Fuel Performance Uncertainty due to Manufacturing Tolerances

von Yang, Jinan
Veröffentlicht in Light Water Reactor Fuel Performance Conference (2019 : Seattle, Wash.) Light Water Reactor Fuel Performance Conference (TOP FUEL 2019) ; Volume 2 of 2 (2020)

PERFORMANCE IMPROVEMENTS TO THE 2D/1D SUBPLANE METHOD IN MPACT

von Stimpson, Shane
Veröffentlicht in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (2019 : Portland, Or.) International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M & C 2019) ; Volume 4 of 4 (2019)

Initial Accident-Tolerant Fuel / Cladding Extensions to the VERA-to-Bison Offline Coupling

von Reynolds, Aaron J.
Veröffentlicht in International Nuclear Fuel Cycle Conference (2019 : Seattle, Wash.) International Nuclear Fuel Cycle Conference (GLOBAL 2019) ; Volume 1 of 2 (2020)

IMPLEMENTATION OF GAMMA TRANSPORT CAPABILITY IN IMPACT

von Wang, Xinyan
Veröffentlicht in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (2019 : Portland, Or.) International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M & C 2019) ; Volume 2 of 4 (2019)

SUBGRID TREATMENT OF SPACER GRIDS IN THE 2D/1D SUBPLANE APPROACH

von Stimpson, Shane G.
Veröffentlicht in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (2019 : Portland, Or.) International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M & C 2019) ; Volume 4 of 4 (2019)

COUPLED DETERMINISTIC AND MONTE CARLO NEUTRONICS FOR VESSEL FLUENCE CALCULATIONS

von Henderson, Shane C.
Veröffentlicht in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (2019 : Portland, Or.) International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M & C 2019) ; Volume 3 of 4 (2019)

Molten Salt Reactor Fuel Depletion Tools in SCALE

von Betzler, Benjamin R.
Veröffentlicht in International Nuclear Fuel Cycle Conference (2019 : Seattle, Wash.) International Nuclear Fuel Cycle Conference (GLOBAL 2019) ; Volume 2 of 2 (2020)