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1. 发明授权

US11217353B2 Method of preparing spent nuclear fuel for dry storage 有权
公开(公告)号：US11217353B2
公开(公告)日：2022-01-04
申请号：US16731000
申请日：2019-12-30
申请人： Holtec International
发明人： Krishna P. Singh
IPC分类号： G21C19/32 , G21F5/008 , G21F9/28 , F26B21/08 , F26B5/04 , F26B21/00 , F26B21/14 , G21C19/30 , G21F5/005
摘要： A system and method for drying cavities containing spent nuclear fuel is devised. The invention utilizes a non-intrusive procedure that is based on monitoring the dew point temperature of a non-reactive gas that is circulated through the cavity. In one aspect, the invention is a system for drying a cavity loaded with spent nuclear fuel comprising: a canister forming the cavity, the cavity having an inlet and an outlet; a source of non-reactive gas; means for flowing the non-reactive gas from the source of non-reactive gas through the cavity; and means for repetitively measuring the dew point temperature of the non-reactive gas exiting the cavity.

2. 发明授权

US10847277B2 Apparatus for reducing radioactive nuclear waste and toxic waste volume 有权
公开(公告)号：US10847277B2
公开(公告)日：2020-11-24
申请号：US15721030
申请日：2017-09-29
申请人： PlasmaNano Corporation
发明人： Jaeyoung Park
IPC分类号： G21F9/30 , G21F9/00 , G21F9/28 , H05H1/46
CPC分类号： G21F9/30 , G21F9/002 , G21F9/28 , H05H1/46 , H05H2001/4667
摘要： Plasma reactors and methods are provided for reducing the volume of radioactive nuclear wastes or toxic wastes where the surface contamination is the main source of radioactivity or toxicity. The radioactive or toxic wastes are prepared in the form of small particles and fed into a pulsed plasma reactor operating in fluidized bed configuration. The repetitively pulsed radio-frequency (rf) powered plasma reactor generates high power plasma for pulse duration between 10 μs-10 ms. During the pulse, the plasma deliver a short burst of intense heat flux to the surface of waste feed particles. Due to the short pulse duration, the heat flux is concentrated on the surface without propagating much to the core of the particles. The localized heat flux preferentially removes the surface contaminants via vaporization. The removed waste in the vapor phase will be transferred out of the reactor where it may undergo additional treatments or disposed accordingly in a reduced volume. The residual particles which are free from surface contaminants can then be recycled or disposed as non-toxic or non-radioactive waste. By controlling the treatment time inside the plasma reactor along with the pulse power, duration and repetition rate, and the plasma chemical composition, the thickness of removed surface layers can be controlled to provide the efficient surface decontamination.

3. 发明申请

US20200286638A1 APPARATUS FOR DRYING SPENT NUCLEAR FUEL BASED ON EVALUATION OF DRYING CHARACTERISTICS OBTAINED FROM GAS SPECTROSCOPY, AND CONTROL METHOD THEREOF 审中-公开
公开(公告)号：US20200286638A1
公开(公告)日：2020-09-10
申请号：US16804187
申请日：2020-02-28
申请人： SAE-AN ENGINEERING CORPORATION
发明人： Gyung Sun CHAE , Kyoung Uk SHIN , Geon Hui LEE , Do Yeong JUNG , Jae Seok PARK
IPC分类号： G21F5/008 , G21F9/28 , F26B21/14
摘要： There is provided an apparatus for drying a spent nuclear fuel based on evaluation of drying characteristics obtained from gas spectroscopy in a drying operation technology of removing moisture from a spent nuclear fuel cladding and a canister (storage container) to store the spent nuclear fuel in a dry state, in which a parameter of drying operation characteristic is extracted from a signal outputted from a gas spectroscopy that directly measures a hot non-reactive gas discharged from a gas outlet port of the canister loaded with a spent nuclear fuel, the signal is inputted as a parameter value for drying operation to execute the drying operation, and if the signal outputted from the gas spectroscopy is below a preset value, it is determined the drying of the canister is completed, so that the drying operation is over.

4. 发明授权

US10229764B2 System and method for preparing a container loaded with wet radioactive elements for dry storage 有权
公开(公告)号：US10229764B2
公开(公告)日：2019-03-12
申请号：US14886844
申请日：2015-10-19
申请人： Holtec International, Inc.
发明人： Krishna P. Singh , John D. Griffiths
IPC分类号： F26B3/00 , G21F5/06 , F26B5/04 , F26B21/08 , F26B21/14 , G21C19/32 , F26B5/12 , G21F5/008 , G21F5/005 , G21F9/28 , G21F9/34
摘要： A system for preparing a container holding radioactive waste for dry storage. In one aspect, the invention can be a system for preparing a container having a cavity loaded with radioactive elements for dry storage, the system comprising: a gas circulation system comprising a condenser module, a desiccant module, and a gas circulator module; the gas circulation system configured to form a hermetically sealed closed-loop path when operably connected to the cavity of the container; and means for adding and removing the desiccant module as part of the hermetically sealed closed-loop path.

