Preliminary Nuclear Design Studies for a Small Modular Advanced High Temperature Reactor (SmAHTR)

摘要

The SmAHTR core was modeled and depleted using the ORNL's SCALE code system to assess the cycle length of the core.rnThe model was also used to estimate certain neutronic parameters of importance for reactor safety (reactivity coefficients), and for materials irradiation fluence estimations.rnThe model can be further used to estimate the power distribution, additional reactivity effects and kinetic parameters of importance for thermo-hydraulic calculations~4 (e.g., control rod worths delayed neutron fraction, neutron lifetime).