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Argonne is 13th Best Place to work for postdocs

Argonne is one of top 15 places in U.S. for postdocs to work
Argonne was recently ranked 13th best place for postdocs to work by life sciences magazine, The Scientist. The annual article, run for the seventh time in 2009, surveys postdocs at hundreds of labs and institutions, private and government, for-profit and not-for-profit, to gauge their opinions on the institutions they work for. Argonne's ranking in the survey jumped seven slots, from 20 to 13, in one year. More...

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Category: Nuclear Systems Modeling and Design Analysis

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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: Mark Nutt
| 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 are desirable.
Contact: Jim Cahalan
| Fax: +1 630-252-4500
or
Contact: Robert N. Hill
| Fax: +1 630-252-4500