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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
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Analytical, Semi-Analytical, and Numerical Heavy-Gas Verification Benchmarks of the Effective Multiplication Factor and Temperature Coefficient
Matthew A. Gonzales, Brian C. Kiedrowski, Anil K. Prinja, Forrest B. Brown
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 1-45
Technical Paper | doi.org/10.1080/00295639.2018.1442546
Modeling of Resonance-Interference Effect in Depleted Fuel Compositions by Pseudo Resonant Isotopes
Qian Zhang, Qiang Zhao, Won Sik Yang, Hongchun Wu
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 46-65
Technical Paper | doi.org/10.1080/00295639.2018.1429174
Acropolis: Novel Approach to Single-Pin Depletion Calculations Using Stochastic Optimization
Lubomír Bureš, Stefano Caruso
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 66-84
Technical Paper | doi.org/10.1080/00295639.2018.1442059
Investigation on the Neutron Transmission of B4C/CF/PI/AA6061 Hybrid Composite Laminates: Experimental and Numerical Simulation Results
Xuelong Fu, Zhengbo Ji, Chunbo Li
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 85-97
Technical Paper | doi.org/10.1080/00295639.2018.1449492
Total Ionizing Dose Effects of SiGe HBTs Induced by 60Co Gamma-Ray Irradiation
Shu-Huan Liu, Aqil Hussain, Da Li, Xiaoqiang Guo, Zhuo-Qi Li, Olarewaju Mubashiru Lawal, Jiangkun Yang, Wei Chen
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 98-103
Technical Paper | doi.org/10.1080/00295639.2018.1450004
Discontinuous Finite Element Quasi-Diffusion Methods
Dmitriy Y. Anistratov, James S. Warsa
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 105-120
Technical Paper | doi.org/10.1080/00295639.2018.1450013
Discrete Eigenvalues of Case Spectrum with Anisotropic Scattering
D. C. Sahni, R. G. Tureci
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 121-135
Technical Paper | doi.org/10.1080/00295639.2018.1463748
Convergence Studies on Nonlinear Coarse-Mesh Finite Difference Accelerations for Neutron Transport Analysis
Hyeon Tae Kim, Yonghee Kim
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 136-149
Technical Paper | doi.org/10.1080/00295639.2018.1463747
Activation Measurements of Cross Sections for Ground and Isomeric States Production in Neutron Threshold Reactions on Y and Au
P. Chudoba, A. Krása, J. Vrzalová, O. Svoboda, S. Kilim, V. Wagner, M. Majerle, M. Štefánik, M. Suchopár, A. Kugler, M. Bielewicz, E. Strugalska-Gola, M. Szuta
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 150-160
Technical Paper | doi.org/10.1080/00295639.2018.1455437
Studies on Reactivity Coefficients of Thorium-Based Fuel (Th-233U)O2 with Molten Salt (Flibe) Cooled Pebble
Indrajeet Singh, Anurag Gupta, Umasankari Kannan
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 161-177
Technical Note | doi.org/10.1080/00295639.2018.1463745
Concept of Stationary Wave Reactor with Rotational Fuel Shuffling
Kazuki Kuwagaki, Jun Nishiyama, Toru Obara
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 178-186
Technical Note | doi.org/10.1080/00295639.2018.1463744
MULTI-PRED: A Software Module for Predictive Modeling of Coupled Multi-Physics Systems
Dan G. Cacuci, Ruixian Fang, Madalina C. Badea
Nuclear Science and Engineering | Volume 191 | Number 2 | August 2018 | Pages 187-202
Computer Code Abstract | doi.org/10.1080/00295639.2018.1451675
A Review of Molten Salt Reactor Kinetics Models
Daniel Wooten, Jeffrey J. Powers
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 203-230
Critical Review | doi.org/10.1080/00295639.2018.1480182
Singular Eigenfunction Expansion Solution for Time-Dependent Neutron Transport with Delayed Neutrons
Jeffery D. Densmore
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 231-247
Technical Paper | doi.org/10.1080/00295639.2018.1466542
Variance Estimation in Monte Carlo Eigenvalue Simulations Using Spectral Analysis Method
Lei Jin, Kaushik Banerjee
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 248-261
Technical Paper | doi.org/10.1080/00295639.2018.1471269
Calculation and Evaluations for n+64,66,67,68,70,natZn Reactions
Jiaqi Hu, Yongli Xu, Yinlu Han
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 262-281
Technical Paper | doi.org/10.1080/00295639.2018.1469334
Investigation of (n, α) Reaction Cross Sections for a Number of Structural Material Isotopes
Tatiana Khromyleva, Ivan Bondarenko, Alexander Gurbich, Vladimir Ketlerov, Vitaly Khryachkov, Pavel Prusachenko
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 282-290
Technical Paper | doi.org/10.1080/00295639.2018.1463746
Developing a Full-Core MCNP6 and RELAP5 Model of the European Pressurized Reactor Using NWURCS
Maria Hendrina Du Toit, Vishana Vivian Naicker
Nuclear Science and Engineering | Volume 191 | Number 3 | September 2018 | Pages 291-304
Computer Code Abstract | doi.org/10.1080/00295639.2018.1468153