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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
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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Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
NextGen MURR Working Group established in Missouri
The University of Missouri’s Board of Curators has created the NextGen MURR Working Group to serve as a strategic advisory body for the development of the NextGen MURR (University of Missouri Research Reactor).
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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