Year-end Sale % OFF 
Abstract
The Japanese prototype fast breeder reactor MONJU developmental project is of prime importance in the establishment of the commercialized fast breeder reactor technology in Japan. This work presents new results obtained by the 3D hexagonal transport nodal code NSHEX, which for the first time has been applied to MONJU criticality analysis in whole core simulation and up to 70 energy groups. Significant energy-group approximation effect on k eff caused by the collapsing into coarse energy-group structure has been found and then confirmed separately using the Monte Carlo analysis. On the basis of the presented applied results, a method of transport correction evaluation, based on 70 energy-group approximation can be recommended instead of the conventional few-group method that assumes inter-independency of energy-group approximation and transport effect.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
