Abstract
We calculated Startup Range Neutron Monitor (SRNM) response during refueling in a boiling water reactor (BWR). The fixed source problem of a diffusion equation is solved by the 4^<th> order nodal expansion method (NEM). A method for calculating SRNM response was devised. The new method for calculation of corner flux at SRNM positions is expanding intra nodal flux by directly using a 4^<th> order nodal expansion coefficient. Compared with actual measured data, the new method is more accurate because the existing method is only multiplying the corner discontinuing factor and node average flux.
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More From: The Proceedings of the International Conference on Nuclear Engineering (ICONE)
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