The utilization of molten fuels in a nuclear reactor to produce power provides significant advantages as compared to solid fuels. For instance, molten fuel reactors generally provide higher power densities compared to solid fuel reactors, while at the same time having reduced fuel costs due to the relatively high cost of solid fuel fabrication.
Molten fluoride fuel salts suitable for use in nuclear reactors have been developed using uranium tetrafluoride (UF4) mixed with other fluoride salts as well as using fluoride salts of thorium. Molten fluoride salt reactors have been operated at average temperatures between 600° C. and 860° C. Binary, ternary, and quaternary chloride fuel salts of uranium, as well as other fissionable elements, have been described in co-assigned U.S. patent application Ser. No. 14/981,512, titled MOLTEN NUCLEAR FUEL SALTS AND RELATED SYSTEMS AND METHODS, which application is hereby incorporated herein by reference. In addition to chloride fuel salts containing one or more of UCl4, UCl3F, UCl3, UCl2F2, and UClF3, the application further discloses fuel salts with modified amounts of 37Cl, bromide fuel salts such as UBr3 or UBr4, thorium chloride fuel salts, and methods and systems for using the fuel salts in a molten fuel reactor. Average operating temperatures of chloride salt reactors are anticipated between 300° C. and 800° C., but could be even higher, e.g., >1000° C.
Direct reactor auxiliary cooling systems (DRACS) are described below and provide decay heat removal to molten chloride fast reactors (MCFR) to limit temperature increases in the reactor before there is damage to any of the components. The DRACS includes a heat exchanger disposed within the reactor and that is dedicated to the removal of decay heat during a reactor shutdown event. This DRACS heat exchanger is referred to as a decay heat heat exchanger (DHHX) to differentiate from primary heat exchangers (PHX) also used in the reactor.
In one aspect, the technology relates to a MCFR including: a plurality of reflectors defining a central core, wherein the central core includes a core geometric center; a flow channel fluidically connected to the central core, wherein the flow channel includes an outlet flow channel downstream of the central core and an inlet flow channel upstream from the central core; a PHX disposed outside the central core and between the outlet flow channel and the inlet flow channel; and a DHHX, wherein at least a portion of the DHHX is disposed above the core geometric center, and wherein a fuel salt is configured to circulate at least partially through the outlet flow channel, the DHHX, the PHX, the inlet flow channel, and the central core.
In an example, the DHHX is disposed upstream from the PHX. In another example, a pump for circulating the fuel salt is included and the DHHX is disposed upstream from the pump. In yet another example, the pump is disposed upstream from the PHX. In still another example, a flow direction of the fuel salt through the DHHX is different than a flow direction of the fuel salt through the pump. In an example, a flow conditioner is disposed at least partially in the outlet flow channel. In another example, the DHHX includes the flow conditioner.
In yet another example, the DHHX includes a shell and a plurality of tubes. In still another example, the plurality of tubes are disposed substantially parallel to the outlet flow channel. In an example, a cooling circuit including the DHHX is included, wherein a coolant fluid is configured to circulate through the cooling circuit and remove heat from the fuel salt. In another example, the cooling circuit is devoid of a circulating pump. In yet another example, a flow of the coolant fluid through the DHHX is substantially orthogonal to a flow of the fuel salt through the DHHX. In still another example, the cooling circuit is a first cooling circuit, and the MCFR further includes a second cooling circuit including the PHX, the first cooling circuit is independent from the second cooling circuit.
In another aspect, the technology relates to a MCFR including: a vessel including a plurality of structures disposed therein and defining at least one flow channel for circulating fuel salt within the vessel; a core geometric center defined within the vessel; and a DHHX disposed within the vessel and at least partially above the core geometric center.
In an example, the DHHX is coupled in flow communication to at least one cooling circuit that removes heat from the fuel salt. In another example, a PHX is disposed within the vessel, and the DHHX is upstream of the PHX relative the circulation of fuel salt.
In another aspect, the technology relates to a DRACS for a MCFR, the DRACS including: a DHHX disposed within a MCFR reactor vessel and at least partially above a core geometric center, wherein the DHHX includes a shell and a plurality of tubes, and wherein the plurality of tubes receive a flow of fuel salt within the MCFR reactor vessel; and a cooling circuit coupled in flow communication with the shell and configured to circulate a coolant fluid therein.
In an example, a second heat exchanger is coupled in flow communication with the cooling circuit, and the second heat exchanger is positioned at a height that is greater than a height of the DHHX. In another example, the second heat exchanger receives a flow of air to remove heat from the coolant fluid. In yet another example, a flow conditioner is included.
The following drawing figures, which form a part of this application, are illustrative of described technology and are not meant to limit the scope of the technology as claimed in any manner, which scope shall be based on the claims appended hereto.
This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor. For the purposes of this application, embodiments of a molten fuel fast reactor that use a chloride fuel will be described. However, it will be understood that any type of fuel salt, now known or later developed, may be used and that the technologies described herein may be equally applicable regardless of the type of fuel used, such as, for example, salts having one or more of U, Pu, Th, or any other actinide. Note that the minimum and maximum operational temperatures of fuel within a reactor may vary depending on the fuel salt used in order to maintain the salt within the liquid phase throughout the reactor. Minimum temperatures may be as low as 300-350° C. and maximum temperatures may be as high as 1400° C. or higher.
