A three-dimensional computational method based on Monte Carlo radiation transport techniques was developed to calculate thermal and fast neutron fields in the downcomer region of a Boilding Water Reactor (BWR). This methodology was validated using experimental data obtained from an operating BWR. In addition to standard activation wire data, helium production was measured in stainless steel at locations near the shroud and compared to with values from the Monte Carlo calculations. The methodology produced results that were in agreement with measurements, thus thereby providing a useful tool for the determination of helium levels in shroud components.
Revised: August 16, 2010 |
Published: January 1, 2003
Citation
Sitaraman S., R. Chiang, and B.M. Oliver. 2003.MCNP-Based Methodology to Calculate Helium Production in BWR Shrouds. In Reactor Dosimetry in the 21st Century: Proceedings of the 11th International Symposium on Reactor Dosimetry, edited by J Wagemans, 245-250. River Edge, New Jersey:World Scientific.PNNL-SA-38394.