• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
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  • 优先权
    • 专利摘要:
    A system and a method for a commercial nuclear repository that turns heat and gamma radiation from spent nuclear fuel into a valuable revenue stream. Gamma radiation from the spent nuclear fuel of the repository may be used to irradiate and sterilize food and other substances. Gamma radiation may also be used to improve the properties of target substances. Additionally, heat decay from the spent nuclear fuel of the repository may be harnessed to heat materials or fluids. The heated fluids may be used, for instance, to produce steam that may make electricity. The heating of working fluids for use in processes, such as heated fluid streams for fermentation or industrial heating, may be transported out of the repository and co-mingled with other heat input, or other fluids.
    公开号:SE1350570A1
    申请号:SE1350570
    申请日:2013-05-08
    公开日:2013-11-12
    发明作者:Eric P Loewen；Jordan E Hagaman
    申请人:Ge Hitachi Nucl Energy America；
    IPC主号:
    专利说明:

    SYSTEM AND METHOD FOR A COMMERCIAL SPENT NUCLEAR FUEL REPOSITORY TURNING HEAT AND GAMMA RADIATION INTO VALUE BACKGROUND OF THE INVENTION Field of the Invention Example embodiments relate generally to a nuclear repository, and moreparticularly to a system and a method for turning heat and gamma radiation into value in a nuclear repository.
    Related Art Light Water reactors (LWRs) produce electricity using enriched uranium.Spent nuclear fuel (SNF), Which may include fission products, 235U, and 239P,is a radioactive by-product of a LWR. The conventional strategy for handlingLWR SNF is to store spent material on-site at LWRs for 10-2O years (in spentnuclear fuel pools) and eventually move the SNF to off-site, long-termgeologic repositories in order to protect the environment as Well as thepublic. Generally, geologic repositories are designed to stock-pile radioactiveWaste in rock deep underground (for instance, in Yucca Mountain inNevada). For instance, as shown in FIG. 1, spent nuclear fuel hasconventionally been stored in reinforced underground tunnels 2. The spentnuclear fuel may be moved into the tunnel 2 on a gantry crane rail 2. Thespent nuclear fuel may include pressurized Water reactor Waste packages 6,co-disposal Waste packages (With high-level Waste canisters and/ orDepartment of Energy spent nuclear fuel canisters) 8 and boiling Waterreactor Waste packages 10, for example. The spent nuclear fuel may becovered by a drip shield 12, to isolate the fuel from Water that may contact the Waste fuel and re-enter the environment through local Water tables.
    During the long-term storage of the spent Waste fuel, gamma radiation andradioactive heat continue to be emitted for extended periods of time (lastingthousands of years). Therefore, by storing the spent nuclear fuel in long-termstorage repositories, the economic value of gamma rays and decay heat is lost.
    SUMMARY OF INVENTION Example embodiments are used to turn a Waste liability (spent nuclear fuel)into a valuable revenue stream. Specifically, example embodiments provide asystem and a method for a commercial nuclear repository using heat andradiation from the spent nuclear fuel as inputs for commercial processes.Gamma radiation from the spent nuclear fuel may be used to irradiate andsterilize food and other substances. Gamma radiation may also be used toimprove the properties of other target substances (such as cross linkingpolymer compounds to make larger polymer chains). Heat decay from thespent nuclear fuel may be used to harness heat energy to heat materials orfluids. The heating of fluids may be used, for instance, to form steam thatmay produce electricity using an organic Rankine cycle. The heating ofWorking fluids may also be used in other processes, such as fermentation(e.g. bio fuels) or industrial heating. Heated fluids from the long-term storage repository may also be co-mingled With other heat input, or With other fluids.
    BRIEF DESCRIPTION OF THE DRAWINGSThe above and other features and advantages of example embodiments Willbecome more apparent by describing in detail, example embodiments With reference to the attached draWings. The accompanying draWings are intended to depict example embodiments and should not be interpreted tolimit the intended scope of the claims. The accompanying draWings are notto be considered as draWn to scale unless explicitly noted.
