Devices, systems, and methods for configuring the layout of unit cell of a reactor core
A configurable unit cell of a core of a nuclear reactor is disclosed herein. The configurable unit cell includes a core block material and a plurality of interchangeable components configured to affect a performance parameter of the core of the nuclear reactor. The configurable unit cell further includes a plurality of channels defined within the core block material. Each channel of the plurality of channels is configured to engage an interchangeable component of the plurality of interchangeable components in an operating configuration. Each channel of the plurality of channels is separated from an adjacent channel of the plurality of channels by a predetermined pitch.
1 . A core of a nuclear reactor, the core having an axial length, the core comprising:
a plurality of components comprising a plurality of heat pipes, a plurality of fuel rods, a plurality of moderators, and a plurality of reactivity control rods; and
a plurality of unit cells arranged in a plurality of rows, wherein each unit cell of the plurality of unit cells is formed of a core block material, wherein the core block material comprises a first moderator material and wherein the plurality of unit cells comprise:
a standard unit cell comprising a first plurality of channels defined within the core block material, wherein the first plurality of channels comprise:
a first channel configured to accommodate a first heat pipe of the plurality of heat pipes;
a second channel configured to accommodate a first fuel rod of the plurality of fuel rods; and
a third channel configured to accommodate a moderator of the plurality of moderators, the moderator comprising a second moderator material; and
a reactivity control cell comprising a second plurality of channels defined within the core block material, wherein the second plurality of channels comprise:
a fourth channel to accommodate a second heat pipe of the plurality of heat pipes;
a fifth channel to accommodate a second fuel rod of the plurality of fuel rods; and
a sixth channel to accommodate a first reactivity control rod of the plurality of reactivity control rods.
2 . The core of claim 1 , wherein the first moderator material and the second moderator material are configured to suppress a propagation of neutrons generated by at least a portion of the plurality of fuel rods.
3 . The core of claim 2 , wherein the first moderator material comprises graphite.
4 . The core of claim 1 , wherein each unit cell of the plurality of unit cells is modularly configured to be coupled to an adjacent unit cell of the plurality of unit cells, such that a number of unit cells in the plurality of unit cells can be adjusted.
5 . The core of claim 4 , wherein the plurality of components comprises the plurality of heat pipes, and wherein each unit cell of the plurality of configurable unit cells is arranged such that a predetermined gap exists between a first unit cell of the plurality of unit cells and a second unit cell of the plurality of unit cells, and wherein the predetermined gap corresponds to a predetermined heat transfer parameter of the core in an event of heat pipe failure.
6 . The core of claim 1 , wherein the first channel, the second channel, and the third channel are defined in the core block material at a uniform predetermined pitch such that the center-to-center distance between any two adjacent channels of the first channel, the second channel, and the third channel is the same.
7 . The core of claim 6 , wherein the uniform predetermined pitch is greater than or equal to 20 millimeters and less than or equal to 40 millimeters.
8 . The core of claim 1 , wherein the first channel comprises a first diameter and wherein the second channel comprises a second diameter, wherein the first diameter is different from the second diameter.
9 . The core of claim 8 , wherein the first diameter is configured to define a first predetermined gap between the first heat pipe and an internal wall of the first channel.
10 . The core of claim 9 , wherein the second diameter is configured to define a second predetermined gap between the first fuel rod and an internal wall of the second channel.
11 . The core of claim 1 , wherein the plurality of unit cells are arranged to define a third predetermined gap between any two adjacent unit cells of the plurality of unit cells.
12 . The core of claim 11 , wherein the third predetermined gap is less than or equal to 2 millimeters.
13 . The core of claim 1 , wherein the first moderator material and the second moderator material are different.
14 . The core of claim 1 , wherein the second moderator material comprises a hydride based material or Beryllium Oxide.
15 . The core of claim 1 , wherein the plurality of unit cells are stacked onto each other to form the axial length of the core.
16 . A core of a nuclear reactor, the core having an axial length, the core comprising:
a plurality of heat pipes;
a plurality of fuel rods;
a plurality of moderators;
a plurality of reactivity control rods; and
a plurality of unit cells arranged in a plurality of rows, wherein each unit cell of the plurality of unit cells is formed of a core block material, wherein the core block material comprises a first moderator material, wherein the plurality of unit cells comprise:
a first unit cell comprising a first plurality of channels defined within the core block material, wherein the first plurality of channels are arranged in the core block material at a uniform pitch such that the center-to-center distance between any two adjacent channels of the first plurality of channels is the same, and wherein the first plurality of channels comprise:
a first channel to receive a first heat pipe of the plurality of heat pipes;
a second channel to receive a first fuel rod of the plurality of fuel rods; and
a third channel to receive a moderator of the plurality of moderators, the moderator comprising a second moderator material; and
a second control cell comprising a second plurality of channels defined within the core block material, wherein the second plurality of channels comprise:
a fourth channel to receive a second heat pipe of the plurality of heat pipes;
a fifth channel to receive a second fuel rod of the plurality of fuel rods; and
a sixth channel to receive a first reactivity control rod of the plurality of reactivity control rods.
17 . The core of claim 16 , wherein the first moderator material and the second moderator material are configured to suppress a propagation of neutrons generated by at least a portion of the plurality of fuel rods.
18 . The core of claim 16 , wherein the first moderator material comprises graphite.
19 . The core of claim 16 , wherein the first moderator material and the second moderator material are different.
20 . The core of claim 16 , wherein the second moderator material comprises a hydride based material or Beryllium Oxide.
21 . The core of claim 16 , wherein the plurality of unit cells are stacked onto each other to form the axial length of the core.