Evaluation of core attributes uncertainties due to input data uncertainties

Transactions of the American Nuclear Society

Volumn 92, Issue , 2005, Pages 546-547

  Abdel Khalik, Hany S ^a,b   Turinsky, Paul J ^a  

^a North Carolina State University   (United States)

^b ANP Inc   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 33244486541     PISSN: 0003018X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (5)

1. N. M. GREENE and M. E. DUNN, AMPX-2000: A Modular Code System for Processing ENDF/B Evaluations, NUREG/CR-6659, ORNL/TM-1999/265, DRAFT (September 2001).
2. M. D. DEHART, TRITON: A Two Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel, NUREG-0200, ORNL/NUREG/CSD-2/R7, DRAFT (2004).
3. B. R. MOORE, P. J. TURINSKY and A. A. KARVE, "FORMOSA-B: A Boiling Water Reactor In-core Fuel Management Optimization Package," Nuclear Technology, 126, 153 (1999).
4. H. S. ABDE-KHALIK and P. J. TURINSKY, "Adaptive Core Simulation, Part I: Theory" Nuclear Technology [In Press] (2005).
5. H. S. ABDEL-KHALIK and P. J. TURINSKY, "Adaptive Core Simulation, Part II: Numerical Experiments" Nuclear Technology [In Press] (2005).