    FIG. 1 is a conventional geological repository for spent nuclear fuel; FIG. 2 is a side-view of a commercial nuclear repository configuration, inaccordance With an example embodiment; FIG. 3 is a rear-view of the commercial nuclear repository configuration ofFIG. 2, in accordance With an example embodiment; FIG. 4 is another commercial nuclear repository configuration, in accordanceWith an example embodiment; and FIG. 5 is a diagram of a Waste heat to electricity generator, in accordance With an example embodiment.
    DETAILED DESCRIPTION Detailed example embodiments are disclosed herein. However, specificstructural and functional details disclosed herein are merely representativefor purposes of describing example embodiments. Example embodimentsmay, however, be embodied in many alternate forms and should not be construed as limited to only the embodiments set forth herein.
    Accordingly, While example embodiments are capable of variousmodifications and alternative forms, embodiments thereof are shown by Wayof example in the draWings and Will herein be described in detail. It shouldbe understood, however, that there is no intent to limit exampleembodiments to the particular forms disclosed, but to the contrary, example embodiments are to cover all modifications, equivalents, and alternatives falling within the scope of example embodiments. Like numbers refer to like elements throughout the description of the figures.
    It Will be understood that, although the terms first, second, etc. may be usedherein to describe various elements, these elements should not be limited bythese terms. These terms are only used to distinguish one element fromanother. For example, a first element could be termed a second element,and, similarly, a second element could be termed a first element, withoutdeparting from the scope of example embodiments. As used herein, the term"and / or" includes any and all combinations of one or more of the associated listed items.
    It Will be understood that when an element is referred to as being"connected" or "coupled" to another element, it may be directly connected orcoupled to the other element or intervening elements may be present. Incontrast, when an element is referred to as being "directly connected" or"directly coupled" to another element, there are no intervening elementspresent. Other words used to describe the relationship between elementsshould be interpreted in a like fashion (e.g., "between" versus "directly between", "adjacent" versus "directly adjacent", etc.).
    The terminology used herein is for the purpose of describing particularembodiments only and is not intended to be limiting of exampleembodiments. As used herein, the singular forms "a", "an" and "the" areintended to include the plural forms as well, unless the context clearlyindicates otherwise. It will be further understood that the terms "comprises", "comprising,", "includes" and/ or "including", when used herein, specify the presence of stated features, integers, steps, operations, elements, and/ orcomponents, but do not preclude the presence or addition of one or moreother features, integers, steps, operations, elements, components, and/ or groups thereof.
    It should also be noted that in some alternative implementations, thefunctions/ acts noted may occur out of the order noted in the figures. Forexample, two figures shown in succession may in fact be executedsubstantially concurrently or may sometimes be executed in the reverse order, depending upon the functionality/ acts involved.
    FIG. 2 is a side-vieW of a commercial nuclear repository configuration 30, inaccordance With an example embodiment. The configuration may includespent nuclear fuel containers 14 that may be held by a support structure 16on a rail car 18. The support structure 16 may be made of a metallicmaterial such as stainless steel that Withstands heat and radiation emittedfrom the spent nuclear fuel 14. The support structure 16 may include semi-circular saddles 16a that support cylindrically-shaped spent nuclear fuelcontainers 14. The saddles 16a may also be formed into other shapes toindividually support spent nuclear fuel containers 14 that may be non- cylindrical.
    Fins 22 mounted on supports 22a may be located on or near the rail car 18to capture heat energf. Fins 22 may be made of metal (such as stainlesssteel) With a high heat of conductivity, to capture and magnify heat energyon and around the rail car 18. The fins 22 may be formed into flat, square or rectangular shapes. The fins 22 may also be formed into cubes, or other three-dimensional shapes. The fins 22 may include ribs 22b, or otherprotrusions 22c that extend from the fins 22, to increase the overall externalsurface area of each fin 22 (and thereby maximize heat that may be radiated from the fins 22).
    In order to easily move the rail car 18 into position in a repository, such asan underground geological repository, the rail car 18 may have wheels 18athat allow the car 18 to be transported on rails 20. Alternative to using rails20 and a rail car 18, a conveyor belt of other similar structure may be usedin order to support and transport the spent nuclear fuel canisters 14 in and out of the tunnel 2.
