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Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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Two steps forward for U.K. advanced nuclear
This week, two significant announcements have emerged from the United Kingdom’s advanced reactor sector.
On June 14, Rolls-Royce, the United Kingdom National Nuclear Laboratory, and the Japan Atomic Energy Agency announced that they had signed two trilateral memorandums of cooperation to collaborate on “advanced modular reactor (AMR) technology, specifically high-temperature gas-cooled reactors (HTGR), and the coated particle fuel these reactors will use.”
Separately, on June 16, Bellevue, Wash.–based TerraPower announced that its Natrium reactor design has been formally submitted for U.K. regulatory review. The company also announced the formation of a new subsidiary, TerraPower UK Ltd.
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)