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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
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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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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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Assigning Uncertainties to Scientific Data
F. H. Fröhner
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 1-18
Technical Paper | doi.org/10.13182/NSE97-A24453
Space-Dependent Resonance Self-Shielding
Mark L. Williams, R. Raharjo
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 19-34
Technical Paper | doi.org/10.13182/NSE97-2
Extension of Analytic Function Expansion Nodal Method to Multigroup Problems in Hexagonal-Z Geometry
Nam Zin Cho, Yong Hee Kim, Keon Woo Park
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 35-47
Technical Paper | doi.org/10.13182/NSE97-A24455
Simplified Spherical Harmonics in the Variational Nodal Method
E. E. Lewis, G. Palmiotti
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 48-58
Technical Paper | doi.org/10.13182/NSE97-A24456
An Assessment of the Continuous Neutron Source Using a Low-Energy Electron Accelerator
Takeshi Kase, Hideo Harada
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 59-70
Technical Paper | doi.org/10.13182/NSE97-A24457
Uniform Particle Beam Distributions Produced by Octupole Focusing
N. Tsoupas, M. S. Zucker, T. E. Ward, C. L. Snead, Jr.
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 71-79
Technical Paper | doi.org/10.13182/NSE97-A24458
Physics Study on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU (DUPIC)
Hangbok Choi, Bo W. Rhee, Hyunsoo Park
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 80-93
Technical Paper | doi.org/10.13182/NSE97-A24459
Weapons-Grade Plutonium Burning with High-Temperature Gas-Cooled Reactors Using Plutonium Burner Balls and Thorium Breeder Balls
Kiyonobu Yamashita, Kazumi Tokuhara, Nozomu Fujimoto
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 94-100
Technical Paper | doi.org/10.13182/NSE97-A24460
Neutron-Induced Reaction Cross Sections Between 9 and 14 MeV
Julio Cezar Suita, Arthur Gerbasi da Silva, Luiz Telmo Auler, Solange de Barros
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 101-107
Technical Paper | doi.org/10.13182/NSE97-A24461
Air-Water Experiment for Annular Flow Pressure Drop in a Small Pipe
Martin A. Lopez de Bertodano, Jian-Feng Shi,Stephen G. Beus
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 108-114
Technical Paper | doi.org/10.13182/NSE97-A24462
A Control Algorithm Capable of Handling Steam Generator Water Level Swell and Shrinkage
Byung Soo Moon
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 115-118
Technical Paper | doi.org/10.13182/NSE97-A24463
Data for the Chilton-Huddleston Photon-Albedo Approximations
Ronald C. Brockhoff, J. Kenneth Shultis, Richard E. Faw
Nuclear Science and Engineering | Volume 126 | Number 1 | May 1997 | Pages 119-126
Technical Note | doi.org/10.13182/NSE97-A24464
Monte Carlo Estimation of Generalized Unreliability in Probabilistic Dynamics—I: Application to a Pressurized Water Reactor Pressurizer
P. E. Labeau
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 131-145
Technical Paper | doi.org/10.13182/NSE97-A24467
Monte Carlo Estimation of Generalized Unreliability in Probabilistic Dynamics—II: Handling Uncertainties in Parameters
P. E. Labeau, Z. Ould Amar
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 146-157
Technical Paper | doi.org/10.13182/NSE97-A24468
High-Probability One-Sided Confidence Intervals in Reliability Models
Enrique Castillo, Cristina Solares, Patricia Gómez
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 158-167
Technical Paper | doi.org/10.13182/NSE97-A24469
The 14N(n,n′γ) Cross Section of the 2.313-MeV First Excited State
P. Staples, J. J. Egan, G. H. R. Kegel, A. Mittler
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 168-175
Technical Paper | doi.org/10.13182/NSE97-A24470
