EP4352752A1 - Système de stockage souterrain à haute densité pour combustible nucléaire et déchets radioactifs - Google Patents

Système de stockage souterrain à haute densité pour combustible nucléaire et déchets radioactifs

Info

Publication number
EP4352752A1
EP4352752A1 EP22805349.2A EP22805349A EP4352752A1 EP 4352752 A1 EP4352752 A1 EP 4352752A1 EP 22805349 A EP22805349 A EP 22805349A EP 4352752 A1 EP4352752 A1 EP 4352752A1
Authority
EP
European Patent Office
Prior art keywords
cask
cavity
air
enclosure container
canister
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
EP22805349.2A
Other languages
German (de)
English (en)
Inventor
Krishna P. Singh
Stephen J. Agace
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Holtec International Inc
Original Assignee
Holtec International Inc
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Holtec International Inc filed Critical Holtec International Inc
Publication of EP4352752A1 publication Critical patent/EP4352752A1/fr
Pending legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/06—Details of, or accessories to, the containers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/06—Details of, or accessories to, the containers
    • G21F5/10—Heat-removal systems, e.g. using circulating fluid or cooling fins
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to spent nuclear fuel and radioactive waste storage systems, and more particularly to such a system suitable for consolidated interim waste storage.
  • Used or spent nuclear fuel and radioactive waste materials are presently stored on an interim basis “on site” at commissioned and some decommissioned nuclear generating plants until the federal government provides a central permanent repository.
  • spent nuclear fuel SNF
  • the fuel can be transferred after a period of cooling in the pool to nuclear waste canisters which are placed in thick-walled outer vessels such as dry storage modules or casks typically constructed of concrete, steel, and iron, etc. to provide containment and radiation shielding.
  • the casks are stored on site at the generating plant.
  • the concept of using consolidated interim storage is intended to provide geographically distributed off-site storage facilities for spent nuclear fuel and other high level nuclear radioactive wastes gathered from a number of individual generating plant sites, thereby providing greater control over the widely dispersed waste stockpiles.
  • the waste materials are stored in sealed nuclear waste canisters such as a multi-purpose canister (MPC) available from Holtec International Inc. of Camden, New Jersey.
  • MPC multi-purpose canister
  • the canister generally includes an elongated cylindrical stainless steel shell, baseplate, and lid hermetically seal welded to the shell to form the confinement boundary for the stored fuel assemblies disposed in the canister.
  • a fuel basket arranged inside the canister has a rectilinear honeycomb construction defining a plurality of open prismatic cells which each hold a nuclear fuel assembly.
  • the fuel assembly comprises a plurality of nuclear fuel rods or “cladding” which contains the uranium fuel pellets that continue to emit considerable decay heat after removal from the nuclear reactor.
  • the nuclear waste canisters may be initially transported to the CIS facility from the generating plants for a period of time, with the eventual goal of a final move to a permanent nuclear waste repository when available from the government.
  • Such so called independent spent fuel storage installations are facilities designed for the interim storage of spent nuclear fuel comprising solid, reactor-related, greater than Class C waste, in addition to other related radioactive materials.
  • Each ISFSI facility would typically maintain an inventory of a multitude of waste canisters containing spent nuclear fuel and/or radioactive waste materials.
  • Some ISFSIs comprise multiple storage modules which store nuclear waste below ground/grade and are ventilated by natural ambient cooling air.
  • the modules may be fluidly coupled to the source of available ambient cooling air and/or each other in a manner which may deprive certain modules of the ventilation air required for optimal cooling of the radioactive waste in each module.
  • the present disclosure in one aspect provides an underground naturally ventilated and passively cooled radioactive nuclear waste storage system designed for below ground/grade storage of fuel.
  • the system comprises a plurality of modules such as CECs (cavity enclosure containers) which may be arrayed in an upright position on a subterranean concrete base pad situated below the storage site’s final cleared grade of topsoil and/or engineered fill.
  • CECs cavity enclosure containers
  • a majority of the height of the underground CECs is therefore preferably located below grade created a low profile for protection against potential intentional or unintentional projectile impacts.
  • the CECs in the array may be arranged in a single-file linear pattern spaced apart manner thereby forming nuclear waste storage row extending horizontally along a common longitudinal axis in in one embodiment.
  • Multiple parallel linear rows of CECs may be provided in a CIS facility which may form an ISFSI facility.
  • each CEC defines an internal cavity having a height and diametrically configured in cross-sectional area for holding a single cylindrical spent nuclear fuel (SNF) canister.
  • the canister holds the SNF assemblies and/or other high level radioactive waste materials as previously described herein which continue to emit considerable amounts of heat that require dissipation in order to protect the structural integrity of fuel assemblies or other waste material.
  • multiple canisters may be vertically stacked one above each other in a single CEC such as disclosed in commonly owned U.S. Patent 9,852,822, which is incorporated herein by reference.
  • the CECs may be diametrically configured in cross- sectional area to hold a single canister at a single elevation in both the upper and lower positions within the CEC.
  • the CECs and canisters inside are cooled using a passive ambient air ventilation system unassisted by fans or blowers in preferred but non- limiting embodiments to circulate cooling air through the CECs.
  • Heat emitted by the canister fluidly drives a convective natural thermo-siphon effect to draw ambient air through the CECs cavity in the annulus between the CEC and canister as the air inside the annulus is heated by the canister.
  • fans/blowers may be provided if necessary, but are less preferred since the interruption of electrical power to the CIS site may interfere with the ability to adequately cool the CECs and radioactive nuclear fuel and/or other waste material housed therein.
  • each CEC includes a minimum of two air inlets. Two air inlets are provided in one embodiment. The air inlets are fluidly coupled via laterally and horizontally extending flow conduits directly to at least one direct source of cooling air (i.e. there are no intervening CECs in the air flow pathway defined by the flow conduits between the cooling air source and air inlets of the CEC). Further, each CEC is not fluidly coupled in a direct manner via the flow conduits to any other CEC (i.e. shell-to-shell).
  • the cooling air source in some implementations may be one or more vertically- elongated and tubular/hollow ambient cooling air feeder shells.
  • the air feeder shells may have a smaller outer diameter than the CECs, thereby allowing the CECs to be spaced as closely as possible to conserve available nuclear waste storage space at the CIS facility within each row of CECs.
  • the air feeder shells are each in fluid communication with ambient atmosphere at top and operable to draw cooling air downwards into the shell via the natural convective thermo-siphon effect driven by the heat emitted from nuclear waste canister within the CEC.
  • the air flows to and enters the CEC via the flow conduits, is heated by the radioactive waste in the canister, and then is exhausted back to atmosphere through the top of the CEC which may be located above grade to define an air outlet.
  • the pair of air inlets of the CEC may each be fluidly coupled directly to a single discrete and separate cooling air feeder shell via the flow conduits.
  • the CEC is fluidly coupled directly to a pair of air feeder shells via flow conduits.
  • a high airflow capacity system is provided in which each CEC is fluidly coupled to two pairs (i.e. four) cooling air feeder shells.
  • each air inlet of the CEC is fluidly coupled directly to an air feeder shell via a separate dedicated single flow conduit rather than a shared branch or header type flow conduit arrangement as in some past approaches which may prevent each CEC from receiving the required volume/flow rate of cooling air in some situations.
  • the provision of at least two separate air inlets for each CEC and direct fluid coupling to one or more feeder shells advantageously improves the ability of the natural ventilation system to adequately cool each CEC to the necessary degree in order to protect the structural integrity of the SNF assemblies and/or other high level nuclear waste stored inside the canisters in the CEC. Because the ambient cooling air flowing to each CEC from one or two cooling air feeder shells does not first pass through any upstream intervening CECs such as employed in some prior systems, the flow rate of ambient cooling air supplied directly to the CEC for naturally ventilating its interior space or cavity and cooling the SNF canister is therefore not diminished.
  • no CEC in one row may be fluidly coupled to any other CECs or cooling air feeder shells in another adjacent row either directly or indirectly (i.e. via an intervening CEC or flow conduits). This prevents fluidic interaction between CECs in adjoining rows which could result in possible pressure and flow imbalances, thereby causing disproportionate cooling of some CECs versus others as previously described herein.
  • the collective array of CECs according to the present disclosure may form part of an independent spent fuel storage installation (ISFSI) facility suitable for a CIS system that may include any suitable number of CECs desired.
  • the CECs may be part of a CIS system such as HI-STORM UMAX (Holtec International Storage Module Underground Maximum Safety) which is an underground Vertical Ventilated Module (VVM) dry spent fuel storage system engineered to be fully compatible with all presently certified multi-purpose canisters (MPCs).
  • VVM Underground Vertical Ventilated Module
  • Each HI-STORM UMAX Vertical Ventilated Module provides storage of an MPC in the vertical configuration inside a cylindrical cavity located entirely below the top-of-grade of the ISFSI.
  • the VVM akin to the aboveground overpack, is comprised of the CECs; each of which includes a removable top closure lid according to the present disclosure.
  • the nuclear waste canisters usable in the present CECs which may contain both radioactive used or spent nuclear fuel (SNF) and/or non-fuel radioactive waste materials, may be stainless steel multi-purpose canisters (MPCs) available from Holtec International of Camden, New Jersey. Other canisters may be used.
  • MPCs multi-purpose canisters
  • the present underground nuclear waste storage system is intended to provide vanishingly low site boundary radiation dose levels and safety during catastrophic events.
  • the system takes advantage of the surrounding soil/engineered fill or subgrade to provide radiation shielding, physical protection, and a low center of gravity for a stable storage installation.
  • an underground passively ventilated nuclear waste storage system comprises: a horizontal longitudinal axis; a subterranean concrete base pad; a vertically elongated first cavity enclosure container located on the base pad and the longitudinal axis, the cavity enclosure container defining a vertical centerline axis and comprising a first air inlet, a second air inlet, an air outlet, and an internal cavity; the cavity of the first cavity enclosure container being configured for holding a nuclear waste canister which contains radioactive nuclear waste emitting heat; a vertically elongated first cooling air feeder shell in fluid communication with an ambient atmosphere and operable to draw in ambient air, the first cooling air feeder shell being fluidly coupled directly to the first air inlet of the first cavity enclosure container via a first flow conduit; a vertically elongated second cooling air feeder shell in fluid communication with the ambient atmosphere and operable to draw in ambient air, the second cooling air feeder shell being fluidly coupled directly to the second air inlet of the first cavity enclosure container via a second flow conduit.
