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ANS Annual Conference session focuses on maritime nuclear
At the American Nuclear Society’s Annual Conference on June 1, an executive session covered the increasingly prominent subject of nuclear applications in the civilian maritime industry.
Panelists who presented during “Advancing Nuclear Powered Maritime Shipping” highlighted the fact that the commercial shipping industry, the nuclear industry, and government agencies are looking at nuclear power as a solution for reducing greenhouse gas emissions, 3 percent of which are attributed to commercial shipping.
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.