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公开(公告)号：US20220406481A1
公开(公告)日：2022-12-22
申请号：US17470053
申请日：2021-09-09
申请人： HOLTEC INTERNATIONAL
摘要： A natural passively cooled ventilated cask includes a cavity which holds a canister containing heat and radiation emitting spent nuclear fuel assemblies or other high level wastes. Ambient ventilation or cooling air is drawn inwards beneath the cask and vertically upwards into a lower portion of the cavity through air inlet ducts formed integrally with a bottom canister support structure coupled to the cask. The air heated by the canister flows upwards in the cavity and returns to atmosphere through air outlet ducts in the cask lid. Air circulation is driven via natural convective thermo-siphon flow. Structural standoff members elevate the bottom of the cask above a concrete base pad forming an air inlet plenum beneath the canister support structure. The lateral sidewall surface of the cask has no penetrations for the air inlets, which eliminates any streaming path for radiation emanating from the spent nuclear fuel.
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公开(公告)号：US20220367078A1
公开(公告)日：2022-11-17
申请号：US17746599
申请日：2022-05-17
申请人： HOLTEC INTERNATIONAL
发明人： Krishna P. SINGH , Stephen J. AGACE
摘要： A passively cooled stackable nuclear waste storage system may include a pair of vertically stacked radiation-shielded nuclear waste storage casks. Each cask has a cavity which holds a nuclear waste canister containing spent nuclear fuel or other high-level radioactive wastes. The lower cask may be founded on an above-grade concrete pad. The upper cask is vertically stacked on and detachably coupled to the lower cask. The upper cask comprises a perforated baseplate which establishes fluid communication between cavities of both casks and is configured to prevent radiation shine. One or both casks may include air inlet vents configured to draw ambient ventilation air into each respective cask cavity for cooling the nuclear waste. In operation, air is drawn inward into each cask cavity independently. Air heated in the lower cask rises into the upper cask where it mixes with air drawn into the upper cask and is returned to atmosphere.
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公开(公告)号：US11430579B2
公开(公告)日：2022-08-30
申请号：US16484251
申请日：2018-02-26
摘要： An apparatus is provided for storing hazardous waste material, which includes one or more of spent nuclear fuel, radioactive material, and fissionable material. A fusible alloy material, for example, a eutectic material, resides within the apparatus and surrounds the hazardous waste material. In the preferred embodiments, it is suggested that the fusible alloy material exhibits liquidus and solidus or melting temperatures that are between about 100 and 300 degrees Fahrenheit for facilities using the apparatus and methods for liquid storage pool loading applications. For facilities using the apparatus and methods for dry loading, the fusible alloy materials may exhibit liquidus and solidus or melting temperatures that are between about 100 and 650 degrees Fahrenheit. The fusible alloy material is introduced in a liquid phase and eventually solidifies into a solid phase as the temperature of the hazardous waste material and/or the local environment decreases.
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公开(公告)号：US11282614B2
公开(公告)日：2022-03-22
申请号：US16257776
申请日：2019-01-25
发明人： Timothy M. Lloyd , Robert D. Quinn , Emiliano Gonzalez Herranz , Emmanuel Mercier , David Castrillon Cabaleiro
摘要： A modular dry spent fuel canister system in which several different types of inner spent nuclear fuel canisters can be loaded into the same outer cask family. This family typically includes a storage overpack, a transfer cask, a transportation cask and support or auxiliary hardware. The various canisters can be loaded interchangeably into the different types of outer casks. The inner canisters are differentiated not by physical fuel type or dimension, but by the engineering objective or criterion that applies to the spent fuel being stored. One such objective may be for a single canister to store a large number of assemblies economically and safely. A second is a canister designed to greatly reduce the cooling time (or radioactive decay time) that must pass in order to load spent nuclear fuel for off-site storage, so as to meet the decay heat requirements and capabilities of the off-site storage system.
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公开(公告)号：US11250963B2
公开(公告)日：2022-02-15
申请号：US16449003
申请日：2019-06-21
申请人： HOLTEC INTERNATIONAL
发明人： Krishna P. Singh
摘要： A spent nuclear fuel storage facility. In one embodiment, the invention is directed to a storage facility including an array of storage containers. Each of the storage containers includes a body portion and a lid. The body portion has a storage cavity configured to hold a canister containing spent nuclear fuel. The lid, which may rest atop the body portion in a detachable manner, includes an inlet vent and an outlet vent. Each of the storage containers may be configured to draw air through the inlet vent and into the storage cavity where the air is warmed and passed through the outlet vent as heated air. The body portion of the storage containers may be positioned below grade and the lid of the storage containers may be positioned above grade.
