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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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The International Criticality Safety Benchmark Evaluation Project
J. Blair Briggs, Lori Scott, Ali Nouri
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 1-10
Technical Paper | doi.org/10.13182/NSE03-14
DICE: Database for the International Criticality Safety Benchmark Evaluation Program Handbook
Ali Nouri, Pierre Nagel, J. Blair Briggs, Tatiana Ivanova
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 11-19
Technical Paper | doi.org/10.13182/NSE03-15
The Benchmark Evaluation Process: From Experimental Data to Benchmark Model
Virginia A. F. Dean
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 20-38
Technical Paper | doi.org/10.13182/NSE03-16
Criticality Experiments Performed in Saclay and Valduc Centers, France (1958-2002)
F. Barbry, P. Grivot, E. Girault, P. Fouillaud, P. Cousinou, G. Poullot, J. Anno, J. M. Bordy, D. Doutriaux
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 39-63
Technical Paper | doi.org/10.13182/NSE03-A2362
A Historical Review of Critical Experiment Research Facilities in the United Kingdom
D. N. Simister, P. D. Clemson
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 64-71
Technical Paper | doi.org/10.13182/NSE03-A2363
Critical Experiment Programs at the Los Alamos National Laboratory in Support of the U.S. Department of Energy/National Nuclear Security Administration's Nuclear Criticality Safety Program
Steven D. Clement
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 72-83
Technical Paper | doi.org/10.13182/NSE03-A2364
Criticality Safety Benchmark Experiments Derived from Argonne National Laboratory Zero Power Reactor Assemblies
R. W. Schaefer, R. M. Lell, R. D. McKnight
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 84-96
Technical Paper | doi.org/10.13182/NSE03-A2365
Influence of the Correlations of Experimental Uncertainties on Criticality Prediction
T. T. Ivanova, M. N. Nikolaev, K. F. Raskach, E. V. Rozhikhin, A. M. Tsiboulia
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 97-104
Technical Paper | doi.org/10.13182/NSE03-27
Analysis of the First Three Zeus Critical Experiments
Russell D. Mosteller, Roger W. Brewer, Peter J. Jaegers
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 105-119
Technical Paper | doi.org/10.13182/NSE03-A2367
Use of International Criticality Safety Benchmark Evaluation Project Data to Benchmark a JEF2.2-Based Library for MONK
David Hanlon, Nigel Smith, Jim Gulliford
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 120-131
Technical Paper | doi.org/10.13182/NSE03-A2368
Validating JENDL-3.3 for Water-Reflected Low-Enriched Uranium Solution Systems Using STACY ICSBEP Benchmark Models
Toshihiro Yamamoto, Yoshinori Miyoshi, Takehide Kiyosumi
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 132-144
Technical Paper | doi.org/10.13182/NSE03-A2369
Research Reactor Benchmarks
Matjaz Ravnik, Robert Jeraj
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 145-152
Technical Paper | doi.org/10.13182/NSE03-A2370
Use of International Criticality Safety Benchmark Evaluation Project Benchmarks for the Validation of CSAS26 (Scale 4.4a) for Configurations of Low-Enriched Uranium
Óscar Zurrón, Guillermo Sánchez, Carolina Álvaro
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 153-159
Technical Paper | doi.org/10.13182/NSE03-A2371
The Critical Mass Laboratory at Rocky Flats
Robert E. Rothe
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 161-172
Technical Paper | doi.org/10.13182/NSE03-A2372
A Brief History of the Lawrence Radiation Laboratory Criticality Facility
David P. Heinrichs, Stephen C. Wofford
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 173-180
Technical Paper | doi.org/10.13182/NSE03-A2373
Programs of Experiments with Critical Assemblies at the Russian Research Centre "Kurchatov Institute"
A. A. Bykov, A. Yu. Gagarinski, E. S. Glushkov, Yu. A. Kravchenko, N. E. Kukharkin, D. Pavlov, N. N. Ponomarev-Stepnoi
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 181-187
Technical Paper | doi.org/10.13182/NSE03-A2374
