TY - GEN
T1 - Depletion calculation and uncertainty/sensitivity analysis for a sodium-cooled fast spectrum fuel assembly
AU - Aures, A.
AU - Bostelmann, F.
AU - Hannstein, V.
AU - Velkov, K.
AU - Zwermann, W.
AU - Guilliard, N.
AU - Lapins, J.
AU - Bernnat, W.
PY - 2015
Y1 - 2015
N2 - The impact of the nuclear data libraries on the multiplication factor and the nuclide densities during depletion of a sodium-cooled fast system are investigated through performance of depletion calculations for one cycle. The model used in this study represents a fuel assembly of the inner core region of the Generation-IV sodium-cooled fast reactor concept MOX-3600. On the basis of this benchmark, comparative analyses are also carried out by the OECD/NEA Working Group SFR-FT. In this paper, the nuclear data libraries ENDF/B-VII.0 /-VII. 1 and JEFF-3.1.1 /-3.1.2 /-3.2 are used in continuous-energy format by the Monte Carlo codes MCNP-6 and Serpent 2. Additionally, multi-group calculations are performed with TRITON/NEWT, TRITON/KENO using the 238-group ENDF/B-VII.O library and with HELIOS using the 190-group ENDF/B-VI library. A reactivity difference of about 500-600 pcm between JEFF-3.1.2 and JEFF-3.2 is observed. For most actinides, the various depletion sequences obtain similar nuclide densities, except for U-234, Np-237, Am and Cm, where the deviations are larger. Furthermore, systematic uncertainty and sensitivity analysis concerning uncertainties of nuclear data are done with the sampling-based XSUSA methodology and with the TSUNAMI module of the SCALE 6.1 code system. In contrast to light water reactor systems, the uncertainty of the multiplication factor is significantly larger. The sensitivity analysis showed that the main contribution originates from the uncertainty of the inelastic scattering of U-238, and due to a strong correlation, also from the elastic scattering.
AB - The impact of the nuclear data libraries on the multiplication factor and the nuclide densities during depletion of a sodium-cooled fast system are investigated through performance of depletion calculations for one cycle. The model used in this study represents a fuel assembly of the inner core region of the Generation-IV sodium-cooled fast reactor concept MOX-3600. On the basis of this benchmark, comparative analyses are also carried out by the OECD/NEA Working Group SFR-FT. In this paper, the nuclear data libraries ENDF/B-VII.0 /-VII. 1 and JEFF-3.1.1 /-3.1.2 /-3.2 are used in continuous-energy format by the Monte Carlo codes MCNP-6 and Serpent 2. Additionally, multi-group calculations are performed with TRITON/NEWT, TRITON/KENO using the 238-group ENDF/B-VII.O library and with HELIOS using the 190-group ENDF/B-VI library. A reactivity difference of about 500-600 pcm between JEFF-3.1.2 and JEFF-3.2 is observed. For most actinides, the various depletion sequences obtain similar nuclide densities, except for U-234, Np-237, Am and Cm, where the deviations are larger. Furthermore, systematic uncertainty and sensitivity analysis concerning uncertainties of nuclear data are done with the sampling-based XSUSA methodology and with the TSUNAMI module of the SCALE 6.1 code system. In contrast to light water reactor systems, the uncertainty of the multiplication factor is significantly larger. The sensitivity analysis showed that the main contribution originates from the uncertainty of the inelastic scattering of U-238, and due to a strong correlation, also from the elastic scattering.
KW - Criticality
KW - Depletion
KW - SFR
KW - U/S analysis
UR - http://www.scopus.com/inward/record.url?scp=84949482872&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:84949482872
T3 - Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015
SP - 1542
EP - 1551
BT - Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015
PB - American Nuclear Society
T2 - Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015
Y2 - 19 April 2015 through 23 April 2015
ER -