5. 发明授权

US09932686B2 Method and device for decontaminating a metallic surface 有权
公开(公告)号：US09932686B2
公开(公告)日：2018-04-03
申请号：US13123870
申请日：2009-10-12
申请人： Jean-Michel Fulconis , Jacques Delagrange , Francis Dalard , Jean-Pierre Caire
发明人： Jean-Michel Fulconis , Jacques Delagrange , Francis Dalard , Jean-Pierre Caire
IPC分类号： C25F7/02 , G21F9/28 , C25F3/06 , C25F1/04 , C25F1/06 , C25F3/02 , G21F9/00
CPC分类号： C25F1/04 , C25F1/06 , C25F3/02 , C25F3/06 , C25F7/02 , G21F9/004 , G21F9/28
摘要： The present invention concerns a method and device for oxidative erosion or for decontamination of a metallic surface, comprising a step consisting of intermittently polarizing the metallic surface to be eroded or decontaminated, placed in contact with a solution containing manganese VII, at a more anodic electric potential than the corrosion potential of said surface.

6. 发明授权

US09837175B2 Method for chemically stabilizing uranium carbide compounds, and device implementing the method 有权
公开(公告)号：US09837175B2
公开(公告)日：2017-12-05
申请号：US14235013
申请日：2012-07-17
申请人： Mickael Marchand , Olivier Fiquet , Méryl Brothier
发明人： Mickael Marchand , Olivier Fiquet , Méryl Brothier
IPC分类号： G21F9/00 , G21F9/30 , C01B31/30 , G21F9/28
CPC分类号： G21F9/30 , C01B32/928 , G21F9/28
摘要： A process for chemical stabilization of a uranium carbide composite material: UCx+yC with x≧1 and y>0, placed in a stabilization chamber, comprises: a rise in chamber internal temperature for oxidation of the compound based on uranium carbide between approximately 380° C. and 550° C., the chamber being fed with a neutral gas; isothermal oxidative treatment at the oxidation temperature, the chamber being placed under O2 partial pressure; controlling completion of stabilization of the compound, comprising monitoring the amount of molecular oxygen consumed and/or carbon dioxide or carbon dioxide and carbon monoxide given off, until achievement of an input set-point value for the amount of molecular oxygen, of a minimum threshold value for the amount of carbon dioxide or minimum threshold values for the carbon dioxide and carbon monoxide. A device implements the process.

7. 发明授权

US09721689B2 Method for decontamination of an object 有权
公开(公告)号：US09721689B2
公开(公告)日：2017-08-01
申请号：US14969866
申请日：2015-12-15
申请人： Hideo Yoshida , MORITA MIYATA CORPORATION
发明人： Hideo Yoshida , Yasuhiro Suyama
IPC分类号： G21F9/06 , G21F9/00 , G21F9/30 , C02F1/461 , G21F9/04 , G21F9/12 , G21F9/28
CPC分类号： G21F9/002 , B09C1/08 , C02F1/28 , C02F1/46104 , C02F2101/006 , C02F2201/46105 , G21F9/04 , G21F9/06 , G21F9/12 , G21F9/125 , G21F9/28 , G21F9/30
摘要： An object to be decontaminated contaminated with radioactive material, e.g., contaminated soil or water, is introduced into eluting solvent and dissolved, and the radioactive material is separated from the object to be contaminated by elution of the radioactive material into the eluting solvent. The eluting solvent containing the radioactive materials dissolved therein and the object to be decontaminated are separated into solid and liquid. The soil after solid-liquid separation and from which the radioactive material is removed is collected, and the eluting solvent after solid-liquid separation and a separated liquid containing contaminated water are introduced into an electrolysis tank and electrolyzed. Metal ions such as those of the radioactive materials are deposited on the cathode in the electrolysis tank. Hydrogen containing tritium generated in electrolysis is collected in the electrolysis tank. The hydrogen is moved to the outside of the electrolysis tank and trapped.

