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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2021 Student Conference
April 8–10, 2021
Virtual Meeting
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 2021
Jul 2020
Latest Journal Issues
Nuclear Science and Engineering
March 2021
Nuclear Technology
February 2021
Fusion Science and Technology
January 2021
Latest News
Complaint filed with FERC over Grand Gulf management
The Louisiana Public Service Commission (LPSC), the New Orleans City Council, and the Arkansas Public Service Commission on March 2 filed a complaint with the Federal Energy Regulatory Commission against Entergy Corporation, seeking damages of more than $360 million for what they term the utility’s “imprudent operation” of the Grand Gulf nuclear plant.
Located in Port Gibson, Miss., Grand Gulf is a single-unit plant with a 1,433-MWe boiling water reactor. The unit, which entered commercial operation in 1985, supplies power to customers of Entergy Louisiana, Entergy Mississippi, Entergy Arkansas, and Entergy New Orleans.
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Two-Level Convergence Speedup Schemes for p-CMFD Acceleration in Neutron Transport Calculation
Seungsu Yuk, Nam Zin Cho
Nuclear Science and Engineering | Volume 188 | Number 1 | October 2017 | Pages 1-14
Technical Paper | dx.doi.org/10.1080/00295639.2017.1332891
Resonance Self-Shielding Methods for Fast Reactor Calculations—Comparison of a New Tone’s Method with the Subgroup Method in APOLLO3Ⓡ
Li Mao, Igor Zmijarevic, Richard Sanchez
Nuclear Science and Engineering | Volume 188 | Number 1 | October 2017 | Pages 15-32
Technical Paper | dx.doi.org/10.1080/00295639.2017.1332890
Improved Approach to Multiregion Supercritical Transient Analysis Based on the Integral Kinetic Model and Monte Carlo Method
Delgersaikhan Tuya, Hiroki Takezawa, Toru Obara
Nuclear Science and Engineering | Volume 188 | Number 1 | October 2017 | Pages 33-42
Technical Paper | dx.doi.org/10.1080/00295639.2017.1337383
Optimal Run Strategies in Monte Carlo Iterated Fission Source Simulations
Paul K. Romano, Amanda L. Lund, Andrew R. Siegel
Nuclear Science and Engineering | Volume 188 | Number 1 | October 2017 | Pages 43-56
Technical Paper | dx.doi.org/10.1080/00295639.2017.1340692
Fission Chain Restart Theory
K. S. Kim, L. F. Nakae, M. K. Prasad, N. J. Snyderman, J. M. Verbeke
Nuclear Science and Engineering | Volume 188 | Number 1 | October 2017 | Pages 57-84
Technical Paper | dx.doi.org/10.1080/00295639.2017.1340691
Effects of Endcaps and Spacer Pads on Unsteady Fluid Forces and Flow Through a 37-Element CANDU Fuel Bundle
M. Fadaee, S. D. Yu
Nuclear Science and Engineering | Volume 188 | Number 1 | October 2017 | Pages 85-101
Technical Paper | dx.doi.org/10.1080/00295639.2017.1337382
Estimation of d-2H Breakup Neutron Energy Distributions From d-3He
B. Hoop (ret.), S. M. Grimes, M. Drosg
Nuclear Science and Engineering | Volume 188 | Number 1 | October 2017 | Pages 102-107
Technical Note | dx.doi.org/10.1080/00295639.2017.1332892
Kernel Density Estimation of Reaction Rates in Neutron Transport Simulations of Nuclear Reactors
Timothy P. Burke, Brian C. Kiedrowski, William R. Martin
Nuclear Science and Engineering | Volume 188 | Number 2 | November 2017 | Pages 109-139
Technical Paper | dx.doi.org/10.1080/00295639.2017.1350000
Space-Dependent Wielandt Shifts for Multigroup Diffusion Eigenvalue Problems
Ben C. Yee, Brendan Kochunas, Edward W. Larsen, Yunlin Xu
Nuclear Science and Engineering | Volume 188 | Number 2 | November 2017 | Pages 140-159
Technical Paper | dx.doi.org/10.1080/00295639.2017.1350001
A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors
Tengfei Zhang, Yongping Wang, E. E. Lewis, M. A. Smith, W. S. Yang, Hongchun Wu
Nuclear Science and Engineering | Volume 188 | Number 2 | November 2017 | Pages 160-174
Technical Paper | dx.doi.org/10.1080/00295639.2017.1350002
Experimental Investigation of Single- and Two-Phase Diversion Cross Flow in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR
M. P. Sharma, A. K. Nayak
Nuclear Science and Engineering | Volume 188 | Number 2 | November 2017 | Pages 175-186
Technical Paper | dx.doi.org/10.1080/00295639.2017.1339539
The Analysis of Global Stability Boundary and Multistability in the Nonlinear Dynamical System of an Advanced Heavy Water Reactor
Vikas Pandey, Suneet Singh
Nuclear Science and Engineering | Volume 188 | Number 2 | November 2017 | Pages 187-197
Technical Paper | dx.doi.org/10.1080/00295639.2017.1350003
Activation Cross Section and Isomeric Cross-Section Ratio for the (n,2n) Reaction on 113,115In
Junhua Luo, Li Jiang, Suyuan Li
Nuclear Science and Engineering | Volume 188 | Number 2 | November 2017 | Pages 198-206
Technical Paper | dx.doi.org/10.1080/00295639.2017.1352366
Improvement of Nodal Accuracy by Using Albedo-Corrected Parameterized Equivalence Constants
Woosong Kim, Woong Heo, Yonghee Kim
Nuclear Science and Engineering | Volume 188 | Number 3 | December 2017 | Pages 207-245
Technical Paper | dx.doi.org/10.1080/00295639.2017.1354592
Neutron Multiplicity Counting Moments for Fissile Mass Estimation in Scatter-Based Neutron Detection Systems
Tony H. Shin, Michael Y. Hua, Matthew J. Marcath, David L. Chichester, Imre Pázsit, Angela Di Fulvio, Shaun D. Clarke, Sara A. Pozzi
Nuclear Science and Engineering | Volume 188 | Number 3 | December 2017 | Pages 246-269
Technical Paper | dx.doi.org/10.1080/00295639.2017.1354591
Research on the Subchannel Analysis Method via CFD Analysis for PWR
Guangliang Chen, Zhijian Zhang, Zhaofei Tian, Thompson Appah, Lei Li, Xiaomeng Dong, Peizheng Hu
Nuclear Science and Engineering | Volume 188 | Number 3 | December 2017 | Pages 270-281
Technical Paper | dx.doi.org/10.1080/00295639.2017.1367568
Parent Isotopic and Elemental Contributing Factors to Minimize Nuclear Radiological Responses and Optimize Material Composition
Sai Chaitanya Tadepalli, Priti Kanth, P. V. Subhash
Nuclear Science and Engineering | Volume 188 | Number 3 | December 2017 | Pages 282-293
Technical Paper | dx.doi.org/10.1080/00295639.2017.1367570
Microfluidic Alpha Spectrometry of UOX PWR UNF in a Molten Salt
Eric Lukosi
Nuclear Science and Engineering | Volume 188 | Number 3 | December 2017 | Pages 294-302
Technical Paper | dx.doi.org/10.1080/00295639.2017.1367248
