摘要:
A moderating fuel rod for a boiling water reactor may include a nuclear fuel section; a neutron moderator section including a metal hydride; and a threaded connector joining the nuclear fuel section and the neutron moderator section. By including one or more moderating fuel rods in a fuel bundle, the neutron moderation within the fuel bundle may be improved, thereby allowing energy to be more efficiently extracted from the entire length of the fuel bundle.
摘要:
A moderating fuel rod for a boiling water reactor may include a nuclear fuel section; a neutron moderator section including a metal hydride; and a threaded connector joining the nuclear fuel section and the neutron moderator section. By including one or more moderating fuel rods in a fuel bundle, the neutron moderation within the fuel bundle may be improved, thereby allowing energy to be more efficiently extracted from the entire length of the fuel bundle.
摘要:
A boiling water reactor core according to an example embodiment may include a core shroud and a plurality of fuel bundles within the core shroud. A plurality of shielding bundles are arranged as a fast flux shield between the plurality of fuel bundles and the core shroud. The plurality of shielding bundles include a metal hydride as a neutron moderator.