    The example embodiment shown in FIG. 2, as well as the other embodimentsdescribed herein, may make use of a constant decay heat input (andconstant gamma radiation, as described in additional embodiments, below)for approximately 10 years without requiring new radioactive material to beadded to the repository. Furthermore, the repositories may be continuouslyoperated for about 30 years, with only about a 50% reduction in poweroutput during that time. During the commercial operating life of apermanent repository, the spent nuclear fuel may be supplemented, orreplaced, with new spent nuclear fuel (as needed) to optimize the repository output.
    FIG. 3 is a rear-view of the commercial nuclear repository configuration 30 ofFIG. 2, in accordance with an example embodiment. The repositoryconfiguration 30 may be located in a reinforced tunnel 2 that may be made of rock 3. The tunnel 2 may be, for instance, an underground tunnel 2.
    Alternatively, the repository 30 may be located in treatment tanks, or in other infrastructure that may be in a remote location.
    The tunnel (known as a drift) 2 may include fluid piping 15. The fluid pipe15 may include a flowing fluid, such as a liquid (for instance, water) or a gas.The pipe 15 may pass through the tunnel 2 and near rail car 18 to capturelow grade heat that is emitted by both the spent nuclear fuel canisters 14themselves, as well as the fins 22. The heated fluid piping 15 may betransported out of the repository 30 and used in commercial processes. Forinstance, the fluid piping 15 may be used as an input for processes requiringlow grade heat, such as fermentation (e.g., to produce bio-fuels). The fluidpiping 15 may also be used for industrial heating, such as a business thatmay wish to reduce their operating costs with an inexpensive form of heat.The fluid piping 15 may be co-mingled with other fluids, in order to heatthose fluids. Alternatively, the fluid piping 15 may be used as an input to aheat exchanger that may heat other fluids. Furthermore, the fluid piping 15 may be used to produce electricity, as described herein in more detail.
    It should be understood that the heat extracted by the repository 30 (both asa volumetric rate, and as a temperature) is a function of the following: thecoolant (fluid in piping 15) properties, coolant flow (temperature of the fluidis inversely proportional to flow), age of the spent nuclear fuel (the greaterthe age, the less heat output), the matrix (physical configuration) of thespent nuclear fuel and fluid piping 15 locations, and the density andcomposition of the spent nuclear fuel. Therefore, the heat extracted by thefluid piping 15 (as a function of a volumetric rate of heat removal, or as a function of temperature of the coolant in the piping 15) may be controlled by: changing the coolant used in piping 15, changing a flow-rate of thecoolant, tracking the age of the spent nuclear fuel, adjusting the locations ofthe spent nuclear fuel in proximity to the fluid piping 15, adjusting theoverall amount of spent nuclear fuel canisters 14 in the drift 2, and trackingthe composition (types of f1ssion products) of the spent nuclear fuel includedin the spent nuclear fuel canisters 14. For a general understanding of therepository 30 capabilities, if the fluid in piping 15 Were to be Water, a Welldesigned drift 2 may create fluid output temperatures in a range of 212 to482 °F (100 to °250 C). Drifts 2 may be placed in parallel or in series Withother drifts 2, to optimize volumetric flow or temperature ranges for the fluidpiping 15, as needed. A flow meter 15a and a temperature gauge 15b may beincluded Within the fluid piping 15, in order to control the volumetric heatremoval and/ or control the temperature of the coolant exiting the fluidpiping 15 as it exits the drift 2. A temperature gauge 15b may also be placedin the drift 2 and near the spent nuclear fuel canisters 14 in order to further control the heating of the fluid piping 15.
    FIG. 4 is another commercial nuclear repository configuration 32, inaccordance With an example embodiment. The configuration may also belocated in an underground tunnel 2 of rock 3 (or in another remote,protected location). The configuration 32 may include a rail car 18 WithWheels 18a on a track 20 that support a target material 24. This allows thetarget material 24 to be easily moved in and out of the tunnel 2 With aminimal amount of radiation exposure to repository personnel. Alternative tousing rails 20 and a rail car 18, a conveyor belt of other similar structuremay be used in order to support and transport the target material 24 in and out of the tunnel 2.