  • an underground passively ventilated nuclear waste storage system comprises: a horizontal longitudinal axis; a subterranean concrete base pad; a vertically elongated first cavity enclosure container located on the base pad and the longitudinal axis; a vertically elongated second cavity enclosure container located on the base pad and the longitudinal axis, the second cavity enclosure container being spaced apart from the first cavity enclosure container; the first and second cavity enclosure containers each defining a vertical centerline axis and comprising a first air inlet, a second air inlet, an air outlet, and an internal cavity; a nuclear waste canister positioned in each of the internal cavities of the first and second cavity enclosure containers, the canister emitting heat; a vertically elongated cooling air feeder shell arranged on the longitudinal axis between the first and second cavity enclosure containers, the cooling air feeder shell being in fluid communication with an ambient atmosphere and operable to draw in ambient air; the cooling air feeder shell fluidly coupled directly to the first air inlet of the first cavity enclosure container via a first
  • a consolidated interim storage facility for nuclear waste comprises: a plurality of elongated cavity enclosure containers each founded on a subterranean base pad and extending vertically upwards therefrom to a concrete top pad; an engineered fill disposed between the base and top pads; the cavity enclosure containers being arranged in an array comprising a plurality of longitudinally-extending and parallel linear rows of cavity enclosure containers, each row defining a longitudinal axis and the cavity enclosure containers each being arranged on the longitudinal axis; a plurality of vertically elongated cooling air feeder shells disposed in each row on the respective longitudinal axis, one cooling air feeder shell being interposed between and fluidly coupled directly to a pair of the cavity enclosure containers on opposite sides of the cooling air feeder shell, the cooling air feeder shells each being in fluid communication with an ambient atmosphere; the one cooling air feeder shell being operable to draw in ambient air and distribute the air to directly to each pair of cavity enclosure containers; wherein the cavity enclosure containers in each row are fluidly isolated from the cavity enclosure containers in
  • an underground passively ventilated nuclear waste storage apparatus for a consolidated interim storage facility, the apparatus comprising: a vertically elongated cavity enclosure container supported on a subterranean base pad and extending vertically upwards therefrom to a concrete top pad; an engineered fill disposed between the base and top pads; a nuclear waste canister positioned in an internal cavity of the cavity enclosure containers, the canister emitting decay heat which heats air in an annulus formed between the cavity enclosure container and the canister; a vertically elongated hollow cooling air feeder shell arranged on a lateral side of the cavity enclosure container, the cooling air feeder shell being in fluid communication with an ambient atmosphere and operable to draw in ambient air; the cooling air feeder shell fluidly coupled directly to a lower portion of the cavity by a first air inlet of the cavity enclosure container via a first flow conduit; the cooling air intake shell further fluidly coupled directly to the lower portion of the cavity by a second air inlet of the cavity enclosure container via a second flow conduit; the first and second flow
  • a stackable nuclear waste storage system may comprise a pair of vertically stacked nuclear waste storage vessels including a lower below grade module and an upper above grade module.
  • the below grade module may be a vertically elongated CEC (cavity enclosure containers) described above which is mounted on the subterranean concrete base pad of the ISFSI and situated below the storage site’s final cleared grade of topsoil and/or engineered fill.
  • the above grade module may be a vertically-elongated radiation- shielded cask positioned above the below grade CEC.
  • the CEC and cask may each have a cylindrical body in one embodiment.
  • the above grade cask may be coaxially aligned with a vertical centerline axis of the below grade CEC.
  • the cask may be fixedly and detachably mounted to the ISFSI top pad such as via bolting or other means.
  • the cask may be directly coupled to top of the CEC (e.g., bolted or otherwise) either instead of or in addition to mounting to the concrete top pad.
  • the CEC and cask each define an internal cavity configured for holding a single nuclear waste canister, such as a multi-purpose canister (MPC) available from Holtec International of Camden, New Jersey, or other dry storage canister.
  • MPC multi-purpose canister
  • Such canisters are known in the art and are unshielded from a radiation attenuation or blockage standpoint which instead is provided by the embedment of the below grade CEC in the concrete top pad and engineered fill for a first canister in the first case, and the above grade thick radiation- shielded cask for a second canister in the second case.
  • the cask may include a sidewall which comprises concrete that may contain hematite or another iron ore to increase conductive heat transfer through the cask sidewall to ambient atmosphere.
  • the internal cavities of the CEC and cask each have a height and transverse cross-sectional area configured to hold no more than a single nuclear waste fuel canister therein.
  • the internal cavities of the CEC and cask may be in direct fluid communication internally within the stacked modules such that heat cooling air from the lower CEC flows directly upwards into the upper cask via natural convective thermo-siphon flow.
  • the process and act of mounting the upper cask above the lower below grade CEC establishes fluid communication between the internal nuclear waste storage cavities of each module.
  • the lower CEC includes a solid metallic baseplate hermetically seal welded to its bottom end which effectively closes body from a fluidic standpoint, the bottom of the upper cask conversely is not fully closed.
  • a perforated support structure may be mounted inside the lower portion of the cask internal cavity which comprises a plurality axial through holes which fluidly interconnect the internal cavities of the CEC and cask.
  • the perforated support structure allows air from the cavity of the lower CEC heated by thermal energy emitted for the nuclear waste canister therein to flow upwards into the cavity of the upper cask.
  • At least the lower below grade CEC includes at least one ventilation or cooling air inlet configured to draw in ambient air for cooling the canisters inside both the CEC and upper cask.
  • the upper cask may include a plurality of air inlets to separately draw ambient air into its internal cavity independently of the air inlet of the lower CEC. This secondary ventilation or cooling air provides additional cooling capacity for the canister in the upper cask and is mixed with the already heated ventilation or cooling air rising upwards into the cavity of the cask from the CEC below.
  • the cooling air system for the below grade CEC may include a vertically elongated cooling air feeder shell in fluid communication with an ambient cooling air and the at least one air inlet of the CEC via a lateral/horizontal flow conduit.
  • the air feeder shell which extends below grade for a majority of its height is operable to draw in ambient cooling air downwards and horizontal into the internal cavity of the CEC.
  • the ventilation or cooling air system for the fluidly interconnected stacked CEC and cask assembly operates via natural convective thermo-siphon flow driven by the decay heat emitted from the canisters inside the casks emanating from the SNF (or other high level nuclear waste) stored in the canisters located inside the lower CEC and upper cask.
  • the cooling air system thus passively cools the nuclear waste without requiring the assistance of blowers or fans.
  • the heated ventilation air is returned to the ambient environment via the top closure lid on the upper cask, as further described herein.
  • the body of the lower CEC of the stackable nuclear waste storage system advantageously is located for a majority of its height below grade, handling and mounting the upper above grade cask over the CEC does not exceed the maximum lifting height limitations of conventional track-driven cask crawlers, thereby allowing use of such standard equipment for moving and mounting the upper cask to the concrete top pad.
  • a passively ventilated nuclear waste storage system comprises: a lower cavity enclosure container configured for mounting at least partially below grade, the cavity enclosure container comprising at least one first air inlet and a first internal cavity configured for holding a first canister which contains radioactive nuclear waste; and an upper cask comprising a second internal cavity configured for holding a second canister which contains radioactive nuclear waste, the cask being located above grade; at least one air outlet configured to allow heated air in a top portion of the second internal cavity to exit the second internal cavity of the cask; the cask stacked atop the lower cavity enclosure container in a vertically stacked arrangement so that a cask-to-cask interface is formed between the cavity enclosure container and the cask; wherein the first and second internal cavities are fluidly interconnected so that heated air in a top portion of the first internal cavity can flow into a bottom portion of the second internal cavity.
  • a method for forming a passively cooled nuclear waste system comprises: positioning a cavity enclosure container on a below above grade concrete base pad, the lower cavity enclosure container including a body comprising a first cavity; inserting a first canister containing nuclear waste emitting thermal energy in the first cavity of the lower cavity enclosure container; providing an upper cask on an above grade including a body comprising a second cavity; inserting a second canister containing nuclear waste emitting thermal energy in the second cavity of the upper cask; positioning the upper cask on an above grade concrete top pad atop of the lower cavity enclosure container in a vertically stacked arrangement, the second cavity being placed in fluid communication with the first cavity of the lower cavity enclosure container; and detachably coupling the upper cask to the top pad.
  • the method may further include drawing ambient cooling air into the first cavity of the lower cavity enclosure container through at least one air inlet in the lower cavity enclosure container.
  • the method may further include: detachably coupling a closure lid on a top end of the upper cask after inserting the second canister therein; heating the cooling air in the first cavity; flowing the heated cooling air upwards into the second cavity of the upper cask; drawing ambient cooling air into the second cavity of the upper cask through a plurality of second air inlet ducts; mixing the heated cooling air with the cooling air drawn into the second cavity of the upper cask; further heating the mixed cooling air in the second cavity; and discharging the further heated cooling air to ambient atmosphere via a closure lid detachably coupled to a top end of the upper cask.
  • the upper cask may comprise a perforated baseplate at bottom, and wherein the foregoing step of flowing the heated cooling air upwards into the second cavity of the upper cask comprises flowing the heated cooling air through the perforated baseplate in the upper cask.
  • the perforated baseplate comprises a plurality of axial through holes configured to prevent radiation streaming or shine to the ambient environment.
  • a method for adding storage capacity to an existing nuclear waste storage system comprises: positioning a lower cavity enclosure container on a below grade concrete base pad at a first point in time, the lower cavity enclosure container including a body comprising a first cavity and at least one air inlet in fluid communication with the first cavity and ambient atmosphere; inserting a first canister containing nuclear waste emitting thermal energy in the first cavity of the lower cavity enclosure container; detachably coupling a first closure lid on top of the lower cavity enclosure container, the first closure lid defining at least one air outlet duct in fluid communication with the second cavity of the lower cavity enclosure container; operating the lower cavity enclosure container for a period of time; removing the first closure lid from the lower cavity enclosure container at a second point in time later than the first point in time; positioning an upper cask on an above grade concrete top pad, the upper cask including a body comprising a second cavity and plurality of radial second air inlet ducts in fluid communication with the second cavity; inserting a second canister containing nuclear waste emitting
  • FIG. 1 is a perspective view of an ISFSI facility comprising a first embodiment of a nuclear waste storage system according to the present disclosure for consolidated interim storage of spent nuclear fuel and other high level radioactive nuclear waste materials;
  • FIG. 2 is a top plan view thereof;
  • FIG. 3 is a perspective view of one of the nuclear waste storage rows of the ISFSI facility of FIGS. 1 and 2;
  • FIG. 4 is a first cross sectional view of a second embodiment of a nuclear waste storage system showing a cavity enclosure container (CEC) and cooling air feeder shell thereof;
  • CEC cavity enclosure container
  • FIG. 5 is a second cross sectional view thereof of the CEC alone
  • FIG. 6 is a top plan view of an arrangement of multiple CECs of the second embodiment
  • FIG. 7 is a perspective view of one nuclear waste storage row according to the second embodiment.
  • FIG. 8 is a top perspective view of the first embodiment of a nuclear waste storage system of FIGS. 1-3 showing one of the modular nuclear waste storage units including a CEC; pair of directly fluidly coupled cooling air feeder shells all mounted on a common support plate;
  • FIG. 9 is a bottom perspective view thereof.
