System and method for annealing nuclear fission reactor materials
Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials.
1. An apparatus comprising:
electrical circuitry for determining an annealing temperature range for at least a portion of at least one metallic component of a nuclear fission fuel assembly of a nuclear fission reactor; and
means for establishing at least the portion of the nuclear fission fuel assembly within the annealing temperature range by adjusting operational parameters of the nuclear fission reactor to establish, while the nuclear fission reactor is operating, operating conditions of a region of the operating nuclear fission reactor containing the at least one metallic component: (i) within the determined annealing temperature range for a period of time selected to produce annealing of at least the portion of the at least one metallic component, (ii) lower than the determined annealing temperature range in a quenching temperature range, and (iii) above the determined annealing temperature range in a tempering temperature range, responsive to the electrical circuitry for determining an annealing temperature range.
2. The apparatus of claim 1 , wherein the means for establishing at least the portion of the nuclear fission fuel assembly within the annealing temperature range includes a reactor coolant system.
3. The apparatus of claim 2 , wherein the reactor coolant system includes at least one reactor coolant pump.
4. The apparatus of claim 2 , wherein the reactor coolant system includes at least one flow adjustment device.
5. The apparatus of claim 1 , wherein the means for establishing at least the portion of the nuclear fission fuel assembly within the annealing temperature range includes a reactor control system.
6. The apparatus of claim 1 , wherein the means for establishing at least the portion of the nuclear fission fuel assembly within the annealing temperature range includes a pressurizer.
7. The apparatus of claim 1 , wherein the annealing temperature range is higher than an operating temperature range of the reactor core.