    Spent nuclear fuel canisters 14 may also be located in the tunnel 2. Thespent nuclear fuel canisters 14 may emit gamma radiation that may be usedto sterilize, or otherwise affect a physical property of the target material 24.Such sterilization may be used, for instance, to kill bacteria or assist in thepreservation of food products, medical instruments, or other suchsterilization needs. Gamma radiation from the spent nuclear fuel canisters14 may also be used to change the chemical structure of the target material24. For instance, gamma radiation may be used to cross link polymers in order to make larger polymers to produce consumer products.
    A radiation monitor 26 may be placed near the target 24, providing operatingpersonnel With a means of remotely monitoring the amount of radiationexposure the target 24 is receiving. The radiation monitor 26 may beattached to the target, itself, in order to accurately measure the entire amount of radiation the target 24 receives While in the tunnel 2.
    It should be understood that the maximum gamma field of the tunnel (drift)2 may be determined by the mass of fission products in the spent nuclearfuel 14, and the amount of shielding in the tunnel 2. Generally, over 700fission products are present in typical spent nuclear fuel 14 derived from aLWR. Each of the fission products has different decay constants,concentrations, and gamma energies. To leverage the fission products tocreate an effective gamma irradiation drift 2, it is best to locate the spentnuclear fuel 14 around a periphery of the drift 2, such that a target material 24 may be surrounded by the spent nuclear fuel 14. Using such a configuration, the target 24 may also be easily moved in and out of the drift2.
    It should be understood that the example embodiment of FIG. 4 (similar tothe embodiment of FIG. 2) may provide a permanent and/ or long-termstorage of spent nuclear fuel, While effectively irradiating target materials fordecades. The repository may have a commercial operating life of about 60years (or longer), and during that period the spent nuclear fuel may besupplemented, or replaced, With new spent nuclear fuel (as needed) tooptimize the repository output. It should also be understood that the gammaradiation produced by the repository 32 is a function of the following: the ageof the spent nuclear fuel (the greater the age, the less heat output), the type(and consistency of fission products) of spent nuclear fuel, the matrix(physical configuration) of the spent nuclear fuel in relation to the position ofthe target, the amount of shielding in the drift, and the density of the spentnuclear fuel. Therefore, the gamma radiation exposure absorbed by a targetmaterial 24 may be controlled by: tracking the age of the spent nuclear fuelin the spent nuclear fuel canisters 14, tracking the composition (types offission products) of the spent nuclear fuel in the spent nuclear fuel canisters14, adjusting the locations of the spent nuclear fuel canisters 14 in relationto the target material 24, adjusting the shielding Within the drift, andadjusting the overall mass of the spent nuclear fuel canisters 14 located in the drift 2.
    FIG. 5 is a diagram of a Waste heat to electricity generator configuration 34,in accordance With an example embodiment. The configuration 34 mayinclude a heat exchanger 40 that exchanges heat between heated piping 15 (of FIG. 3) and a high pressure liquid 58. The heat exchanger 40 may ll produce heated and pressurized vapor 42 that may be sent to an integratedpower module 44 to produce electrical energy 46. Low pressure vapor 48from the power module 44 may be sent to an evaporative condenser 50 witha recirculation pump 52 (and recirculation line 52a), to condense the vapor48. Condensed liquid 54 may be pressurized with pump 56 to provide acomplete electricity generator configuration 34. Other known configurationsmaking use of heated piping 15 as an input to a Rankine cycle to produce electricity may also be used.
    Example embodiments having thus been described, it will be obvious thatthe same may be varied in many ways. Such variations are not to beregarded as a departure from the intended spirit and scope of exampleembodiments, and all such modif1cations as would be obvious to one skilledin the art are intended to be included within the scope of the following claims.