  • FIG. 10 is a first lateral side view thereof
  • FIG. 11 is a second lateral side view thereof
  • FIG. 12 is a front view thereof
  • FIG. 13 is a top view thereof with the top lid in place on the CEC;
  • FIG. 14 is a top view thereof with the top lid removed to show the internal cavity of the CEC;
  • FIG. 15 is a top view thereof with the top air intake housing removed from the pair of cooling air feeder shells to reveal the array of radiation attenuator plates therein;
  • FIG. 16 is a top perspective view thereof
  • FIG. 17 is a cross-sectional perspective view thereof showing the modular nuclear waste storage unit installed on a concrete base pad below grade, a concrete top pad, and engineered fill therebetween;
  • FIG. 18 is a cross-sectional side view thereof
  • FIG. 19 is a cross-sectional side view thereof showing multiple CECs and cooling air feeder shells; in part of the nuclear waste storage row of FIG. 3;
  • FIG. 20 is a top view of a third embodiment of a nuclear waste storage system according to the present disclosure showing a pair of CECs and cooling air feeder shells;
  • FIG. 21 is a side cross sectional view of a stackable nuclear waste storage system for storing high level nuclear radioactive waste material including the below grade lower CEC of FIGS. 4-5 and an above grade upper cask mounted over and atop the CEC;
  • FIG. 22 is a first perspective view thereof
  • FIG. 23 is a second perspective view thereof
  • FIG. 24 is a first side view thereof
  • FIG. 25 is a second side view thereof
  • FIG. 26 is a first top view of the storage system
  • FIG. 27 is a second top view of the storage system
  • FIG. 28 is a transverse cross sectional view through the lower CEC showing the air inlet ducts and air inlet of the CEC;
  • FIG. 29 is a first vertical cross sectional view of the storage system including the lower CEC and upper cask;
  • FIG. 30 is a second vertical cross sectional view thereof
  • FIG. 31 is a third vertical cross sectional view thereof.
  • FIG. 32 is a fourth vertical cross sectional view thereof.
  • FIG. 33 is a fifth vertical cross sectional view thereof.
  • FIG. 34 is a perspective view of a first embodiment of a central portion of a perforated baseplate of the upper cask;
  • FIG. 35 is a perspective view of a second embodiment of a central portion of the perforated baseplate showing the entire structure of the baseplate;
  • FIG. 36A is an enlarged partial transverse cross sectional view of storage system showing the cask-to-CEC interface area
  • FIG. 36B is a detail taken from FIG. 36A;
  • FIG. 37 is a partial transverse cross sectional view of the upper portion of the upper cask and cask lid;
  • FIG. 38 is a first perspective view of the CEC and cask assembly
  • FIG. 39 is a second perspective view thereof.
  • FIG. 40 is first side view thereof
  • FIG. 41 is a second side view thereof
  • FIG. 42 is a first exploded perspective view thereof
  • FIG. 43 is a second exploded perspective view thereof.
  • FIG. 44 is a transverse cross sectional view taken through the air inlet ducts of the upper cask.
  • All drawings are schematic and not necessarily to scale. Parts given a reference numerical designation in one figure may be considered to be the same parts where they appear in other figures without a numerical designation for brevity unless specifically labeled with a different part number and described herein. References herein to a whole figure number herein which may comprise multiple figures with the same whole number but different alphabetical suffixes shall be construed to be a general reference to all those figures sharing the same whole number, unless otherwise indicated.
  • any reference to direction or orientation is merely intended for convenience of description and is not intended in any way to limit the scope of the present invention.
  • Relative terms such as “lower,” “upper,” “horizontal,” “vertical,”, “above,” “below,” “up,” “down,” “top” and “bottom” as well as derivative thereof (e.g., “horizontally,” “downwardly,” “upwardly,” etc.) should be construed to refer to the orientation as then described or as shown in the drawing under discussion. These relative terms are for convenience of description only and do not require that the apparatus be constructed or operated in a particular orientation.
  • FIGS. 1 and 2 depict a top views of an ISFSI facility comprising a passively cooled subterranean consolidated interim storage (CIS) system 100 according to the present disclosure.
  • CIS passively cooled subterranean consolidated interim storage
  • System 100 comprises an array of underground vertical ventilated cavity enclosure containers (CECs) 110 each holding a single nuclear waste canister 150 containing the radioactive nuclear waste, and vertically elongated cooling air feeder shells 130 interspersed between and fluidly coupled to the CECs according to the present disclosure.
  • CECs underground vertical ventilated cavity enclosure containers
  • the CECs and air feeder shells are configured to form integral parts of an unpowered natural convective ventilation system which operates via the thermo-siphon effect to cool the nuclear waste fuel stored in each CEC, as further described herein.
  • FIGS. 4 and 5 depict one embodiment of a CEC 110 and cooling air feeder shell 110 of a nuclear waste storage system according to the present disclosure in greater detail.
  • the CECs 110 and cooling air feeder shells 130 are founded on and supported by a thick and horizontally extending subterranean bottom base pad 101 located below a cleared top surface or grade “G” of the native soil “S” at the CIS system site.
  • Base pad 101 may be made of reinforced concrete in one embodiment; however, in other embodiments other materials may be used such as compacted gravel so long a stable and firm base is provided to support the CECs and air feeder shells.
  • the CECs and air feeder shells may be rigidly anchored to the base pad via multiple anchor members 103 such as robust J-shaped fasteners (threaded or otherwise), or other suitable types of anchors commonly used for fastening structural objects to concrete.
  • base pad 101 has a suitable thickness and construction robust enough to withstand postulated seismic events and maintain safe support the CECs 110 and containment of their nuclear waste contents.
  • a horizontally and longitudinally extending concrete top pad 102 is formed on top of the engineered fill 140 described below which is placed after pouring base pad 101. Top pad 102 therefore protrudes upwards from and is raised above the cleared grade G of the surrounding native soil S.
  • the top pad is vertically spaced apart from the below grade base pad 101.
  • the top pad defines an upward facing top surface 102a elevated above grade to prevent the ingress of standing water from the surrounding native soil S into the CECs 110 originating from rain events.
  • Top surface 102a is substantially parallel to an upward facing top surface 101a of base pad 101 (the term “substantially” accounting for small variations in the level of surfaces 101a, 102a and recesses and/or contours formed therein for various purposes).
  • the top pad 102 preferably extends at least one CEC outer diameter beyond the peripheral CECs 110. A gradually sloping terrain of native soil S around the top pad is preferred to facilitate rainwater drainage away from the CECs.
  • the vertical gap or space formed between base and top pads 101, 102 including the open horizontal/lateral space between adjacent CECs 110 and cooling air feeder shells 130 is filled with a suitable “engineered fill” 104 to provide both lateral radiation shielding for the nuclear waste stored inside the CECs 110, and full lateral structural support to the CECs and the cooling air feeder shells 130.
  • a suitable engineered fill may be used, such as without limitation flowable CLSM (controlled low-strength material) which is a self-compacting cementitious fill material often used in the industry as a backfill in lieu of ordinary compacted soil fill.
  • Plain concrete may also be used as the inter-CEC and base pad to top pad gap filler material if it is desired to further increase the CIS system’s radiation dose blockage capabilities.
  • Other types of fill material which can provide radiation shielding and lateral support of the CECs and air feeder shells may be used.
  • each CEC 110 comprises a vertically elongated metallic shell body 111 defining a vertical centerline axis VC1 and which extends between a top end 112 and bottom end 113 of the body.
  • the upper portion 11 la of the shell body which defines top end 112 may be embedded in in concrete top pad 102 including between the top surface 102a and bottom surface 102b of the top pad 102 as shown.
  • the top end 112 of the CEC shell body 111 may terminate at the top surface 102a of the top pad.
  • body 111 of CEC 110 may be cylindrical with a circular transverse cross-sectional shape in preferred non-limiting embodiments; however, other non-poly gonal and polygonal shaped bodies may be used in certain other acceptable embodiments.
  • the shell body 111 of each CEC 110 defines a vertically extending internal cavity 120 extending between ends 112, 113 which is configured for holding a cylindrical nuclear waste canister 150.
  • the waste canister 150 defines an interior space which holds spent fuel assemblies and/or other high level radioactive waste from the nuclear reactor.
  • the nuclear waste canister 150 stored in CEC 110 includes a vertically-elongated hollow cylindrical shell 151, top closure plate 152, and bottom closure plate 153.
  • the top and bottom closure plates are hermetically seal welded to the top and bottom ends of shell 151 to form a gas-tight containment boundary for the nuclear waste stored in the canister.
  • Canister 150 i.e. shell and closure plates
  • Canister 150 may be formed of stainless steel in preferred embodiments for corrosion resistance.
  • Canister 150 has a height H3 smaller than the height H2 of the CEC shell body 111 such that the top of the canister is spaced vertically apart and downwards from the bottom of the concrete top pad 102 (see, e.g., FIG. 3).
  • Canister 150 may be any type of nuclear waste/SNF canister, including without limitation Multi-Purpose Canisters (MPCs) available from Holtec International of Camden, New Jersey.
  • MPCs Multi-Purpose Canisters
  • CEC 110 further includes a baseplate 114 hermetically seal welded to the bottom end
  • a plurality of metallic radial support lugs 124 are welded to baseplate
  • the support lugs 124 may be generally L-shaped having a horizontal portion 124a welded to baseplate 114 and an integral adjoining vertical portion 124b welded to the inner surface of the CEC shell body 111.
  • Vertical portions 124b each define radially-extending lower seismic restraint members which engage the sides of the canister 150 to keep it centered in the cavity 120 of the CEC 110 particularly during a seismic event (e.g., earthquake).
  • a plurality of radially-extending upper seismic restraint members 123b project inwards from the shell body 111 in cavity 120 to keep the upper portion of the canister 150 centered.
  • Restraint members 123b may be formed by circumferentially spaced apart metal plates or lugs welded to the inner surface of the CEC shell body 111.
  • a ventilation annulus 121 is formed therebetween which extends for the full height of the canister.
  • the ventilation annulus is fluid communication with the cooling air feeder shells 130 at the bottom via flow conduits 160 and an air outlet plenum 152 formed inside the CEC cavity 120 above the canister.
  • each CEC 110 may be formed of a suitable metal such as stainless steel for corrosion resistance.
  • lid 115 detachably mounted on top of the CEC shell body 111.
  • the lid may have a composite metal and concrete construction including an outer shell 115a formed of steel such as stainless steel, and interior concrete lining 115b. This robust construction not only provides radiation shielding, but also offers added protection against projectile impacts.
  • lid 115 includes a cylindrical circular upper portion 116a and adjoining cylindrical circular lower portion 116b having an outer diameter D4 smaller than an outer diameter D3 of the upper portion.
  • An annular stepped shoulder 116c is formed between the upper and lower portions of the lid. Diameters D3 and/or D4 in some embodiments may be larger than an outer diameter D2 of the CEC shell body 111.
  • Lower portion of 116b of lid 115 is insertably positioned inside a corresponding upwardly open circular recess 117 formed into the top surface 102a of the top pad 102 around the top end 112 of each CEC 110 as shown (see, e.g., FIGS. 4-5).
  • Recess 117 is larger in diameter D5 that the outer diameter D2 of the CEC shell body 111.
  • the upper portion 11 la of CEC 110 i.e. shell body 111
  • the lid is slightly elevated and ajar from top pad 102 in its recess to create an air outlet 118 thereby forming an exit pathway between the lid and CEC 110 for the rising ventilation air from the cavity 120 of the CEC to return to ambient atmosphere.
