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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
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 Science and Engineering
October 2024
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August 2024
Latest News
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
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Neutron Capture and Transmission Measurements and Resonance Parameter Analysis of Samarium
G. Leinweber, J. A. Burke, H. D. Knox, N. J. Drindak, D. W. Mesh, W. T. Haines, R. V. Ballad, R. C. Block, R. E. Slovacek, C. J. Werner, M. J. Trbovich, D. P. Barry, T. Sato
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 1-21
Technical Paper | doi.org/10.13182/NSE02-A2283
Radiological Hazard of Spallation Products in Accelerator-Driven System
M. Saito, A. Stankovskii, V. Artisyuk, Yu. Korovin, A. Shmelev, Yu. Titarenko
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 22-36
Technical Paper | doi.org/10.13182/NSE02-A2284
Organization for Economic Cooperation and Development/Nuclear Energy Agency International Benchmark on the VENUS-2 MOX Core Measurements
Byung-Chan Na, Enrico Sartori
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 37-47
Technical Note | doi.org/10.13182/NSE02-A2285
Computational Experience with the Reich-Moore Resolved-Resonance Equations in the AMPX Cross-Section Processing System
M. E. Dunn
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 48-56
Technical Note | doi.org/10.13182/NSE02-A2286
Spatial Adaptivity Applied to the Variational Nodal Pn Equations
Hui Zhang, E. E. Lewis
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 57-63
Technical Note | doi.org/10.13182/NSE02-A2287
Convergence Analysis of Additive Angular Dependent Rebalance Acceleration for the Discrete Ordinates Transport Calculations
Chang Je Park, Nam Zin Cho
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 64-74
Technical Note | doi.org/10.13182/NSE02-A2288
Single-Ray Streaming Behavior for Discontinuous Finite Element Spatial Discretizations
R. P. Smedley-Stevenson
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 75-84
Technical Note | doi.org/10.13182/NSE02-A2289
Adaptive Mesh Refinement for the Time-Dependent Nodal Integral Method
Allen J. Toreja, Rizwan-uddin
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 85-95
Technical Note | doi.org/10.13182/NSE02-A2290
Assessment of Reactivity Effects due to Localized Perturbations in BWR Lattices
R. van Geemert, F. Jatuff, P. Grimm, R. Chawla
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 96-106
Technical Note | doi.org/10.13182/NSE02-A2291
Boiling Water Reactor Fuel Assembly Axial Design Optimization Using Tabu Search
C. Martín-del-Campo, J. L. François, L. B. Morales
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 107-115
Technical Note | doi.org/10.13182/NSE02-A2292
Optimization of Boiling Water Reactor Loading Pattern Using Two-Stage Genetic Algorithm
Yoko Kobayashi, Eitaro Aiyoshi
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 119-139
Technical Paper | doi.org/10.13182/NSE02-A2293
Dead-Time Effects on Counting Statistics in Subcritical Nuclear Systems
Felix C. Difilippo
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 140-149
Technical Paper | doi.org/10.13182/NSE02-A2294
Effects of Backscattering on One-Dimensional Electron Beam Transport
F. Andersson, H. Smith, D. Anderson, M. Lisak, P. Helander
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 150-157
Technical Paper | doi.org/10.13182/NSE02-A2295
Photon Leakage from Spherical and Hemispherical Samples with a Central 14-MeV Neutron Source
A. I. Saukov, B. I. Sukhanov, A. M. Ryabinin, V. D. Lyutov, V. M. Shmakov, A. P. Vasiliev
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 158-164
Technical Paper | doi.org/10.13182/NSE02-A2296
Matrix Diffusion of Radionuclides from a Finite Porous Rock Matrix to a Fracture: Importance of Back-Diffusion with a Constant Inlet Boundary Condition
