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Title

A Detailed Parametric Study of the use of Variance Reduction Techniques in the Shielding Analysis of a Used Nuclear Fuel Pyrochemical Reprocessing Facility

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

Mitchell M. Frasure

Publisher

Idaho State University

Type

Thesis

Is Complete

No

Date Published

6/25/2025

Archive

digital

City: Pocatello

Degree

Master

Document Attachments

Abstracts

A generic metallic fuel pin was modeled and depleted using both MCNP 6.2 and SCALE 6.2.4. The results were used in the bootstrap validation of the depletion capabilities of MCNP 6.2. A generic pyrochemical reprocessing facility was modeled in MCNP 6.2. The photon and neutron source spectrums from the depleted fuel material were used within the modeled facility. A shielding analysis was performed to estimate the background radiation expected at a shielded detector. The use of variance reduction techniques was explored to determine their efficacy in the shielding analysis of the facility. Key Words: MCNP, depletion analysis, variance reduction, shielding analysis