TY - GEN
T1 - Integral parameter sensitivity, uncertainty, and representativity of a fast critical experiment with regard to a gen-IV fast reactor concept
AU - Stover, Tracy E.
AU - Turinsky, Paul J.
AU - Bays, Samuel E.
AU - Abdel-Khalik, Hany S.
AU - Iqbal, Masood
PY - 2009
Y1 - 2009
N2 - A criticality benchmark experiment, ZPPR-15 Assembly B, is selected for analysis to reduce uncertainties on a Generation IV reactor design, ABTR, via a data assimilation method. The ABTR is modeled with fuel compositions reflecting both start-up and equilibrium recycle cores. The ZPPR experiment is modeled as built and then computationally modified to include minor actinide targets to give information on their reaction rates. All four models are created in the REBUS code system for fast reactor analysis. The Efficient Subspace Method is used for a sensitivity and uncertainty analysis of several integral parameters, selected reaction rates at various spatial nodes, and disposal heat load. The similarity of the benchmark experiment to the reactor design concept is quantitatively compared using representativity. Finally, uncertainty and sensitivity information from the benchmark models is used to compute posteriori uncertainty information for the design concept via a data assimilation technique.
AB - A criticality benchmark experiment, ZPPR-15 Assembly B, is selected for analysis to reduce uncertainties on a Generation IV reactor design, ABTR, via a data assimilation method. The ABTR is modeled with fuel compositions reflecting both start-up and equilibrium recycle cores. The ZPPR experiment is modeled as built and then computationally modified to include minor actinide targets to give information on their reaction rates. All four models are created in the REBUS code system for fast reactor analysis. The Efficient Subspace Method is used for a sensitivity and uncertainty analysis of several integral parameters, selected reaction rates at various spatial nodes, and disposal heat load. The similarity of the benchmark experiment to the reactor design concept is quantitatively compared using representativity. Finally, uncertainty and sensitivity information from the benchmark models is used to compute posteriori uncertainty information for the design concept via a data assimilation technique.
KW - Data adjustment
KW - Fast critical experiment
KW - Generation IV reactor
KW - Integral parameters
KW - Sensitivity and uncertainty
UR - https://www.scopus.com/pages/publications/74549115371
M3 - Conference contribution
AN - SCOPUS:74549115371
SN - 9781615673513
T3 - American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
SP - 1202
EP - 1221
BT - American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
T2 - American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Y2 - 12 April 2009 through 15 April 2009
ER -