The primary heat exchangers 110 transfer heat from the molten fuel salt 106 to a primary coolant 114 that is circulated through a primary coolant loop 115. In an embodiment the primary coolant may be another salt, such as NaCl—MgCl2, or lead. Other coolants are also possible including Na, NaK, supercritical CO2 and lead bismuth eutectic. In an embodiment, a reflector 108 is between each primary heat exchanger 110 and the reactor core 104 as shown in
In the embodiment shown in
Salt-facing elements of the heat exchanger 110 and the primary coolant loop 115 may be clad to protect against corrosion. Other protection options include protective coatings, loose fitting liners or press-fit liners. In an embodiment, cladding on the internal surface of the tubes is molybdenum that is co-extruded with the base heat exchanger tube material. For other fuel salt contacting surfaces (exterior surfaces of the tube sheets and exterior surface of the shell), the cladding material is molybdenum alloy. Nickel and nickel alloys are other possible cladding materials. Niobium, niobium alloys, and molybdenum-rhenium alloys may be used where welding is required. Components in contact with primary cooling salt may be clad with Alloy 200 or any other compatible metals, such as materials meeting the American Society of Mechanical Engineers' pressure vessel code. The tube primary material may be 316 stainless steel or any other compatible metals. For example, in an embodiment, alloy 617 is the shell and tube sheet material.
The molten fuel reactor 100 further includes at least one containment vessel 118 that contains the fuel circuit 116 to prevent a release of molten fuel salt 106. The containment vessel 118 is often made of two components: a lower, vessel portion 118v that takes the form of a unitary, open-topped vessel with no penetrations of any kind; and an upper, cap portion 118h referred to as the vessel head that covers the top of the vessel portion 118v. All points of access to the reactor 100 are from the top through the vessel head 118h.
One possible situation faced by the reactor 100 is a loss of forced flow event in which, possibly due to a power failure or some other cause, the salt pumps 112 cease to function. In such an event, the reactor 100 must still be cooled to prevent an unacceptable temperature increase even after the protection system shuts down the fission chain reaction because fission products in the fuel salt 106 will continue to produce decay heat. As such, reactors 100 are often provided with a direct reactor auxiliary cooling system (DRACS) 120 specifically to limit this temperature increase before there is damage to any of the components. A DRACS 120 is an auxiliary cooling system, which may or may not be completely independent of the primary coolant loop 115, which is designed to provide auxiliary cooling in certain circumstances, such as to remove decay heat from the fuel salt 106 during a loss of forced flow event or other events. The DRACS 120 may be a single loop system with a heat exchanger 122 disposed within the reactor 100. In some examples, multiple independent DRACS 120 loops may be used in the reactor 100, each corresponding to different parallel fuel salt flow paths. Additionally or alternatively, the DRACS 120 may have any number of multiple loops connected through additional external heat exchangers (not shown) to remove the heat from the reactor 100.
In some cases, a DRACS 120 relies on the natural circulation of the fuel salt through the fuel circuit 116, because higher temperature molten salt is less dense than lower temperature salt. For example, in one fuel salt (71 mol % UCl4-17 mol % UCl3-12 mol % NaCl) for a 300° C. temperature rise (e.g., 627° C. to 927° C.), the fuel salt density was calculated to fall by about 18%, from 3680 to 3010 kg/m3. The density differential created by the temperature difference between the higher temperature salt in the core and the lower temperature salt elsewhere in the fuel circuit 116 creates a circulation cell in the fuel circuit. This circulation is referred to as natural circulation and occurs without the use of pumps 112. In other examples, the circulation may be an active flow driven by the pumps 112.
In various embodiments depicted herein, one or more DHHXs 122 may be disposed in the containment vessel 118, in various locations as required or desired for a particular application. In
In the embodiment shown in
The primary coolant and the DRACS coolant may be the same composition or may be different. In an embodiment the primary and/or DRACS coolant may be another salt, such as NaCl—MgCl2, or lead. Other coolants are also possible including Na, NaK, supercritical CO2, lead bismuth eutectic, Galinstan (e.g., eutectic alloy of gallium, indium, and tin), as well as liquid metals, air, etc. During normal, power-generating operation, the DRACS 120 may or may not be cooling the fuel salt 106. In one embodiment, for example, the DHHXs 122 do not provide any significant cooling during normal operation so that vast majority of the heat removed from the fuel salt is removed by the PHXs 110. In this embodiment, DRACS coolant in the DHHX 122 is allowed to heat up to the operating temperature. The heated DRACS coolant may be periodically or continuously circulated, such as through the DHHX 122 or the DRACS coolant loop 124, to prevent fouling. In an alternative embodiment, the DRACS 120 is continuously operated and the heat removed by the DRACS coolant loop 124 may or may not be recovered for power generation or general heating.
In operation, the fuel salt exits the reactor core 104 and may enter the DHHX 122 that, for example, is contained within an upper flow channel. In an aspect, the DHHX 122 may be a single path cross-flow shell and tube heat exchanger, and as such, the fuel salt is channeled through the tube-side of the DHHX 122 and heat is removed on the shell-side of the DHHX 122 via a coolant fluid channeled through the DRACS coolant loop 124. Examples of the DRACS coolant includes, but is not limited to, molten salts, liquid metals (e.g., Galinstan), air, etc. The DRACS coolant loop 124 may be a forced active flow (e.g., pumped) or driven via natural circulation of the coolant through the DHHX 122 (e.g., devoid of any primary circulating pumps). When the loop 124 is driven by natural circulation, the loop 124 may include a pump for startup, shakedown, or testing as required or desired. The DRACS 120 may further include any number of additional coolant loops connected through additional heat exchangers (e.g., the heat exchanger 126) to remove heat through the DHHX 122 from the core 104. In the example depicted in
Broadly speaking, this disclosure describes multiple alterations and component configurations that improve the performance of the reactor 100 described with reference to
Example Molten Fuel Reactor Configurations
Fuel salt flow 206 may continue to an optional displacement volume 216 so that the amount of fuel salt through the flow path can be reduced and/or increased as required or desired. In other examples, the displacement volume 216 may be in fluid communication with a separate displacement tank (not shown) that is configured to store at least a portion of the fuel salt. Additionally or alternatively, a displacement volume 217 (shown in
With regard to cooling flow circuits (that is, flow circuits that are partially within and partially outside of the vessel 202), two interconnected circuits are depicted. A primary coolant loop 220 is connected to the PHX 214 and transfers heat to a primary coolant that is channeled through the PHX 214. Similarly, a DRACS coolant loop 224 transfers decay heat to a DRACS coolant that is channeled through the DHHX 210. In the depicted configuration, both the primary coolant loop 220 and the DRACS coolant loop 224 are served by a single coolant loop 228, where heat is withdrawn for energy production, as described elsewhere herein. In the single coolant loop 228 depicted, coolant 230 (e.g., cold molten salt) is delivered, via one or more pumps 234, in parallel to the inlet of both the PHX 214 and DHHX 210, with heated coolant 232 (e.g., hot molten salt) exhausted from those components. The coolant loop 228 may be a single coolant loop (e.g., only include the DHHX 210 and PHX 214 within the vessel 202) or have multiple coolant loops and include one or more external heat exchangers (not shown) disposed outside of the vessel 202. In other examples, the coolant loop 228 may include other coolant fluids, such as, but not limited to, liquid metals (e.g., Galinstan), air, etc. as required or desired. By using the coolant loop 228, the number of redundant systems and components decreases, thereby lowering costs of the coolant loop.
