NE Postdoctoral Projects

Category: Nuclear Systems Technologies

NUCLEAR CRITICALITY SAFETY

Criticality safety and shielding analyses are performed for complex configurations and operations involving wide ranges of geometries, materials, and neutron spectra. These analysis efforts employ state-of-the-art nuclear data libraries and software and are complemented by ongoing R&D in methods development, software development, critical experimental evaluation, safety analysis report preparation, and nuclear data library validation.
Contact: James A. Morman
| Fax: +1 630-252-4780 | Related Information or
Contact: R. McKnight
| Fax: +1 630-252-4500

ANALYSIS AND MODELING OF MATERIALS BEHAVIOR IN ENERGY SYSTEMS

A modern, high-speed, digital computer is employed to simulate the physical behavior of materials used in advanced energy systems (fission and fusion). In the fission area, the thermal, mechanical, and irradiation response of fuel elements for the Reduced Enrichment Research and Test Reactor (RERTR) program are analyzed. Emphasis is placed on realistic models that accurately describe the physical situation. The DART code system is being developed in order to assess the behavior of dispersion fuels for the RERTR. In the fusion area, the thermal, mechanical, and irradiation performance of solid breeders (Li2O and other ternary oxides) are being modeled. The TIARA code has been developed, verified and validated to predict the tritium inventory in lithium ceramics under fusion reactor operation conditions. Other research activities include the analysis of specific phenomena (e.g. helium-induced swelling) in order to identify key process and/or physical parameters that affect material performance and the thermal and mechanical responses of fusion first-wall structures under novel cooling schemes is being modeled.
Contact: Totju L. Totev, | Fax: +1 630-252-5161 or
Contact: Yousry Gohar
| Fax: +1 630-252-4500

ARTIFICIAL INTELLIGENCE APPLICATION

Large volumes of digitized data from operating nuclear power plants are processed, analyzed, and interpreted using state-of-the-art interactive signal processing techniques on distributed workstations and PCs. Software packages for various numerical, statistical, pattern- recognition and time-series analyses are developed, modified, and maintained using a variety of languages and software-engineering tools. On-line expert systems are being developed that use automated reasoning techniques for assistance with the tasks of surveillance, diagnosis,control and interpretation of physical parameters in advanced nuclear, aerospace, and industrial systems.
Contact: Tom Wei
| Fax: +1 630-252-4978 | Related Information

FUEL PROCESS MODELING

Various chemical, thermal, and mechanical processes are involved in treating spent nuclear fuel and special nuclear materials to produce suitable waste forms for storage. Simulation of these processes is required to enable proper planning of the sequence of operations and material usage. Activities include development of a simulator for the overall process, including detailed models for the various processing steps, such as electrochemical transport and distillation. Data from the processes will be used to guide development of the models, especially in the area of process losses and material accountability.
Contact: Tanju Sofu
| Fax: +1 630-252-4500

APPLIED ACCELERATOR TECHNOLOGY

These activities entail the development of advanced accelerator technology and require physics, engineering or computer programming support in the following areas:
· design and development of accelerator-based neutron and/or photon sources for neutron radiography and boron neutron capture therapy;
· design and development of targets and strippers for high power accelerators such as the Rare Isotope Accelerator (RIA).
Contact: Claude Reed
| Fax: +1-630-252-5287