Nuclear Technology · 2011 · 85 citations · 11 references
EngineeringNuclear EngineeringPhysicsNuclear PhysicsRadiation TransportReactor PhysicsNuclear FissionReactor Core DesignReactor DesignReactor KineticsReactor ModelingAdvanced Reactor ConceptsFuel Depletion ModelingNuclide Inventory DeterminationReactor Core NeutronicsReactor Core PhysicsSpent Fuel TransportSpent Nuclear Fuel Storage
The TRITON sequence of the SCALE code system offers a robust, rigorous framework for reactor physics analysis, enabling accurate prediction of depleted fuel nuclide composition essential for design, licensing, operation, and spent‑fuel transport and storage. The study presents a detailed description of TRITON’s key components for reactor calculations. TRITON provides high‑fidelity physics methods that accurately model both evolutionary and revolutionary reactor concepts beyond conventional light‑water reactors.
The TRITON sequence of the SCALE code system provides a powerful, robust, and rigorous approach for performing reactor physics analysis. This paper presents a detailed description of TRITON in terms of its key components used in reactor calculations. The ability to accurately predict the nuclide composition of depleted reactor fuel is important in a wide variety of applications. These applications include, but are not limited to, the design, licensing, and operation of commercial/research reactors and spent-fuel transport/storage systems. New complex design projects such as next-generation power reactors and space reactors require new high-fidelity physics methods, such as those available in SCALE/TRITON, that accurately represent the physics associated with both evolutionary and revolutionary reactor concepts as they depart from traditional and well-understood light water reactor designs.
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Development of a New Monte Carlo reactor physics code
Jaakko Leppänen · Aaltodoc (Aalto University) · 2007 · 210 citations · Full text
Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE
Ian C Gauld, Georgeta Radulescu, Germina Ilas et al. · Nuclear Technology · 2011 · 176 citations