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公开(公告)号：US20220023925A1
公开(公告)日：2022-01-27
申请号：US17497282
申请日：2021-10-08
发明人： Henry Crichlow , Gary Schneider
摘要： Self-loading systems and methods for disposal of waste materials in a deep underground formation may include at least one wellbore that runs from the Earth's surface to the deep underground formations, wellbore viscous fluid within that at least one wellbore, and at least one waste capsule, wherein the at least one waste capsules houses some waste and is configured to fall within both the at least one wellbore and the wellbore viscous fluid. The systems and methods may also include at least one human-made cavern located in the deep underground formation and connected to the at least one wellbore, wherein the at least one human-made cavern may be configured to receive the at least one waste capsule. The systems and methods may also include a counter for counting waste capsules and/or a robot for dropping waste capsules into a wellhead leading to the at least one wellbore.
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公开(公告)号：US20210343440A1
公开(公告)日：2021-11-04
申请号：US17194564
申请日：2021-03-08
申请人： Deep Isolation, Inc.
发明人： Richard A. Muller
摘要： Techniques for inspecting a weld of a nuclear waste canister include positioning a gamma ray image detector near a nuclear waste canister that encloses nuclear waste. The nuclear waste canister includes a housing that includes a volume in which the waste is enclosed and a top connected to the housing with at least one weld to seal the nuclear waste in the nuclear waste canister. The techniques further include receiving, at the gamma ray image detector, gamma rays from the nuclear waste that travel through one or more voids in the weld; generating an image of the received gamma rays with the gamma ray image detector; and based on the generated image, determining an integrity of the at least one weld.
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公开(公告)号：US11107597B2
公开(公告)日：2021-08-31
申请号：US16636426
申请日：2018-07-25
发明人： Akira Higuchi , Kenta Hamada , Hiroyuki Morita , Akihiro Shin
摘要： A cask includes a cask body, an outer cylinder, a plurality of fins, and a plurality of neutron shields. The cask body has a tubular shape around a central axis and is capable of housing fuel assemblies. The outer cylinder has a tubular shape surrounding the cask body. The fins are aligned in a circumferential direction in a tubular space formed between the cask body and the outer cylinder, and connect an outer peripheral surface of the cask body and an inner peripheral surface of the outer cylinder to divide the tubular space into a plurality of divided spaces. The neutron shields contain a neutron shielding material with which the divided spaces are filled. Each neutron shield includes a void portion extending in the axial direction along the central axis. Accordingly, it is possible to reduce stress that may be exerted on the outer cylinder or other components by thermal expansion of the neutron shielding material when the fuel assemblies are housed in the cask.
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公开(公告)号：US20210098145A1
公开(公告)日：2021-04-01
申请号：US17036132
申请日：2020-09-29
发明人： Jin Seok PARK , Soung Kyu LEE , Sung Hwan KIM , Kwang Jeok KO , Min Gyu KIM , Yeon Ho CHO
摘要： The present disclosure relates to a sliding type transfer cask for transferring spent nuclear fuel, the sliding type transfer cask being easy to install and move. The sliding type transfer cask includes a transfer container having a space for accommodating the canister; a neutron shielding body disposed around an outer circumference; an opening/closing portion coupled to a lower portion of the transfer container, wherein the opening/closing portion includes a support portion that has a first through-hole communicating with the transfer container and supports the transfer container; a base plate that is arranged below the support portion; and a lid assembly that includes a first lid portion and a second lid portion, wherein the first lid portion includes a first lid and a first motor for sliding the first lid, and the second lid portion includes a second lid and a second motor for sliding the second lid.
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公开(公告)号：US20210074444A1
公开(公告)日：2021-03-11
申请号：US17088960
申请日：2020-11-04
申请人： Holtec International
发明人： Krishna P. SINGH , Stephen J. AGACE , Stephen E. THOMPSON , John D. GRIFFITHS , Richard M. SPRINGMAN , Charles W. BULLARD, II , P. Stefan ANTON
IPC分类号： G21F5/008
摘要： A method of retrofitting a spent nuclear fuel system with a neutron absorbing apparatus. The method includes inserting a neutron absorbing apparatus into a first cell of an array of cells each configured to hold a spent nuclear fuel assembly. The neutron absorbing apparatus includes a first wall and a second wall supported by a corner spine to form a chevron shape and a first locking tab protruding outwardly from the first wall towards a first cell wall of the first cell. The method includes cutting a half-sheared second locking tab in the first cell wall of the first cell adjacent to and above the first locking tab of the neutron absorbing apparatus. Finally, the second locking tab is positioned to locking engage the first locking tab to retain the neutron absorbing apparatus in the first cell during removal of one of the fuel assemblies from the first cell.
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