Alternative embodiments are also possible. For example, the DHHXs 210 in a heat exchanger circuit may be different types of heat exchanges. In addition to shell and tube heat exchangers, plate (sometimes also called plate-and-frame), plate and shell, printed circuit (also known as diffusion bonded compact heat exchangers), plate fin heat exchangers, concentric tube (or pipe) heat exchangers (sometimes also called jacketed pipe or double pipe heat exchangers), and bayonet tube heat exchangers may be suitable. Likewise, the location of the coolant inlet 240 and return ducts may be varied.
In the example, the tubeset 238 is supported by one or more plates 242. In addition to enabling support of the tubeset 238, the plates 242 also perform as an integrated flow straightening device so as to straighten the flow of the molten fuel salt 206 as it is channeled through the tubeset 238. By placing the DHHX 210 within the exit channel 208, undesirable flow conditions such as turbulence, eddies, swirl flows, non-uniform velocity profiles, and the like may be reduced or eliminated in the fuel salt flow 206. To reduce pump cavitation induced by these undesirable flow conditions and to increase pump efficiencies, the plates 242 are configured to reduce the swirl components in the fluid flow when channeled through the DHHX 210. Flow straightening may be done using any other kind of baffles, contours, vanes, flow conditioners, and/or other equipment as required or desired. For example, the plates 242 may act in concert with the exit channel 208 (formed by one or more reflectors) to define the flow conditioner that straightens the fuel salt flow 206.
Alternative embodiments are also possible. For example, the flow straightening device may be a separate flow conditioner component from the DHHX 210 and positioned downstream from the DHHX 210 and upstream of the pump 212. In other examples, the flow straightening device may be upstream of the DHHX 210. In another example, the flow straightening device may be positioned proximate the end of the exit channel 208 where the fuel salt flow 206 turns a corner and as such may be shaped, angled, or otherwise aligned to direct the flow around the corner in order to enhance the efficiencies of the pump 212 even more.
In the configuration of
The placement of the DHHX 210 may be based at least partially on the size and space required for operation of the pump 212 and/or the PHX 214. As such, in this example, the DHHX 210 is adjacent to the PHX 214, while in other examples, (e.g.,
In alternative examples, the bypass 256 may initially be blocked by frozen fuel salt during normal operation. Initial decay heat can be absorbed by phase change (e.g., melting) of the frozen fuel salt and long-time decay heat removal can be through fuel salt flow through the bypass 256 and the DHHX 210.
Additionally, in this example, the configuration of the primary coolant loop 220 and the DRACS coolant loop 224 are similar to that depicted in
Additional outlet and inlet channels are not depicted, but may be circumferentially spaced and radiate from the substantially cylindrical central core 310 out towards outer walls of the vessel portion 304a. In examples, a total of four flow channels (each including an outlet channel 308 and an inlet channel 312) are utilized. In other examples, six, eight, or ten or more channels may be utilized, although odd numbers may also be utilized.
A number of reflectors form the various channels 308, 312 and the core 310 of the reactor 300. For example, a plurality of vertical reflectors 314 surrounds the core 310. Although the construction of such reflectors 314 may differ as required or desired for a particular application, the vertical reflectors 314 form an annulus to reflect energy back into the core 310. A lower reflector 316 is disposed below the core 310 and extends outwards towards the walls of the vessel 304 so as to at least partially form (along with the vertical reflectors 314) the inlet channels 312. Although a single lower reflector 316 is depicted, the reflector 316 may be made of more than a single component, arranged as required to form the desired channels 312. An upper reflector 318 is disposed above the reactor core 310 and, in examples, extends outward towards the walls of the vessel portion 304a. The vessel head 304b is disposed above the upper reflector 318. The core 310, defined by the reflectors, is disposed within the interior 306 a central core distance 332 above the bottom portion, and the central core distance 332 is less than the head distance 330.
In the example depicted in
In alternative examples, the openings 322 may initially be blocked and/or filled by frozen fuel salt during normal operation. Initial decay heat can be absorbed by phase change (e.g., melting) of the frozen fuel salt and long-time decay heat removal can be through fuel salt flow through the openings 322 and heat transfer through the DHHX 302.
