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AmBe Source Room MCNP Simulation and Humidity Evaluation to Estimate the Dose Rates Within Mirion Technologies Neutron Facility
Department: Nuclear Eng'g & Health Physics
ResourceLengthWidthThickness
Paper000
Specimen Elements
Pocatello
Unknown to Unknown
Aaron Otterstein
Idaho State University
Thesis
No
2/7/2025
digital
City: Pocatello
Master
This study demonstrates that the MCNP tool can be used to determine the dose rate from an AmBe source in the room where it is stored and used. The results show that accounting for the primary components of the room geometry that may perturb the neutron field and defining a well-defined source is sufficient to accurately predict the dose rate within uncertainty of the known value at a known distance. Additionally, the known impact of hydrogen as a moderator is tested as simulated results of the changes to the air are performed to include 0 to 10% water vapor in air. These results indicate that there is no identifiable impact to the dose rate within the simulation from water vapor in the air. This work demonstrates that MCNP is a versatile tool that can be modified to test varying conditions and generate results about hypothetical dose rates that may help in decision making. Key Words: AmBe, MCNP

AmBe Source Room MCNP Simulation and Humidity Evaluation to Estimate the Dose Rates Within Mirion Technologies Neutron Facility

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