CASMO5/TSUNAMI-3D spent nuclear fuel reactivity uncertainty analysis

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22105792

Ferrer, R.; Rhodes, J. ^[1]; Smith, K. ^[2]

---

1. Studsvik Scandpower, Inc., 504 Shoup Ave., Idaho Falls, ID 83402 (United States)
2. Dept. of Nuclear Science and Engineering, Massachusetts Inst. of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139 (United States)

The CASMO5 lattice physics code is used in conjunction with the TSUNAMI-3D sequence in ORNL's SCALE 6 code system to estimate the uncertainties in hot-to-cold reactivity changes due to cross-section uncertainty for PWR assemblies at various burnup points. The goal of the analysis is to establish the multiplication factor uncertainty similarity between various fuel assemblies at different conditions in a quantifiable manner and to obtain a bound on the hot-to-cold reactivity uncertainty over the various assembly types and burnup attributed to fundamental cross-section data uncertainty. (authors)

• Research Organization: American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
• OSTI ID: 22105792
• Resource Relation: Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 9 refs.
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BURNUP
COMPUTER GRAPHICS
CROSS SECTIONS
DATA COVARIANCES
FUEL ASSEMBLIES
MULTIPLICATION FACTORS
ORNL
PWR TYPE REACTORS
RADIOACTIVE WASTES
REACTIVITY
REACTOR LATTICES
REACTOR PHYSICS
SPENT FUELS
THREE-DIMENSIONAL CALCULATIONS