  • the air outlet 118 is configured to form a circuitous multi angled pathway such that there is no direct line of sight from cavity 120 to atmosphere for radiation to escape (i.e. radiation streaming).
  • Outlet 118 may have a double L-shaped configuration in one embodiment for this purpose as shown in FIG. 2; however other circuitous shaped pathways may be used.
  • the top section 111b of the CEC shell body 111 may further include a flat radially projecting annular seating flange 111c.
  • the seating flange is configured for engaging and resting on top surface 102a of the concrete top pad 102.
  • Each cooling air feeder shell 130 is a tubular hollow structure comprising a metallic vertically-elongated body 131 defining a vertical centerline axis VC2 and bottom closure plate 132 welded to the bottom end 134 of the shell.
  • the vertical centerlines VC2 and VC1 of the CECs 110 are parallel to each other.
  • the body 131 may be cylindrical with a circular transverse cross-sectional shape in preferred non-limiting embodiments; however, other non poly gonal and polygonal shaped bodies may be used in certain other acceptable embodiments.
  • the body 131 of each feeder shell defines an open vertical air passage 133 extending between the bottom end 134 and top end 135 of the shell 130 for drawing ambient cooling air downwards through the shell.
  • the top end of shell 130 may terminate at the top surface 102a of the concrete top pad 102 in some embodiments.
  • a perforated air intake housing 136 is coupled to the top end 135 of the shell 130 which projects vertically upwards from the top pad 102 as shown.
  • housing 136 may be formed of a cylindrical shell which is perforated to form a plurality of lateral openings extending 360 degrees circumferentially around for drawing air laterally into the feeder shell 130.
  • a circular cap 137 encloses the top of the air inlet housing 136 to prevent the ingress of rain.
  • the air feeder shell 130, bottom closure plate 132, air intake housing 136, and cap 137 may be formed of metal such as stainless steel for corrosion protection. Other shaped caps and intake housings may be used in other embodiments.
  • each feeder shell is preferably spaced apart from the shell bodies 101 of adjacent CECs by a sufficient lateral/horizontal distance such as at least one outer diameter D1 of feeder shell in some embodiments.
  • cooling air feeder shells 130 have a height HI which is at least coextensive as height H2 of CEC shell bodies 111.
  • H2 and HI may be about 227 inches (576.6 cm).
  • shells 130 may have a slightly greater height HI (measured between bottom and top ends 134, 135) than height H2 of the CEC shell bodies 111 (measured between bottom and top ends 113, 112 of the bodies in including upper portion 111a).
  • the canister 150 has a total height H3 (inclusive of the top and bottom closure plates 152, 153) less than height H2 of the CEC shell bodies 111 so that an air outlet plenum 154 is formed between the bottom of CEC lid 115 and the top closure plate 152 of the canister.
  • the top of the canister defined by top closure plate 152 terminates beneath the concrete top pad 102 of the CIS system at an elevation that may fall within the vertical extent of the engineered fill 140. This helps prevent “sky shine” radiation streaming to the ambient environment.
  • the cavity enclosure containers 110 and cooling air feeder shells 130 in one embodiment may be arranged in a tightly packed array to minimize spatial site requirements at the CIS facility.
  • the array comprises a plurality of longitudinally- extending and parallel linear nuclear waste storage rows R each including a plurality of CECs 110 and cooling air feeder shells 130.
  • the array in FIGS. 1-2 shows only five rows R; however, it is recognized that more or less rows of CECs and air feeder shells may of course be provided as needed.
  • Each row defines a respective horizontally-extending longitudinal axis LA.
  • each CEC which intersect their vertical centerline axes VC1 intersect the respective longitudinal axis LA in each row such that the CECs 110 may be considered to be located on the longitudinal axis.
  • a transverse axis TA may be defined as oriented perpendicularly to the longitudinal axis LA in each row extending front to back between rows R in the array (see, e.g., FIG. 2).
  • the nuclear waste storage rows R of CECs 110 are spaced apart and parallel to each other to form longitudinally-extending access aisles AI which provide access for commercially-available motorized wheeled or track driven lifting equipment such as without limitation cask crawlers or other equipment which transport, maneuver, and raise/lower the canisters 150 for insertion into and removal from the CECs 110.
  • the equipment may straddle the row of CECs 110 and the wheels or tracks run in aisles AI on each side of the row. Such equipment is well known to those skilled in the art without further elaboration.
  • the low exposed vertical profile of the CECs 110 allows the equipment to move over the CECs modules in a single row to the desired CEC for inserting or removing canisters.
  • FIGS. 4-7 show a possible first embodiment and arrangement of CECs 110 and cooling air feeder shells 130.
  • each CEC 110 in each row R is fluidly coupled directly to a pair of cooling air feeder shells 130 by horizontally/laterally extending flow conduits 160; one each of feeder shells 130 being on opposite lateral sides of the CECs along the longitudinal axis LA as shown.
  • each air feeder shell 130 may be considered centrally located between a pair of CECs.
  • Each CEC therefore comprises a pair of air inlets 125 on opposite sides forming openings which extend through the shell body 111 of the CEC 110 to the internal cavity 120.
  • the air inlets 125 are therefore formed in and through the lower portion 11 Id of the CECs (i.e. shell body 111) to introduce cooling air into the bottom of the CEC cavity 120 and ventilation annulus 121.
  • the air inlets 125 are each configured and arranged to introduce cooling ventilation air tangentially into the cavity 120 of each CEC 110 as shown. Introduction of cooling air in this tangential manner which flows circumferentially around the inner surface of the CEC to quickly fill the CEC cavity and ventilation advantageously results in less pressure drop than introducing the air radially and perpendicularly at the canister shell 151.
  • the flow conduits 160 comprise sections of horizontally-extending metal piping spanning between the cooling air feeder shells 130 and their respective CECs 110.
  • the flow conduits fluidly couple each CEC air inlet 125 “directly” to a respective air feeder shell 130 meaning that the cooling air passes from the feeder shell to the respective CEC without passing through any other CEC or feeder shell on the way.
  • this arrangement advantageously maximizes the amount of cooing air received by each CEC 110 commensurate with the level of heat emitted by the canisters in each CEC which may differ. Accordingly, no CEC is starved of its required cooling air flow by any upstream CEC.
  • each CEC 110 receives the needed amount of cooling air based on its particular heat load generated by the nuclear waste canister 150 therein, it further bears noting that there is no interconnecting flow conduits between any CECs or cooling air feeder shells 130 in one row and any other rows R. Accordingly, each nuclear waste storage row R is fluidly isolated from every other row.
  • each CEC 110 in a single row R is fluidly isolated from adjacent CECs and every other CEC in the same row when the ambient air cooling ventilation system is in operation (i.e. nuclear waste canisters 150 disposed in the CECs thereby creating active air flow through the ventilation system via the thermo-siphon effect previously described herein).
  • ambient cooling air will be drawn downwards in the centrally located air feeder shell 130 and then flow laterally outwards to each of the two CECs 110 pictured via flow conduits 160 (see directional air flow arrows).
  • the cool air enters the bottoms of the CECs and flows vertically upwards as the air in the CEC cavities 120 is heated by the canisters 150 (see, e.g., FIG. 2). Accordingly, given the direction of flow through these nuclear waste storage system components, air cannot possibly flow from one CEC 110 backwards through the centrally located air feeder shell 130 and into the remaining CEC.
  • the CECs are therefore effectively fluidly isolated from each other.
  • the flow conduits 160 may comprise sections of metal piping such as stainless steel of suitable diameter.
  • the flow conduits are configured such that there is no straight line of sight between each cooling air feeder shell 130 and either of its respective pair of cavity enclosure containers 110 fluidly coupled thereto to prevent radiation streaming. This concomitantly also ensures there is no straight line of sight between any of the CECs 110 in the row R through the feeder shells 130.
  • flow conduits 160 may each comprise an angled transverse section 162 oriented transversely to the longitudinal axis LA, and an adjoining longitudinal section 161 oriented parallel to the longitudinal axis.
  • a welded mitered joint 163 may be formed between the transverse and longitudinal sections (see, e.g., FIG. 6). An oblique angle is formed between these two sections of the flow conduit.
  • curved piping elbows may be used instead of mitered sections of straight piping to prevent the straight line of sight.
  • each cooling air feeder shell 130 need only be sized in diameter to supply cooling air to a pair of CECs 110, the diameter of the feeder shells can be minimized to allow CECs in each row to be closely spaced. This advantageously allows more CECs and nuclear waste to be packed into each row R.
  • the outer diameter D1 of the feeder shells 130 may be smaller than the outer diameter D2 of the CECs 110.
  • D1 may be about 30 inches (76.2 cm) and D2 may be about 84 inches (213.4 cm).
  • the flow conduits 60 may have a smaller diameter than D1 or D2; such as for example without limitation about 24 inches (61 cm) in one embodiment. Other diametrical sizes may be used in other embodiments and does not limit the invention.
  • nuclear waste canisters 150 containing radioactive waste materials are loaded into the CECs 110.
  • the lids 115 are then placed onto the CECs to enclose the CECs and their internal cavities.
  • each CEC 110 creates a negative pressure which draws ambient air down into the cooling air feeder shell 130 via the known thermo-siphon effect or mechanism.
  • the CEC draws the air from the bottom of the air feeder shell into the lower portion of its internal cavity 120 and ventilation annulus 121 through the flow conduits 160 to complete the ventilation air flow circuit. It bears noting that this natural air flow is unassisted by powered fans or blowers, thereby avoiding operating costs associated with electric power consumption, but importantly ensuring continued cooling of the CECs 110 in the event of power disruption to prevent overheating the CECs and protect the containment of the nuclear waste materials.
  • FIG. 20 depicts an alternative second embodiment and arrangement of a nuclear waste storage system and corresponding air ventilation system.
  • each CEC 110 is fluidly coupled to only a single cooling air feeder shell 130 by a pair of angled/curved flow conduits 160 to prevent radiation streaming as previously described herein.
  • the CEC includes two air inlets 125 also arranged to introduce ventilation air tangentially into the internal cavity of the CEC.
  • the bifurcated ventilation air supply effectively creates a curtain of cooling air around the nuclear waste canister 150 inside the CEC with minimal flow resistance to maximize the air flow for cooling the radioactive waste material.
  • This alternative embodiment may be appropriate where certain canisters 150 are still emitting extremely high levels of thermal energy (heat) which must be dissipated in order to protect the structural integrity of the canister and nuclear waste therein.
  • Multiple pairs of the fluidly isolated CECs 110 and cooling air feeder shells 130 in FIG. 20 may be arranged in a row R of the CIS facility.
  • the CECs 110 and air feeder shells 130 are arranged on the longitudinal axis LA of each row R that may be provided in the array of CECs.
  • certain CIS facilities may combine some rows of CECs 110 and air feeder shells 130 according to the arrangement shown in FIG. 20 for high thermal energy emitting nuclear waste canisters, and some other rows of CECs and air feeder shells according to the arrangement shown in FIGS. 4-7 for lower thermal energy emitting nuclear waste canisters.
  • the two different arrangements of CECs and air feeder shells may be mixed in a single row R. Accordingly, numerous variations are possible depending on particular nuclear waste material storage needs and level of thermal energy emitted by the canisters 150.
