Validation of Improved 3D ATR Model

Conference · Thu Nov 17 00:00:00 EST 2005 · Transactions of the American Nuclear Society

OSTI ID:911618

Kim, Soon S. ^[1]; Schnitzler, Bruce G. ^[1]

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1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)

A full-core Monte Carlo based 3D model of the Advanced Test Reactor (ATR) was previously developed. An improved 3D model has been developed by the International Criticality Safety Benchmark Evaluation Project (ICSBEP) to eliminate homogeneity of fuel plates of the old model, incorporate core changes into the new model, and to validate against a newer, more complicated core configuration. This new 3D model adds capability for fuel loading design and azimuthal power peaking studies of the ATR fuel elements.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC07-99ID-13727
• OSTI ID: 911618
• Report Number(s): INL/CON-05-00322; TRN: US0800045
• Journal Information: Transactions of the American Nuclear Society, Vol. 03, Issue 1; Conference: ANS 2005 Winter Meeting, Washington, DC (United States), 13-17 Nov 2005; Related Information: https://www.ans.org/pubs/transactions/volume-93/; ISSN 0003-018X
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
97 MATHEMATICS AND COMPUTING
BENCHMARKS
CONFIGURATION
CRITICALITY
DESIGN
EVALUATION
FUEL ELEMENTS
FUEL PLATES
SAFETY
TEST REACTORS
VALIDATION
Nuclear Criticality Safety Program (NCSP)
Advanced Test Reactor (ATR)
Fuel Loading Design
Azimuthal Power Peaking Studies
International Criticality Safety Benchmark Evaluation Project (ICSBEP)
Monte Carlo
Fuel Plates