    权利要求:
    Claims (24)
    [1] 1. A method of storing spent nuclear fuel, comprising:arranging spent nuclear fuel canisters in a drift,placing a target material in the drift,controlling an exposure of the target material to the spentnuclear fuel canisters, to heat and/ or irradiate the target material, removing the target material from the drift.
    [2] 2. The method of claim 1, further comprising: placing fluid piping in the drift, running coolant through the fluid piping, the coolant being thetarget material, the controlling of the exposure of the target material including controlling the heating of the coolant.
    [3] 3. The method of claim 2, further comprising: positioning fins around the spent nuclear fuel canisters.
    [4] 4. The method of claim 2, Wherein the fins are made of metal.
    [5] 5. The method of claim 4, Wherein the fins include one of ribs or protrusions on the fins.
    [6] 6. The method of claim 3, further comprising: 13 providing a flow meter and a temperature gauge on the fluidpiping,positioning another temperature gauge near the spent nuclear fuel canisters in the drift.
    [7] 7. The method of claim 6, Wherein the controlling of the heating ofthe coolant includes adjusting at least one of an identity of thecoolant, a floW-rate of the coolant, a proximity of the spent nuclearfuel canisters relative to the fluid piping, an overall quantity of spentnuclear fuel canisters, and a composition of spent nuclear fuel in the spent nuclear fuel canisters.
    [8] 8. The method of claim 2, further comprising:supporting the spent nuclear fuel canisters on saddles locatedon rail cars, moving the spent nuclear fuel canisters into the drift via rails.
    [9] 9. The method of claim 6, further comprising:connecting the fluid piping to a commercial process, to provide the heated coolant as an input to the commercial process.
    [10] 10. The method of claim 6, Wherein the coolant is Water, the methodfurther comprising:connecting the fluid piping to a Waste heat electricity generator, producing electricity using the heated coolant. 14
    [11] 11. The method of claim 1, Wherein the arranging of the spentnuclear fuel canisters in the drift includes arranging the spent nuclear fuel canisters around the target material.
    [12] 12. The method of claim 11, further comprising: placing a radiation monitor on the target material, the controlling of the exposure of the target material includingcontrolling a gamma radiation exposure of the target material in order to change a physical property of the target material.
    [13] 13. The method of claim 11, further comprising:supporting the target material on rail cars, moving the target material into the drift via rails.
    [14] 14. The method of claim 12, Wherein the controlling of the radiationexposure of the target material includes adjusting at least one of acomposition of spent nuclear fuel in the spent nuclear fuel canisters, alocation of the spent nuclear fuel canisters in relation to the targetmaterial, a shielding Within the drift, and an overall quantity of spent nuclear fuel canisters.
    [15] 15. A system for storing spent nuclear fuel, comprising:spent nuclear fuel canisters arranged in a drift, fins being located around the spent nuclear fuel canisters, fluid piping running through the drift, the fluid piping being configured to provide a floW of coolant through the piping.
    [16] 16. The system of claim 15, Wherein the fins are made of metal.
    [17] 17. The system of claim 15, Wherein the fins include one of ribs or protrusions on the fins.
    [18] 18. The system of claim 15, further comprising:a floW meter and a temperature gauge on the fluid piping,another temperature gauge near the spent nuclear fuel canisters in the drift.
    [19] 19. The system of claim 15, further comprising: rail cars With saddles, the saddles being configured to supportthe spent nuclear fuel canisters, rails running through the drift, the rails being configured to allow the rail cars to move in and out of the drift.
    [20] 20. The system of claim 15, further comprising:a commercial process located near the drift,an outlet pipe connecting the fluid piping to the commercial process.
    [21] 21. The system of claim 20, Wherein, 16 the coolant is Water,the commercial process is a Waste heat electricity generator configured to produce electricity.
    [22] 22. A system for storing spent nuclear fuel, comprising:a target material located in a drift, spent nuclear fuel canisters around the target material in the drift.
    [23] 23. The system of claim 22, further comprising:rail cars supporting the target material,rails running through the drift, the rails being configured to allow the rail cars to move in and out of the drift.
    [24] 24. The system of claim 23, further comprising: a radiation monitor on the target material.
