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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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!
Latest Magazine Issues
Mar 2023
Jan 2023
Latest Journal Issues
Nuclear Science and Engineering
April 2023
Nuclear Technology
Fusion Science and Technology
February 2023
Latest News
GEH Nuclear Energy celebrates three-nation plan for BWRX-300 standard design
“I’m glad you came to our party!” said GE Hitachi Nuclear Energy (GEH) chief nuclear officer Nicole Holmes as she prepared to announce that Wilmington, N.C.–based GEH will develop a standard design for its BWRX-300 boiling water small modular reactor with not one but three power producers representing three countries: Tennessee Valley Authority (TVA), Ontario Power Generation (OPG), and Synthos Green Energy (SGE). Celebration was a theme throughout the March 23 event held in Washington, D.C., which was flush with dignitaries representing the United States, Canada, and Poland.
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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