Gamma and Neutron Dosimetry Using CaF2:Tm Thermoluminescent Dosimeters for Fusion Reactor Shielding Experiments
M. Angelone, P. Batistoni, M. Pillon, V. Rado, A. Esposito
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 176-186
Technical Paper | doi.org/10.13182/NSE97-A24471
Measurement of Gamma-Ray Spectra and Heating Rates in Iron and Stainless Steel Shields Bombarded by Deuterium-Tritium Neutrons and Validation of Secondary-Gamma-Ray Data in Evaluated Nuclear Data Libraries
F. Maekawa, Y. Oyama, C. Konno, M. Wada, Y. Ikeda
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 187-200
Technical Paper | doi.org/10.13182/NSE97-A24472
Fission Cross-Section Measurements of 241Am Between 0.1 eV and 10 keV with Lead Slowing-Down Spectrometer and at Thermal Neutron Energy
Shuji Yamamoto, Katsuhei Kobayashi, Mitsuharu Miyoshi, Itsuro Kimura, Ikuo Kanno, Nobuo Shinohara, Yoshiaki Fujita
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 201-212
Technical Paper | doi.org/10.13182/NSE97-A24473
Alkaline Peroxide Processing of Low-Enriched Uranium Targets for 99Mo Production—Decomposition of Hydrogen Peroxide
Daojie Dong, George F. Vandegrift
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 213-223
Technical Paper | doi.org/10.13182/NSE97-A24474
Effective Atomic Numbers of Low-Z Compounds for Photon Interaction
S. Guru Prasad, K. Parthasaradhi, W. D. Bloomer
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 224-228
Technical Paper | doi.org/10.13182/NSE97-A24475
Critical Flow of Initially Highly Subcooled Water Through a Short Capillary
S. M. Ghiaasiaan, J. R. Muller, D. L. Sadowski, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 229-238
Technical Paper | doi.org/10.13182/NSE97-A24476
The ASYNT Adjoint Synthesis Method for Neutron Irradiation Assessment of VVER/Pressurized Water Reactor Pressure Vessel
Sergey I. Belousov, Krassimira D. Ilieva
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 239-244
Technical Paper | doi.org/10.13182/NSE97-A24477
Advances in the Development of a Subgroup Method for the Self-Shielding of Resonant Isotopes in Arbitrary Geometries
Alain Hébert
Nuclear Science and Engineering | Volume 126 | Number 3 | July 1997 | Pages 245-263
Technical Paper | doi.org/10.13182/NSE97-A24479
Exponential Characteristic Nonlinear Radiation Transport Method for Unstructured Grids of Triangular Cells
Kirk A. Mathews, Charles R. Brennan
Nuclear Science and Engineering | Volume 126 | Number 3 | July 1997 | Pages 264-281
Technical Paper | doi.org/10.13182/NSE97-A24480
Variational Estimates for Use with the Improved Quasistatic Method for Reactor Dynamics
J. A. Favorite, W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 126 | Number 3 | July 1997 | Pages 282-292
Technical Paper | doi.org/10.13182/NSE97-A24481
The Green's Function Method for Nuclear Engineering Applications
Drew E. Kornreich, Barry D. Ganapol
Nuclear Science and Engineering | Volume 126 | Number 3 | July 1997 | Pages 293-313
Technical Paper | doi.org/10.13182/NSE97-A24482
A Measurement-Based Method to Determine the Photofission Contribution to Fission Rate
R. Venkataraman, R. F. Fleming, E. D. McGarry
Nuclear Science and Engineering | Volume 126 | Number 3 | July 1997 | Pages 314-323
Technical Paper | doi.org/10.13182/NSE97-A24483
Delayed Neutron Energy Spectra of 87Br, 88Br, 89Br, 90 Br, 137l, 138l, 139l, and 136Te
R. C. Greenwood, K. D. Watts
Nuclear Science and Engineering | Volume 126 | Number 3 | July 1997 | Pages 324-332
Technical Paper | doi.org/10.13182/NSE97-A24484
The Potential of Accelerator-Driven Systems for Transmutation or Power Production Using Thorium or Uranium Fuel Cycles
M. Salvatores, I. Slessarev, A. Tchistiakov, G. Ritter
Nuclear Science and Engineering | Volume 126 | Number 3 | July 1997 | Pages 333-340
Technical Paper | doi.org/10.13182/NSE97-A24485
Evidence of Source Dominance in the Dynamic Behavior of Accelerator-Driven Systems
R. A. Rydin, M. L. Woosley, Jr.
Nuclear Science and Engineering | Volume 126 | Number 3 | July 1997 | Pages 341-344
Technical Note | doi.org/10.13182/NSE97-A24486