Neutronic evaluation of LEU 30-20 fuel for the Texas A&M Nuclear Science Center Reactor
Date
1996
Authors
Journal Title
Journal ISSN
Volume Title
Publisher
Texas A&M University
Abstract
A neutronic evaluation of the Texas A&M University Nuclear Science Center Reactor (TAMU NSCR) using the General Atomic Company (GA) low enrichment uranium (LEU 30-20 fuel was performed to determine the feasibility of this type of fuel. To perform this evaluation, the WIMSD4m transport code and DIF3D diffusion code were utilized. These codes were provided by Argonne National Laboratory (ANL). WIMSD4m was used to calculate macroscopic cross-sections for the various core materials and DIF3D was used to calculate the effective multiplication factor and thermal neutron flux for various core configurations. In order to benchmark these codes and the core model used to evaluate the proposed LEU 30-20 core, the current FLIP core was first modeled. Various neutronic parameters, such as excess reactivity, shutdown margin, critical rod height and control rod worths were calculated using the core model and codes, and the results compared with actual experimental results for the FLIP core. Once the core model and codes were validated, the core model was modified using LEU 30-20 fuel and an optimum core configuration obtained which satisfied certain design criteria, including values for excess reactivity, shutdown margin and thermal neutron flux. In addition to modeling the LEU 30-20 core, a control rod model was developed to generate effective macroscopic cross-sections for the control rod materials in the core, based on previous work in this area performed at ANL. The results of this analysis indicate the feasibility of converting the TAMU NSCR to GA LEU 30-20 fuel.
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Includes bibliographical references.
Issued also on microfiche from Lange Micrographics.
Includes bibliographical references.
Issued also on microfiche from Lange Micrographics.