Further components of the reactor 300 are depicted in
Relative positions of the various components within the vessel can also have an effect on performance of the DHHX 302. The vessel 304 containing the molten fuel salt includes a lower extent 350 characterized by the lowest location in the vessel in which molten fuel salt is present. This is, in most cases, the lowest point of the inlet channels 312. An upper extent 352 (that is, the highest location of the molten fuel salt) is generally located at the underside of the vessel head 304b. A geometric center plane 354 of the core, generally the location within the core 310 where the most heat is generated, is also depicted. The elevation 356 of the geometric center 354 is also depicted. Due to the flow direction 328 of the molten fuel salt through the core 310 and the position of the PHX 324, the fuel salt has a higher temperature as it is channeled through the outlet channels 308 than when it is channeled through the inlet channels 312. As such, the DHHX 302 is positioned above the elevation 356 of the geometric center 354 so as to increase the buoyant driving force and extract a greater amount of decay heat from the reactor 300.
By positioning the DHHX 302 within the higher temperature flow areas of the reactor 300, the efficiency of the DHHX 302 and the reactor 300 overall is increased. Additionally, by positioning the DHHX 302 above the geometric center 354 of the reactor 300, upon a reactor shutdown event (e.g., a planned reactor shutdown or an unplanned loss of forced flow in the fuel salt circuit) decay heat will rise within the reactor 300 and proximate to the DHHX 302 for a more efficient heat removal system.
In addition to those described above, further examples are disclosed in the following numbered clauses:
1. A molten chloride fast reactor (MCFR) comprising:
a plurality of reflectors defining a central core, wherein the central core includes a core geometric center;
a flow channel fluidically connected to the central core, wherein the flow channel includes an outlet flow channel downstream of the central core and an inlet flow channel upstream from the central core;
a primary heat exchanger (PHX) disposed outside the central core and between the outlet flow channel and the inlet flow channel; and
a decay heat heat exchanger (DHHX), wherein at least a portion of the DHHX is disposed above the core geometric center, and wherein a fuel salt is configured to circulate at least partially through the outlet flow channel, the DHHX, the PHX, the inlet flow channel, and the central core.
2. The MCFR of clause 1 or any clause that depends from clause 1, wherein the DHHX is disposed upstream from the PHX.
3. The MCFR of clause 1 or any clause that depends from clause 1, further comprising a pump for circulating the fuel salt, wherein the DHHX is disposed upstream from the pump.
4. The MCFR of clause 3 or any clause that depends from clause 3, wherein the pump is disposed upstream from the PHX.
5. The MCFR of clause 3 or any clause that depends from clause 3, wherein a flow direction of the fuel salt through the DHHX is different than a flow direction of the fuel salt through the pump.
6. The MCFR of clause 1 or any clause that depends from clause 1, further comprising a flow conditioner disposed at least partially in the outlet flow channel.
7. The MCFR of clause 6, wherein the DHHX includes the flow conditioner.
8. The MCFR of clause 1 or any clause that depends from clause 1, wherein the DHHX includes a shell and a plurality of tubes.
9. The MCFR of clause 8, wherein the plurality of tubes are disposed substantially parallel to the outlet flow channel.
10. The MCFR of clause 1 or any clause that depends from clause 1, further comprising a cooling circuit including the DHHX, wherein a coolant fluid is configured to circulate through the cooling circuit and remove heat from the fuel salt.
11. The MCFR of clause 10 or any clause that depends from clause 10, wherein the cooling circuit is devoid of a circulating pump.
12. The MCFR of clause 10 or any clause that depends from clause 10, wherein a flow of the coolant fluid through the DHHX is substantially orthogonal to a flow of the fuel salt through the DHHX.
13. The MCFR of clause 10 or any clause that depends from clause 10, wherein the cooling circuit is a first cooling circuit, and further comprising a second cooling circuit including the PHX, wherein the first cooling circuit is independent from the second cooling circuit.
14. A molten chloride fast reactor (MCFR) comprising:
a vessel including a plurality of structures disposed therein and defining at least one flow channel for circulating fuel salt within the vessel;
a core geometric center defined within the vessel; and
a decay heat heat exchanger (DHHX) disposed within the vessel and at least partially above the core geometric center.
15. The MCFR of clause 14 or any clause that depends from clause 10, wherein the DHHX is coupled in flow communication to at least one cooling circuit that removes heat from the fuel salt.
16. The MCFR of clause 14 or any clause that depends from clause 10, further comprising a primary heat exchanger (PHX) disposed within the vessel, wherein the DHHX is upstream of the PHX relative the circulation of fuel salt.
17. A direct reactor auxiliary cooling system (DRACS) for a molten chloride fast reactor (MCFR), the DRACS comprising:
a decay heat heat exchanger (DHHX) disposed within a MCFR reactor vessel and at least partially above a core geometric center, wherein the DHHX includes a shell and a plurality of tubes, and wherein the plurality of tubes receive a flow of fuel salt within the MCFR reactor vessel; and
a cooling circuit coupled in flow communication with the shell and configured to circulate a coolant fluid therein.
18. The DRACS of clause 17 or any clause that depends from clause 17, further comprising a second heat exchanger coupled in flow communication with the cooling circuit, wherein the second heat exchanger is positioned at a height that is greater than a height of the DHHX.
19. The DRACS of clause 18, wherein the second heat exchanger receives a flow of air to remove heat from the coolant fluid.
20. The DRACS of clause 17 or any clause that depends from clause 17, further comprising a flow conditioner.
21. A molten chloride fast reactor (MCFR) comprising:
a plurality of reflectors defining a central core, wherein the central core includes a core geometric center;
a flow channel fluidically connected to the central core, wherein the flow channel includes an outlet flow channel downstream of the central core and an inlet flow channel upstream from the central core;
a primary heat exchanger (PHX) disposed outside the central core and between the outlet flow channel and the inlet flow channel;
a pump for circulating a fuel salt through the outlet flow channel, the primary heat exchanger, the inlet flow channel, and the central core;
a decay heat heat exchanger (DHHX), wherein at least a portion of the DHHX is disposed above the core geometric center; and
a flow conditioner disposed in the outlet flow channel and upstream of the pump.
