NE Postdoctoral Projects

Category: Nuclear Systems Modeling and Design Analysis

ADVANCED REACTOR CONCEPT DEVELOPMENT

Opportunities exist for students to participate in development, analysis, and experiment activities supporting innovative concepts for future nuclear power plants. The advanced concepts emphasize passive safety, nonproliferation, long core lifetime, simplicity, low cost, and high reliability. Students will work with experienced researchers to study existing concepts, address new approaches, develop and utilize analytical models, and perform trade-off and optimizing studies. Specific disciplines of interest include heat transfer, fluid mechanics, materials science, heat exchanger technology, steam/gas turbine technology, component design, and cost/efficiency modeling. Students may also select to participate in experiment activities including development of apparatus, assist staff in conducting experiments, interpret results, and compare data with model predictions.
Contact: Christopher Grandy
| Fax: +1 630-252-7577

NUCLEAR WASTE AND REPOSITORY MODELING

The radiological characteristics of spent nuclear fuel and other potential waste forms are evaluated; and the impact of various waste processing techniques is assessed. The performance of nuclear wastes in a deep geological repository is modeled. Repository modeling must account for release of radionuclides from the waste package, and subsequent geochemical transport in the surrounding environment. Probabilistic risk evaluation tools are used to account for model and data uncertainties. Model development and validation requires an ability to integrate performance considerations from a wide variety of scientific fields. Experience with large-scale scientific and PRA computer codes is desirable.
Contact: Jim Cahalan
| Fax: +1 630-252-4500

SPENT NUCLEAR FUEL PROCESSING

Pilot Scale - Demonstration of electrometallurgical technology for metallic fast reactor fuel from EBR-II is being conducted at the Fuel Conditioning Facility. This technology employs a combination of electrochemical and metallurgical processes to prepare spent nuclear fuel for disposal. Processing takes place in a heavily shielded argon-atmosphere cell. Process control is automated to the extent possible through the use of computer and programmable logic controllers. Areas of research include computer modeling of the pyroprocesses and engineering of improved equipment with faster process rates and greater automation.
Contact: Rajesh K. Ahluwalia
| Fax: +1 630-252-5287 | Related Information

COMPUTER STUDIES OF NUCLEAR REACTORS

Analyses are performed to predict the behavior of nuclear reactor systems in steady state or in operational and accidental transients. Large-scale computer codes containing models of heat transfer, single and two-phase flow, reactor physics (cross section data processing, reactor statics, fuel depletion, and reactor kinetics), and structural-mechanical behavior are employed. The participant should have a basic understanding of one or more of the following areas: heat transfer, fluid flow, reactor physics, structural mechanics, and a working knowledge of FORTRAN.
Experience with large-scale scientific computer codes and applications is desirable.
Contact: Jim Cahalan
| Fax: +1 630-252-4500 or
Contact: Robert N. Hill
| Fax: +1 630-252-4500