  • FIGS. 1-3 and 8-19 depict yet another third alternative embodiment and arrangement of a nuclear waste storage system and corresponding air ventilation system.
  • the cooling air requirements of these high heat load CECs may exceed even the higher airflow capacity provided by the CECs in FIG. 20 with a dedicated separate pair of cooling air feeder shells 130 as shown.
  • CECs 110 in this high airflow capacity third embodiment may each be fluidly coupled to two pairs (i.e. four) cooling air feeder shells 130 by air flow conduits 160 (see, e.g., FIGS. 1-3 and 14).
  • air flow conduits 160 see, e.g., FIGS. 1-3 and 14.
  • one pair of feeder shells 130 may be located on one lateral side of the CEC, and the remaining pair of feeder shells may be located on the opposite other lateral side as shown.
  • the CEC includes four air inlets 125; each of which is fluidly coupled by a flow conduit 160 to one of the four cooling air feeder shells 130.
  • the flow conduits 160 may be similarly configured and arranged to the prior embodiments of the ambient air ventilation system previously described herein to introduce ventilation air tangentially into the lower/bottom portion of internal cavity 120 of the CEC 110 in order to achieve the same airflow benefits noted above.
  • each CEC 110 in a single row R need not necessarily be coupled to four cooling air feeder shells 130 as seen in FIGS. 1-3.
  • one CEC 110 located at one end of row R is shown fluidly coupled to only a pair of cooling air feeder shells 130 as this CEC may not have a heat load as high as the heat loads of the remaining other CECs in the depicted row which require a higher ambient ventilation air flow volume or rate (e.g. CFM -cubic feet per minute) to dissipate the higher heat emissions from the canisters 150 stored therein.
  • the present passively cooled nuclear waste storage and ventilation system offers considerable flexibility in configuration which can be customized in order to accommodate the particular heat load dissipation needs of the CECs which may differ.
  • the construction and structural details of the CECs 110 in this third embodiment and arrangement of passively- cooled nuclear waste storage system may be similar to the previously described embodiments with exception of the additional cooling air inlets 125 to accommodate the two pairs of cooling air feeder shells 130.
  • the description of the CEC structure including lid 115 will therefore not be repeated here for sake of brevity.
  • the features or parts of the CEC in the presently illustrated third embodiment of the nuclear waste storage system are therefore numbered the same as in the figures for the first and second embodiments.
  • the modular unit 200 is a self-supported and transportable assemblage or structure which includes a common or shared support plate 202 formed of a suitably strong and appropriate metallic material (e.g., stainless steel or other).
  • the support plate 202 has a horizontally broadened and flat body 201 configured for mounting and anchoring onto the top surface of the subterranean concrete base pad 101 such as via anchors 103 which may be threaded fasteners or other type anchoring/mounting devices.
  • the support plate 202 may have any suitable configuration, such as a U-shaped mixed polygonal-non-polygonal configuration in one non-limiting embodiment as shown.
  • a plurality of horizontally-extending cross-support members 204 e.g., structural beams of suitable shape
  • the CEC 110 in each modular nuclear waste storage unit 200 is structurally tied and laterally braced to each of the pair of cooling air feeder shells 130 by a plurality of vertically spaced apart cross-support members 204.
  • three cross-support members are shown to tie each of the lower portion 11 Id, middle portion 11 le, and upper portion 11 la of the CEC to each of the two feeder shells 130. More or less cross-support members 204 may be used.
  • the pair of cooling air feeder shells 130 are similarly structurally tied together and laterally braced by vertically spaced apart cross-support members 204 which may be of the same type or different than the cross-support structural members tying the CEC 110 to each of the cooling air feeder shells 130.
  • a W-beam may be used for cross-support structural members 204; however, other suitable type/shape structural members may be used.
  • the modular nuclear waste storage unit 200 advantageously allows the units to be fabricated under controlled shop conditions in the fabrication facility, and then shipped to the installation site (e.g., Consolidated Interim Storage facility). Since the CEC 110 and pair of cooling air feeder shells 130 are already palletized so to speak on the common support plate 201, installation requires only making the piping connections with the flow conduits 160 at the installation site. This results in rapid installation and deployment of the modular nuclear waste storage units.
  • the installation process or method includes pouring the concrete base pad 101 and then positioning and mounting a first storage unit 200 on the pad when cured and hardened.
  • a second storage unit 200 is next positioned and mounted on the base pad adjacent to the first storage unit in a longitudinally spaced apart manner along the row R.
  • the piping connections can now be made for the first storage unit.
  • Each of the four cooling air feeder shells 130 are then fluidly coupled directly to the CEC 110 of the first storage unit by a separate flow conduit 160.
  • the piping connections between the CEC and feeder shells 160 may be welded or preferably bolted piping flange type connections which can be made more expediently than welded connections. Since the air flowing inside the flow conduits 160 is at most at air a slight negative (sub-atmospheric) pressure when the ventilation system is in operation, flanged type connections are suitable for these service conditions.
  • the next additional third, fourth, so on nuclear waste storage units 200 may then be added and installed in a similar manner.
  • the flowable engineered fill 140 may be installed on top of the base pad and around the CECs and feeders shells of the CIS facility to fill the voids between this equipment for lateral support and radiation attenuation/blocking as shown in FIGS. 17-19 (note engineered fill not shown in FIG. 3 for clarity).
  • the concrete top pad 102 may be formed on top of the engineered fill.
  • the modular nuclear waste storage units 200 are now ready for receiving a nuclear waste canister 150 in each cavity 120.
  • a pair of canisters 150 may be vertically stacked in each CEC 110 and supported therein in the manner described. It bears noting that the CEC 110 whether holding a single or two vertically stacked canisters 150 has a cross-sectional area sufficient for holding only a single canister at a single elevation (i.e. no side-by-side canister placement).
  • the foregoing CECs 110 of the multiple modular nuclear waste storage units 200 are preferably positioned on the longitudinal axis LA of the storage row R (i.e. vertical centerline axis VC1 intersects longitudinal axis LA).
  • the first and second cooling air feeder shells 130 of the first pair of feeder shells may be transversely spaced apart perpendicularly to and on opposite sides of longitudinal axis LA).
  • the first and second feeder shells are located on a first lateral side of a first CEC 110.
  • the third and fourth cooling air feeder shells of the second pair of feeder shells may similarly be transversely spaced apart in the same manner and located on a second lateral side of the first CEC 110 opposite the first lateral side.
  • the first, second, third, and fourth cooling air feeder shells 130 are preferably fluidly coupled directly to the first CECs by separate metallic flow conduits 160 as shown in FIG. 3 (see also variously FIGS. 8-19). Accordingly, there are no intervening CECs or cooling air shells.
  • Flow conduits 160 may be formed by sections of piping as previously described herein.
  • the flow conduits 160 may each comprise a horizontally-extending straight piping section fluidly coupling a lower portion of the cavity 120 of the first CEC 110 to a lower portion of each of the cooling air feeder shells 130.
  • Each straight piping section flow conduit 160 defines a horizontal centerline axis He which is acutely angled to longitudinal axis LA by angle A1 (see, e.g., FIG. 14). This angled arrangement of the cooling air feeder shells 130 to the longitudinal axis is sufficient to ensure there is no straight line of sight between the first CEC 110 and the next adjacent CEC which is mounted on a different support plate 201.
  • angle A1 may be between about and including 10 to 20 degrees.
  • the cooling air feeder shells 130 in each pair on opposite lateral sides of the depicted CEC 110 are on opposite sides of longitudinal axis LA.
  • the geometric vertical centerline VC2 of each of the feeder shells falls on a horizontal reference line R1 which is oriented at an acute angle A2 to the longitudinal axis LA of the nuclear waste storage row R.
  • Angle A2 may be about 30 degrees (+/- 5 degrees) in one embodiment as illustrated. It bears noting that the angular arrangement of the flow conduits 160 and cooling air feeder shells 130 to the longitudinal axis LA by angles A1 and A2 respectively advantageously contributes to allow closer spacing between the CECs 110 and feeder shells in each row. This allows more CECs to be tightly packed into each row R.
  • each cooling air feeder shell 130 in some embodiments may include an array 170 of vertically elongated radiation attenuator plates 171.
  • the plates 171 may be flat, and are structurally coupled together (e.g. welded, via clips/brackets, etc.) and arranged in an orthogonal grid as shown. Plates 171 are disposed in the vertical air passage 133 of the cooling air feeder shells 130 and create vertically-extending grid openings between them through which the ventilation air is drawn downwards through the shells. Attenuator plates 171 may extend vertically for a majority of the HI the cooling air feeder shells.
  • the attenuator plates extend vertically from top end 135 of the shells downwards towards bottom end 134 and terminate at a point just above and proximate to the top of the flow conduits 160 so as to not interfere with the ventilation air flow from the shells 130 to the CECs 110.
  • attenuator plates 171 may be formed of steel; however, other suitable materials including boron-containing materials and metals may be used. The attenuator plates 171 advantageously help prevent radiation streaming to the ambient environment surrounding the nuclear waste storage system.
  • the ambient cooling air ventilation system of the present high airflow capacity embodiment shown in FIGS. 1-3 and 8-19 functions and follows the same general path as the previously described embodiments.
  • the air inlets 125 are each configured and arranged to introduce cooling ventilation air tangentially into the cavity 120 of each CEC 110 as shown.
  • Ambient ventilation air is drawn downwards through and between the attenuator plates 171 inside each cooling air feeder shell 130, and then flows horizontal/laterally to the CEC 110 through flow conduits 160 to cool the canister 150 in each CEC via the convective natural thermo-siphon effect previously described herein.
  • an alternative air outlet 220 is shown which is formed directly through lid 215 rather than between the periphery of the lid and upper portion 11 la of the CEC 110 and top pad 102 as with previous lid 115 in prior embodiments of FIGS. 4-7 described herein.
  • the air outlet 220 forms a circuitous multi-angled passageway internally through the lid terminating in air discharge housing 216 mounted to the top surface of the lid (see, e.g., FIG. 18 and directional airflow arrows).
  • lid 215 is configured slightly differently than lid 115 previously described herein.
  • Air discharge housing 216 of present lid 215 comprises a perforated cylindrical metal shell which projects vertically upwards from the top surface of the lid 215 as shown.
  • housing 216 comprises a plurality of lateral openings extending 360 degrees circumferentially around for discharging air laterally outwards therefrom back to the ambient environment.
  • a circular cap 217 encloses the top of the air discharge housing 216 to prevent the ingress of rain.
  • the air discharge housing 216 and to cap 217 may be formed of metal such as stainless steel for corrosion protection. Other shaped caps and intake housings may be used in other embodiments.
  • the present lid 215 may have a composite metal and concrete construction and shape similar to previous lid 115 in FIGS. 4-7 including an outer shell 215a formed of steel such as stainless steel, and interior concrete lining 215b. This robust construction not only provides radiation shielding, but also offers protection against projectile impacts.
  • lid 215 includes a circular upper portion 218a and adjoining circular lower portion 218b having an outer diameter smaller than an outer diameter of the upper portion similar to previous lid 115.