22. The MCFR of clause 21 or any clause that depends from clause 21, wherein the DHHX is disposed upstream from the PHX.
23. The MCFR of clause 21 or any clause that depends from clause 21, wherein the DHHX is disposed upstream from the pump.
24. The MCFR of clause 23, wherein the pump is disposed upstream from the PHX.
25. The MCFR of clause 21 or any clause that depends from clause 21, wherein the DHHX is the flow conditioner.
26. The MCFR of clause 21 or any clause that depends from clause 21, wherein the plurality of reflectors at least partially define the flow conditioner.
27. The MCFR of clause 21 or any clause that depends from clause 21, wherein the DHHX is disposed in the outlet flow channel, and wherein the outlet flow channel at least partially includes a DHHX bypass.
28. The MCFR of clause 21 or any clause that depends from clause 21, wherein the MCFR includes a reflector of the plurality of reflectors disposed proximate the outlet flow channel.
29. The MCFR of clause 28, wherein the DHHX is disposed within the reflector.
30. The MCFR of clause 21 or any clause that depends from clause 21, wherein the DHHX is disposed downstream of the pump.
31. The MCFR of clause 30 or any clause that depends from clause 30, wherein the DHHX is disposed upstream of the PHX.
32. The MCFR of clause 30 or any clause that depends from clause 30, wherein the DHHX is disposed adjacent the PHX, such that a volume of the fuel salt passes through only one of the DHHX and the PHX.
33. The MCFR of clause 31, wherein the DHHX is disposed so as to define a DHHX bypass.
34. The MCFR of clause 21 or any clause that depends from clause 21, wherein the PHX is disposed opposite at least one reflector of the plurality of reflectors from the central core.
35. The MCFR of clause 21 or any clause that depends from clause 21, further comprising a vessel and a plurality of structures disposed therein and defining the flow channel.
36. The MCFR of clause 35 or any clause that depends from clause 35, wherein the plurality of reflectors, the pump, the PHX, and the DHHX are disposed in the vessel.
37. The MCFR of clause 35 or any clause that depends from clause 35, wherein the vessel includes a bottom portion and a head disposed a head distance above the bottom portion.
38. The MCFR of clause 37, wherein the central core is disposed a central core distance above the bottom portion, wherein the central core distance is less than the head distance.
39. The MCFR of clause 38 or any clause that depends from clause 38, wherein the PHX is disposed a PHX distance above the bottom portion.
40. The MCFR of clause 39 or any clause that depends from clause 39, wherein the PHX distance is substantially equal to the central core distance.
41. The MCFR of clause 39 or any clause that depends from clause 39, wherein the PHX distance is greater than the central core distance.
42. The MCFR of clause 38 or any clause that depends from clause 38, wherein the DHHX is disposed a DHHX distance above the bottom portion.
43. The MCFR of clause 42 or any clause that depends from clause 42, wherein the DHHX distance is greater than the PHX distance.
44. The MCFR of clause 42 or any clause that depends from clause 42, wherein the DHHX distance is substantially equal to the PHX distance.
45. The MCFR of clause 21 or any clause that depends from clause 21, wherein a flow direction of the fuel salt through the DHHX is substantially similar to a flow direction of the fuel salt through the pump.
46. The MCFR of clause 45 or any clause that depends from clause 45, wherein the flow direction of the fuel salt through the DHHX is substantially vertical.
47. The MCFR of clause 45 or any clause that depends from clause 45, wherein the flow direction of the fuel salt through the DHHX is primarily horizontal.
48. The MCFR of clause 21 or any clause that depends from clause 21, wherein a flow direction of the fuel salt through the DHHX is different than a flow direction of the fuel salt through the pump.
It is to be understood that this disclosure is not limited to the particular structures, process steps, or materials disclosed herein, but is extended to equivalents thereof as would be recognized by those ordinarily skilled in the relevant arts. It should also be understood that terminology employed herein is used for the purpose of describing particular examples only and is not intended to be limiting. It must be noted that, as used in this specification, the singular forms “a,” “an,” and “the” include plural referents unless the context clearly dictates otherwise.
It will be clear that the systems and methods described herein are well adapted to attain the ends and advantages mentioned as well as those inherent therein. Those skilled in the art will recognize that the methods and systems within this specification may be implemented in many manners and as such is not to be limited by the foregoing exemplified examples and examples. In this regard, any number of the features of the different examples described herein may be combined into one single example and alternate examples having fewer than or more than all of the features herein described are possible.
While various examples have been described for purposes of this disclosure, various changes and modifications may be made which are well within the scope contemplated by the present disclosure. Numerous other changes may be made which will readily suggest themselves to those skilled in the art and which are encompassed in the spirit of the disclosure.
The present application claims the benefit of U.S. Provisional Patent Application No. 62/624,646, titled “DIRECT HEAT EXCHANGER FOR MOLTEN CHLORIDE FAST REACTOR,” filed Jan. 31, 2018, the entire disclosure of which is incorporated by reference herein.
This invention was made with government support under DE-NE0008473 awarded by The Department of Energy. The government has certain rights in the invention.