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    同族专利:
    公开号 | 公开日
    DE102013104555B4|2022-03-03|
    SE537419C2|2015-04-21|
    DE102013104555A1|2013-11-14|
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    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    US3007859A|1956-08-15|1961-11-07|Phillips Petroleum Co|Atomic reactor|
    US2943986A|1957-09-16|1960-07-05|Shell Oil Co|Operation of radiation emitting apparatus|
    US3297537A|1958-05-05|1967-01-10|Richfield Oil Corp|Crude petroleum transmission system|
    US3716099A|1969-11-17|1973-02-13|Sanders Nuclear Corp|Means and method for obtaining high temperature process fluids from low temperature energy sources|
    US3828197A|1973-04-17|1974-08-06|Atomic Energy Commission|Radioactive waste storage|
    US3866424A|1974-05-03|1975-02-18|Atomic Energy Commission|Heat source containing radioactive nuclear waste|
    US3911684A|1974-08-29|1975-10-14|Us Energy|Method for utilizing decay heat from radioactive nuclear wastes|
    US4040480A|1976-04-15|1977-08-09|Atlantic Richfield Company|Storage of radioactive material|
    FR2388380B1|1977-04-22|1980-01-18|Messier Sa|
    DE2929467C2|1979-07-20|1985-04-25|Kraftwerk Union AG, 4330 Mülheim|Storage building for spent nuclear reactor fuel elements|
    US4464330A|1982-05-13|1984-08-07|The United States Of America As Represented By The Department Of Energy|Apparatus for irradiating a continuously flowing stream of fluid|
    US4749541A|1986-12-05|1988-06-07|Westinghouse Electric Corp.|Position sensing mechanism for a nuclear fuel transfer system|
    US5512253A|1991-11-04|1996-04-30|Woodbridge; Thomas C.|Irradiator apparatus|
    US5406600A|1993-10-08|1995-04-11|Pacific Nuclear Systems, Inc.|Transportation and storage cask for spent nuclear fuels|
    GB2295484A|1994-11-17|1996-05-29|William Robert Burton|Improvements in or relating to disposal of waste|
    US5771265A|1996-12-19|1998-06-23|Montazer; Parviz|Method and apparatus for generating electrical energy from nuclear waste while enhancing safety|
    FR2791805B1|1999-03-30|2001-08-03|Commissariat Energie Atomique|EXTREMELY LONG-TERM STORAGE FACILITY OF HEAT PRODUCTS SUCH AS NUCLEAR WASTE|
    US6183243B1|1999-08-23|2001-02-06|Stuart Snyder|Method of using nuclear waste to produce heat and power|
    US20030179844A1|2001-10-05|2003-09-25|Claudio Filippone|High-density power source utilizing decay heat and method thereof|
    JP4850536B2|2006-02-27|2012-01-11|日立Ｇｅニュークリア・エナジー株式会社|Natural circulation reactor power control device and natural circulation reactor power control method|
    KR100733700B1|2006-05-29|2007-06-28|한국원자력연구원|Irradiation device for testing materials using gamma ray from spent nuclear fuel assembly|
    JP4966214B2|2008-01-21|2012-07-04|東京電力株式会社|Spent fuel heat recovery system|
    US20100105975A1|2008-10-12|2010-04-29|James Russell Baird|Nuclear Assisted Hydrocarbon Production Method|
    CA2738804A1|2008-10-13|2010-04-22|Shell Internationale Research Maatschappij B.V.|Circulated heated transfer fluid heating of subsurface hydrocarbon formations|
    US9001958B2|2010-04-21|2015-04-07|Holtec International, Inc.|System and method for reclaiming energy from heat emanating from spent nuclear fuel|
    US9937273B2|2012-11-06|2018-04-10|Russell Goff|Method of managing spent nuclear fuel to irradiate products|US9937273B2|2012-11-06|2018-04-10|Russell Goff|Method of managing spent nuclear fuel to irradiate products|
    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    US13/469,846|US10210961B2|2012-05-11|2012-05-11|System and method for a commercial spent nuclear fuel repository turning heat and gamma radiation into value|
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