculations

Sung Hoon Choi, Hyung Jin Shim, Chang Hyo Kim

Nuclear Science and Engineering / Volume 189 / Number 2 / February 2018 / Pages 171-187

Technical Paper / dx.doi.org/10.1080/00295639.2017.1388089

HORUS3D/N Neutron Calculation Tool, a Deterministic Scheme Dedicated to JHR Design and Safety Studies

F. Jeury, J. Politello, C. D’Aletto, L. Gaubert, C. Vaglio-Gaudard, J. F. Vidal, J. M. Vidal

Nuclear Science and Engineering / Volume 189 / Number 2 / February 2018 / Pages 188-198

Computer Code Abstract / dx.doi.org/10.1080/00295639.2017.1381505

Number 3

Monte Carlo Perturbation Theory Estimates of Sensitivities to System Dimensions

Timothy P. Burke, Brian C. Kiedrowski

Nuclear Science and Engineering / Volume 189 / Number 3 / March 2018 / Pages 199-223

Technical Paper / dx.doi.org/10.1080/00295639.2017.1388093

A Study on Reconstruction of Intrapin Power Distribution in Pinwise Two-Group Diffusion Analysis

Xuan Ha Nguyen, Yonghee Kim

Nuclear Science and Engineering / Volume 189 / Number 3 / March 2018 / Pages 224-242

Technical Paper / dx.doi.org/10.1080/00295639.2017.1394086

Treatment of Double Heterogeneity in the Resonance and Thermal Energy Regions in High-Temperature Reactors

Indrajeet Singh, S. B. Degweker, Anurag Gupta

Nuclear Science and Engineering / Volume 189 / Number 3 / March 2018 / Pages 243-258

Technical Paper / dx.doi.org/10.1080/00295639.2017.1402568

An Accurate Globally Conservative Subdomain Discontinuous Least-Squares Scheme for Solving Neutron Transport Problems

Weixiong Zheng, Ryan G. McClarren, Jim E. Morel

Nuclear Science and Engineering / Volume 189 / Number 3 / March 2018 / Pages 259-271

Technical Paper / dx.doi.org/10.1080/00295639.2017.1407592

A Local Adaptive Coarse-Mesh Nonlinear Diffusion Acceleration Scheme for Neutron Transport Calculations

Sicong Xiao, Kangyu Ren, Dean Wang

Nuclear Science and Engineering / Volume 189 / Number 3 / March 2018 / Pages 272-281

Technical Paper / dx.doi.org/10.1080/00295639.2017.1394088

Surrogate Fluid Experimental Study and CFD Simulation on the Hydraulic Characteristics of Vortex Diode

Shi-Xiang Qu, Yan-Hua Wu, Zhao-Zhong He, Kun Chen

Nuclear Science and Engineering / Volume 189 / Number 3 / March 2018 / Pages 282-289

Technical Paper / dx.doi.org/10.1080/00295639.2017.1405652

Experimental Research on Fluid-Elastic Instability in Tube Bundles Subjected to Air-Water Cross Flow

Baoqing Liu, Ruijia Cheng, Yanan Zhang, Xiaoge Chen, Zilong Xu

Nuclear Science and Engineering / Volume 189 / Number 3 / March 2018 / Pages 290-300

Technical Note / dx.doi.org/10.1080/00295639.2017.1394084

 
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