Number | Name | Date | Kind |
---|---|---|---|
2375009 | Lepsoe | May 1945 | A |
2874106 | Hammond et al. | Feb 1959 | A |
2920024 | Barton et al. | Jan 1960 | A |
2945794 | Winters et al. | Jul 1960 | A |
3018239 | Happell | Jan 1962 | A |
3029130 | Moore | Apr 1962 | A |
3046212 | Anderson | Jul 1962 | A |
3136700 | Poppendiek et al. | Jun 1964 | A |
3216901 | Teitel | Nov 1965 | A |
3218160 | Knighton et al. | Nov 1965 | A |
3262856 | Bettis | Jul 1966 | A |
3287225 | Ackroyd et al. | Nov 1966 | A |
3383285 | Ackroyd et al. | May 1968 | A |
3450198 | Brunner | Jun 1969 | A |
3785924 | Notari | Jan 1974 | A |
3909351 | Tilliette | Sep 1975 | A |
3996099 | Faugeras | Dec 1976 | A |
3997413 | Fougner | Dec 1976 | A |
4039377 | Andrieu | Aug 1977 | A |
4045286 | Blum | Aug 1977 | A |
4056435 | Carlier | Nov 1977 | A |
4216821 | Robin | Aug 1980 | A |
4342721 | Pomie | Aug 1982 | A |
4397778 | Lloyd | Aug 1983 | A |
4762667 | Sharbaugh | Aug 1988 | A |
5185120 | Fennern | Feb 1993 | A |
5196159 | Kawashima | Mar 1993 | A |
5223210 | Hunsbedt | Jun 1993 | A |
5380406 | Horton | Jan 1995 | A |
5421855 | Hayden | Jun 1995 | A |
6181759 | Heibel | Jan 2001 | B1 |
7217402 | Miller | May 2007 | B1 |
8416908 | Mann | Apr 2013 | B2 |
8594268 | Shu | Nov 2013 | B2 |
8734738 | Herrmann | May 2014 | B1 |
9171646 | Moses et al. | Oct 2015 | B2 |
10043594 | Scott | Aug 2018 | B2 |
10438705 | Cheatham | Oct 2019 | B2 |
10497479 | Abbott et al. | Dec 2019 | B2 |
10734122 | Cisneros et al. | Aug 2020 | B2 |
20040114703 | Bolton | Jun 2004 | A1 |
20050220251 | Yokoyama | Oct 2005 | A1 |
20080310575 | Cinotti | Dec 2008 | A1 |
20110222642 | Gautier | Sep 2011 | A1 |
20110286563 | Moses | Nov 2011 | A1 |
20120051481 | Shu | Mar 2012 | A1 |
20120056125 | Raade | Mar 2012 | A1 |
20120183112 | Leblanc | Jul 2012 | A1 |
20120288048 | Mann | Nov 2012 | A1 |
20120314829 | Greene | Dec 2012 | A1 |
20130083878 | Massie | Apr 2013 | A1 |
20130180520 | Raade | Jul 2013 | A1 |
20130272470 | Whitten et al. | Oct 2013 | A1 |
20140166924 | Raade | Jun 2014 | A1 |
20140348287 | Huke et al. | Nov 2014 | A1 |
20150010875 | Raade | Jan 2015 | A1 |
20150117589 | Kamei | Jan 2015 | A1 |
20150036779 | Leblanc | Feb 2015 | A1 |
20150078504 | Woolley | Mar 2015 | A1 |
20150170766 | Singh et al. | Jun 2015 | A1 |
20150228363 | Dewan | Aug 2015 | A1 |
20150243376 | Wilson | Aug 2015 | A1 |
20150357056 | Shayer | Dec 2015 | A1 |
20160005497 | Scott | Jan 2016 | A1 |
20160189806 | Cheatham, III et al. | Jun 2016 | A1 |
20160189812 | Czerwinski | Jun 2016 | A1 |
20160189813 | Cisneros | Jun 2016 | A1 |
20160196885 | Singh | Jul 2016 | A1 |
20160217874 | Dewan | Jul 2016 | A1 |
20160260505 | Cadell et al. | Sep 2016 | A1 |
20160260509 | Kim et al. | Sep 2016 | A1 |
20170084355 | Scott | Mar 2017 | A1 |
20170092381 | Cisneros | Mar 2017 | A1 |
20170117065 | Scott | Apr 2017 | A1 |
20170213610 | Sumita et al. | Jul 2017 | A1 |
20170301413 | Cisneros | Oct 2017 | A1 |
20170301421 | Abbott | Oct 2017 | A1 |
20170316840 | Abbott | Nov 2017 | A1 |
20170316841 | Abbott et al. | Nov 2017 | A1 |
20180019025 | Abbott | Jan 2018 | A1 |
20180047467 | Czerwinski | Feb 2018 | A1 |
20180068750 | Cisneros | Mar 2018 | A1 |
20180137944 | Abbott | May 2018 | A1 |
20180277260 | Marcille et al. | Sep 2018 | A1 |
20190311816 | Sumita et al. | Oct 2019 | A1 |
20200027590 | Cisneros | Jan 2020 | A1 |
20200118698 | Cheatham | Apr 2020 | A1 |
20200122109 | Kruizenga | Apr 2020 | A1 |
20200185114 | Abbott | Jun 2020 | A1 |
Number | Date | Country |
---|---|---|
631890 | Nov 1961 | CA |
107112055 | Sep 2020 | CN |
1112791 | Aug 1961 | DE |
1439107 | Feb 1969 | DE |
0617430 | Sep 1994 | EP |
2296248 | Jul 1976 | FR |
739968 | Nov 1955 | GB |
835266 | May 1960 | GB |
964841 | Jul 1964 | GB |
2073938 | Oct 1981 | GB |
2508537 | Dec 2014 | GB |
S57 1991 | Jan 1982 | JP |
1991282397 | Dec 1991 | JP |
2001-133572 | May 2001 | JP |
2014-119429 | Jun 2014 | JP |
2014534413 | Dec 2014 | JP |
2015510588 | Apr 2015 | JP |
57040 | Sep 2006 | RU |
2424587 | Jul 2011 | RU |
WO 2013116942 | Aug 2013 | WO |
WO 20140128457 | Aug 2014 | WO |
2014196338 | Dec 2014 | WO |
WO 2013180029 | May 2015 | WO |
WO 2014074930 | May 2015 | WO |
WO 2015140495 | Sep 2015 | WO |
WO 2016109565 | Jul 2016 | WO |
2018013317 | Jan 2018 | WO |
Entry |
---|
PCT International Preliminary Report on Patentability in International Application PCT/US2019/015967, dated Aug. 13, 2020, 16 pages. |
PCT International Preliminary Report on Patentability in International Application PCT/US2019/021791, dated Sep. 24, 2020, 9 pages. |
International Search Report/Written Opinion of PCT/US2019/015967, dated Jun. 12, 2019, 25 pages. |
