Student Abstracts: Nuclear Science at ANL

Operations Modeling of the Fast Flux Testing Facility(FFTF) Fuel Cycle Demonstration. VERED ANZENBERG (University of California, Berkeley, Berkeley, CA 94720) DR. HUMBERTO GARCIA (Argonne National Laboratory, Argonne, IL 60439) .
Discrete Event modeling is used to simulate complex processes. One such process is the Fuel Cycle Demonstration for the Fast Flux Testing Facility (FFTF). FFTF is currently in consideration of reactivation and relies on fueling the reactor core using facilities at Argonne National Laboratory- West. Using the software Extend, a model is produced portraying relevant facilities and their corresponding stations. The model is to show bottlenecks within the process and to see whether ANLW will be able to support the fueling needs of FFTF. This research produced a preliminary model; a basic structure to the process and is currently awaiting further data.

Transmission-Corrected Barrel Segmented Gamma Scanner Analysis. ANDREW BARAN (University of Illinois at Urbana-Champaign, Urbana, IL 61820) WILLIAM RUSS (Argonne National Laboratory, Argonne, IL 60439) .
The Barrel Segmented Gamma Scanner is an instrument for the nondestructive mass assay of 55-gallon barrels of low level radioactive waste contaminated with a small amount of fissile Uranium and Plutonium. The analysis of data collected by the Barrel Scanner results in a record of the masses of these isotopes shipped to disposal and is important for safeguarding the non-proliferation of nuclear materials. Currently spectrum data is analyzed using a Microsoft Excel MACRO on a Macintosh platform. The updated analysis software will be written in the more versatile LabVIEW programming language to create a more easily used and adaptable system for obtaining mass data from waste barrels. The code is modular and well documented to facilitate changes and upgrades in the future, and the new software performs all of the data handling internally from input file data extraction to calibration and the saving of results and error analysis.

Lead Bismuth Eutectic Target. ROBERT KAPHEIM (University of Illinois, Urbana, IL 61801) JOE HERCEG (Argonne National Laboratory, Argonne, IL 60439) .
The history of nuclear power has been relatively brief, but two of the main players (nuclear reactor and particle accelerator) are coming together. The key component to the hybrid is a spallation target. In this case the Lead-Bismuth eutectic target is developed using Pro/Engineer and analyzed using Computational Fluid Dynamics code Star CD software. A near 2-D slice of the 3-D tube was analyzed for temperature of the solid walls and of the liquid lead-bismuth, and for the velocity of the lead-bismuth. Multiple problems occur with the heat distribution on the solid tube. Major design changes are in order and other current designs may be superior.