  • the present lid 215 effectively seals off the upwardly open recess 117 formed into the top surface 102a of the top pad 102 around the top end 112 of each CEC 110 by the upper diametrically enlarged top cylindrical section 111b of the CEC.
  • FIGS. 21-44 depict various aspects of a passively cooled and stackable nuclear waste storage system which provides both below grade and above grade storage.
  • the system comprises a pair of vertically stacked nuclear waste storage vessels including a lower below grade module and an upper above grade module.
  • the below grade module may be one or more of the embodiments of the vertically elongated CEC 110 (cavity enclosure containers) previously described herein which is mounted on the subterranean concrete base pad 101 of the ISFSI and situated below the storage site’s final cleared grade of topsoil and/or engineered fill.
  • CEC 110 is passively cooled via the natural thermo-siphon ventilation system described above via one or more cooling air feeder shells 130 fluidly coupled to the internal storage cavity 120 of the CEC by one or more horizontal/lateral flow conduits 160.
  • the lid 115 on the CEC is omitted and instead an above grade module is mounted immediately above the CEC.
  • the above grade module may be a vertically-elongated radiation- shielded cask 300 positioned above the below grade CEC 110.
  • the stacked casks and CEC may be concentrically arranged with respect to one another and coaxially aligned along a common vertical centerline collectively defined by vertical centerline axis VC1 of CEC 110 and vertical centerline cask axis CA1 of cask 300 (see, e.g., FIG. 41).
  • the cask 300 may be fixedly and detachably mounted to the ISFSI top pad 102 such as via bolting or other means. There may be no direct fixed coupling via bolting or other means of the cask to the below grade CEC.
  • the cask 300 may be directly coupled to top of the CEC (e.g., bolted or otherwise) either instead of or in addition to mounting to the concrete top pad.
  • cask 300 is an above grade nuclear waste storage module, it is a heavily radiation- shielded double-walled vessel.
  • a suitable basic cask usable in the stacked storage system may be a HI-STORM cask available from Holtec International of Camden, New Jersey when is modified to include the unique features described herein for a stacked installation above the below grade CEC including the special cooling air ventilation provisions disclosed to fluidly interconnect the internal nuclear waste canister cavities of the CEC 110 and cask 300 thereby forming a fluidly contiguous internal space of the cooling air ventilation system as further described herein.
  • Cask 300 in one embodiment includes a vertically orientated and elongated cask body
  • the cask body is formed by a cylindrical outer shell
  • the shells 311, 312 and shielding material 313 collectively define a cylindrical vertical sidewall 318 of the cask having the foregoing composite construction of different materials.
  • the inner and outer shells are concentrically arranged and coaxial relative to each other as shown.
  • the shielding material 313 may comprise a concrete mass or liner for neutron and gamma radiation blocking.
  • a concrete aggregate comprising hematite or another type iron ore preferably may be used. This advantageously maximizes conductive heat transfer through the sidewalls 318 of the cask body to help dissipate and transmit a portion of the thermal energy (e.g., heat) emitted by the SNF (or other radioactive waste) stored inside the casks within the canister.
  • the passive ventilation air system described herein dissipates the remainder of the decay heat to protect the structural integrity of the canister and SNF assemblies stored therein.
  • radiation shielding materials may be used in addition to or instead of concrete including lead for gamma radiation shielding, boron containing materials for neutron blocking (e.g. Metamic ® or others), steel, and/or others shielding material typically used for such purposes in the art.
  • lead for gamma radiation shielding boron containing materials for neutron blocking (e.g. Metamic ® or others), steel, and/or others shielding material typically used for such purposes in the art.
  • Inner shell 312 of the cask 300 defines an inner or internal surface 312a and outer shell 311 defines an outer or external surface 311a of the casks.
  • Surfaces 311a, 312a formed by the cylindrical shells 311, 312 may correspondingly be cylindrical and arcuately curved in one embodiment.
  • the cask further defines a top end 319 defined by the upper end of the cask body 310 and bottom end 320 defined by the lower end.
  • the inner and outer shells 312, 311 may be formed of a suitable metallic material, such as without limitation steel (e.g. carbon or stainless steel). If carbon steel is used at least the external surface 31 la of the cask may be epoxy painted/coated for corrosion protection.
  • the metal shells 311, 312 may each have representative thickness of about 3/4 inches as one non-limiting example; however, other suitable thicknesses may be used.
  • Above grade cask 300 comprises a vertically-extending internal cavity 321 which extends along the vertical cavity axis CA1 defined by the cask body 318. Cask 300 is concentrically and coaxially aligned with vertical centerline axis VC1 of the CEC 110.
  • Cavity 321 extends vertically for substantially the entire height of the cask.
  • Cavity 321 may be of cylindrical configuration in one embodiment with a circular cross-sectional shape to conform to the cylindrical shape of the nuclear waste canister 150; however, other shaped cavities with corresponding cross-sectional shapes may be used including polygonal shapes and other non-polygonal shapes (e.g. rectilinear, hexagon, octagonal, etc.) depending on configuration of the nuclear waste container stored therein.
  • the cavity of cask 300 may have a height and transverse cross-sectional area configured to hold only a single nuclear waste canister 150 loaded with SNF assemblies (not shown) or other high level radioactive waste emitting radiation and substantial amounts of thermal energy in the form of decay heat.
  • Cask 300 further comprises a bottom baseplate 315 which may be seal welded to the inner and outer shells 312, 311 at the bottom end 320 of the cask body. Structurally, this forms a rigid self-supporting cask assemblage or structure which can be fabricated in the shop, and then transported to the desired nuclear waste storage site (e.g., nuclear generating plant and/or ISFSI) where it can be moved and handled by suitable lifting equipment such as track-driven cask crawlers (used and are well known in the art). The cask crawlers are also used for loading the nuclear waste canisters into the casks.
  • the desired nuclear waste storage site e.g., nuclear generating plant and/or ISFSI
  • suitable lifting equipment such as track-driven cask crawlers (used and are well known in the art).
  • the cask crawlers are also used for loading the nuclear waste canisters into the casks.
  • Baseplate 315 may be structurally reinforced and stiffened by a plurality of circumferentially spaced apart angled gusset plates 315b welded to the peripheral portion of the baseplate which projects radially outward beyond outer shell 311 and the lower portion of external surface 31 la of outer shell 311 as shown.
  • the peripheral portion of baseplate 315 defines a user-accessible mounting flange 350 for anchoring the cask to the concrete top pad 102.
  • Baseplate 315 of upper cask 300 is configured for placement and seating on a top surface of a substantially flat horizontal support structure such as the ISFSI concrete top pad 102 to rigidly and detachably anchor the cask 100a thereto. This laterally stabilizes the stacked cask assemblage to withstand vibrational loads and moments during a seismic event.
  • Cask 300 directly engages top pad 102, and in some embodiments abuttingly engages the annular seating flange 111c at the top of the CEC 110 (see, e.g., FIGS. 36A-B). This forms an annular cask-to-CEC interface 448.
  • baseplate 315 of cask 300 is not fixedly coupled to the CEC seating flange 111c (e.g., bolted, welded, etc.) since the flange 111c is not accessible being located to abutting engage only the inner annular bottom surface portion of the cask baseplate (best shown in FIG. 36B).
  • the peripheral portion of baseplate 315 which defines the mounting flange 350 abuttingly engages and is fixedly coupled to the top surface of the concrete top pad 102 as shown.
  • a plurality of circumferentially spaced apart threaded mounting fasteners 324 such as anchor bolts may embedded in concrete pad and arranged in a bolt circle may be used to fixedly anchor the peripheral mounting flange 350 defined by baseplate 315 of cask 300 in place such as via threaded nuts.
  • Other forms of mounting the baseplate to the concrete pad may be used.
  • Baseplate 315 may be made of a similar metallic material as the shells 111, 112 (e.g., steel or stainless steel). The bottom surface of baseplate 315 may be considered to define the bottom end 320 of the cask 300 for convenience of description purposes.
  • Baseplate 315 comprises peripheral portion which projects radially outward beyond outer shell 311 and defines the mounting flange 350 as previously described herein.
  • the baseplate 315 may be structurally reinforced and stiffened by a plurality of circumferentially spaced apart angled gusset plates 315b welded to the mounting flange and the lower portion of the external surface 311a of outer shell 311 of cask 300 as shown.
  • baseplate 315 of upper cask 300 is a perforated baseplate comprising a plurality of perforations in the form of axial through holes 315a.
  • the through holes may have a circular cross-sectional shape in one embodiment; however, other suitably shaped through holes in cross section such as polygonal (e.g., square, rectangular etc.) and non-polygonal shapes may be used.
  • the through holes 315a are vertically elongated and may be oriented parallel to each other and vertical cavity axis CA1 of the cask.
  • only the central portion of the perforated baseplate 315 which resides inside the internal cavity 321 of the cask 300 includes the perforations (i.e. through holes 315a).
  • Baseplate 315 of the above grade upper cask 300 is structured to support the entire weight of the nuclear waste canister 150 stored in the cask.
  • the perforated baseplate 315 of cask 300 provides a structural purpose and in addition functions as an integral part of the cask and CEC ventilation air system described herein which removes decay heat (thermal energy) emitted by the nuclear waste canisters 150 in the stacked storage assembly.
  • the through holes 315a of perforated baseplate 315 places the cavity 321 of the cask in fluid communication with the cavity 120 of the lower grade CEC 110.
  • the fluid communication is established by the act of mounting the upper cask above the CEC, which in effect forms a common fluidly interconnected and contiguous ventilation riser extending in a vertical direction internally through the stack of cask 300 and CEC 110. Because the top end of the below grade CEC 110 and its cavity 120 are upwardly open (when lid 115 is removed to mount cask 300 above), the perforated baseplate 315 forms the only physical barrier between the cavities of the lower CEC and upper cask.
  • the through holes 215a in perforated baseplate 215 defines an air transmissible barrier or structure which permits ventilation air in the lower cavity 120 of CEC 110 to be transferred and flow upwards into the upper cavity 321 of cask 300. Operation of the ventilation system will be further described herein.
  • Perforated baseplate 315 of upper cask 300 further plays an important role in preventing radiation streaming or shine therethrough during the process of mounting the upper cask above the embedded lower CEC 110.
  • a nuclear waste canister 150 is loaded into cavity 321 of upper cask 300 while positioned on the concrete top pad 102 (as further described herein)
  • the upper cask must be lifted off of the pad by a commercially-available cask crawler to position the cask on top of the lower CEC already seated elsewhere on the pad. While the upper cask is suspended in mid air, the potential for radiation streaming or shine from the nuclear waste inside the cask cavity through the perforated baseplate to the ambient environment is created.
  • the axial through holes 315a in baseplate 315 therefore have a profile with height to diameter ratio of at least 2:1, and preferably more than 3:1.
  • the baseplate 215 therefore is a vertically thick metallic structure which may be about 6 inches thick or more for this purpose in some non-limiting embodiments.
  • the vertically elongated through holes 215a act to scatter the radiation to prevent radiation streaming to the environment through the baseplate.