Jin Beak Park, Yong Soo Hwang, Chul Hyung Kang
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 165-176
Technical Paper | doi.org/10.13182/NSE02-A2297
Neutron and Proton Cross-Section Evaluations for 232Th up to 150 MeV
A. V. Ignatyuk, V. P. Lunev, Yu. N. Shubin, E. V. Gai, N. N. Titarenko, W. Gudowski
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 177-194
Technical Paper | doi.org/10.13182/NSE02-A2298
Analysis for Cross Sections of (p,xn) Reactions on 208Pb at Intermediate Energies by Using Quantum Molecular Dynamics
Sheng Fan, Zhuaxia Li, Zhixiang Zhao
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 195-202
Technical Paper | doi.org/10.13182/NSE02-A2299
Differential Cross-Section Measurement for the 10B(n,)7Li Reaction
Guohui Zhang, Guoyou Tang, Jinxiang Chen, Songbai Zhang, Zhaomin Shi, Jing Yuan, Zemin Chen, Yu. M. Gledenov, M. Sedysheva, G. Khuukhenkhuu
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 203-206
Technical Paper | doi.org/10.13182/NSE02-A2300
UNF Code for Fast Neutron Reaction Data Calculations
Jingshang Zhang
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 207-219
Technical Paper | doi.org/10.13182/NSE02-02
A Numerical Model for Evaluating the Impact of Noble Metal Chemical Addition in Boiling Water Reactors
Tsung-Kuang Yeh
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 220-229
Technical Paper | doi.org/10.13182/NSE01-72
PCCSAC: A Three-Dimensional Code for AC600 Passive Containment Cooling System Analysis
Jiyang Yu, Baoshan Jia
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 230-236
Technical Paper | doi.org/10.13182/NSE02-A2303
Observations of Confined Spray-Driven Air Vortices
Douglas W. Stamps
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 237-243
Technical Note | doi.org/10.13182/NSE02-A2304
Computing Moment-Based Probability Tables for Self-Shielding Calculations in Lattice Codes
Alain Hébert, Mireille Coste
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 245-257
Technical Paper | doi.org/10.13182/NSE01-56
Simulation of Mixed-Oxide and Low-Enriched Uranium Fuel Burnup in a Pressurized Water Reactor and Validation Against Destructive Analysis Results
B. D. Murphy, R. T. Primm III
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 258-269
Technical Paper | doi.org/10.13182/NSE02-A2306
Finite Element Solution of the Self-Adjoint Angular Flux Equation for Coupled Electron-Photon Transport
Jennifer L. Liscum-Powell, Anil B. Prinja, Jim E. Morel, Leonard J. Lorence, Jr.
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 270-291
Technical Paper | doi.org/10.13182/NSE142-270
Comparative Measures of Radionuclide Containment in the Crystalline Geophere
V. Cvetkovic, S. Painter, J. O. Selroos
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 292-304
Technical Paper | doi.org/10.13182/NSE02-A2308
Mechanisms of Positive Temperature Reactivity Coefficients of Dilute Plutonium Solutions
Toshihiro Yamamoto, Yoshinori Miyoshi
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 305-314
Technical Paper | doi.org/10.13182/NSE02-A2309
A Spent-Fuel Combination Method for Minimizing Composition Variability of DUPIC Fuel
Man Gyun Na, Won Il Ko, Hangbok Choi
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 315-326
Technical Paper | doi.org/10.13182/NSE02-A2310
An Alternative Implementation of the Differential Operator (Taylor Series) Perturbation Method for Monte Carlo Criticality Problems
Jeffrey A. Favorite
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 327-341
Technical Paper | doi.org/10.13182/NSE02-A2311
Photon Interaction Studies with Some Glasses and Building Materials
Harvinder Singh, Kulwant Singh, Gopi Sharma, R. Nathuram, H. S. Sahota
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 342-348
Technical Paper | doi.org/10.13182/NSE02-A2312
BOT3P: Bologna Transport Analysis Pre-Post-Processors Version 1.0
Roberto Orsi
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 349-354
Technical Note | doi.org/10.13182/NSE02-A2313