Criticality Calculations and Shielding Analysis of the Missouri S&T Research Reactor using Scale-6.2.2
Abstract
A 3D model of the Missouri S&T Research Reactor (MSTR) was developed using SCALE-6.2.2 in this study. The criticality calculation of MSTR was modeled with the CSAS6/KENO-VI sequence within the SCALE-6.2.2 package. The critical control rods height was predicted, and the criticality was achieved when the control rod withdrawn 22.25 in with the keff value of 1.0001±0.00083. Then, the neutron source distribution of the critical core was used as a mesh source for the shielding analysis. The shielding analysis was performed using a flexible MAVRIC/FW-CADIS model of the MSTR that could perform and analyze deep penetration shielding problems.
Recommended Citation
A. A. Bugis and X. Liu, "Criticality Calculations and Shielding Analysis of the Missouri S&T Research Reactor using Scale-6.2.2," Proceedings of the 20th Topical Meeting of the Radiation Protection and Shielding Division (2018, Santa Fe, NM), American Nuclear Society (ANS), Aug 2018.
Meeting Name
20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018 (2018: Aug. 26-31, Santa Fe, NM)
Department(s)
Nuclear Engineering and Radiation Science
Keywords and Phrases
3D modeling; Control rods; Criticality (nuclear fission); Neutron sources; Research reactors; Shielding, Criticality calculations; Deep penetration; Missouris; Neutron source distribution; Shielding analysis; Shielding problems, Reactor shielding
International Standard Book Number (ISBN)
978-089448746-0
Document Type
Article - Conference proceedings
Document Version
Citation
File Type
text
Language(s)
English
Rights
© 2018 American Nuclear Society (ANS), All rights reserved.
Publication Date
01 Aug 2018
