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Title

Verification of the 3-Region Advanced Test Reactor MCNP Model

Organization

Department: Nuclear Eng'g & Health Physics

University: Idaho State University College: Science & Engineering Department: Nuclear Eng'g & Health Physics 23

Document Attachments

Resource	Length	Width	Thickness
Paper	0	0	0

Specimen Elements

City

Pocatello

Coverage

Unknown to Unknown

Creator

Brenna Carbno

Publisher

Idaho State University

Type

Thesis

Is Complete

No

Date Published

7/11/2023

Archive

digital

City: Pocatello

Degree

Master

Document Attachments

Abstracts

The verification of the 3-region homogenized fuel Advanced Test Reactor MCNP model. The 3- region model was compared to the 19-plate model found in the 94-CIC report. Flux tallies, energy deposition tallies, and quarter core mesh tallies were used to compare the two models. The 3-region model needed updating in order to make good comparisons between the models. The percent error from the flux and energy deposition tallies data shows that experiment positions inside the flux trap have higher errors than positions outside the fuel ring. The standard deviation data obtained from the mesh tallies shows that the two models agree within two standard deviations throughout the reactor. It is concluded that the model works adequately for what it is used for.