High-fidelity lattice physics capabilities of the scale code system using TRITON
Creators
- 1. Oak Ridge National Laboratory, MS 6170, P.O. Box 2008, Oak Ridge, TN 37831-6170 (United States)
Description
Increasing complexity in reactor designs suggests a need to reexamine of methods applied in spent-fuel characterization. The ability to accurately predict the nuclide composition of depleted reactor fuel is important in a wide variety of applications. These applications include, but are not limited to, the design, licensing, and operation of commercial/research reactors and spent-fuel transport/storage systems. New complex design projects such as space reactors and Generation IV power reactors also require calculational methods that provide accurate prediction of the isotopic inventory. New high-fidelity physics methods will be required to better understand the physics associated with both evolutionary and revolutionary reactor concepts as they depart from traditional and well-understood light-water reactor designs. The TRITON sequence of the SCALE code system provides a powerful, robust, and rigorous approach for reactor physics analysis. This paper provides a detailed description of TRITON in terms of its key components used in reactor calculations. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-059-6
- Imprint Pagination
- 14 p.
Conference
- Title
- Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications - M and C + SNA 2007
- Dates
- 15-19 Apr 2007
- Place
- Monterey, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43000993
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- INVENTORIES; POWER REACTORS; REACTOR LICENSING; REACTOR OPERATION; RESEARCH REACTORS; SPENT FUEL STORAGE; SPENT FUELS; THREE-DIMENSIONAL CALCULATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ENERGY SOURCES; FUELS; LICENSING; MATERIALS; NUCLEAR FUELS; OPERATION; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; STORAGE
Optional Information
- Notes
- 16 refs.