Clarno, K.T. et al., “Trade studies for the liquid-salt-cooled very high-temperature reactor: fiscal year 2006 progress report”, ORNL/TM-2006 140 (2007), 35 pgs. |
Kimura, “Neutron spectrum in small iron pile surrounded by lead reflector”, Journal of Nucear Science and Technology 15, No. 3 (1978): 183-191. |
PCT International Search Report and Written Opinion in International Application PCT/US2019/051345, dated Mar. 5, 2020, 15 pages. |
Wang, Jun-Wei et al., “Influence of MgC12content on corrosion behavior of GH1140 in molten naCl—MgC12as thermal storage medium”, Solar Energy Materials and Solar Cells, Elsevier Science Pub., Amsterdam, NL, vol. 179, Nov. 20, 2017, pp. 194-201. |
Holcomb, et al. “Fast Spectrum Molten Salt Reactor Options”, Jul. 2011, 46 pages. Available at: http://info.ornl.gov/sites/publications/files/Pub29596.pdf. |
Kramer et al., Fusion-Fission Blanket Options for the LIFE Engine, Fusion Science and Technology, vol. 60, pp. 72-77, Jul. 2011. |
Kramer et al., Parameter study of the LIFE engine nuclear design, Energy Conversion and Management, 51, pp. 1744-1750, 2010. |
PCT International Search Report and Written Opinion in International Application PCT/US2016/055001, dated Jan. 25, 2017, 11 pages. |
Mourogov et al., Potentialities of the fast spectrum molten salt reactor concept: REBUS-3700, Energy Conversion and Management, Mar. 30, 2006, vol. 47, No. 17, pp. 2761-2771. |
PCT International Search Report and Written Opinion in International Application PCT/US2017/030666 dated Jul. 20, 2017, 11 pages. |
Abbott et al, Thermal and Mechanical Design Aspects of the LIFE Engine, Fusion Science and Technology Dec. 2008; 56(2), 7 pages. |
Harder, et al. “Compatibility and Processing Problems in the Use of Molten Uranium Chloride-Alkali Chloride Mixtures as Reactor Fuels”, UKAEA, Atomic Energy Research Establishment, Harwell, England, 1969, 28 pages. |
PCT International Preliminary Report on Patentability in International Application PCT/US2017/030666 dated Nov. 6, 2018, 9 pages. |
PCT International Preliminary Report on Patentability in International Application PCT/US2016/055001, dated Apr. 12, 2018, 9 pages. |
Donnelly et al., Fabrication of Heat Exchanger Tube Bundle for the Molten-Salt Reactor Experiment, ORNL-3500, Dec. 9, 1963, 42 pgs. |
PCT International Preliminary Report on Patentability in International Application PCT/US2017/030455, dated Nov. 6, 2018, 17 pages. |
PCT International Preliminary Report on Patentability in International Application PCT/US2017/030457, dated Nov. 15, 2018, 15 pages. |
PCT International Search Report and Written Opinion in International Application PCT/US2017/030455, dated Jan. 30, 2018, 23 pages. |
PCT International Search Report and Written Opinion in International Application PCT/US2017/030457, dated Jan. 23, 2018, 20 pages. |
Andreades et al., Technical Description of the Mark 1 Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant, Department of Nuclear Engineering, University of California, Berkeley (Sep. 30, 2014), 153 pages. |
ASTM International, Designation: B898-11, Standard Specification for Reactive and Refractory Metal Clad Plate (Sep. 2011), 15 pages. |
Cohen et al., “Vanadium-Lined HT9 Cladding Tubes”, Argonne National Lab ANL/ET/CP-80384, (Feb. 1994), 12 pgs. |
European Extended Search Report for EP 15876187.4 dated Sep. 11, 2018, 10 pages. |
Forsberg et al., Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Commercial Basis and Commercialization Strategy, MIT Center for Advanced Nuclear Energy Systems, MIT-ANP-TR-153, Dec. 2014, 148 pgs. |
Forsberg et al., Fluoride-Salt-Cooled High-Temperature Reactor (FHR) for Power and Process Heat, Final Project Report, MIT-ANP-TR-157, Dec. 2014, 62 pgs. |
Forsberg et al., Fluoride-Salt-Cooled High-Temperature Reactor (FHR): Goals, Options, Ownership, Requirements, Design, Licensing, and Support Facilities, MIT Center for Advanced Nuclear Energy Systems, MIT-ANP-TR-154, Dec. 2014, 217 pgs. |
Forsberg, Appendix D: Test Reactor Workshop Conclusions, NEUP Integrated Research Project Workshop 6: Fluoride Salt-Cooled High Temperature Reactor (FHR) Test Reactor Goals; Designs, and Strategies, Oct. 2-3, 2014, 11 pages. |
Freeman et al., “Archimedes Plasma Mass Filter”, AIP Cont. Proc. 694, 403 (2003), 9 pages. |
Gen IV International Forum, Molten Salt Reactor (MSR), https://www.gen-4.org/gif/jcms/c_9359/msr, accessed Feb. 26, 2016, 3 pgs. |
Grimes, W.R., “Molten-Salt Reactor Chemistry” Nucl. Appl. Technol. 8(137) (1970), 19 pgs. |
Harder, B.R., Long, G., and Stanaway, W.P., “Compatibility and Processing Problems in the Use of Molten Uranium Chloride-Alkali Chloride Mixtures as Reactor Fuels,” Symposium on Reprocessing of Nuclear Fuels, Iowa State University, 405-432, Aug. 1969. |