  • some or all of the through holes may be obliquely oriented to the cavity axis CA1 of the upper cask 300 instead of being parallel thereto.
  • the perforated baseplate 315 of upper cask 300 alternatively may have a two-piece construction (see, e.g., FIGS. 34-36). This includes a circular central portion 315e located inside the cavity 321 (which is perforated with the axial through holes 315a previously described herein) for supporting the upper canister 150, and an outer annular portion formed by a flat annular bottom closure plate 315f welded to the bottom ends of the upper cask cylindrical outer and inner shells 311, 312.
  • Closure plate 315f defines a central opening 315h which allows rising air from the lower below grade CEC 110 to flow through the perforated central portion 315e of the baseplate 315 into the internal cavity 321 of upper above grade cask 300.
  • the bottom closure plate 315f may be considered part of the entire structure of the baseplate 315. It bears noting that bottom closure plate 315f defines the peripheral portion of baseplate 315, which in turn defines the mounting flange 450 for coupling the upper cask 300 to lower CEC 110.
  • the perforated central portion 315e of baseplate 315 may be supported by an inner portion of bottom closure plate 315f located inside cavity 321 of above grade cask 300 via an annular stepped shoulder 315g formed by an inward radial extension or protrusion of closure plate 315f in one embodiment.
  • Central portion 315e may loosely engage the stepped shoulder 315g of bottom closure plate 315f to be removable, or alternatively may be welded to outer closure plate 315f for rigid fixation thereto.
  • the circular perforated central portion 315e may be inserted through the top end of upper cask 300 after the annular bottom closure plate 315f is welded to outer and inner shells 311, 312 of the cask body.
  • the central portion 315e may be thicker in construction than the bottom closure plate 315f of upper cask 300 as depicted herein because the central portion supports the weight of the canister 150 in the cask (see, e.g., FIG. 21).
  • the entire baseplate 315 may have a uniform thickness.
  • the circular central portion 315e of baseplate 315 may have a variety of structures whether a monolithic one-piece or two-piece construction of the baseplate is used.
  • FIG. 35 depicts one embodiment of central portion 315e formed by a plurality of orthogonally arranged and intersecting metallic flat plates 315m which define the plurality of axial through holes 315a.
  • the outside perimeter of this embodiment defines an imaginary circle which conforms to and is complementary configured to the circular transverse cross-sectional area defined by internal cavity 321 of the above grade cask 300 which receives the central portion.
  • central portion 315e of baseplate 315 of the cask 300 is formed by a solid circular metallic plate through which the plurality of through holes 315a previously described herein are formed.
  • This central portion 315e formed by a thick steel plate allows formation of the through holes 315a which may offer greater protection against radiation streaming or shine through the perforated baseplate 315 in some cases than the embodiment of FIG. 35.
  • Other perforated structures may be used for central portion 315e so long as through holes of any suitable configuration are provided to fluidly interconnect cavity 120 of the below grade CEC 110 to cavity 321 of above grade cask 300.
  • a plurality of spacer plates 315d may be rigidly attached (e.g., welded) to a top surface of the perforated baseplate 315 inside cavity 321 as shown in FIG.
  • the spacer plates may be distributed over and spaced apart across the baseplate. Any suitably shaped structural steel plates may be used to construct the spacer plates.
  • the spacer plates 315d are configured to engage and elevate a bottom of the nuclear waste canister 150 above the perforated baseplate in the above grade cask 300. This advantageously allows ventilation air to circulate and flow beneath the canister to enhance cooling the nuclear waste therein.
  • Spacer plates 315d may be about 6 inches high in some embodiments and are arranged in a plurality of orientations to each other to create radiation scattering which further prevent radiation streaming or shine through the perforated baseplate 315.
  • the internal cavities 120, 321 of both the lower CEC 110 and upper cask 300 each have a height and transverse cross-sectional are configured for holding no more than a nuclear waste canister 150 therein, as previously described herein.
  • the diameter of each cavity is intentionally larger than the outer diameter of the fuel canister 150 by an amount (e.g., less than 1/3 the diameter of the canister) to form a respective ventilation annulus 121 (CEC 110) or 322 (cask 300) between the canister 150 and CEC shell body 111 or inner shell 312 of the cask within internal cavities 120 or 321, respectively (see, e.g. FIG. 36A).
  • the radial width W1 of annulus 121 in lower CEC 110 and width W2 of annulus 322 in upper cask 300 are each preferably sufficient to draw heat generated by the nuclear waste within each canister 150 away from the canister as the cooling ventilation air flows upwards alongside the outer surface of the canisters as it is heated via a natural convective thermo-siphon effect.
  • a typical ventilation annulus inside a CEC or cask may be in the range of about and including 2-6 inches in radial width as a non-limiting example depending on the estimated heat load generated by the fuel canister 150.
  • the ventilation annulus is defined by and extends vertically for the full height of the canister in each of the CEC and cask, and may terminate at top proximate to the top ends of the internal cavities as shown (see, e.g., FIG. 21). Accordingly, the canister 150 has a height approaching the full height of the cavity of the CEC and cask, and at least greater than 3/4th the height of its respective cavity in which it is housed.
  • This lower portions of each ventilation annulus 121 and 322 in the CEC and cask are placed in fluid communication with ambient atmosphere via the air inlet ducts extending through the sidewalls of the CEC and cask, as further described elsewhere herein.
  • the radial width W2 of ventilation annulus 322 in upper cask 300 is preferably larger than radial width W1 of the ventilation annulus 121 in lower CEC 110. Because the nuclear waste canisters 150 stored in the CEC and cask have the same diameter which is standardized, the larger radial width W2 of the upper cask is the result of the cavity 321 of the upper cask having a larger diameter D2 than the diameter D1 of cavity 120 in the lower CEC (see, e.g., FIG. 36A).
  • the additional annulus 322 volume thus created in the cavity 321 of upper cask 300 can advantageously accommodate the additional volume of heated ventilation air received from the lower CEC 110 without compromising the ability of the upper annulus 322 to absorb the additional heat generated by the canister 150 in the upper cask.
  • the CEC 110 may have a smaller diameter D1 cavity 120 since it only draws the volume of ambient cooling air inwards through its air inlets 125 necessary to accommodate the heat load created by a single nuclear waste canister 150 inside the CEC.
  • a cask-to-cask interface 448 is formed between the upper cask 300 and lower CEC 110.
  • the interface may be defined by the joint between the bottom mounting flange 350 of the upper cask defined by baseplate 315 and the top surface 102a of the top pad 102.
  • nuclear waste canister 150 in the cavity 321 of upper cask 300 is positioned above the interface 448 (e.g., bottom end of canister), and conversely the canister 150 in the cavity 120 of lower CEC 110 is positioned below interface 448 (e.g., top end of canister).
  • a radiation-shielded closure lid 314 is detachably coupled to the top end 319 of the above grade upper cask 300. Reference is made in general to FIGS. 21-44 as applicable, and in particular FIG. 37 which shows the lid in greater and enlarged cross-sectional detail.
  • Lid 314 closes the normally upwardly open cavity 321 of upper cask 300 when in place.
  • Lid 314 may be a circular cylindrical structure comprising a hollow metal outer housing 314b defining an interior space filled with a radiation shielding material 314a such as a concrete plug or liner encased by the outer housing. Other shielding materials may be used in addition to or instead of concrete.
  • Lid 314 provides radiation shielding in the vertical upward direction, whereas the concrete liner 313 disposed between the inner and outer shells 312,
  • the foregoing lid-related components are preferably all formed of a metal such as without limitation steel (e.g. carbon or stainless).
  • Housing 314b of lid 314 may include circular top cover plate 314b-l, circular bottom cover plate 314b-2, and a circumferentially-extending peripheral ring wall or shell 314b-3 extending vertically between the ring plate and top plate (see, e.g. FIG. 6).
  • the top and bottom cover plates may be flat and the ring shell 314b-3 may be cylindrical in shape in a certain embodiment.
  • a plurality of circumferentially spaced apart cylindrical standoffs 441 may be provided which elevate the bottom cover plate 314b-2 of lid 314 above the top end 319 of the upper cask 300. This provides a vertical gap of annular configuration which extends circumferentially all around the lid between the bottom cover plate and the top end of the cask to define an air outlet duct 440 through the lid to atmosphere.
  • the air outlet duct 440 may extend 360 degrees all around the lid 314 except for interruptions by the standoffs 441.
  • An annular mesh screen 444 with open flow areas encloses the annular air outlet duct 340 to prevent the ingress of debris or other materials into the cask, while concomitantly allowing the heated ventilation air to exit the lid back to atmosphere.
  • a central air collection recess 314c is formed beneath bottom cover plate 314b-2 of lid 314 on the underside of the lid by gap created by the standoffs 441.
  • Central air collection recess 314c is downwardly open to internal cavity 321 of cask 300to receive the vertically rising ventilation air from the ventilation annulus 322 which is heated by the canister.
  • the central air collection recess collects the heated ventilation air and directs the air radially outwards back to ambient atmosphere through the air outlet ducts 440.
  • the stiffening plates 314d welded between the top and bottom cover plates through the concrete radiation shielding material 314a structurally stiffens the lid housing.
  • the stiffening plates are further configured and operable to detachably engage the top end 319 of the cask 300 to which the lid is mounted.
  • the stiffening plates 314d may include a step-shaped cutout 314d-l configured to engage the top end of the cask.
  • the stiffening plates therefore serve to primarily support the full weight of the heavy radiation- shielded lid which is not imposed on the standoffs 441.
  • the bottom cover plate 314b-2 may be welded to each of the standoffs which partially supports the weight of the lid.
  • the standoffs 441 may play a further role in detachably coupling the lid 314 to the upper cask 300.
  • a plurality of threaded lid bolts 442 may be provided each of which extends vertically through one standoff 441 and threadably engages a mating threaded socket 445 provided in the top end 319 of the cask 300.
  • each socket may be provided by a vertically oriented lid mounting plate 246 which is welded between inner and outer shells 312, 311 of the cask (see, e.g., FIG. 21).
  • Each threaded socket is welded to its associated lid mounting plate which is embedded in the concrete radiation- shielding material 314a.
  • Each standoff 441 includes a tubular access sleeve 443 which extends vertically through the radiation shielding material 314a of the lid 314 as shown to allow an operator to access the lid bolting.
  • the present nuclear waste storage system disclosed herein includes a natural circulation air ventilation system (i.e. unpowered by fans/blowers) for removing decay heat emitted from the canister 150 which holds the SNF or other high level radioactive waste.
  • the cooling airflow provided by the ambient air surrounding the cask has flow driven by the natural convective thermo-siphon effect in which ventilation air within the ventilation annuluses 121 and 322 of the lower CEC 110 and upper cask 300 is heated by the canisters 150 therein which emit the heat generated by the decaying SNF or other radioactive waste stored inside. This air heating generates an upflow of the heated air within each respective ventilation annulus.
  • This natural convection driven airflow effect is well understood in the art without further elaboration.
  • the cask ventilation provisions of the upper cask 300 include a plurality of circumferentially spaced apart ventilation air inlet ducts 420 configured to draw in and introduce ambient ventilation air radially inwards into the internal cavity 321 of the cask.
