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Links to the latest version of the manual are provided in the sections below. For the previous version of the manual, please visit this page.

Each channel represents a fuel pin, its cladding, the associated coolant, and a fraction of the subassembly duct wall. Other positioning hardware, such as wire wraps or grid spacers, is usually lumped into the structure field with the duct wall. Within a channel, the flow is assumed to be one-dimensional in the axial direction, and the temperature field in the fuel, cladding, coolant, and structure is assumed to be two-dimensional in the radial and axial directions.

Usually, a channel represents an average fuel element in a subassembly or a group of subassemblies. A channel may also represent pins in blanket or control subassemblies.

Alternately, a single channel may also be used to represent the hottest pin in an assembly, or any other subset of a subassembly.

Different channels may be used to account for radial and azimuthal design geometry, power, coolant flow, and burnup variations within the reactor core. From ten to thirty channels normally provide sufficient discretization, depending on the core design. Significantly more channels can be used if necessary. Also, the subassembly-to-subassembly heat transfer model has been improved, and axial conduction in the coolant has been added.

These modeling additions have been proven in validation analyses of EBR-II Shutdown Heat Removal Tests, and are required for accurate predictions of intra-subassembly flow and temperature variations in EBR-II during transients from normal to shutdown operating conditions.

The new addition to this module is an option for an EBR-II-specific reactivity feedback model that is being validated with analysis of reactor operating data and used for predictive calculations of margins in design basis analyses. This model provides boundary coolant pressure and flow conditions for the core channel models, including transient heat losses through normal and emergency heat removal systems and the transient performance of pumps.

It was implemented to permit 1 improved simulation of EBR-II design basis transients, 2 whole-plant analysis of IFR designs for optimization of advanced reactor control system strategies, and 3 core temperature margin assessments in unprotected accident sequences i. If you are either not familiar with the MediaWiki collaboration platform or have never edited this wiki before, please visit the Help page. In order to edit this wiki you must first log in. From Safety Analysis System. The full code manual is available as a separate download below.

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