Nodal methods for three-dimensional simulators

A few-group coarse mesh method has been developed for the calculation of power distribution in 2-dimensional geometry of a fast breeder reactor by extending Askew's one-group coarse mesh method. This method employs modified macroscopic cross sections including group-dependent corrections for coarse meshes of one point per hexagonal assembly and can be easily incorporated into conventional diffusion codes. Results obtained in few-group 2-dimensional test cases on a prototype fast breeder reactor indicate that this method is as accurate as fine mesh calculations with six mesh points per assembly and the computing time is about ¼ of that of fine mesh calculations.

https://www.tandfonline.com/doi/pdf/10.1080/18811248.1978.9735544

Extension of Askew's Coarse Mesh Method to Few-Group Problems for Calculating Two-Dimensional Power Distribution in Fast Breeder Reactors

The Japanese prototype fast breeder reactor Monju restarted its system startup test in May 2010 after a 14-year interruption. In the first stage of the test, reactor physics parameters have been me...

Criticality Evaluation for the Monju Restart Core

Monte Carlo current-based diffusion coefficients: application to few-group constants generation in Serpent

Three-dimensional (3-D) transport corrections for Keff, control rod worths, neutron spectra and power distributions are calculated for the fast critical assemblies ZPPR-9, -10 and -13. The calculations are performed in 7 energy groups using the 3-D and 2-D transport codes TRITAC and TWOTRAN-II. The evaluated 3-D transport corrections are compared with those predicted by a 2-D RZ model and a combined XY, RZ and R model to assess the accuracy of these 2-D models. The RZ model yielded some errors in estimating the transport corrections to Keff, control rod worths, neutron spectrum and power distribution, while the combined model predicted them with good accuracy.

https://www.tandfonline.com/doi/pdf/10.1080/18811248.1986.9735068

Three-dimensional transport correction in fast reactor core analysis.

This study has been undertaken to evaluate an uncertainty in a finite difference method for two-dimensional neutron diffusion calculations and to provide a simple method to eliminate the uncertaint...

A Coarse-Mesh Correction of the Finite Difference Method for Neutron Diffusion Calculations

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A Coarse-Mesh Correction of the Finite Difference Method for Neutron Diffusion Calculations