  • Air inlet ducts 420 establish fluid communication between cask cavity 321 (including ventilation annulus 322 formed in the cavity between canister 150 and inner shell 312 of the cask body 310) and ambient atmosphere which provides the source of the cooling air.
  • the air inlet ducts 420 may be circumferentially spaced apart around the perimeter/circumference of upper cask 300.
  • the inlet ducts 300 may be equally or unequally spaced apart and may include at least four ducts to deliver ambient cooling air to each quadrant of the nuclear waste canister 150 contained in internal cavity 321 of upper cask 300.
  • each quadrant of the canister is cooled by a pair of inlet ducts 420 (i.e. 8 ducts total).
  • the air inlet ducts 420 are disposed in and formed through the lower portion of the upper cask body 310 proximate to the bottom end 320 of the cask and cavity 321 therein to introduce ambient cooling or ventilation air into the lower portion of the cavity and upper ventilation annulus 322 of the upper cask 300. Accordingly, each air inlet duct 420 extends horizontally/laterally and radially completely through the sidewall 318 formed by the cask body 310 from outer shell 311 to inner shell 312. The radially oriented ducts 420 define air inlet passageways which place the lower portion of the cask cavity 321 and ventilation annulus 322 of upper cask 300 in fluid communication with ambient atmosphere and cooling air.
  • Air inlet ducts 210 of upper cask 100b introduces fresh cool ambient ventilation air radially inwards into the upper cask cavity 321 where it mixes with already heated ventilation air flowing vertically upwards from the lower CEC 110 into the upper cask cavity.
  • this mixing of air streams tempers and cools the rising heated ventilation air from the lower CEC so that it is better able to absorb heat emitted by the nuclear waste canister 150 inside the upper cask 300.
  • the stacked assemblage of the lower CEC 110 and upper cask 300 therefore are cooled by two vertically spaced apart sets of air inlets; air inlets 125 of CEC 110 being below grade and air inlet ducts 420 of cask 300 being above grade. This provides adequate cooling capacity for the heat load generated by the thermal energy emissions for both nuclear waste canisters 101 accommodated by the nuclear waste storage system.
  • the air inlet ducts 420 of the upper cask 300 each include an entrance opening 411 located at and penetrating the outer or external surface 31 la of the upper cask outer shell 311 and an exit opening 412 located at and penetrating the inner or internal surface 312a of inner shell 311.
  • a metallic flow conduit 413 of suitable configuration extends between and fluidly couples the entrance and exit of each inlet duct.
  • the flow conduits 413 may have any suitable configuration and polygonal or non-polygonal cross-sectional shape. In one embodiment, as shown, the flow conduits may have a box-like configuration with a rectilinear cross-sectional shape (e.g.,. rectangular or square).
  • Air inlet ducts 420 of upper cask 300 may be vertically elongated in configuration n one non- limiting embodiment.
  • Each flow conduit 413 of the upper air inlet ducts 420 extends radially through the sidewall 318 of the cask body 310 (i.e. shells 311, 312 and radiation shielding material 313 therebetween) to fluidly connect ambient air to the internal cavity 321 and ventilation annulus 322 of the upper cask 300 (see, e.g., FIG. 44).
  • the flow conduit 313 may therefore be embedded within the radiation- shielding material liner of the upper cask 100b.
  • each inlet duct may have a circuitous configuration to draw ambient ventilation air radially inwards into the cask cavity 321 in a circuitous path such that no straight line of sight exists between external entrance opening 201 and the internal exit opening 212 of each air inlet duct.
  • the entrance opening 211 may be radially and angularly offset from exit opening 212 of the duct.
  • the entrance opening 211 may be located at a first angular position defined by a radial reference line R1 and the exit opening 212 may be located at a second angular position defined by a second radial reference line R2 (see, e.g., FIG. 44).
  • the entrance and exit openings 411, 412 may be angularly offset at an angle A1 between about and including 20 to 40 degrees. Angle A1 may be about 30 degrees in one preferred but non limiting embodiment.
  • the flow conduit 413 located therebetween extends transversely to radial references lines R1 and R2 through the radiation-shielding material 313 liner of the upper cask body 310 as shown to fluidly coupled the entrance and exit openings.
  • the foregoing configuration and arrangement eliminates any straight line of sight through the upper set of air inlet ducts 420.
  • the process continues with the rising heated ventilation air in the lower CEC 110 which leaves the lower CEC and flows through the through holes 315a of the upper cask perforated baseplate 315 to enter the bottom of the ventilation annulus 322 inside upper cask 300.
  • This heated ventilation air mixes with cool ambient air drawn into the upper cask via the set of air inlet ducts 420 as previously described herein.
  • the mixed air is further heated by the canister 150 in the upper cask 300 as noted above.
  • the further heated ventilation air continues to flow upwards and reaches the top end of the upper cask from which it is discharged back to atmosphere through the annular air outlet duct 440 defined by top closure lid 314 on the cask.
  • This ventilation air circulation pattern continues indefinitely as long as the canisters emit some degree of heat.
  • one or more below grade CECs 110 alone may be used at a first point in time for a period of time until additional nuclear waste storage capacity is required in the future at the storage site.
  • the mounting of the lower CECs and later upper casks 300 into the tiered assemblage disclosed herein is therefore intended to be staggered over time instead of during the same in installation sequence as in the second deployment scenario described below.
  • Each lower CEC of the stacked storage modules may be buried and positioned at a discrete location on the concrete pad S of the storage facility (see, e.g., FIGS. 1-3).
  • the cooling air feeder shells 130 and flow conduits 160 associated with each CEC 110 are fluidly coupled to their respective one or more CECs as previously described herein.
  • a first nuclear waste canister 150 is lowered and inserted into each CEC internal cavity 120.
  • the canister 150 is in a dry condition and may be loaded into cask 100a via a commercially-available transfer cask which is a lighter vessel with thinner walls providing less radiation shielding (sidewalls without concrete) than heavier thick walled storage casks with concrete sidewalls such as lower and upper casks 100a, 100b.
  • Transfer casks are typically submerged in the fuel pool with a nuclear waste canister (e.g., MPC) pre-loaded therein, which is then with SNF assemblies in a known manner.
  • MPC nuclear waste canister
  • the canisters are in a wetted condition inside the transfer cask rather than a dry condition such as when canisters 101 disclosed herein are loaded into the lower and upper casks 100a, 100b.
  • Examples transfer casks which may be used are disclosed in commonly-owned U.S. Patents 9,466,400 and 7,330,525, which are incorporated herein by reference in their entireties. Transfer casks may also be used to load the canister into the upper cask 300 described below.
  • thermo-siphon ventilation air system becomes activated due to the heat generated by the canister inside.
  • Cool ambient ventilation air is drawn through the one or more cooling air feeder shells 130 and flow conduits 160 into the CEC cavity 120 via the air inlets 125.
  • the cooling air is heated by the thermal energy emitted from nuclear waste in the canister and rises upwards through the ventilation annulus 121 of the CEC, and is then returned to atmosphere as heated ventilation air through the air outlet 118 defined by the lid 115 as previously described herein.
  • the method includes operating the CEC 110 for a period of time to store and cool the radioactive waste in the CEC.
  • additional storage capacity may be added as required by installing one or more upper casks 300 on some or all of the lower CECs 110 previously installed at the nuclear waste storage site.
  • An empty and upwardly open upper cask 300 is first positioned on concrete top pad 102 in a temporary staging area.
  • a second canister 150 is loaded and inserted into the upper cask.
  • the lid 115 on the lower CEC 110 may be removed leaving an upwardly open vessel.
  • the upper cask 300 may then be lifted and positioned over and above the corresponding below grade CEC and bolted to the top pad 102.
  • the perforated baseplate 315 of upper cask may abuttingly engage the upper annular seating flange 111c of the CEC on the top surface 102a of top pad 102 (see, e.g., FIG. 36B), but is not bolted or otherwise fixedly coupled thereto in any manner.
  • the mutual engagement is one of a flat-to- flat interface and seal at this cask-to-CEC interface 448.
  • the cask lid 314 may then be installed and bolted on the top end 319 of the upper cask 300 either while the cask is still on top pad 102 after loading the second canister 150 therein and before lifting, or after the cask is positioned on the top pad above the CEC.
  • thermo- siphon effect is triggered by heat generated by the canister inside the cask as previously described herein.
  • the venturi effect is triggered by the velocity of the rising and upward flowing heated stream received in the upper cask cavity 321 from the lower CEC 110 below. Cool ambient air drawn through the upper air inlet ducts 420 via the venturi effect in part and thermo-siphon in part rises upwards through the ventilation annulus 322 of the upper cask 300, and is then returned to atmosphere as further heated ventilation air through the air outlet ducts 440 defined by the lid 314.
  • the ventilation air introduced into the upper cask via the upper air inlet ducts 320 of the cask system is mixed in the ventilation annulus 322 with the already heated ventilation received from the lower CEC 110, as previously described herein.
  • the combined and mixed ventilation air streams are thus discharged together from the lid on the upper cask.
  • both the lower CEC 110 and upper cask 300 may be installed at the storage site (e.g., ISFSI) contemporaneously at the same point in time initially.
  • the method or process includes positioning the CEC 110 on the concrete base pad 101, preferably anchoring the CEC to the pad to provide stability, and then loading/inserting the first nuclear waste canister 150 therein.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Processing Of Solid Wastes (AREA)

Abstract

La présente invention concerne un système de stockage de déchets nucléaires superposables à refroidissement passif, comprenant un conteneur à enceinte à cavité (CEC) au moins partiellement enterré et un fût situé en surface. Chaque cuve comprend une cavité contenant une cartouche de déchets nucléaires contenant du combustible nucléaire usé ou d'autres déchets radioactifs de haute activité. Le CEC est fondé sur un socle en béton situé au-dessous du niveau du sol et le fût est monté sur un socle supérieur en béton situé au-dessus du niveau du sol, selon une disposition d'empilement vertical. Le fût supérieur comprend une plaque de base perforée qui établit une communication fluidique entre les cavités des deux fûts et est configurée pour empêcher la brillance du rayonnement. L'un et/ou l'autre fût comprend/comprennent des entrées d'air qui aspirent l'air de refroidissement ambiant dans leurs cavités respectives pour refroidir les déchets nucléaires. L'air chauffé dans le CEC inférieur monte dans le fût supérieur par la plaque de base où il se mélange avec l'air aspiré dans le fût et est renvoyé dans l'atmosphère. Le système augmente la capacité de stockage d'installations nouvelles ou existantes.
EP22805349.2A 2021-05-17 2022-05-17 Système de stockage souterrain à haute densité pour combustible nucléaire et déchets radioactifs Pending EP4352752A1 (fr)

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PCT/US2022/029697 WO2022245871A1 (fr) 2021-05-17 2022-05-17 Système de stockage souterrain à haute densité pour combustible nucléaire et déchets radioactifs

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DE7822589U1 (de) * 1978-07-28 1978-12-07 Nukem Gmbh, 6450 Hanau Lagergestell zur aufnahme von behaeltern fuer bioschaedliche abfaelle
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