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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Technology
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November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2017.1373520
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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2017.1381505
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 | 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 | doi.org/10.1080/00295639.2017.1394086
Treatment of Double Heterogeneity in the Resonance and Thermal Energy Regions in High-Temperature Reactors
Nuclear Science and Engineering | Volume 189 | Number 3 | March 2018 | Pages 243-258
Technical Paper | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2017.1394084