8. 发明授权

US09653190B2 Removal device for radioactive cesium 有权
公开(公告)号：US09653190B2
公开(公告)日：2017-05-16
申请号：US14412664
申请日：2013-06-19
申请人： Taiheiyo Cement Corporation
发明人： Yoshihisa Tanaka , Tetsuo Ogiri , Kenichi Honma , Soichiro Okamura , Takuya Shindo
IPC分类号： G21F9/32 , G21F9/28 , G21F9/30 , G21F9/02 , F23G5/027 , F23G5/033 , F23G5/04 , F23J7/00 , G21F9/34 , G21F9/06 , B09B3/00 , C04B7/44 , B01D53/50 , B01D53/86
CPC分类号： G21F9/32 , B01D53/508 , B01D53/8625 , B01D2257/302 , B01D2257/404 , B01D2258/02 , B09B3/0083 , C04B7/4423 , F23G5/0276 , F23G5/033 , F23G5/04 , F23J7/00 , G21F9/02 , G21F9/06 , G21F9/28 , G21F9/30 , G21F9/34 , Y02P40/126
摘要： To provide a device for removing radioactive cesium from waste material containing radioactive cesium, doing so at low energy and in a dependable manner. The removal device 1 for radioactive cesium is provided with: a rotary kiln 41 which is provided with a burner 41b supplying from the kiln outlet an organic matter O3 contaminated with radioactive cesium, and an inorganic matter charging port 41a supplying from the kiln inlet inorganic matter S4 contaminated with radioactive cesium, and which is employed to burn the organic matter O3 together with the inorganic matter S4; and a recovery device cooling tower 51, a cyclone 52, a bag filter 53 for recovering cesium that has volatilized in the rotary kiln. A drying/crushing device (dryer 21, crusher 22) for drying and crushing the organic matter O1 prior to charging the radioactive cesium-contaminated organic matter to the rotary kiln can be provided. Additionally, a reforming/drying/crushing device (reformer 31, dryer 32, crusher 23) for reforming, drying, and crushing the inorganic matter S1 can be provided. During burning of the organic matter O3 together with the inorganic matter S4, a calcium source can be added as a reaction accelerant A to the rotary kiln.

9. 发明授权

US09390822B2 Oxidation decontamination reagent for removal of the dense radioactive oxide layer on the metal surface and oxidation decontamination method using the same 有权
标题翻译：用于去除金属表面致密的放射性氧化物层的氧化去污试剂和使用其的氧化去污方法
公开(公告)号：US09390822B2
公开(公告)日：2016-07-12
申请号：US14304744
申请日：2014-06-13
申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE
发明人： Sang Yoon Park , Hui-Jun Won , Wangkyu Choi , Jeikwon Moon , Chong-Hun Jung , In-Ho Yoon , Jun-Young Jung
IPC分类号： G21F9/00 , C23F15/00 , G21F9/28 , C23G1/08 , C23G1/10
CPC分类号： G21F9/004 , C23F15/00 , C23G1/085 , C23G1/10 , G21F9/28
摘要： The present invention provides an oxidative decontamination reagent for removal of the dense radioactive oxide layer on a metal surface, which comprises an oxidizing agent, a metal ion, and an inorganic acid. The oxidative decontamination reagent of the present invention is characteristically prepared by adding a metal ion to the conventional oxidative decontamination reagent containing an oxidizing agent and an inorganic acid. When the oxidative decontamination reagent of the present invention is used, electric potential of the metal parts of the primary system of the nuclear power plant can be regulated as passive potential owing to the added metal ion during the oxidative decontamination of the primary metal part of the nuclear power plant. Therefore, by maintaining electric potential of the metal part as passive potential, local corrosion can be inhibited and at the same time secondary waste can be significantly reduced.
摘要翻译：本发明提供一种用于去除金属表面上的致密放射性氧化物层的氧化去污试剂，其包括氧化剂，金属离子和无机酸。本发明的氧化去污试剂的特征在于，将常规的含有氧化剂和无机酸的氧化性去污剂加入金属离子。当使用本发明的氧化性去污试剂时，核电站的一次系统的金属部分的电位可以被调节为被动电位，这是由于在金属离子的主要金属部分的氧化去污期间由于添加的金属离子核电站。因此，通过将金属部件的电位维持为被动电位，可以抑制局部腐蚀，同时能够显着降低二次废弃物。

10. 发明授权

US09174304B2 Laser decontamination device 有权
标题翻译：激光去污装置
公开(公告)号：US09174304B2
公开(公告)日：2015-11-03
申请号：US14351934
申请日：2012-10-24
申请人： Eisuke Minehara
发明人： Eisuke Minehara
IPC分类号： B23K26/36 , G21F9/28 , B23K26/00 , G21F9/00 , G21F9/30 , B23K26/08 , B23K26/14
CPC分类号： B23K26/08 , B23K26/082 , B23K26/142 , B23K26/36 , G21F9/005 , G21F9/28 , G21F9/30
摘要： The laser decontamination device includes: a laser oscillator; a scanning device provided with an XY axis scanner and a Z axis scanner to condense the laser beam emitted from the laser oscillator onto the surface of the contaminated article without the intervention of any compound lens such as an f θ lens so as to optically scan the surface; and a surface shape measuring device to measure the surface shape of the contaminated article, the Z axis scanner being provided with a focus position controlling section to automatically adjust a focus position in accordance with an irradiation position such that a focus of the laser beam comes on the surface of the contaminated article based on a shape data obtained at the surface shape measuring device.
摘要翻译：激光去污装置包括：激光振荡器; 设置有XY轴扫描器和Z轴扫描器的扫描装置，用于将从激光振荡器发射的激光束冷凝到被污染物品的表面上，而不需要任何复合透镜（例如f＆amp; 透镜，以便光学扫描表面; 以及用于测量被污染物品的表面形状的表面形状测量装置，Z轴扫描器设置有聚焦位置控制部分，以根据照射位置自动调节聚焦位置，使得激光束的焦点进入基于在表面形状测量装置处获得的形状数据，污染物品的表面。

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