Benchmark Experiments at VNIITF Test Facilities for Verification of Nuclear Data Libraries
A. P. Vasiliev, Yu. A. Sokolov, V. A. Terekhin, Yu. I. Chernukhin, A. V. Lukin, A. I. Saukov, B. I. Sukhanov, A. M. Ryabinin
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 188-195
Technical Paper | doi.org/10.13182/NSE03-A2375
Use of Sensitivity and Uncertainty Analysis to Select Benchmark Experiments for the Validation of Computer Codes and Data
K. R. Elam, B. T. Rearden
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 196-212
Technical Paper | doi.org/10.13182/NSE03-A2376
Monte Carlo Eigenvalue Calculations with ENDF/B-VI.8, JEFF-3.0, and JENDL-3.3 Cross Sections for a Selection of International Criticality Safety Benchmark Evaluation Project Handbook Benchmarks
A. C. Kahler
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 213-224
Technical Paper | doi.org/10.13182/NSE03-A2377
Criticality Safety of Low-Enriched Uranium and High-Enriched Uranium Fuel Elements in Heavy Water Lattices
Milan P. Pesic
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 225-233
Technical Paper | doi.org/10.13182/NSE03-A2378
Use of International Criticality Safety Benchmark Evaluation Project Data for Validation of the Nuclear Data Library BAS
V. M. Shmakov, V. D. Lyutov, V. A. Bekhterev
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 234-246
Technical Paper | doi.org/10.13182/NSE03-A2379
Use of International Criticality Safety Benchmark Evaluation Project Data for Validation of the ABBN Cross-Section Library with the MMK-KENO Code
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 247-255
Technical Paper | doi.org/10.13182/NSE03-35
Examination of the 2×2 SiO2, Al, and Fe Experiments Mixed with Highly Enriched Uranium on the Thermal Energy Region
David J. Loaiza, Rene Sanchez
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 256-266
Technical Paper | doi.org/10.13182/NSE03-A2381
Validation of the Continuous-Energy Monte Carlo Criticality-Safety Analysis System MVP and JENDL-3.2 Using the Internationally Evaluated Criticality Benchmarks
Susumu Mitake
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 267-277
Technical Paper | doi.org/10.13182/NSE03-A2382
Autocorrelation and Dominance Ratio in Monte Carlo Criticality Calculations
Taro Ueki, Forrest B. Brown, D. Kent Parsons, Drew E. Kornreich
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 279-290
Technical Paper | doi.org/10.13182/NSE03-04
Convergence Improvement of Response Matrix Method with Large Discontinuity Factors
Akio Yamamoto
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 291-298
Technical Paper | doi.org/10.13182/NSE03-A2384
DORT-TD: A Transient Neutron Transport Code with Fully Implicit Time Integration
Andreas Pautz, Adolf Birkhofer
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 299-319
Technical Paper | doi.org/10.13182/NSE03-A2385
Coupling of Time-Dependent Neutron Transport Theory with the Thermal Hydraulics Code ATHLET and Application to the Research Reactor FRM-II
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 320-341
Technical Paper | doi.org/10.13182/NSE03-A2386
Evaluation of Data with Systematic Errors
F. H. Fröhner
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 342-353
Technical Paper | doi.org/10.13182/NSE03-A2387
Radiological Assessment of Target Materials for Accelerator Transmutation of Waste Applications
Linda D. Vickers
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 354-375
Technical Paper | doi.org/10.13182/NSE03-A2388
Using NJOY99 and MCNP4B2 to Estimate the Radiation Damage Displacements per Atom per Second in Steel Within the Boiling Water Reactor Core Shroud and Vessel Wall from Reactor-Grade Mixed-Oxide/Uranium Oxide Fuel for the Nuclear Power Plant at Laguna Verde, Veracruz, Mexico
Lisa Vickers
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 376-389
Technical Paper | doi.org/10.13182/NSE03-A2389
Definition and Application of Proton Source Efficiency in Accelerator-Driven Systems
Per Seltborg, Jan Wallenius, Kamil Tucek, Waclaw Gudowski
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 390-399
Technical Paper | doi.org/10.13182/NSE03-A2390
