Standing wave nuclear fission reactor and methods
Disclosed embodiments include nuclear fission reactor cores, nuclear fission reactors, methods of operating a nuclear fission reactor, and methods of managing excess reactivity in a nuclear fission reactor.
1. A method of operating a nuclear fission reactor, the method comprising:
fissioning fissile nuclear fuel material in a plurality of fissile nuclear fuel assemblies in a central core region of a nuclear fission reactor core of a nuclear fission reactor;
breeding fissile material in ones of a plurality of fertile nuclear fuel assemblies in the central core region of the nuclear fission reactor core; and
shuffling selected ones of the plurality of fissile nuclear fuel assemblies and selected ones and selected others of the plurality of fertile nuclear fuel assemblies in a manner that establishes a standing wave of breeding fissile nuclear fuel material and fissioning fissile nuclear fuel material.
2. The method of claim 1 , wherein fissioning fissile nuclear fuel material in a plurality of fissile nuclear fuel assemblies in a central core region of a nuclear fission reactor core of a nuclear fission reactor includes generating in the central core region at least a predetermined amount of power in the nuclear fission reactor core.
3. The method of claim 1 , further comprising:
absorbing neutrons in a peripheral core region.
4. The method of claim 3 , wherein absorbing neutrons in a peripheral core region includes absorbing neutrons in others of the plurality of fertile nuclear fuel assemblies in the peripheral core region.
5. The method of claim 4 , wherein absorbing neutrons in others of the plurality of fertile nuclear fuel assemblies in the peripheral core region includes breeding fissile material in others of the plurality of fertile nuclear fuel assemblies in the peripheral core region.
6. The method of claim 3 , wherein absorbing neutrons in a peripheral core region includes absorbing neutrons in a plurality of neutron absorber assemblies in the peripheral core region.
7. The method of claim 6 , wherein absorbing neutrons in a plurality of neutron absorber assemblies in the peripheral core region includes absorbing neutrons in a plurality of neutron absorber assemblies in the peripheral core region such that power produced in the peripheral core region is maintained below a predetermined power level.
8. The method of claim 3 , wherein absorbing neutrons in a peripheral core region includes absorbing neutrons in others of the plurality of fertile nuclear fuel assemblies in the peripheral core region and absorbing neutrons in a plurality of neutron absorber assemblies in the peripheral core region.
9. The method of claim 1 , further comprising:
shutting down the nuclear fission reactor before shuffling selected ones of the plurality of fissile nuclear fuel assemblies and selected ones and selected others of the plurality of fertile nuclear fuel assemblies.
10. The method of claim 1 , wherein shuffling selected ones of the plurality of fissile nuclear fuel assemblies and selected ones and selected others of the plurality of fertile nuclear fuel assemblies in a manner that establishes a standing wave of breeding fissile nuclear fuel material and fissioning fissile nuclear fuel material includes shuffling selected ones of the plurality of fissile nuclear fuel assemblies and selected ones and selected others of the plurality of fertile nuclear fuel assemblies between the central core region and the peripheral core region in a manner that establishes a standing wave of breeding fissile nuclear fuel material and fissioning fissile nuclear fuel material.
11. The method of claim 1 , wherein shuffling selected ones of the plurality of fissile nuclear fuel assemblies and selected ones and selected others of the plurality of fertile nuclear fuel assemblies includes replacing selected ones of the plurality of fissile nuclear fuel assemblies of the central core region with selected ones of the plurality of fertile nuclear fuel assemblies of the central core region and with selected others of the plurality of fertile nuclear fuel assemblies of the peripheral core region.
12. The method of claim 1 , wherein shuffling selected ones of the plurality of fissile nuclear fuel assemblies and selected ones and selected others of the plurality of fertile nuclear fuel assemblies includes shuffling selected ones of the plurality of fissile nuclear fuel assemblies having a predetermined burnup level and selected ones and selected others of the plurality of fertile nuclear fuel assemblies.
13. The method of claim 1 , further comprising:
controlling reactivity in the central core region.
14. The method of claim 13 , wherein controlling reactivity in the central core region includes controlling reactivity in the central core region with a plurality of movable reactivity control assemblies.
15. The method of claim 13 , wherein controlling reactivity in the central core region includes shuffling selected ones of the plurality of fissile nuclear fuel assemblies and selected ones and selected others of the plurality of fertile nuclear fuel assemblies.
16. The method of claim 13 , wherein controlling reactivity in the central core region includes controlling reactivity in the central core region with a plurality of movable reactivity control assemblies and shuffling selected ones of the plurality of fissile nuclear fuel assemblies and selected ones and selected others of the plurality of fertile nuclear fuel assemblies.
17. The method of claim 1 , further comprising:
flowing reactor coolant through a first plurality of reactor coolant flow orifices in the central core region; and
flowing reactor coolant through a second plurality of reactor coolant flow orifices in the peripheral core region.
18. The method of claim 17 , wherein flowing reactor coolant through a first plurality of reactor coolant flow orifices in the central core region includes flowing reactor coolant through a plurality of reactor coolant flow orifice groups in the central core region.
19. The method of claim 18 , wherein flow rate through a selected one of the plurality of reactor coolant flow orifice groups is based upon a power profile at a radial location of the selected one of the plurality of reactor coolant flow orifice groups.
20. The method of claim 17 , wherein flow rate through the second plurality of reactor coolant flow orifices includes a predetermined flow rate based upon power level in the peripheral core region.
21. The method of claim 17 , wherein flowing reactor coolant through a first plurality of reactor coolant flow orifices in the central core region and flowing reactor coolant through a second plurality of reactor coolant flow orifices in the peripheral core region includes maintaining substantially steady flow of reactor coolant through ones of the first and second pluralities of reactor coolant flow orifices.
22. The method of claim 17 , wherein flowing reactor coolant through a first plurality of reactor coolant flow orifices in the central core region and flowing reactor coolant through a second plurality of reactor coolant flow orifices in the peripheral core region includes varying flow of reactor coolant through others of the first and second pluralities of reactor coolant flow orifices.
23. The method of claim 17 , wherein flowing reactor coolant through a first plurality of reactor coolant flow orifices in the central core region and flowing reactor coolant through a second plurality of reactor coolant flow orifices in the peripheral core region includes maintaining substantially steady flow of reactor coolant through ones of the first and second pluralities of reactor coolant flow orifices and varying flow of reactor coolant through others of the first and second pluralities of reactor coolant flow orifices.
24. The method of claim 17 , further comprising:
varying flow of reactor coolant through at least one of the shuffled nuclear fuel assemblies.
25. The method of claim 24 , wherein varying flow of reactor coolant through at least one of the shuffled nuclear fuel assemblies includes rotating at least one of the shuffled nuclear fuel assemblies.
26. The method of claim 6 , further comprising:
moving ones of the plurality of neutron absorber assemblies among a plurality of locations in the peripheral core region.
27. The method of claim 26 , wherein the plurality of locations in the peripheral core region includes a plurality of predetermined radial locations in the peripheral core region that are selectable based upon a predetermined burnup level of ones of the fissile nuclear fuel assemblies that have been shuffled into the peripheral core region.