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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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 Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Terrestrial Energy looks at EnergySolutions-owned sites for IMSR plants
Advanced reactor developer Terrestrial Energy and Utah-based waste management company EnergySolutions announced they have signed a memorandum of understanding to collaborate on the siting and deployment of Terrestrial Energy’s integral molten salt reactor plants at EnergySolutions-owned sites.
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Best-Estimate Predictions and Model Calibration for Reactor Thermal Hydraulics
Madalina C. Badea, Dan G. Cacuci, Aurelian F. Badea
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 1-19
Technical Paper | doi.org/10.13182/NSE11-10
Fission Neutron Spectrum Sensitivity Study for the Case of Advanced Heavy Water Reactor
Anek Kumar, S. Ganesan
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 20-32
Technical Paper | doi.org/10.13182/NSE11-16
A Robust Arbitrarily High-Order Transport Method of the Characteristic Type for Unstructured Grids
Rodolfo M. Ferrer, Yousry Y. Azmy
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 33-51
Technical Paper | doi.org/10.13182/NSE10-106
Nonlinear Acceleration of Transport Criticality Problems
H. Park, D. A. Knoll, C. K. Newman
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 52-65
Technical Paper | doi.org/10.13182/NSE11-81
Generation of Few-Group Diffusion Theory Constants by Monte Carlo Code McCARD
Ho Jin Park, Hyung Jin Shim, Han Gyu Joo, Chang Hyo Kim
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 66-77
Technical Paper | doi.org/10.13182/NSE11-22
Simulation of Neutron Pulse Height Distributions with a Response Matrix Method
S. Prasad, S. D. Clarke, S. A. Pozzi, E. W. Larsen
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 78-86
Technical Paper | doi.org/10.13182/NSE11-60
Neutron Interactions with 3He Revisited—I: Elastic Scattering Around and Beyond 10 MeV
M. Drosg, R. Avalos Ortiz, P. W. Lisowski
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 87-101
Technical Paper | doi.org/10.13182/NSE11-66
Theoretical Calculations and Analysis of n + 27Al Reaction
Yinlu Han, Yongli Xu, Haiying Liang, Hairui Guo, Chonghai Cai, Qingbiao Shen
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 102-121
Technical Paper | doi.org/10.13182/NSE11-28
Measurements of the 71Ga(n,)72m+gGa Cross Section in the Neutron Energy Range of 13.5 to 14.8 MeV
Junhua Luo, Rong Liu, Li Jiang
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 122-126
Technical Note | doi.org/10.13182/NSE11-109
Asymptotic Wielandt Method and Superhistory Method for Source Convergence in Monte Carlo Criticality Calculation
Ding She, Kan Wang, Ganglin Yu
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 127-137
Technical Paper | doi.org/10.13182/NSE11-44
Calculating the Second Eigenpair in Criticality Calculations Using the Monte Carlo Method with Source Points Pairing as an Efficient Net-Weight (Cancellation) Algorithm
Bo Shi, Bojan Petrovic
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 138-150
Technical Paper | doi.org/10.13182/NSE11-19
A Monte Carlo Code for Radiation Damage by Neutrons
V. Kumar, Nagendra Singh Raghaw, H. S. Palsania
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 151-163
Technical Paper | doi.org/10.13182/NSE11-41
Zero Variance Penalty Model for the Generation of Covariance Matrices in Integral Data Assimilation Problems
G. Noguere, P. Archier, C. De Saint Jean, B. Habert
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 164-179
Technical Paper | doi.org/10.13182/NSE11-72
Uncertainty Quantification for New Approaches to Spent Fuel Assay
Tom Burr, Jeremy Conlin, Jianwei Hu, Jack Galloway, Vladimir Henzl, Howard Menlove, Martyn Swinhoe, Stephen Tobin, Holly Trellue, Timothy Ulrich
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 180-192
Technical Paper | doi.org/10.13182/NSE11-73
Explicit Flux Autocorrelation Dependence on Dominance Ratio in Monte Carlo Criticality Calculations of Large Cores
Sergey S. Gorodkov
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 193-201
Technical Paper | doi.org/10.13182/NSE11-105
Dispersion Properties of B4C Microparticles as Emergency Neutron Absorbers in Spent-Fuel Pool Water
You-Jin Jung, Jaesik Hwang, Jei-Won Yeon, Bong Hyun Boo, Kyuseok Song
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 202-207
Technical Paper | doi.org/10.13182/NSE11-98
Fluctuations of Mass Yield Distribution for the Epithermal Fission of 235U and Its Impact on HCLWR Calculations
P. Leconte, J.-P. Hudelot, M. Antony
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 208-215
Technical Paper | doi.org/10.13182/NSE11-33
A Parallel Krylov-Based Adjoint Sensitivity Analysis Procedure
R. T. Evans, D. G. Cacuci
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 216-222
Technical Note | doi.org/10.13182/NSE11-110
Revisiting Insights from Three Mile Island Unit 2 Postaccident Examinations and Evaluations in View of the Fukushima Daiichi Accident
Joy Rempe, Mitchell Farmer, Michael Corradini, Larry Ott, Randall Gauntt, Dana Powers
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 223-248
Technical Paper | doi.org/10.13182/NSE12-3
Critical Heat Flux in TRIGA-Fueled Reactors Cooled by Natural Convection
Michael Avery, Jun Yang, Mark Anderson, Michael Corradini, Earl Feldman, Floyd Dunn, James Matos
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 249-258
Technical Paper | doi.org/10.13182/NSE11-69
Utilization of Discontinuity Factor in Integrodifferential Type of Boltzmann Transport Equation
Akio Yamamoto
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 259-267
Technical Paper | doi.org/10.13182/NSE11-88
Beryllium and Graphite Neutron Total Cross-Section Measurements from 0.4 to 20 MeV
M. J. Rapp, Y. Danon, F. J. Saglime, R. M. Bahran, D. G. Williams, G. Leinweber, D. P. Barry, R. C. Block
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 268-277
Technical Paper | doi.org/10.13182/NSE11-55
New Analysis of Neutron-Induced Reactions at 14.5 MeV
N. V. Kornilov, S. M. Grimes, A. Voinov
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 278-286
Technical Paper | doi.org/10.13182/NSE11-61
Random Adjustment of the H in H2O Neutron Thermal Scattering Data
D. Rochman, A. J. Koning
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 287-299
Technical Paper | doi.org/10.13182/NSE12-2
Statistical Theory of Fission Chains and Generalized Poisson Neutron Counting Distributions
Manoj K. Prasad, Neal J. Snyderman
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 300-326
Technical Paper | doi.org/10.13182/NSE11-86
Estimation of Reactivity in a Research Reactor by Using a Second-Order Sliding Mode Observer
Syed Hameed Qaiser, Masood Iqbal, Aamer Iqbal Bhatti, Raza Samar, Javed Qadir
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 327-336
Technical Paper | doi.org/10.13182/NSE11-46
