Development of an object-oriented ORIGEN for advanced nuclear fuel modeling applications

Conference · Mon Jul 01 00:00:00 EDT 2013

OSTI ID:22212902

Skutnik, S. ^[1]; Havloej, F. ^[2]; Lago, D. ^[3]; Gauld, I. ^[4]

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1. Department of Nuclear Engineering, University of Tennessee (United States)
2. Nuclear Research Institute Husinec, Rez 130, Rez, 250 68 (Czech Republic)
3. Department of Nuclear and Radiological Engineering, Georgia Institute of Technology (United States)
4. Oak Ridge National Laboratory, MS-6315, One Bethel Valley Road, Oak Ridge, TN 37831 (United States)

The ORIGEN package serves as the core depletion and decay calculation module within the SCALE code system. A recent major re-factor to the ORIGEN code architecture as part of an overall modernization of the SCALE code system has both greatly enhanced its maintainability as well as afforded several new capabilities useful for incorporating depletion analysis into other code frameworks. This paper will present an overview of the improved ORIGEN code architecture (including the methods and data structures introduced) as well as current and potential future applications utilizing the new ORIGEN framework. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22212902
• Resource Relation: Conference: M and C 2013: 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, ID (United States), 5-9 May 2013; Other Information: Country of input: France; 10 refs.; Related Information: In: Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013| 3016 p.
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICAL METHODS AND COMPUTING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
DECAY
NUCLEAR FUELS
NUCLEAR PHYSICS
SIMULATION