Methods and apparatus for suppressing tritium permeation during tritium production
A tritium production element for use in a conventional power reactor, and methods of use and making, are provided, wherein the element experiences reduced tritium permeation during irradiation by incorporating a silicon carbide barrier that encapsulates one or more burnable absorber pellets. The tritium production element includes a tubular cladding that encloses a plurality of burnable absorber pellets, such that individual pellets or groups of pellets are disposed within a silicon carbide barrier layer.
1. A tritium production element for use in a nuclear reactor, comprising:
a substantially cylindrical cladding having a length and an inner diameter;
a plurality of tritium producing burnable absorber pellets disposed within the cladding, each pellet of the plurality including a first surface, a second surface, and a substantially cylindrical sidewall extending between the first surface and the second surface, the sidewall including an outer diameter dimensioned to fit within the inner diameter of the cladding, the plurality of pellets arranged in an end-to-end relation; and
at least one silicon carbide barrier substantially hermetically sealing tritium within the pellets of the plurality, each of the at least one silicon carbide barriers including a first portion arranged radially over the first surface of at least one of the pellets of the plurality, a second portion arranged radially over the second surface of at least one of the pellets of the plurality, and a sidewall portion axially extending between the first portion and the second portion, the sidewall portion being concentrically arranged between the substantially cylindrical sidewall of at least one of the pellets of the plurality and the substantially cylindrical cladding,
wherein the at least one silicon carbide barrier comprises a free-standing container into which one or more of the tritium producing burnable absorber pellets are sealed.
2. The tritium production element of claim 1 , wherein each one of the plurality of tritium producing burnable absorber pellets is sealed within a corresponding silicon carbide barrier.
3. The tritium production element of claim 1 , wherein a plurality of tritium producing burnable absorber pellets is sealed within a corresponding silicon carbide barrier.
4. The tritium production element of claim 1 , wherein at least some of the plurality of tritium producing burnable absorber pellets have an annular configuration.
5. The tritium production element of claim 1 , wherein the sidewall portion of each of the at least one silicon carbide barriers contacts the substantially cylindrical cladding.
6. The tritium production element of claim 1 , wherein the at least one silicon carbide barrier has a thickness of between about 200 micron and 500 micron.
7. The tritium production element of claim 1 , wherein the cylindrical cladding has outer dimensions substantially the same as the outer dimensions of a fuel rod used within the nuclear reactor.
8. The tritium production element of claim 1 , wherein the tritium producing burnable absorber pellets comprise lithium aluminate.
9. A tritium production assembly for use in a nuclear reactor, comprising:
a plurality of tritium production elements arranged in a bundle, the bundle having hydraulic characteristics substantially the same as a fuel bundle used in the nuclear reactor, wherein each tritium production element comprises:
a substantially cylindrical cladding having a length and an inner diameter;
a plurality of tritium producing burnable absorber pellets disposed within the cladding, each pellet of the plurality including a first surface, a second surface, and a substantially cylindrical sidewall extending between the first surface and the second surface, the sidewall including an outer diameter dimensioned to fit within the inner diameter of the cladding, the plurality of pellets arranged in an end-to-end relation; and
at least one silicon carbide barrier substantially hermetically sealing tritium within the pellets of the plurality, each of the at least one silicon carbide barriers including a first portion arranged radially over the first surface of at least one of the pellets of the plurality, a second portion arranged radially over the second surface of at least one of the pellets of the plurality, and a sidewall portion axially extending between the first portion and the second portion, the sidewall portion being concentrically arranged between the substantially cylindrical sidewall of at least one of the pellets of the plurality and the substantially cylindrical cladding,
wherein, within each tritium production element, the at least one silicon carbide barrier comprises a free-standing container into which one or more of the tritium producing burnable absorber pellets are sealed.
10. The tritium production assembly of claim 9 , wherein, within each tritium production element, each one of the plurality of tritium producing burnable absorber pellets is sealed within a corresponding silicon carbide barrier.
11. The tritium production assembly of claim 9 , wherein, within each tritium production element, a plurality of tritium producing burnable absorber pellets is sealed within a corresponding silicon carbide barrier.
12. The tritium production assembly of claim 9 , wherein, within each tritium production element, at least some of the plurality of tritium producing burnable absorber pellets has an annular configuration.
13. The tritium production assembly of claim 9 , wherein, within each tritium production element, the sidewall portion of each of the at least one silicon carbide barriers contacts the substantially cylindrical cladding.
14. The tritium production assembly of claim 9 , wherein, within each tritium production element, the at least one silicon carbide barrier has a thickness of between about 200 microns and 500 microns.
15. The tritium production assembly of claim 9 , wherein the tritium producing burnable absorber pellets comprise lithium aluminate.
16. The tritium production assembly of claim 15 , wherein a majority of the tritium production elements within the assembly have cylindrical cladding having outer dimensions substantially the same as the outer dimensions of fuel rods used within the nuclear reactor.