Masters Theses
Keywords and Phrases
Computer Simulation; Decay-Heat; Delayed-Particles; FMESH Reactor Source; MCNP; Pulse-Reactors
Abstract
"Energy is deposited into experiment packages due to post-shutdown decay heat created from delayed particles. Modeling these delayed particles in a reactor assists researchers in quantifying the expected energy deposition sources to an experiment package before irradiation. This paper focuses on modeling the delayed particles in a reactor in MCNP6.2 by capturing a reactor as a source, converting this source capture to a source definition, applying appropriate physics such as activation and photonuclear interactions, and finally using proper tallies to create the expected delayed particle tail of a reactor.
To capture the source distribution, the FMESH capability within MCNP was used with the keyword TYPE set to SOURCE. To capture the energy distribution, an F4 tally with an E card would be applied to the reactor of interest to find the energy-dependent flux. The output MESHTAL of the FMESH and F4 tally results were then normalized and converted to a source definition. The ACT card within MCNP was utilized to create delayed particles and photonuclear interactions were turned on using the PHYS:P card. The F4 tally was utilized in tandem with T4 cards to model the time-dependent flux behavior within the reactor system which represents the delayed particle tail of the reactor.
This methodology was validated using compensating ion chamber detector data from the Missouri S&T Reactor (MSTR). The normalized trend of the MCNP F4 output agrees generally well with the normalized MSTR detector data and conservatively overestimates the normalized MSTR detector data, especially at later time bins"--Abstract page iii
Advisor(s)
Alajo, Ayodeji Babatunde
Committee Member(s)
Alam, Syed B.
Lum, Edward
Department(s)
Nuclear Engineering and Radiation Science
Degree Name
M.S. in Nuclear Engineering
Publisher
Missouri University of Science and Technology
Publication Date
Summer 2022
Pagination
xii, 63 pages
Note about bibliography
Includes bibliographic references (pages 61-62).
Rights
© 2022 Eli James Boland, All rights reserved.
Document Type
Thesis - Open Access
File Type
text
Language
English
Thesis Number
T 12153
Electronic OCLC #
1344518752
Recommended Citation
Boland, Eli James, "Modeling the reactor time-dependent delayed particle tail with Monte Carlo N-Particle (MCNP) version 6.2" (2022). Masters Theses. 8105.
https://scholarsmine.mst.edu/masters_theses/8105
Comments
This material is based upon work supported under a Department of Energy, Office of Nuclear Energy, Integrated University Program Graduate Fellowship.