Volume 4, Issue 2 (5-2016)                   IJRSM 2016, 4(2): 45-51 | Back to browse issues page

XML Persian Abstract Print

Download citation:
BibTeX | RIS | EndNote | Medlars | ProCite | Reference Manager | RefWorks
Send citation to:

Nasri Nasrabadi M, Teimouri B, Akbari K. Neutronic core calculations of Bushehr VVER-1000 reactor and investigating the control rod worth using MCNPX code. IJRSM 2016; 4 (2) :45-51
URL: http://rsm.kashanu.ac.ir/article-1-144-en.html
University of Isfahan
Abstract:   (10440 Views)

In this research, required information to simulate and perform neutronic calculations for Bushehr nuclear power plant using the MCNPX code was provided. The results of the code were verified with at least one of the operational data from the reactor. In this work, by writing and implementing a comprehensive program to solve the equations of statistical distribution, neutron flux was obtained and then various parameters including the infinite multiplication factor in terms of fluence were calculated and the control rod worth for Groups 9 and 10 were calculated at Hot Zero Power (HZP) state.

Full-Text [PDF 1737 kb]   (10486 Downloads)    
Type of Study: Research | Subject: Special

Send email to the article author

Rights and permissions
Creative Commons License This work is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License.

© 2022 CC BY-NC 4.0 | Iranian Journal of Radiation Safety and Measurement

Designed & Developed by : Yektaweb