Neutron reflector assembly for dynamic spectrum shifting
A dynamic neutron reflector assembly for a “breed-and-burn” fast reactor incrementally adjusts neutron spectrum and reactivity in a reactor core. The composition of materials in the dynamic neutron reflector may be adjusted to change neutron reflectivity levels, or to introduce neutron moderating or absorption characteristics. The dynamic neutron reflector may contain a flowing reflecting liquid of adjustable volume and/or density. Submergible members may be selectively inserted into the flowing reflecting liquid to alter its volume and introduce other neutron modifying effects such as moderation or absorption. Selective insertion of the submergible members allows for concentration of the neutron modifying effects in a selected portion of the reactor core. The flowing reflecting liquid may also act as a secondary coolant circuit by exchanging heat with the molten fuel salt.
1. A system comprising:
a neutron reflector assembly configured to surround a nuclear reactor core during a sustained nuclear fission reaction; and
the neutron reflector assembly being further configured to adjust fast neutron flux and thermal neutron flux within the reactor core by altering reflectivity characteristics of reflector material in the neutron reflector assembly during a sustained nuclear fission reaction;
wherein the neutron reflector assembly includes a plurality of cylindrical tubes containing reflector material, at least two of the tubes in the plurality of tubes having different radius values.
2. The system of claim 1 , further comprising:
a heat exchanger, wherein the neutron reflector assembly is in thermal communication with the heat exchanger.
3. The system of claim 2 , further comprising:
a molten nuclear fuel salt in the nuclear reactor core, wherein the neutron reflector assembly is in thermal communication with the molten nuclear fuel salt.
4. The system of claim 3 , further comprising:
a tube and shell heat exchanger, wherein the neutron reflector assembly is in thermal communication with the molten nuclear fuel salt via the tube and shell heat exchanger.
5. The system of claim 1 , wherein the reflector material includes a flowing liquid neutron reflector.
6. The system of claim 5 , further comprising a flowing liquid neutron reflector spillover reservoir.
7. The system of claim 1 , wherein the neutron reflector assembly includes a plurality of refractory clad sleeves.
8. The system of claim 1 , further comprising a plurality of neutron moderating members, each neutron moderating member selectively insertable into neutron reflector assembly.
9. The system of claim 5 , wherein the flowing liquid neutron reflector is molten lead.
10. The system of claim 5 , wherein the flowing liquid neutron reflector is molten lead-bismuth.
11. The system of claim 5 , wherein the neutron reflector assembly is further configured to maintain the flowing liquid neutron reflector in a creeping flow.
12. The system of claim 1 , wherein the neutron reflector assembly includes a flowing liquid moderator.
13. The system of claim 1 , wherein the neutron reflector assembly includes a primary static neutron reflector sub-assembly and a secondary dynamic neutron reflector sub-assembly.
14. The system of claim 1 , wherein the neutron reflector assembly includes a plurality of cylindrical tubes flowing reflector material in neutronic communication with the nuclear reactor core during the sustained nuclear fission reaction.
15. A system comprising:
a neutron reflector assembly configured to surround a nuclear reactor core during a sustained nuclear fission reaction;
the neutron reflector assembly being further configured to adjust fast neutron flux and thermal neutron flux within the reactor core by altering reflectivity characteristics of reflector material in the neutron reflector assembly during a sustained nuclear fission reaction;
a heat exchanger, wherein the neutron reflector assembly is in thermal communication with the heat exchanger; and
a molten nuclear fuel salt in the nuclear reactor core, wherein the neutron reflector assembly is in thermal communication with the molten nuclear fuel salt.
16. The system of claim 15 , wherein the heat exchanger is a tube and shell heat exchanger.
17. The system of claim 15 , wherein the heat exchanger is a tube and shell heat exchanger and the neutron reflector assembly is in thermal communication with the molten nuclear fuel salt via the tube and shell heat exchanger.
18. The system of claim 15 , wherein the reflector material includes a flowing liquid neutron reflector.
19. The system of claim 18 , further comprising a flowing liquid neutron reflector spillover reservoir.
20. The system of claim 15 , wherein the neutron reflector assembly includes a plurality of refractory clad sleeves.
21. The system of claim 15 , further comprising a plurality of neutron moderating members, each neutron moderating member selectively insertable into neutron reflector assembly.
22. The system of claim 18 , wherein the flowing liquid neutron reflector is molten lead.
23. The system of claim 18 , wherein the flowing liquid neutron reflector is molten lead-bismuth.
24. The system of claim 18 , wherein the neutron reflector assembly is further configured to maintain the flowing liquid neutron reflector in a creeping flow.
25. The system of claim 15 , wherein the neutron reflector assembly includes a flowing liquid moderator.
26. The system of claim 15 , wherein the neutron reflector assembly includes a primary static neutron reflector sub-assembly and a secondary dynamic neutron reflector sub-assembly.
27. The system of claim 15 , wherein the neutron reflector assembly includes a plurality of cylindrical tubes flowing reflector material in neutronic communication with the nuclear reactor core during the sustained nuclear fission reaction at least two of the tubes in the plurality of tubes having different radius values.