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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Jul 2025
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Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
Technical Session|Sponsored by MCD
Tuesday, June 18, 2024|1:00–2:45PM PDT|Jasmine B
Session Chair:
Jilang Miao
Alternate Chair:
Sebastian Schunert
Session Organizer:
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Development of Verification Methodology for Thermo-Mechanical Solver of MERCURY Fuel Performance Code
1:00–1:20PM PDT
Dong-hwa Lee (KAERI), Sung-Uk Lee (KAERI), Hyochan Kim (KAERI)
Paper
Influence of Variance Reduction Techniques on the Wrong Results Obtained from Monte Carlo Radiation Transport Simulations when Random Number Stride is Exceeded
1:20–1:40PM PDT
Arief Rahman Hakim (Ulsan Nat'l Institute Science and Technology), Wooil Lee (Ulsan Nat'l Institute Science and Technology), Douglas A. Fynan (Ulsan Nat'l Institute Science and Technology)
FMI-Based Multi-Fidelity and Multi-Scale Simulations of a Nuclear Reactor
1:40–2:00PM PDT
Thomas Guilbaud (École Polytechnique Fédérale de Lausanne), Carlo Fiorina (TAMU), Alessandro Scolaro (École Polytechnique Fédérale de Lausanne), Andreas Pautz (École Polytechnique Fédérale de Lausanne)
Wrong Results when Random Number Stride is Exceeded in Monte Carlo Radiation Transport: Reanalysis of Legacy Stride Exceedance Study
2:00–2:20PM PDT
Arief Rahman Hakim (Ulsan Nat'l Institute Science and Technology), Douglas A. Fynan (Ulsan Nat'l Institute Science and Technology)
Uncertainty Estimation by Correlated Sampling for the Neutronics Analysis of Sodium-Cooled Fast Reactors by the iDTMC Methodology
2:20–2:40PM PDT
Sunjoo Yoon (KAIST), Inyup Kim (KAIST), Taesuk Oh (KAIST), Yonghee Kim (KAIST)
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