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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Crash Course: The DOE’s Package Performance Demonstration
Inspired by a history of similar testing endeavors and recommended by the National Academy of Sciences and the Blue Ribbon Commission on America’s Nuclear Future, the Department of Energy is planning to conduct physical demonstrations on rail-sized spent nuclear fuel transportation casks. As part of the project, called the Spent Nuclear Fuel Package Performance Demonstration (PPD), the DOE is considering a number of demonstrations based on regulatory tests and realistic transportation scenarios, including collisions, drops, exposure to fire, and immersion in water.
Zeyun Wu, Qiong Zhang, Hany Abdel-Khalik
Nuclear Technology | Volume 180 | Number 3 | December 2012 | Pages 372-382
Technical Paper | Special Issue on the Initial Release of MCNP6 / Fission Reactors | doi.org/10.13182/NT12-A15350
Articles are hosted by Taylor and Francis Online.
A new variant of a hybrid Monte Carlo-deterministic approach for simulating particle transport problems is presented and compared to the SCALE FW-CADIS approach. The new approach, denoted as the SUBSPACE approach, improves the selection of the importance maps in order to reduce the computational overhead required to achieve global variance reduction - that is, the uniform reduction of variance everywhere in the phase-space. The intended applications are reactor analysis problems where detailed responses for all fuel assemblies are required everywhere in the reactor core. Like FW-CADIS, the SUBSPACE approach utilizes importance maps obtained from deterministic adjoint models to derive automatic weight-window biasing. Unlike FW-CADIS, the SUBSPACE approach does not employ flux-based weighting of the adjoint source term. Instead, it utilizes pseudoresponses generated with random weights to help identify the correlations between the importance maps that could be used to reduce the computational time required for global variance reduction. Numerical experiments, serving as proof of principle, are presented to compare the SUBSPACE and FW-CADIS approaches in terms of the global reduction in standard deviation and the associated figures of merit for representative nuclear reactor assembly and core models.