Merle-Lucotte, E., Introduction to the Physics of the Molten Salt Fast Reactor, Thorium Energy Conference 2013 (ThEC13), 2013, 82 pgs. |
MSR-FUJI General Information, Technical Features, and Operating Characteristics., pp. 1-30. |
Ottewitte, E. H., Cursory First Look at the Molten Chloride Fast Reactor as an Alternative to the Conventional BATR Concept, 1992, 75 pgs. |
PCT International Search Report and Written Opinion in International Application No. PCT/US2017/030672, dated Sep. 27, 2017, 9 pages. |
PCT International Search Report and Written Opinion in International Application PCT/US2015/067905 dated Aug. 5, 2016, 18 pages. |
PCT International Search Report and Written Opinion in International Application PCT/US2015/067923, dated Apr. 19, 2016, 10 pages. |
Reactor Start-up Procedure. Technical University Dresden. Reactor Training Course. pp. 3-4. <https://tu-dresden.de/ing/maschinenwesen/iet/wket/ressourcen/dateien/akr2/Lehrrnaterialien/start_e.pdf?lang=en>. (Mar. 2015), 21 pgs. |
Scott, Ian and Durham John, The Simple Molten Salt Reactor, Practical, safe and cheap, Moltex Energy LLP presentation slides, 19 pgs. |
Scott, Ian, Safer, cheaper nuclear: The simple molten salt reactor (Dec. 2, 2014), http://www.ee.co.za/article/safer-cheaper-nuclear-simple-molten-salt-reactor.hlml, 10 pgs. |
Taube, et al., Molten Plutonium Chlorides Fast Breeder Reactor Cooled by Molten Uranium Chloride, Annals of Nuclear Science and Engineering, vol. 1, pp. 277-281., 1974. |
Thoma, R. E., “Chemical Aspects of MSRE Operations,” ORNL-4658, Dec. 1971, 151 pages. |
TransAtomic Power Technical White Paper, Mar. 2014, V1 .0.1., (2014), http://www.transatomicpower.com/, 34 pgs. |
Van't Eind, R.J.S., Simulation of a Fast Molten Salt Reactor, PSR-131-2011-009, Jul. 2011, 68 pages. |
Xu et al., Thorium Energy R&D in China, THEO13, CERN, Oct. 28, 2013, 59 pgs. |
Molten Salt Reactor (MSR) Review: Feasibility Study of developing a pilot scale molten salt reactor in the UK, Jul. 2015, Energy Process Development, LTD., www.energyprocessdevelopments.com, 75 pgs. |
Ottewitte, E. H., “Configuration of a Molten Chloride Fast Reactor on a Thorium Fuel Cycle to Current Nuclear Fuel Cycle Concerns,” Ph.D. dissertation, University of California at Los Angeles, 1982, 310 pgs. |
PCT International Search Report and Written Opinion in International Application PCT/US2017/061843, dated Oct. 29, 2018, 23 pages. |
PCT International Preliminary Report on Patentability in International Application PCT/US2017/061843, dated May 21, 2019, 13 pages. |
PCT International Search Report and Written Opinion in International Application PCT/US2017/038806, dated Oct. 16, 2017, 13 pgs. |
PCT International Preliminary Report on Patentability in International Application PCT/US2017/038806, dated Jan. 15, 2019, 7 pgs. |
Maltsev et al., “Redox potentials of uranium in molten eutectic mixture of lithium, potassium, and cesium chlorides”, Russian Metallurgy, Maiknauka-Interperidica, RU, vol. 2016, No. 8, Dec. 2016, 2 pgs. |
Kuznetsov et al., “Electrochemical Behavior and Some Thermodynamic Properties of UC1 [sub 4] and UC1 [sub 3] Dissolved in a LiC1—KC1 Eutectic Melt”, Journal of the Electrochemical Society, vol. 152, No. 4, Jan. 2005, 11 pgs. |
PCT International Search Report and Written Opinion in International Application PCT/US2017/046139, dated Jan. 17, 2018, 16 pages. |
PCT International Preliminary Report on Patentability in International Application PCT/US2017/046139, dated Feb. 12, 2019, 8 pages. |
PCT International Search Report and Written Opinion in International Application PCT/US2019/021791, dated Nov. 19, 2019, 15 pages. |
Harder, B.R., Long, G., and Stanaway, W.P., “Compatibility and Processing Problems in the Use of Molten Uranium Chloride-Alkali Chloride Mixtures as Reactor Fuels,” Symposium on Reprocessing of Nuclear Fuels, Iowa State University, 405-432, 28 pages, Aug. 1969. |
Rouch et al, Preliminary thermal-hydraulic core design of the Molten Salt Fast Reactor (MSFR), Annals of Nuclear Energy 64 (2014) 449-456. |
Yamaji et al., Experimental and numerical thermal-hydraulics investigation of a molten salt reactor concept core, Kerntechnik 82 (2017) 4. |
Yamaji et al., Experimental investigation of the MSFR molten salt reactor concept, Kerntechnik 79 (2014) 5, pp. 408-416. |
Yamaji et al., Experimental Modelling and Numerical Analysis of a Molten Salt Fast Reactor, PHYSOR 2014—The Role of Reactor Physics Toward a Sustainable Future, Kyoto, Japan, Sep. 28-Oct. 2, 2014. |
Yamaji et al., Thermal-hydraulic analyses and experimental modelling of MSFR, Annals of Nuclear Energy 64 (2014) 457-471. |
Number | Date | Country | |
---|---|---|---|
20190237205 A1 | Aug 2019 | US |
Number | Date | Country | |
---|---|---|---|
62624646 | Jan 2018 | US |